RC-11-0006, License Amendment Request - LAR-10-03108, Proposed Change to Relocate Administrative Control Requirements Related to Quality Assurance and Submittal of Quality Assurance Program Description (QAPD): Difference between revisions

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{{#Wiki_filter:Thomas D. Gatlin Vice President,Nuclear Operations 803.345.4342 March 18, 2011 A SCANA COMPANY                                                                                                  RC-1 1-0006 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
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==Dear Sir / Madam:==
 
==Subject:==
VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSE AMENDMENT REQUEST - LAR-10-03108 PROPOSED CHANGE TO RELOCATE ADMINISTRATIVE CONTROL REQUIREMENTS RELATED TO QUALITY ASSURANCE AND SUBMITTAL OF QUALITY ASSURANCE PROGRAM DESCRIPTION (QAPD)
Pursuant to 10 CFR 50.90, South Carolina Electric & Gas Company (SCE&G) requests an amendment to the Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Facility Operating License NFP-12. SCE&G proposes to relocate several requirements of Technical Specification (TS)
Section 6.0, Administrative Controls, to the new V.C.Summer Nuclear Station Unit 1 Quality Assurance Program Description (QAPD).
In support of the License Amendment, SCE&G is submitting a revision to the station's Quality Assurance (QA) Program for your review and approval under 10CFR50.54(a)(4). The current QA Program is based on specific ANSI standards and Regulatory Guide commitments. The new QAPD is a complete revision and replaces in total the VCSNS Quality Assurance Operational Plan as currently described in Final Safety Analysis Report (FSAR) Chapter 17. The new QAPD is based on 10 CFR 50, Appendix B, ANSI/ASME NQA-1-1994, and NEI 06-14A Rev. 7/August 2010. The guidance in ANSI/ASME NQA-1-1994 and NEI 06-14NAugust 2010 has been determined to provide the basis for an acceptable QA program and has been approved in an NRC safety evaluation (ML101800497). Nevertheless, the change is being submitted as a reduction in commitment since some commitments to the ANSI standards and regulatory guides will no longer apply. The proposed QAPD is provided as Attachment IVand a discussion of changes is provided as Attachment V. Also, Attachment V provides a comparison of the plant's existing program with the QAPD and provides a basis for concluding that the program, as changed, continues to meet 10 CFR 50, Appendix B requirements.
The proposed change to the Technical Specifications will delete TS 6.5, "Review and Audit," TS 6.8.2, and TS 6.10, "Record Retention." The requirements of the deleted TS 6.5.1, TS 6.5.2, TS 6.5.3, TS 6.8.2, TS 6.10.1, and TS 6.10.2 will be implemented in the new QAPD. Deletion of the above Technical Specifications requires the rewording of TS 6.13.2 and TS 6.14.2 to reflect the deletion of TS 6.10.2. TS 6.8.1 .a will be revised to identify that applicable procedures which are to be established, implemented and maintained are delineated in the QAPD. Also, some required changes are being made to the TS index.
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Virgil C.Summer Station - Post Office Box 88 *Jenkinsville, SC - 29065 *T (803) 345-5209
 
Document Control Desk Attachment I CR-1 0-03108 RC-1 1-0006 Page 2 of 3 The proposed TS change is consistent with the recommendations of NRC Administrative Letter 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance" and guidance given in NEI 06-14A Rev. 7/August 2010.
SCE&G's evaluation of the proposed TS change is provided as Attachment I to this letter. This attachment also provides a description of the proposed change and the regulatory basis for the change. SCE&G has determined that there are no significant hazards considerations associated with the proposed change. Attachment IIprovides the marked-up TS pages and Attachment III provides the re-typed TS pages.
The VCSNS FSAR has been reviewed and requires revisions to Chapter 17, 13 and Appendix 3A.
The proposed changes to the FSAR are included as Attachment VI for information only purposes.
VCSNS commitments on Regulatory Guides are being realigned to incorporate the requirements of NQA-1-1994. The changes to the Regulatory Guide commitments are identified in the proposed revision to FSAR Appendix 3A. Several of the Regulatory Guides were previously withdrawn by the NRC.
The QAPD closely follows the template guidance in NEI 06-14A Rev. 7/August 2010 which was previously reviewed and approved by an NRC Safety Evaluation (ML101800497). As precedence, the application of NQA-1 -1994 as a basis for their QA programs was previously approved for Dominion Nuclear Connecticut, Inc. and Virginia Electric and Power Company (Millstone Units 1, 2 and 3; North Anna Units 1 and 2; and Surry Units 1 and 2) by an NRC Safety Evaluation (ML052490337). Approval for the application of NQA-1-1994 was also given to Southern Nuclear Generating Company (Farley Units 1 and 2, Hatch Units 1 and 2, and Vogtle Units 1 and 2) by another NRC Safety Evaluation (ML071510506). Inaddition to these utilities, there are others which have also received approval of NQA-1 -1994 for their QA programs.
SCE&G requests approval of the proposed TS amendment and QAPD by September 30, 2011 with a 180-day implementation period to permit plant program changes and training. This expedited review is being requested to support the Units 2 &3 Combined License Application (COLA) and allow VCSNS to move to a common QA program. As requested during a telephone conversation, a comparison of the Unit 1 QAPD to the Units 2 &3 QAPD which was submitted with the COLA is provided for your information as Attachment VII.
The proposed amendment has been reviewed by the appropriate VCSNS review committees.
SCE&G has notified the State of South Carolina in accordance with 10CFR50.91. Regulatory commitments to NQA-1 -1994 are identified in the QAPD and Regulatory Guide commitments are also identified in the QAPD and the proposed revision to FSAR Appendix 3A, as previously stated.
Ifyou have any questions or require additional information, please contact Bruce Thompson at (803) 931-5042.
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 3 of 3 I certify under penalty of perjury that the information contained herein is true and correct.
Executed on                        Thomas D. Gatlin GARPTDG/jw Attachment(s):
I. Evaluation of the Proposed TS Change II. Marked Up TS Pages Ill. Retyped TS Pages IV. V.C. Summer Nuclear Station Unit 1 Quality Assurance Program Description V. Consolidated Matrix VI. Proposed Revisions to the FSAR VII. Comparison of Unit 1 QAPD to Units 2 & 3 QAPD c:        K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton R. J. White W. M. Cherry V. M. McCree R. E. Martin NRC Resident Inspector K. M. Sutton T. P. O'Kelley P. Ledbetter NSRC RTS (CR-10-03108)
File    (813.20)
PRSF (RC-11-0006)
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 1 of 8 ATTACHMENT I EVALUATION OF THE PROPOSED CHANGE TO RELOCATE ADMINISTRATIVE CONTROL REQUIREMENTS RELATED TO QUALITY ASSURANCE
 
==1.0    DESCRIPTION==
 
SCE&G proposes to relocate the requirements of TS 6.5, "Review and Audit," TS 6.8.2, and TS 6.10, "Record Retention," to the Quality Assurance Program Description (QAPD),
which is the controlling document for the V. C. Summer Nuclear Station (VCSNS) Unit l's quality assurance program. Future changes to these administrative requirements will be subject to the regulatory controls of 10 CFR 50.54(a). Accordingly, administrative improvements and clarifications, spelling errors, organizational title changes, as well as other changes that do not reduce the quality assurance program commitments as described in 10 CFR 50.54(a), could be implemented without NRC approval. This will reduce the implementation time and resources spent by SCE&G and NRC staff in the preparation and review of license amendment requests associated with these types of changes.
The proposed change is consistent with the recommendations of NRC Administrative Letter (AL) 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance," dated December 12, 1995.
Additionally, deletion of the above sections entails the rewording of TS 6.13.2 and TS 6.14.2 to reflect the deletions.
 
==2.0    PROPOSED CHANGE==
 
Delete TS 6.5.1, "Plant Safety Review Committee (PSRC)." The generic template in NEI 06-14A Rev. 7, August 2010, will be used in the development of VCSNS Unit 1 QAPD by incorporating Part V, Section 2.2, and Option I of Section 2.2 to address independent review and PSRC requirements.
Delete TS 6.5.2, "Nuclear Safety Review Committee (NSRC)." The generic template in NEI 06-14A Rev. 7, August 2010, will be used in the development of VCSNS Unit 1 QAPD by incorporating Part V, Section 2.2, and Option IIof Section 2.2 to address independent review and NSRC requirements. Part II, Section 18 of VCSNS Unit 1 QAPD will address audit types and audit frequencies as delineated in the generic template.
Delete TS 6.5.3, "Technical Review and Control Activities." The deleted requirements will be relocated to the QAPD. This TS section describes the review and approval requirements for procedures and programs identified in TS 6.8.1.
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 2 of 8 Revise TS 6.8.1 .a. This TS states the applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. Part V, Section 3 of VCSNS Unit 1 Quality Assurance Program Description will address operating procedures. FSAR Chapter 3, Appendix 3A will be revised deleting the position to Regulatory Guide 1.33, Revision 2, with reference to NQA-1-1994 and NEI 06-14A Revision 7, August 2010.
Delete TS 6.8.2. This TS references the procedure review requirements of TS Section 6.5 that are proposed above for deletion. The deleted requirements will be relocated to the QAPD.
Delete TS 6.10, "Record Retention" which includes the deletion of TS 6.10.1 and TS 6.10.2. This section describes the record retention requirements. The deleted requirements will be relocated to the QAPD.
Revise the PCP (Process Control Program) record retention requirement of TS 6.13.2.a to reflect the above deletion of TS 6.10.2. Revise TS 6.13.2.a to replace this sentence:
"Shall be documented and recordsof reviews performed shall be retainedas required by Specification 6.10.2.o. "with this sentence: "Shallbe documented and records of reviews performed shall be retainedfor the duration of the Unit OperatingLicense".
Revise the ODCM (Offsite Dose Calculation Manual) record retention requirement of TS 6.14.2.a to reflect the above deletion of TS 6.10.2. Revise TS 6.14.2.a to replace this sentence: "Shallbe documented and records of reviews performed shall be retainedas requiredby Specification 6.10.2.o. "with this sentence: "Shallbe documented and records of reviews performed shall be retainedfor the duration of the Unit OperatingLicense".
Revise the TS index to reflect some required changes.
The administrative control requirements identified above will be relocated to the QAPD.
Subsequent changes to these requirements will be controlled in accordance with 10 CFR 50.54(a). Implementation of the amendment will be performed within 180 days of NRC issuance of the amendment. Relocation of these requirements will be completed during implementation of the NRC approved License Amendment. In the absence of a basis section for TS Section 6.0, "Administrative Controls," there are no bases changes proposed by this amendment request.
 
==3.0      BACKGROUND==
 
NRC regulatory requirements related to the content of the technical specifications are set forth in 10 CFR 50.36. Addressing administrative controls, 10 CFR 50.36(c)(5) states that they are "the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner."
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 3 of 8 According to 58 FR 39132, "Final Policy Statement on Technical Specifications Improvements For Nuclear Reactors," the purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by identifying those features that are of controlling importance to safety and establishing on them certain conditions of operation which cannot be changed without prior Commission approval. The following criteria delineate those constraints on design and operation of nuclear power plants that are derived from the plant safety analysis report or probabilistic safety assessment (PSA) information and that belong in technical specifications in accordance with 10 CFR 50.36 and the purpose of technical specifications stated above: 1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; 2) a process variable, design feature, or operating restriction that is an initial condition of a Design Basis Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; 3) a structure, system, or component that is a part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; and 4) a structure, system, or component which operating experience of probabilistic safety assessment has shown to be significant to the public health, and safety.
LCOs which do not meet any of the above criteria may be proposed for removal from the technical specifications and relocation to licensee-controlled documents, such as the FSAR or other licensee-controlled documents. Changes to the FSAR or to procedures described in the FSAR are to be made in accordance with 10 CFR 50.59. Changes made in accordance with the provisions of other licensee-controlled documents are subject to the specific requirements for those documents. The criteria may be applied to either standard or custom technical specifications. Any changes to a licensee's technical specifications to apply this Policy Statement's criteria will be made by the license amendment process prior to implementation. Compliance with technical specifications is required by the Commission, and adherence to commitments contained in licensee-controlled documents is expected by the Commission.
Specific guidance for relocation of technical specifications related to quality assurance is found in AL 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance." The technical specification requirements related to review and audit, procedure review, and records and record retention may be relocated to the quality assurance plan with the following considerations:
: 1) Review and audit commitments may be incorporated into the quality assurance plan by relocating the existing technical specifications intact or by capturing existing structural requirements by a description of the review and audit organizations and
 
Document Control Desk Attachment I CR-1 0-03108 RC-1 1-0006 Page 4 of 8 referencing the appropriate quality assurance standards, such as ANSI standard N18.7, that explicitly duplicate current technical specification provisions.
Adherence to the standard language of the generic template NEI 06-14A Rev. 7, August 2010, in VCSNS Unit 1 QAPD will capture the existing structural requirements of independent review and audit/audit frequencies.
: 2) As a minimum, the quality assurance plan should contain a commitment to process procedures and procedure changes in accordance with an accepted standard such as ANSI N18.7. Site-specific aspects currently in technical specifications that do not duplicate ANSI N1 8.7 provisions should be relocated intact to the quality assurance plan.
Procedures and procedure change requirements of VCSNS Unit 1 Technical Specifications will be relocated intact to the Unit 1 QAPD.
: 3) The review of any license amendments related to the relocations of requirements related to records and record retention can be facilitated by licensee references to an existing quality assurance plan commitment or by the simultaneous submittal of a revision of the quality assurance plan that incorporates the relocated technical specification requirements. The review process is less complicated if the requirements are moved intact to the quality assurance plan.
Records and record retention requirements will be relocated intact to VCSNS Unit 1 QAPD.
: 4) Subsequent changes to the relocated requirements would be controlled in accordance with 10 CFR 50.54 (a).
In summary, the specific content of the administrative controls section of the TS is that information which the Commission deems essential to safe operation of the facility, and which is not already adequately covered by other regulations. Accordingly, the NRC has determined that the requirements that are not specifically required under 10 CFR 50.36(c)(5), and are not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety, can be removed from the administrative controls section of the technical specifications. AL 95-06 provides guidance for relocating the administrative controls section of the TS related to quality assurance. NEI generic template NEI 06-14A Rev. 7, August 2010 has been reviewed and accepted by the Commission as documented in the Commission safety evaluation report.
 
Document Control Desk Attachment I CR-1 0-03108 RC-1 1-0006 Page 5 of 8
 
==4.0    TECHNICAL ANALYSIS==
 
The proposed license amendment requests the relocation of several administrative control requirements from TS Section 6.0 to the VCSNS Unit 1 QAPD. This relocation applies to review and audit requirements, procedural review and approval requirements, and the record retention requirements.
As presented in the Background section, above, the NRC staff concluded that the technical specifications not specifically required under 10 CFR 50.36(c)(5), and not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety, can be removed from the administrative controls section of the technical specifications. Consistent with this policy position, the NRC staff issued Administrative Letter AL 95-06, December 12, 1995, identifying TS administrative control requirements that qualify for relocation to licensee quality assurance documents subject to the controls of 10 CFR 50.54(a). Requirements identified by AL 95-06 include review and audit, procedure review and approval, and record retention requirements. The changes proposed herein conform to the NRC staff position presented in AL 95-06 and NEI 06-14A Rev. 7, August 2010.
Revisions to the administrative controls section of the VCSNS Unit 1 TS are currently subject to a no hazards consideration determination pursuant to 10 CFR 50.92. This determination is oriented to design and operational requirements described in the TS.
The administrative controls selected for relocation are considered by the NRC in the above referenced AL 95-06 to be quality assurance requirements and, therefore, qualify for incorporation into documents describing the licensee's quality assurance program. As stated in AL 95-06, 10 CFR 50.54(a) is the appropriate regulation for controlling changes to these and other quality assurance program requirements. Prior NRC approval is required of any changes to the quality assurance program that reduce the commitments in the program description as accepted by the NRC. Accordingly, the proposed license amendment relocating these administrative requirements from the TS to a document subject to the controls of 10 CFR 50.54(a), results in an equivalent level of regulatory authority while providing for a more appropriate change control process.
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 6 of 8 5.0    REGULATORY SAFETY ANALYSIS 5.1    No Significant Hazards Consideration SCE&G has evaluated the proposed changes to the VCSNS Unit 1 license described above against the significant hazards criteria of 10 CFR 50.92 and has determined that the changes do not involve any significant hazard. The following is provided in support of this conclusion.
: 1.      Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
No.
The proposed changes involve the relocation of several administrative requirements from the TS to a document subject to the controls of 10 CFR 50.54(a), and is, therefore, administrative in nature. The relocated requirements involve review and audit, procedure review and approval, and record retention requirements. The change will not alter the physical design or operational procedures associated with any plant structure, system, or component. The change does not reduce the duties and responsibilities of the organizations performing the review, audit, and approval functions essential to ensuring the safe operation of the plant.
: 2.      Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No.
The proposed changes are administrative in nature. The changes do not alter the physical design, safety limits, or safety analysis assumptions, associated with the operation of the plant. Accordingly, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not introduce a new or different accident initiator or introduce a new or different equipment failure mode or mechanism.
: 3.      Does the proposed amendment involve a significant reduction in a margin of safety?
No.
 
Document Control Desk Attachment I CR-10-03108 RC-1 1-0006 Page 7 of 8 The proposed changes conform to NRC regulatory guidance regarding the content of plant Technical Specifications. The guidance is presented in Final Policy Statement 58 FR 39132 and Administrative Letter AL 95-06. The relocation of these administrative requirements will not reduce the quality assurance commitments as accepted by the NRC, nor reduce administrative controls essential to the safe operation of the plant. Future changes to these administrative requirements will be performed in accordance with 10 CFR 50.54 (a), consistent with the guidance identified above. Accordingly, the relocation results in an equivalent level of regulatory control.
Therefore, these changes do not involve a significant reduction in a margin of safety because the proposed changes do not reduce the margin of safety that exists in the present Technical Specifications.
5.2    Applicable Regulatory Requirements/Criteria The NRC provided guidance for the contents of TS in its "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors", 58 FR 39132, July 22,1993. In particular, the NRC indicated that certain items could be relocated from the TS to licensee controlled documents, and identified criteria to be used to determine the functions to be included in TS. The NRC's policy statement provides that particular details of administrative controls may be relocated to licensee-controlled documents where section 50.54, 50.59, or other regulations provide adequate regulatory control. The specific content of the administrative controls section of the TS is that information which the Commission deems essential for the safe operation of the facility and which is not already adequately covered by other regulations. Accordingly, the NRC has determined that requirements that are not specifically required under 50.36(c)(5), and are not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety, can be removed from TS administrative controls.
Consistent with this policy position, the NRC staff issued Administrative Letter (AL) 95-06, December 12, 1995, identifying TS administrative control requirements that qualify for relocation to licensee quality assurance control documents subject to the controls of 10 CFR 50.54(a). Requirements identified by AL 95-06 include review and audit, procedure review and approval, and record retention requirements. The changes proposed herein conform to the NRC staff position presented in AL 95-06.
The proposed license amendment to relocate these administrative requirements to a document subject to the controls of 10 CFR 50.54(a), conforms with NRC guidance as stated above, and results in an equivalent level of regulatory control.
 
Document Control Desk Attachment I CR-1 0-03108 RC-1 1-0006 Page 8 of 8 In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
 
==6.0    ENVIRONMENTAL CONSIDERATION==
 
The proposed amendment is confined to changes to administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
 
==7.0    REFERENCES==
: 1. NUREG 1431, Revision 3, Standard Technical Specifications Westinghouse Plants
: 2. NRC "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors," (58 FR 39132, dated July 22, 1993).
: 3. 10 CFR 50.36, "Technical Specifications."
: 4. 10 CFR 50.54, "Conditions of Licenses."
: 5. 10 CFR 50.92, "Issuance of Amendment."
: 6. NRC Administrative Letter 95-06, "Relocation of Technical Specifications Administrative Controls Related to Quality Assurance."
: 7. NEI 06-14A Rev. 7, August 2010, "Quality Assurance Program Description"
 
Document Control Desk Attachment II CR-1 0-03108 RC-1 1-0006 Page 1 of 16 ATTACHMENT II PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages        Insert Pages XVIII            XVIII XlX                ---
XX                ---
6-4              6-4 6-5                ---
6-6                ---
6-7                ---
6-8                ---
6-9                ---
6-10              6-10 6-11              6-11 6-17              6-17 6-18              6-18 6-19              6-19 6-20                ---
 
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.6.7    SAFETY LIMIT VIOLATION ...............................................................................                                      6-10 6.8    PROCEDURES AND PROGRAMS ....................................................................                                                6-11 6,9    REPORTING REQUIREMENTS 6.9.1        ROUTINE REPORTS Startup R eport ........................................................................................                              6-13 A nnual R eport ........................................................................................                              6-13 Annual Radiological Environmental OperatingReport...........................                                                          6-14 Annual Radioactive Effluent Release Report ......................................... .. t .....                v                      6-14
                                                                                                                                                            ]
Core Operating Limits Report ................................................................                                          6-16 6.9.2        SPECIAL REPORTS ..............................................................................                                        6-17 6,o ..... DR*;-N:FITlo:: ...... &14                -. 4:        . . . . . . . . . . . . . . . . . . :.. . . . . . . . . . .                        6-17 6.11    RADIATION PROTECTION PROGRAM ......................................................                                                        6`,1,8 6.12    HIGH RADIATION AREA.......................................                  . . . .. . .. . . .. . . .. . .. . .. . .. . . .. . .. . ...... 6X-
            ý5rit              ý&,j~16psp 7Wmg-                                                      iwAVPEc TjDAJ                                    RcFIKr6-4 SUMMER - UNIT I                                        XIX                                  Amendment No. 3", 99,-. 04, 175
 
INDEX                                      el j EA ADMINISTRATIVE CONTROLS SECTION                                                                      PAGE 6.13  PROCESS CONTROL PROGRAM/. e)..................................          6-W 6.14  OFFSITE BOSE CALCULATION MANUALZ.*!,I .... t:  ......  .......
SUMER - UNIT 1                                                ,NAmwndmnt No. ;$, 104
 
ADMINISTRATIVE CONTROLS I-S  6      6.5 REVIEW AND AUDIT the General Manager, Nuclear            Pat 6..6.5..5x.1 The PSRC shall function to toadvise  nuclear    safety.
Opera ons on all matters            related of a (PSRC) shall be compo 6.5.1              Plant Safety Review Committee to ten members of the Virgil yq~e                                                              Station C. Summer Nudean a Station chairman and                                    Nuclear  Plant above. Operations Gneral These    positi  *s  will be des6gnated by management                          Manager, eta/the at the manager level        or tOperations, r  e At la minimue, representtives              Services shall be Adm inistrative P                                                  Eniner Maintenance, Chemist              and Health Physitcs, and                                                    t appointed to the PSRC...
ALTERNATES 6.5.1.3 All alternate                  r shall be appoin            in writing by the PSRC Chairman to serve on a tempora                basis; howev , alternates, including the chairman's alternate, who are pa Icipating s voting members in the PSRC shall hold a                  vote in all        Ract ities.
MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at leasi by the PSRC Chairman or his designqli 6.5.1.5 The minimum quorum o the PSRC necessa                        for the performance of the PSRC responsibility          and  aut  n rity or  provision his          of designated  the alt    Technical nate            majority of and a Specifications shall consist of the Chal the PSRC appointed membe/ including their alternates.
R.ESPONSIBILITIE_...SS review:
6.5.1.6 The Plant /afety Review Co,.uttee shall
: a. Static administrative procedures and changes theret*
t ~procedures,
: b. Thei afety evaluations for 1) procedures, 2) changes                            under the ea ipuent osyesand 3) tests orexperiments                          complet~ed CFR,  to  verify    that  such  actions  did zrovision of Section 50.59, 10                                        program    required otconstitute an unreviewed          safety  question    and  all by Specification 6.8 and changes thereto.
SProposed                procedures and changes to procedures, equipment or sys in which may involve an unreviewed safety question as defined Section 50.59, 10 CFR, t( -1~e-e4eA SUMMER - UNIT I                                    6-4                              Amendment No.      95
 
ADMINISTRATIVE CONTROLS W      d. Proposed tests or experiments which may involVe*n        unreviewed safety question as defined in Section 50.59, 10 CFR.
: e. Proposed changes to Technical Specificatibns or the Operating Li nse.
: f. Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nucl ar afety significance or reports of abnormal degradation of s tems IWgned to contain radioactive material.
: g. Rep eats cted of significant performanceoperating and                          of plantabnormalities  or devia ons 'from normal equipment that affe    nuclear safety.
: h. Review      all REPORTABLE EVENTS.
: i. All recogn ied indications of an unanticipated de ciency in some aspect of design or operation of safety relatod tructures, systems, or component,/
: j. The plant Secur      Plan and changes thereto.
: k. The Emergency Plan nd changes thereto.
: 1. Items which may cons tute a potential          clear safety hazardas identified during revi      of facility o eratons.
M. Investigations or analyses of sped          subjects as requested by the Chairman of the Nuclear Sa ty Rev*w Camittee..
: n. The unexpected offsite releas      qo radioactive material and the report as described in 10 CFR        .73.
: o. Changes to the PROCESS CONT        P RAN and the OFFSITE DOSE CALCULATION MANUAL.
: p. The plant Fire Protectio Program an          evisions there to.
AUTHORI"/
6.5.1.7  The Plant Safety Re ew Committee shall:
: a. Recomend in wri ng to the General Manager,            clear Plant Operations, ap      val or disapproval of items co sidered under 6.5.1.6a, c, , e, j, and k above.
: b. Render detominations in writing to the General Man* er, Nuclear Plant Operatioo , with regard to whether or not each iter          nsidered under 6.5.1.6      c, and d above constitutes an unreviewed saoety question.
C. Make    comendations in writing to the General Manager, Nuclear Plant Oper tions, that actions reviewed under f.5.1.6(b) above d          not con-st*        an unreviewod safety question.                        4.
: d.        vide written notification within 24 hours to the Vice Presi nt, Nuclear Operations and the Nuclear Safety Review Committee of di-agreement between the PSRC and the General Manager, Nuclear Plant Operations however, the General Manager, Nuclear Plant Operations s          11 I have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
SU"MER - UNIT 1                          6-5                        Amendment No. ;,    79.
 
AOMINIS'TRATIVE CONTROLS.          -
: 6. 6.8 The Plant Safety Review Committee shall maintain written minutes of each RC meeting that, at a minim=, document the results of all PSRC actIv-a ities      armed under the responsibility and authority provisions of these tectmica specifications. Copies shall be provided to the Vice President a
Nuclear,      ations, and the Chairman of the Nuclear Safety Review Commit, 6.5.2.1 The.Nudle        Safety Review Committee shall function to              vi .
Independent. review        audit of designated activities in. the                of:
: a. nuclear            plant operations....
b,. cW.che        Ois"ad- r ng nuclear: engi            omli
* d. metal~lurgy,            md      r
: e. t1 -,  mm  tton and1,o f1. radiological, safety.
: g. mechanical and electrical                    ng.
: h. quality, aswance practices 6.5.2.2 NSRC shall consist of a C                man and      or more other members appointed by th. Vice President.                lear Operati        No more than a minority of the members of the NSRC        shal      ave  line  respons  ility  for the operation of the unit.
The NSRC members shall hal              Bachelor's degree* in an e ineering or physical science field or equival              experience and a minimumi.of ve years of..technical experience of which a            =ml of three years shall be in a or more of the.
disciplines  of 6.5.2.                        In the. aggregate, the through h.practical                            ership of the comittee    shall    prov    specific                  experience in the      ority of the disciplines of 6.5 .1a through h..
6.5.2.3 All lternate members shall be appointed inwriting by the V. President,                I Nuclear      ations; however, no more than two alternates shall particip                  as voting        rs in NSRC activities at any one time.
: 6. .4 Consultants shall be utilized as determined by the 16RC Chairman to p ide expert advice to the NSRCi..
SUMM4ER -  UNIT 1                                            Amendment No. 10,702117 .
6-I~o~6.4
 
ADMINISTRATIVE CONTROLS ETING FRE UENCY              0/
6.5. .5  The NSRC shall meet at least once per calendar quarter during the initi 1 year of unit operation following fuel' loading and at least once p r six mo hs thereafter.
rQUORUM 6.5.2.6 A qu uum of the NSRC necessary for the performance of th NSRC review and audit funct ns of these Technical Specifications shall con st of the Chairman or his esignated alternate and at least 3 NSRC memb s including alternates.: No no    than a minority of the quorum shall hav line responsibilit for operation of the unit.
REVIEW 6.5.2.7  The NSRC shail re ew:
: a. The safety evaluatioRks for 1) changes t procedures, equipment or systems, and 2) tests qr experiments      mpleted under the provision of Section 50.59, 10 CFP., to verify    at such actions did not constitute an unreviewed s.aety qu tion.
: b. Proposed changes to procedur    ,  quipment or systems wiich involve an unreviewed safety question    s defined in Section 50.59, 10 CFR.
: c. Proposed tests or experimepts whio    involve an unreviewed safety question as defined in S tion 50.        10 CFR.
: d. Proposed changes to T hnical Specific      ions or this Operating License.
: e. Violations of cod s, regulations, orders, echnical Specifications, license require nts, or internal procedures r instructions having nuclear safet significance.
: f. Significan operating abnormalities or deviations r om      normal and expected    rformance of unit equipment that affect      clear safety.
: g. All RE    RTABLE EVENTS.
: h. All recognized indications of an unanticipated deficiency        some a ect of design or operation of structures, systems, or com nents hat could affect nuclear safety.
i    Reports and meetings minutes of the Plant Safety Review Committee.
0                                T~~ek-~
SUMMER - UNIT 1                        6-7                        Amendment No. ý$, 79 1
 
ADMINISTRATIVE CONTROLS DITS perfo    r byl using established SCE&G groups such as determin 6.5.2. ThebyNSRC              Audit reports or of shall have the NSRC.            cognizance                        QA orbelow.
the audits listed      by outside Audits may be summaries will be the basis for groups            as          //
NSRC
: a.          "leconformance of unit
: b. b.. TheThpe                      e/    operation to provisions
                        *pications e0r and applicable ormance,                                              contained within the training andlicense      conditions.                                  T/echnical qualifications        n ,n                    //
bc.
The results actions taken to correct deficie of the entire unit 7        as nes occurr"nin unit equipment, structures.,  sy es or method of operation that affect nuc~lear safety.
: d. The perfoflmance "tactivities required by the Prog'ram to meet th cnrteria                                Operatlionii Quality Assurance of Appendix "B',10 C/FR 50.
: e.      The Emergency Plan animplementing g      A oharea                                              proceduires.
: f.      The Security Plan  of uni and opertion-nsided imple enting procepJres.
                                                                          'appopriate by the NSRC or the 0
Vice President, Nuclear Operationa p
: h.      The Fire Protection Program ~ //
and.jrnhplehenting procedures.
: i.      A needn              ieprotectior)'nd
: a.      qualified                                      loss pre ntion inspection pe fo ecton m d1nua      l                                                          and audit shall be programto4er      .G 41 outside and    aunit  Riev. 1,F~pebruary1979.~f50 "tlzng,4i/ther qrualified    ofte licensee firm. otertie tprotection                                personnel or a
                                                /                          and
: e.      The FIEmrecDOSE CaLCLTO              iml        m AnUALg        ancdw to prevention ipeenigp                drs program    shall 3years.
be peformed by a kI.      Te PRCSScrt Teeir              COanTOPRGA 9        sie  "qualified andipe          d  impemetnspoeurst ntgr fire consultant af tervals no greater than iu      e  perf th                                                                    7 s.Ayotidifiation ofraditopactive      wastdes.pora phe.ults ormance activities                  g                yteN 1 Co h o
required by                        thereof, the quality Assurance
: 6.  .9 The NSRC shall report se areas                              to and advise of responsibility                            the Vice President, specified                                        Nuclear Operations, in Sections                                                  on 6.5.2.7 and SUMMER- UNIT                                                                    6.5.2.8.
1      a6-8                                                                          sa, Amendment No.
shall
 
ADMINISTRATIVE CONTROLS              I
: 6. .2.10 Records of NSRC activities shall be prepared, approved and distribut as ndicated below:
: a. Minutes of each NSRC meeting shall be prepared, approved and f rwarded to the Vice President, Nuclear Operations, within 14 days fo owing each meeting.
: b.        ports of reviews encompassed by Section 6.5.2.7 above shall be pre-p d, approved and forwarded to the Vice President, N lear Ope tions, within 14 days following completion of t review.
: c. Audit umary reports encompassed by Section 6.5. .8 above, shall be forwardl    to the NSRC and the Vice President, N ear Operations.
Full audi    shall be forwarded to the manageie    positions responsible for the are    audited within 30 days after c letion of the audit by the auditing ranizatlon.
653 TECHNICAL REVIEW AND            NTROL ACTIVITIES 6.5.3.1    Activities which affect      lear safe  shall be conducted as follows:
: a. Procedures required by T      nc    Specification 6.8 and other proce-dures which affect plant nu I ar safety, and changes thereto, shall be prepared, reviewed and a      ved. Each such procedure or procedure change shall be reviewed b an ndividual/group other than the Individual/group which p pared t~e procedure or procedure change, but who may be from the s      organiza on as the individual/group which prepared the procedu or procedure        ange. Procedures other than Administrative Proures will be          o    as delineated in writing by ned the General Manage , Nuclear Plant Op tions. The General Manager.
Nuclear Plant Opqratlons will approve % tnlstrative procedures, security impleemhtling procedures, and emergency plan implementing procedures. Taemporary approval to procedur. which clearly do not change the Iptent of the approved procedures \an be made by two members of/he plant management staff, at leas one of whom holds a Senior Reactor Operator's License. For changes tp procedures which may 1nv91ve a change in intent of the approved procedures, the nperson and authorized above to approve the procedures shall al~jove the change.
0r
: b. Pi psed changes or modifications to plant nuclear sa            ~-related sructures, systems and components shall be reviewed as eslgnated by the General Manager, Nuclear    Plant Operations. Each such      ifoica-Iton shall be designed as authorized by Engineering Servicr and
* shall be reviewed by an individual/group other than the tndi dual/
group which designed the modification, but who may be from th same organization as the individual/group which designed the modific ions.
Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the SGeneral                Manager, Nuclear Plant Operations.
SUMMER  -  UNIT 1                            6-9      Amendment No. 3,70.117
 
ADMINISTRATIVE CONTROLS
  'c.          Proposed tests and experflents which affect plant nuclear safety and a
F7-. are not addressed in the Final Safety Analysis Report shall be
            -ýreviewed by an individual/group other than the individual/group
              'wh~h prepared the proposed test or experiment.
                                                                                          "    4
: d.      Events'rportable pursuant to the Technical Specification 64--and violatioinisOf Technical Specifications shall be investi gtgtd and a report prepaped which evaluates the event and which pjiogtdes recom-mendations to prevnt recurrence. Such report sh"-be approved by the General Manager',.NIuclear Plant Operations _nd forwarded to the Chairman of the Nuclea'S~ety Review Co.i          e.
: e.      Individuals responsible for'pqViews pe rued in accordance with 6 .5.3.1.a, 6.5.3.1.b, 6.5.3.1., -nd
                                                      .5.3.1.d shall be members of the plant staff that meet or exceed      g.*ualification requirements of Sec-tion 4 of ANSI 18.1, 1971, a reviou I designated by the General Manager, Nuclear Plant Op      ions. Each sch review shall include a determination of wheth or not addti onal,,ross-disciplinary, review is necessa      If deemed necessary, suc rview shall be performed by th      view personnel of the appropritel discipline.
: f. Each review Ill include a determination of whether or~not an unrevi      safety question is involved.
RECORDS 6..5.3. .Zecords of the above activities shall be provided to the General              'S[ .
Man gor, Nuclear Plant Operations, PSRC and/or NSRC as necessary for required
_?i ews.
6.6 6.6.1 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:
4.~~Ae~Ae~c
: a. The Commiission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73.to 10 CFR Part 50, and
: b. Each REPORTABLE EYENT shall be reviewed by the PSRC and the results of this review shall be submitted to the NSRC and the Vice President, Nuclear Operations.
6.7 SAFETY LINIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
: a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President, Nuclear Operations and the NSRC shall be notified within 24 hours.
: b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
: c.      The Safety Limit Violation Report shall be submitted to the Comission, the NSRC and the Vice President, Nuclear Operations within 14 days of the violation.
SUMMER - UNIT I                            6"10                        Amendment No. 75,77.79
 
        /4-pp;<?_              pfCeA V-      LA  ae            Y-e~  c  .n  4-Uie-
                              /fgL~JVCeThPr0            af-3r7 Pe->C""eJ).
ADMINISTRATIVE CONTROLS
: d. Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8    PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
: a. The Gu-ide_*applio*-!_e  ped 42, r_*
1.33, Revision        re te Feb.r-_.ry ,-,le-_
1978.
9    in Apn-fi, "A" noRzlati=-y
: b. Refueling operations.
c.-  Surveillance and test activities of safety-related equipment.
: d. Security Plan.
: e. Emergency Plan.
: f. Fire Protection Program.
PROCESS CONTROL PROGRAM.
OFFSITE DOSE CALCULATION MANUAL.
: i. Effluent and environmental monitoring program-using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.
6.8.3 NOT USED.
6.8.4 The following programs shall be established, implemented and maintained:
: a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the chemical and volume control, letdown, safety injection, residual heat removal, nuclear sampling, liquid radwaste handling, gas radwaste handling and reactor building spray system.
The program shall include the following:
: 1)        Preventive maintenance and periodic visual inspection requirements, and
: 2)        Integrated leak test requirements for each system at refueling cycle intervals or less.
: b. In-Plant Radiation Monitoring
: 1)      Training of personnel,
: 2)      Procedures for monitoring, and
: 3)      Provisions for maintenance of sampling and analysis equipment.
S SUMMER - UNIT 1                                    6-11 jiAmendment 3o071No.#*, ,',
 
ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.
6.10    RECORD RETENTION addition to the applicable record retention requirements of Title 10, C e of ederal Regulations, the following records shall be retained for at 1 st the *nmum period indicated.
6.10.1        e following records shall be retained for at least five yrs:
: a.      Re rds and logs of unit operation covering time inter al at each    _"
powe level.
inspections,
: b.      Records ad logs of principal maintenance activites, repair an ~eplacement of principal items of /e qipment related to nuclearsafe.
c Al r rEPRAL            NT nsumte  ace to thi pections activities,      Coisinand calibrations,
: d.      Records of surveill O :.]/*required                    by these Tec    icl Specifi    tions.
: e.      Records of changes made t the p      cedures required by Specification 6.8.1.
: f.      Records of radioactive shi ents
: g.      Records of sealed sourc    and fissio    detector leak tests and results.
Records of annual plasical inventory of        11 sealed source material h.
of record.
6.10.2 The following records shall be retained for the uration of the Unit Operating License.                                          . ..
e                a.      Records a*( drawing changes reflecting unit design m~difications made to systi s and equipment described in the Final Safet)y(nalysis Report.
: b.      Rec          new and tds ofburnup    irradiated fuel inventory, fuel translrs and histories.
aembly
~c.                    fRecords of radiation exposure for all individuals entering rad Fation
                          /controlareas.
material released to the
: d.      Records of gaseous and liquid radioactive environs.
SUMMER    -  UNIT 1                        6-17                        Amendment No. 19
 
ADMINISTRATIVE CONTROLS                                                                  .O
: e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.
: f. Records of reactor tests and experiments.
: 5.                  &"
                          "bYMU
                            &U          IUALkVA W&ii.&        W %.%PA A IUAk  WWAAULU a W"A  %
: h. Records o, -service inspections performed p                  ohs Technical S ifications.
: i. Recordsof                  ance activities as ecified in the NRC's approved      E&        *tion on Regulato      uide 1.88, Rev. 2, October 1976.4
: j. Records ofreviews perform                      made to procedures or equipent or reviews oftxperiments                    pursuant to 10 CFR
: k. Records of meetings/        e PSRC and        SRC.
I. Records of the        ce lives of all hydraulic      mechanical snubbers definediaS        on3.7.7      uding the date at whthe service life commenc and associated installation and main ace            ,    records.
: m. Rec        seondary water sampling and water quai
: n.        ords of analysis required by the radiological environme moniorg program.
: o. Records of reviews performed for changes made to the Ofite Dose Calculation Manual and the Process Control Program.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREAS 6.12.1 In lieu of the "control device" or "alarm signal" reuired by paragraph 20.1601(a) of 10 CFR20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr* but less than 1000 mrem/hr* shall be barricaded and conspiuously posted as a high radiation area and entrance I
thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Health Physics personnel or individuals escorted by Health Physics personnel shall be exempt fion the RWP issuance requirement during the performance of their assigned duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
: a. A radiation monitorin device which continuously indicates the radiation dose rate in the area.
* Measurement made at 30 cm (12 in.) from the radiation source or from any                -
surface penetrated by the radiation.
SUMMER - UNIT 1                                  6-18              l,/l        ent No. ,
 
ADMINISTRATIVE CONTROLS
*  -4          b. A radiation montoring device which continuously integrates the radiation dose rate in the: area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device:
may be made after the dose rate level in the area has been establidhed and personnel have been made knowledgeable of them.:.
: c. A health physics qualified.individual (i.e., qualified in radiation..
protection procedures) with.a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall peorm periodic radiation surveillance at the frequency specified by the RWP.
6.12.2 In addition to the requirements of 6612.1, areas accessibleto personnel
  !V
:    with radiation lavels greater than 1000 mrem/hr* but less than 500 rads/hr**
shall be provided-with locked doors to prevent unauthorized entry, and the keys shall be maint ained under the administrative control of the duty.Shift Supervisor,:.
and/or health physics supervisimon. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area. The maximum allowable stay time for individuals in that area shall be established prior to entry. In lieu of the stay time specification of the RWP, direct or remote continuous surveillance,. .
(such as closed circuit TV cameras) shall be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
:. For individual areas accessible to personnel with radiation levels greater than 1000 mrem/hr* but less than 500 radslhr* that are located within larger areas (such as PWR containment) where no enclosure can be reasonably constructed around the individual areas, then those areas shall be barricaded, onspicuously:
posted, and a flashing light shall be activated as a warning device. .. i            .
6.13 PROCESS CONTROL PROGRAM (PCP).
6.13.1 The PCP shall be approved by the:Commission prior to implementation.
6.13.2 Changes to the POP            for 4),e cXr&+I-6n 0f-h4e "/4 Ore-.4 tvS9 Lcne.. a
: a. Shall be *ec t*..and records of reviews performed shall be
                                      - ---J        _e -=--n..:2.. This documentation..
shall,c~dhainm
: 1) Sufficient information to support the change together with the appropriate analyses.or evaluations justifying the change (s);
and::...
: 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
: b. Shall become: effective after review and acceptance by the PSRC and....:
approval of the General Manager,.Nuclear Plant Operations.
* Measurement made at 30 cm (12 in.) from the radiation source or from any surface penetrated by the radiation.:
      ** Measurement made at 1 meter from the radiation source or from any surface penetrated by the radiation.
SU.MER-UTJ          1                            .6-19            _endmentNo.#
130          "''
 
ADMINISTRATIVE CONTROLS                                                          '---
6.14OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Changes to the ODCM:          -Q0r- The 8 '.r&4;o 0n d(4Ae    Vn;4      w
: a. Shall be        ented anrecords of reviews perfored shall be irtainby .fienden 6.40.0.e. This documentation
                                                          .p_
shall C
: 1)  Sufficient information to support the change together with appropriate analyses or evaluations justifng the change(s);
E and
: 2)    A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
: b. Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Nuclear Plant Operations.
: c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Re port for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the m        of the affected pages, clearly indicating the area of the pag that was change, andshall indicate the date (e.g., monthyear) the change was implemented.
                                                                                  -4 r A4 SUMMER - UNIT 1                              6-20
                                                                  ~'~7;1*~0
 
Document Control Desk Attachment III CR-1 0-03108 RC-1 1-0006 Page 1 of 8 ATTACHMENT III PROPOSED TECHNICAL SPECIFICATION CHANGES (RETYPED)
 
INDEX ADMINISTRATIVE CONTROLS SECTION                                                                                                              PAGE 6.1  R ES PO NS IBILITY ............................................................................................ 6-1 6.2  ORGANIZATION 6.2.1      OFFSITE AND ONSITE ORGANIZATIONS .........................................                                6-1 6.2.2      UNIT STA FF ........................................................................................      6-1 6.2.3      NOT USED 6.2.4      SHIFT TECHNICAL ADVISOR ............................................................                      6-3 6.3  UNIT STAFF QUALIFICATIONS ......................................................................                6-3 6.4  NOT USED 6.5  DELETED 6.6  REPORTABLE EVENT ACTION ......................................................................                  6-10 6.7  SAFETY LIM IT VIO LATIO N .............................................................................        6-10 6.8  PROCEDURES AND PROGRAMS ..................................................................                      6-11 6.9  REPORTING REQUIREMENTS 6.9.1      ROUTINE REPORTS S tartup R eport ..................................................................................... 6-13 A nnual R eport ...................................................................................... 6-13 Annual Radiological Environmental Operating Report ..........................                              6-14 Annual Radioactive Effluent Release Report .......................................                        6-14 Core O perating Lim its Report ..............................................................              6-16 Steam Generator Tube Inspection Report ............................................                        6-16b 6.9.2      SPECIAL REPO RTS ...........................................................................              6-17 6.10  DELETED 6.11  RADIATION PROTECTION PROGRAM ........................................................                          6-17 6.12  HIG H RADIATIO N AREAS .............................................................................          6-17 6.13  PROCESS CONTROL PROGRAM (PCP) .....................................................                            6-18 6.14  OFFSITE DOSE CALCULATION MANUAL (ODCM) .....................................                                  6-19 SUMMER - UNIT 1                                          XVIII                              Amendment No. 104, 151,
 
ADMINISTRATIVE CONTROLS The following pages were deleted:
6-4 6-5 6-6 6-7 6-8 6-9 SUMMER - UNIT 1                      6-4            Amendment No. Q&,
(next page is 6-10)
 
ADMINISTRATIVE CONTROLS 6.5  DELETED 6.6  REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
: a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
: b. Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review shall be submitted to the NSRC and the Vice President, Nuclear Operations.
6.7  SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
: a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President, Nuclear Operations and the NSRC shall be notified within 24 hours.
      *b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
: c. The Safety Limit Violation Report shall be submitted to the Commission, the NSRC and the Vice President, Nuclear Operations within 14 days of the violation.
: d. Critical operation of the unit shall not be resumed until authorized by the Commission.
SUMMER - UNIT 1                                  6-10                  Amendment No. 48,-72, 79,
 
ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
: a.      Applicable procedures addressed in the Quality Assurance Program Description.
: b.      Refueling operations.
: c.      Surveillance and test activities of safety-related equipment.
: d.      Security Plan.
: e.      Emergency Plan.
: f.      Fire Protection Program.
: g.      PROCESS CONTROL PROGRAM.
: h.      OFFSITE DOSE CALCULATION MANUAL.
: i.      Effluent and environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.
6.8.2    DELETED 6.8.3    NOT USED.
6.8.4    The following programs shall be established, implemented and maintained:
: a.      Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the chemical and volume control, letdown, safety injection, residual heat removal, nuclear sampling, liquid radwaste handling, gas radwaste handling and reactor building spray system. The program shall include the following:
: 1)      Preventive maintenance and periodic visual inspection requirements, and
: 2)      Integrated leak test requirements for each system at refueling cycle intervals or less.
: b.      In-Plant Radiation Monitoring
: 1)      Training of personnel,
: 2)      Procedures for monitoring, and
: 3)      Provisions for maintenance of sampling and analysis equipment.
SUMMER - UNIT 1                                  6-11                Amendment No. ,49,-7-2, 7Q9 147 3g
 
ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.
6.10    DELETED 6.11    RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12    HIGH RADIATION AREAS 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr* but less than 1000 mrem/hr* shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Health Physics personnel or individuals escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
: a.      A radiation monitoring device which continuously indicates the radiation dose rate in the area.
: b.      A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
: c.      A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RWP.
* Measurement made at 30 cm (12 in.) from the radiation source or from any surface penetrated by the radiation.
SUMMER - UNIT 1                                    6-17                  Amendment No. 35, 49, 75, 79, 10'4, 130,
 
ADMINISTRATIVE CONTROLS 6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mrem/hr* but less than 500 rads/hr** shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the duty Shift Supervisor and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area. The maximum allowable stay time for individuals in that area shall be established prior to entry. In lieu of the stay time specification of the RWP, direct or remote continuous surveillance (such as closed circuit TV cameras) shall be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
For individual areas accessible to personnel with radiation levels greater than 1000 mrem/hr* but less than 500 rads/hr** that are located within larger areas (such as PWR containment) where no enclosure can be reasonably constructed around the individual areas, then those areas shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13    PROCESS CONTROL PROGRAM (PCP) 6.13.1    The PCP shall be approved by the Commission prior to implementation.
6.13.2    Changes to the PCP:
: a.      Shall be documented and records of reviews performed shall be retained for the duration of the Unit Operating License. This documentation shall contain:
: 1)      Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s); and
: 2)      A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
: b.      Shall become effective after review and acceptance by the PSRC and approval of the General Manager, Nuclear Plant Operations.
* Measurement made at 30 cm (12 in.) from the radiation source or from any surface penetrated by the radiation.
** Measurement made at 1 meter from the radiation source or from any surface penetrated by the radiation.
SUMMER - UNIT 1                                  6-18              Amendment No. 35, 79, !04, 4*,7
 
ADMINISTRATIVE CONTROLS 6.14  OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Changes to the ODCM:
: a. Shall be documented and records of reviews performed shall be retained for the duration of the Unit Operating License. This documentation shall contain:
: 1)    Sufficient information to support the change together with appropriate analyses or evaluations justifying the change(s); and
: 2)    A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
: b. Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Nuclear Plant Operations.
: c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
SUMMER - UNIT 1                                  6-19              Amendment No. 6 , 5*= 4 1 79, 104,117,130,
 
Document Control Desk Attachment IV CR-1 0-03108 RC-1 1-0006 Page 1 of 66 ATTACHMENT IV V.C. SUMMER NUCLEAR STATION UNIT 1 QUALITY ASSURANCE PROGRAM DESCRIPTION
 
V. C. Summer Nuclear Station Unit I Quality Assurance Program Description Revision 0 South Carolina Electric & Gas Co.
Policy Statement South Carolina Electric & Gas Co. (SCE&G) shall design, procure, and operate the V. C.
Summer nuclear plant in a manner that will ensure the health and safety of the public and workers. These activities shall be performed in compliance with the requirements of the Code of Federal Regulations (CFR), the applicable Nuclear Regulatory Commission (NRC) Facility Operating Licenses, and applicable laws and regulations of the state and local governments.
The SCE&G Quality Assurance Program (QAP) is the Quality Assurance Program Description (QAPD) provided in this document and the associated implementing documents. Together they provide for control of SCE&G activities that affect the quality of safety-related nuclear plant structures, systems, and components (SSCs) and include all planned and systematic activities necessary to provide adequate confidence that such SSCs will perform satisfactorily in service.
The QAPD may also be applied to certain equipment and activities that are not safety-related, but support safe plant operations, or where other NRC guidance establishes program requirements.
The QAPD is the top-level policy document that establishes the manner in which quality is to be achieved and presents SCE&G's overall philosophy regarding achievement and assurance of quality. Implementing documents assign more detailed responsibilities and requirements and define the organizational interfaces involved in conducting activities within the scope of the QAP. Compliance with the QAPD and implementing documents is mandatory for personnel directly or indirectly associated with implementation of the SCE&G QAP.
L444A*L-                                              Date:________
K. B. Marsh President / COO i
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 TABLE OF CONTENTS PO LICY STATEM ENT ....................................................................................................................... i PART I        INTRO DUCTIO N ................................................................................................              1 SECTIO N 1    GEN ERA L............................................................................................................        1 1.1  Scope / Applicability .........................................................................................              1 PART II      QA PD DETAILS ..................................................................................................            2 SECTION 1    ORGANIZATION ................................................................................................                2 1.1  SCE&G Corporate Management Organization ................................................                                    2 1.1.1 SCANA Chief Executive Officer (CEO) ....................................................                              2 1.1.2 SCE&G President & Chief Operating Officer (COO) ..............................                                        2 1.1.3 Executive Vice President, Generation (EVPG) .....................................                                      3 1.1.4 Senior Vice President & Chief Nuclear Officer (SVP/CNO) ..................                                            3 1.1.5 Vice President, Nuclear Operations (VPNO) .......................................                                      3 1.1.6 Director, Nuclear Training ...................................................................                        3 1.1.6.1        Manager, Nuclear Training ...........................................................                        3 1.2  V. C. Summer Unit 1 Operating Plant Management Organization ..................                                              4 1.2.1 General Manager, Nuclear Plant Operations (GMNPO) .......................                                              4 1.2.1.1        M anager, Operations ......................................................................                  4 1.2.1.2        Manager, Maintenance Services ...................................................                            4 1.2.1.3        Manager, Chemistry Services ........................................................                          4 1.2.1.4        Manager, Health Physics and Safety Services ................................                                  5 1.2.2 General Manager, Nuclear Support Services (GMNSS) ........................                                            5 1.2.2.1        Manager, Nuclear Licensing ...........................................................                        5 1.2.2.2        Manager, Planning & Scheduling ....................................................                          6 1.2.2.3        Manager, Emergency Services ........................................................                          6 1.2.2.4        Outage M anager .............................................................................                6 1.2.2.5        Workweek Management ...............................................................                          6 1.2.3 General Manager, Engineering Services (GMES) ..................................                                        6 1.2.3.1        Manager, Design Engineering ........................................................                          6 1.2.3.2        Manager, Plant Support Engineering .............................................                              7 1.2.3.3        Manager, Materials & Procurement ...............................................                              7 1.2.4 General Manager, Organizational Effectiveness (GMOE) ....................                                              7 1.2.4.1        Manager, Organizational Development & Performance ................                                            7 1.2.4.2        Manager, Nuclear Protection Services ..........................................                              8 1.2.4.3        Manager, Quality Systems .............................................................                        8 1.2.4.4      Manager, Information and Systems Technology ............................                                      8 1.2.4.5      Supervisor Records, Documents, and Reproduction ......................                                        8 1.2.5 Manager, Business and Financial Services ............................................                                8 1.2.6 Corporate Services ................................................................................                  9 1.3  Q uality Assurance .............................................................................................            9 1.4  Authority to Stop W ork .....................................................................................                9 ii
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.5    Quality Assurance Organizational Independence .............................................                      9 1.6    NQA-1-1994 Commitment ................................................................................            9 Figure 11.1-1 SCE&G Corporate Organization ..........................................................                    10 Figure 11.1.2 Unit 1 Plant Management Organization ............................................                          11 SECTION 2    QUALITY ASSURANCE PROGRAM ....................................................................                    12 2.1    Responsibilities ............................................................................................. 12 2.2    Delegation of W ork ......................................................................................... 13 2.3    Periodic Review of the Quality Assurance Program .......................................                        13 2.4    Issuance and Revision to Quality Assurance Program ..................................                            13 2.5    Personnel Qualifications ................................................................................        13 2.6    NQA-1-1994 Commitment / Exceptions ........................................................                      14 SECTION 3      DESIGN CONTROL ...........................................................................................      16 3.1    Design Verification ......................................................................................... 16 3.2    Design Records ................................................................................................. 17 3.3    Computer Application and Digital Equipment Software ................................                            17 3.4    Setpoint Control .............................................................................................. 17 3.5    NQA-1-1994 Commitment ..............................................................................            17 3.6    Design Control Commitment (Section 3) ........................................................                  17 SECTION 4      PROCUREMENT DOCUMENT CONTROL .........................................................                          18 4.1    NQA-1-1994 Commitment / Exceptions .......................................................                      18 SECTION 5      INSTRUCTIONS, PROCEDURES, AND DRAWINGS ............................................                              20 5.1    Procedure Adherence ....................................................................................        20 5.2    Procedure Content .........................................................................................      20 5.3    NQA-1-1994 Commitment .............................................................................              20 SECTION 6      DOCUMENT CONTROL .................................................................................              21 6.1    Review and Approval of Documents ............................................................                    22 6.2    Changes to Docum ents ..................................................................................        22 6.3    NQA-1-1994 Commitment ..............................................................................            22 6.4    Alternative Commitment to Biennial Review of Procedures (Section 6.1.(d))...                                    23 SECTION 7      CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES .............                                            24 7.1    Acceptance of Item or Service ......................................................................            24 7.2    NQA-1-1994 Commitment / Exceptions ........................................................                      25 SECTION 8      IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS..                                                27 8.1    NQA-1-1994 Commitment .............................................................................              27 SECTION 9      CONTROL OF SPECIAL PROCESSES .................................................................                  28 9.1    NQA-1-1994 Commitment .............................................................................              28 SECTIO N 10    INSPECTIO N..................................................................................................... 29 10.1    Inspection Program ......................................................................................... 29 10.2    Inspector Qualification ..................................................................................      29 10.3    NQA-1-1994 Commitment / Exceptions ........................................................                      29 SECTION 11    TEST CONTROL ................................................................................................ 31 11.1    NQA-1-1994 Commitment .............................................................................              31 11.2    NQA-1-1994 Commitment for Computer Program Testing ...........................                                  31 iii
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 12  CONTROL OF MEASURING AND TEST EQUIPMENT ........................................                                          32 12.1 Installed Instrument and Control Devices .....................................................                            32 12.2 NQA-1-1994 Commitment / Exceptions .......................................................                                32 SECTION 13  HANDLING, STORAGE, AND SHIPPING ............................................................                              33 13.1 Housekeeping ................................................................................................            33 13.2 NQA-1-1994 Commitment / Exceptions .......................................................                                33 SECTION 14  INSPECTION, TEST, AND OPERATING STATUS ................................................                                  35 14.1 NQA-1-1994 Commitment .............................................................................                      35 SECTION 15  NONCONFORMING MATERIALS, PARTS, OR COMPONENTS ......................... 36 15.1 Interface with the Reporting Program ............................................................                        36 15.2 NQA-1-1994 Commitment .............................................................................                      36 SECTION 16  CORRECTIVE ACTION ......................................................................................                  37 16.1 Interface with the Reporting Program ............................................................                        37 16.2 NQA-1-1994 Commitment / Exception ..........................................................                              37 SECTION 17  QUALITY ASSURANCE RECORDS ....................................................................                            38 17.1 Record Retention ............................................................................................            38 17.2 Electronic Records .........................................................................................              38 17.3 NQA-1-1994 Commitment / Exceptions .......................................................                                38 SECTION 18  A UD ITS ................................................................................................................ 39 18.1 Performance of Audits ....................................................................................                39 18.2 Internal Audits .................................................................................................        39 18.3 NQA-1-1994 Commitment .............................................................................                      40 PART III    NON-SAFETY-RELATED SSC QUALITY CONTROL ...........................................                                        41 SECTION 1  NON-SAFETY-RELATED SSCS - SIGNIFICANT CONTRIBUTORS TO PLANT SAFETY                                                        41 SECTION 2  NON-SAFETY-RELATED SSCS CREDITED FOR REGULATORY EVENTS ...............                                                    44 PART IV    REGULATORY COMMITMENTS ......................................................................                            45 NRC Regulatory Guides and Quality Assurance Standards .............................                                      45 Regulatory Guides ..........................................................................................              45 Standards ............................................................................................................ 46 PART V      ADDITIONAL QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR THE PLANT OPERATIONAL PHASE ....................................                                            47 SECTION  1  D EFIN ITIO NS ...................................................................................................      47 SECTION  2  REVIEW OF ACTIVITIES AFFECTING SAFE PLANT OPERATION ........................                                            48 SECTION  3  OPERATIONAL PROCEDURES ..........................................................................                        53 SECTION  4  CONTROL OF SYSTEMS AND EQUIPMENT DURING PLANT OPERATION ......                                                            60 SECTION  5  PLANT MAINTENANCE ...................................................................................                    61 iv
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 PART I            INTRODUCTION SECTION 1          GENERAL SCE&G's Operational Phase Quality Assurance Program Description (QAPD) is the top-level policy document that establishes the quality assurance policy and assigns major functional responsibilities for operations activities conducted by or for SCE&G. The QAPD describes the methods and establishes quality assurance (QA) and administrative control requirements that meet 10 CFR 50, Appendix B.The QAPD is based on the requirements and recommendations of ASME NOA-1-1994, "Quality Assurance Requirements for Nuclear Facility Applications," Parts I, II,and III, as specified in this document.
The QA Program (QAP) is defined by the NRC-approved regulatory document that describes the QA elements (i.e. the QAPD), along with the associated implementing documents. Procedures and instructions that control Operational Phase activities were or will be developed prior to commencement of those activities. Policies establish high-level responsibilities and authority for carrying out important administrative functions which are outside the scope of the QAPD. Procedures establish practices for certain activities which are common to all SCE&G organizations performing those activities so that the activity is controlled and carried out in a manner that meets QAPD requirements. Procedures specific to a site, organization, or group establish detailed implementation requirements and methods, and may be used to implement policies or be unique to particular functions or work activities.
1.1      Scope / Applicability The QAPD applies to operational phase activities affecting the quality and performance of safety-related structures, systems, and components, including, but not limited to:
Designing                                      Storing                                Operating Maintaining                                    Procuring                              Erecting Repairing                                      Fabricating                            Installing Modifying                                      Cleaning                                Inspecting Refueling                                      Handling                                Testing Training                                        Shipping                                Startup Decommissioning                                Receiving Safety-related SSCs, under the control of the QAPD, are identified by design documents. The technical aspects of these items are considered when determining program applicability, including, as appropriate, the item's design safety function. The QAPD may be applied to certain activities where regulations other than 10 CFR 50 establish QA requirements for activities within their scope.
The policy of SCE&G is to assure a high degree of availability and reliability of the V.C.Summer Nuclear Station Unit I while ensuring the health and safety of its workers and the public. To this end, selected elements of the QAPD are also applied to certain equipment and activities that are not safety-related, but support safe, economic, and reliable plant operations, or where other NRC guidance establishes quality assurance requirements. Implementing documents establish program element applicability.
The definitions provided in ASME NQA-1-1994, Part I, Section 1.4, apply to select terms as used in this document. Additional definitions are provided in Part V,Section 1.0 of this QAPD.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 PART II          QAPD DETAILS SECTION 1 ORGANIZATION This Section describes the SCE&G organizational structure, functional responsibilities, levels of authority and interfaces for establishing, executing, and verifying QAPD implementation. The organizational structure includes Corporate Support/off-site and on-site functions for Nuclear Plant Operations including interface responsibilities for multiple organizations that perform quality-related functions. Implementing documents assign more specific responsibilities and duties, and define the organizational interfaces involved in conducting activities and duties within the scope of the QAPD. Management gives careful consideration to the timing, extent and effects of organizational structure changes.
SCE&G Vice President Nuclear Operations (VPNO) is responsible to size the Quality Assurance organization commensurate with the duties and responsibilities assigned.
The SCE&G Nuclear Operations organization is responsible for implementing and supporting the QAPD.
Several organizations within SCE&G Nuclear Operations support New Nuclear Development through implementing and supporting the QAPD. These organizations include, but are not limited to the Procurement Group, Engineering, Training, Security, Emergency Preparedness, and SCANA Corporate Services.
During the operating life of V. C. Summer Nuclear Station (VCSNS) Unit 1, SCE&G may delegate the work of executing portions of the QAPD. However; SCE&G shall retain the responsibility for its overall effectiveness.
Outside organizations that perform activities in support of the design, procurement, fabrication, modification, inspection, test or maintenance of the safety related SSCs of the plant are required to work under an approved QAPD.
The following sections describe the reporting relationships, functional responsibilities and authorities for organizations implementing and supporting the SCE&G QAP. The SCE&G Corporate Organization and the Operating Plant Management Organization are shown in Figures 11.1-1 and 11.1-2.
1.1 SCE&G Corporate Management Organization 1.1.1    SCANA Chief Executive Officer (CEO)
The Chief Executive Officer (CEO) has the ultimate responsibility for the safe and reliable operation of each nuclear unit owned and/or operated by SCE&G. The CEO is responsible for the overall direction and management of the corporation, and the execution of the company policies, activities, and affairs. The CEO is assisted by the Executive Vice President, Generation (EVPG), and other executive staff in the nuclear division of the corporation.
1.1.2  SCE&G President & Chief Operating Officer (COO)
As delegated from the CEO, the President & Chief Operating Officer (COO) is responsible for the design, construction, and operation of SCE&G's nuclear plants. The COO directs the EVPG, who in turn directs the Senior Vice President of Nuclear Operations.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.1.3    Executive Vice President, Generation (EVPG)
The EVPG reports to the CEO through the COO. The EVPG is responsible for electric generation, overall plant nuclear safety, and takes the measures needed to provide acceptable performance of the staff in operating, maintaining, and providing technical support to the nuclear site. The EVPG delegates authority and responsibility for the operation and support of the site through the Senior Vice President, Nuclear Operations (SVP/CNO). It is the responsibility of the EVPG to provide guidance and direction such that safety-related activities, including engineering, construction, operations, operations support, maintenance, and planning, are performed following the guidelines of the quality assurance program. The EVPG is responsible for new nuclear plant licensing, design, and construction through the SVP/CNO.
1.1.4    Senior Vice President & Chief Nuclear Officer (SVP/CNO)
The SVP/CNO reports to the EVPG. The SVP/CNO serves as the Chief Nuclear Officer (CNO) and is responsible for the safe operation of all current nuclear plant operations along with the design, licensing, and construction of new nuclear plants. The SVP/CNO delegates authority and responsibility for the operation and support of the operating nuclear plants through the VPNO. The SVP/CNO is responsible for new nuclear plant licensing, design, and construction via the Vice President, New Nuclear Deployment (VPNND) who maintains control of nuclear plant construction through construction completion.
1.1.5    Vice President, Nuclear Operations (VPNO)
The Vice President, Nuclear Operations reports to the SVP/CNO and is responsible for the overall safe and efficient operation of VCSNS operating plants and for the implementation of quality assurance requirements in the areas specified by the QAPD.
1.1.6    Director, Nuclear Training The Director, Nuclear Training, reports directly to the SVP/CNO and has the overall responsibility for the accredited and non-accredited training programs at VCSNS. This includes the responsibility for providing the required training for personnel within the VCSNS Unit 1. This position is responsible for the management of all nuclear learning programs for the VCSNS Unit 1. The position is also part of the Senior Management team that provides overall strategic direction for nuclear operations.
1.1.6.1 Manager, Nuclear Training The Manager, Nuclear Training, reports directly to the Director, Nuclear Training, and is responsible for the operations-related training programs. This includes the operation, certification, and coordination of the maintenance and modification of the VCSNS Simulators. This also includes training programs for manager/technical staff personnel, shift engineers/technical advisors, and licensed and non-licensed operators. The Manager, Nuclear Training, is also responsible for the maintenance and technical training programs for the V. C. Summer Nuclear Station. This includes training in the areas of Maintenance, Health Physics, Chemistry, and Engineering.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.2 VCSNS Unit 1 Operating Plant Management Organization The operating organization is responsible for keeping the VPNO abreast of plant conditions and verifying that the day to day operations of the plant are conducted safely and in accordance with all administrative controls including the QAPD.
1.2.1    General Manager, Nuclear Plant Operations (GMNPO)
The GMNPO reports to the VPNO, and is responsible for overall safe operation of the plant, and has control over those onsite activities necessary for safe operation and maintenance of the plant including operations, chemistry, maintenance, and modification. Additionally, the GMNPO has overall responsibility for occupational and public radiation safety. The GMNPO is the Chairman of the Plant Safety Review Committee (PSRC). The GMNPO is also referred to as the Plant Manager.
1.2.1.1          Manager, Operations The Manager, Operations, is responsible for the day to day operation of the plant in a safe and efficient manner in compliance with the operating license. Manager, Operations is responsible for review and implementation of normal and emergency training and retraining programs. He/she has the assistance of the Operations Supervisor. In the absence of the Manager, Operations, the Operations Supervisor will assume his/her responsibilities.
1.2.1.2          Manager, Maintenance Services The Manager, Maintenance Services, is responsible for establishing and implementing the programs for maintenance activities to ensure the continued safe, efficient, and reliable operation of the V. C. Summer Station. Manager, Maintenance Services is responsible to ensure the Station is maintained in compliance with company policies as they relate to Maintenance Services.
1.2.1.3          Manager, Chemistry Services The Manager, Chemistry Services is responsible for directing and coordinating in-plant chemistry and water treatment programs.
The Manager, Chemistry Services, has the responsibility of supervising the Chemistry Supervisors and the Chemistry Specialists. Through this staff, the Manager, Chemistry Services is charged with implementing the chemistry programs, controlling non-rad releases, maintaining the quality of fluids in various plant systems within the prescribed limits, operating water treatment facilities, ensuring that written procedures within his/her scope of supervision reflect the criteria of performance standards established by regulatory agencies, and ensuring that these procedures are followed. He/she is responsible for ensuring that training and retraining of Chemistry personnel are performed as scheduled by the Nuclear Training Department. The Chemistry Specialists, under the direction of the Chemistry Supervisors, perform tasks incident to the categories of work implemented by the Manager, Chemistry Services.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.2.1.4            Manager, Health Physics and Safety Services The Manager, Health Physics and Safety Services (MHPSS), is responsible for directing and coordinating station health physics and radwaste programs. In addition, the MHPSS establishes occupational safety and health policy as well as providing technical support to plant staff concerning occupational health and safety issues.
The MHPSS is responsible for directing and coordinating health physics, count room and radwaste processing, environmental monitoring, and dosimetry activities. He/she plans, coordinates and / or directs supportive station activities with regard to the Radiation Protection, Radiological Effluent Control, Environmental Surveillance, Dosimetry, Radwaste Processing and Disposal, and Analytical programs. Through evaluations, he/she advises management on program status issues related to these programs and technical guidance for issue resolution. He/she has direct access to the General Manager, Nuclear Plant Operations for matters concerning any phase relative to radiological protection and occupational safety.
The MHPSS, has the responsibility of supervising the activities of the Health Physics Supervisors and the Health Physics Specialists as well as the subcontractor support. Through this staff, the Manager, HPSS is charged with controlling the exposure of plant personnel and the public to radiation, preventing the spread of radioactive contamination, ensuring that written procedures reflect the criteria for establishing performance standards, and ensuring that these procedures are followed. He/she is responsible for ensuring that training and retraining of health physics personnel are performed as well as providing health physics services, radiological engineering expertise, and periodic health physics reviews for all plant personnel.
He/she is responsible for the timely submission of reports pertaining to health physics, radioactive waste releases to the environment, and other areas as required.
1.2.2    General Manager, Nuclear Support Services (GMNSS)
The GMNSS reports to the VPNO, and is overall responsible for Nuclear Licensing; Emergency Services; the Planning and Scheduling processes; Outage Planning; and the scheduling of modification, testing, and inspection activities.
The GMNSS is responsible for directing the Manager, Nuclear Licensing, to develop and maintain effective communications with and in response to regulatory authorities; directing the Manager, Emergency Services to ensure emergency plans, programs and procedures are being properly maintained and implemented to meet the requirements of SCE&G and the regulatory authorities; directing the Manager, Planning &
Scheduling, to ensure that maintenance activities are properly planned to minimize unavailability of Safety-Related SSCs; and directing the Outage Manager to ensure that refueling outages are properly planned, scheduled, and executed.
1.2.2.1      Manager, Nuclear Licensing The Manager, Nuclear Licensing is responsible for the development and implementation of the SCE&G nuclear licensing policy while ensuring that applicable safety and environmental regulatory standards are met. Additionally, the Manager, Nuclear Licensing is responsible for reviewing general safety questions, safety issues, and safety goals; Probabilistic Risk and Safety Analyses Programs, NRC industry issues and vendor correspondence for insight on industry activities and practices, and evaluating the potential impact of generic regulatory issues. Working together with all SCE&G organizations, Manager, Nuclear Licensing coordinates the generation, amendment, and distribution of various licensing documents, such as the FSAR, and development of Licensee Event Reports (LERs) per 10CFR50.73 and other written reports 5
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 required by regulations or the Operating License. As the principal interface with the Nuclear Regulatory Commission and other regulatory agencies, NL ensures that the respective directives, requests, and information documents are distributed to the proper organizations and that any necessary responses are developed and submitted within the prescribed time frame. Also reporting to the Manager, Nuclear Licensing is the PRA group. The PRA group is responsible for the development and maintenance of PRA models used to support risk informed applications and for providing risk insights to: processes which control risk informed applications, proposed changes to plant design and licensing basis, maintenance activities, and off normal plant events or conditions.
1.2.2.2      Manager, Planning & Scheduling The Manager, Planning & Scheduling is responsible for the scheduling of maintenance, modification, test and inspection activities within the constraints imposed by operational, regulatory, and system load requirements.
1.2.2.3      Manager, Emergency Services The Manager, Emergency Services is responsible for the effective planning, coordination, and management of the V.C.Summer Nuclear Plant emergency preparedness program. Additional responsibilities include ensuing that the emergency plans, programs, and procedures are being properly maintained and implemented to meet the requirements of SCE&G and the regulatory authorities.
1.2.2.4      Outage Manager The Outage Manager is responsible for planning, scheduling, and executing refueling outages within the established outage schedule and budget.
1.2.2.5      Workweek Management Workweek Management organization is responsible for and serves as primary organizational interface with outside organizations for management, engineering, planning and implementation of capital projects. The organization provides coordination and interface for resolving conflicts and delays for execution of activities as necessary for project implementation.
1.2.3    General Manager, Engineering Services (GMES)
The GMES is the onsite lead position for engineering and reports to the VPNO. The GMES is responsible for engineering activities related to the operation or maintenance of the plant and design change implementation support activities. The GMES directs functional managers responsible for plant support engineering, design engineering, and materials and procurement.
1.2.3.1      Manager, Design Engineering The Manager, Design Engineering is responsible for resolving design issues, onsite development of design-related change packages and plant modifications, managing contractors who may perform design-related activities, maintaining the configuration control program, and developing and maintaining engineering programs such as accident analysis activities and ISI.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 The Nuclear Design and Analysis Engineers, who report to the Manager, Design Engineering, ensure that reactor engineering tests are performed in accordance with plant procedures and manuals and ensuring that current industry techniques are utilized to monitor and reduce megawatt loss. The Core Design Engineers are responsible for evaluating, designing, and managing core design changes.
1.2.3.2        Manager, Plant Support Engineering The Manager, Plant Support Engineering supervises a technical staff of engineers and other engineering specialists and coordinates interfaces with other groups as necessary. The Manager, Plant Support Engineering is responsible for providing direction and guidance to system engineers for monitoring the efficiency and proper operation of balance of plant and reactor systems, planning programs for improving equipment performance, reliability, or work practices; overseeing operational tests and analyzing the results; and maintaining engineering programs such as IST, valve testing, maintenance rule, piping erosion/corrosion, and system/equipment reliability.
1.2.3.3        Manager, Materials & Procurement The Manager, Materials & Procurement (MMPR) is responsible for all site purchasing activities, Supplier Quality Audits, Receipt Inspections, and Procurement Engineering functions. The MMPR is also responsible for providing sufficient and proper materials to support the needs of the plant and performing related activities including procedure development, procurement and materials storage, and supply system database management.
1.2.4    General Manager, Organizational Effectiveness (GMOE)
The GMOE reports to the VPNO. The GMOE directs managers responsible for Nuclear Protection Services, Quality Systems" overall coordination of station Information Systems Technology activities, Change Management, Organizational Development & Performance and Corrective Action Program, and supervisor for Records and Document Control. Additionally, the GMOE holds the position and responsibilities of Chairman of the Corrective Action Review Board.
1.2.4.1        Manager, Organizational Development & Performance The Manager, Organizational Development & Performance (MOD&P), is responsible for directing and coordinating the station organizational effectiveness programs, to include human performance, operating experience, root cause, corrective action, self-assessment, management observation, trending and benchmarking programs to effectively develop and coordinate these programs to aid in the development of a strong learning organization and to promote continuous improvement.
The MOD&P, has the responsibility of supervising the Corrective Action Supervisor and Human Performance Supervisor. Through this staff, the MOD&P, is responsible for the implementation of the OD&P organizational effectiveness programs and ensuring written procedures accurately reflect the criteria for establishing performance standards and are adhered to. The incumbent is responsible for ensuring that training and retraining of the OD&P personnel is performed and providing OD&P expertise and service to the station. This incumbent establishes and maintains rapport with plant personnel, encouraging the reporting of problems and events that can adversely affect plant performance at the V.C. Summer Nuclear Station Unit 1.
The MOD&P, is responsible for performing OD&P improvement initiatives and assists in identifying and training of human error reduction techniques for all station employees. The incumbent develops and 7
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 participates in activities to identify human error challenges and opportunities for improvement, communicates to the station results to be achieved and the part they play in obtaining them, facilitates group learning sessions with supervisors and managers to identify barriers, develops goals and measures for monitoring improvement plan results and provides results to management in periodic reports, tracks initiatives and assists in the development of measures for less than desirable results and ensures strong interfaces and exchanges of information exists with others involved in improvement activities to ensure effective integration of improvement efforts.
1.2.4.2        Manager, Nuclear Protection Services The Manager, Nuclear Protection Services, is responsible for management control activities of Nuclear Security and the access control and fitness for duty program. Reporting to the Manager, Nuclear Protection Services, is the Supervisor, Operations Security, and the Supervisor, Access Control/Fitness For Duty.
The Manager, Nuclear Protection Services, is responsible for physical security, security force operations, training and qualification programs, and maintenance and testing activities for security equipment.
1.2.4.3        Manager, Quality Systems The Manager, Quality Systems (MQS), is responsible for audit, surveillance, and inspection of Nuclear Operations activities to ensure that all safety-related activities are performed in accordance with a quality assurance program which meets the criteria of 10 CFR 50, Appendix B.Quality Assurance and Quality Control services may be subcontracted as needed. Further detail can be found in Section 18 of the QAPD. The MQS is responsible for independent oversight activities performed during refueling outages, startup activities, and normal and off-normal operational activities.
The responsibility for developing, maintaining and verifying effective implementation of the QAPD rests with the MQS. The MQS through the GMOE has the responsibility and authority to report quality matters to any management level necessary within SCE&G in order to establish timely and effective corrective action. The MQS is authorized by this QAPD to identify concerns adverse to quality directly to the VPNO.
1.2.4.4        Manager, Corporate Information and Systems Technology The Manager, Corporate Information and Systems Technology reports through a dotted-line to the GMOE and is responsible for ensuring station computer operation and records applications are installed and maintained per approved procedures and working with departments to ensure regulatory compliance.
1.2.4.5      Supervisor Records, Documents, and Reproduction The Supervisor Records, Documents, and Reproduction is responsible for providing for acceptable records storage systems and locations; obtaining, filing and maintaining auditable records; and maintenance of the Station document control program.
1.2.5    Manager, Business and Financial Services The Manager, Business and Financial Services, is responsible for business and financial services and reports to the VPNO.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.2.6    Corporate Services The SCANA/SCE&G Corporate Services organizations are responsible for supporting the Nuclear Organization by performing activities related to accounting, safety and health, and environmental services where applicable, These organizations will serve the Nuclear Organization through "dotted-line" reporting to the Nuclear Organization managers.
1.3 Quality Assurance The SCE&G Quality Assurance Organization is responsible for independently planning and performing activities to verify the development and effective implementation of the SCE&G QAPD, including but not limited to engineering, licensing, document control, corrective action program, and procurement that support the operational phase of the V. C Summer nuclear power plant.
1.4      Authority to Stop Work Quality assurance and inspection personnel have the authority, and the responsibility, to stop work in progress which is not being done in accordance with approved procedures or where safety or SSC integrity may be jeopardized. This extends to off-site work performed by suppliers furnishing safety-related materials and services to SCE&G.
1.5      Quality Assurance Organizational Independence For operational phase activities, independence shall be maintained between the organization or organizations performing the checking (quality assurance and control) functions and the organizations performing the functions. This provision is not applicable to design review / verification.
1.6      NQA-1-1994 Commitment In establishing its organizational structure, SCE&G commits to compliance with NQA-1-1994, Basic Requirement I and Supplement 1S-1.
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                                                              '** Supports NND in the procurement of safety and non-safety related materials, equipment, and services. Supports NND QS personnel in the performance of external activities by the participation of NUPIC audits to determine contractor/vendor conformance to their QA program.
Figure 11.1-2 Unit 1 Plant Management Organization 11
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 2                  QUALITY ASSURANCE PROGRAM SCE&G has established the necessary measures and governing procedures to implement the QAP as described in the QAPD. SCE&G is committed to implementing the QAP in all aspects of work that are important to the safety of the nuclear plant as described and to the extent delineated in the QAPD. Further, SCE&G ensures through the systematic process described herein that its suppliers of safety-related equipment or services meet the applicable requirements of 10 CFR 50, Appendix B. Senior management is regularly apprised of the adequacy of implementation of the QAP through the audit functions described in Part II, Section 18.
The objective of the QAP is to assure that the V. C. Summer Nuclear Station Unit 1 is designed and operated in accordance with governing regulations and license requirements. The program is based on the requirements of ASME NQA-1-1994, "Quality Assurance Requirements for Nuclear Facility Applications," as further described in this document. The QAP applies to those quality-related activities that involve the functions of safety-related structures, systems, and components (SSCs) associated with the design, maintenance, testing, and safe operation of the nuclear facility and managerial and administrative controls as described in the Final Safety Analysis Report. A list or system that identifies SSCs and activities to which this program applies is maintained at the V. C. Summer Nuclear Station Unit 1. Cost and scheduling functions do not prevent proper implementation of the QAP.
As described in Part III of the QAPD, specific program controls are applied to non-safety related SSCs, for which 10 CFR 50, Appendix B, is not applicable, that are significant contributors to plant safety. The specific program controls consistent with applicable sections of the QAPD are applied to those items in a selected manner, targeted at those characteristics or critical attributes that render the SSC a significant contributor to plant safety.
Delegated responsibilities may be performed under a suppliers or principal contractors QAP, provided that the supplier or principle contractor has been approved as a supplier in accordance with the QAPD. Periodic audits and assessments of supplier QA programs are performed to assure compliance with the supplier's or principle contractors QAPD and implementing procedures. In addition, routine interfaces with the supplier's personnel provide added assurance that quality expectations are met.
For the operational phase, the QAPD applies to those operational and SCE&G activities that can affect, either directly or indirectly, the safety-related site characteristics or analysis of those characteristics.
In general, the program requirements specified herein are detailed in implementing procedures that are either SCE&G implementing procedures, or supplier implementing procedures governed by a supplier quality program.
A grace period of 90 days may be applied to provisions that are required to be performed on a periodic basis unless otherwise noted. Annual evaluations and audits that must be performed on a triennial basis are examples where the 90 day general period could be applied. The grace period does not allow the "clock" for a particular activity to be reset forward. The "clock" for an activity is reset backwards by performing the activity early. Audit schedules are based on the month in which the audit starts.
2.1      Responsibilities Personnel who work directly or indirectly for SCE&G are responsible for achieving acceptable quality in the work covered by the QAPD. This includes the activities delineated in Part I, Section 1.1. SCE&G personnel 12
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 performing verification activities are responsible for verifying the achievement of acceptable quality.
Activities governed by the QAPD are performed as directed by documented instructions, procedures and drawings that are of a detail appropriate for the activity's complexity and effect on safety. Instructions, procedures and drawings specify quantitative or qualitative acceptance criteria as applicable or appropriate for the activity, and verification is against these criteria. Provisions are established to designate or identify the proper documents to be used in an activity, and to ascertain that such documents are being used. The Manager, Quality Systems is responsible to verify that processes and procedures comply with QAPD and other applicable requirements, that such processes or procedures are implemented, and that management appropriately ensures compliance.
2.2      Delegation of Work SCE&G retains and exercises the responsibility for the scope and implementation of an effective QAPD.
Positions identified in Part II, Section I, may delegate all or part of the activities of planning, establishing, and implementing the program for which they are responsible to others, but retain the responsibility for the program's effectiveness. Decisions affecting safety are made at the level appropriate for its nature and effect, and with any necessary technical advice or review.
2.3      Periodic Review of the Quality Assurance Program Management of those organizations implementing the QA program, or portions thereof, assess the adequacy of that part of the program for which they are responsible to assure its effective implementation at least once every two years or at least once during the life of the activity, whichever is shorter.
2.4      Issuance and Revision to Quality Assurance Program Administrative control of the QAPD will be in accordance with 10 CFR 50.54(a). Changes to the QAPD are evaluated by the Manager, Quality Systems to ensure that such changes do not degrade previously approved quality assurance controls specified in the QAPD. This document shall be revised as appropriate to incorporate additional QA commitments that may be established during the operating life of the V. C.
Summer Nuclear Station Unit 1. New revisions to the document will be reviewed, at a minimum, by the Manager, Quality Systems, and approved by the Senior Vice President, Nuclear Operations/CNO.
Regulations require that the Final Safety Analysis Report (FSAR) include, among other things, the managerial and administrative controls to be used to assure safe operation, including a discussion of how the applicable requirements of Appendix B will be satisfied. In order to comply with this requirement, the FSAR references the QAPD and, as a result, the requirements of 10 CFR 50.54(a) are satisfied by, and apply to, the QAPD.
2.5      Personnel Qualifications Personnel assigned to implement elements of the QAPD shall be capable of performing their assigned tasks.
To this end, SCE&G establishes and maintains formal indoctrination and training programs for personnel performing, verifying, or managing activities within the scope of the QAPD to assure that suitable proficiency is achieved and maintained. Plant and support staff minimum qualification requirements are as delineated in the V. C. Summer Technical Specifications. Other qualification requirements may be established but will not reduce those required by Technical Specifications. Sufficient managerial depth is provided to cover absences of incumbents. When required by code, regulation, or standard, specific qualification and selection of personnel is conducted in accordance with those requirements as established in the applicable SCE&G procedures. Indoctrination includes the administrative and technical objectives, requirements of the 13
 
V. C. Summer Nuclear Station Unit I Quality Assurance Program Description Revision 0 applicable codes and standards, and the QAPD elements to be employed. Training for positions identified in 10 CFR 50.120 is accomplished according to programs accredited by the National Nuclear Accrediting Board of the National Academy of Nuclear Training that implement a systematic approach to training. Records of personnel training and qualification are maintained.
The minimum qualifications of the Manager, Quality Systems are that he/she holds an engineering or related science degree and a minimum of four years of related experience including two years of nuclear power plant experience, one year of supervisory or management experience, and one year of the experience is in performing quality verification activities. Special requirements shall include management and supervisory skills and experience or training in leadership, interpersonal communication, management responsibilities, motivation of personnel, problem analysis and decision making, and administrative policies and procedures.
Individuals who do not possess these formal education and minimum experience requirements should not be eliminated automatically when other factors provide sufficient demonstration of their abilities. These other factors are evaluated on a case-by-case basis and approved and documented by senior management.
The minimum qualifications of the individuals responsible for planning, implementing and maintaining the programs for the QAPD are that each has a high school diploma or equivalent and has a minimum of one year of related experience. Individuals who do not possess these formal education and minimum experience requirements should not be eliminated automatically when other factors provide sufficient demonstration of their abilities. These other factors are evaluated on a case-by-case basis and approved and documented by senior management.
2.6      NQA-1-1994 Commitment / Exceptions In establishing qualification and training programs, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 2 and Supplements 2S-1, 2S-2, 2S-3 and 2S-4, with the following clarifications and exceptions:
* NQA-1-1994, Supplement 2S-1
                  - Supplement 2S-1 will include use of the guidance provided in Appendix 2A-1 the same as if it were part of the Supplement. The following two alternatives may be applied to the implementation of this Supplement and Appendix:
(1) In lieu of being certified as Level I, II,or III in accordance with NQA-1-1994, personnel that perform independent quality verification inspections, examinations, measurements, or tests of material, products, or activities will be required to possess qualifications equal to or better than those required for performing the task being verified; and the verification is within the skills of these personnel and/or is addressed by procedures. These individuals will not be responsible for the planning of quality verification inspections and tests (i.e., establishing hold points and acceptance criteria in procedures, and determining who will be responsible for performing the inspections),
evaluating inspection training programs, nor certifying inspection personnel.
(2) Aqualified engineer may be used to plan inspections, evaluate the capabilities of an inspector, or evaluate the training program for inspectors. For the purpose of these functions, a qualified engineer is one who has a baccalaureate in engineering in a discipline related to the inspection activity (such as electrical, mechanical, civil) and has a minimum of five years engineering work experience with at least two years of this experience related to nuclear facilities.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 NQA-1-1994, Supplement 25-2 In lieu of Supplement 2S-2, for qualification of nondestructive examination personnel, SCE&G will follow the applicable standard cited in the version(s) of Section III and Section XI of the ASME Boiler and Pressure Vessel Code approved for use at the V. C. Summer Nuclear Station Unit 1.
NQA-1-1994, Supplement 2S-3 The requirement that prospective Lead Auditors have participated in a minimum of five (5) audits in the previous three (3) years is replaced by the following, "The prospective lead auditor shall demonstrate his/her ability to properly implement the audit process, as implemented by SCE&G, to effectively lead an audit team, and to effectively organize and report results, including participation in at least one nuclear audit within the year preceding the date of qualification."
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 3                  DESIGN CONTROL SCE&G has established and implements a process to control the design, design changes and temporary modifications (e.g., temporary bypass lines, electrical jumpers and lifted wires, and temporary setpoints) of items that are subject to the provisions of the QAPD. The design process includes provisions to control design inputs, outputs, changes, interfaces, records and organizational interfaces within SCE&G and with suppliers.
These provisions assure that design inputs (such as design bases and the performance, regulatory, quality, and quality verification requirements) are correctly translated into design outputs (such as analyses, specifications, drawings, procedures, and instructions) so that the final design output can be related to the design input in sufficient detail to permit verification. Design change processes and the division of responsibilities for design-related activities are detailed in SCE&G and supplier procedures. The design control program includes interface controls necessary to control the development, verification, approval, release, status, distribution, and revision of design inputs and outputs. Design changes and disposition of nonconforming items as "use as is" or "repair" are reviewed and approved by the SCE&G design organization or by other organizations so authorized by SCE&G.
Design documents are reviewed by individuals knowledgeable in QA to ensure the documents contain the necessary QA requirements.
3.1      Design Verification SCE&G design processes provide for design verification to ensure that items and activities subject to the provisions of the QAPD are suitable for their intended application, consistent with their effect on safety.
Design changes are subjected to these controls, which include verification measures commensurate with those applied to original plant design.
Design verifications are performed by competent individuals or groups other than those who performed the original design but who may be from the same organization. The verifier shall not have taken part in the selection of design inputs, the selection of design considerations, or the selection of a singular design approach, as applicable. This verification may be performed by the originator's supervisor provided the supervisor did not specify a singular design approach, rule out certain design considerations, and did not establish the design inputs used in the design, or if the supervisor is the only individual in the organization competent to perform the verification. If the verification is performed by the originator's supervisor, the justification of the need is documented and approved in advance by management.
The extent of the design verification required is a function of the importance to safety of the item under consideration, the complexity of the design, the degree of standardization, the state-of-the- art, and the similarity with previously proven designs. This includes design inputs, design outputs, and design changes.
Design verification procedures are established and implemented to assure that an appropriate verification method is used, the appropriate design parameters to be verified are chosen, the acceptance criteria are identified, and the verification is satisfactorily accomplished and documented. Verification methods may include, but are not limited to, design reviews, alternative calculations and qualification testing. Testing used to verify the acceptability of a specific design feature demonstrates acceptable performance under conditions that simulate the most adverse design conditions expected for item's intended use.
SCE&G normally completes design verification activities before the design outputs are used by other organizations for design work, and before they are used to support other activities such as procurement, manufacture, or installation. When such timing cannot be achieved, the design verification is completed before relying on the item to perform its intended design or safety function.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 3.2      Design Records SCE&G maintains records sufficient to provide evidence that the design was properly accomplished. These records include the final design output and any revisions thereto, as well as record of the important design steps (e.g., calculations, analyses and computer programs) and the sources of input that support the final output.
Plant design drawings reflect the properly reviewed and approved configuration of the plant.
3.3      Computer Application and Digital Equipment Software The QAPD governs the development, procurement, testing, maintenance, and use of computer application and digital equipment software when used in safety-related applications and designated non-safety-related applications. SCE&G and suppliers are responsible for developing, approving, and issuing procedures, as necessary, to control the use of such computer application and digital equipment software. The procedures require that the application software be assigned a proper quality classification and that the associated quality requirements be consistent with this classification. Each application software and revision thereto is documented and approved by authorized personnel. The QAPD is also applicable to the administrative functions associated with the maintenance and security of computer hardware where such functions are considered essential in order to comply with other QAPD requirements such as QA records.
3.4      Setpoint Control Instrument and equipment setpoints that could affect nuclear safety shall be controlled in accordance with written instructions. As a minimum, these written instructions shall:
: 1. Identify responsibilities and processes for reviewing, approving, and revising setpoints and setpoint changes originally supplied by the A/E for V. C. Summer Nuclear Station Unit 1 and the plant's technical staff;
: 2. Ensure that setpoints and setpoint changes are consistent with design and accident analysis requirements and assumptions;
: 3. Provide for documentation of setpoints, including those determined operationally; and
: 4. Provide for access to necessary setpoint information for personnel who write or revise plant procedures, operate or maintain plant equipment, develop or revise design documents, or develop or revise accident analyses.
3.5      NQA-1-1994 Commitment In establishing its program for design control and verification, SCE&G commits to compliance with NQA 1994, Basic Requirement 3, and Supplement 3S-1, and the standards for computer software contained in Subpart 2.7.
3.6      Design Control Commitment (Section 3)
The requirement that design documents are reviewed by individuals knowledgeable in QA to ensure the documents contain the necessary QA requirements is not applicable to VCSNS Operating Unit I as discussed in 10CFR50.34(f)(3)(iii)(H).
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 4                    PROCUREMENT DOCUMENT CONTROL SCE&G has established the necessary measures and governing procedures to assure that purchased items and services are subject to appropriate quality and technical requirements. Procurement document changes shall be subject to the same degree of control as utilized in the preparation of the original documents. These controls include provisions such that:
* Where original technical or quality assurance requirements cannot be determined, an engineering evaluation is conducted and documented by qualified staff to establish appropriate requirements and controls to assure that interfaces, interchangeability, safety, fit, and function, as applicable, are not adversely affected or contrary to applicable regulatory requirements.
* Applicable technical, regulatory, administrative, quality and reporting requirements (such as specifications, codes, standards, tests, inspections, special processes, and 10 CFR 21) are invoked for procurement of items and services. 10 CFR 21 requirements for posting, evaluating, and reporting will be followed and imposed on suppliers when applicable. Applicable design bases and other requirements necessary to assure adequate quality shall be included or referenced in documents for procurement of items and services. To the extent necessary, procurement documents shall require suppliers to have a documented QA program that is determined to meet the applicable requirements of 10 CFR 50, Appendix B, as appropriate to the circumstances of procurements (or the supplier may work under SCE&G's approved QA program).
Reviews of procurement documents shall be performed by personnel who have access to pertinent information and who have an adequate understanding of the requirements and intent of the procurement documents.
4.1      NQA-1-1994 Commitment I Exceptions In establishing controls for procurement, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 4 and Supplement 4S-1, with the following clarifications and exceptions:
e NQA-1 -1994, Supplement 4S-1:
                    - Section 2.3 of this Supplement 4S-1 includes a requirement that procurement documents require suppliers to have a documented QAP that implements NQA-1-1994, Part I. In lieu of this requirement, SCE&G may require suppliers to have a documented supplier QAP that is determined to meet the applicable requirements of 10 CFR 50, Appendix B, as appropriate to the circumstances of the procurement;
                  - With regard to service performed by a supplier, SCE&G procurement documents may allow the supplier to work under the SCE&G Q.AP, including implementing procedures, in lieu of the supplier having its own QAP;
                  - Section 3 of this supplement 4S-1 requires procurement documents to be reviewed prior to bid or award of contract. The quality assurance review of procurement documents is satisfied through review of the applicable procurement specification, including the technical and quality procurement requirements, prior to bid or award of contract.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 Procurement document changes (e.g., scope, technical or quality requirements) will also receive the quality assurance review; and
- Procurement documents for Commercial Grade Items that will be procured by SCE&G for use as safety-related items shall contain technical and quality requirements such that the procured item can be appropriately dedicated.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 5                  INSTRUCTIONS, PROCEDURES, AND DRAWINGS SCE&G has established the necessary measures and governing procedures to ensure that activities affecting quality are prescribed by and performed in accordance with instructions, procedures or drawings of a type appropriate to the circumstances and which, where applicable, include quantitative or qualitative acceptance criteria to implement the QAPD as described in the QAPD. Such documents are prepared and controlled according to Part II, Section 6. In addition, means are provided to disseminate to the staff instructions of both general and continuing applicability, as well as those of short-term applicability. Provisions are included for reviewing, updating, and canceling such procedures.
5.1      Procedure Adherence SCE&G's policy is that procedures are followed, and the requirements for use of procedures have been established in administrative procedures. Where procedures cannot be followed as written, provisions are established for making changes in accordance with Part II, Section 6. Requirements are established to identify the manner in which procedures are to be implemented, including identification of those tasks that require:
(1) the written procedure to be present and followed step-by-step while the task is being performed; (2) the user to have committed the procedure steps to memory; and (3) verification of completion of significant steps, by initials or signatures or use of check-off lists. Procedures that are required to be present and referred to directly are those developed for extensive or complex jobs where reliance on memory cannot be trusted, tasks that are infrequently performed, and tasks where steps must be performed in a specified sequence.
In cases of emergency, personnel are authorized to depart from approved procedures when necessary to prevent injury to personnel or damage to the plant. Such departures are recorded describing the prevailing conditions and reasons for the action taken.
5.2        Procedure Content The established measures address the applicable content of procedures as described in the introduction to Part II of NQA-1-1994. In addition, procedures governing tests, inspections, operational activities and maintenance will include as applicable, initial conditions and prerequisites for the performance of the activity.
5.3      NQA-1-1994 Commitment In establishing procedural controls, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 5.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 6                    DOCUMENT CONTROL SCE&G has established the necessary measures and governing procedures to control the preparation of, issuance of, and changes to documents that specify quality requirements or prescribe how activities affecting quality, including organizational interfaces, are controlled to assure that correct documents are being employed, The control systems (including electronic systems used to make documents available) are documented and provide for the following:
(a) identification of documents to be controlled and their specified distribution; (b) a method to identify the correct document (including revision) to be used and control of superseded documents; (c) identification of assignment of responsibility for preparing, reviewing, approving, and issuing documents; (d) review of documents for adequacy, completeness, and correctness prior to approval and issuance; (e) a method for providing feedback from users to continually improve procedures and work instructions; and (f) coordinating and controlling interface documents and procedures.
The types of documents to be controlled include:
(a) drawings, such as design, construction, installation, and as-built drawings; (b) engineering calculations; (c) design specifications; (d) purchase orders and related documents; (e) vendor-supplied documents; (f) audit, surveillance, and quality verification/inspection procedures; (g) inspection and test reports; (h) instructions and procedures for activities covered by this QAPD including design, modification, installation, operating (including normal and emergency operations), maintenance, calibration, and routine testing; (i) technical specifications; and (j)  nonconformance reports and corrective action reports.
Where temporary procedures are used, they shall include a designation of the period of time during which it is acceptable to use them.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 6.1        Review and Approval of Documents Documents are reviewed for adequacy by qualified persons other than the preparer. Station Administrative Procedures, as identified by the Manager, Quality Systems, defining and/or implementing portions of the Quality Assurance Program, shall be reviewed by Quality Systems to ensure quality assurance measures have been appropriately applied. This documented review signifies concurrence.
Documents affecting the configuration or operation of the station as described in the FSAR are screened to identify those that require review by the PSRC prior to implementation as described in Part V, Section 2 of the QAPD.
To ensure effective and accurate procedures, applicable procedures are reviewed, and updated as necessary, based on the following conditions:
(a) following any modification to a system; (b) following an unusual incident, such as an accident, significant operator error, or equipment malfunction; (c) when procedure discrepancies are found; (d) prior to use if not used in the previous two years; or (e) results of QA audits conducted in accordance with Part II,Section 18.1.
Prior to issuance or use, documents including revisions thereto, are approved by the designated authority. A listing of all controlled documents identifying the current approved revision, or date, is maintained so personnel can readily determine the appropriate document for use.
6.2        Changes to Documents Changes to documents, other than those defined in implementing procedures as minor changes, are reviewed and approved by the same organizations that performed the original review and approval unless other organizations are specifically designated. The reviewing organization has access to pertinent background data or information upon which to base their approval. Where temporary procedure changes are necessary, changes that clearly do not change the intent of the approved procedure may be implemented provided they are approved by two members of the staff knowledgeable in the areas affected by the procedures. Minor changes to documents, such as inconsequential editorial corrections, do not require that the revised documents receive the same review and approval as the original documents. To avoid a possible omission of a required review, the type of minor changes that do not require such a review and approval and the persons who can authorize such a classification shall be clearly delineated in implementing procedures.
6.3        NQA-1-1994 Commitment In establishing provisions for document control, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 6 and Supplement 6S-1.
22
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 6.4      Alternative Commitment To Biennial Review Of Procedures (Section 6.1(d))
VCSNS Unit 1 continues to implement an alternative commitment to performing biennial procedure reviews as documented in NRC Letter from Albert F. Gibson, Director Division of Reactor Safety to John L. Skolds, Vice President, Nuclear Operations dated 11/29/1990. This alternative commitment is described below:
The following programs and activities provide adequate procedure revision control and a method to verify the adequacy of these programs and activities:
      "  Plant Design Change Program
* Non-Conformance and Corrective Action Program
      "  Licensee Event Report System
      "  Operator Feedback Program
      "  Surveillance Test Program
* Operating Experience Review Program
      "  Technical Specification and FSAR Revision Process
      "  Corrective Actions for Regulatory Issues
      "  Quality Assurance Program
* Quality Assurance audit of the procedural development program using a representative sample process. The biennial audit will provide verification that the existing plant programs and activities listed above are effective in maintaining procedures current.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 7          CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SCE&G has established the necessary measures and governing procedures to control the procurement of items and services to assure conformance with specified requirements. Such control provides for the following as appropriate: source evaluation and selection, evaluation of objective evidence of quality furnished by the supplier, source inspection, audit, and examination of items or services.
7.1      Acceptance of Item or Service SCE&G establishes and implements measures to assess the quality of purchased items and services, whether purchased directly or through contractors, at intervals and to a depth consistent with the item or service's importance to safety, complexity, quantity, and the frequency of procurement. Verification actions include testing, as appropriate, during design, fabrication and operation activities. Verifications occur at the appropriate phases of the procurement process, including, as necessary, verification of activities of suppliers below the first tier.
Measures to assure the quality of purchased items and services include the following, as applicable:
* Items are inspected, identified, and stored to protect against damage, deterioration, or misuse.
Prospective suppliers of safety-related items and services are evaluated to assure that only qualified suppliers are used. Qualified suppliers are audited on a triennial basis. Inaddition, ifa subsequent contract or a contract modification significantly enlarges the scope of, or changes the methods or controls for activities performed by the same supplier, an audit of the modified requirements is conducted, thus starting a new triennial period. SCE&G may utilize audits conducted by outside organizations for supplier qualification provided that the scope and adequacy of the audits meet SCE&G requirements. Documented annual evaluations are performed for qualified suppliers to assure they continue to provide acceptable products and services. Industry programs, such as those applied by ASME, Nuclear Procurement Issues Committee (NUPIC), or other established utility groups, are used as input or the basis for supplier qualification whenever appropriate. The results of the reviews are promptly considered for effect on a supplier's continued qualification and adjustments made as necessary (including corrective actions, adjustments of supplier audit plans, and input to third party auditing entities, as warranted). Inaddition, results are reviewed periodically to determine if, as a whole, they constitute a significant condition adverse to quality requiring additional action.
Provisions are made for accepting purchased items and services, such as source verification, receipt inspection, pre- and post-installation tests, certificates of conformance, and document reviews (including Certified Material Test Report/Certificate). Acceptance actions/documents should be established by the Purchaser with appropriate input from the Supplier and be completed to ensure that procurement, inspection, and test requirements, as applicable, have been satisfied before relying on the item to perform its intended safety function.
    " Controls are imposed for the selection, determination of suitability for intended use (critical characteristics), evaluation, receipt, and acceptance of commercial-grade services or items to assure they will perform satisfactorily in service in safety-related applications.
* If there is insufficient evidence of implementation of a QA program, the initial evaluation is of the existence of a QA program addressing the scope of services to be provided. The initial audit is 24
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 performed after the supplier has completed sufficient    work  to demonstrate    that its organization is implementing a QA program.
7.2      NQA-1-1994 Commitment/Exceptions Inestablishing procurement verification controls, SCE&G commits to compliance with NQIA-1-1994, Basic Requirement 7 and Supplement 7S-1, with the following clarifications and exceptions:
NQA-1-1994, Supplement 7S-1
                - SCE&G considers that other 10 CFR 50 licensees, Authorized Nuclear Inspection Agencies, National Institute of Standards and Technology, or other State and Federal agencies which may provide items or services to the V.C.Summer plant are not required to be evaluated or audited.
                - When purchasing commercial grade calibration services from a calibration laboratory, procurement source evaluation and selection measures need not be performed provided each of the following conditions are met:
(1)The purchase documents impose any additional technical and administrative requirements, as necessary, to comply with the SCE&G QA program and technical provisions. At a minimum, the purchase document shall require that the calibration certificate/report include identification of the laboratory equipment/standard used; (2)The purchase documents require reporting as-found calibration data when calibrated items are found to be out-of-tolerance; and (3) Adocumented review of the supplier's accreditation will be performed and will include a verification of the following:
* The calibration laboratory holds a domestic (United States) accreditation by any one of the following accrediting bodies, which are recognized by the International Laboratory Accreditation Cooperation (ILAC) Mutual Recognition Arrangement (MRA):
                                              - National Voluntary Laboratory Accreditation Program (NVLAP), administered by the National Institute of Standards & Technology;
                                              - American Association for Laboratory Accreditation (A2LA);
                                              - ACLASS Accreditation Services (ACLASS);
                                              - International Accreditation Service (IAS);
                                              - Laboratory Accreditation Bureau (L-A-B); or 25
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0
                            - Other NRC-approved laboratory    accrediting body.
                    " The accreditation encompasses ANSI ANS/ISO/IEC 17025, "General Requirements for the Competence of Testing and Calibration Laboratories".
                    " The published scope of accreditation for the calibration laboratory covers the necessary measurement parameters, ranges, and uncertainties.
  - For Section 8.1, SCE&G considers documents that may be stored in approved electronic media under SCE&G or vendor control not physically located on the V.C.Summer Nuclear Station Unit 1 site, but are accessible from the site, as meeting the NQA-1 requirement for documents to be available at the site. The SCE&G records management system will provide for timely retrieval of necessary records.
-  In lieu of the requirements of Section 10, Commercial Grade Items, controls for commercial grade items and services are established in SCE&G documents using 10 CFR 21 and the guidance of EPRI NP-5652 as discussed in Generic Letter 89-02 and Generic Letter 91-05.
          - For commercial grade items, special quality verification requirements are established and described in SCE&G documents to provide the necessary assurance an item will perform satisfactorily in service. The SCE&G documents address determining the critical characteristics that ensure an item is suitable for its intended use, technical evaluation of the item, receipt requirements, and quality evaluation of the item.
          - SCE&G will also use other appropriate approved regulatory means and controls to support SCE&G commercial grade dedication activities. SCE&G will assume 10 CFR 21 reporting responsibility for all items that SCE&G dedicates as safety-related.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 Section 8                  IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS SCE&G has established the necessary measures and governing procedures to identify and control items to prevent the use of incorrect or defective items. This includes controls for consumable materials and items with limited shelf life. The identification of items is maintained throughout fabrication, erection, installation and use so that the item can be traced to its documentation, consistent with the item's effect on safety.
Identification locations and methods are selected so as not to affect the function or quality of the item.
8.1      NQA-1-1994 Commitment In establishing provisions for identification and control of items, SCE&G commits to compliance with NQA 1994, Basic Requirement 8 and Supplement 8S-1.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 9                  CONTROL OF SPECIAL PROCESSES SCE&G has established the necessary measures and governing procedures to assure that special processes that require interim process controls to assure quality, such as welding, heat treating, and nondestructive examination, are controlled. These provisions include assuring that special processes are accomplished by qualified personnel using qualified procedures and equipment. Personnel are qualified and special processes are performed in accordance with applicable codes, standards, specifications, criteria or other specially established requirements. Special processes are those where the results are highly dependent on the control of the process or the skill of the operator, or both, and for which the specified quality cannot be fully and readily determined by inspection or test of the final product.
9.1 NQA-1-1994 Commitment In establishing measures for the control of special processes, SCE&G commits to compliance with NQA 1994, Basic Requirement 9 and Supplement 9S-1.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 10                INSPECTION SCE&G has established the necessary measures and governing procedures to implement inspections that assure items, services and activities affecting safety meet established requirements and conform to applicable documented specifications, instructions, procedures, and design documents. Inspection may also be applied to items, services, and activities affecting plant reliability and integrity. Types of inspections may include those verifications related to procurement, such as source, in-process, final, and receipt inspection, as well as installation, maintenance, modification, in-service, and operations activities. Inspections are carried out by properly qualified persons independent of those who performed or directly supervised the work.
Inspection results are documented.
10.1 Inspection Program The inspection program establishes inspections (including surveillance of processes), as necessary to verify quality: (1) at the source of supplied items or services, (2) in-process during fabrication at a Supplier's facility or at a Company Facility, (3) for final acceptance of fabricated and/or installed items, (4) upon receipt of items at the V. C. Summer Nuclear Station Unit 1, as well as (5) during maintenance, modification, in-service, and operating activities.
The inspection program establishes requirements for planning inspections, such as the group or discipline responsible for performing the inspection, where inspection hold points are to be applied, determining applicable acceptance criteria, the frequency of inspection to be applied, and identification of special tools needed to perform the inspection. Inspection planning is performed by personnel qualified in the discipline related to the inspection and includes qualified inspectors or engineers. Inspection plans are based on, as a minimum, the importance of the item to the safety of the facility, the complexity of the item, technical requirements to be met, and design specifications. Where significant changes in inspection activities are to occur, management responsible for the inspection programs evaluates the resource and planning requirements to ensure effective implementation of the inspection program.
Inspection program documents establish requirements for performing the planned inspections, and documenting required inspection information such as rejection, acceptance, and re-inspection results, and the person(s) performing the inspection.
Inspection results are documented by the inspector, reviewed by authorized personnel qualified to evaluate the technical adequacy of the inspection results, and are controlled by instructions, procedures, and drawings.
10.2      Inspector Qualification SCE&G has established qualification programs for personnel performing quality inspections. The qualification program requirements are described in Part II, Section 2. These qualification programs are applied to individuals performing quality inspections regardless of the functional group where they are assigned.
10.3      NQA-1-1994 Commitment I Exceptions In establishing inspection requirements, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 10, Supplement 10S-1 and Subpart 2.4, with the following clarification. In addition, SCE&G commits to compliance with the requirements of Subparts 2.5 and 2.8 for establishing appropriate inspection requirements.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0
" Subpart 2.4 commits SCE&G to IEEE 336-1985. IEEE 336-1985 refers to IEEE 498- 1985. Both IEEE 336 -1985 and IEEE 498-1985 use the definition of "Safety Systems" from IEEE 603-1980. SCE&G commits to the definition of Safety Systems in IEEE 603- 1980, but does not commit to the balance of that standard. This definition is only applicable to equipment in the context of Subpart 2.4.
" An additional exception to Subpart 2.4 is addressed in Part II,Section 12 of the QAPD.
" Where inspections at the V.C.Summer Nuclear Facility are performed by persons within the same organization (e .g. Maintenance group), SCE&G takes exception to the requirements of NQA  1994, Supplement 10S-1, Section 3.1, the inspectors report to quality systems management while performing those inspections.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 11 TEST CONTROL SCE&G has established the necessary measures and governing procedures to demonstrate that items subject to the provisions of the QAPD will perform satisfactorily in service, that the plant can be operated safely and as designed, and that the coordinated operation of the plant as a whole is satisfactory. These programs include criteria for determining when testing is required, such as proof tests before installation, post-maintenance tests, post-modification tests, in-service tests, and operational tests (such as surveillance tests required by Plant Technical Specifications), to demonstrate that performance of plant systems is in accordance with design. Programs also include provisions to establish and adjust test schedules and to maintain status for periodic or recurring tests. Tests are performed according to applicable procedures that include, consistent with the effect on safety, (1) instructions and prerequisites to perform the test, (2) use of proper test equipment, (3) acceptance criteria, and (4) mandatory verification points as necessary to confirm satisfactory test completion. Test results are documented and evaluated by the organization performing the test and reviewed by a responsible authority to assure that the test requirements have been satisfied. If acceptance criteria are not met, re-testing is performed as needed to confirm acceptability following correction of the system or equipment deficiencies that caused the failure.
Tests are performed and results documented in accordance with applicable technical and regulatory requirements, including those described in the Technical Specifications and FSAR. Test programs ensure appropriate retention of test data in accordance with the records requirements of the QAPD. Personnel that perform or evaluate tests are qualified in accordance with the requirements established in Part II, Section 2.
11.1      NQA-1-1994 Commitment In establishing provisions for testing, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 11 and Supplement 11S-1.
11.2      NQA-1-1994 Commitment for Computer Program Testing SCE&G establishes and implements provisions to assure that computer software used in applications affecting safety is prepared, documented, verified and tested, and used such that the expected output is obtained and configuration control maintained. To this end SCE&G commits to compliance with the requirements of NQA-1-1994, Supplement 11S-2 and Subpart 2.7 to establish the appropriate provisions.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 12                  CONTROL OF MEASURING AND TEST EQUIPMENT SCE&G has established the necessary measures and governing procedures to control the calibration, maintenance, and use of measuring and test equipment (M&TE) that provides information important to safe plant operation. The provisions of such procedures cover equipment such as indicating and actuating instruments and gages, tools, reference and transfer standards, and nondestructive examination equipment.
The suppliers of commercial grade calibration services are controlled as described in Part II, Section 7.
12.1      Installed Instrument and Control Devices SCE&G has established and implements procedures for the calibration and adjustment of instrument and control devices installed in the facility. The calibration and adjustment of these devices is accomplished through the facility maintenance programs to ensure the facility is operated within design and technical requirements. Appropriate documentation will be maintained for these devices to indicate the control status, when the next calibration is due, and identify any limitations on use of the device.
12.2      NQA-1-1994 Commitment/Exceptions In establishing provisions for control of measuring and test equipment, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 12 and Supplement 12S-1 with the following clarification and exception:
          - The out of calibration conditions described in paragraph 3.2 of Supplement 12S-1 refers to when the M&TE is found out of the required accuracy limits (i.e. out of tolerance) during calibration.
          - Measuring and test equipment are not required to be marked with the calibration status where it is impossible or impractical due to equipment size or configuration (such as the label will interfere with operation of the device) provided the required information is maintained in suitable documentation traceable to the device. This exception also applies to the calibration labeling requirement stated in NQA-1-1994, Subpart 2.4, Section 7.2.1 (ANSI/IEEE Std. 336-1985).
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 13                  HANDLING, STORAGE, AND SHIPPING SCE&G has established the necessary measures and governing procedures to control the handling, storage, packaging, shipping, cleaning, and preservation of items to prevent inadvertent damage or loss, and to minimize deterioration. These provisions include specific procedures, when required to maintain acceptable quality of the items important to the safe operations of the plant. Items are appropriately marked and labeled during packaging, shipping, handling, and storage to identify, maintain, and preserve the item's integrity and indicate the need for special controls. Special controls (such as containers, shock absorbers, accelerometers, inert gas atmospheres, specific moisture content levels, and temperature levels) are provided when required to maintain acceptable quality.
Special or additional handling, storage, shipping, cleaning, and preservation requirements are identified and implemented as specified in procurement documents and applicable procedures. Where special requirements are specified, the items and containers (where used) are suitably marked.
Special handling tools and equipment are used and controlled as necessary to ensure safe and adequate handling. Special handling tools and equipment are inspected and tested at specified time intervals and in accordance with procedures to verify that the tools and equipment are adequately maintained.
Operators of special handling and lifting equipment are experienced or trained in the use of the equipment.
SCE&G establishes and implements controls over hoisting, rigging and transport activities to the extent necessary to protect the integrity of the items involved, as well as potentially affected nearby structures and components. Where required, SCE&G complies with applicable hoisting, rigging and transportation regulations and codes.
13.1      Housekeeping Housekeeping practices are established to account for conditions or environments that could affect the quality of structures, systems and components within the plant. This includes control of cleanliness of facilities and materials, fire prevention and protection, disposal of combustible material and debris, control of access to work areas, protection of equipment, radioactive contamination control, and storage of solid radioactive waste. Housekeeping practices help assure that only proper materials, equipment, processes, and procedures are used and that the quality of items is not degraded. Necessary procedures or work instructions, such as for electrical bus and control center cleaning, cleaning of control consoles, and radioactive decontamination, are developed and used.
13.2      NQA-1-1994 Commitment I Exceptions In establishing provisions for handling, storage and shipping, SCE&G commits to compliance with NQA  1994, Basic Requirement 13 and Supplement 13S-1. SCE&G also commits to compliance with the requirements of NQA 1994, Subpart 2.1, Subpart 2.2, Subpart 2.3, and Subpart 3.2, Appendix 2.1, with the following clarifications and exceptions:
NQA-1-1994, Subpart 2.1
          - Subpart 2.1, Section 3.1 and 3.2 establish criteria for classifying items into cleanness classes and requirements for each class. Instead of using the cleanness level system of Subpart 2.1, SCE&G may establish cleanness requirements on a case-by-case basis, consistent with the other provisions of Subpart 2.1. SCE&G establishes appropriate cleanliness controls for work on safety-related equipment to minimize introduction of foreign material and maintain system/component 33
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 cleanliness throughout maintenance or modification activities, including documented verification of absence of foreign material prior to system closure.
NQA-1-1994, Subpart 2.2
      - Subpart 2.2, Section 2.2 establishes criteria for classifying items into protection levels.
Instead of classifying items into protection levels, SCE&G may establish controls for the packaging, shipping, handling, and storage of such items on a case-by-case basis with due regard for the item's complexity, use, and sensitivity to damage. Prior to installation or use, the items are inspected and serviced as necessary to assure that no damage or deterioration exists which could affect their function.
      - Subpart 2.2, Section 6.6, "Storage Records:" This section requires written records be prepared containing information on personnel access. As an alternative to this requirement, SCE&G documents establish controls for storage areas that describe those authorized to access areas and the requirements for recording access of personnel. However, these records of access are not considered quality records and will be retained in accordance with the administrative controls established for the V.C.Summer Nuclear Station Unit 1.
      - Subpart 2.2, Section 7.1 refers to Subpart 2.15 for requirements related to handling of items. The scope of Subpart 2.15 includes hoisting, rigging and transporting of items for the nuclear power plants during construction.
NQA-1-1994, Subpart 2.3
      - Subpart 2.3, Section 2.3 requires the establishment of five zone designations for housekeeping cleanliness controls. Instead of the five-level zone designation, SCE&G bases its control over housekeeping activities on a consideration of what is necessary and appropriate for the activity involved. The controls are implemented through procedures or instructions which, in the case of maintenance or modification work, are developed on a case-by-case basis. Factors considered in developing the procedures and instructions include cleanliness control, personnel safety, fire prevention and protection, radiation control and security. The procedures and instructions make use of standard janitorial and work practices to the extent possible.
NQA-1-1994, Subpart 3.2
      - Subpart 3.2, Appendix 2.1: Only Section 3 precautions are being committed to in accordance with RG 1.37. In addition, a suitable chloride stress-cracking inhibitor should be added to the fresh water used to flush systems containing austenitic stainless steels.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 14                INSPECTION, TEST, AND OPERATING STATUS SCE&G has established the necessary measures and governing procedures to identify the inspection, test, and operating status of items and components subject to the provisions of the QAPD in order to maintain personnel and reactor safety and avoid inadvertent operation of equipment. Where necessary to preclude inadvertent bypassing of inspections or tests, or to preclude inadvertent operation, these measures require the inspection, test or operating status be verified before release, fabrication, receipt, installation, test or use. These measures also establish the necessary authorities and controls for the application and removal of status indicators or labels.
In addition, temporary design changes (temporary modifications), such as temporary bypass lines, electrical jumpers and lifted wires, and temporary trip-point settings, are controlled by procedures or work instructions that include requirements for appropriate installation and removal, independent / concurrent verifications and status tracking.
Administrative procedures also describe the measures taken to control altering the sequence of required tests, inspections, and other operations. Review and approval for these actions is subject to the same control as taken during the original review and approval of tests, inspections, and other operations.
14.1      NQA-1-1994 Commitment In establishing measures for control of inspection, test and operating status, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 14.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 15                NONCONFORMING MATERIALS, PARTS, OR COMPONENTS SCE&G has established the necessary measures and governing procedures to control items, including services that do not conform to specified requirements to prevent inadvertent installation or use. Instructions require that the individual discovering a nonconformance identify, describe, and document the nonconformance in accordance with the requirements of Part II, Section 16. Controls provide for identification, documentation, evaluation, segregation when practical, and disposition of nonconforming items, and for notification to affected organizations. Controls are provided to address conditional release of nonconforming items for use on an at-risk basis prior to resolution and disposition of the nonconformance, including maintaining identification of the item and documenting the basis for such release. Conditional release of nonconforming items for installation requires the approval of the designated management.
Nonconformances are corrected or resolved prior to depending on the item to perform its intended safety function. Nonconformances are evaluated for impact on operability of quality structures, systems, and components to assure that the final condition does not adversely affect safety, operation, or maintenance of the item or service. Nonconformances to design requirements dispositioned repair or use-as-is, are subject to design control measures commensurate with those applied to the original design. Nonconformance dispositions are reviewed for adequacy, analysis of quality trends, and reports provided to the designated management. Significant trends are reported to management in accordance with SCE&G procedures, regulatory requirements, and industry standards.
15.1      Interface with the Reporting Program SCE&G has appropriate interfaces between the QAP for identification and control of nonconforming materials, parts, or components and the non-QA Reporting Program to satisfy the requirements of 10 CFR 21 during operations.
15.2      NQA-1-1994 Commitment In establishing measures for nonconforming materials, parts, or components, SCE&G commits to compliance with NQA-1 -1994, Basic Requirement 15, and Supplement 15S-1.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 16                  CORRECTIVE ACTION SCE&G has established the necessary measures and governing procedures to promptly identify, control, document, classify and correct conditions adverse to quality. SCE&G procedures assure that corrective actions are documented and initiated following the determination of conditions adverse to quality in accordance with regulatory requirements and applicable quality standards. SCE&G procedures require personnel to identify known conditions adverse to quality. When complex issues arise where it cannot be readily determined if a condition adverse to quality exists, SCE&G documents establish the requirements for documentation and timely evaluation of the issue. Reports of conditions adverse to quality are analyzed to identify trends. Significant conditions adverse to quality and significant adverse trends are documented and reported to responsible management. In the case of a significant condition adverse to quality, the cause is determined and actions to preclude recurrence are taken.
Inthe case of suppliers working on safety-related activities, or other similar situations, SCE&G may delegate specific responsibilities for corrective actions, but SCE&G maintains responsibility for the effectiveness of corrective action measures.
16.1      Interface with the Reporting Program SCE&G has appropriate interfaces between the QAP for corrective actions and the non-QA Reporting Program to satisfy the requirements of 10 CFR 21 during operations.
16.2      NQA-1-1994 Commitment In establishing provisions for corrective action, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 16.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 17                  QUALITY ASSURANCE RECORDS SCE&G has the necessary measures and governing procedures to ensure that sufficient records of items and activities affecting quality are developed, reviewed, approved, issued, used, and revised to reflect completed work. The provisions of such procedures establish the scope of the records retention program for SCE&G and include requirements for records administration, including receipt, preservation, retention, storage, safekeeping, retrieval, access controls, user privileges, and final disposition.
17.1      Record Retention Measures are established that ensure that sufficient records of completed items and activities affecting quality are appropriately stored. Records of activities for design, engineering, procurement, manufacturing, inspection and test, installation, operations, maintenance, modification, decommissioning, and audits and their retention times are defined in appropriate procedures. The records and retention times are based on construction records that are similar in nature based on Regulatory Position C.2 and Table I in Regulatory Guide 1.28, Revision 3. In all cases where state, local, or other agencies have more restrictive requirements for record retention, those requirements will be met.
17.2      Electronic Records When using electronic records storage and retrieval systems, SCE&G complies with NRC guidance in Generic Letter 88-18, "Plant Record Storage on Optical Disks." SCE&G will manage the storage of QA Records in electronic media consistent with the intent of RIS 2000-18 and associated NIRMA Guidelines TG 11-1998, TG15-1998, TG16-1998, and TG21 -1998.
17.3      NQA-1-1994 Commitment I Exceptions In establishing provisions for records, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 17 and Supplement 17S-1, with the following clarifications and exceptions:
* NQA-1-1994, Supplement 17S-1
                  - Supplement 17S-1, section 4.2(b) requires records to be firmly attached in binders or placed in folders or envelopes for storage in steel file cabinets or on shelving in containers.
For hard-copy records maintained by SCE&G, the records are suitably stored in steel file cabinets or on shelving in containers, except that methods other than binders, folders or envelopes may be used to organize the records for storage.
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V. C. Summer Nuclear Station Unit I Quality Assurance Program Description Revision 0 SECTION 18                  AUDITS SCE&G has established the necessary measures and governing procedures to implement audits to verify that activities covered by the OAPD are performed in conformance with the requirements established. The audit programs are themselves reviewed for effectiveness as a part of the overall audit process.
18.1      Performance of Audits Internal audits of selected aspects of licensing, design, and operating activities are performed with a frequency commensurate with safety significance and in a manner which assures that audits of safety-related activities are completed. Functional areas of an organization's QA program for auditing include, at a minimum, verification of compliance and effectiveness of implementation of internal rules, procedures (e .g.,
operating, design, procurement, maintenance, modification, refueling, surveillance, test, security, radiation control procedures, and the Emergency Plan), Technical Specifications, regulations and license conditions, programs for training, retraining, qualification and performance of operating staff, corrective actions, and observation of performance of operating, refueling, maintenance and modification activities, including associated record keeping.
The audits are scheduled on a formal preplanned audit schedule. The audit system is reviewed periodically and revised as necessary to assure coverage commensurate with current and planned activities. Additional audits may be performed as deemed necessary by management. The scope of the audit is determined by the quality status and safety Importance of the activities being performed. These audits are conducted by trained personnel not having direct responsibilities in the area being audited and in accordance with preplanned and approved audit plans or checklists, under the direction of a qualified lead auditor and the cognizance of the Manager, Quality Systems.
SCE&G is responsible for conducting periodic internal and external audits. Internal audits are conducted to determine the adequacy of programs and procedures (by representative sampling), and to determine if they are meaningful and comply with the overall QAPD. External audits determine the adequacy of supplier and contractor quality assurance program.
The results of each audit are reported in writing to the Senior Vice President, Nuclear Operations, or designee, as appropriate. Additional internal distribution is made to other concerned management levels in accordance with approved procedures.
Management responds to all audit findings and initiates corrective action where indicated. Where corrective action measures are indicated, documented follow-up of applicable areas through inspections, review, re-audits, or other appropriate means is conducted to verify implementation of assigned corrective action.
Audits of suppliers of safety-related components and/or services are conducted as described in Section 7.1.
18.2      Internal Audits Internal audits of activities should be performed in such a manner as to assure that an audit of all applicable QA program elements is completed for each functional area within a period of two years. Internal audit frequencies of well established activities, conducted after placing the facility in operation, may be extended one year at a time beyond the above two-year interval based on the results of an annual evaluation of the applicable functional area and objective evidence that the functional area activities are being satisfactorily accomplished. The evaluation should include a detailed performance analysis of the functional area based 39
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 upon applicable internal and external source data and due consideration of the impact of any function area changes in responsibility, resources or management. However, the internal audit frequency interval should not exceed a maximum of four years. Ifan adverse trend is identified in the applicable functional area, the extension of the internal audit frequency interval should be rescinded and an audit scheduled as soon as practicable.
Audits are performed at a frequency commensurate with the safety significance of the activities and in such a manner to assure audits of all applicable OA program elements are completed within a period of two years.
These audits will include, as a minimum, activities in the following areas:
(1) The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions including administrative controls.
(2) The performance, training, and qualifications of the facility staff.
(3) The performance of activities required by the QAPD to meet the criteria of 10 CFR 50, Appendix B.
(4) The Fire Protection Program and implementing procedures. A fire protection equipment and program implementation inspection and audit are conducted utilizing either a qualified off-site licensed fire protection engineer or an outside qualified fire protection consultant.
(5) Other activities and documents considered appropriate by the Vice President, Nuclear Operations.
Audits may also be used to meet the periodic review requirements of the code for the Security, Emergency Preparedness, and Radiological Protection programs within the provisions of the applicable code.
Internal audits include verification of compliance and effectiveness of the administrative controls established for implementing the requirements of this QAPD; regulations and license provisions; provisions for training, retraining, qualification, and performance of personnel performing activities covered by this QAPD; corrective actions taken following abnormal occurrences; and observation of the performance of fabrication, operating, refueling, maintenance, and modification activities including associated record keeping.
18.3      NQA-1-1994 Commitment In establishing the independent audit program, SCE&G commits to compliance with NQA-1-1994, Basic Requirement 18 and Supplement 18S-1.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 PART III                    NON-SAFETY-RELATED SSC QUALITY CONTROL SECTION 1        Non-safety-Related SSCs - Significant Contributors to Plant Safety Specific program controls are applied to non-safety related SSCs, for which 10 CFR 50, Appendix B is not applicable, that are significant contributors to plant safety. The specific program controls consistent with applicable sections of the QAPD are applied to those items in a selected manner, targeted at those characteristics or critical attributes that render the SSC a significant contributor to plant safety.
The following clarify the applicability of the QA Program to the non-safety related SSCs and related activities, including the identification of exceptions to the QA Program described in Part II,Sections 1 through 18 taken for non-safety related SSCs.
1.1      Organization The verification activities described in this Part may be performed by the SCE&G line organization.
The QA organization described in Part II is not required to perform these functions.
1.2      QA Program SCE&G QA requirements for non-safety related SSCs are established in the QAPD and appropriate procedures. Suppliers of these SSCs or related services describe the quality controls applied in appropriate procedures. A new or separate QA program is not required.
1.3      Design Control SCE&G has established design control measures to ensure that the established design requirements are included in the design. These measures ensure that applicable design inputs are included or correctly translated into the design documents, and deviations from those requirements are controlled. Design verification is provided through the normal supervisory review of the designer's work.
1.4      Procurement Document Control Procurement documents for items and services obtained by or for SCE&G shall include or reference documents describing applicable design bases, design requirements, and other requirements necessary to ensure component performance. The procurement documents are controlled to address deviations from the specified requirements.
1.5      Instructions, Procedures, and Drawings SCE&G provides documents such as, but not limited to, written instructions, plant procedures, drawings, vendor technical manuals, and special instructions in work orders, to direct the performance of activities affecting quality. The method of instruction employed provides an appropriate degree of guidance to the personnel performing the activity to achieve acceptable functional performance of the SSC.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.6  Document Control SCE&G controls the issuance and change of documents that specify quality requirements or prescribe activities affecting quality to ensure that correct documents are used. These controls include review and approval of documents, identification of the appropriate revision for use, and measures to preclude the use of superseded or obsolete documents.
1.7  Control of Purchased Items and Services SCE&G employs measures, such as inspection of items or documents upon receipt or acceptance testing, to ensure that all purchased items and services conform to appropriate procurement documents.
1.8  Identification and Control of Purchased Items SCE&G employs measures where necessary, to identify purchased items and preserve their functional performance capability. Storage controls take into account appropriate environmental, maintenance, or shelf life restrictions for the items.
1.9  Control of Special Processes SCE&G employs process and procedure controls for special processes, including welding, heat treating, and nondestructive testing. These controls are based on applicable codes, standards, specifications, criteria, or other special requirements for the special process.
1.10 Inspection SCE&G uses documented instructions to ensure necessary inspections are performed to verify conformance of an item or activity to specified requirements or to verify that activities are satisfactorily accomplished. These inspections may be performed by knowledgeable personnel in the line organization. Knowledgeable personnel are from the same discipline and have experience related to the work being inspected.
1.11 Test Control SCE&G employs measures to identify required testing that demonstrates that equipment conforms to design requirements. These tests are performed in accordance with test instructions or procedures. The test results are recorded, and authorized individuals evaluate the results to ensure that test requirements are met.
1.12  Control of Measuring and Test Equipment (M&TE)
SCE&G employs measures to control M&TE use, and calibration and adjustment at specific intervals or prior to use.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 1.13 Handling, Storage, and Shipping SCE&G employs measures to control the handling, storage, cleaning, packaging, shipping, and preservation of items to prevent damage or loss and to minimize deterioration. These measures include appropriate marking or labels, and identification of any special storage or handling requirements.
1.14 Inspection, Test, and Operating Status SCE&G employs measures to identify items that have satisfactorily passed required tests and inspections and to indicate the status of inspection, test, and operability as appropriate.
1.15 Control of Nonconforming Items SCE&G employs measures to identify and control items that do not conform to specified requirements to prevent their inadvertent installation or use.
1.16 Corrective Action SCE&G employs measures to ensure that failures, malfunctions, deficiencies, deviations, defective components, and non-conformances are properly identified, reported, and corrected.
1.17 Records SCE&G employs measures to ensure records are prepared and maintained to furnish evidence that the above requirements for design, procurement, document control, inspection, and test activities have been met.
1.18 Audits SCE&G employs measures for line management to periodically review and document the adequacy of the process, including taking any necessary corrective action. Audits independent of line management are not required. Line management is responsible for determining whether reviews conducted by line management or audits conducted by any organization independent of line management are appropriate. If performed, audits are conducted and documented to verify compliance with design and procurement documents, instructions, procedures, drawings, and inspection and test activities. Where the measures of this Part III are implemented by the same programs, processes, or procedures as the comparable activities of Part 1i,the audits performed under the provisions of Part II may be used to satisfy the review requirements of this Part III, Section 1.18.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 2        Non-safety-Related SSCs Credited for Regulatory Events The following criteria apply to fire protection (10 CFR 50.48), anticipated transients without scram (ATWS)
(10 CFR 50.62), the station blackout (SBO) (10 CFR 50.63) SSCs that are not safety-related.
    -    SCE&G implements quality requirements for the fire protection system in accordance with Section C to Appendix A of Branch Technical Position 9.5-1.
    -    SCE&G implements the quality requirements for ATWS equipment in accordance with Part Ill, Section 1.
    -    SCE&G implements quality requirements for SBO equipment in accordance with Regulatory Guide 1.155, "Station Blackout," and Part II, Section 1.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 PART IV          REGULATORY COMMITMENTS NRC Regulatory Guides and Quality Assurance Standards This section identifies the NRC Regulatory Guides (RGs) and the other quality assurance standards which have been selected to supplement and support the SCE&G QAPD. SCE&G complies with these standards to the extent described or referenced herein. Commitment to a particular RG or standard does not constitute a commitment to the RGs or standards that may be referenced therein.
Regulatory Guides:
See FSAR Chapter 3 for the SCE&G evaluation of conformance with the guidance in NRC Regulatory Guides.
Regulatory Guide 1.8, Rev. 2, "Personnel Selection and Training," April 1987 Regulatory Guide 1.8 provides guidance that is acceptable to the NRC staff regarding qualifications and training for nuclear power plant personnel.
SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Regulatory Guide 1.26, Rev. 3,"Quality Group Classification and Standards for Water, Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants,"
February 1976 Regulatory Guide 1.26 defines classification of systems and components.
SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Regulatory Guide 1.28, Rev 3, "Quality Assurance Program Requirements (Design and Construction), August 1985 Regulatory Guide 1.28 describes a method acceptable to the NRC staff for complying with the provisions of Appendix B with regard to establishing and implementing the requisite quality assurance program for the design and construction of nuclear power plants.
SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Regulatory Guide 1.29, Rev. 2 for Comment, "Seismic Design Classification," February 1976 Regulatory Guide 1.29 defines systems required to withstand a safe shutdown earthquake (SSE).
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Regulatory Guide 1.37, Rev. 1, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants," March 2007.
Regulatory Guide 1.37 provides guidance on specifying water quality and precautions related to the use of alkaline cleaning solutions and chelating agents.
SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Regulatory Guide 1.54, Rev. 0, "Quality Assurance Requirements for Protective Coatings Applied to Water Cooled Nuclear Power Plants," June 1973 Regulatory Guide 1.54 provide guidance for the application of protective coatings within nuclear power plants to protect surfaces from corrosion, contamination from radionuclides, and for wear protection.
SCE&G identifies conformance and exceptions for the applicable regulatory position guidance provided in this regulatory guide in FSAR Chapter 3, Appendix 3A.
Standards:
ASME NQA-1-1994 Edition, Quality Assurance Requirements for Nuclear Facility Applications SCE&G commits to NQA-1-1994, Parts I, II,and III, as described in Parts IIand Vof this document.
Nuclear Information and Records Management Association, Inc. (NIRMA) Technical Guides (TGs)
SCE&G commits to NIRMA TGs as described in Part II,Section 17.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 PART V            ADDITIONAL QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR THE PLANT OPERATIONAL PHASE SCE&G includes the requirements of Part V that follow when establishing the necessary measures and governing procedures for the operations phase of the plant.
Section 1        Definitions SCE&G uses the definitions of terms as provided in Section 4 of the Introduction of NQA-1-1994 in interpreting the requirements of NQA-1-1994 and the other standards to which the QAPD commits. In addition, definitions are provided for the following terms not covered in NQA-1-1994:
administrative controls: rules, orders, instructions, procedures, policies, practices and designations of authority and responsibility experiments: performance of plant operations carried out under controlled conditions in order to establish characteristics or values not previously known independent review: a review completed by personnel not having direct responsibility for the work function under review regardless of whether they operate as a part of an organizational unit or as individual staff members (see review) nuclear power plant: any plant using a nuclear reactor to produce electric power, process steam or space heating on-site operating organization: on-site personnel concerned with the operation, maintenance and certain technical services operating activities: work functions associated with normal operation and maintenance of the plant, and technical services routinely assigned to the on-site operating organization operational phase: that period of time during which the principal activity is associated with normal operation of the plant. This phase of plant life is considered to begin formally with commencement of initial fuel loading, and ends with plant decommissioning review: a deliberately critical examination, including observation of plant operation, evaluation of assessment results, procedures, certain contemplated actions, and after-the-fact investigations of abnormal conditions supervision: direction of personnel activities or monitoring of plant functions by an individual responsible and accountable for the activities they direct or monitor surveillance testing: periodic testing to verify that safety related structures, systems, and components continue to function or are in a state of readiness to perform their functions system: an integral part of nuclear power plant comprising components which may be operated or used as a separate entity to perform a specific function 47
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 Section 2          Review of Activities Affecting Safe Plant Operation 2.1      Onsite Operating Organization Review The SCE&G onsite organization employs reviews, both periodic and as situations demand, to evaluate plant operations and plan future activities. The important elements of the reviews are documented and subjects of potential concern for the independent review described below are brought to the attention of the General Manager, Nuclear Plant Operations. The reviews are part of the normal duties of plant supervisory personnel in order to provide timely and continuing monitoring of operating activities in order to assist the General Manager, Nuclear Plant Operations in keeping abreast of general plant conditions and to verify that day-to-day operations are conducted safely in accordance with the established administrative controls. The General Manager, Nuclear Plant Operations ensures the timely referral of the applicable matters discussed in the reviews to appropriate management and independent reviewers.
2.2      Independent Review Activities occurring during the operational phase shall be independently reviewed on a periodic basis. The independent review function performs the following:
: a. Reviews proposed changes to the facility as described in the safety analysis report (SAR). The Independent Safety Review Body (Plant Safety Review Committee (PSRC))/Independent Review Committee (Nuclear Safety Review Committee (NSRC)) also verifies that changes do not adversely affect safety and if a technical specification change or NRC review is required.
: b. Reviews proposed tests and experiments not described in the SAR prior to implementation. Verifies the determination of whether changes to proposed tests and experiments not described in the SAR require a technical specification change or license amendment.
: c. Reviews proposed technical specification changes and license amendments relating to nuclear safety prior to NRC submittal and implementation, except in those cases where the change is identical to a previously approved change.
: d. Reviews violations, deviations, and events that are required to be reported to the NRC. This review includes the results of investigations and recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
: e. Reviews any matter related to nuclear safety that is requested by the Vice President, Nuclear Operations, Plant Manager, or any PSRC/NSRC member.
: f. Reviews corrective actions for significant conditions adverse to quality.
: g. Reviews internal audit reports.
: h. Reviews the adequacy of the internal audit program every 24 months.
Plant Safety Review Committee The PSRC functions as an independent review body. In discharging its review responsibilities, the PSRC keeps Safety considerations paramount when opposed to cost or schedule considerations. One or more organizational units may collectively perform this function.
: 1. PSRC reviews are supplemented as follows:
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0
: a. A qualified person, independent of the preparer, reviews proposed changes in the procedures as described in the SAR prior to implementation of the change to determine ifa technical specification change or NRC approval is required.
: b. Audits of selected changes in the procedures described in the SAR are performed to verify that procedure reviews and revision controls are effectively implemented.
: c. Competent individual(s) or group(s) other than those who performed the original design but who may be from the same organization verify that changes to the facility do not result in a loss of adequate design or safety margins.
: 2. The results of supplemented reviews of matters involving the safe operation of the facility are periodically independently reviewed by the PSRC. This review is intended to support management in identifying and resolving issues potentially affecting safe plant operation. This review supplements the existing corrective action programs and audits.
: a. The review is performed by a team consisting of personnel with experience and competence in the activities being reviewed, but independent from cost and schedule considerations and from the organizations responsible for those activities. The PSRC supervisor or chairman has a minimum six (6) years combined managerial and technical support experience. The members of the PSRC should have a minimum of five (5)years of experience in their own area of responsibility as applicable to the activities being reviewed (i.e., a minimum of five years of experience in one of the twelve areas listed below:
(1) Nuclear power plant operations (2) Nuclear engineering (3) Chemistry and radiochemistry (4) Metallurgy (5) Nondestructive testing (6) Instrumentation and control (7) Radiological safety (8) Mechanical engineering (9) Electrical engineering (10)Administrative control and quality assurance practices (11)Training (12) Emergency plans and related procedures and equipment).
: b. The review is supplemented by outside consultants or organizations as necessary to ensure the team has the requisite expertise and competence.
: c. Results of the review are documented and reported to responsible management, PSRC Chairman, and NSRC.
: d. PSRC periodically consider issues they determine warrant special attention, such as deficient plant programs, declining performance trends, employee concerns, or other issues related to safe plant operations and determine what issues warrant the review.
: e. PSRC determines the scheduling and scope of review and the composition of the team performing the review.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 Nuclear Safety Review Committee
: 1. The NSRC is assigned independent review responsibilities.
: 2. The NSRC reports to Vice President Nuclear Operations.
: 3. The NSRC is composed of no less than 5 persons and no more than a minority of members are from the on-site operating organization.
For example, at least 3 of the 5 members must be from off-site ifthere are 5 members on the committee. A minimum of the chairman or alternative chairman and 2 members must be present for all meetings.
: 4. During the period of initial operation, meetings are conducted no less frequently than once per calendar quarter. Afterwards meetings are conducted no less than twice a year.
S. Results of the meeting are documented and recorded.
: 6. Consultants and contractors are used for the review of complex problems beyond the expertise of the off site/on site independent review committee.
: 7. Persons on the NSRC are qualified as follows:
: a. Supervisor or Chairman of the NSRC
          -  Education: baccalaureate in engineering or related science
          -  Minimum experience: 6 years combined managerial and technical support
: b. NSRC members Education: Baccalaureate in engineering or related science for those Independent review personnel who are required to review problems in
        -    nuclear power plant operations,
        -    nuclear engineering
        -    chemistry and radiochemistry,
        -    metallurgy,
        -    nondestructive testing,
        -    instrumentation and control,
        -    radiological safety,
        -    mechanical engineering, and electrical engineering.
High school diploma for those independent review personnel who are required to review problems in administrative control and quality assurance practices, training, and emergency plans and related procedures and equipment.
Minimum experience: 5 years experience in their own area of responsibility (nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, nondestructive testing, instrumentation and control, radiological safety, mechanical engineering, and electrical engineering, administrative control and quality assurance practices, training, and emergency plans and related procedures and equipment).
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V. C. Summer Nuclear Station Unit I Quality Assurance Program Description Revision 0 2.3  TECHNICAL REVIEW AND CONTROL 2.3.1  ACTIVITIES Activities which affect nuclear safety shall be conducted as follows:
: a. Procedures required by Technical Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed, and approved. Each such procedure or procedure change shall be reviewed by an individual/group other than the individual/group which prepared the procedure or procedure change, but who may be from the same organization as the individual/group who prepared the procedure or procedure change. Procedures other than administrative procedures will be approved as delineated in writing by the General Manager, Nuclear Plant Operations. The General Manager, Nuclear Plant Operations will approve administrative procedures, security implementing procedures, and emergency plan implementing procedures.
Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedures shall approve the change.
: b. Proposed changes or modifications to plant nuclear safety-related structures, systems, and components shall be reviewed as designated by the General Manager, Nuclear Plant Operations.
Each such modification shall be designed as authorized by Engineering Services and shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.
Implementation of modifications to plant nuclear safety-related structures, systems, and components shall require concurrence by the General Manager, Nuclear Plant Operations.
: c. Proposed tests and experiments which affect nuclear plant safety and are not addressed in the Final Safety Analysis Report shall be reviewed by an individual/group other than the individual/group which proposed the test or experiment.
: d.      Events reportable pursuant to the Technical Specification 6.9 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the event and which provides recommendations to prevent recurrence. Such report shall be approved by the General Manager, Nuclear Plant Operations and forwarded to the Chairman of the NSRC.
: e.      Individuals responsible for reviews performed in accordance with 2.3.1 a through d above shall be members of the plant staff that meet or exceed the qualification requirements of Section 4 of ANSI 18.1, 1971, as previously designated by the General Manager, Nuclear Plant Operations. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.
: f.      Each review will include a determination of whether or not prior NRC approval is required.
: g. Procedures listed in Part V, Section 3.2 and Technical Specifications 6.8.1, and changes thereto, shall be reviewed prior to implementation as set forth in Part V, Sections 2.2 and 2.3 above.
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V. C. Summer Nuclear Station Unit I Quality Assurance Program Description Revision 0 2.3.2  RECORDS Records of the above activities shall be provided to the General Manager, Nuclear Plant Operations, PSRC and/or NSRC as necessary for required reviews.
2.4  RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
2.4.1  RETENTION FOR FIVE YEARS The following records shall be retained for at least five years:
: a. Records and logs of unit operation covering time interval at each power level.
: b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
: c. All Reportable Events submitted to the Commission.
: d. Records of surveillance activities, inspections, and calibrations required by the Technical Specifications and Part V of the QAPD.
: e. Records of changes made to the procedures required by TS 6.8.1 as listed in 2.1.6.b above.
: f. Records of radioactive shipments.
: g. Records of sealed source and fission detector leak tests and results.
: h. Records of annual physical inventory of all sealed source material of record.
2.4.2  RETENTION FOR THE DURATION OF THE UNIT OPERATING LICENSE The following records shall be retained for the duration of the unit operating license:
: a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the UFSAR.
: b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
: c. Records of radiation exposure for all individuals entering radiation control areas.
: d. Records of gaseous and liquid radioactive material released to the environment.
: e. Records of transient or operational cycles for those unit components identified in TS Table 5.7-1.
: f. Records of reactor tests and experiments.
: g. Records of training and qualification for current member of the unit staff.
: h. Records of in-service inspections performed pursuant to the Technical Specifications and this Part V of the CAPD.
: i. Records of Quality Assurance activities as specified in the NRC's approved SCE&G position on Regulatory Guide 1.28, Revision 3, August 1985.
: j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
: k. Records of meetings of the PSRC and the NSRC.
I. Records of the service lives of all hydraulic and mechanical snubbers defined in TS 3.7.7 including the date at which the service life commences and associated installation and maintenance records.
: m. Records of secondary water sampling and water quality.
: n. Records of analysis required by the radiological environmental monitoring program.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0
: o. Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.
I Section 3        Operational Procedures The following is a description of the various types of procedures used by SCE&G to govern the design, operation, and maintenance of its nuclear generating plants. SCE&G follows the guidance of Appendix A to Regulatory Guide 1.33 in identifying the types of activities that should have procedures or instructions to control the activity. Each procedure shall be sufficiently detailed for a qualified individual to perform the required function without direct supervision, but need not provide a complete description of the system or plant process.
3.1      Format and Content The SCE&G procedure format and content include the following elements as appropriate to the purpose or task to be described:
        " Title/Status Each procedure is given a title descriptive of the work or subject it addresses, and includes a revision number and/or date and an approval status.
* Purpose/Statement of Applicability/Scope The purpose for which the procedure is intended is clearly stated (if not clear from the title). The systems, structures, components, processes or conditions to which the procedure applies are also clearly described.
        " References Applicable references, including reference to appropriate Technical Specifications, are required.
References are included within the body of the procedure when the sequence of steps requires other tasks to be performed (according to the reference) prior to or concurrent with a particular step.
* Prerequisites/Initial Conditions Prerequisites/initial conditions identify those independent actions or procedures that must be accomplished and plant conditions which must exist prior to performing the procedure. A prerequisite applicable to only a specific portion of a procedure is so identified.
        " Precautions Precautions alert the user to those important measures to be used to protect equipment and personnel, including the public, or to avoid an abnormal or emergency situation during performance of the procedure. Cautionary notes applicable to specific steps are included in the main body of the procedure and are identified as such.
        " Limitations and actions Limitations on the parameters being controlled and appropriate corrective measures to return the parameter to the normal control band are specified.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0
        " Main body The main body of the procedure contains the step-by-step instructions in the degree of detail necessary for performing the required function or task.
* Acceptance criteria The acceptance criteria provide the quantitative or qualitative criteria against which the success or failure (as of a test-type activity) of the step or action would be judged.
* Checklists Complex procedures utilize checklists which may be included as part of the procedure or appended to it.
3.2      Procedure Types Administrative Control Procedures The administrative control procedures and directives provide a clear understanding of operating philosophy and management policies to ensure safe operation of the plant within the limits set by the operating license and Technical Specifications. They provide that plant activities are conducted in a manner that will protect the general public, plant personnel, and equipment. A description of these procedure categories is as follows:
* Plant Organization and Responsibility Procedures These procedures describe the plant organization and give the responsibility of the individuals by position and authority to operate the plant in a safe and efficient manner.
* Development, Review, Approval, and Control of Safety-Related Plant Procedures These procedures describe the method by which plant procedures are written, the control process for review and approval, and the system utilized to revise the procedures where needed. Administrative procedures, security plan implementing procedures, and emergency plan implementing procedures receive final approval by the General Manager, Nuclear Plant Operations or his/her designated alternate.
They are reviewed under the direction of a supervisor from a group other than the originating group before final approval.
" Conduct of Plant Operations Procedures These procedures describe the rules and instructions issued by the General Manager, Nuclear Plant Operations pertaining to personnel conduct and control. These rules and instructions provide a clear understanding of operating philosophy and management policies. They delineate the authority and responsibility of the Reactor Operators and Senior Reactor Operators for the safe operation of the reactor. They establish the rules for procedure use and the designation of the persons responsible to authorize a temporary change to an approved procedure. Additional procedures establish standard operating orders which deal with such matters as job turnover and relief, designation of the confines of the Control Room including a diagram of the Control Room that indicates the area designated as at the controls, transmittal of operating data, limitations on access to equipment, and other such matters.
Provisions are made for periodic review and updating of standing orders. Instructions which have short 54
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 time applicability such as housekeeping, publications and their distribution, and personnel actions are issued as special orders.
These procedures define the procedural steps for relief of shift personnel. Checklists are provided for the oncoming and off-going Control Room Supervisor and the oncoming Shift Supervisor to complete and sign. These checklists provide assurance that actual plant parameters are within allowable limits and that required systems are available and are in proper alignment for the prevention and mitigation of operational transients. Systems and components that are in a degraded mode of operation permitted by Technical Specifications shall be listed and time in degraded mode is compared with Technical Specification action statements. Auxiliary Operator checklists include any equipment under maintenance or test that could degrade a system or initiate an operational transient and shall include criteria for acceptable status. The Operations Supervisor will make unannounced audits of shift relief to evaluate the effectiveness of shift relief and turnover.
Also these procedures establish the authority and responsibility of the person in charge of the Control Room to limit access.
Conduct of Plant Operations administrative procedures establish actual work time limitations for plant shift personnel who maintain or operate any structures, systems, or components important to safety.
Shift Supervisor's Responsibility Upper level management shall issue a directive that establishes the management responsibility for the Shift Supervisor under all plant conditions. It shall contain clear delineation of management chain of authority as to who can, and when the Shift Supervisor is relieved of the responsibility for direct control of the plant.
An administrative procedure is provided that gives the authority and responsibilities of the Shift Supervisor, Control Room Supervisor, Control Room Operator, and other shift personnel.
Both on the job training and classes emphasize responsibility for safe operation and management functions as given in the administrative procedure.
A review of administrative duties of the Shift Supervisor has been conducted by senior plant and corporate management. Additional administrative personnel have been added to the operating group that relieves the Shift Supervisor of routine duties that distract from the management responsibility for assuring the safe operation of the plant.
* Control of Plant Documents Procedures These procedures describe the preparation and retention of plant records. Retention periods are established to assure the ability to reconstruct significant events and satisfy statutory requirements.
Corrective Action Reporting Procedures These procedures assure that conditions adverse to plant safety such as equipment and material malfunction, abnormal occurrences, and nonconformances are promptly identified and corrected.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 They ensure that the cause of the conditions is determined and reported to the appropriate level of management for corrective action.
* Equipment Control Procedures These procedures describe the control measures and actions such as locking, tagging, notification, removal of tags, and identification of equipment. They provide for control of equipment to maintain reactor and personnel safety and to avoid unauthorized operation of equipment. They provide instructions for verifying correct performance of operating activities.
"  Design Modification Control Procedures These procedures ensure that plant modifications satisfy, at a minimum, the same design requirements as the original equipment.
Procurement and Materials Control Procedures These procedures provide for the control of purchased material, equipment, and services. They provide for proper identification, quality level requirements, control, handling, storage, and shipping of materials, parts, and components. These procedures also provide for the proper documentation to ensure quality of safety-related systems, equipment, and structures after maintenance or repair.
"  Control and Calibration of Test Equipment and Instrumentation Procedures These procedures ensure that testing and measuring devices are of the proper range and type and are controlled, calibrated, adjusted, and maintained at specified intervals or prior to use to assure the necessary accuracy of calibrated devices. Records are made and equipment suitably marked to indicate calibration status.
"  Control of Special Processes During Operations Procedures These procedures assure that special processes are accomplished under controlled conditions in accordance with applicable codes, standards, specifications, criteria, and other special requirements using qualified personnel and procedures.
* Non-Conformance Control/Deficiency Reporting Procedures These procedures provide for control of items, services, or activities which do not conform to requirements. These procedures include instructions for identification, documentation, segregation, notification of affected organizations, and method of disposition of such items, services, or activities.
"  Test Control Procedures These procedures assure that testing required to demonstrate that an item will perform satisfactorily in service is accomplished properly. Test procedures incorporate or reference the requirements and acceptance limits contained in applicable design documents. These test procedures may include preoperational tests, initial operational phase tests, surveillance tests, and tests during design, 56
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 fabrication, and construction activities associated with plant maintenance and modification.
* Feedback of Operating Experience These procedures establish a program for evaluating operating plant experience and providing the results of the evaluations, as necessary, to pertinent plant personnel. The services of "Industry Groups" such as INPO will be utilized to the extent possible in the performance of this function.
Control Room Operating Procedures Control Room operating procedures are those procedures that are performed by the licensed Control Room Operator or under his/her direction and control. They are a preplanned method for the conduct of operations to minimize reliance on memory. These procedures include anticipated operating conditions, the normal method of control, means for and limits on operation of the plant, or plant systems that affect the safety of the plant and the public.
"  General Operating Procedures General Operating Procedures (GOP) provide for the integrated operation of the plant. These procedures provide the sequence of plant operations to take the plant from a given initial condition to a final expected condition. Associated system operating procedures are referenced as applicable.
Necessary precautions are inserted at critical points.
" Emergency Operating Procedures Emergency Operating Procedures (EOP) are written so that a trained operator and crew will be able to identify an emergency from the symptoms available to them and take immediate action on the expected course of events to place the plant in a known safe condition and to mitigate the consequence of a serious condition should it occur. Since emergencies may not follow anticipated patterns these procedures provide sufficient flexibility to accommodate variations. Those sections of the procedure that require immediate response action from the operating crew are committed to memory. Considerable judgment on the part of competent personnel is exercised before departure from these procedures.
* System Operating Procedures System Operating Procedures (SOP) provide instructions for energizing, starting up, shutting down, changing modes of operation, and other instructions for operations of systems related to the safety of the plant.
These procedures are concerned with systems only and include valve and switch lineups, control operations, and instrumentation within the system boundaries. They are subdivided into normal operations, infrequent operations, and off normal conditions in the main body.
" Annunciator Response Procedures Annunciator Response Procedures (ARPs) are written to instruct the operator on the proper action to be taken in response to annunciators on the Main Control Board. They contain annunciator identification, inputs into the annunciator, and logical operator responses to be taken to ensure proper corrective 57
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 action. The ARPs are identified by panel number. An illustration in the beginning of the ARP depicts the annunciator panel. In the case of computer alarms each alarm's unique identifier is listed.
When use of the ARP is required, the operator selects the proper tab by an alarm panel number.
"    Fuel Handling Procedures Fuel Handling Procedures (FHP) are written to specify actions and philosophy for core alterations and partial or complete refueling operations. They include requirements for continuous monitoring of neutron flux throughout core loading and audible annunciation of abnormal flux increases. The duties of personnel assigned to refueling, such as periodic data taking, response actions to alarms during refueling, and criteria for stopping the refueling are specified. Also, instructions for proper sequence of events, verification, and frequency of sampling to ensure shutdown margin, communications between the control room and the fuel loading station, documentation of final fuel component serial numbers and location, containment integrity requirements, and rules for periods when refueling is interrupted are included. System operating procedures are referenced as required.
"    Special Procedures Special procedures are written and issued to direct operations during testing, refueling, maintenance, and modifications. These *procedures provide guidance in unusual situations not covered by existing procedures. They ensure orderly and uniform operations for short periods when the plant, a system, or a component is not performing in a normal manner and an existing procedure does not apply. Special procedures designate the period of time during which they may be used and are subject to the same review and approval process as other operating procedures.
Maintenance and Modification Procedures Maintenance and modification procedures define the policies and practices by which structures, systems, and components are kept in a condition of good repair so that they are capable of reliably performing their intended functions. This includes those activities performed by maintenance or contractor personnel to maintain, repair, or modify safety-related equipment. Additional related activities covered are those by operating personnel to ensure that a planned maintenance activity can be safely accomplished, that proper plant operating conditions exist, to authorize the release of equipment to be maintained using equipment control procedures, and to assure that the equipment has been returned to normal operating status at the completion of maintenance work, as well as verification of functional acceptability. Procedures are written to assure measurement accuracies are adequate to keep safety parameters and controls within safety and operational limits. This instrumentation includes interlocks, alarm devices, sensors, readout instruments, transmitters, signal conditioners, laboratory equipment, key recorders, and protective logic circuits.
Calibration, testing, and checking of instrumentation channels are performed at the frequency specified in Technical Specifications.
Emergency Plan Procedures These procedures are written in sufficient detail that a qualified individual can perform the required actions without supervision. They provide a step by step order and logical sequence in a concise manner but are flexible enough to give latitude to the user for the exercise of judgment in implementing specific actions or 58
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 parts of the procedure. These instructions specify the individual or organization having authority and responsibility for performing critical tasks. The actions to be performed by support agencies and the coordination with other elements of the emergency organization are also specified. Guidelines for initiating recovery after the emergency is over to restore the plant to the pre-emergency conditions are given.
Chemical Radiochemical Control Procedures These procedures provide instructions for maintaining reactor coolant, condensate, and feedwater within prescribed quality limits and include the nature and frequency of sampling and analysis. They also include laboratory instructions and instructions for calibration of laboratory equipment. Limitations on concentrations of agents that could cause corrosive attack, foul heat transfer surfaces, or become sources of radiation hazards due to activation are given.
Plant Radiation Protection Procedures These procedures cover plant personnel, other personnel temporarily assigned, contractor and vendor personnel, and visitor protection to maintain occupational dose rate to as low as reasonably achievable. They provide coverage for all normal operations and anticipated operational occurrences. This includes refueling, purging, fuel handling and storage, also radioactive material handling, processing, use, and storage. Other areas covered are maintenance, routine operational surveillance, inservice inspection, and calibration.
Plant Security Procedures These procedures are written to supplement physical barriers and features designed to control access to the plant and as appropriate to sensitive areas and equipment within the plant. Information concerning design features and administrative provisions is protected and distribution is limited.
Surveillance Test Procedures These tests and inspections are performed in accordance with the Technical Specifications to ensure that the required reliability of safety systems is maintained. These surveillance test procedures contain a description of the test objectives, the acceptance criteria used to evaluate the test results, and the prerequisites for performing the test. They include any special conditions to be used to simulate normal or abnormal operating conditions, limiting conditions, the test procedure, and any special test equipment or calibrations required to conduct the test. A master surveillance schedule, reflecting the status of surveillance testing is also maintained. Additional control procedures ensure timely conduct of surveillance testing, appropriate documentation, reporting, and evaluation of test results. Significant deficiencies identified by the tests are reported to management. The deficiencies will be evaluated and the condition corrected in a timelv manner.
Test and Inspection Procedures These documents provide the necessary measures to assure quality is achieved and maintained for the nuclear facilities. The instructions for tests and inspections may be included within other procedures, such as installation and maintenance procedures, but will contain the objectives, acceptance criteria, prerequisites for performing the test or inspection, limiting conditions, and appropriate instructions for performing the test or inspection, as applicable. These procedures also specify any special equipment or calibrations required to conduct the test or inspection and provide for as appropriate documentation and evaluation by responsible 59
 
V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 authority to assure test or inspection requirements have been satisfied. Where necessary, hold or witness points are identified within the procedures and require appropriate approval for the work to continue beyond the designated point. These procedures provide for recording the date, identification of those performing the test or inspection, as-found condition, corrective actions performed (if any), and as-left condition, as appropriate, for the subject test or inspection.
Fire Protection Procedures These associated procedures provide the necessary planning and instructions to ensure adequate fire protection. Included, but not limited to, are the provisions made in the Fire Protection Evaluation Report (FPER). The responsibilities for preparation of schedules and procedures required by the Operations, Maintenance, and Technical Groups are stated in this report and are detailed in administrative procedures.
Section 4        Control of Systems and Equipment During Plant Operation Permission to release systems and equipment for maintenance or modification is controlled by designated operating personnel and documented. Measures, such as installation of tags or locks and releasing stored energy, are used to ensure personnel and equipment safety. When entry into a closed system is required, SCE&G has established control measures to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed.
Administrative procedures require the designated operating personnel to verify that the system or equipment can be released and determine the length of time it may be out of service. In making this determination, attention is given to the potentially degraded degree of protection where one subsystem of a redundant safety system is not available for service. Conditions to be considered in preparing equipment for maintenance include, for example: shutdown margin; method of emergency core cooling; establishment of a path for decay heat removal; temperature and pressure of the system; valves between work and hazardous material; venting, draining and flushing; entry into closed vessels; hazardous atmospheres; handling hazardous materials; and electrical hazards.
When systems or equipment are ready to be returned to service, designated operating personnel control placing the items in service and document its functional acceptability. Attention is given to restoration of normal conditions, such as removal of jumpers or signals used in maintenance or testing, or actions such as returning valves, breakers or switches to proper start-up or operating positions from "test" or "manual" positions. Where necessary, the equipment placed into service receives additional surveillance during the run-in period.
Independent verifications, where appropriate, are used to ensure that the necessary measures have been implemented correctly. The minimum requirements and standards for using independent verification are established in company documents.
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V. C. Summer Nuclear Station Unit 1 Quality Assurance Program Description Revision 0 SECTION 5          Plant Maintenance SCE&G establishes controls for the maintenance or modification of items and equipment subject to this QAPD to ensure quality at least equivalent to that specified in original design bases and requirements, such that safety-related structures, systems and components are maintained in a manner that assures their ability to perform their intended safety function(s). Maintenance activities (both corrective and preventive) are scheduled and planned so as not to unnecessarily compromise the safety of the plant.
In establishing controls for plant maintenance, SCE&G commits to compliance with NQA-1-1994, Subpart 2.18, with the following clarifications:
          " Where Subpart 2.18 refers to the requirements of ANS-3.2, it shall be interpreted to mean the applicable standards and requirements established within the QAPD
          " Section 2.3 requires cleanliness during maintenance to be in accordance with Subpart 2.1. The commitment to Subpart 2.1 is described in the QAPD, Part II, Section 13.2.
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Document Control Desk Attachment V CR-10-03108 RC-1 1-0006 Page 1 of 392 A'TACHMENT V CONSOLIDATED MATRIX
 
CRITERION 1                                              BASIC REQUIREMENT 1Iouvrr ANSI N45.2-19711N18.7-1 976                                                NQA-1 1994 N45.2 &sect; 2 &#xb6; 2 - The program shall define the organizational      The organizational structure, functional responsibilities, levels Similar requirement, but structure within which the quality assurance program is to be    of authority, and lines of communication for activities affecting NQA- 1 addresses this in the planned and implemented and shall clearly delineate the          quality shall be documented.                                      Introduction to Part I, &sect; 2 responsibility and authority of the various personnel and                                                                          Applicability.
organizations involved.
N45.2 &sect; 3 &#xb6; 1 - The organizational structure, functional                                                                            Overall Note: Aspects from responsibilities, levels of authority, and lines of internal and                                                                    N45.2 and N18.7 dealing external communication for management, direction and                                                                                with qualification and execution of the quality assurance program shall be                                                                                training are addressed with documented.                                                                                                                        Criterion 2, and Reg. Guide N45.2 &sect; 1.2 &#xb6; 2 - This standard applies to the plant owner,                                                                        1.8 regarding selection, major contractors, such as the nuclear steam supply system                                                                          training and qualification of designer or supplier, the architect engineer or plant designer,                                                                    personnel.
and the plant constructor, and other organizations participating in activities affecting quality.
N18.7&sect; 3.2 &#xb6; 1 Assignment of Authority and Responsibility. It is essential that all members of the organization involved in operation of nuclear power plants, including those at the highest management levels, recognize the necessity that the plants be operated under a well formulated and detailed administrative controls and quality assurance program to assure safety and efficiency. Lines of authority, responsibility and communication shall be established from the highest management level through intermediate levels to and including the onsite operating organization (including those offsite organizational units assigned responsibility for procurement, design and construction, quality assurance, and technical support activities). These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships and job descriptions for key personnel positions or in equivalent forms of documentation.
N18.7&sect; 3.2 &#xb6; 2 The owner organization shall specify in writing the authority and responsibility assigned individuals and organizations involved in establishing, executing and measuring the overall effectiveness of the administrative controls and quality assurance program required by this Standard.
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CRITERION 1I                                    .        BASIC REQUIREMENT. 1.                                COMMENTS ANSI N45.2-1971/N18.7-. 976                                                NQA-1 1994 N 45.2 &sect;3 &#xb6; 2 - The authority and responsibility of persons and  Persons or organizations responsible for assuring that an          Similar requirement.
organization performing activities affecting quality shall be    appropriate quality assurance program has been established and clearly established. Persons and organizations performing        verifying that activities affecting quality have been correctly quality assurance functions shall have sufficient authority and  performed shall have sufficient authority, access to work areas, organizational freedom to:                                        and organizational freedom to:
(1) identify quality problems;                                    (a) identify quality problems; (2) initiate, recommend, or provide solutions through            (b) initiate, recommend, or provide solutions to quality designated channels;                                              problems through designated channels; (3) verify implementation of solutions; and                      (c) verify implementation of solutions; and (4) control further processing, delivery, or installation of a    (d) assure that further processing, delivery, installation, or use nonconforming item, deficiency, or unsatisfactory condition      is controlled until proper disposition of a nonconformance, until proper dispositioning has occurred.                        deficiency, or unsatisfactory condition has occurred.
N18.7 &sect; 3.2 &#xb6; 4 Persons or organizations performing functions of assuring that the administrative controls and quality assurance program is established and implemented or of assuring that an activity has been correctly performed shall have sufficient authority and organizational freedom to: identify quality problems; initiate, recommend or provide solutions, through designated channels; and verify implementation of solutions.
N45.2 &sect; 3 &#xb6; 3 The person or organization responsible for          Such persons or organizations shall have direct access to          Similar requirement.
defining and measuring the overall effectiveness of the quality  responsible management at a level where appropriate action can assurance program shall be designated, shall be sufficiently      be effected. Such persons or organizations shall report to a independent from the pressures of production, shall have direct  management level such that required authority and access to responsible management at a level where appropriate    organizational freedom are provided, including sufficient action can be required, and shall report regularly on the        independence from cost and schedule considerations.
effectiveness of the program.
N18.7 &sect; 3.2 &#xb6; 3 The persons or organizations responsible for defining and measuring the overall effectiveness of the program shall be designated, shall be sufficiently independent from cost and scheduling considerations when opposed to safety considerations, shall have direct access to responsible management at a level where appropriate action can be accomplished, and shall report regularly on the effectiveness of the program to the plant manager and the cognizant offsite management.
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CRITERION. 1                                              BASI.C REQ        IRE    I                            COMMENTS ANSI N45.2-1971/N.18.7-1976.BAS.C                                                  1994 R QNROT*-          1      .      ,  ..        .'  r SUPPLEMENT iS-i Supplementary Requirements for Organization 1 GENERAL This Supplement provides amplified requirements for organization.
It supplements the requirements of Basic Requirement I of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
2 RESPONSIBILITY 2.1 Purpose N45.2 &sect; 3 &#xb6; 4 The organizational structure and the functional    The organizational structure and the responsibility assignments  Similar requirement.
responsibility assignments shall be such that                    shall be such that:
N18.7 &sect; 3.2 &#xb6; 5 The organizational structure and the functional responsibility assignment shall be such that:
N45.2 &sect; 3 &#xb6; 4 (1) attainment of quality objectives is            (a) quality is achieved and maintained by those who have been    Similar requirement.
accomplished by those who have been assigned responsibility      assigned responsibility for performing work; and for performing work; e.g. the designer, the welder, or the power plant operator. This may included interim examinations, checks, and inspections of the work by the individual performing the work.
N18.7 &sect; 3.2 &#xb6; 5 (1) Attainment of program objectives is accomplished by those who have been assigned responsibility for performing work. This may include interim examinations, checks, and inspections of the work by the individual performing the work.
N45.2 &sect; 3 &#xb6; 4 (2) verification of conformance to established    (b) quality achievement is verified by persons or organizations  Similar requirement.
quality requirements is accomplished by those who do not have    not directly responsible for performing the work.
direct responsibility for performing the work; e.g., the design                                                                  Nl 8.7 includes a statement reviewer, the checker, the inspector, or the tester                                                                              that the verification also N18.7 &sect; 3.2 &#xb6; 5 (2) Verification of conformance to established                                                                    cannot be done by the program requirements is accomplished by a qualified person                                                                        person directly supervising who does not have responsibility for performing or directly                                                                      the work. NQA- 1 addresses supervising the work. The method and extent of such                                                                              the independence in the verification shall be commensurate with the importance of the                                                                    respective sections of activity to plant safety and reliability,                                                                                        design control (Criterion PIf), inspection (Criterion 10/28/2010                                                                Organization                                                              Page 3 of 7
 
CRITERION 1                                                            BASIC REQUIREMENT 1                                COMMENTS ANSI N45.2-1971/N18.7-1976          ...                                                  NQA-1 1.994..
X), and testing (Criterion XI).
There is no specific requirement or definition for "the checker" as stated in N45.2. This checking could be accomplished by any of the other three functions.
___________________________________________2.2 Delegation of Work_____________
N45.2 &sect; 1.3 &#xb6; 1 - The plant owner may delegate to other                The individual(s) or organization(s) responsible for establishing    Similar requirement for organizations the work of establishing and executing the quality and executing a quality assurance program under this Standard              N45.2 and NQA-l.
assurance program, or any part thereof, but shall retain                may delegate any or all of the work to others but shall retain responsibility for overall program effectiveness. In no  way  shall responsibility therefore.                                            N 18-7 goes into details that the program operate to diminish the responsibility of any                                                                                    are covered in the NQA-l contractor for the quality of items or services furnished or for                                                                            integrated QAPD through
                                ;"?:' *"
10/28/2010:of the contractor's designated execution
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                                                                *"*'***
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                                                                                          ****"'                          !**  .. i;**. "* other**......:**
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1,7 assurance program.                                                                                                                          Organization, such as ANS N18.7 &sect; 3.4.2 The Plant Manager shall have overall                                                                                      description of the Unit 1 responsibility for the execution of the administrative controls                                                                              Plant Management and quality assurance program at the plant to assure safety. An                                                                              organization and Quality individual or organizational unit knowledgeable and                                                                                          Assurance organization.
experienced in nuclear power plant operational phase activities                                                                              However, overall the QAPD and quality assurance practices shall be designated and assigned                                                                            and NQA-lI -1994 meet the the responsibility to verify that the program is being effectively                                                                          intent of these sections for implemented. Depending on the organizational structure, the                                                                                  both N45.2 and N 18.7.
individual or organizational unit may report functionally to onsite plant management or an offsite organization (see also 3.2). Reporting to onsite plant management is preferable since such an arrangement actually results in improved communications in identifying problems and initiating corrective action. The individual or organizational unit in this case may receive technical guidance from offsite support groups. This individual's or organizational unit's duties and responsibilities shall be such that the required attention can be devoted, as required, to verifying that the program is being            _______________________________________
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S.CRITERION 1=. I.                                          BASIC REQUIREMENT 1                      ..            COM.
ANSI N45.2-1971/Nl8.7-1976
                                    ...                                                        .                          .1994 effectively executed. The individual or organizational unit shall report on the effectiveness of the program to the Plant Manager and to other cognizant management as may be designated. Their activities shall be periodically audited by designated offsite personnel.
2.3 Nonconforming Items Responsibility for the control of further processing, delivery,    Addressed in implementing installation, or operation of nonconforming items shall be          procedures.
designated in writing.
3 MULTIPLE ORGANIZATIONS 3.1 Responsibility N45.2 &sect; 3 &#xb6; 1 - Where multiple organizational arrangements        Where more than one organization is involved in the execution      Similar requirement.
exist, the responsibility of each organization shall be clearly    of activities covered by this Part (Part I), the responsibility and established,                                                      authority of each organization shall be clearly established and    Additional explanatory N45.2 &sect; 3 &#xb6; 5 In structuring the organization and assigning        documented.                                                        information from N45.2 and responsibility, quality assurance should be recognized as an                                                                          N18.7 is more a factor of interdisciplinary function involving many organizational                                                                              the founding principles and components and, therefore, should not be regarded as the sole                                                                          policy of quality assurance.
domain of a single quality assurance group. For example, it may                                                                        Much of this is addressed in be more appropriate for design engineers to perform design                                                                            the Policy section of the reviews rather than quality assurance engineers because of the                                                                        QAPD. Additional special competence required to perform these reviews. Quality                                                                          information is contained in assurance encompasses many functions and activities and                                                                                the various sections of the extends to various levels in all participating organizations, from                                                                    QAPD related to the the top executive to all workers whose activities may influence                                                                        specific functions such as quality,                                                                                                                              inspections, testing, N18.7 &sect; 3.2 In structuring the organization and assigning                                                                              auditing, design reviews, responsibility, quality assurance should be recognized as an                                                                          and independent reviews by interdisciplinary function involving many organizational                                                                              the review bodies and components and, therefore, should not be regarded as the sole                                                                          functions.
domain of a single quality assurance group. For example, it may be more appropriate for nuclear engineers to perform reviews of plant nuclear engineering activities rather than quality assurance engineers because of the special competence required to perform these reviews. Quality assurance encompasses many functions and activities and extends to various levels in all participating organizations, from the top executive to all 10/28/2010                                                                  Organization                                                                Page 5 of 7
 
CRITERION 1                                              BASIC REQUIREMENT 1                                coIi.......
ANSI N45.2-1971"N18.7-1976        .                                    NQA-1 1994.
workers whose activities may influence quality.
3.2 Interface Control N18.7 &sect; 3.4 Onsite Operating Organization                        3.2.1 The external interfaces between organizations and the  N45.2 and N 18.7 only 3.4.1 General. A number of factors influence management in its  internal interfaces between organizational units, and changes addresses interface control decision regarding the establishment of an onsite operating      thereto, shall be documented.                                with external organizations organization. These include the owner organization's                                                                          related to the design control established staffing policies, the physical size and complexity                                                                function. However, this of the nuclear power plant, the number of units, the extent of                                                                should have further controls assistance provided by offsite technical support organizations,                                                                where external the extent of reliance on consultants and the availability of                                                                  organizations provide a qualified personnel from other sources to assist in activities,                                                                quality function for the such as initial start-up, refueling, maintenance or modification                                                              facility, such as a contractor work.                                                                                                                          performing construction A nuclear power plant onsite operating organization may                                                                        activities, or providing an change with time. For example, the number and qualifications                                                                  audit service, as well as of personnel making up the onsite technical support staff can                                                                  other functions.
generally be reduced as a plant progresses through initial operation to operational maturity. Management shall give                                                                      N18.7 focuses only on the careful consideration to the timing and extent of such changes.                                                                onsite operating organization functions.
This particular section provides more of a philosophy on the initial onsite organization and changes thereto rather than any specific requirements.
3.2.2 Interface responsibilities shall be defined and documented.
N18.7 &sect; 3.4.2 Requirements for the Onsite Operating                                                                            Part II, Section 1 of the Organization. The onsite operating organization shall include                                                                  QAPD and SCE&G one or more individuals knowledgeable in the following fields:                                                                commitment to Reg. Guide nuclear power plant operation; nuclear power plant mechanical,                                                                1.8 as defined in Part IV of electrical and electronic systems; nuclear engineering;                                                                        the QAPD.
chemistry and radiochemistry; radiation protection; and quality assurance. Initial incumbents or replacements for members of                                                                  N18.7 also addresses the onsite operating organization and offsite technical support                                                                positions requiring NRC 10/28/2010                                                                Organization                                                            Page 6 of 7
 
CRIT.ERION 1                                                    BASIC REQUIREMENT 1 "'4r'                      .
N.S          9                                ...... ....    ..... .      NQA-1 1994 organizations shall have appropriate experience, training and                                                      license requirements. This retraining to assure that necessary competence is maintained in                                                    is likewise addressed in Part accordance with the provisions of American National Standard                                                        II, Section 1 of the QAPD for Selection and Training of Nuclear Power Plant Personnel,                                                        and the specific N 18.1-1971. [4] Personnel whose qualifications do not meet                                                        commitment to Reg. Guide those specified in N18.1 and who are performing inspection,                                                          1.8 addressed in Part IV of examination, and testing activities during the operations phase                                                    the QAPD.
of the plant, including preoperational and start-up testing, shall be qualified to American National Standard Qualifications of                                                        N 18.7 requires the Inspection, Examination, and Testing Personnel for the                                                              minimum staffing levels of Construction Phase of Nuclear Power Plants, N45.2.6-1973 [5],                                                      licensed personnel who except that the QA experience cited for Levels 1,1, and m                                                          shall be present during should be interpreted to mean actual experience in carrying out                                                    various operating conditions the types of inspection, examination, or testing activity being                                                    and situations to be performed.                                                                                                          specified. These staffing The owner organization shall designate those positions in the                                                      levels are specified in the onsite operating organization, which shall be filled by personnel                                                  technical specifications holding NRC reactor operator and senior reactor operator                                                            rather than the QAPD.
licenses. Requirements for the minimum number of personnel holding such licenses who shall be present at the plant under various operating conditions and situations shall also be specified.
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CRITERION 2                                                  BASIC REQUIREMENT 2                                  COMMENTS      .
                  .ANSI N45.2-1971I18~.7-1976                .NQAf,4                                    19
: 2. QUALITY ASSURANCE PROGRAM N45.2 &sect; 1.3 &#xb6;1 - It is the responsibility of the plant owner to      A documented quality assurance program shall be planned,        Similar requirement.
provide for the establishment and execution of a quality            implemented, and maintained in accordance with this Part (Part assurance program for the plant consistent with the provisions      I), or portions thereof.
of this standard.
N45.2 &sect;2 &#xb6;3 - The program shall identify the items and services      The program shall identify the activities and items to which it  Similar requirement.
to which this and other standards apply.                            applies.
N45.2 &sect;2 &#xb6; 1 - The establishment of the program shall include        The establishment of the program shall include consideration of  Similar requirement.
considerations of the technical aspects of the activities to be      the technical aspects of the activities affecting quality.
performed. The program shall contain provisions to assure identification of and compliance with requirements of pertinent ANSI and other recognized and appropriate engineering codes, standards, requirements, and practices.
N45.2 &sect;2 &#xb6;3 - Since items and services will differ in regard to      The program shall provide control over activities affecting      Similar requirement.
relative safety, reliability, and performance importance. Various    quality to an extent consistent with their importance.
methods or levels of control and verification may be used to assure adequate quality. Regardless of the methods or levels used, the program shall provide for the assurance of quality consistent with applicable codes, standards, and other requirements. As a guideline, some factors to be considered in assigning methods or levels of quality assurance are as follows:
(1) The importance of malfunction or failure of the item to plant safety or reliability (2) The design and fabrication, complexity or uniqueness of the item. (3) The need for special controls and surveillance over processes and equipment. (4) The degree to which functional compliance can be demonstrated by inspection or test. (5) The quality history and degree of standardization of the item.
N45.2 &sect;2 &#xb6;1 - A quality assurance program which complies            The program shall be established at the earliest time consistent Similar requirement.
with the applicable sections and elements of this standard shall    with the schedule for accomplishing the activities.
be established at the earliest practical time consistent with the schedule for accomplishing the activities for the nuclear power plant.
N45.2 &sect;2 &#xb6;6 - The program shall provide for the                      The program shall provide for the planning and                  Similar requirements.
accomplishment of activities affecting quality under suitably      accomplishment of activities affecting quality under suitably controlled conditions. Controlled conditions include the use of    controlled conditions. Controlled conditions include the use of
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CRITERION.2    ...                  .    ..
* BASIC REQUIREMENT 2 ANSI N45.2-19711N18.7-1976                                                    NQA-1 1994T" appropriate equipment, suitable environmental conditions for      appropriate equipment, suitable environmental conditions for accomplishing the activity, and assurance that prerequisites for  accomplishing the activity, and assurance that prerequisites for the given activity have been satisfied. The program shall take    the given activity have been satisfied. The program shall into account the need for special controls, processes, test      provide for any special controls, processes, test equipment, equipment, tools, and skills to attain the required quality and  tools, and skills to attain the required quality and for the need for verification of quality by inspection, examination,  verification of quality.
or test.
N45.2 &sect;2 &#xb6;2 - The program shall define the organizational        The program shall provide for indoctrination and training, as    Organizational structure is structure within which the quality assurance program is to be    necessary, of personnel performing activities affecting quality  covered in Basic planned and implemented and shall clearly delineate the          to assure that suitable proficiency is achieved and maintained. Requirement 1 of NQA-1.
responsibility and authority of the various personnel and                                                                          NQA-1 focuses on organizations involved,                                                                                                            indoctrination and training of personnel under this basic requirement, is covered in QAPD, Section 2.
N45.2 &sect;2 &#xb6;7 - The program shall provide for the regular review,  Management of those organizations implementing the quality      Similar requirement.
by management of organizations participating in the program,      assurance program, or portions thereof, shall regularly assess of the status and adequacy of that part of the Quality Assurance  the adequacy of that part of the program for which they are Program for which they have designated responsibility,            responsible and shall assure its effective implementation.
Note: Supplement 2S-1 provides requirements while Appendix      NRC Reg. Guides 1.8 and Note: ANSI N45.2.6 addresses the qualification of inspection      2A-1 is considered nonmandatory (by NQA-1) guidance on          QAPD Section 2.6 require and test personnel.                                              qualification of inspection and test personnel.                  using NQA-1, Appendix 2A-1 for inspection and test personnel qualification.
ANSI N45.2.6-1978 QUALIFICATIONS OF INSPECTION,                  SUPPLEMENT 2S-1 EXAMINATION AND TESTING PERSONNEL FOR                            Supplementary Requirements for the Qualification of NUCLEAR POWER PLANTS                                              Inspection and Test Personnel
: 1. INTRODUCTION                                                  1 GENERAL 1.1 Scope This Standard delineates the requirements for the qualification  This Supplement provides amplified requirements for the          NQA-1 does not define of personnel who perform inspection, examination, and testing    qualification of personnel who perform inspection and testing    "examination" separate to verify conformance to specified requirements of nuclear        to verify conformance to specified requirements for the purpose  from inspection and testing, power plant items (structures, systems, and components of        of acceptability,                                                but the intent is the same.
nuclear power plants) whose satisfactory performance is required to prevent postulated accidents which could cause undue risk to the health and safety of the public; or to mitigate 10/28/2010                                                        Quality Assurance Program                                                        Page 2 of 26
 
CRITERION 2                                                BASIC REQUIREMENT 2 ANSI N45,.2-1971/N 18.7-1976                                              NQA-l 1994          CMET the consequences of such accidents if they were to occur. The requirements may also be extended to other items of nuclear power plants when specified in contract documents.
Regulatory Guide-l1.58 C-I "The requirements for qualification of nuclear power plant inspection, examination, and testing personnel (4) that are included in ANSI N45.2.6-1978 are acceptable to the NRC staff and provide an adequate basis for complying with the pertinent quality assurance requirements of Appendix B to CFR Part 50, subject to the following:
(4)The terms "inspection," "examination," and "testing" are defined in Section 1.4, "Definition," of ANSI N45.2.6-1978. 1.
Section 1.2, "Applicability," of ANSI N45.2.6-1978 states that the standard applies "to personnel who perform inspections, examinations, and tests.. .during preoperational and startup testing, and during operational phases of nuclear power plants."
However, for qualification of personnel (1) who approve preoperational, startup, and operational test procedures and test results and (2) who direct or supervise the conduct of individual preoperational, startup, and operational tests, the guidelines contained in Regulatory Guide 1.8, "Personnel Selection and Training," should be followed in lieu of the guidelines of ANSI N45.2.6-1978."                                                    -I 1.2 Auolicabilitv
: 1.              AD              iablt The requirements of this Standard apply to personnel who                                                Applicability of NQA perform inspections, examinations, and tests during fabrication                                          1994 is addressed in the prior to and during receipt of items at the construction site,                                          Introduction (Section I- 2, during construction, during preoperational and startup testing,                                          not in each section.)
and during operational phases of nuclear power plants. The requirements of this Standard do not apply to personnel who                                              Note VCSNS was perform inspections for government or municipal authorities, or                                          previously committed to who perform as authorized inspectors in accordance with the                                              Regulatory Guide 1.58, ASME Boiler and Pressure Vessel Code. The requirements of                                                which was withdrawn by this Standard are not intended to apply to personnel who only                                            the NRC based on perform inspection, examination, or testing in accordance with                                          acceptance of NQA-l-1983.
ANST "Recommended Practice No. SNT-TC-IA", since these                                                  The NRC has accepted personnel are certified in accordance with the requirements of                                          NQA- I- 1994 as equivalent SNT-TC- 1A and its applicable supplements. The requirements                                              to NQA 1983 (Exelon Page 3 of 26 Quality Assurance Program 10/28/2010                                                          Quality Assurance Program                            Page 3 of 26
 
CRITERION 2.                                            BASIC REQUIREMENT. 2          ME ANSI N45.2-19711N18.7-1976                                            NQA-1 1994 of this Standard are optional, at the discretion of the employer,                                      SER), therefore any specific for application to personnel who perform calibration or to                                            reference in this table to RG craftsmen who perform installation checkouts as part of their                                          1.58 is met or superseded basic installation responsibility to ready the installation for                                        by use of NQA-1.
preoperational testing.
Regulatory Guide-l.58 C-2. Section 1.2, "Applicability," of ANSI N45.2.6-1978 states: "The requirements of this Standard are not intended to apply to personnel who only perform inspection, examination, or testing in accordance with ASNT
'Recommended Practice No. SNT-TC- 1A', since these personnel are certified in accordance with the requirements of SNT-TC-1A and its applicable supplements." SNT-TC-1A-1975 is acceptable for the qualification of personnel performing nondestructive examinations and should be used where applicable, subject to the following: a. SNT-TC-1A-1975 applies to qualification of nondestructive testing personnel for the following nondestructive test methods: (1) Radiographic Testing; (2) Magnetic Particle Testing; (3) Ultrasonic Testing; (4) Liquid Penetrant Testing;(5) Eddy Current Testing;(6)
Neutron Radiographic Testing; and (7) Leak Testing. b. For qualification of personnel performing nondestructive examinations required by Section mI and Section XI of the ASME Boiler and Pressure Vessel Code, SNT-TC-1A-1975 should be used in conjunction with the additional provisions of the Code.
Regulatory Guide-1.58 C-3. Section 1.2, "Applicability," of ANSI N45.2.6-1978 states: "The ASME Boiler and Pressure Vessel Code, as well as other ANSI Standards, have been considered in the development of the Standard, and this Standard is intended to be compatible with their requirements."
While Section mI and Section XI of the ASME Boiler and Pressure Vessel Code address requirements for the qualifications of certain personnel who perform inspection, examination, and testing, these sections do not address the qualification of all personnel described in ANSI Standard N45.2.6.-1978. ANSI N45.2.6-1978, subject to the exceptions of the regulatory positions, should be used in conjunction with 10/28/2010                                                      Quality Assurance Program                            Page 4 of 26
 
S CRITERION I          2,    .      ...              .  ... BASIC REQUIREMENT2*
ANSI N45.2-4971/N18.&7-1976                                              NQA-1 1994 Section I1and Section XI of the ASME Boiler and Pressure Vessel Code for the qualification of inspection, examination, and testing personnel where the ASME Code does not address the requirements covered by ANSI N45.2.6-1978.
Regulatory Guide-1.58 C4. Section 1.5, "Referenced Documents," of ANSI N45.2.6-1978 states: "Other documents that are required to be included as a part of this Standard are either identified at the point of reference or described in Section 6 of this Standard." The specific applicability or acceptability of listed standards has been or will be covered separately in other regulatory guides, where appropriate.
Regulatory Guide-1.58 C-9. Section 1.2, "Applicability," of ANSI N45.2.6-1978 states: "The requirements of this Standard do not apply to personnel who perform inspections for government or municipal authorities, or who perform as authorized inspectors in accordance with the ASME Boiler and Pressure Vessel Code." The requirements and recommendations of ANSI N45.2.6-1978, subject to the provisions of Regulatory Positions I through 8, are considered acceptable for use by or for all NRC permit holders and licensees, including those that are government or municipal authorities.
This Standard is to be used in conjunction with ANSI N45.2.                                            NQA-1 incorporates ANSI The requirements apply to personnel of the owners, architect-                                          N45.2. NQA-1 is also engineers, nuclear power plant system designers and system                                              intended to be compatible suppliers, plant designers and plant constructors, equipment                                            with ASME Boiler and suppliers, outside testing agencies, and consultants. The ASME                                          Pressure Vessel Code.
Boiler and Pressure Vessel Code, as well as other ANSI Standards have been considered in the development of the standard, and this Standard is intended to be compatible with their requirements.
1.3 Responsibility It is the responsibility of each organization participating in the                                      Responsibility is defined in project to assure that only those personnel within their                                                the Introduction to Part I of respective organizations who meet the requirements of this                                              NQA-1-1994, Section 3.
Standard are permitted to perform inspection, examination, and testing activities covered by this Standard that verify conformance to quality requirements.
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CRITERION 2BASIC                                                    .REQUIREMENT.2                                COMMENTS ANSI N45.2-1971/N18.-7-1976                                                NQA-1 1994 The organization or organizations responsible for establishing the applicable requirements for activities covered by this Standard shall be identified and the scope of their responsibility shall be documented. The work of establishing selection and training practices and qualification procedures and of providing the resources in terms of personnel, equipment, and services necessary to implement the requirements of this Standard, may be deleted to other qualified organizations and such delegations be documented. It is the responsibility of each organization using personnel covered by this Standard to conform to the requirements of this Standard applicable to the organization's work. It is the responsibility of the organization performing these activities to specify the detailed methods and procedures for meeting the requirements of this Standard, unless they are specified in the contract documents.
1.4 Definitions 1.4.1 Inspection. A phase of quality control which by means of    inspection - examination or measurement to verify whether an      NQA- 1-1994, Part I -
examination, observation, or measurement determines the            item or activity conforms to specified requirements (From        Introduction defines conformance of materials, supplies, parts, components,            NQA- 1-1994, Part I - Introduction)                              inspection similar to ANSI appurtenances, systems, processes, or structures to                                                                                  N45.2.6 predetermined quality requirements 1.4.2 Examination. An element of action consisting of              (NQA-I-1994, Part II definitions) examination - an element of    NQA-1 Subpart 2.8 defines investigation of materials, supplies, parts, components,          inspection consisting of investigation of materials, components,  examination similar to appurtenances, systems, processes, or structures to determine      supplies, and services to determine conformance to those          ANSI N45.2.6 conformance to those specified requirements which can be          specified requirements which can be determined by such determined by such investigation. Examination is usually          investigation. Examination is usually nondestructive and nondestructive and includes simply physical manipulation,          includes simple physical manipulation, gaging, and gaging, and measurement                                            measurement.
1.4.3 Testing. The determination or verification of the            testing - an element of verification for the determination of the NQA-1 defines testing capability of an item to meet specified requirements by            capability of an item to meet specified requirements by          similar to ANSI N45.2.6 subjecting the item to a set of physical, chemical,                subjecting the item to a set of physical, chemical, environmental, or operating conditions.                            environmental, or operating conditions 1.4.4 Refer to ANSI N45.2.10 for other definitions to be used in                                                                    NQA- 1 contains definitions conjunction with this Standard.                                                                                                      in the Introduction to Part I that are used with this section.
It supplements the requirements of Basic Requirement 2 of this    Not a requirement.
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CRITERION 2                .BASIC                                                              REQUIREMENT 2                                      o    iirr ANSI N45.2-19711N18.7-1976                                                                            NQA-1 1994 Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I). The requirements of this Supplement do not apply to the qualification of personnel for performance of nondestructive examination.                        ____________
1.5 Referenced Documents_____________
Other documents that are required to be included as a part of                                                                                                Not a requirement.
this Standard are either identified at the point of reference or described in Section 6 of this Standard. The issue or edition of the referenced document that is required will be specified either at the point of reference or in Section 6 of this Standard._____________
NI 8.7 - 3.3 Indoctrination and Training.                                              2 CERTIFICATION____________
Provisions shall be made for indoctrination and training of                                                                                                  N 18.7 and NQA-lI have those personnel in the owner organization performing activities                                                                                              similar requirements for affecting quality to assure that suitable proficiency is achieved                                                                                            qualification and training.
and maintained. Such personnel also shall be provided training                                                                                                NQA- 1 covers this with concerning the administrative controls and quality assurance                                                                                                  section 2.1 through 2.7 10/28/2010...
program which, as a minimum, shall  ... . .include
                                                . .......,.:. following the        ......
                                                                        .... *..":*.. i. Quality
                                                                                            *.* >.**. Assurance.
Prog..ram
                                                                                                                        .  *">* :**." * ** *. ... **  !i::*: below. .....:.*... .:*:i.:**
In addition, PageNQA-7 of 26...
1, areas: overall company policies, procedures, or instructions                                                                                                  SUPPLEMENT 2S-4, calls which establish the program; procedures or instructions which                                                                                                out additional implement the program related to the specific job-related                                                                                                    indoctrination and training activity,                                                                                                                                                    requirements. Intent of the standards is consistent, although NQA-lI- 1994 is more specific.
: 2. GENERAL REQUIREMENTS                                                                2.1 Qualification Requirements____________
2.1 Planning Plans shall be developed for staffing, indoctrination, and                                                                                                    NQA-l addresses Planning training of an adequate number of personnel to perform the                                                                                                    in Part HI.
required actions, examinations, and tests and shall reflect the schedule of project activity so as to know adequate time for assignment or selection and training of the required personnel.                        _____________________________
: 4. PERFORMA4NCE                                                                        The responsible organization shall designate those activities        Similar requirements.
Personnel who are assigned the responsibility and authority to                          that require qualified inspection and test personnel and the          Rather than NQA-lI perform fuinctions covered by this Standard shall have, as a                            minimum requirements for such personnel. Further, the                containing a table for levels minimum, the level of capability shown in Table 1. When a                              responsible organization shall establish written procedures for      of capability the single inspection or test requires implementation by a team or                          the qualification of inspection and test personnel, and for the      information is contained in 10/28/2010                                                                              Quality Assurance Program                                                                      Page 7 of 26
 
CRITERION 2                        .BASIC                                        REQUIREMENT 2 ANSI N45.2-1971/N 18.7-1976                                                                NQA-1 1994,                                      COMMENT group, personnel not meeting the requirements of this Standard              assurance that only those personnel who meet the requirements            Appendix 2A- 1.
may be used in data-taking assignments or in plant or                        of this Supplement are permitted to perform inspection and test equipment operation provided they are supervised or overseen                activities.                                                              Note: VCSNS was by a qualified individual participating in the inspection,                  When a single inspection or test requires implementation by a            previously conmmitted to examination, or test.                                                        team or a group, personnel not meeting the requirements of this          Regulatory Guide 1.58, Regulatory Guide-i .58 C-7. Section 4, "Performance, t ' of ANSI            Part (Part I) may be used in data taking assignments or in plant        which was withdrawn by N45.2.6-1 978 states: "When a single inspection or test requires            or equipment operation, provided they are supervised or                  the NRC based on implementation by a team or group, personnel not meeting the                overseen by a qualified individual,                                      acceptance of NQA-l-1983.
requirements of this Standard may be used in data-taking                                                                                              The NRC has accepted assignments or in plant or equipment operation provided they                                                                                          NQA- 1-1994 as equivalent are supervised or overseen by a qualified individual                                                                                                  to NQA-lI- 1983 (Exelon participating in the inspection, examination, or test." These                                                                                        SER), therefore any specific personnel should have sufficient training to ensure an                                                                                                reference in this table to RG acceptable level of competence in the performance of their                                                                                            1.58 is met or superseded activities.                                                                  __________________by                                                        use of NQ2A-  1.
2.2 Personnel Selection Personnel selected for performing inspection and test activities 10/28/2010                          . . ..... . *,....... :      ... shall
                                                                            .:**  *.*.,,:haveAssuranc Quality..      the experience or training commensurate ProgamI                        with the 2 ".,.'.:....i.**.**,,    ... .. *.*:*. PageEE 8.of..26..:
_____________________________________________scope, complexity, or special nature of the activities.
: 2. 1.1 Indoctrination.                                                      2.3 Indoctrination Provisions shall be made for the indoctrination of personnel as              Provisions shall be made for the indoctrination of personnel as          Similar Requirements to the technical objectives of the project; the codes and                    to the technical objectives and requirements of the applicable standards that are to be used; and the quality assurance                    codes and standards, and the quality assurance program elements that are to be employed,                                            elements that are to be employed.
2.1.2 Training.                                                              2.4 Training The need for formal training programs shall be determined, and The need for a formal training program shall be determined,                            Similar Requirements such training activities shall be conducted as required to qualify and such training activities shall be conducted as required to personnel who perform inspections, examinations, and tests.                  qualify personnel who perform inspections and tests.
On-the job participation shall also be included in the program,              On-the-job training shall also be included in the program, with          Similar Requirements with emphasis on first-hand experience gained through actual                emphasis on first-hand experience gained through actual performance of actions, examinations, and tests.                            performance of inspections and tests.
Records of training, when used as the basis for certification,                                                                                        Records are addressed in shall be maintained.                                                                                                                                  Section 3 of this
________________________________________ _______________________________SupplementSppleent o NQ- 1 2.2 Determination of Initial Capability                                      2.5 Determination of Initial Capability____________
The capabilities of a candidate for certification shall be initially        The capabilities of a candidate for certification shall be initially Similar Requirements deternined by a suitable evaluation of the candidate's                      deternined by a suitable evaluation of the candidate's_____________
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2                                          BASIC    REQUIREMENT2CMMNT
                                                                                      .CRITERION ANSI N45.2-1971/Nl8.7-1976                                                  NQA-1 1994                                        CM ET education, experience, training, test results, or capability      education, experience, training, and either test results or          Note: VCSNS was demonstration.                                                    capability demonstration.                                            previously committed to Regulatory Guide-l.58 C-10. Section 2.2, "Determination of                                                                              Regulatory Guide 1.58, Initial Capability," and Section 2.3, "Evaluation of                                                                                    which was withdrawn by Performance," of ANSI N45.2.6-1978 deal with the use of                                                                                  the NRC based on evaluation of job performance and determination of initial                                                                              acceptance of NQA-1-l1983.
capability to perform the job. Use of the measures outlined in                                                                          The NRC has accepted these sections to establish that an individual has the required                                                                          NQA- 1-1994 as equivalent qualifications in lieu of required education and experience                                                                              to NQA 1983 (Exelon should result in documented objected evidence (i.e., procedures                                                                          SER), therefore any specific and record of written test) demonstrating that the individual                                                                            reference in this table to RG indeed does have "comparable" or "equivalent" competence to                                                                              1.58 is met or superseded that which would be gained from having the required education                                                                            by use of NQA-1.
and experience.
2.3 Evaluation of Performance                                      2.6 Evaluation of Performance The job performance of inspection, examination, and testing        The job performance of inspection and test personnel shall be        The requirements of this personnel shall be reevaluated at periodic intervals not to        reevaluated at periodic intervals not to exceed 3 years.              subsection are similar for exceed three years.                                                                                                                      ANSI N45.2.6 and NQA                                                                                                                                          1994.
Reevaluation shall be by evidence of continued satisfactory        Reevaluation shall be by evidence of continued satisfactory          Similar requirements performance or redetermination of capability in accordance        performance or re-determination of capability in accordance with Subsection 2.2.                                              with the requirements of para. 2.5 above.
If, during this evaluation or at any other time, it is determined  If during this evaluation or at any other time, it is determined by  Similar requirements by the responsible organization that the capabilities of an        the responsible organization that the capabilities of an individual are not in accordance with the qualifications          individual are not in accordance with the qualification specified for the job, that person shall be removed from that      requirements specified for the job, that person shall be removed activity until such time as the required capability has been      from that activity until such time as the required capability has demonstrated                                                      been demonstrated.
Any person who has not performed inspection, examination, or      Any person who has not performed inspection or testing                Similar requirements testing activities in his qualified area for a period of one year  activities in his qualified area for a period of 1 year shall be shall be reevaluated by a redetermination of required capability  reevaluated by a re-determination of required capability in in accordance with Subsection 2.2.                                accordance with the requirements of para. 2.5 above.
2.4 Written Certification of Qualification                        2.7 Certificate of Qualification The qualification of personnel shall be certified in writing in an The qualification of personnel shall be certified in writing in an The requirements of this appropriate form, including the following information:            appropriate form, including the following information:                subsection are virtually the 1.__employer'snameI_(a)_employer'sname;_                            Isame in both standards.
: 1. employer's name                                                (a) employer's name;                                                _____________
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CRITERION2                                            BASIC      EQUIR          T2                    ..  .
ANSI N45.2-19711N1.8.7-1976                                                  NQA-1. 1994
: 2. identification of person being certified                        (b) identification of person being certified;
: 3. level of capability                                            _
: 4. activities certified to perform                                  (c) activities certified to perform;
: 5. basis used for certification, including:                        (d) basis used for certification, which includes such factors as:
(a) records of education, experience and training                  (1) education, experience, indoctrination, and training (b) test results, where applicable                                  (2) test results, where applicable (c) results of capability demonstration                            (3) results of capability demonstration
: 6. results of periodic evaluations                                  (e) results of periodic evaluation;
: 7. results of physical examinations, when required                  (f) results of physical examinations, when required;
: 8. signature of employer's designated representative                (g) signature of employer's designated representative who is      Clarification in NQA-1 responsible for such certification;
: 9. date of certification and date of certification expiration      (h) date of certification and date of certification expiration.
2.5 Physical                                                        2.8 Physical The responsible organization shall identify any special physical    The responsible organization shall identify any special physical  Similar requirements.
characteristics needed in the performance of each activity,        characteristics needed in the performance of each activity,      NQA-I requires Personnel requiring these characteristics shall have them          including the need for initial and subsequent physical            "Subsequent examinations" verified by examination at intervals not to exceed one year.        examination,                                                      whereas N45.2 requires "intervals not to exceed one year."9
: 3. QUALIFICATIONS                                                  The following information is from Appendix 2A-1 3.1 General                                                        1GENERAL The requirements contained within this Section define the          This Appendix provides nonmandatory guidance on the                NQA- 1-1994, Supplement minimum capabilities that qualify personnel to perform            qualifications of inspection and test personnel. This Appendix    2S-1, Supplementary inspections, examinations, and tests which are within the scope    may be used in conjunction with Basic Requirement 2 and            Requirements for the of this Standard. There are three levels of qualification. The      Supplement 2S-1 of Part I.                                        Qualification of Inspection requirements for each level are not limiting with regard to        2 FUNCTIONAL QUALIFICATIONS                                      and Test Personnel will organizational position of professional status, but rather, are    Three levels of qualification may be utilized depending on the    include use of the guidance limiting with regard to functional activities which are within the complexity of the functions involved. The recommendations for      provided in Appendix 2A-1, scope of this Standard.                                            each level are not limiting with regard to organizational          or the proposed alternatives position or professional status but, rather, are limiting with    as approved.
regard to functional activities.
Proposed alternative to qualification requirements for VCSNS QA Program - (1) SCE&G company may choose to not specifically use the designations of Level I, II, and III for 10/28/2010                                                          Quality Assurance Program                                                      Page 10 of 26
 
CRITERION 2                                                  BASIC REQUIREMENT 2                                    COMMENTS ANSI N45.2-1971 1N8.7-1976                                                  NQA-1 1994 qualification of inspectors. However, the qualification program will ensure that only personnel that meet the required education and experience requirements, and have demonstrated appropriate capabilities in the inspection activities they are assigned will be certified and used to perform those inspections.
The inspectors used in planning inspections will meet or exceed the education and experience requirements of for a Level II inspector plus have an additional three years of related inspection experience for nuclear facilities. The inspectors used to evaluate the capabilities of other inspectors will meet or exceed the education and experience requirements for a Level II inspector plus have an additional five years of related experience in inspection, examination, or testing activities for nuclear facilities. This related experience may include ASME VT 1, 2, or 3 examinations, NDE, or ASME Section XI in-service inspection or testing activities. A qualified engineer may also be used to evaluate the capabilities of an inspector.
The training program for inspectors will be evaluated and approved by personnel who meet the education, experience, and capabilities designated for a Level III person specific to the discipline or a qualified engineer. For the purposes of this alternative, a qualified engineer is one who has a baccalaureate in engineering in a discipline related to the inspection activity (such as, electrical, mechanical, civil) and has a minimum of five years engineering work experience with at least two years of this experience related to nuclear facilities. (2) As an alternative to the education requirement of high school graduation (or GED), satisfactory demonstration of reading, writing, and mathematical skills through completion of an NANT accredited training development program or an approved inspector training program for nuclear facility personnel will be deemed equivalent.
The following information on Level I, II, and III is from Appendix 2A-1 3.2 Level I Personnel Capabilities                              2.1 Level I Personnel Capabilities A Level I person shall be capable of performing the inspections, A Level I person should be capable of performing and                Similar capabilities examinations, and tests that are required to be performed in    documenting the results of inspections or tests that are required I described.
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CRITERION 2                                                  BASIC RE QUIREMENT 2                                    CM ET ANSI N45.2-19711Nl8.7-1976.                                                  NQA-1 199~4                                          M E accordance with documented procedures and/or industry                to be performed in accordance with documented procedures, practices. The individual shall be familiar with the tools and      acceptance standards, and/or industry practices as defined in equipment to be employed and shall have demonstrated                user's written procedures.
proficiency in their use. The individual shall also be capable  of determining that the calibration status of inspection and measuring equipment is current, that the measuring and test equipment is in proper condition for use, and that the inspection, examination, and test procedures are approved.          ____________________________
3.3 Level II Personnel    Capabilities                              2.2 Level II Personnel Capabilities A Level 11 person shall have all of the capabilities of a Level I    A Level HI person should have all of the capabilities of a Level I  Similar capabilities person for the inspection, examination or test category or class    person for the inspection or test category or class in question. described.
in question. Additionally, a Level HI person shall have              Additionally, a Level HI person should have demonstrated demonstrated capabilities in planning inspections,                  capabilities in planning inspections and tests; in setting up tests, examinations, and test; in setting up tests including preparation    including preparation and setup of related equipment, as and  set-up of related  equipment,  as appropriate; in supervising  appropriate; in supervising or maintaining surveillance over the or maintaining surveillance over the inspections, examinations,      inspections and tests; in supervising and certifying lower level and tests; in supervising and certifying lower level personnel; in personnel; and in evaluating the validity and acceptability of reporting inspection, examination, and testing results; and in      inspection and test results.
evaluating the validity and acceptability of inspection, examination, and test results                                      _____________________________
3.4 Level IIl Personnel Capabilities                                2.3 Level III Personnel Capabilities A Level 111 person shall have all of the capabilities of a Level Hl A Level Ill person should have all of the capabilities of a Level    Similar capabilities person for the inspection, examination or test category or class    H person for the inspection or test category or class in question. described.
in question. In addition, the individual shall also be capable of    in addition, the individual should also be capable of evaluating evaluating the adequacy of specific programs used to train and      the adequacy of specific programs used to train and certify test inspection, examination, and test personnel whose              inspection and test personnel whose qualifications are covered qualifications are covered by this Standard.                        by this Appendix.
Regulatory 10/28/2010  Guide-l  .58 C-5. Section  3.4, "Level M  Personnel      QualityidAssuranceceProbilit                                                      Pagens12ctf26 Capabilities," of ANSI N45.2.6-1978 specifies the capability requirements of Level III personnel. In additional, the individual should be capable of reviewing and approving inspection, examination, and testing procedures and of evaluating the adequacy of such procedures to accomplish the inspection, examination, and test objectives areapproved.
The following information on education and experience is from
________________________________________Appendix 2A- 1____________
3.5 Education and Experience - Recommendations                      3 EDUCATION AND EXPERIENCE QUALIFICATIONSt, 10/28/2010                                                            Quality Assurance Program                                                        Page 12 of 26
 
CRITERION..2 ....                                          BASIC REQUIREMENT 2.....              ..........    ........
ANSI N45.2-19711N18.7-1976,                                              NQA-i 1994                                          CM ET The following is the recommended personnel education and        These education and experience recommendations should be              Similar recommendations.
experience for each level. These education and experience        considered with recognition that other factors commensurate recommendations should be treated to recognize that other        with the scope, complexity, or special nature of the activity may factors may provide reasonable assurance that a person can      provide reasonable assurance that a person can competently competently perform a particular task. Other factors which may  perform a particular task. Other factors which may demonstrate demonstrate capability in a given job are previous performance  capability in a given job are previous performance or or satisfactory completion of capability testing                satisfactory completion of capability testing. These factors and Regulatory Guide-i.58 C-6. Section 3.5, "Education and          the basis for their equivalency should be documented.
Experience-Recommendations," of ANSI N45.2.6.-1978 states that the education and experience specified are recommendations and that other factors may provide reasonable assurance that a person can competently perform a particular task. The set of recommendations has been reviewed by the NRC staff and found to be acceptable with one exception. In addition to the recommendations listed under Section 3.5 for Level I, II, and III personnel, the candidate should be a high school graduate or have earned the General Education Development equivalent of a high school diploma. Since only one set of recommendations is provided for the education and experience of personnel, a commitment to comply with the regulatory positions of this guide in lieu of providing an alternative to the recommendations of the standard means that the specified education and experience recommendations of the standard will be followed.
3.5.1 Level  I                                                  3.1 Level I
: 1. Two years of related experience in equivalent inspection,    3.1.1 Two years of related experience in equivalent inspection        Similar recommendations.
examination, or testing activities, or                          or testing activities; or
: 2. High school graduation and six months of related experience  3.1.2 High school graduation and 6 months of related                  Similar recommendations.
in equivalent inspection, examination, or testing activities, or experience in equivalent inspection or testing activities; or
: 3. Completion of college level work leading to an Associate      3.1.3 Completion of college level work leading to an associate        Similar recommendations.
Degree in a related discipline plus three months of related      degree in a related discipline plus 3 months of related experience in equivalent inspection, examination, or testing    experience in equivalent inspection or testing activities.
activities.
3.5.2 Level II                                                  3.2 Level II
: 1. One year of satisfactory performance as Level I in the        3.2.1 One year of satisfactory performance as a Level I in the        Similar recommendations.
corresponding inspection, examination or test category or class, corresponding inspection or test category or class; or or 10/28/2010                                                        Quality Assurance Program                                                        Page 13 of 26
 
CRITERION 2..                                              . BASIC REQUIREMENT 2                                    COMMENTS ANSI N451-19711N18.7-1976                                                        NQA-1 1994
: 2. High school graduation plus three years of related experience      3.2.2 High school graduation plus 3 years of related experience      Similar recommendations.
in equivalent inspection, examination, or testing activities, or      in equivalent inspection or testing activities; or
: 3. Completion of college level work leading to associate Degree      3.2.3 Completion of college level work leading to an associate      Similar recommendations.
in a related discipline plus one year related experience in          degree in a related discipline plus 1 year of related experience equivalent inspection, examination, or testing activities, or        in equivalent inspection or testing activities; or
: 4. Four-year college graduation plus six months of related            3.2.4 Graduation from a 4 year college plus 6 months of related      Similar recommendations.
experience in equivalent inspection, examination, or testing          experience in equivalent inspection or testing activities.
activities 3.5.3 Level III                                                      3.3 Level III
: 1. Six years of satisfactory performance as a Level II in the        3.3.1 Six years of satisfactory performance as a Level HIin the      Similar recommendations.
corresponding inspection, examination or test category or class,      corresponding inspection or test category or class; or or
: 2. High school graduation plus ten years of related experience        3.3.2 High school graduation plus 10 years of related                Similar recommendations.
in equivalent inspection, examination, or testing activities; or      experience in equivalent inspection or testing activities; or high high school graduation plus eight years experience in equivalent      school graduation plus 8 years of experience in equivalent inspection, examination, or testing activities, with at least two    inspection or testing activities with at least 2 years as a Level II years as Level II, and with at least two years associated with        and with at least 2 years associated with nuclear facilities - or, nuclear facilities-or if not, at least sufficient training to be      if not, at least sufficient training to be acquainted with the acquainted with the relevant quality assurance aspects of a          relevant quality assurance aspects of a nuclear facility; or nuclear facility, or
: 3. Completion of college level work leading to an associate          3.3.3 Completion of college level work leading to an associate      Similar recommendations.
Degree and seven years of related experience in equivalent            degree and 7 years of related experience in equivalent inspection, examination, or testing activities, with at least two    inspection or testing activities with at least 2 years of this years of this experience associated with nuclear facilities-or if    experience associated with nuclear facilities - or, if not, at least not, at least sufficient training to be acquainted with the          sufficient training to be acquainted with the relevant quality relevant quality assurance aspects of a nuclear facility, or          assurance aspects of a nuclear facility; or
: 4. Four-year college graduation plus five years of related            3.3.4 Graduation from a 4 year college plus 5 years of related      Similar recommendations.
experience in equivalent inspection, examination, or testing          experience in equivalent inspection or testing activities with at activities, with at least two years of this experience associated    least 2 years of this experience associated with nuclear facilities with nuclear facilities-or if not, at least sufficient training to be - or, if not, at least sufficient training to be acquainted with the acquainted with the relevant quality assurance aspects of a          relevant quality assurance aspects of a nuclear facility.
nuclear facility.
The following is from Supplement 2S-1
: 5. RECORDS                                                            3 RECORDS 3.1 Record Files A File of records of personnel qualification shall be established    Records of personnel qualification shall be established and          Similar requirement.
and maintained by the employer. Collection, storage, and              maintained by the employer. These records shall include the 10/28/2010                                                            Quality Assurance Program                                                          Page 14 of 26
 
CRITERION 2                                                BASIC REQUIREMENT 2                                  CM      ET ANSI N45.2-1971NI8i.7-1976                                                  NQA-I 1994 control of records required by this Standard shall be in          information required by para. 2.7 above.
accordance with ANSI N45.2.9.
SUPPLEMENT 2S-2 Supplementary Requirements for the Qualification of Nondestructive Examination Personnel ANSI N45.2.6 addresses the qualification of inspection and test    NQA-l -1994, Supplement 2S-2, Supplementary Requirements        Exceptions and personnel, as described above. For NDE activities, N45.2.6        for the Qualification of Nondestructive Examination Personnel,  clarifications to NQA-l-refers to the use of SNT-TC- 1A for qualification,                subsection 2.1, requires application of Recommended Practice    1994, supplement 2S-2 Regulatory Guide-i.58 C-8. An important concept that is not        SNT-TC-1A, June 1980 Edition to NDE personnel. SCE&G            defined.
addressed directly in ANSI N45.2.6-1978. ANST                      will implement the qualification program required by this Recommended Practice No. SNT-TC-IA-1975, or the ASME              supplement in accordance with the applicable standard for the  Note: VCSNS was Boiler and Pressure Vessel Code is that occupational radiation    facility's commitment to the ASME code or other applicable      previously committed to exposure should be maintained as low as is reasonable              code governing the activity. This alternative is considered    Regulatory Guide 1.58, achievable (ALARA). In all cases where inspection,                acceptable because other editions of this recommended practice  which was withdrawn by examination, and testing personnel may be exposed to radiation    or other national standards may be required by industry codes  the NRC based on field during their activities in restricted areas, these personnel or regulations for qualification of NDE personnel              acceptance of NQA- I-1983.
should receive instruction in radiation protection and radiation-                                                                  The NRC has accepted dose-reduction considerations related to work they are expected                                                                    NQA- 1-1994 as equivalent to perform. Regulatory Guide 8.8, "Information Relevant to                                                                        to NQA-I- 1983 (Exelon Ensuring that Occupational Radiation Exposures at Nuclear                                                                          SER), therefore any specific Power Stations Will Be As Low As Is Reasonably Achievable,"                                                                        reference in this table to RG describes techniques, features, and recommendations to                                                                            1.58 is met or superseded maintain occupational exposures ALARA.                                                                                            by use of NQA-1.
1 GENERAL This Supplement provides amplified requirements for the qualification of personnel who perform radiographic (RT),
magnetic particle (MT), ultrasonic (UT), liquid penetrant (PT),
eddy current (ET), neutron radiographic (NRT), leak testing (LT), acoustic emission (AE), and visual testing (VT)
[hereinafter referred to as nondestructive examination (NDE)]
to verify conformance to specified requirements.
It supplements the requirements of Basic Requirement 2 of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
2 CERTIFICATION 10/28/2010                                                          Quality Assurance Program                                                      Page 15 of 26
 
CRITERION 2                                                BASIC REQUIREMENT 2..                                      m* s.
ANSI N45.2-19711N18.7-19,76;.                                              NQA-.. 1        "994 2.1 Applicable Documents The American Society of Nondestructive Testing                  Each standard invokes a Recommended Practice No. SNT-TC- 1A, December 1980              different edition of Edition, and its applicable supplements shall apply as          SNT-TC- 1A. The quality requirements to NDE personnel covered by this Supplement.      program should designate the specific edition SCE&G will meet. It may be that we describe that as being specified in the implementing procedures and correspondence with the NRC (similar to changed ASME codes).
2.2 Program The responsible organization shall establish written procedures for the control and administration of NDE personnel training, examination, and certification.
2.3 Records Records of personnel qualification shall be established and maintained by the employer.
SUPPLEMENT 2S-3                                                ANSI N45.2.23 addresses Supplementary Requirements for the Qualification of Quality    the qualification of lead Assurance Program Audit Personnel                              auditors. NQA- 1-1994 is consistent with ANSI N45.2.23.
ANSI N45.2.23 addresses the qualification of lead auditor:
This Standard provides requirements and guidance for the qualification of audit team leaders, henceforth identified as a "Lead Auditor", who organizes and directs audits, reports, audit findings, and evaluates corrective action. This Standard also provides requirements and guidance for the qualifications of individuals, henceforth referred to as "Auditor", who participate in an audit, such as technical specialists, management representatives, and auditors-in-training.
1.2 Applicability                                                1 GENERAL                                                      N45.2.23 was a standalone document therefore repeats applicability and definitions 10/28/2010                                                        Quality Assurance Program                                                      Page 16 of 26
 
CRITERION 2                                ....          BASIC REQUIREMENT 2 ANSI N45.2-1971/N1.8.7-1976                                              NQA-1 1994                              CO MET defined in NQA- 1-1994.
The requirements of this Standard apply to Auditors and Lead Auditors who perform audits for the plant owner, contractors, or other organizations participating in activities affecting the quality of structures, systems, and components of nuclear power plants which are subject to audit in accordance with requirements of ANSI N45.2. This Standard shall be used in conjunction with the requirements of ANSI N45.2.12.
1.3 Responsibility The organization or organizations responsible for                                                                          Responsibility is defined in implementation of the applicable requirements of this standard                                                              the Introduction of NQA-l-shall be identified and the scope of their responsibilities and                                                            1994, Section 1-3.
authorities shall be documented. The work of establishing practices and procedures and providingthe resources in terms of personnel, equipment, and services necessary to implement the requirements of this Standard may be delegated to other organizations, and such delegations shall also be documented. It is the responsibility of each of these organizations to comply with the practices and procedures so established and to conform with the applicable requirements of this Standard.
1.4 Definitions The following definitions are provided to assure uniform                                                                    NQA-I-1994 calls out in understanding of selected terms as they are used in this                                                                    Supplement 2S-3-1 Standard. Other terms and definitions are contained in ANSI                                                                "General" what an N45.2. 10.                                                                                                                  "auditor" and "lead" auditor means rather than specific definitions.
1.4.1 Auditor. Any individual who performs any portion of an audit, including Lead Auditors, technical specialists, and others such as management representatives and auditors-in-training.
1.4.2 Lead Auditor. An individual qualified to organize and direct an audit, report audit findings, and evaluate corrective action.
1 4.3 Audit. A documented activity performed in accordance        audit - a planned and documented activity performed to    NQA-1 similar definition to with written procedures or checklists to verify, by examination  determine by investigation, examination, or evaluation of ANSI N45.2.10.
and evaluation of objective evidence, that applicable elements    objective evidence the adequacy of and compliance with of the quality assurance program have been developed,            established procedures, instructions, drawings, and other 10/28/2010                                                        Quality Assurance Program                                              Page 17 of 26
 
                        *CRITERION2.                                                BASIC REQUIREMENT 2                            COMMENTS
                  .ANSI N45.2-1971/N18..7-1976                                                NQA-l1 1994 documented, and effectively implemented in accordance with        applicable documents, and the effectiveness of implementation.
specified requirements. An audit should not be confused with      An audit should not be confused with surveillance or inspection surveillance or inspection for the sole purpose of process        activities performed for the sole purpose of process control or control or product acceptance.                                    product acceptance. [from Part I - Introduction]
1.5 Referenced Documents Documents that are referenced in this Standard are identified at the point of reference and described in Section 6 of this Standard REGULATORY POSITION RG 1.146 C l. Section 1.5 of ANSI/ASME N45.2.23-1978 states that documents that are referenced in this standard are identified at the point of reference and described in Section 6 of the standard. The specific applicability of these listed documents has been addressed in the latest revision of the following regulatory guides:
ANSI Standard Regulatory Guide N45.2 1.28 N45.2.9 1.88 N45.2.10 1.74 REGULATORY POSITION RG 1.146 C2. ANSI/ASME N45.2.23-1978 does not include the statement that is found in other N45.2 series standards excluding activities covered by ASME Boiler and Pressure Vessel Code Section III, Divisions I and 2, and Section XI from the requirements of the standard. The NRC staff considers that ANSI/ASME N45.2.23-1978 applies to these Code-covered activities where the ASME Code does not address the requirements covered by ANSI/ASME N45.2.23-1978.
: 2. QUALIFICATIONS OF AUDITORS AND LEAD AUDITORS (ANSI N45.2.23) 2.1 General                                                        This Supplement provides amplified requirements for the This Section delineates the qualifications of Auditor and Lead    qualification of an audit team leader, henceforth identified as a Auditors.                                                          Lead Auditor, who organizes and directs audits, reports audit findings, and evaluates corrective action.
This Supplement also provides amplified requirements for the qualifications of individuals, henceforth referred to as Auditors, who participate in an audit, such as technical specialists, management representatives, and auditors-in-training.
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CRITERION 2                                                BASIC REQUIREMENT 2                                    COMMENTS ANSI N45.2-19711N18.7-1976.                                                NQA-19~9~4 It supplements the requirements of Basic Requirement 2 of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
2.2 Qualification of Auditors                                      2 QUALIFICATION OF AUDITORS 2.1 Responsibility of Auditing Organization The responsible auditing organization shall establish the audit    The responsible auditing organization shall establish the audit    Similar requirements.
personnel qualifications and the requirements for the use of      personnel qualifications and the requirements for the use of technical specialists to accomplish the auditing of the quality    technical specialists to accomplish the auditing of quality assurance programs                                                assurance programs.
Personnel selected for quality assurance auditing assignments      Personnel selected for quality assurance auditing assignments      Similar requirements.
shall have experience or training commensurate with the scope,    shall have experience or training commensurate with the scope, complexity, or special nature of the activities to be audited. complexity, or special nature of the activities to be audited.
Auditors shall have, or be given, appropriate training or          Auditors shall have, or be given, appropriate training or          Similar requirements.
orientation to develop their competence for performing required    orientation to develop their competence for performing required audits.                                                            audits.
Competence of personnel for performance of the various            Competence of personnel for performance of the various            Similar requirements.
auditing functions shall be developed by one or more of the        auditing functions shall be developed by one or more of the following methods:                                                methods given in (a) through (c) below:
2.2.1 Orientation to provide a working knowledge and              (a) orientation to provide a working knowledge and                Similar requirements.
understanding of ANSI B45.2, this Standard, and the auditing      understanding of this Part (Part I) and the auditing organization's procedures for implementing audits and reporting    organization's procedures for implementing audits and reporting results.                                                          results; 2.2.2 Training programs to provide general and specialized        (b) training programs to provide general and specialized          Similar requirements.
training in audit performance.                                    training in audit performance.
General training shall include fundamentals, objectives,          General training shall include fundamentals, objectives,          Similar requirements.
characteristics, organization, performance, and results of quality characteristics, organization, performance, and results of quality auditing..                                                        auditing.
Specialized training shall include methods of examining,          Specialized training shall include methods of examining,          Similar requirements.
questioning, evaluating, and documenting specific audit items      questioning, evaluating, and documenting specific audit items and methods of closing out audit findings                          and methods of closing out audit findings.
2.2.3 On-the-job training guidance, and counseling under the      (c) on-the-job training, guidance, and counseling under the        Similar requirements.
direct supervision of a Lead Auditor. Such training shall          direct supervision of a Lead Auditor. Such training shall include planning, performing, reporting, and follow-up action      include planning, performing, reporting, and follow-up action involved in conducting audits.                                    involved in conducting audits.
2.3 Qualification of Lead Auditors                                3 QUALIFICATION OF LEAD AUDITORS An individual shall meet the requirements of paragraphs 2.3.1      An individual shall meet the requirements of para[graph]s 3.1      Similar requirements.
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CRITERION 2
                          ..                                                          BASIC                                          . COMMENTS
                                                                                                                                          .EQUIR..**NT    .
ANSI N45.2-19711N18.7-1976                                                  NQA-1 1994 through 2.3.5 prior to being designated a Lead Auditor.              through 3.4 below prior to being designated a Lead Auditor 2.3.1 Education and Experience. The prospective Lead Auditor                                                                      NQA-I-1994 does not shall have verifiable evidence that a minimum of ten (10)                                                                          require specific education credits under the following scoring system have been                                                                              and experience to the level accumulated.                                                                                                                      described in N45.2.23, but 2.3.1.1 Education (4 credits maximum). Associate degree from                                                                      has included this an accredited institution score one (1) credit or if the degree is                                                                information in Appendix an engineering, physical sciences, mathematics, or quality                                                                        2A-3, Non-mandatory assurance, score two (2) credits or, a bachelor degree from an                                                                    Guidance on the Education accredited institution score two (2) credits or if the degree is in                                                                and Experience of Lead engineering, physical sciences, mathematics, or quality                                                                            Auditors. NQA-l assurance, score three (3) credits; in addition score one (1)                                                                      SUPPLEMENT 2S-4 credit for a master degree in engineering, physical sciences,                                                                      (described below) meets the business management, or quality assurance from an accredited                                                                      intent of this section.
institution.
2.3.1.2 Experience (9 points maximum). Technical experience in engineering, manufacturing, construction, operation, or maintenance, score one (1) credit for each full year with a maximum of five (5) credits for this aspect of experience. If two (2) or more years of this experience have been in the nuclear field, score one (1) additional credit, or, if two (2) or more years of this experience have been in quality assurance, score two (2) additional credits, or, if two (2) or more years of this experience have been in auditing, score three (3) additional credits, or, if two (2) or more years of this experience have been in nuclear quality assurance, score three (3) additional credits, or, if two (2) or more years of this experience have been in nuclear quality assurance auditing, score four (4) additional credits.                                                            4                                                            +
2.3.1.3 Other Credentialsof ProfessionalCompetence (2 credits maximum). Certification of competency in engineering, science, or quality assurance specialties issued and approved by a State Agency, or National Professional or Technical Society, score two (2) credits.
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CRITERION2.2:            .        ...                    BASIC REQUIREMENT 2 ANSI N45.2-19711N18.7-1976                                                  NQA-1,1994              2    ~
2.3.1.4 Rights of Management (2 points maximum). The Lead Auditor's employer may grant up to two (2) credits for other performance factors applicable to auditing which may not be explicitly called out in this standard. Examples of these factors are leadership, sound judgment, maturity, analytical ability, tenacity, past performance, QA training courses.
2.3.2 Communication Skill.                                        3.1 Communication Skills The prospective Lead Auditors shall have the capability to        The prospective Lead Auditor shall have the capability to          Similar requirements.
communicate effectively, both written and oral.                    communicate effectively, both in writing and orally.
These skills shall be attested to in writing by the Lead Auditor's These skills shall be attested to in writing by the Lead Auditor's Similar requirements.
employer,                                                          employer.
2.3.3 Training                                                    3.2 Training Prospective Lead Auditors shall have training to the extent        Prospective Lead Auditors shall have training to the extent        Similar requirements.
necessary to assure their competence in auditing skills.          necessary to assure their competence in auditing skills.
Training in the following areas shall be given based upon          Training in the following areas shall be given based upon          Similar requirements.
management evaluation of the particular needs of each              management evaluation of the particular needs of each prospective Lead Auditor.                                          prospective Lead Auditor.
2.3.3.1 Knowledge and understanding of ANSI N45.2, its            3.2.1 Knowledge and understanding of this Part (Part I) and        N45.2.23 called out details associated Standards, particularly ANSI N45.2.12, and other        other nuclear-related codes, standards, regulations, and          met by the statement in nuclear-related codes, standards, regulations, regulatory guides,  regulatory guides, as applicable.                                  NQA- 1 regarding the as applicable,                                                                                                                        elements in NQA-1-1994, Part I.
2.3.3.2 General structure of quality assurance programs as a      3.2.2 General structure of quality assurance programs as a        N45.2.23 called out details whole and applicable elements such as organization; design        whole and applicable elements as defined in this Part (Part I). met by the statement in control; procurement document control; instructions;                                                                                  NQA- 1 regarding the procedures and drawings; document control; control of                                                                                elements in NQA-I-1994, purchased material equipment and services; identification and                                                                        Part I.
control of materials, parts and components; control of special processes; inspection; test control; control of measuring and test equipment; handling, storage and shipping; inspection, test, and operating status; nonconforming materials, parts, or components; corrective action; quality assurance records; audits; and quality information feedback.
2.3.3.3 Auditing techniques of examining, questioning,            3.2.3 Auditing techniques of examining, questioning,              Similar requirements.
evaluating and reporting; methods of identifying and following    evaluating, and reporting; methods of identifying and following up on corrective action items; and closing out audit findings,    up on corrective action items; and closing out audit findings.
2.3.3.4 Audit planning in the quality-related functions for the    3.2.4 Audit planning in the quality-related functions for the      NQA-1 adds "siting",
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* CRITERION 2              .BASIC                                        REQUIREMENT 2 ANSI N45*-1971/Nl8.7-1976                                                    NQA-1 1994 following activities: design, purchasing, fabrication, handling,    following activities: siting, designing, purchasing, fabricating,  "refueling" and shipping, storage, cleaning, erection, installation, inspection,    handling, shipping, receiving, storing, cleaning, erecting,        "decommissioning" as the testing, statistics, nondestructive examination, maintenance,      installing, inspecting, testing, operating, maintaining, repairing, standard addresses repair, operation, modification of nuclear facilities or associated refueling, modifying, and decommissioning of nuclear facilities    construction.
components and safety aspects of the nuclear facility,              or associated components, and safety aspects of the nuclear facility.
2.3.3.5 On-the-job training to include the elements of audit        3.2.5 On-the-job training to include applicable elements of the    Similar requirements.
activity as described in ANSI N45.2.12.                            audit program.
2.3.4 Audit Participation.                                          3.3 Audit Participation The prospective Lead Auditor shall have participated in a          The prospective Lead Auditor shall have participated in a          Similar requirements.
minimum of five (5) quality assurance audits within a period of    minimum of five (5) quality assurance audits within a period of time not to exceed three (3) years prior to the date of            time not to exceed 3 years prior to the date of qualification, one qualification, one audit of which shall be a nuclear quality        audit of which shall be a nuclear quality assurance audit within assurance audit within the year prior to his qualification,        the year prior to his qualification.
2.3.5 Examination.                                                  3.4 Examination The prospective Lead Auditor shall pass an examination which        The prospective Lead Auditor shall pass an examination which        Similar requirements.
shall evaluate his comprehension of and ability to apply the        shall evaluate his comprehension of and ability to apply the body of knowledge identified in paragraph 2.3.3.                    body of knowledge identified in para. 3.2 above.
The test may be oral, written, practical, or any combination of    The examination may be oral, written, practical, or any            Similar requirements.
the three types.                                                    combination of the three types.
The development and administration of the examination shall        The development and administration of the examination shall        Similar requirement.
be in accordance with Section 4 of this Standard.                  be in accordance with Section 5 of this Supplement.
: 3. MAINTENANCE OF QUALIFICATION                                    4 MAINTENANCE OF QUALIFICATION 3.1 General The maintenance of proficiency established in this Section shall apply to the Lead Auditor only.
3.2 Maintenance of Proficiency                                      4.1 Maintenance of Proficiency Lead Auditors shall maintain their proficiency through one or      Lead Auditors shall maintain their proficiency through one or      Similar requirement.
more of the following: regular and active participation in the      more of the following: regular and active participation in the audit process; review and study of codes, standards, procedures,    audit process; review and study of codes, standards, procedures, instructions, and other documents related to quality assurance      instructions, and other documents related to quality assurance programs and program auditing; participation in training            program and program auditing; or participation in training programs.                                                          program(s).
Based on management annual assessment, management may              Based on annual assessment, management may extend the              Similar requirement.
extend the qualification, require retraining, or require            qualification, require retraining, or require requalification.
requalification.
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                          *CRITERION 2              .BASIC                                  REURMN              2                        COMME~NTS ANSI N45.2-1971/N18.7-1976                                                NQA-1 1994 3.3 Requalification                                              4.2 Requalification Lead Auditors who fail to maintain their proficiency for a        Lead Auditors who fail to maintain their proficiency for a        Similar requirement.
period of two years or more shall require requalification.        period of 2 years or more shall require requalification.
Requalification shall include retraining in accordance with the  Requalification shall include retraining in accordance with the  Similar requirement.
requirements of paragraph 2.3.3, reexamination in accordance      requirements of para. 3.2 above, reexamination in accordance with paragraph 2.3.5 and participation as an Auditor in at least  with para. 3.4 above, and participation as an Auditor in at least one nuclear quality assurance audit.                              one nuclear quality assurance audit.
These evaluations shall be documented.                            These evaluations shall be documented.                            Similar requirement.
: 4. ADMINISTRATION                                                5 ADMINISTRATION 4.1 Organizational Responsibility                                5.1 Organizational Responsibility Training of auditors shall be the responsibility of the employer. Training of auditors shall be the responsibility of the employer. Similar requirement.
The responsible auditing organization shall select and assign    The responsible auditing organization shall select and assign    Similar requirement.
personnel who are independent of any direct responsibility for    personnel who are independent of any direct responsibility for performance of the activities which they will audit.              performance of the activities which they will audit.
The Lead Auditor shall, prior to commencing the audit, concur    The Lead Auditor shall, prior to commencing the audit, concur    Similar requirement.
that assigned personnel collectively have experience or training  that assigned personnel collectively have experience or training commensurate with the scope, complexity, or special nature of    commensurate with the scope, complexity, or special nature of the activities to be audited.                                    the activities to be audited.
4.2 Qualification Examination                                    5.2 Qualification Examination The development and administration of the examination for        The development and administration of the examination for a      Similar requirement.
Lead Auditor required by paragraph 2.3.5 is the responsibility    Lead Auditor required by para. 3.4 above is the responsibility of the employer,                                                  of the employer.
The employer may delegate this activity to an independent        The employer may delegate this activity to an independent        Similar requirement.
certifying agency, but shall retain responsibility for            certifying agency, but shall retain responsibility for conformance of the examination and its administration to this    conformance of the examination and its administration to this Standard.                                                        Part (Part 1).
Integrity of the examination shall be maintained by the          Integrity of the examination shall be maintained by the          Similar requirement.
employer or certifying agency through appropriate                employer or certifying agency through appropriate confidentiality of files and, where applicable, proctoring of    confidentiality of files and, where applicable, proctoring of examinations,                                                    examinations.
Copies of the objective evidence regarding the type(s) and        Copies of the objective evidence regarding the type(s) and        Similar requirement.
content of the examination(s) shall be retained by the employer  content of the examination(s) shall be retained by the employer in accordance with the requirements of Section 5.                in accordance with the requirements of Section 6 below.
: 5. RECORDS                                                        6 RECORDS 5.1 General                                                      6.1 General Records of personnel qualifications for Auditors and Lead        Records of personnel qualifications for Auditors and Lead        Similar requirement.
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CRITERION 2'.                                            BASC REQUIREMENT 2                                COMM.ENTS ANSI N45.2-19711N18.7-1976                                                NQA-1 1994 Auditors performing audits shall be established and maintained  Auditors performing audits shall be established and maintained by the employer,                                                by the employer.
5.2 Certification of Qualification                              6.2 Certification of Qualification Each Lead Auditor shall be certified by his employer as being  Each Lead Auditor shall be certified by his employer as being  Similar requirement.
qualified to lead audits.                                      qualified to lead audits.
This certification shall, as a minimum, document the following: This certification shall, as a minimum, document the following: Similar requirement.
a) Employer's name                                              (a) employer's name:
b) Lead Auditor's name                                          (b) Lead Auditor's name; c) Date of certification or recertification                    (c) date of certification or recertification; d) Basis for qualification (i.e., education, experience,        (d) basis of qualification (i.e., education, experience, communication skills, training, examination, etc.)              communication skills, training, examination, etc.);
e) Signature of employers' designated representative who is    (e) signature of employer's designated representative who is responsible for such certification                              responsible for such certification.
An example of a format for documenting the records of a Lead                                                                    Example not called out in Auditor is given in Appendix A                                                                                                  NQA-1 but exists in standard as Non-Mandatory Appendix 2A-3 5.3 Updating of Lead Auditors' Records                          6.3 Updating of Lead Auditors' Records Records for each Lead Auditor shall be maintained and updated  Records for each Lead Auditor shall be maintained and updated  Similar requirement.
annually.                                                      annually.
5.4 Record Retention Qualification records shall be retained as required by ANSI                                                                    Records requirements are N45.2.12 and maintained as required by ANSI N45.2.9.                                                                            addressed in Basic and Supplemental requirements (Section 17) of NQA                                                                                                                                1994.
SUPPLEMENT 2S-4                                                This Supplement of NQA-Supplementary Requirements for Personnel Indoctrination and    1-1994 is met in Training                                                        conjunction with applicable ANSI N 18.1 and/or ANS-3.1 standards.
I GENERAL This Supplement provides amplified requirements for the indoctrination and training of personnel performing or managing activities affecting quality.
It supplements the requirements of Basic Requirement 2 of this  NQA-1, SUPPLEMENT 10/28/2010                                                      Quality Assurance Program                                                    Page 24 of 26
 
              *CRITERION 2          *BASIC
                                      .                                REQUIREMENT 2.....                  *..........COMMENTS ANSI N45.2-19711N18.7-1976                                    NQA-l 1994                                        CON ENT Part (Part 1)and shall be used in conjunction with that Basic          2S-4, describes Requirement when and to the extent specified by the                    indoctrination and training organization invoking this Part (Part I).                              requirements that meet the intent of those stated in ANSI N45.2.23.
2 APPLICABILITY This Supplement applies to personnel performing or managing activities affecting quality. Personnel to be indoctrinated or trained shall be identified.
The extent of indoctrination and training shall be commensurate with the following:
(a) the scope, complexity, and nature of the activity; and (b) the education, experience, and proficiency of the person.
Activities affecting quality include siting, designing, purchasing, fabricating, handling, shipping, receiving, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, modifying, and decommissioning.
3 INDOCTRINATION Personnel shall be indoctrinated in the following subjects as they relate to a particular function:
(a) general criteria, including applicable codes, standards, and company procedures; (b) applicable quality assurance program elements; and (c) job responsibilities and authority.
4 TRAINING Training shall be provided, if needed, to:
(a) achieve initial proficiency; (b) maintain proficiency; and (c) adapt to changes in technology, methods, or job responsibilities.
5 RECORDS Records of the implementation of indoctrination and training may take the form of:
(a) attendance sheets; (b) training logs; or (c) personnel training records.
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CRITERION 3                                                BASIC REQUIREMENT -3:                                  COMMENTS ANSI N45.2-1971;:N45-.2.11-1974; N18.7-l.9.76                  .      .    .      .NQA-    1994 N45.2, &sect; 4.1 General N45.2 Measures shall be established and documented to assure      The design shall be defined, controlled, and verified. Applicable Similar requirements.
that the applicable specified design requirements, such as        design inputs shall be appropriately specified on a timely basis design bases, regulatory requirements, codes, and standards are    and correctly translated into design documents.
correctly translated into specifications, drawings, procedures, or instructions.
Design interfaces shall be identified and controlled.            Addressed in later parts of N45.2.11.
Design adequacy shall be verified by persons other than those    Addressed in later parts of who designed the item.                                            N45.2.1 1.
Design changes, including field changes, shall be governed by    Addressed in later parts of control measures commensurate with those applied to the          N45.2.11.
original design.
N45.2.11 &sect; 2 Program Requirements 2.1 Establishment and Documentation                                This subsection is covered by NQA-1, Requirements 1 and 2        NQA-1 does not repeat A quality assurance program for design shall be established and    and is not repeated in criterion 3.                              information from other documented to comply with the requirements of this Standard.                                                                        criteria as in the ANSI The program documents shall define the organizational                                                                                standards. Establishment structure within which the program is to be implemented, and                                                                        and documentation of a shall delineate the authority and responsibility of the persons                                                                      quality assurance program and organizations involved performing design activities                                                                              for design is addressed as affecting the quality of design.                                                                                                    NQA-1 1994, Basic The program documents shall identify the items and services                                                                          Requirements 1 and 2.
and the specific activities to which this standard is applied. The                                                                  Separate Tables for NQA- I design responsibilities and interfaces among the contributing                                                                        Basic Requirements I and 2 organizations, both internal and external, should be identified.                                                                    address establishment and Provisions should be made in the program for periodic audits,                                                                        documentation of a quality review, and evaluation of the effectiveness of the program in                                                                        assurance program for achieving quality objectives. Correction of deficiencies shall be                                                                    design.
an integral part of the program.
N45.2.11, &sect; 2.2 Program Procedures                                NOTE: Program procedure requirements have been                    NQA-1 does not repeat Procedures shall be employed to assure that design activities are  incorporated into multiple sections of NQA-I and are not          information from other carried out in a planned, controlled, orderly and correct manner. generally repeated for specific programs.                        criteria as in the ANSI Program procedures shall cover the following as applicable:        1. and 2. Responsibilities of organizations is addressed in Basic standards. Additional
: 1. Responsibilities of organizations involved in the program,      Requirement 1 and Supplement 1S-1.                                standards and NRC such as owner, A-E, NSSS supplier and other contractors.          3. Interface control is addressed in Supplements I S-1 and 3S-1. Regulatory Guides also
: 2. Responsibilities within design organizations.                  4. Document control is addressed in Basic Requirement 6 and      provide information on
: 3. Technical information exchanges across external and internal    Supplement 6S-1.                                                  many of these program interfaces.                                                        5. Maintenance of design documents is addressed under            requirements.
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CRITERION 3                                BASIC REQUIREMENT3OM                                        NT ANSI N45.2-19,74N .N4.2l-1974;N1.7-16                                        -      -N QAN 1994                          ____________
: 4. Document control including review, approval, release,          document control and retention is addressed in basic distribution, and revision,                                      requirement 17 and Supplement 17S-1.
: 5. Maintenance and retention of design documents.                6. Management review of the program is addressed under Basic
: 6. Management review of status and adequacy of program.          Requirement 2.
: 7. Necessary training of personnel performing activities covered  7. Training requirements are addressed in Basic Requirement 2.
by this standard.                                                8. Design input is addressed in Basic Requirement 3 and
: 8. Identifying appropriate design input.                          Supplement 3S-1.
: 9. Preparation of design documents.                              9. Preparation of design documents is addressed in Basic
: 10. Specifying quality levels, acceptance standards, and record  Requirement 3 and Supplement 3 S-1.
requirements.                                                    10. Specifying quality levels is addressed in Basic Requirement
: 11. Performance of design verifications.                          2. Specifying acceptance standards is addressed in Basic
: 12. Conducting audits of design activities, their reporting and  Requirements 3, 5, 10, and 11 with associated Supplements.
follow-up.                                                        Records requirements are addressed in Supplement 3S-1 and
: 13. Taking corrective action (see Section 9).                    Basic Requirement 17 and Supplement 17S-1.
: 14. Making experience reports available to cognizant design      11. Design verification is addressed in Supplement 3S-1.
personnel.                                                        12. Audits is addressed in Basic Requirement 18 and
: 15. Controlling design changes.                                  Supplement 18S-1.
: 16. Other procedures as required by this standard.                13. Corrective Action is addressed in Basic Requirements 15 and 16 and their associated Supplements.
: 14. Experience reports (operating experience included) are not addressed to any significant degree in NQA- 1 related to design.
: 15. Change control is addressed in Supplement 3S-1.
: 16. Other procedures may be addressed throughout NQA-1 in addition to Supplement 3S-1.
N45.2.11, &sect; 2.3 Factors Considered                                These factors are generally addressed as principles throughout  Not requirements.
Some of the factors to be considered in establishing the program  the standards of NQA-1.
include:                                                          A similar list of factors to consider is contained as
: 1. Nature of the organization such as the plant owner,            noumandatory guidance in Appendix 3A-1.
manufacturer, or architect-engineer, and the nature of the design interfaces among them.
: 2. Importance of the design activity to plant safety.
: 3. State of the art such as experimental, developmental, or standard design.
: 4. Nature of design activity such as conceptual, preliminary, detailed design, or field engineering.
N45.2.11 &sect; I Introduction                                        See NQA-l-1994, Part 1, Introduction, for Purpose and 1.1 Scope                                                        Applicability.
This standard provides requirements and guidance for a quality assurance program for the design of nuclear power plant 10/28/2010                                                                Design Control                                                        Page 2 of 25
 
                          ... CRITERION.3...                                      BASIC REQUIREMENT 3                                  COMMENTS ANSIUN45.2-1971; N45.2.11-1974; N18047-.6."                                      NQA-1 1994            "_._ ...... _  __
structures, systems and components whose satisfactory and reliable performance is required:
: 1. To prevent accidents that could cause undue risk to the health and safety of the public; or
: 2. To mitigate the consequences of such accidents if they were to occur.
SUPPLEMENT 3S-1 SUPPLEMENTARY REQUIREMENTS FOR DESIGN CONTROL 1  GENERAL This Supplement provides amplified requirements for design control.
N45.2.11 &sect; 1.1 - The requirements of this standard may also be    It supplements the requirements of Basic Requirement 3 of this  Similar statement regarding extended to other structures, systems and components in whole    Part and shall be used in conjunction with that Basic          use to the extent specified or in part as specified by the purchaser.                        Requirement when and to the extent specified by the            by the purchaser This standard covers activities which affect the final design. organization invoking this Part.                                (organization invoking this This standard is intended to be used in conjunction with ANSI                                                                    Part)
N45.2.
N45.2.11 &sect; 1.2 Applicability This standard applies to the plant owner, nuclear steam supply    See NQA-1-1994, Part 1, Introduction, for Applicability and    Similar applicability system (NSSS) designer, architect engineer or plant designer,    Responsibility.                                                established between the and other organizations participating in design activities                                                                        standards.
affecting quality of items covered by this standard. The extent to which the individual sections and elements of this standard are applied will depend upon factors such as the nature and scope of the work to be performed and the importance of the structures, systems and components to safe plant operation.
The ASME Boiler and Pressure Vessel Code (Hereafter referred to as the Code) as well as other ANSI Standards, has been considered in the development of this standard, and this standard is intended to be compatible with their requirements.
However, this standard does not apply to activities covered by Section III Division I and 2 and Section XI of the Code for those activities covered by the Code.
N45.2.11 &sect; 1.3 Responsibility It is the responsibility of the plant owner to provide for the    See NQA-I-1994, Part I, Introduction, for Applicability and    Similar responsibilities establishment and execution of a quality assurance program for    Responsibility.                                                exist between the standards.
the plant design consistent with the provisions of this standard.
The plant owner may delegate to other organizations the work of establishing and executing the quality assurance program, or 10/28/2010                                                              Design Control                                                            Page 3 of 25
 
                    ........ CRITERION 3                                              BASIC REQUIREMENT 3                                      COMMENTS ANSI N4$.2-1971;.4..117;N8717                                                        NQk.A-i* 1904                          __________
any part thereof, but shall retain responsibility for overall program effectiveness. It is the responsibility of the plant owner and other organizations invoking this standard to identify the structures, systems and components, and to specify the extent to which the provisions of this standard apply to such structures, systems and components. In no way shall the program operate to diminish the responsibility of any contractor for the quality of services furnished.
N45.2.11 &sect; 1.4 Definitions The following definitions are provided to assure a uniform          Note that the below definitions are copied from the introduction  Definitions are contained in understanding of select terms as they are used in this standard. to Part I of NQA- 1.                                              NQA-1-1994, Part I, Introduction, &sect; 4 Terms and Definitions Design - Technical and management processes which                  Design process - technical and management processes that          Similar requirement.
commence with identification of design input and which lead to      commence with identification of design input and that lead to and include the issuance of design output documents.                and include the issuance of design output documents Design Input - Those criteria, parameters, bases or other design    Design input - those criteria, parameters, bases, or other design Similar requirement.
requirements upon which detailed final design is based.            requirements upon which detailed final design is based Design Output - Documents such as drawings, specifications          Design output - drawings, specifications, and other documents    Similar requirement and other documents defining technical requirements of              used to define technical requirements of structures, systems, structures, systems and components as delineated in Section 4.      components, and computer programs External Design Interface - Relationship between design                                                                              Design interface is not groups from different companies. Examples are the interfaces                                                                          defined in NQA-1, but between the plant owner and the architect engineer or the plant                                                                      controls for interface are owner and the NSSS supplier, or the architect engineer and the                                                                        described in Supplement NSSS supplier.                                                                                                                        3S-1, &sect; 6 Interface Control Final Design - Approved design output documents and                Design, final - approved design output documents and              Similar requirement approved changes thereto.                                          approved changes thereto Internal Design Interface - Relationship between design                                                                              Design interface is not groups or organizations within a company.                                                                                            defined in NQA-1, but controls for interface are described in Supplement 3S-1, &sect; 6 Interface Control Procedures - A document that specifies or describes how an          Procedure - a document that specifies or describes how an        Similar requirement activity is to be performed. It may include methods to be          activity is to be performed employed, equipment or materials to be used and sequence of operations.
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CRITERION 3                                                BAIIEQIEET3 ANSI N45.2-1,971; .N45.2.ll-1974;.N18.7-1976                    .NQA71                      1994 Design change - any revision or alteration of the technical      New requirement.
requirements defined by approved and issued design output documents and approved and issued changes thereto N45.2.11, &sect; 1.5 Referenced Documents                                                                                              Applicability of other Other documents that are required to be included as part of this                                                                  standards and Regulatory standard will be identified at the point of reference and                                                                          Guides is addressed in the described in Section 12 of this standard. The issue or edition of                                                                  QAPD.
the referenced document that is required will be specified either at the point of reference or in Section 12 of this standard.
NRC Reg. Guide 1.64, Reg. Position C.1 indicates that the specific acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations where appropriate.
N45.2.11, &sect; 3 Design Input Requirements                          2 DESIGN INPUT 3.1 General                                                      Applicable design inputs, such as design bases, performance      Similar requirement.
Applicable design inputs, such as design bases, regulatory        requirements, regulatory requirements, codes, and standards, requirements, codes and standards, shall be identified,          shall be identified and documented, and their selection reviewed documented and their selection reviewed and approved,            and approved by the responsible design organization.
The design input should be specified on a timely basis and to    The design input shall be specified and approved on a timely    Similar requirement.
the level of detail necessary to permit the design activity to be basis and to the level of detail necessary to permit the design carried out in a correct manner and to provide a consistent basis activity to be carried out in a correct manner and to provide a for making design decisions, accomplishing design verification    consistent basis for making design decisions, accomplishing measures, and evaluating design changes.                          design verification measures, and evaluating design changes.
N45.2 Changes or deviations from specified design                Changes from approved design inputs, including the reason for    Similar requirement.
requirements or quality standards shall be identified,            the changes, shall be identified, approved, documented, and documented, and controlled.                                      controlled.
N45.2.11 &sect; 3.1, &#xb6; 1 Changes from specified design inputs including the reasons for the changes shall be identified, approved, documented and controlled.
N45.2.11 &sect; 3.2 Requirements                                                                                                        The detailed list of design The design input shall include but is not limited to the                                                                          input requirements has been following, where applicable:                                                                                                      moved to (and expounded
: 1. Basic functions of each structure, system and component.                                                                        upon as nonmandatory
: 2. Performance requirements such as capacity, rating, system                                                                      guidance in) NQA-1, output.                                                                                                                            Appendix 3A-1.
: 3. Codes, standards, and regulatory requirements including the applicable issue and/or addenda.
: 4. Design conditions such as pressure, temperature, fluid chemistry and voltage.
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CRITERION 3                                      BASIC  'RQ    *IM.ENT 3        COM.ENTS ANSI N45.2-1971*;N45.2.11-1974; NI8.7-1976 .                            NQA-l,1994        _____.. _______        ,__......
: 5. Loads such as seismic, wind, thermal and dynamic.
: 6. Environmental conditions anticipated during storage, construction and operation such as pressure, temperature, humidity, corrosiveness, site elevation, wind direction, nuclear radiation, electromagnetic radiation and duration of exposure.
: 7. Interface requirements including definition of the functional and physical interfaces involving structures, systems and components.
: 8. Material requirements including such items as compatibility, electrical insulation properties, protective coating and corrosion resistance.
: 9. Mechanical requirements such as vibration, stress, shock and reaction forces.
: 10. Structural requirements covering such items as equipment foundations and pipe supports.
: 11. Hydraulic requirements such as pump net positive suction heads (NPSH), allowable pressure drops, and allowable fluid velocities.
: 12. Chemistry requirements such as provisions for sampling and limitations on water chemistry.
: 13. Electrical requirements such as source of power, voltage, raceway requirements, electrical insulation and motor requirements.
: 14. Layout and arrangement requirements.
: 15. Operational requirements under various conditions, such as plant startup, normal plant operation, plant shutdown, plant emergency, operation, special or infrequent operation, and system abnormal or emergency operation.
: 16. Instrumentation and control requirements including indicating instruments, controls and alarms required for operation, testing, and maintenance. Other requirements such as the type of instrument, installed spares, range of measurement, and location of indication should also be included.
: 17. Access and administrative control requirements for plant security.
: 18. Redundancy, diversity and separation requirements of structures, systems and components.
: 19. Failure effects requirements of structures, systems and components, including a definition of those events and Page 6 of 25 Design Control 10/28/2010 10/28/2010                                                        Design Control                                    Page 6 of 25
 
CRITERION 3              "                                BASIC REQUIREMEN 3                                      COMMEN TS ANSI N45.2,1971; N45.2.11-1974';N18.7-19'76 '                                      NQA-1.1994,,'      ".    '      "_..____                      ._'__"""
accidents which they must be designed to withstand.
: 20. Test requirements including in-plant tests and the conditions under which they will be performed.
: 21. Accessibility, maintenance, repair and inservice inspection requirements for the plant including the conditions under which these will be performed.
: 22. Personnel requirements and limitations including the qualification and number of personnel available for plant operation, maintenance, testing and inspection and permissible personnel radiation exposures for specified areas and conditions.
: 23. Transportability requirements such as size and shipping weight, limitations, I.C.C. regulations.
: 24. Fire protection or resistance requirements.
: 25. Handling, storage and shipping requirements.
: 26. Other requirements to prevent undue risk to the health and safety of the public.
: 27. Materials, processes, parts and equipment suitable for application.
: 28. Safety requirements for preventing personnel injury including such items as radiation hazards, restricting the use of dangerous materials, escape provisions from enclosures, and grounding of electrical systems.
N45.2.11, &sect; 4 Design Process                                      3 DESIGN PROCESS                                                    Similar requirement.
Design activities shall be prescribed and accomplished in          The responsible design organization shall prescribe and accordance with procedures of a type sufficient to assure that    document the design activities on a timely basis and to the level applicable design inputs are correctly translated into            of detail necessary to permit the design process to be carried out specifications, drawings, procedures or instructions,            in a correct manner, and to permit verification that the design N45.2.11 &sect; 4.1, &#xb6; 2 The design activities may be prescribed in    meets requirements. Design documents shall be adequate to job specifications, work-instructions, planning sheets, procedure  support facility design, construction, and operation.
manuals, test procedures, or any other type of written form, which provides adequate control and permits reviewing, checking or verifying the results of the activity, by personnel who are experienced in the subject activity.
ANSI N45.2 These measures shall include provisions to assure      Appropriate quality standards shall be identified and              Similar requirement.
that appropriate quality standards are specified and included or  documented, and their selection reviewed and approved.
referenced in design documents.
N45.2.11 &sect; 4.1, &#xb6; 1 Appropriate quality standards shall be identified, documented and their selection reviewed and 10/28/2010                                                              Design Control                                                              Page 7 of 25
 
CRITERION 3                '                                  BASIC:REQURMENT 3                            "MENTS. C.
ANSI N45.2-19?1; N45:2..1I-19-74; N18.7-1976                                            NQA-1 1994            ...            .. _...._.    ,..,...  ._.
approved.
N45.2.11 &sect; 4.1, &#xb6; 1 Changes from specified quality standards        Changes from specified quality standards, including the reasons Similar requirement.
including reasons for the changes shall be identified, approved,    for the changes, shall be identified, approved, documented, and documented and controlled.                                          controlled.
N45.2 Measures shall also be established for the selection and      Design methods, materials, parts, equipment, and processes that Similar requirement.
review for suitability of application of materials, parts,          are essential to the function of the structure, system, or equipment, and processes that are essential to the function of      component shall be selected and reviewed for suitability of the structure, system, or component.                                application.
Applicable information derived from experience, as set forth in Reference ANSI N45.2.11, reports or other documentation, shall be made available to      &sect; 2.2, Item 14 regarding cognizant design personnel.                                    experience.
N45.2.11 &sect; 4.1, &#xb6; 3 Methods shall provide for relating the final    The final design (approved design output documents and          Similar requirement. New design back to the source of design input. This traceability shall  approved changes thereto) shall:                                information regarding be documented in accordance with the requirements of Section        (a) be relatable to the design input by documentation in        assemblies and component
: 10.                                                                sufficient detail to permit design verification; and            parts.
N45.2.11 &sect; 4.1, &#xb6; 4 The design activities shall be documented in    (b) identify assemblies and/or components that are part of the sufficient detail to permit verification and auditing as required  item being designed. When such an assembly or component part by this standard.                                                  is a commercial grade item that, prior to its installation, is modified or selected by special inspection and/or testing to requirements that are more restrictive than the Supplier's published product description, the component part shall be represented as different from the commercial grade item in a manner traceable to a documented definition of the difference.
N45.2.11, &sect; 4.2, Design Analyses                                    3.1 Design Analyses Design analyses such as physics, stress, thermal, hydraulic and    Design analyses shall be performed in a planned, controlled,    Similar requirement.
accident, shall be performed in a planned, controlled and correct  and documented manner.                                          Examples removed from manner.                                                                                                                            NQA-1.
N45.2.11, &sect; 4.2, &#xb6; 2 Design analysis shall be legible and be in a  Design analysis documents shall be legible and in a form        Similar requirement.
form suitable for reproduction, filing and retrieving,              suitable for reproduction, filing, and retrieval.
N45.2 Design control measures shall provide for design              They shall be sufficiently detailed as to purpose, method,      Similar requirement.
analyses, such as physics, stress, thermal, hydraulic, accident;    assumptions, design input, references, and units such that a    Examples removed from compatibility of materials; accessibility for inservice inspection, person technically qualified in the subject can review and      NQA-1.
maintenance, and repair; and delineation of acceptance criteria    understand the analyses and verify the adequacy of the results for inspections and tests.                                          without recourse to the originator.
N45.2.11, &sect; 4.2, &#xb6; 2 Analyses shall be sufficiently detailed as to purpose, method, assumptions, design input, references and units such that a person technically qualified in the subject can review and understand the analyses and verify the adequacy of the results without recourse to the originator.
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CRITERION. 3                                                BA.SIC REQU        EMENT 3'                            COM ENT'S ANSI N45.,21971iiN45.2.11-1974; N,18.7-19760.                                        NQA-1 1994..,_                                  ,_._...............
N45.2.1 1, &sect; 4.2, &#xb6; 2 Calculations shall be identified by subject Calculations shall be identifiable by subject (including structure, Similar requirement.
(including structure, system, or component to which the          system, or component to which the calculation applies),
calculation applies) originator, reviewer and date or by other    originator, reviewer, and date; or by other data such that the data such that the calculations are retrievable,                  calculations are retrievable.
(a) Computer programs may be utilized for design analysis          New requirement.
without individual verification of the program for each            NQA-1 provides additional application provided:                                              controls on use of computer programs for design analyses.
(1) the computer program has been verified to show that it          New requirement.
produces correct solutions for the encoded mathematical model within defined limits for each parameter employed; and (2) the encoded mathematical model has been shown to produce        New requirement.
a valid solution to the physical problem associated with the particular application.
Computer programs shall be controlled to assure that changes        New requirement.
are documented and approved by authorized personnel.
Where changes to previously verified computer programs are          New requirement.
made, verification shall be required for the change, including evaluation of the effects of these changes on (1) and (2) above.
N45.2.11, &sect; 4.2, &#xb6; 2 Procedures shall include requirements for:  (b) Documentation of design analyses shall include (1) through      Similar requirement. For
: 1. Identifying documents to permit ready reference and          (6) below:                                                          N45.2.1 1, item 1, the retrieval.                                                        (1) definition of the objective of the analyses;                    identification of documents
: 2. Defining the objective of the analyses.                        (2) definition of design inputs and their sources;                  is addressed under NQA-1,
: 3. Definition of design inputs and their sources.                (3) results of literature searches or other applicable background  Supplement 17S-1.
: 4. Documenting the results of literature searches or other        data; applicable background data.                                      (4) identification of assumptions and indication of those that
: 5. Documenting assumptions, and identifying those assumptions    must be verified as the design proceeds; that must be verified as the design proceeds.                    (5) identification of any computer calculation, including
: 6. Identification of computer calculations, including computer    computer type, computer program (e.g., name), revision type, code or programming, inputs and outputs.                    identification, inputs, outputs, evidence of or reference to
: 7. Review and approval,                                          computer program verification, and the bases (or reference thereto) supporting application of the computer program to the specific physical problem; (6) review and approval.
N45.2.11, &sect; 4.3 Drawings                                                                                                              Requirements for control of documents (i.e. drawings) are addressed as NQA 1 1994, Basic Requirement 6.
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                        .CRITERION3                          BASICREQUIREMEN    3              COMMENTS ANSI N45.2-1971; N45.2,11'1974; N18.7-1976,.                . NQA-1 1994  _____,___,..,. "    ,,    ,,..
A separate table for NQA- 1 Basic Requirement 6 addresses requirements for control of documents.
Specific information regarding drawings is contained as non-mandatory guidance in NQA-1, Appendix 3A-1, &sect; 3(a).
N45.2.11, &sect; 4.4 Specifications                                                      Requirements for control of documents (i.e.
specifications) are addressed as NQA 1 1994, Basic Requirement 6. A separate table for NQA- 1 Basic Requirement 6 addresses requirements for control of documents.
Specific information regarding specifications is contained as non-mandatory guidance in NQA-1, Appendix 3A-1, &sect; 3(b).
N45.2.11, &sect; 4.5 Other Design Documents                                              Requirements for control of procedures are addressed as NQA 1 1994, Basic Requirement 5. A separate table for NQA- 1 Basic Requirement 5 addresses requirements for control of procedures. Specific information regarding other design documents is contained as non-mandatory guidance in NQA-1, Appendix 3A-1, &sect; 3(b). NQA-I, Appendix 10/28/2010                                          Design Control                                  Page 10 of 25
 
CRITERION 3                                                BASIC REQUIREMENT 3                                          MET ANSI N45.2407;!WN45.2.lf-1974; N18.7-1976                                            NQA-1 1994                      '"__" ____,          _    -_ ______
3A-1, &sect; 3(c) provides guidance on information that design documents should include to support facility operation.
N45.2 &sect; 4.3 Design Verification                                  4 DESIGN VERIFICATION N45.2.11 &sect; 6 Design Verification N45.2 Design control measures shall be applied to verify or      Design control measures shall be applied to verify the adequacy  Similar requirement.
check the adequacy of design, such as by the performance of      of design, such as by one or more of the following: the design reviews, by the use of alternate or simplified            performance of design reviews, the use of alternate calculations, calculational methods, or by the performance of a suitable        or the performance of qualification tests.
testing program.
N45.2.11, &sect; 6.1 General Measures shall be applied to verify the adequacy of design.
Design verification is the process of reviewing, confirming, or substantiating the design by one or more methods to provide assurance that the design meets the specified design inputs.
Verification of computer programs shall include appropriate      New requirement.
testing.
N45.2 The responsible design organization shall identify the      The responsible design organization shall identify and            Similar requirement.
particular design verification methods utilized.                  document the particular design verification method(s) used.
The results of design verification shall be clearly documented    New requirement.
with the identification of the verifier clearly indicated.
N45.2 The verifying or checking process shall be performed by    Design verification shall be performed by any competent          Similar requirement.
individuals or groups other than those who perform the original  individual(s) or group(s) other than those who performed the design but who may be from the same organization.                original design but who may be from the same organization.
N45.2.11, &sect; 6.1, &#xb6; 2 Design verification shall be performed by any competent individuals or groups other than those who performed the original design but who may be from the same organization.
N45.2.11, &sect; 6.1, &#xb6; 2 This verification may be performed by the    This verification may be performed by the originator's            NRC Reg. Guide 1.64 has originator's supervisor provided the supervisor did not specify a supervisor, provided the supervisor did not specify a singular    been withdrawn with singular design approach, or rule out certain design              design approach or rule out certain design considerations and    endorsement of NQA- 1 considerations and did not establish the design inputs used in    did not establish the design inputs used in the design or,        through NRC SER on NEI the design, or if the supervisor is the only individual in the    provided the supervisor is the only individual in the            06-14A, Rev. 7, August organization competent to perform the verification,              organization competent to perform the verification.              2010 (ML101800497).
NRC Reg, Guide 1.64, Reg. Position C.2 states to replace the above sentence with the following: "The duties of a 'supervisor' and the relationship with subordinates varies widely in different 10/28/2010                                                                Design Control                                                            Page I11 of 25
 
CRITERIO&#xfd;1N  j1 3.                                          BASIC REQUIRE9ME-NT3                                      COMMENTS ANSI N45.2-1 74; N52l-94N1.176                          jNQA-1                                1994                          ___________
organizations. Regardless of their title, individuals performing design verification should not (1) have immediate supervisory responsibility for the individual performing the design, (2) have specified a singular design approach, (3) have ruled out certain design considerations, or (4) have established the design inputs for the particular design aspect being verified. While design verification by the designer's immediate supervisor is encouraged, it should not be construed that such verification constitutes the required independent design verification, nor should the independent design verification be construed to dilute or replace the clear responsibility of supervisors for the quality of work performed under their supervision."
N45.2.1 1, &sect; 6.1, &#xb6; 2 Cursory supervisory reviews do not satisfy    Cursory supervisory reviews do not satisfy the intent of this      Similar requirement.
the intent of this standard.                                        Part.
N45.2 The depth of review can range from a detailed check of                                                                            Design review is addressed the complete design to a limited check of such things as the                                                                            in Section 3.1 of the QAPD.
design approach and the results obtained in the original design.
N45.2.11, &sect; 6.1, &#xb6; 2 Design verification may vary from spot checking of calculations to actual tests in the field.
Verification shall be performed in a timely manner.                New requirement.
Design verification, for the level of design activity              New requirement.
accomplished, shall be performed prior to release for procurement, manufacture, construction, or release to another organization for use in other design activities except in those cases where this timing cannot be met, such as when insufficient data exist. In those cases, the unverified portion of the design shall be identified and controlled.
In all cases the design verification shall be completed prior to    New requirement.
relying upon the component, system, structure, or computer program to perform its function.
N45.2.11, &sect; 6.2 Extent                                              4.1 Extent of Design Verification The extent of the design verification required is a function of    The extent of the design verification required is a function of    Similar requirement.
the importance to safety of the item under consideration, the      the importance to safety, the complexity of the design, the complexity of the design, the degree of standardization, the        degree of standardization, the state of the art, and the similarity state-of-the-art, and the similarity with previously proven        with previously proven designs.
designs.                                                          I N45.2.11, &sect; 6.2, &#xb6; 1 Where the design of a particular structure,    Where the design has been subjected to a verification process in    Similar requirement.
system, or component for a particular nuclear power plant has      accordance with this Part, the verification process need not be been subjected to a verification process in accordance with this    duplicated for identical designs.
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ANICRITE"RION!3                                                            BASIC!REQUIREMENT 3                                      COMMENTS ANS!N45.2-1971; N475,2.-!974; NI8.7-19,6,                ".        ., ....            .. _A . 1994..
                                                                                                            ..                                              _=.......
standard, the verification process need not be duplicated for identical designs.
N45.2 Regardless of the degree of standardization or similarity      However, the applicability of standardized or previously proven Similar requirement.
to previously proven designs, the applicability of standardized      designs, with respect to meeting pertinent design inputs, shall be or previously proven designs with respect to meeting pertinent      verified for each application.
design requirements shall be verified for each application.
N45.2.11, &sect; 6.2, &#xb6; 1 However, the applicability of standardized or previously proven designs, with respect to meeting pertinent design inputs, including environmental conditions, shall be verified for each application.
N45.2.11, &sect; 6.2, &#xb6; 1                                                Known problems affecting the standard or previously proven          Similar requirement.
However, known problems affecting the standardized design            designs and their effects on other features shall be considered.
and their effects on other features shall be considered.
N45.2.1 1, &sect; 6.2,&#xb6; 1                                                The original design and associated verification measures shall      Similar requirement.
The original design and associated verification measures shall,      be adequately documented and referenced in the files of however, be adequately documented and referenced in the files        subsequent application of the design.
of subsequent application of the design.
N45.2.11, &sect; 6.2, &#xb6; 2                                                Where changes to previously verified designs have been made,        Similar requirement, but Where changes to previously verified designs have been made,        design verification shall be required for the changes, including    added clarification to check design verification shall be required for the changes, including    evaluation of the effects of those changes on the overall design    impacts from a change on evaluation of the effects of those changes on the overall design. and on any design analyses upon which the design is based that      other design analyses.
are affected by the change to previously verified design.
N45.2.11, &sect; 6.3 Methods                                              4.2 Methods N45.2 Verifying or checking should consist of, as a minimum,        Acceptable verification methods include, but are not limited to,    Similar requirement.
reviewing the design, spot-checking the calculations or              any one or a combination of the following: design reviews, analyses, and assessing the results against the original design      alternate calculations, and qualification testing.
bases and functional requirements.
N45.2.11, &sect; 6.3, &#xb6; 1 The responsible design organization shall identify and document the particular design verification methods to be used.
Acceptable verification methods include but are not limited to:
: 1. Design reviews-
: 2. Alternate calculations-
: 3. Qualification testing-N45.2.11, &sect; 6.3.1 Design Reviews                                    4.2.1 Design Reviews N45.2 There are many ways of performing design reviews, and          These are critical reviews to provide assurance that the final      Not a requirement; various depths of reviews may be required depending upon the        design is correct and satisfactory.                                  introductory statement.
importance and complexity of the design being reviewed, the                                                                            I 10/28/2010                                                                    Design Control                                                            Page 13 of 25
 
CRITERION 3                                    .BASIC              REQUIREMENT 3                              COMMENTS ANSI.N45.2-!971;..N45.2.11-1974;      N18. 7-1976                                    NQA-1 1994 degree of standardization, the state-of-the-art, and the similarity with previously proven designs.
N45.2 The methods for design review can range from a formalized, multi-organization review to an informal, single-person review.
N45.2.11, &sect; 6.3.1, &#xb6; 1 Design reviews are critical reviews to provide assurance that design documents such as drawings, calculations, analyses or specifications are correct and satisfactory. Design reviews can range from multi-organization reviews to single-person reviews.
The depth of review can range from a detailed check of the complete design to a limited check of such things as the design approach and the results obtained. The results of the review shall be documented and measures taken to ensure that the findings are implemented. Whether the review is conducted by one individual or a multi-organization there are a number of basic questions that shall be addressed such as:
N45.2.11, &sect; 6.3.1 - Lists the following 19 items to consider in    Where applicable, (a) through (f) below shall be addressed. Similar requirement.
the design review.
: 1. Were the inputs correctly selected and incorporated into        (a) Were the design inputs correctly selected?                Similar requirement.
design? (See paragraph 3.2).
: 2. Are assumptions necessary to perform the design activity        (b) Are assumptions necessary to perform the design activity  Similar requirement.
adequately described and reasonable, where necessary, are the      adequately described and reasonable?
assumptions identified for subsequent re-verifications when the    Where necessary, are the assumptions identified for subsequent detailed design activities are completed?                          reverifications when the detailed design activities are completed?
: 7. Was an appropriate design method used?                          (c) Was an appropriate design method used?                    Similar requirement.
: 3. Are the appropriate quality and quality assurance                (d) Were the design inputs correctly incorporated into the    Multiple questions in requirements specified?                                            design?                                                        N45.2.1 1 related to
: 4. Are the applicable codes, standards and regulatory                                                                              incorporating design inputs requirements including issue and addenda properly identified                                                                      into the design combined and are their requirements for design met?                                                                                        into one question on design
: 5. Have applicable construction and operating experience been                                                                      inputs for NQA- 1-1994.
considered?
: 9. Are the specified parts, equipment, and processes suitable for the required application?
: 10. Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed?
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CRITERION 3                                                BASI    REQUE            NT 3Y                      COMMENTS ANSI N45.2.-971; N452111974 ii              NX18.7-1976                                  NQ"&- 1994
: 11. Have adequate Maintenance features and requirements been specified?
: 12. Are accessibility and other design provisions adequate for performance of needed maintenance and repair?
: 13. Has adequate accessibility been provided to perform the in-service inspection expected to be required during the plant life?
: 14. Has the design properly, considered radiation exposure to the public and plant personnel?
: 15. Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?
: 16. Have adequate preoperational and subsequent periodic test requirements been appropriately specified?
: 17. Are adequate handling, storage, cleaning and shipping requirements specified?
: 8. Is the output reasonable compared to inputs?                  (e) Is the design output reasonable compared to design inputs?  Similar requirement.
: 6. Have the design interface requirements been satisfied?        (f) Are the necessary design input and verification requirements Similar requirement.
for interfacing organizations specified in the design documents or in supporting procedures or instructions?
: 18. Are adequate identification requirements specified?                                                                          N45.2.11 identifies these
: 19. Are requirements for record preparation review, approval,                                                                    two items regarding design retention, etc., adequately specified?                                                                                            reviews. These are covered in NQA- 1 under Requirements 8 and 17 along with associated Supplements.
N45.2.11, &sect; 6.3.2 Alternate Calculations                          4.2.2 Alternate Calculations Verification of some types of calculations or analyses may be    These are calculations or analyses that are made with alternate  Similar requirement.
achieved by comparison with alternate methods of calculation      methods to verify correctness of the original calculations or or analyses. This shall be performed by a person or persons      analyses. The appropriateness of assumptions, input data used, other than those who performed the original calculation. Where    and the computer program or other calculation method used alternate calculations are performed to verify the correctness of shall also be reviewed.
the original calculation a review shall also be performed to address the appropriateness of assumptions, input data, and the code.or other calculation method used. The alternate method used for comparison may be a more simplified approach or less rigorous, such as when a hand calculation is used to check the computer code output. Although the simplified or less rigorous method may not exactly check the original calculation or 10/28/2010                                                                Design Control                                                          Page 15 of 25
 
CRITERION3                                                      BASIC' REUIREMENT 3                                  O lE        S ANSI N45.2-1971; N45.2.11*        974;"N18.7-1976          ,QA..                                    1J99 analysis, it must provide results consistent with the original calculation or analyses.
N45.2.11, &sect; 6.3.3 Qualification Testing                                4.2.3 Qualification Tests N45.2.11, &sect; 6.3.3, &#xb6; 1 Design verification for some designs or                                                                          Not a requirement.
specific design features can be achieved by suitable qualification testing of a prototype or initial production unit.
N45.2 In those cases where the adequacy of a design is to be            Where design adequacy is to be verified by qualification tests,  Similar requirement.
verified by tests, the testing shall be identified.                    the tests shall be identified. The test configuration shall be N45.2.11, &sect; 6.3.3, &#xb6; 2 In those cases where the adequacy of a          clearly defined and documented.
design is to be verified by a qualification test, the testing shall be identified and documented.
N45.2 Testing shall demonstrate adequacy of performance                Testing shall demonstrate adequacy of performance under          Similar requirement.
under the most adverse design conditions.                              conditions that simulate the most adverse design conditions.
N45.2.11, &sect; 6.3.3, &#xb6; 2 Testing shall demonstrate adequacy of performance under the most adverse design conditions.
N45.2 Operating modes and environmental conditions in which            Operating modes and environmental conditions in which the        Similar requirement.
the item must perform satisfactorily shall be considered in            item must perform satisfactorily shall be considered in determining the most adverse conditions.                                determining the most adverse conditions.
N45.2.11, &sect; 6.3.3, &#xb6; 2 All pertinent operating modes shall be considered in determining these design conditions where it is intended that the test program confirm the adequacy of the overall design, N45.2.11, &sect; 6.3.3, &#xb6; 2 Where the test is only intended to verify a      Where the test is intended to verify only specific design        Similar requirement.
specific design feature, the other features of the design shall be      features, the other features of the design shall be verified by  Example from N45.2.11 is verified by other means. For example, it may be most effective          other means.                                                    eliminated in NQA-1.
to verify that an instrumentation cabinet is designed to withstand the maximum earthquake-caused vibratory motions by actually subjecting the cabinet and its associated components to shaker tests which correspond to these vibratory motions.
The shaker tests will not, however, verify that the circuitry is designed correctly, or that the component in the cabinet will perform its intended function. Other tests or verification means are required to confirm that remaining design functions are adequately performed by the instrumentation and that those components perform the intended functions for the varying design conditions to which they are subjected.
N45.2.1, &sect; 6.3.3, &#xb6; 3 Qualification testing shall be performed in      Test results shall be documented and evaluated by the            Similar requirement for accordance with written test procedures which incorporate or            responsible design organization to assure that test requirements documenting and reference the requirements and acceptance limits contained in          have been met.                                                  evaluating test results.
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CRTERION 3                                            .. ,BASIC REQUIREMNT 3 .                                  COMMENTS ANSI N45.-91 N451.2.1-97 N18.7-1076                                                  NQA-1 1994 applicable design documents. The test procedures shall include provisions for assuring that prerequisites for the given test have been met, that adequate instrumentation of the required range and accuracy is available and used, and that necessary monitoring is performed. Prerequisites include such items as calibrated instrumentation, appropriate equipment, trained personnel, condition of test equipment and the item to be tested, suitable environmental conditions and provisions for data acquisition. Test results shall be documented and evaluated by the responsible designer to assure that test requirements have been satisfied.
N45.2 If testing indicates that modifications to the item are      If qualification testing indicates that modifications to the item  Similar requirement.
necessary to obtain acceptable performance, the item shall be      are necessary to obtain acceptable performance, the modified and retested as necessary to assure satisfactory          modification shall be documented and the item modified and performance.                                                      retested or otherwise verified to assure satisfactory N45.2.1, &sect; 6.3.3, &#xb6; 4 If testing indicates that modifications to  performance.
the item are necessary to obtain acceptable performance, the modification shall be documented and the item modified and retested or otherwise verified to assure satisfactory performance.
N45.2.1, &sect; 6.3.3, &#xb6; 4 When tests are being performed on models    When tests are being performed on models or mockups, scaling      Similar requirement.
or mock-ups, scaling laws shall be established and verified. The  laws shall be established and verified.
test configuration shall be clearly defined and documented.
N45.2.1, &sect; 6.3.3, &#xb6; 4 The results of model test work shall be      The results of model test work shall be subject to error analysis, Similar requirement.
subject to error analysis, where applicable, prior to use in final where applicable, prior to use in final design work.
design work.
N45.2, &sect; 4 Change Control                                          5 CHANGE CONTROL N45.2.11, &sect; 8 Design Change Control N45.2 Design changes, including field changes, shall be            Changes to final designs, field changes, modifications to          Similar requirement.
governed by design control measures commensurate with those        operating facilities, and nonconforming items dispositioned use-applied to the original design.                                    as-is or repair shall be justified and subject to design control N18.7, 5.2.7.2 Modifications. Design activities associated with    measures commensurate with those applied to the original modifications of safety-related structures, systems, and          design.
components shall be accomplished in accordance with N45.2.11-1974.[9]
N45.2.11, &sect; 8, &#xb6; 1 Documented procedures shall be provided for design changes to approved design documents, including field changes, which assure that the impact of the change is carefully considered, required actions documented and 10/28/2010                                                                Design Control                                                            Page 17 of 25
 
C**",RION 3                                                  BASIC REQUIREMENT 3                                  COMMENTS "ANSI N45.2-1971; N45.2.1141974, NIS7-1976                                            N.A-4 1994 information concerning the change is transmitted to all affected persons and organizations. These changes shall be justified and subjected to design control measures commensurate with those applied to the original design.
N45.2.11, &sect; 8.1 Reasons for Changes                                                                                                  Not a requirement; Design changes frequently result from such things as the                                                                            introductory statement.
following:                                                                                                                          Examples not stated in
: 1. Qualification, preoperational, or operational test results are                                                                    NQA-1.
not satisfactory.
: 2. Interference problems discovered during construction.
: 3. Failures of structures, systems, or components to meet functional requirements.
: 4. Disposition of nonconforming items.
: 5. Changes in regulatory or other requirements.
: 6. Operational experience.
: 7. Design improvement.
N45.2, &sect; 4 It is the intent of this standard that design changes be These measures shall include assurance that the design analyses  Similar requirement.
reviewed and approved by the organizations that performed the      for the structure, system, or component are still valid. Changes original design, review, and approval. In the event that it is not  shall be approved by the same affected groups or organizations practical for the original organizations to perform the required    which reviewed and approved the original design documents; review or approval, other responsible design organizations may      except where an organization which originally was responsible be designated, provided the designated organizations have          for approving a particular design document is no longer access to pertinent background information, have demonstrated      responsible, then the Owner or his designee shall designate a competence in the specific design area of interest, and have        new responsible organization which could be the Owner's adequate understanding of the requirements and intent of the        engineering organization. The designated organization shall original design.                                                    have demonstrated competence in the specific design area of N45.2.11, &sect; 8.2 Review of Changes                                  interest and have an adequate understanding of the requirements Normally, the procedures for effecting design changes shall        and intent of the original design.
require that the documents which reflect the design change be reviewed and approved by the same groups or organizations which reviewed and approved the original design documents.
Where an organization which originally was responsible for approving a particular design document is no longer responsible, the plant owner shall designate the new responsible organization which may be the owner's own engineering organization. The designated organization shall have access to pertinent background information, have demonstrated competence in the specific design area of interest and have an adequate understanding of the requirements and intent of the 10/2 8/2 010                                                                Design Control                                                          Page 18 of 25
 
C~iTEION 3BASIC                                    REQUIREMENT 3                    ..              COMMENTS ANSI N45214971; N:45.2.t--074; N1&7-1976                                              NQA4-11994                              ___________
original design.
When a design change is approved other than by revision to the    New requirement.
affected design documents, measures shall be established to incorporate the change into these documents, where such incorporation is appropriate.
N45.2.11, &sect; 9.2 Review of Procedure                                Where a significant design change is necessary because of an      Similar requirement.
Where a significant design change is necessary because of an      incorrect design, the design process and verification procedure incorrect design the design process and verification procedure    shall be reviewed and modified as necessary.
shall be reviewed and modified as necessary.
N45.2, &sect; 4.2 Interface Control                                    6 INTERFACE CONTROL N45.2.11, &sect; 5 Interface Control N45.2 Design control measures shall be applied as necessary to    Design interfaces shall be identified and controlled and the      Similar requirement.
identify and control design interfaces and for coordination        design efforts shall be coordinated among the participating among participating design organizations.                          organizations.
N45.2.11, &sect; 5.1 External 5.1.1 Identification of Interface. The external interfaces between organizations performing work affecting quality of design shall be identified in writing and shall include those organizations providing criteria, designs, specifications and technical direction.
N45.2.11, &sect; 5.2 Internal 5.2.1 Identification of Interface. Each organization performing work affecting quality of design shall identify in writing its internal design interfaces for managing the flow of design information between organizational units.
N45.2 These measures shall include the establishment of            Interface controls shall include the assignment of responsibility  Similar requirement.
procedures among participating design organizations for the        and the establishment of procedures among participating design review, approval, release, distribution, and revision of          organizations for the review, approval, release, distribution, and documents involving design interfaces.                            revision of documents involving design interfaces.
N45.2.11, &sect; 5.1 External 5.1.2 Responsibilities. Responsibilities for organizations shall be defined and documented in sufficient detail to cover the preparation, review and approval of documents involving design interfaces. Responsibilities may be set forth in tabular form or flow charts accompanied by appropriate text to clarify the intent. Appendices A and B provide examples.
N45.2.11, &sect; 5.2 Internal 5.2.2 Responsibilities. Responsibilities for each organizational unit shall be defined and documented in sufficient detail to 10/28/2010                                                                Design Control                                                            Page 19 of 25
 
CRITERION 3.                                              BASIC REUMMN                                              COMMENTS        .
ANSI N45.2-197 N4.2.1-1974; N1.7-1976                                              NQA-1 1994                            _____..... ____________
cover the preparation, review, approval, distribution and revision of documents involving design interfaces.
N45.2.11, &sect; 5.1 External                                          Design information transmitted across interfaces shall be          Similar requirement. NQA-5.1.3 Lines of Communication. Systematic methods shall be        documented and controlled. Transmittals shall identify the        1-1994 added detail on established for communicating needed design information          status of the design information or document provided and,        informal communication.
across external design interfaces, including changes to the      where necessary, identify incomplete items which require design information as work progresses. Documents shall            further evaluation, review, or approval. Where it is necessary to identify the positions and titles of key personnel in the        initially transmit design information orally or by other informal communication channels and their responsibilities for decision-  means, the transmittal shall be confirmed promptly by a making, for resolution of problems, for providing and reviewing  controlled document.
information, and for taking other action within the scope of this standard.
5.1.4 Documentation. Procedures shall be established to control the flow of design information between organizations. Design information transmitted from one organization to another shall be documented in specifications, drawings or other controlled documents which are uniquely identified and issued by authorized persons. The procedures shall provide that design interface information be transmitted to affected organizations and that any information requested in the design interface transmittal be transmitted back to the originator. Documentation requesting information or action shall be controlled by a system which assures that the response and the request can be related.
Where it is necessary to initially transmit design information orally or by other informal means, the transmittal shall be confirmed promptly by a controlled document.
N45.2.11, &sect; 5.2 Internal 5.2.3 Lines of Communication. Systematic methods shall be established for communicating needed design information across the internal design interfaces, including changes to the design information as work progresses.
5.2.4 Documentation. Procedures shall be established to control the flow of design information between organizational units.
Design information transmitted from one organizational unit to another shall be documented and controlled. Transmittals shall identify, the status of the design information or document provided and, where necessary, identify incomplete items which require further evaluation, review or approval. Where it is necessary to initially transmit design information orally or by Page 20 of 25 Design Control 10/28/2010 10/2 8/2 010                                                            Design Control                                                            Page 20 of 25
 
CRITERION 3                                                  BAS9IC REQ1Vi.rdEME        3 ANSIrN45.2-1971;*    N45,2.11I97'4;N18.771976                                        NQ1*" 1994                            _._..:._......,_....-      -.
other informal means, the transmittal shall be confirmed promptly by a controlled document.
N45.2.11, &sect; 7 Document Control                                      7 DOCUMENTATION AND RECORDS N45.2 Records of implementation of these design control            Design documentation and records, which provide evidence that    Similar requirement.
measures shall be available for review,                            the design and design verification processes were performed in N45.2.11, &sect;6.1, &#xb6; 3 The results of design verification efforts      accordance with the requirements of this Part (Part 1), shall be shall be clearly documented, with the identification of the        collected, stored, and maintained in accordance with verifier clearly indicated thereon, and filed.                      documented procedures.
N45.2.11, &sect; 7 Document Control Documented procedures shall be used to control issuance of design documents and changes thereto. These procedures shall assure that documents, including changes, are reviewed for adequacy and approved for release by authorized personnel and are properly distributed.
N45.2.11, &sect;6.1, &#xb6; 3 Documentation of results shall be auditable    The documentation shall include not only final design            Similar requirement.
against the verification methods identified by the responsible      documents, such as drawings and specifications, and revisions design organization.                                                thereto but also documentation which identifies the important N45.2.11, &sect; 10, &#xb6; 2 The documentation shall include not only        steps, including sources of design inputs that support the final the final design documents such as drawings and specifications,    design.
and revisions thereto but also records of the important steps including sources of design inputs, which support the final design. The records shall be legible, identifiable and retrievable.
ANSI N45.2.11, &sect; 7.1 Document Preparation, Approval and                                                                              Document control is Issue                                                                                                                                addressed as NQA 1 1994, Personnel shall be made aware of and use proper and current                                                                          Basic Requirement 6 and instructions, procedures, drawings and design inputs.                                                                                Supplement 6S-1. A Participating organizations shall have documented procedures                                                                          separate table for NQA-1 for control of design documents and changes thereto to assure                                                                        Basic Requirement 6 and that current and appropriate documents are available for use.                                                                        Supplement 6S-1 addresses The document control procedures shall provide for:                                                                                    requirements for document
: 1. Identification of personnel positions or organizations                                                                            control.
responsible for preparing, reviewing, approving ,and issuing documents and revisions thereto. This identification may take the form of Project General Instructions, design organization Policy Statements, a matrix showing document type against function, or other written forms appropriate to the organizational method of performing the design process.
: 2. Identification of the proper documents to be used in performing the design. The identification should include title 10/28/2010                                                                  Design Control                                                                Page 21 of 25
 
AS*5.-9;          RCTERION      3 .. N N45.2.11.1974,;N.      -19767"  .COMMENTS          ASIC REQUIREMENT 3 NQA 11994 ,___.._:,            _,______    ,__..
applicable revisions, date of issue or any other relevant information that would precisely identify the document to be used.
: 3. Coordination and control of design (internal and external) interface documents. These interface documents should be mutually agreed to and prepared in sufficient detail to assure that the required reviews and approvals are accomplished.
: 4. Ascertaining that proper documents are accessible and are in fact being used. This might be accomplished by several schemes including the following examples: periodic issuance of master drawing or specification lists showing the latest applicable revision (such lists could provide a reference for auditing the accessibility and use of the latest documents); or some type of receipting system can provide assurance that the latest documents have been received and obsolete revisions recalled. An example of such a receipting system is Appendix C, Drawing Issue Check List.
: 5. Establishing distribution lists which are updated and maintained current to assure that the proper personnel are sent all the required documents to perform the work.
ANSI N45.2.11, &sect; 7.2 Document Revision Significant changes to documents shall be reviewed and approved by the same organizations that performed the original review and approval unless other organizations are specifically designated. The reviewing organizations shall have access to pertinent background data information upon which to base their approval. However, minor changes to design documents, such as inconsequential editorial corrections or changes to commercial terms and conditions, may not require that the revised document receive the same review and approval as the original documents. To avoid a possible omission of a required review, the type of minor changes which do not require such a review and approval and the persons who can authorize such a decision shall be clearly delineated in the document control procedures.
N45.2.11, &sect; 9 Corrective Action                                                                            Corrective action is In addition to correcting a deficiency (or error), corrective                                              addressed as NQA 1 1994, action also includes, for significant or recurring deficiencies (or                                        Basic Requirements 15 and errors), determining the cause and instituting appropriate                                                16 and associated 10/28/2010                                                              Design Control                                    Page 22 of 25
 
CRITERION 3                                      &#xfd;BASIC REQUIRMENT 3        COMMIENTS ANSI N45-7 N5.2 40-174; N18.7-1976                                      NA1 1994                    '
changes in the design process and the quality assurance                                        Supplements. Separate program to prevent similar types of deficiencies (or errors) from                              tables for NQA-1 Basic recurring. A procedure shall be employed for providing such                                    Requirements 15 and 16 corrective action. This procedure shall also contain provisions                                and associated Supplements for reporting the deficiency and corrective action to appropriate                              address requirements for levels of supervision and management. The procedure shall also                                corrective action.
include follow-up actions that cannot be immediately completed to assure timely resolution and/or completion of the corrective action.
9.1 Detection of Errors Deficiencies or error in the design or the design quality assurance program may, be detected by:
: 1. Design verification measures.
: 2. Personnel using the design documents.
: 3. Audits.
: 4. Tests conducted.
: 5. Actual failure during operation.
: 6. Other means.
N45.2.11, &sect; 10 Records                                                                        Records are addressed as Design documentation and records which provide evidence that                                  NQA 1 1994, Basic the design and review process was performed in accordance                                      Requirement 17 and with the requirements of this standard shall be collected, stored                              Supplement 17S-1.
and maintained in accordance with the requirements of ANSI N45.2.9.
Documentation and records will be either of the lifetime or nonpermanent category as defined in ANSI N45.2.9.
N45.2.11, &sect; 11 Audits                                                                          Audit requirements are A comprehensive system of planned and documented audits                                        addressed as NQA 1 1994, shall be carried out to verify compliance with all aspects of the                              Basic Requirements 2 and Quality Assurance program for design including those                                          18 and associated procedures delineating quality assurance actions required during                              Supplements. Separate the design process.                                                                            tables for NQA-1 Basic 11.1 Personnel                                                                                Requirements 2 and 18 and These audits shall be performed in accordance with written                                    associated Supplements procedures or checklist by personnel not having direct                                        address requirements for responsibilities in the areas being audited. For example, the                                  audit requirements.
person who performs an audit on design verification should not have been responsible for performing the design verification.
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CRITERION3 ANSI N45.2-1971; N4$.2.1141974; N18.7-1976NQ-194___________
j          BASIC REQUIREMENTY 3 .OMMENTS The personnel performing audits shall be of a level of competency and have sufficient authority and organizational freedom to make the audit process meaningful and effective.
11.2 Internal Audits Design organizations performing work in accordance with the requirements of this standard shall be audited to assure that their design quality assurance programs are being implemented.
Audits may be conducted internally by the design organization or by a unit independent of the design organization.
11.3 External Audits Organizations shall conduct or delegate the conduct of external audits of design organizations performing work for them to assure that specified design quality assurance program requirements are being implemented and are effective.
11.4 Audit Control Audits shall include an evaluation of design quality assurance policies, practices, procedures and instructions; the effectiveness of implementation; and actions taken to correct deficiencies in the program. The audits should include the examination of design activities, processes and documents and records. An audit plan shall be developed and should identify the functional areas to be audited, the extent of audit within these areas to determine effectiveness, the names and assignments of those who will perform the audit, the scheduling arrangements and the methods of reporting findings and recommendations.
11.5 Audit Schedule Audits should be conducted on a routine basis to establish the adequacy of and conformance to the design quality assurance requirements. Audits should also be conducted when one or more of the following conditions exists:
: 1. When it is necessary to determine the capability of a subcontractor's quality assurance program prior to awarding of contract of purchase order for design services.
: 2. When, after award of contract, sufficient time has elapsed for the implementation of the quality assurance program for design and it is appropriate to determine that the organization is performing the functions as defined in the quality assurance program description, codes, standards and other contract 10/28/2010                                                            Design Control                        Page 24 of 25
 
CRITERON 3                                        ]BASIC  EQUIREMENT 3      COMMENT 452-97; 45 1.1-1974; N18.7-1976 ANI                                                4                NQA-1 1994    _ __________
documents.
: 3. When significant changes are made in functional areas of the quality assurance program for design including significant reorganizations and procedure revisions.
: 4. When it is suspected that safety related performance of the item is in jeopardy due to deficiencies and nonconformances in the quality assurance program.
: 5. When a systematic, independent assessment of program effectiveness or item quality or both is considered necessary.
: 6. When it is considered necessary to verify implementation of required corrective actions.
11.6 Results Audit results shall be documented and reviewed by management having responsibility in the areas audited. Audit reports shall be in sufficient detail to permit management evaluation of the breadth of the audit as well as the validity of the findings.
11.7 Follow-Up Appropriate corrective action and timely follow-up action, including re-audit of deficient areas, shall be taken where indicated by the audit findings.
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ANSI. N45. -11. CRITERION4                                                BASIC.REQUIREMENT 4                              COMMENTS
    *.N. N45.2-1971"&sect; 5, N45.2.13-1976 &sect; 3,N18.7-1976 &sect;                                      NQA-1 1994 5.2.13.1____________________________________                                                                            ___
N45.2 Measures shall be established and documented to assure        Applicable design bases and other requirements necessary to Similar requirements.
that applicable regulatory requirements, design bases, and other assure adequate quality shall be included or referenced in requirements which are necessary to assure adequate quality are documents for procurement of items and services.                ANSI N1 8.7 contains more included or referenced in the documents for procurement of                                                                      detail on the applicability of items and services.                                                                                                            the measures and the need N45.2.13 &sect; 3.1 The Purchaser shall establish measures to assure                                                                for procedures to control the that applicable regulatory requirements, design bases, and other                                                                procurement process. These requirements (including specific issue dates and applicable                                                                    are covered in a more addenda) which are necessary to assure adequate quality are                                                                    general sense in the included or invoked by reference in the documents for                                                                          Introduction section of procurement of items and services.                                                                                              NQA-1, Part I.
N18.7 &sect; 5.2.13 Procurement and Materials Control &#xb6; 1                                                                            ANSI N18.7 invokes the Measures shall be provided for procurement, documentation                                                                      use of ANSI N45.2.13 and control of those materials and components including spare                                                                  requirements related to and replacement parts necessary for plant operation, refueling,                                                                Procurement Document maintenance and modification. These measures shall utilize                                                                      Control (Section 3 of that American National Standard Quality Assurance Requirements                                                                      standard). The applicable for the Control of Procurement of Items and Services for                                                                        requirements have been Nuclear Power Plants, N45.2.13-1976. Procedures shall be                                                                        included in NQA-1, established and implemented to ensure that purchased materials                                                                  Supplement 4S-1.
and components associated with safety-related structures or                                                                    This has been systems are:                                                                                                                    acknowledged by the NRC (1) Purchased to specifications and codes equivalent to those                                                                  through the withdrawal of specified for the original equipment, or those specified by a                                                                  the Regulatory Guide 1.123 properly reviewed and approved revision. (In those cases where                                                                  that endorsed ANSI the original item or part is found to be commercially "off the                                                                  N45.2.13 where licensees shelf," or without specifically identified quality assurance                                                                    are committing to NQA-1.
requirements, spare and replacement parts may be similarly procured but care shall be exercised to assure at least equivalent performance. In those cases where the QA requirements of the original item cannot be determined, an engineering evaluation shall be conducted by qualified individuals to establish the requirements and controls. This evaluation shall assure that interfaces, interchangeability, safety, fit and function are not adversely affected or contrary to applicable regulatory or code requirements. The results of this evaluation shall be documented)
N18.7 . 5.2.13.1 Procurement Document Control. Measures Procurement Document Control                                                  Page 1 of7 10/28/2010                                                        Procurement Document Control                                                  Page I of 7
 
CRITERION 4                                              BASIC REQUJIREMENT 4                                CM ET AN SI N45.2-1971 &sect; 5, N45.2.13-1976 &sect; 3, N 18.7-17 &sect;                                    NQA-1 1994
                              .52.13.1 shall be provided to assure that applicable regulatory requirements, design bases and other requirements which are necessary to assure adequate quality are included or referenced in the procedures for procurement of items and services.
N45.2 To the extent necessary, procurement documents shall        To the extent necessary, procurement documents shall require  Similar requirement.
require contractors to provide a Quality Assurance Program        Suppliers to have a quality assurance program consistent with consistent with the pertinent requirements of this standard.      the applicable requirements of this Part (Partl).
N18.7 5.2.13.1 To the extent necessary, procurement documents shall require suppliers to provide a quality assurance program consistent with the pertinent requirements of American National Standard Quality Assurance Program Requirements for Nuclear Power Plants, N45.2-1971. [2]
SUPPLEMENT 4S-1 SUPPLEMENTARY REQUIREMENTS FOR PROCUREMENT DOCUMENT CONTROL 1 GENERAL This Supplement provides amplified requirements for procurement document control.
It supplements the requirements of Basic Requirement 4 of this Part and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Partl).
2 CONTENT OF THE PROCUREMENT DOCUMENTS N45.2 Procurement documents shall include provisions for the      Procurement documents issued at all tiers of procurement shall Similar requirement; following, as applicable:                                        include provisions for the following, as deemed necessary by  introductory statement.
N45.2.13 &sect; 3.2 Content of the Procurement Documents -            the Purchaser.
Procurement documents issued at all tiers of procurement shall include provisions for the following, as deemed necessary by the Purchaser:
N45.2.13 &sect; 3.2.1 Scope of Work.                                  2.1 Scope of Work N45.2.13 &sect; 3.2.1 A statement of the scope of the work to be      A statement of the scope of the work to be performed by the    Similar requirement.
performed by the Supplier shall be in the procurement            Supplier shall be in the procurement documents.
documents.
ANSI N45.2, (2) Basic Technical Requirements                      2.2 Technical Requirements ANSI N45.2 Drawings, specifications, codes and industrial        Technical requirements shall be specified in the procurement  Similar requirement.
standards with applicable revision data, test and inspection      documents. Where necessary, these requirements shall be requirements, and special instructions and requirements, such as  specified by reference to specific drawings, specifications, 10/2 8/2 010                                                    Procurement Document Control                                                      Page 2 of 7
 
      .    ..            CRITERION 4                                      .          BASIC REQUIREMEN&#xfd;T 4                    ..      .      COMMNTS            .
ANSI N45.2-1971 &sect; 5, N45.2.13-1976 &sect; 3, N18.7-1976 &sect;                                        NQA-1 1994                                  <..
for designing, fabricating, cleaning, erecting, packaging,          codes, standards, regulations, procedures, or instructions, handling, shipping, and, if applicable, extended storage in the      including revisions thereto that describe the items or services to field; and for test equipment.                                      be furnished. The procurement documents shall provide for N45.2.13 &sect; 3.2.2 Technical Requirements. Technical                  identification of test, inspection, and acceptance requirements requirements shall be specified in the procurement documents        of the Purchaser for monitoring and evaluating the Supplier's by reference to the specific drawings, specifications, codes,        performance.
regulations, procedures or instructions including revisions thereto that describe the items or services to be furnished. The procurement documents shall identify or provide for later identification of test, inspection and acceptance requirements, and any special instructions and requirements for such activities as designing, identification, fabrication, cleaning, erecting, packaging, handling, shipping and extended storage. All such technical requirement documents shall be prepared, reviewed and released under the requirements established by ANSI N45.2.1 1.
N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include provisions for the following, as applicable: (2) Basic Technical Requirements. Where specific technical requirements apply, such as drawings, specifications, and industrial codes and standards, they shall be identified by titles and dates of issue in such a way as to clearly set forth the applicable documents.
Where procedural requirements apply, in such areas as test and inspection needs, fabrication, cleaning, erecting, packaging, handling, shipping and storage, they too, shall be identified clearly and in such a way as to avoid uncertainty as to source and need.
N45.2 (1) Supplier Quality Assurance Program                        2.3 Quality Assurance Program Requirements N45.2 (1) Identification of quality assurance requirements and      Procurement documents shall require that the Supplier have a      Similar requirement.
the elements of the program applicable to the items or services      documented quality assurance program that implements              The appendix referred to in procured. This may be accomplished in various ways, such as          portions or all of the requirements of this Part (Part 1).        N45.2.13 was not the following: (a) invoking this standard by reference, or (b)                                                                          considered a part of the invoking applicable sections or elements of this standard, or (c)                                                                      standard. The guidance in invoking other specific requirements which meet the intent of                                                                          the appendix has been this standard.                                                                                                                          incorporated into the N45.2.13 &sect; 3.2.3 Quality Assurance Program Requirements.                                                                                NQA-1 nonmandatory Procurement documents shall require that the Supplier have a                                                                            guidance of Appendices documented quality assurance program that implements                                                                                    4A-1 and 7A-1.
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CRITERION 4                                                    BASIC REQUIREMIENT 4                                    COMMENTS ANSI
: N45.2-1971
      *"    ......."' t':,.5.."1"3.1            Ni8.7-1976 &sect;....
                        &sect;.5, N45.2.13-1976 &sect; k!***Zf'*              ""9......'......
                                                                  ':**,*                          A 194                          ..
* portions or all of ANSI N45.2 as well as applicable quality assurance program requirements of other nationally recognized codes and standards. (The Appendix provides an explanation and examples of logic and considerations which may be used to decide how and to what extent quality assurance program requirements shall be specified in procurement documents. The Appendix is not a part of this standard.)
N18.7 &sect; 5.2.13.1, &#xb6; 1, Sentence 2 - To the extent necessary, procurement documents shall require suppliers to provide a quality assurance program consistent with the pertinent requirements of American National Standard Quality Assurance Program Requirements for Nuclear Power Plants, N45.2-1971.
N18.7 &sect; 5.2.13, &#xb6; I The Appendix to N45.2.13 is particularly          The extent of the program required shall depend upon the type      Similar requirement.
useful in determining the quality assurance requirements              and use of the item or service being procured.                      The appendix referred to in depending on the complexity or safety of the item.                                                                                        N45.2.13 was not N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include                                                                                considered a part of the provisions for the following, as applicable: (1) Supplier Quality                                                                        standard. The guidance in Assurance Program. Identification of quality assurance                                                                                    the appendix has been requirements applicable to the items or services procured.                                                                                incorporated into the NQA-1 nonmandatory guidance of Appendices 4A-1 and 7A-1.
N45.2 (5 ) Lower Tier Procurements. Provisions for                    The procurement documents shall require the Supplier to            Similar requirement.
extending applicable requirements of procurement documents to        incorporate appropriate quality assurance program requirements      The appendix referred to in lower tier subcontractors and suppliers, including purchaser's        in subtier procurement documents.                                  N45.2.13 was not access to facilities and records.                                                                                                        considered a part of the N45.2.13 &sect; 3.2.3 The procurement documents shall require the                                                                              standard. The guidance in Supplier to incorporate appropriate quality assurance program                                                                            the appendix has been requirements in subtier procurement documents.                                                                                            incorporated into the N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include                                                                                NQA- I nonmandatory provisions for the following, as applicable: (5) Lower Tier                                                                              guidance of Appendices Procurement. Provisions for extending applicable requirements                                                                            4A-I and 7A-1.
to lower tier subcontractors and suppliers, including purchaser's access to facilities and records.
N45.2(3) Source Inspection and Audit                                  2.4 Right of Access N45.2 Provisions for access to the plant facilities and records      At each tier of a procurement, the procurement documents shall      Similar requirements.
for source inspection and audit when the need for such                provide for access to the Supplier's plant facilities and records  N45.2.13 contains guidance 10/28/2010                                                          Procurement Document Control                                                          Page 4 of 7
 
CRIT.ERON 4                                                BASIC REQUIREMENT 4                                    COMMENTS ANSI N45.2-1971 &sect;.5, N45.2.13-1976 &sect;.3 1.-96&sect;NA119 5.2.13.1 inspection or audit has been determined,                          for inspection or audit by the Purchaser, his designated          on sufficient notice for N45.2.13 &sect; 3.2.4 Right of Access. At each tier of a              representative, and/or other parties authorized by the Purchaser. access to a supplier's procurement, the procurement document shall provide, as                                                                            facility that are more good deemed necessary by the Purchaser, for access to the Supplier's                                                                    business sense than quality plant facilities and records for inspection or audit by the                                                                        assurance requirements.
Purchaser, his designated representative, and/or other parties authorized by the Purchaser. The provisions should include a statement of the minimum time of advance notice and the method of communication of such notice. They should include or provide for the later identification (see Section 6.2) of the events such as witness and hold points established or considered appropriate for the Purchaser's presence at the Supplier's facility.
N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include provisions for the following, as applicable: (3) Source Inspection and Audit. Provisions for access to the supplier's facilities and records for source inspection and audit when the need for such inspection or audit has been determined.
(4) Documentation Requirements.                                  2.5 Documentation Requirements N45.2 Records to be prepared, maintained, submitted. Or made      The procurement documents at all tiers shall identify the        Similar requirement.
available for review, such as drawings, specifications,          documentation required to be submitted for information, procedures, procurement documents, inspection and test            review, or approval by the Purchaser. The time of submittal records, personnel and procedure qualifications, and material,    shall also be established.
chemical, and physical test results.
N45.2.13 &sect; 3.2.5 Documentation Requirements. The procurement documents at all tiers shall identify the documentation required to be submitted, including quality assurance records for information, review, or approval of the Purchaser. The time of submittal shall also be established.
N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include provisions for the following, as applicable: (4) Documentation Requirements. Records to be prepared, maintained, submitted or made available for review, such as drawings, specifications, procedures, procurement documents, inspection and test records, personnel and procedure qualifications, and material, chemical, and physical test results....
N45.2 Instruction on record retention and disposition shall be    When the Purchaser requires the Supplier to maintain specific    Similar requirement.
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CRITERION 4                                                  BASIC REQUIREMENT 4                                  COMMENTS ANSI N45.2-1971 &sect; 5, N45.2.13-1976 &sect; 3, N18.7-1976 &sect;                                        NQA-I 1994 provided,                                                            quality assurance records, the retention times and disposition N45.2.13 &sect; 3.2.5 - The Purchaser shall prescribe to the Supplier    requirements shall be prescribed.
those quality assurance records of compliance for which retention responsibility remains with the Supplier. ANSI N45.2.9 provides guidance for retention and disposition of quality assurance records.
N18.7 &sect; 5.2.13.1, &#xb6; 2 Procurement documents shall include provisions for the following, as applicable: (4) ... Instruction on record retention and disposition shall be provided.
2.6 Nonconformances N45.2.13 &sect; 3.2.6 Nonconformances. The procurement                    The procurement documents shall include Purchaser's              Similar requirement.
documents shall include Purchaser's requirements for reporting      requirements for reporting and approving disposition of and approving disposition of nonconformances. Section 8 of          nonconformances.
this standard provides further guidelines on handling nonconformances.
2.7 Spare and Replacement Parts N18.7 &sect; 5.2.13 Procurement and Materials Control. &#xb6; 1                The procurement documents shall require the identification of    Similar requirement.
Measures shall be provided for procurement, documentation            appropriate spare and replacement parts or assemblies and the and control of those materials and components including spare        appropriate delineation of the technical and quality assurance and replacement parts necessary for plant operation, refueling,      related data required for ordering these parts or assemblies.
maintenance and modification.
N45.2.13 &sect; 3.3 Procurement Document Review                          3 PROCUREMENT DOCUMENT REVIEW N45.2.13 &sect; 3.3 A review of the procurement documents shall be        A review of the procurement documents and changes thereto        Similar requirement.
made to assure that documents transmitted to the prospective        shall be made to assure that documents transmitted to the Suppliers for bid or contract purposes include appropriate          prospective Supplier(s) include appropriate provisions to assure provisions to assure items or services meet the specified            that items or services will meet the specified requirements.
requirements.
N45.2.13 &sect; 3.3 - a. Such reviews shall be performed prior to        Reviews shall be performed and documented to provide            Similar requirement.
release for bid and contract award and shall assure that the        objective evidence of satisfactory accomplishment of such documents are complete and contain the applicable                    review prior to contract award.
requirements specified in Section 3.2 of this standard.
: d. Performance of reviews shall be documented to provide objective evidence of accomplishment.
N45.2.13 &sect; 3.3 - b. Changes made in the procurement                  Changes made as a result of the bid evaluations or precontract  Similar requirement.
documents as a result of the bid evaluations or precontract          negotiations shall be incorporated into the procurement negotiations shall be incorporated into the procurement              documents. The review of such changes and their effects shall documents. The review of such changes and their effects shall        be completed prior to contract award.
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CRITERION 4-                                                BASIC REQUIREMENT 4                                  COMMENT ANSI N45.2-1971 &sect; 5, N45.2.13-1976 &sect; 3, N18.7-1976 &sect;                                      NQA-1 1994 5.2.13.1                              __________________________
be completed prior to contract award.____________________________
N45.2.13 &sect; 3.3 - b - This review shall include the following      This review shall include the following considerations:          Similar requirement.
considerations.                                                    (a) appropriate requirements specified in Section 2 of this
: 1) Appropriate requirements specified in Section 3.2.              Supplement;
: 2) Determination of any additional or modified design criteria      (b) determination of any additional or modified design criteria, imposed after preparation of the procurement documents.            (c) analysis of exceptions or changes requested or specified by
: 3) Analysis of exceptions or changes requested or specified by    the Supplier and determination of the effects such changes may the Supplier and determination of the effects such changes may have on the intent of the procurement documents or quality of have on the intent of the procurement documents or quality of      the item or service to be furnished.
the item or service to be furnished.
N45.2.13 &sect; 3.3 - c. Reviews required by this section shall be      Reviews required by this Section shall be performed by            Similar requirement.
performed by personnel who have access to pertinent                personnel who have access to pertinent information and who information and who have an adequate understanding of the          have an adequate understanding of the requirements and intent requirements and intent of the procurement documents.              of the procurement documents.
4 PROCUREMENT DOCUMENT CHANGES N45.2 Changes in procurement documents shall be subject to        Procurement document changes shall be subject to the same        Similar requirements.
the same degree of control as was utilized in the preparation of  degree of control as utilized in the preparation of the original  The controls of ANSI the original document.                                            documents.                                                        N45.2 Section 7 are those N45.2.13 &sect; 3.4 Procurement Document Control Procurement                                                                              related to Criterion 6, documents shall be controlled in accordance with ANSI N45.2                                                                          Document Control.
Section 7.
N18.7 &sect; 5.2.13.1 &#xb6;1, sentence 3 - Where changes are made to procurement documents, they shall be subject to the same degree of control as was used in the preparation of the original documents.
N45.2.13 &sect; 3.1, sentence 2 - Procurement document changes shall be subject to the same degree of control as utilized in the preparation of the original documents.,__________________________
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C.,RITERION 5                                                  BASIC REQUIREMENT 5                  '      . COME**NTS ANSI N45.2-1971 &sect; 6 - ANSI N18.7-1976                ...                          ..............-
QA.... 1994..."
Related Definitions: ANSI N45.2.10                                    Procedure - a document that specifies or describes how an  Similar definition.
Procedure - a document that specifies or describes how an            activity is to be performed activity is to be performed. It may include methods to be employed, equipment or materials to be used and sequence of operations.
Related Definitions: ANSI N45.2.10                                    Qualified Procedure - an approved procedure that has been  Similar definition.
Qualified Procedure- A procedure which incorporates all              demonstrated to meet the specified requirements for its applicable codes and standards, manufacturer's parameters, and        intended purpose.
engineering specifications and has been proven adequate for its intended purpose.
Related Definitions: ANSI N18.7                                                                                                  No related definitions in emergency procedures. Written procedures which specify                                                                          NQA-1. Procedure types actions, including manipulation of plant controls, to reduce the                                                                are discussed in Part V, consequence of an accident or potentially hazardous condition                                                                    Section 3.0 of the QAPD.
which has already occurred, to implement the emergency plan, or to prepare for possible hazardous natural occurrences.
maintenance and modification procedures. Written procedures defining the policies and practices by which structures; mechanical, electrical and instrumentation and control systems; and components thereof of a nuclear power plant are kept in a condition of good repair or efficiency so that they are capable of performing their intended functions. As used in this Standard, these procedures apply to those activities performed by maintenance or contractor personnel to maintain, repair or modify safety-related equipment. Related activities are those actions taken by operating personnel to determine that a planned maintenance activity can be safely performed under the existing plant operating conditions, to authorize the release of equipment to be maintained in accordance with equipment control procedures, and to assure that the equipment has been returned to normal operating status at the completion of the maintenance work including verification of functional acceptability. Procedures for these related activities by operating personnel are considered to be operating procedures, but may be included in maintenance procedures.
off-normal condition procedures. Written procedures which specify operator actions for restoring an operating variable to its normal controlled value when it departs from its range or to Page 1 of 15 10/28/2010                                                      Instructions, Procedures, and Drawings Instructions, Procedures, and Drawings                                          Page I of 15
 
CRITERION 5                                                  BASIC REQUIIREMENT 5                                COMMENTS ANSI N45.2-197,                N18.7-1976"                        .6-'ANSI        NQA.1 1994*4          .
restore normal operating conditions following a perturbation.
Such actions are invoked following an operator observation or an annunciator alarm indicating a condition which, if not corrected, could degenerate into a condition requiring action under an emergency procedure operating procedures. Written procedures defining the normal method, means and limits of operation of a nuclear power plant, a plant system or systems, or processes, including actions to be taken by operating personnel for removal from and return to service equipment on which maintenance is to be or has been performed (see also maintenance and modification procedures).
Related Definitions: ANSI N45.2.10                                  Document - any written or pictorial information describing,    Similar definition.
Documentation - any written or pictorial information                defining, specifying, reporting or certifying activities, describing, defining, specifying, reporting or certifying            requirements, procedures, or results. A document is not activities, requirements, procedures, or results,                    considered to be a Quality Assurance Record until it satisfies the definition of a Quality Assurance Record as defined in this Supplement.
ANSI N45.2 Activities affecting quality shall be prescribed by      Activities affecting quality shall be prescribed by and        Similar requirement.
documented instructions, procedures, or drawings, of a type          performed in accordance with documented instructions, appropriate to the circumstances and shall be accomplished in        procedures, or drawings of a type appropriate to the            ANSI Nl18.7 contains a lot accordance with these instructions, procedures, or drawings.        circumstances.                                                  of specific detail on the type and content of procedures.
N18.7 - 5.3 The administrative controls and quality assurance                                                                        Will incorporate the program shall be carried out through plant life in accordance                                                                        appropriate information into with written procedures. Activities affecting safety at nuclear                                                                      Part V of the QAPD using power plans shall be described by written procedure of a type                                                                        current alternatives to appropriate to the circumstances and shall be accomplished in                                                                        N 18.7 without a specific accordance with these instructions and procedures.                                                                                  commitment to N 18.7 to 5.2.7 Maintenance or modifications of equipment shall be                                                                            avoid confusion by use of preplanned and performed in accordance with written                                                                                  redundant standards.
procedures, documented instructions or drawings appropriate to                                                                     
 
==Reference:==
ANSI N45.2.4, the circumstances which conform to applicable codes,                                                                                5, 6, 8, and 11 contain standards, specifications, and criteria. Skills normally possessed                                                                  additional procedure by qualified maintenance personnel may not require detailed                                                                          requirements. These have step-by-step delineations in a written procedure.                                                                                    been incorporated into NQA-1, Subparts 2.4, 2.5, 2.6, and 2.8. N45.2.11 requirements are 10/28/2010                                                      Instructions, Procedures, and Drawings                                                Page 2 of 15
 
CRITE." ON  .              ...........                        BASIC REQUIREMENT  ..        5..  . ... .    ........      COM,.ENT ANSIN45.2-1971. &sect;6. ANSI N18.741976                        __________                      __A ______"___"_______1__1__94.."
incorporated into Supplement 3S-1 of NQA-1.
Reg. Guide 1.33 lists the activities that require procedures. Will continue to have procedures of the types addressed by Reg.
Guide 1.33.
N45.2 - Instructions, procedures, or drawings shall include            These documents shall include or reference appropriate                Similar requirement. NQA-appropriate quantitative or qualitative criteria for determining      quantitative or qualitative acceptance criteria for determining        1 is not as detailed in that important activities have been satisfactorily accomplished,      that prescribed activities have been satisfactorily accomplished,      describing examples of The activity may be prescribed in job specifications, work                                                                                    quantitative criteria. The instructions, shop construction drawings, job tickets, planning                                                                              requirement regarding sheets, operating or procedure manuals, test procedures, or any                                                                              approved preplanned other type of written form, provided that the activity is                                                                                    methods is addressed in the adequately described. Quantitative criteria, such as dimensions,                                                                              Introduction to Part II of tolerances, and operating limits, and qualitative criteria, such as                                                                          NQA-1 and in the comparative workmanship samples, shall be specified, as                                                                                      appropriate Subparts.
appropriate, for determining satisfactory work performance and quality compliance.
ANSI N18.7 - 5.3 These procedures shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
These procedures shall provide an approved preplanned method of conducting operations. Procedures shall be prepared and approved prior to implementation as required by 4.3 and 5.2.15.
ANSI N18.7 - 5.2.2 Procedure Adherence. Procedures shall be                                                                                  The requirement to have followed, and the requirements for use of procedures shall be                                                                                and work in accordance prescribed in writing. Rules shall be established which provide                                                                              with procedures is methods by which temporary changes to approved procedures                                                                                    addressed in the Basic can be made, including the designation of a person or persons                                                                                Requirement of NQA- 1.
authorized to approve such changes. Temporary changes which                                                                                  The level of detail of N18.7 clearly do not change the intent of the approved procedure,                                                                                  is not contained in the Basic shall as a minimum be approved by two members of the plant                                                                                    or Supplemental staff knowledgeable in the areas affected by the procedures. At                                                                              requirements of NQA- 1.
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CRITERION'$,.                                                BASIC.REQUIREMENTW 5          CMMEN.
ANSI N45.2-1971. 6-  6 ANSI N18.741976                                              NQA-l 1994    ___________
least one of these individuals shall be the supervisor in charge                                              This is addressed in Part V, of the shift and hold a senior operators license on the unit                                                  Section 3 of the QAPD.
affected. Such changes shall be documented and, if appropriate, incorporated in the next revision of the affected procedure. In the event of an emergency not covered by an approved procedure, operations personnel shall be instructed to take action so as to minimize personnel injury and damage to the facility and to protect health and safety.
Guidance should be provided to identify the manner in which procedures are to be implemented. Examples of such guidance include identification of those tasks that require:
(1) The written procedure to be present and followed step by step while the task is being performed (2) The operator to have committed the procedural steps to memory (3) Verification of completion of significant steps, by initials or signatures, of checkoff lists.
The types of procedures that shall be present and referred to directly are those developed for extensive or complex jobs where reliance on memory cannot be trusted, e.g., reactor start-up, tasks which are infrequently performed, and tasks in which operations must be performed in a specified sequence.
Procedural steps for which actions should be committed to memory include, for example, immediate actions in emergency procedures. Routine procedural actions that are frequently repeated may not require the procedure to be present. Copies of all procedures shall be available to appropriate members of the plant staff. If documentation of an action is required, the necessary data shall be recorded as the task is performed.
Examples of procedures requiring verification are furnished in 5.3.4.1 and 5.3.4.2.
ANSI N18.7 5.2.3 Operating Orders. A mechanism shall be                                                      No similar specifics in provided for dissemination to the plant staff of instructions of                                              NQA-1. Addressed in Part general and continuing applicability to the conduct of business.                                              V, Section 3.0 of the Such instructions, sometimes also referred to as standing orders                                              QAPD.
or standard operating procedures, should deal with job turnover and relief, designation of confines of control room, definition of duties of operators and others, transmittal of operating data to 10/28/2010                                                        Instructions, Procedures, and Drawings                      Page 4 of 15
 
CRITERION 5BASIC                                                      REQUIREMENT 5                COMMENTS ANSI N45.2-l971:J 6- ANSI N18.7-1976                                              NQA-1 1994.~___________
management filing of charts, limitations on access to certain areas and equipment, shipping and receiving instructions, or other such matters. Provisions should be made for periodic review and updating of standing orders.
ANSI N18.7 5.2.4 Special Orders. A mechanism shall be                                                                  No similar specifics in provided for issuing management instructions which have short-                                                        NQA-1. Addressed in Part term applicability and which require dissemination. Such                                                              V, Section 3.0 of the instructions, sometimes referred to as a special orders, should                                                        QAPD.
encompass special operations, housekeeping, data taking, publications and their distribution, plotting process parameters, personnel actions, or other similar matters. Provisions should be made for periodic review, updating and cancellation of special orders.
ANSI N18.7 5.2.5 Temporary Procedures. Temporary                                                                      No similar specifics in procedures may be issued during the operational phase: to                                                              NQA-1. Addressed in Part direct operations during testing, refueling, maintenance and                                                          V, Section 3.0 of the modifications; to provide guidance in unusual situations not                                                          QAPD.
within the scope of the normal procedures; and to insure orderly and uniform operations for short periods when the plant, a system, or a component of a system is performing in a manner not covered by existing detailed procedures or has been modified or extended in such a manner that portions of existing procedures do not apply. Temporary procedures shall include designation of the period of time during which they may be used and shall be subject to the review process prescribed in 4.3 and 5.2.15 as applicable.
Temporary procedures shall be approved by the management representative assigned approval authority.
ANSI N18.7 5.3 Preparation of Instructions and Procedures.                                                            No similar specifics in The administrative controls and quality assurance program shall                                                        NQA-1. Addressed in Part be carried out throughout plant life in accordance with written                                                        V, Section 3.0 of the procedures. Activities affecting safety at nuclear power plants                                                        QAPD.
shall be described by written procedures of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions and procedures. These procedures shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished. These procedures shall provide an 10/28/2010                                                      Instructions, Procedures, and Drawings                                Page 5 of 15
 
CRITERION          .      ,.    .                            BASIC.REQUIREMENT..        COMMENTS ANSI N45.2-197:&sect; 66- ANSI N1*.7-4976                                                NQA-1 1994 approved preplanned method of conducting operations.
Procedures shall be prepared and approved prior to implementation as required by 4.3 and 5.2.15.
.ANSI N18.7 5.3.1 Procedure Scope. Each procedure shall be                                                  No similar specifics in sufficiently detailed for a qualified individual to perform the                                            NQA-1. Addressed in Part required function without direct supervision, but need not                                                  V, Section 3.0 of the provide a complete description of the system or plant process                                              QAPD.
ANSI N18.7 5.3.2 Procedure Content. The format of                                                          NQA- I addresses the main procedures may vary from plant to plant, depending on the                                                  requirements of this in Part policies of the owner organization. However, procedures shall                                              II, the remainder is include, as appropriate, the following elements:                                                            addressed in Part V, Section (1) Title. Each procedure should contain a title                                                  3.0 of the QAPD.
descriptive of the work or system or unit to which it applies, a revision number or date, and an approval status.
(2) Statement of Applicability. The purpose for which the procedure is intended should be clearly stated; for example, for use during reactor or plant start-up. If the purpose is not clear from the title, a separate statement of applicability should be provided, which may identify the reasons for particular operations.
(3) References. References, including reference to technical specifications, should be included in procedures as applicable. References should be identified within the body of procedures when the sequence of steps requires other tasks to be performed prior to or concurrent with a particular step within that task.
(4) Prerequisites. Each procedure should identify those independent actions or procedures which shall be completed and plant conditions which shall exist prior to its use.
Prerequisites applicable only to certain sections of a procedure should be so identified.
(5) Precautions. Precautions should be established to alert the individual performing the task to those important measures which should be used to protect equipment and personnel, including the public, or to avoid an abnormal or emergency situation. It may be convenient to specify precautions separately. Cautionary notes applicable to specific steps in the procedure should be included in the main body of Page 6 of 15 10/28/20 10 10/28/2010                                                      Instructions, Procedures, and Drawings Instructions, Procedures, and Drawings                    Page 6 of 15
 
CRIT.ERION5                                                  BASICREQUIREMENT 5      COMMENTS ANSI N45.2-1971 &sect; 6-A  -NS.I N10-.7-4970                                          NQA- 1994 the procedure and should be identified as such.
(6) Limitations and Actions. Limitations on the parameters being controlled and appropriate corrective measures to return the parameter to the normal control band should be specified. It may be convenient to specify limitations and setpoints in a separate section. Where appropriate, quantitative control guides should be provided; for example, an appropriate step of a procedure should say "Manually adjust the feedwater flow controller to maintain the reactor water level at x feet," rather than "Manually adjust the feedwater flow to maintain water level."
(7) Main Body. The main body of a procedure should contain step-by-step instructions in the degree of detail necessary for performing a required function or task.
(8) Acceptance Criteria. Procedures should contain, where applicable, acceptance criteria against which the success or failure of test-type activity would be judged. In some cases there would be qualitative criteria, i.e., a given event does or does not occur. In other cases quantitative values would be designated.
(9) Checkoff Lists. Complex procedures should have checkoff lists. These lists may be included as part of the procedure or may be appended to the procedure.
ANSI N18.7 5.3.3 System Procedures. Instructions for                                                      No similar specifics in energizing, filling, venting, draining, starting up, shutting down,                                        NQA-I.
changing modes of operation and other instructions appropriate                                            Addressed in Part V, for operations of systems related to the safety of the plant shall                                        Section 3.0 of the QAPD.
be delineated in system procedures. Procedures for correcting off-normal conditions shall be developed for those events where system complexity may lead to operator uncertainty. System procedures shall contain checkoff lists where appropriate.
ANSI N18.7 5.3.4 General Plant Procedures. General plant                                                  No similar specifics in procedures provide instructions for the integrated operations of                                          NQA-1. Addressed in Part the plant. In addition to the characteristics of procedures                                                V, Section 3.0 of the presented in 5.3.1 and 5.3.2, details concerning specific general                                          QAPD.
plant procedures are emphasized in the following sections.
ANSI N18.7 5.3.4.1 Start-up Procedures. Start-up procedures                                                No similar specifics in shall be provided that include starting the reactor from cold or                                          NQA-1.
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CRITERION 5                                                BASIC REQUIEME'NT 5                    COMMENTS ANSI &#xfd;N45.2-1971&sect;* 6- ANSI N!8.7-976                                              NQA-1 1994....... .......
hot conditions and establishing power operation, with the                                                              Addressed in Part V, generator synchronized to the line. Recovery from reactor trips                                                        Section 3.0 of the QAPD.
shall be in accordance with the start-up procedure and shall be subject to the determinations set forth in 5.2.1.
(1) Prerequisites. Start-up procedures shall include provisions for documented determination that prerequisites have been met, including confirmation that necessary instruments are operable and properly set; valves are properly aligned; necessary systems procedures, tests and calibrations have been completed; and required approvals have been obtained. Checkoff lists are normally used for this purpose.
(2) Main Body. The main body of the start-up procedures shall include the major steps of the start-up sequence, including reference to appropriate system procedures.
Such major steps shall include or reference detailed instructions for their performance, for example, minimum instrumentation requirements, coverage of control rod withdrawal sequence or soluble poison dilution, manipulation of controls, establishment of feed and steam flow and turbine start-up and synchronization. Checkoff lists should be used for the purpose of confirming completion of major steps in proper sequence.
ANSI N18.7 5.3.4.2 Shutdown Procedures. Shutdown                                                                        No similar specifics in procedures shall be provided to guide operations during and                                                            NQA-1.
following controlled shutdown or reactor trips and shall include                                                        Addressed in Part V, instructions for establishing or maintaining hot standby or cold                                                        Section 3.0 of the QAPD.
shutdown conditions, as applicable. The major steps involved in shutting down the plant shall be specified, including detailed instructions for the performance of such actions as monitoring and controlling reactivity, load reduction and cooldown rates, sequence of activating or deactivating equipment, requirements for prompt analyses of causes of reactor trips or abnormal conditions requiring unplanned controlled shutdowns, and provisions for decay heat removal. Checkoff lists should be used for the purpose of confirming completion of major steps in proper sequence.
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SCRITERION                                                    BASIC REQUIREMENT 5
                                                        ,CRITERON                                            5COMMENTS ANSI N45.2-1971 &sect; 6- ANSI N18 7-1976.NQA-1                                                  1994 .
ANSI N18.7 5.3.4.3 Power Operation and Load Changing                                                                    No similar specifics in Procedures. Procedures for steady-state power operation and                                                            NQA-l.
load changing shall be provided that include, for example,                                                              Addressed in Part V, provisions for use of control rods, chemical shim, coolant flow                                                        Section 3.0 of the QAPD.
control or any other system available for long- or short-term control of reactivity, making deliberate load changes, responding to unanticipated load changes and adjusting operating parameters.
ANSI N18.7 5.3.4.4 Process Monitoring Procedures.                                                                      No similar specifics in Procedures for monitoring performance of plant systems shall                                                            NQA-1.
be required to assure that core thermal margins and coolant                                                            Addressed in Part V, quality are maintained at all times, that integrity of fission                                                          Section 3.0 of the QAPD.
product barriers is maintained at all times and that engineered safety features and emergency equipment are in a state of readiness to maintain the plant in a safe condition if needed.
The limits (maximum and minimum) for significant process parameters shall be identified. The nature and frequency of this monitoring shall be covered by operating procedures, as appropriate.
ANSI N18.7 5.3.4.5 Fuel-Handling Procedures. Fuel-handling                                                              No similar specifics in operations shall be performed in accordance with written                                                                NQA-1.
procedures. These procedures shall specify actions for core                                                            Addressed in Part V, alterations, accountability of fuel and partial or complete                                                            Section 3.0 of the QAPD.
refueling operations that include, for example, continuous monitoring of the neutron flux throughout core loading, periodic recording of date, audible annunciation of abnormal flux increases and evaluation of core neutron multiplication to verify the safety of loading increments.
Provisions shall be made for preparing specific procedures for each refueling outage and for receipt and shipment of fuel.
Plant procedures should, nonetheless, prescribe the general preplanning for the fuel-handling program and its associated safety measures and should identify those aspects of the program for which procedures are to be prepared for each refueling outage.
(1) Prerequisites. Prerequisites shall be provided in the fuel-handling procedures that include, for example, the status of plant systems required for refueling; inspection of replacement 10/28/2010                                                      Instructions, Procedures, and Drawings                                Page 9 of 15
 
            .  **..  :i**.CRITERION"5.".: .*.;..i:.":. . *,.." ,* . ' *!.        '""*.BASIC  REQ,.UI[REMENT 5,* : ....... ..... .. "!",*COM MENTfS*."
N45.2-147if&sect; -.ANSI N18.7-1976                  .ANSI                    NQA-1 1994                                C.MM.NTS fuel, control rods, poison curtains and internals; designation of proper tools; proper conditions for spent fuel movement; proper conditions for fuel cask loading and movement; and status of interlocks, reactor trip circuits and mode switches.
(2) Main Body. The main body of fuel- handling procedures shall include requirements for refueling; for example, the status of the core, instructions for proper sequence, orientation, and seating of fuel and components, rules for minimum operable instrumentation, actions to be followed in the event of fuel damage, rules for periods when refueling is interrupted, verification of the shutdown margin and the frequency of determination, communications between control room and the fuel loading station, independent verification of fuel and component location, criteria for stopping refueling and for reducing the size of the fuel loading increment, and a containment evacuation plan and its associated safety measures.
Documentation of final fuel and component serial numbers and locations shall be maintained.
ANSI N18.7 5.3.6 Radiation Control Procedures. Procedures                                                                        No similar specifics in shall be provided for implementation of a radiation control                                                                      NQA-1.
program to meet applicable program requirements. The                                                                              Addressed in Part V, radiation control program involves the acquisition of data and                                                                    Section 3.0 of the QAPD.
provision of equipment to perform necessary radiation surveys, measurements and evaluations for the assessment and control of radiation hazards associated with a nuclear power plant.
Procedures shall be developed and implemented for: monitoring both external and internal exposures of employees, utilizing accepted techniques; routine radiation surveys of work areas; environmental monitoring in the vicinity of the plant; radiation monitoring of maintenance and special work activities; and for maintaining records demonstrating the adequacy of measures taken to control radiation exposures of employees and others.
ANSI N18.7 5.3.7 Calibration and Test Procedures. Procedures                                                                      No similar specifics in shall be provided for periodic calibration and testing of safety-                                                                NQA-1.
related instrumentation and control systems. Procedures shall                                                                    Addressed in Part V, also be provided for periodic calibration of measuring and test                                                                  Section 3.0 of the QAPD.
equipment used in activities affecting the quality of these systems. The procedures shall provide for meeting surveillance 10/28/2010                                                    Instructions, Procedures, and Drawings                                          Page 10 of 15
 
CRITERION 5.                                              BASIC REQUIR-EMENT 5                            COMMENTS ANSI N451.-1971 &sect; 6- ANSI N18.7-1976.                                            NQA-1 1994 .____._.___'___""....                            _
schedules and for assuring measurement accuracy adequate to keep safety-related parameters within operational and safety limits.
ANSI N18.7 5.3.8 Chemical-Radiochemical Control                                                                              No similar specifics in Procedures. Procedures shall be provided for chemical and                                                                      NQA-1.
radiochemical control activities. They should include, for                                                                    Addressed in Part V, example, the nature and frequency of sampling and analyses;                                                                    Section 3.0 of the QAPD.
instructions for maintaining coolant quality within prescribed limits; and limitations on concentrations of agents that could cause corrosive attack, foul heat transfer surfaces or become sources of radiation hazards due to activation.
Procedures shall also be provided for the control, treatment and management of radioactive wastes and control of radioactive calibration sources.
ANSI N18.7 5.3.9 Emergency Procedures. Procedures shall be                                                                    No similar specifics in provided to guide operations during potential emergencies.                                                                    NQA-1. Addressed in Part They shall be written so that a trained operator will know in                                                                  V, Section 3.0 of the QAPD advance the expected course of events that will identify an                                                                    in accordance with current emergency and the immediate action he should take. Since                                                                      requirements for these type emergencies may not follow anticipated patterns, the                                                                          procedures.
procedures should provide sufficient flexibility to accommodate variations.
Emergency procedures that cover actions for manipulations of controls to prevent accidents or lessen their consequences should be based on a general sequence of observations and actions. Emphasis should be placed on operator responses to observations and indications in the control room; that is, when immediate operator actions are required to prevent or mitigate the consequences of a serious condition, procedures should require that those actions be implemented promptly The emergency procedure format given in 5.3.9.1 provides a basis for coping with emergencies and is an acceptable format for prescribing operator observations and actions. Emergency procedures may contain supplemental background information to further aid operators in taking proper emergency actions, but this information shall be separated from the procedural actions.
It is extremely difficult to distinguish between procedures prepared for the purpose of correcting off-normal conditions 10/28/2010                                                    Instructions, Procedures, and Drawings                                        Page I11 of 15
 
                              !ITERI[ONS 1: 717                                      BASIC REQUIREMENT 5CM                          ET
.......... AN.SI N45.27,1971',:4.6 -'ANSI N 8        976. .                                  NQA-.1  1994.,.,
4._..  ,....        . ...  .    .. . ..
which in themselves do not constitutes actual emergency situations, but which conceivably can degenerate into true emergencies in the absence of positive corrective action and procedures required for coping with true emergencies that have already occurred. Some owner organizations choose the term "Off-normal Procedures" for the same purpose that others choose "Emergency Procedures." When initially available intelligence provided to operating personnel via instrument readings, physical conditions, and personal observations may not clearly indicate the difference between a simple operational problem and a serious emergency, the actions outlined in the emergency procedures shall be based on a conservative course of action by the operating crew. Considerable judgment on the part of competent personnel is required before departing from the emergency procedure.
(17) With regard to Section 5.3.9 of ANSI N18.7-1976, titled Emergency Procedure: As directed by the NRC, the Industry follows a format for emergency procedures which is "symptom" based as opposed to "event" based as stipulated in Section 5.3.9.1. Since VCSNS has these "symptom" based procedures; "event" based procedures are not normally provided.
ANSI N18.7 5.3.9.1 Emergency Procedure Format and Content.                                                            No similar specifics in Emergency procedures shall include, as appropriate, the                                                              NQA-1. Addressed in Part following elements:                                                                                                  V, Section 3.0 of the QAPD (1) Title. The title should be descriptive of the                                                          in accordance with the emergency for which the procedure is provided.                                                                        current requirements for (2) Symptoms. Symptoms should be included to aid in                                                        these type procedures.
the identification of the emergency. They should include alarms, operating conditions and probable magnitudes of parameter changes. If a condition is peculiar only to the emergency under consideration, it should be listed first (3) Automatic Actions. The automatic actions that will probably occur as a result of the emergency should be identified.
(4) Immediate Operator Actions. These steps should specify immediate actions for operation of controls or confirmation of automatic actions that are required to stop the degradation of conditions and mitigate their consequences.
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CRITERION 5                              1BASIC                    REQUIREMENT 5      COMMENT ANSI N45.2-19 .71, 66-r ANSI N18.7-1976                                            NQA-l14994    _ __________
Examples include the following: (a) The verification of automatic actions. This step is based on equipment operating as designed and the sequence of events following an expected course. Since variations from the expected course may occur, operators should be prepared to manipulate controls as necessary to cope with the problem. However, the procedure should caution the operator not to place systems in "manual" unless misoperation in "automatic" is apparent and should require him to make frequent checks for proper operation of systems placed in manual control. (b) Assurance that reactor is in a safe condition. This step usually means shutdown of the reactor with sufficient reactivity margin and establishment of required core cooling. (c) Notification to plant personnel of the nature of the emergency. (d) Determination that the reactor coolant system pressure boundary is intact. (e) Confirmation of the availability of adequate power sources. (f) Confirmation that containment and exhaust systems are operating properly in order to prevent uncontrolled release of radioactivity.
(5) Subsequent Operator Actions. Steps should be included to return the reactor to a normal condition or to provide for a safe extended shutdown period under abnormal or emergency conditions.
5.3.9.2 Events of Potential Emergency. Potential emergency conditions shall be identified and procedures for coping with them shall be prepared. The following categories of events may, depending upon the design of the plant, be considered as examples of potential emergencies for which procedures are written and for which immediate action is indicated:
(1) Loss of coolant from identified and unidentified sources, from small loss to design-basis-accident loss (2) Reactor transients and excursions (3) Failure of vital equipment (4) Loss or degradation of vital power sources (5) Civil disturbances (6) Abnormally high radiation levels (7) Excessive release of radioactive liquid or gaseous effluent (8) Malfunction of reactivity control system Page 13 of 15 10/28/2010                                                      Instructions, Procedures, and Drawings Instructions, Procedures, and Drawings                    Page 13 of 15
 
CRITERION 5                          "BASIC                          REQUWMENT 5          COMMENTS ANSIN45.2r1971 &sect; 6 ,ANSI N18.7-1976                                                NQA-1 1994  ___________
(9) Loss of containment integrity (10) Conditions that require use of standby liquid poison systems (11) Possible natural occurrences (12) Fires 5.3.9.3 Procedures for Implementing Emergency Plan.
Implementing procedures for emergency plan actions shall contain, as appropriate, the following elements:
(1) Individual assignment of authorities and responsibilities for performance of specific tasks to specific individuals or staff positions.
(2) Protective action levels and protective measures outlined for the emergency identified.
(3) Specific actions to be taken by coordinating support groups.
(4) Procedures for medical treatment and handling of contaminated individuals.
(5) Special equipment requirements for items such as medical treatment, emergency personnel removal, specific radiation detection, personnel dosimetry and rescue operations, procedures for making this equipment available, plus operating instructions for such equipment, and provisions for its periodic inspection and maintenance.
(6) Identification of emergency communications network, including communications required for personnel identification and effective coordination of all support groups.
(7) Description of alarm signals in each facility. At sites with multiple units, alarm signals should be consistent from one unit to another. (Signals for initiating protective measures should be clear and distinct from process or operational alarm system to avoid confusion.)
(8) Procedures required to restore the plant to normal conditions following an emergency.
(9) Requirements for periodically testing of procedures, communications network and alarm systems to assure that they function properly.
5.3.9.3 See also U.S. Nuclear Regulatory Commission (NRC) "Guide 10/28/2010                                                      Instructions, Procedures, and Drawings                  Page 14 of 15
 
CRIUTERION 5                                                BASIC REQUIREMENT S        COMMENTS ANSI N45.2-197.1 &sect; 6 -ANSI N18.7-1976                                              NQA-711994 '
to the Preparation of Emergency Plans for Production and Utilization Facilities."
(19) With regard to Section 5.3.9.3 of ANSI N18.7-1976, titled Procedures for Implementing Emergency Plan: VCSNS's NRC accepted Emergency Plan will be implemented.
ANSI N18.7 5.3.10 Test and Inspection Procedures. Test and                                                  No similar specifics in inspection procedures shall contain a description of objectives;                                            NQA-1. Addressed in Part acceptance criteria that will be used to evaluate the results;                                              V, Section 3.0 of the prerequisites for performing the tests or inspections including                                            QAPD.
any special conditions to be used to simulate normal or abnormal operating conditions; limiting conditions; and the test or inspection procedure. These procedures shall also specify any special equipment or calibrations required to conduct the test or inspection. Test and inspection results shall be documented and evaluated by responsible authority to assure that test and inspection requirements have been satisfied.
Where tests and inspections are to be witnessed, the procedure shall identify hold points in the testing sequence to permit witnessing. The procedure shall require appropriate approval for the work to continue beyond the designated hold point. The test and inspection procedures shall require recording the date, identification of those performing the test or inspection, as-found condition, corrective actions performed, if any, and as-left condition.
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CRITERION.6                                                BASIC REQUI.EMENT.6                                  COMMENTS.
ANSI N45.2.-19711Nj4.7,-t976 &sect; 5.2.15                                            N"Q4 1994                                                          "
N45.2 &sect;7 &#xb6; 1 Measures shall be established and documented to      The preparation, issue, and change of documents that specify  Similar requirement.
control the issuance of documents, such as instructions,          quality requirements or prescribe activities affecting quality procedures, and drawings, including changes thereto, which        shall be controlled to assure that correct documents are being ANSI N 18.7 contains some prescribe activities affecting quality.                            employed,                                                      additional information ANSI N18.7-5.2.15 The administrative controls and quality                                                                        regarding Document control assurance program shall provide measures to control and                                                                          that is not reflected in the coordinate the approval and issuance of documents, including                                                                      basic or supplemental changes thereto, which prescribe all activities affecting quality,                                                                requirements of NQA-1.
Such documents include those which describe organizational                                                                        These aspects are addressed interfaces, or which prescribe activities affecting safety-related                                                                in the QAPD, Part II, structures, systems, or components. These documents also                                                                          Section 6.
include operating and special orders, operating procedures, test procedures, equipment control procedures, maintenance or modification procedures, refueling, and material control procedures.
N 45.2 &sect;7 &#xb6; 1 These measures shall assure that documents,          Such documents, including changes thereto, shall be reviewed  Similar requirement.
including changes, are reviewed for adequacy and approved for      for adequacy and approved for release by authorized personnel.
release by authorized personnel and are distributed to and used                                                                  N18.7 has more detailed at the location where the prescribed activity is performed.                                                                      review requirements. The ANSI N18.7-5.2.15 These measures shall assure that                                                                                QAPD has met the intent of documents, including revisions or changes, are reviewed for                                                                      Nl18.7 through the modified adequacy by appropriately qualified personnel and approved for                                                                    review programs that had release by authorized personnel; and are distributed in                                                                          previously been established accordance with current distribution lists and used by the                                                                        in lieu of the specific personnel performing the prescribed activity, and that                                                                            review periodicity defined procedures are provided to avoid the misuse of outdated or                                                                        in N 18.7 (biennial review).
inappropriate documents.                                                                                                          The VCSNS Unit 1 review Procedures for operational phase activities of a nuclear power                                                                    program is addressed in Part plant reflect the conditions that exist at the time the procedures                                                                HI,Section 6 of the QAPD are written. These conditions include the technical information                                                                  and a biennial review for all available, industry experience, and in the case of the initial                                                                    procedures is not committed procedures for a new plant, assumptions made regarding the                                                                        to in the new program.
detailed behavior of the plant that may not be fully known prior                                                                  Regulatory requirements for to operation. In order to ensure that the procedures in current                                                                  specific reviews will use provide the best possible instructions for performance of                                                                    continue to be met.
the work involved, systematic review and feedback of information based on use is required.
Each procedure shall be reviewed and approved prior to initial 10/28/2010                                                              Document Control                                                            Page I of 5
 
CRITERION 6                                          BASIC REQQUIREM.ENT 6 COMMENTS ANSI N45.2-19711/N1.7-1976 ..... &sect; ....
5.2.15 ..        1
                                                              ......                  NQA-1 1994 use. The frequency of subsequent reviews shall be specified and may vary depending on the type and complexity of the activity involved, and may vary with time as a given plant reaches operational maturity. Applicable procedures shall be reviewed following an unusual incident, such as an accident, an unexpected transient, significant operator error, or equipment malfunction. Applicable procedures shall be reviewed following any modification to a system.
Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years to determine if changes are necessary or desirable. A revision of a procedure constitutes a procedure review.
Procedures shall be approved as designated by the owner organization before initial use. Rules shall be established which clearly delineate the review of procedures by knowledgeable personnel other than the originator and the approval of procedures and procedure changes by authorized individuals.
The following exception is in the FSAR Section 3, Appendix 3A:
VCSNS complies with the recommendations of Regulatory Guide 1.33 as discussed in Section 17.2 and Section 6.0 of the Technical Specifications with the following exceptions and clarifications: 1. The plant has programmatic control requirements in place that make the biennial review process redundant. These programmatic controls were affected in an effort to ensure that plant instructions and procedures are reviewed for possible revision when pertinent source material is revised, therefore maintaining the procedures current. In addition to these controls, the Quality Systems group will perform a biennial Quality Assurance Audit of the procedural development program utilizing a representative sampling process, thereby providing verification that the controls are effective in maintaining procedures current. SCE&G believes that this approach better addresses the intent of the biennial review process and is more acceptable from both a technical and a practical perspective than a static two-year review process.
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CRITERION 6:            ...                              BASIC REQUIREMENT 6                                COMMENTS ASI_ N4.971iIN8.7-1976:&sect; 5.2.15~                                          NQA-1 1994 SUPPLEMENT 6S-1 Supplementary Requirements For Document Control I GENERAL This Supplement provides amplified requirements for a document control system.
It supplements the requirements of Basic Requirement 6 of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
The documents which shall be controlled in accordance with    NQA 1-1994 added a this Supplement are only those documents which specify        requirement that describes quality requirements or prescribe activities affecting quality what falls under the such as instructions, procedures, and drawings.                document control supplement.
The term document control used throughout this Supplement is  NQA 1-1994 added defined as the act of assuring that documents are reviewed for language to bound and limit adequacy, approved for release by authorized personnel, and    what falls under document distributed to and used at the location where the prescribed  control.
activity is performed.
2 DOCUMENT PREPARATION, REVIEW, APPROVAL, AND ISSUANCE N 45.2 &sect;7 &#xb6; 2 Those participating in an activity shall be made                                                                General language that meets aware of and use proper and current instructions, procedures,                                                                  the intent of N18.7 has been drawings, and engineering requirements for performing the                                                                      included in Section 6 of the activity. Participating organizations shall have procedures for                                                                QAPD.
control of the documents and changes thereto to preclude the possibility of use of outdated or inappropriate documents.
ANSI N18.7-5.2.15 Those participating in any activity shall be made aware of, and use, proper and current instructions, procedures, drawings, and engineering requirements for performing the activity. Participating organizations shall have procedures for control of the documents and changes thereto to preclude the possibility or use of outdated or inappropriate documents.
N 45.2 &sect;7 &#xb6; 3 Document control measures shall provide for: (1)  The control system shall be documented and shall provide for  Similar requirement.
identification of individuals or organizations responsible for  (a) through (c) below:
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C.RITERION 6                                              BASIC REQUIREMENT,6                                    COMMENTS,*
ANSI N45.2-19711N.18.7-1976 &sect; 5.115NQA-1                                                199,4 preparing, reviewing, approving, and issuing documents and      (a) identification of documents to be controlled and their        ANSI Ni18.7 contains some revisions thereto; (2) identifying the proper documents to be    specified distribution;                                          additional information used in performing the activity; (3) coordination and control of (b) identification of assignment of responsibility for preparing, regarding Document control interface documents; (4) ascertaining that proper documents are  reviewing, approving, and issuing documents;                      that is not reflected in the being used; (5) establishing current and updated distribution    (c) review of documents for adequacy, completeness, and          basic or supplemental lists.                                                          correctness prior to approval and issuance.                      requirements of NQA-1.
ANSI N18.7-5.2.15 Document control measures shall provide                                                                          These aspects are addressed for: (1) Identification of individuals or organizations                                                                            in the QAPD, Part II, responsible for preparing, reviewing, approving, and issuing                                                                      Section 6.
documents and revisions thereto; (2) Identifying the proper documents to be used in performing the activity; (3)
Coordination and control of interface documents; (4)
Ascertaining that proper documents are being used; (5)
Establishing current and updated distribution lists.
3 DOCUMENT CHANGES 3.1 Major Changes N 45.2 &sect;7 &#xb6; 1 Changes to documents shall be reviewed and        Changes to documents, other than those defined as minor          Similar requirements approved by the same organizations that performed the original  changes in para. 3.2 below, are considered as major changes review and approval unless other organizations are specifically  and shall be reviewed and approved by the same organizations designated.                                                      that performed the original review and approval unless other ANSI N18.7-5.2.15 Changes to documents shall be reviewed        organizations are specifically designated.
and approved by the same organizations that perform the original review and approval unless the owner organization designates another qualified organization.
N 45.2 &sect;7 &#xb6; 1 The reviewing organizations shall have access to  The reviewing organization shall have access to pertinent        Similar requirements pertinent background information upon which to base its          background data or information upon which to base their approval and shall have adequate understanding of the            approval.
requirements and intent of the original document.
ANSI N18.7-5.2.15 The reviewing organizations shall have access to pertinent background information upon which to base its approval and shall have adequate understanding of requirements and intent of the original document.
3.2 Minor Changes Minor changes to documents, such as inconsequential editorial    Additional requirement.
corrections, shall not require that the revised documents receive the same review and approval as the original documents.
To avoid a possible omission of a required review, the type of    Additional requirement.
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CRITEffQN 6~.                              BASIC REQUJIREMENT 6.                          COMMENTS AN 5"1N9711199741976&sect;"5.2.15    "                ."  "    A-9          .      ....      . ',
minor changes that do not require such a review and approval and the persons who can authorize such a decision shall be I clearly delineated.
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CRITERION 7                                                  BASIC REQUIREM.ENT 7                                        COMMENTS ASI N45.2 1971 -ANSI N45.2.13-1976                                                  NQA-1 1994
:'ANSI N18.7- 19.76                                                    <.,
N45.2 &sect; 8 and N18.7 &sect; 5.2.13.2, unless otherwise noted.
N45.2 Measures shall be established and documented to assure          The procurement of items and services shall be controlled to        Similar requirement.
that purchased items and services, whether purchased directly        assure conformance with specified requirements.
or through contractors, conform to the procurement documents.
N18.7 Measures shall be provided to assure that purchased items and services, whether purchased directly or through contractors, conform to the procurement documents.
N45.2 These measures shall include provisions, as appropriate,        Such control shall provide for the following as appropriate:        Similar requirement.
for source evaluation and selection, objective evidence of            source evaluation and selection, evaluation of objective quality furnished by the contractor, inspection and audit at the      evidence of quality fuirnished by the Supplier, source source, and examination of items upon delivery,                      inspection, audit, and examination of items or services upon N18.7 These measures shall include provisions, as appropriate,        delivery or completion.
for source evaluation and selection, objective evidence of quality furnished by the contractor, inspection and audit at the source and examination of items upon delivery.
SUPPLEMENT 7S-1, SUPPLEMENTARY REQUIREMENTS FOR CONTROL OF PURCHASED 102/00Cnrlo                                  ucae ITEMSMaterial:,
AND Equipment:
                                                                                          *'.=..,i (Items)*and:".***...
SERVICES                  Services :. . ..    ..:., _________
                                                                                                                                                      *"
* Page'*
                                                                                                                                                              * *1 of: 22*
:i .
___________________________ 1 GENERAL________
N45.2.13 &sect; 1.1 Scope                                                  This Supplement provides amplified requirements for control of NQA- 1 addresses This standard describes requirements and provides guidelines          purchased items and services. It supplements the requirements        applicability of the standard for the control of activities to be exercised during procurement      of Basic Requirement 7 of this Part (Part 1) and shall be used in in the introduction to Part 1.
of items and services which affect the quality of nuclear power      conjunction with that Basic Requirement when and to the extent NQA- 1-1994 does not plants. These requirements and guidelines apply to procurement specified by the organization invoking this Part (Part 1). This            contain the limits on use activities for items and services such as designing, purchasing,      Supplement includes requirements for source selection, bid          with ASME 1111  and XI code fabricating, handling, shipping, storing, cleaning, constructing,    evaluation, Supplier performance evaluation, and verification of requirements; therefore, the erecting, installing, inspecting, testing, maintaining, repairing,    conformance.                                                        NRC regulatory position initial fueling, refuieling, and modifying. This standard provides                                                                        (C.2) is addressed.
guidelines for application of quality assurance, program requirements listed in ANSI N45.2 for various types of                                                                                    The quality assurance procurement such as; total system supply, hardware, services,                                                                              requirements of the VCSNS or a combination thereof.                                                                                                                  program, including the This standard applies to the work of any individual or                                                                                    standards of NQA-l, would organization participating in the procurement of those items and                                                                          be used for all activities, services from which satisfactory performance is required. The                                                                              including ASME III and XI extent to which the individual requirements of this standard                                                                              activities and would shall apply will depend upon the nature and scope of the work        ______________________________supplement any specific 10/28/2010                                          Control of Purchased Material, Equipment, (Items) and Services                                        Page I of 22
 
CRITERION7...                                              BASIC REQUIREMENT 7                .COMMENTS*
ANSI N45.2 1971-- ANSI N45.2.13-1976                    I                        NQA-I 1994 ANSI N18.7.-:1976                          1 to be performed and the required quality of the items or services                                                      quality requirements those purchased.                                                                                                            codes invoke.
The ASME Boiler & Pressure Vessel Code (hereafter referred to as the Code, as well as other American National standards,                                                          The NRC regulatory has been considered in the development of this standard, and                                                          position (C.5) is addressed this standard is intended to be compatible with Code                                                                  by exception. No exception requirements. This standard does not, however, apply to                                                                is granted to the purchase of activities covered by Section Ill Divisions I and 2 and Section                                                        spare or replacement parts.
XI of the Code for those activities covered by the Code.                                                              Therefore, these quality Reg. Guide 1.123 Regulatory Position C.2. Section 1.1 of                                                              assurance requirements ANSI N45.2.13-1976 states: "The ASME Boiler & Pressure                                                                would be applied to spare Vessel Code (hereafter referred to as the Code) as well as other                                                      and replacement parts the ANSI standards, has been considered in the development of this                                                        same as new items.
standard, and this standard is intended to be compatible with Code requirements. This standard does not, however, apply to activities covered by Section II, Divisions 1 and 2, and Section XI of the Code for those activities covered by the Code." While Section mI, Division 1 and 2, and Section XI (which addresses the control of spare and replacement parts) of the ASME Boiler and Pressure Vessel Code address general requirements for control of procurement of items and services for nuclear power plants, these sections do not explicitly address all the activities described in the ANSI N45.2.13-1976 standard. ANSI N45.2.13-1976, subject to the exceptions of the regulatory position, should be used in conjunction with the ASME Boiler and Pressure Vessel Code, Section IM,Divisions 1 and 2, and Section XI for control of procurement of items and services where the ASME Code does not address the activities covered by ANSI N45.2.13-1976.
Reg. Guide 1.123 Regulatory Position C.5. ANSI N45.2.13-1976 addresses the control of procurement of items and services that affect the quality of nuclear power plants, including spare and replacement parts. The standard, however, does not provide "requirements" specific to spare and replacement parts. Section 5.2.13 of ANSI N18.7-1976/ANS 3.2, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," which is endorsed by Regulatory Guide 1.33,          J                                              .5.
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CIEIN7BASIC                                                REQUIREMENT 7                              COMMENTS IN45:2 CIEIN              7 NN 4      .2171 ANSI N45.2.13-1976          .                                ,NQA-1199~4          .        ..                .          .      .
ANSI N18.7    - 1976                          ________________________
"Quality Assurance Program Requirements (Operation),"
addresses control of spare and replacement parts during the operations phase of nuclear power plants. As a result, the provisions of Section 5.2.13 of ANSI N 18.7-1976 related to control of spare and replacement parts are considered applicable and should be used in conjunction with the provisions of ANSI N45.2.13-1976.
2 PROCUREMENT PLANNING N45.2.13 &sect; 2. PLANNING                                                Procurement activities shall be planned and documented to          Similar requirement.
Measures established for the control of the procurement of            assure a systematic approach to the procurement process.
items or services shall include planning.
N45.2.13 &sect; 2 - Control of the procurement process requires the        Procurement planning shall result in the documented                Similar requirement.
identification of organizations involved in the execution of the      identification of procurement methods and organizational activity and the delineation of each organization's                  responsibilities.
responsibility.
Planning shall result in the documented identification of methods to be used in procurement activities, sequence of actions and milestones indicating the completion of these activities, and the preparation of applicable procedures prior to the initiation of each individual activity listed below.
N45.2.13 &sect; 2 - Planning shall determine the following                Planning shall determine the following:                            Similar requirement.
objectives:                                                          (a) what is to be accomplished;
: a. What is to be accomplished.                                        (b) who is to accomplish it;
: b. Who is to accomplish it.                                          (c) how it is to be accomplished;
: c. How it is to be accomplished.                                      (d) when it is to be accomplished
: d. When it is to be accomplished.
N45.2.13 &sect; 2 - These objectives shall be accomplished as early        Planning shall be accomplished as early as practicable, and no    Similar requirement.
as practicable and no later than the start of those procurement      later than at the start of those procurement activities which are activities which are required to be controlled, to assure            required to be controlled, to assure interface compatibility and a interface compatibility and a uniform approach to the                uniform approach to the procurement process.
procurement process.
N45.2.13 &sect; 2 - Planning shall provide for the integration of the      Planning shall result in the documented identification of          These requirements are following:                                                            methods to be used in procurement activities, sequence of          addressed by Supplement
: a. Procurement Document Preparation, Review and Change                actions and milestones indicating the completion of these          7S-I to NQA- I, but this Control.                                                              activities, and the preparation of applicable procedures prior to  level of detail leading in to
: b. Selection of Procurement Sources.                                  the initiation of each individual activity listed below. Planning  the requirements is not used
: c. Bid Evaluation and Award.                                          shall provide for the integration of (a) through (i) below:        within NQA-I.
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CRITERION 7                                                    BASIC REQUIREMENT 7                                      COMMENTS ANI N45.2 1971    - ANSI N45.2.13-1976.                                            NQA-1 1994 ANSI.N18.~7 -1976.                                                                                                _________
: d. Purchaser Control of Supplier Performance.                        (a) procurement document preparation, review, and change
: e. Verification (surveillance, inspection, or audit) Activities by    control; Purchaser.                                                            (b) selection of procurement sources;
: f. Control of Nonconformances.                                        (c) bid evaluation and award;
: g. Corrective Action.                                                (d) Purchaser control of Supplier performance;
: h. Acceptance of Item or Service.                                    (e) verification (surveillance, inspection, or audit) activities by
: i. Quality Assurance Records.                                        Purchaser, including notification for hold and witness points;
: j. Audit of Procurement Program.                                      (f) control of nonconformances; Subsequent sections discuss these activities and their control in    (g) corrective action; accordance with the general requirements of ANSI N45.2 (and          (h) acceptance of item or service; this standard) in greater detail. These activities shall be capable  (i) quality assurance records.
of being verified and their effectiveness determined by audit.
Where any of the procurement activities are delegated or applicable to subtier Suppliers, the appropriate controls and requirements of this standard shall also apply.
3 SUPPLIER SELECTION N45.2 Source inspection or audit shall be performed as                3.1 Source Evaluation and Selection                                Similar requirement.
necessary to assure the required quality of an item. Source          The selection of Suppliers shall be based on evaluation of their inspection or audit may not be necessary when the quality of          capability to provide items or services in accordance with the the item can be verified by review of test reports, inspection        requirements of the procurement documents prior to award of upon receipt, or other means.                                        contract.
N18.7 Source inspection or audit shall be performed as necessary to assure the required quality of an item. Source inspection or audit may not be necessary when the quality of the item can be verified by review of test reports, inspection upon receipt, or other means.
N45.2.13 &sect; 4. SELECTION OF PROCUREMENT SOURCES -
4.1 General - The selection of Suppliers shall be based on evaluation of their capability to provide items or services in accordance with the requirements of the procurement documents, N45.2.13 &sect; 4.2 Selection Measures - Procurement source                Procurement source evaluation and selection measures shall be      Similar requirement.
evaluation and selection measures shall be adopted by the            implemented by the Purchaser and shall provide for Purchaser and shall provide for identification of the Purchaser's    identification of the Purchaser's organizational responsibilities organizational responsibilities for determining Supplier            for determining Supplier capability.
capability. This may require integrated action involving one or more organizations (e.g., engineering, construction, 10/28/2010                                          Control of Purchased Material, Equipment, (Items) and Services                                      Page 4 of 22
 
CRII .      .*TERION 7                                          BASIC REQUIREMNT 7                                      COMM.ENTS ANSI N45.2 1971 - ANSI N45.2.13-1**.                                              NQA-1 1 94 ANS N18.7 -1976 manufacturing, operations, purchasing, or quality assurance) based upon the item or service being procured.
N45.2 Measures for evaluation and selection of procurement          Measures for evaluation and selection of procurement sources,      Similar requirement.
sources include the use of historical quality performance data,    and the results therefrom, shall be documented and shall source surveys or audits, or source qualification programs.        include one or more of (a) through (c) below:
N18.7 Measures for evaluation and selection of procurement sources include the use of historical quality performance data, source surveys or audits, or source qualification programs.
N45.2.13 &sect; 4.2 Methods to be utilized in evaluation of Supplier sources, and the results therefrom, shall be documented and shall include any or all of the following:
N45.2.13 &sect; 4.2 - a. Evaluating the suppliers history of providing  (a) evaluation of the Supplier's history of providing an identical Similar requirement.
a product which performs satisfactory in actual use. Information    or similar product which performs satisfactorily in actual use.
which should be evaluated should include:                          The Supplier's history shall reflect current capability.          This addresses NRC
: 1) Experience of users of identical or similar products of the                                                                        Regulatory Position C.6.a.
prospective Supplier.
: 2) Purchaser's records that have been accumulated in                                                                                  Other details of items 1, 2 connection with previous procurement actions and product                                                                              and the subsequent operating experience.                                                                                                                  paragraph in N45.2.13 are Quality performance is highly dependent upon the Supplier's                                                                            guidance and are addressed personnel capabilities, physical conditions of the manufacturing                                                                      as nonmandatory guidance factory and equipment, and management attitude towards                                                                                in Appendix 7A-1 of NQA-quality. Historical data should be representative of the                                                                              1 &sect;2.1.
Supplier's current capability. If there has been no recent experience with the Supplier, or if he is a new Supplier, the prospective Supplier shall be requested to submit information on a similar item or service for evidence of his current capabilities.
Reg. Guide 1.123 Regulatory Position C.6 In addition to the requirements of the standard, the guidelines (indicated by the verb "should") identified below are considered to have sufficient safety importance to be treated the same as the requirements of the standard. - a. Section 4.2.a - The guidelines used in evaluating the Supplier's history of providing a product that performs satisfactorily in actual use.
N45.2.13 &sect; 4.2 - b. The Supplier's current quality records          (b) Supplier's current quality records supported by documented    Similar requirement.
supported by documented qualitative and quantitative                qualitative and quantitative information which can be 10/28/2010                                        Control of Purchased Material, Equipment, (Items) and Services                                      Page 5 of 22
 
CRITERION 7                                                BASIC RFEQUI          MENT 7                          . COMMENTS            .
ANSI N45.2 1971 - ANSI N45.2.13-1976                                              NQA-1 1994 ANSIN18.7-1976 information which can be objectively evaluated. This would          objectively evaluated; include review and evaluation of the Supplier's Quality Assurance Program, Manual, and Procedures, as appropriate.
N45.2.13 &sect; 4.2 - c. The Supplier's technical and quality            (c) Supplier's technical and quality capability as determined by  Similar requirement.
capability as determined by a direct evaluation of his facilities  a direct evaluation of his facilities and personnel and the and personnel, and the implementation of his quality assurance      implementation of his quality assurance program.
program.
N45.2.13 &sect; 5. BID EVALUATION AND AWARD                              4 BID EVALUATION                                                  Requirement addressed 5.1 General - A documented system for reviewing and                                                                                    through the following evaluating the bids and awarding of contracts shall be                                                                                statements.
established by the Purchaser.
N45.2.13 &sect; 5.2 Conformance to Procurement Document                  Bid evaluation shall determine the extent of conformance to the    Similar requirement.
The Purchaser shall establish measures to assure that the bid      procurement documents. This evaluation shall be performed by conforms to the procurement document requirements. The bid          individuals or organizations designated to evaluate the            NQA-I does not address evaluation shall be made by individuals or organizations            following subjects, as applicable to the type of procurement:      research and development designated to evaluate the following subjects, as applicable to    (a) technical considerations                                      effort as a factor in bid the type of procurement:                                            (b) quality assurance requirements                                evaluation. This would be
: a. Technical considerations.                                        (c) Supplier's personnel                                          covered by evaluation of a
: b. Quality assurance requirements.                                  (d) Supplier's production capability                              Supplier's technical
: c. Research and development effort.                                (e) Supplier's past performance                                    considerations.
: d. Suppliers' Personnel.                                            (f) alternates
: e. Suppliers' production capability.                                (g) exceptions                                                    NQA-1 does not address
: f. Suppliers' past performance.                                                                                                        those items that are not
: g. Alternates.                                                                                                                        considered quality related.
: h. Exceptions.
Other considerations such as warranties, schedule, price, price adjustments commercial terms and conditions, although not quality related, are recognized as factors affecting bid evaluation.
N45.2.13 &sect; 5.3 Preaward Evaluation - Prior to the award of the                                                                        Addressed in section 3 of contract, the Purchaser shall have performed a preaward                                                                                this supplement to NQA-I.
evaluation of the Supplier as described in Section 4.2 of this standard.
N45.2.13 &sect; 5.4 Award - Prior to the award of the contract, the      Prior to the award of the contract, the Purchaser shall resolve or Similar requirement.
Purchaser shall also resolve or obtain commitments to resolve      obtain commitments to resolve unacceptable quality conditions unacceptable conditions resulting from the bid evaluation,          resulting from the bid evaluation.
5 SUPPLIER PERFORMANCE EVALUATION 10/28/2010                                        Control of Purchased Material, Equipment, (Items) and Services                                      Page 6 of 22
* 7
                                                                                .CRITERION BS .. REQU,      . E,.                          COMMENTS ANSI N45.2 1971 - ANSI N45.2.13-1976                                          ASI REQIRMET4 1
      -              ~ANSI N183.;-, 1976:, e9A-1 N45.2.13 &sect; 6. PURCHASER EVALUATION OF SUPPLIER                        The Purchaser of items and services shall establish measures to  Similar requirement.
PERFORMANCE                                                          interface with the Supplier and to verify Supplier's performance 6.1 General - Purchasers at all tiers shall retain the                as deemed necessary by the Purchaser. The measures shall responsibility of monitoring and evaluating Supplier                  include (a) through (f) below:
performance to the specified requirements of the procurement document. In exercising this responsibility, the Purchaser of items and services shall establish measures to verify Supplier's performance. As deemed necessary by the Purchaser, the methods shall include:
N45.2.13 &sect; 6.1 - a. Establishing an understanding between            (a) establishing an understanding between Purchaser and          Similar requirement.
Purchaser and Supplier of the provisions and specifications of        Supplier of the provisions and specifications of the procurement the procurement documents.                                            documents; N45.2.13 &sect; 6.1 - b. Requiring the Supplier to identify planning      (b) requiring the Supplier to identify planning techniques and    Similar requirement.
techniques and processes to be utilized in fulfilling procurement    processes to be utilized in fulfilling procurement document document requirements.                                                requirements; N45.2.13 &sect; 6.1 - c. Reviewing documents which are generated          (c) reviewing Supplier documents which are generated or          Similar requirement.
or processed during activities fulfilling procurement                processed during activities fulfilling procurement requirements; requirements.
N45.2.13 &sect; 6.1 - d. Identifying and processing necessary change      (d) identifying and processing necessary change information;      Similar requirement.
information.
N45.2.13 &sect; 6.1 - e. Establishing exchange method of document          (e) establishing method of document information exchange          Similar requirement.
information between Purchaser and Supplier.                          between Purchaser and Supplier; N45.2.13 &sect; 6.2 Planning and Coordination - (3d sentence)              (f) establishing the extent of source surveillance and inspection Similar requirement.
Purchaser notification points, including hold and witness            activities.
points, should be identified and documented based upon mutual                                                                          This addresses the NRC agreement between Purchaser and Supplier.                                                                                              Reg. Guide 1.123 Position Reg. Guide 1.123 Regulatory Position C.6 In addition to the                                                                            C.6.b requirements of the standard, the guidelines (indicated by the verb "should") identified below are considered to have sufficient safety importance to be treated the same as the requirements of the standard. - b. Section 6.2 - The guideline concerning purchaser notification points as part of pre-and post-award activities.
N45.2.13 &sect; 6.2 Planning and Coordination - (4h sentence)              These verification activities shall be conducted as early as      Similar requirement.
These activities shall be implemented as early as practicable in      practicable.
the procurement process.
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CRITERION7                                                  BASIC REQUIREMENT 7                  '                  COMMENTS ANSI N45.2 1971 - ANSI N45.1.13-197                                                  NQA-l 1994 ANSI N1.8.7 197 N45.2.13 &sect; 7.1 - These verification activities shall be conducted as early as practicable to preclude subsequent activities from preventing disclosure of deficiencies.
N45.2.13 &sect; 7.1 - The Purchaser's verification activities are not      The Purchaser's verification activities, however, shall not        Similar requirement.
intended to relieve the Supplier of his responsibilities for          relieve the Supplier of his responsibilities for verification of verification of quality requirements.                                quality achievement.
6.2 Planning and Coordination                                                                                                            These requirements are Depending on the complexity or scope of the item or service,                                                                              contained as nonmandatory the Purchaser shall initiate pre- and post-award activities. These                                                                        guidance in NQA-1, activities may take the form of meetings or other forms of                                                                                Appendix 7A- I &sect; 3.
communication to establish an understanding between the Purchaser and Supplier of the procurement requirements; the intent of the Purchaser in monitoring and evaluating the Supplier's performance; and the planning, manufacturing techniques, tests, inspections, and processes to be employed by the Supplier in meeting procurement requirements. Purchaser notification points, including hold and witness points, should be identified and documented based upon mutual agreement between Purchaser and Supplier. These activities shall be implemented as early as practicable in the procurement process.
The depth and necessity of pre- and post-award activity depends on the uniqueness, complexity, procurement frequency with the same Supplier and past Supplier performance for the specific items or services covered by the procurement document.
5.1 Extent of Activities N45.2.13 &sect; 7.2 Planning - Planning shall be an integral part of      The extent of verification activities, including planning, shall be Similar requirement.
verification activities. The extent of verification activities,      a function of the relative importance, complexity, and quantity including planning, shall be a function of the relative              of the item or services procured and the Supplier's quality importance, complexity, and quantity of the item procured and        performance.
the Supplier's quality performance. See Section 10 of this standard for guidance in selecting verification methods.
N45.2.13 &sect; 7.2.1 Source Verification Planning. The verification activity plans shall, relative to fabrication sequence and assembly processes, identify the appropriate inspections, tests, prerequisites and inspection sequence, hold and witness points, acceptance criteria, and the documentation required by the procurement document.
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CRITERION 7                                                BASIC REQUIREMENT 7                                  COMMENTS
        .ANSI    N45.2 1,971 -ANSI N45.2.13-1976                                            NQA-1 1994 ANSI N18.7 -1976                                                                    ..
N45.2.13 &sect; 7.1 - Purchaser verification activities shall be        Verification activities shall be accomplished by qualified      Similar requirement.
accomplished by qualified personnel assigned to check, inspect,    personnel assigned to check, inspect, audit, or witness the audit or witness the activities of Suppliers.                      activities of Suppliers.
5.2 Records N45.2 The effectiveness of the control of quality shall be          Activities performed to verify conformance to requirements of  Similar requirement.
assessed by the purchaser at intervals consistent with the          procurement documents shall be recorded. Source surveillances importance, complexity, and quality of the item or service.        and inspections, audits, receiving inspections,                NQA-1 further addresses N18.7 The effectiveness of the control of quality shall be          nonconformances, dispositions, waivers, and corrective actions  records in Basic assessed by the purchaser at intervals consistent with the          shall be documented.                                            Requirement 17 and importance, complexity and quality of the item or service.          The Purchaser shall assure that his documentation is evaluated  Supplement 17S-1.
N45.2.13 &sect; 11. QUALITY ASSURANCE RECORDS                            to determine the Supplier's quality assurance program Measures shall be established and implemented for the control      effectiveness.
of:
: a. Supplier-generated documents and records that are required to be submitted to the Purchaser or retained by the Supplier as specified by the procurement documents.
: b. Purchaser-generated quality related documents and records.
The collection, storage, and maintenance of quality assurance records shall be in accordance with ANSI N45.2.9.
6 CONTROL OF SUPPLIER GENERATED DOCUMENTS N45.2 This documentary evidence shall be retained at the            Supplier generated documents shall be controlled, handled, and  Similar requirement.
nuclear power plant site and shall be sufficient to identify the    approved in accordance with established methods. Means shall specific requirements such as codes, standards, and                be implemented to assure that the submittal of these documents specifications met by the purchased item.                          is accomplished in accordance with the procurement document N18.7 This documentary evidence shall be retrievable and shall      requirements. These measures shall provide for the acquisition, be sufficient to identify the specific requirements such as codes,  processing, and recorded evaluation of technical, inspection, standards and specifications met by the purchased item.            and test data against acceptance criteria.
N45.2.13 &sect; 6.3 Control of Supplier Generated Documents - The Purchaser and Supplier shall assure that established measures for the control, handling and approval of Supplier generated documents are implemented, and that the submittal time and frequency for these documents is accomplished in accordance with the procurement documents. These measures shall provide for the acquisition, processing and recorded evaluation of inspection and test data against acceptance criteria.
7 CONTROL OF CHANGES IN ITEMS OR SERVICES N45.2.13 &sect; 6.4 Control of Changes in items or Services - The        The Purchaser and Supplier shall assure that measures to        Similar requirement.
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CRITERION 7                                                        BASIC REQUIREMENT 7                      .                  COMMENTS ASI N45.2 1971.- ANSI N45.2.13-1976                  .                                    QA-1 1994**
ANSI N 18.7 -1976 Purchaser and Supplier shall assure that measures to control              control changes in procurement documents are established, changes in procurement documents are established,                        implemented, and documented and are in accordance with this            For NQA-1I this is primarily implemented and documented, and are in accordance, with                  Part (Part 1).                                                        addressed by Basic ANSI N45.2 Section 7.                                                                                                                            Requirement 4 and
________________________________________Supplement                                                                        4S-1.
N45.2.13 &sect; 10. ACCEPTANCE OF ITEM OR SERVICE                              8 ACCEPTANCE OF ITEM OR SERVICE
___________________________________________8.1 General                                                                        ____________
N45.2 Where required by code, regulation, or contract                    Methods shall be established for the acceptance of an item or          Similar requirement.
requirements, documentary evidence that items conform to                  service being furnished by the Supplier. Prior to offering the procurement requirements shall be available at the nuclear                item or service for acceptance, the Supplier shall verify that the NRC Regulatory Position power plant site prior to installation or use of such items.              item or service being fturnished complies with the procurement        C.4 from Reg. Guide 1.123 N18.7 Where required by code, regulation, or contract                    requirements. Where required by code, regulation, or contract          is addressed in NQA-1I &sect; requirements, documentary evidence that items conform to                  requirement, documentary evidence that items conform to                8.2.3 by requiring receiving procurement requirements shall be available at the nuclear                procurement documents shall be available at the nuclear facility inspection to be performed power plant site prior to installation or use of such items.              site prior to installation or use.                                    in accordance with N45.2.13 &sect; 10. 1 General - The Purchaser shall establish the                                                                                    established procedures and method  of acceptance of 10/28/2010                  an item or service *being Control...
                          'RTEIN7                    furnishedof..by Purchased MateialEquiment Item)      (,**:..:AadUSRviesT,:                    instructions. Pag.*
                                                                                                                                      *.:'......,*.:..*CM          eNT:. of...
the Supplier. Prior to offering the item or service for acceptance, the Supplier shall verify that the item or service being furnished complies with the procurement requirements.
Where required by code, regulation or contract requirement, documentary evidence that items conform to procurement documents shall be available at the nuclear power plant site prior to installation or use of such items regardless of acceptance methods.
Reg. Guide 1.123 Regulatory Position CA4. Section 10. 1 of ANSI N45.2. 13-1976 states that the Purchaser shall establish the method of acceptance of an item or service being furnished by the Supplier. In order for receiving inspection personnel to be aware of what methods of acceptance are established, the applicable portion of the procurement document identifying the method of acceptance of an item or service, or other documents containing the same procurement document information, should be______on_____hand._______________                                    j_8.2 Methods of Acceptance                                            _____________
N45.2 Where not precluded by other requirements, such                    Purchaser methods used to accept an item or related service            Similar requirement.
documentary evidence may take the form of written                      Ifrom a Supplier shall be Supplier Certificate of Conformance,          ____________
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CRITERION 7                                                  BASIC REQUIREMENT 7                                COMMENTS SIN45.2 1971 - ANSI N45.2.13-1..                                                NQA-1 1994.                ..
ANSI N18.7 - 1976 certifications of conformance which identify the requirements        source verification, receiving inspection, or post-installation met by the items, provided means are available to verify the          test at the nuclear facility site, or a combination thereof.
validity of such certifications.
N18.7 Where not precluded by other requirements, such documentary evidence may take the form of written certifications of conformance which identify the requirements met by the items, provided means are available to verify the validity of such certifications.
N45.2.13 &sect; 10.3 Methods of Acceptance, Selection and Implementation - Purchaser methods used to accept an item or service from a Supplier are source verification, receiving inspection, Supplier certificate of conformance, post installation test at the nuclear power plant site, or a combination thereof.
N45.2.13 &sect; 10.2 Certificate of Conformance - Where not                8.2.1 Certificate of Conformance. When a Certificate of        Similar requirement.
precluded by other requirements, documentary evidence may            Conformance is used, the minimum criteria of (a) through (f) take the form of written certificates of conformance which            below shall be met.                                            The NRC Regulatory identify the requirements met by the items. Where certificates                                                                        Position C.6 from Reg.
of conformance are used, the following minimum criteria shall                                                                        Guide 1.123 has been be met:                                                                                                                              addressed in NQA- 1.
Reg. Guide 1.123 Regulatory Position C.6 In addition to the requirements of the standard, the guidelines (indicated by the verb "should") identified below are considered to have sufficient safety importance to be treated the same as the requirements of the standard. - c. Section 10.2 (a though f) -
The guidelines that specify the minimum criteria for Certificates of Conformance.
N45.2.13 &sect; 10.3.3 Acceptance by Supplier Certificate of Conformance. In certain procurement actions which do not involve direct inspection by the Purchaser, the Purchaser may accept an item or service from a Supplier based only on a Supplier's certificate of conformance that the specified requirements have been met. However, specific supplemental documentation, such as material certificates or reports of tests performed, may be required by procurement documents.
Acceptance by this method is satisfactory when the item or service is of simple design and involves standard materials, 10/28/2010                                          Control of Purchased Material, Equipment, (Items) and Services                                  Page 11 of 22
 
CRITERION 7                                                    BASIC REQUIREMENT 7                                            CONMMNTS ANSI N45.2 1971 - ANSI N45.2.13-1976                                                NQA-1 1994.
ANSI N1 8.7 -1976 processes and tests. Such items may be fabricated subject to selected qualification, sample, or batch testing to establish or maintain a minimum quality confidence level.                        __________________________
N45.2.13 &sect; a. The certificate should identify the purchased          (a) The certificate shall identify the purchased material or          Similar requirement.
material or equipment, such as by the purchase order number.          equipment, such as by the purchase order number.
N45.2.13 &sect; b. The certificate should identify the specific            (b) The certificate shall identify the specific procurement            Similar requirement.
procurement requirements met by the purchased material or            requirements met by the purchased material or equipment, such equipment, such as codes, standards, and other specifications.        as codes, standards, and other specifications. This may be This may be accomplished by including a list of the specific          accomplished by including a list of the specific requirements or requirements or by providing, onsite, a copy of the purchase          by providing, on-site, a copy of the purchase order and the order and the procurement specifications or drawings, together        procurement specifications or drawings, together with a suitable with a suitable certificate. The procurement requirements            certificate. The procurement requirements identified shall identified should include any approved changes, waivers, or          include any approved changes, waivers, or deviations deviations applicable to the subject material or equipment.          applicable to the subject material or equipment.
N45.2.13 &sect; c. The certificate should identify any procurement        (c) The certificate shall identify any procurement requirements        Similar requirement.
requirements that have not been met, together with an                that have not been met, together with an explanation and the explanation and the means for resolving the nonconformances.          means for resolving the nonconformances.
N45.2.13 &sect; d. The certificate should be attested to by a person      (d) The certificate shall be signed or otherwise authenticated by      Similar requirement.
who is responsible pr~oesses    andtets for this quality assurance Schitmsoaib              function and to fab1ctersujc              a person who isqlmnqiem~au~riesrg naetva              responsible for this quality assurance function                                      . 1~
whose fuinction and position are described in the Purchaser's or      and whose function and position are described in the Suppler's qualit assurance program.                                  Purchaser's or Supplier's quality assurance program.                  _____________
N45.2.13 &sect; e. The certification system, including the;                (e) The certification system, including the procedures to be          Similar requirement.
procedures to be followed in filling out a certificate and the        followed in filling out a certificate and the administrative administrative Procedures for review and approval of the              procedures for review and approval of the certificates, shall be certificates, should be described in the Purchaser's or Supplier's    described in the Purchaser's or Supplier's quality assurance quality assurance program.                                            program.
N45.2.13 &sect; f. Means should be provided to verify the validity of      (f) Means shall be provided to verify the validity of Supplier        Similar requirement.
Supplier certificates and the effectiveness of the certification      certificates and the effectiveness of the certification system, system, such as during the performance of audits of the              such as during the performance of audits of the Supplier or Supplier or independent inspection or test of the items. Such        independent inspection or test of the items. Such verification verifications should be conducted by the Purchaser at intervals      shall be conducted by the Purchaser at intervals commensurate commensurate with the Supplier's past quality performance.            with the Supplier's past quality performance.
(Section 7 of this standard provides requirements and guidance relative to the conduct of source verification activities and receiving inspections.)                                                                  *___.._'_.__________..___  ___.___.'. ______.__
N45.2.13 &sect; 7.3.1 Source Verification Activities. When planning 8.2.2 Source Verification. When source verification is used, it              Similar requirement.
_______________________________________          I shall be performed at intervals consistent with the importance      I_________I___
1 U/1.0//ZU U                                      Control of Purchased Material, Equipment, kite s) and Services                                                    rage l2. or 1.2
 
CRITERION 7                                                    BASIC REQUIREMENT 7                                  COMMENTS ANSI N45.2 1971 - ANSI N45.2.13-1976                                                  NQA-I199 ANSI N18.7 -19,76__                                _  _  _  _  _  _  _  _  _  _  _  _  _ _  _  _ _  _  _ __  _  _    _  _  _  _  _ _
requires Purchaser source surveillance, it shall be implemented        and complexity of the item or service, and it shall be to monitor, witness or observe activities. Similarly, source          implemented to monitor, witness, or observe activities. Source inspection shall be implemented in accordance with plans to            verification shall be implemented in accordance with plans to perform inspections, examinations, or tests at predetermined          perform inspections, examinations, or tests at predetermined points. Source surveillance and inspection may require the            points. Upon Purchaser acceptance of source verification, assignment of personnel to a Supplier's facilities.                    documented evidence of acceptance shall be furnished to the N45.2.13 &sect; 10.3.1 Acceptance by Source Verification.                  receiving destination of the item, to the Purchaser, and to the Acceptance by source verification should be considered when            Supplier.
the item or service is:
: a. vital to plant safety; or
: b. difficult to verify quality characteristics after delivery; or
: c. complex in design, manufacture, and test.
The source verification activities should include but not be limited to the following as applicable:
: a. Documentation has been submitted as required and provides verification of approvals, material, applicable inspections, and tests.
: b. Fabrication procedures and processes have been approved and complied with and the applicable qualifications, process records, and certifications are available.
: c. Components and assemblies have been inspected, examined, and tested as required and applicable inspection, test and certification records are available.
: d. Nonconformances have been dispositioned as required.
: e. Components and assemblies are cleaned, preserved, packed and identified in accordance with specified requirements.
Upon Purchaser acceptance by source verification, documented evidence of acceptance shall be furnished to the receiving destination of the item, to the Purchaser, and to the Supplier.
N45.2.13 &sect; 7.2.2 Receiving Inspection Planning. The receiving          8.2.3 Receiving Inspection. When receiving inspection is used,    Similar requirement.
inspection plans shall identify the characteristics to be verified    purchased items shall be inspected as necessary to verify and documentation to be reviewed at receiving inspection. For          conformance to specified requirements, taking into account        Within NQA-1, Subpart 2.2 characteristics to be considered during receiving inspection, see      source verification and audit activities and the demonstrated    is commensurate with ANSI ANSI N45.2.2.                                                          quality performance of the Supplier. Receiving inspection shall  N45.2.2.
N45.2.13 &sect; 7.3.2 Receiving Inspection. When planning requires          be performed in accordance with established procedures and        NRC Regulatory Position Purchaser receiving inspection, it shall be implemented and            inspection instructions, to verify by objective evidence such    C.6 from Reg. Guide 1.123 coordinated with source verifications performed. During                features as proper configuration; identification; dimensional,    related to N45.2.13, &sect; 102/00                                      oto    f ucae      Maeil    Eqimn,(Ies            n  Srie                                    ag  3o2 10/28/2010                                            Control of Purchased Material, Equipment, (Items) and Services                                    Page 13 of 22
 
CRITERIO~N 7                                                BASIC REQUIREMENT 7                              1        COMMENTS ANSI N45.2 1971 - ANSI N45.2.13-1976          ,                                  NQA-1 1994      ,
S...            ANSI N18.7-1976 "                                                                                              .
receiving inspection, emphasis shall be placed on assuring that    physical, and other characteristics; freedom from shipping            10.3.2 is addressed in the items have not sustained damage in shipment that would              damage; and cleanness. Receiving inspection shall be                  wording of NQA-1.
influence subsequent fabrication, construction, installation, or    coordinated with review of Supplier documentation when end use. Sampling may be utilized during receiving inspection      procurement documents require such documentation to be when conducted in accordance with established procedures or        furnished prior to receiving inspection.
recognized standards. Receiving inspection measures shall include provisions for receiving documentation (such as drawings, certifications, test results and other materials) offered as objective evidence in satisfaction of requirements. These measures shall also include provisions for dispositioning (i.e.,
accept, reject or hold) and handling of items received and services performed. See ANSI N45.2.2 for additional requirements.
N45.2.13 &sect; 10.3.2 Acceptance by Receiving Inspection.
Acceptance solely by receiving inspection is satisfactory when the items or services are
: a. relatively simple and standard in design, manufacture, and test; and
: b. adaptable to standard or automated inspections and/or tests of the end product to verify quality characteristics after delivery; and
: c. such that receiving inspection does not require operations which could adversely affect the integrity, function, or cleanness of the item.
Receiving inspection should be coordinated with review of Supplier documentation when procurement documents require such documentation to be furnished prior to receiving inspection.
Reg. Guide 1.123 Regulatory Position C.6 In addition to the requirements of the standard, the guidelines (indicated by the verb "should") identified below are considered to have sufficient safety importance to be treated the same as the requirements of the standard. - d. Section 10.3.2 - The guideline concerning acceptance by receiving inspection.
N45.2.13 &sect; 10.3.4 Acceptance by Post Installation Test at the      8.2.4 Post-Installation Testing. When post-installation testing is    Similar requirement.
Nuclear Power Plant Site. Acceptance by this method is              used, post-installation test requirements and acceptance satisfactory when performed following the accomplishment of        documentation shall be mutually established by the Purchaser          NQA-I does not address the 10/28/2010                                        Control of Purchased Material, Equipment, (Items) and Services                                        Page 14 of 22
 
CRITERION 7                                                      BASIC. REQUIREMENT 7                                  COMMENTS ANI N45.2 1971    - ANSI N45.2.13-197                                                NQA-1 1994.                                  .
ANSI N18.7 - 1976 at least one of the preceding methods and when                          and Supplier.                                                    reasons why a post-
: a. it is difficult to verify the quality characteristics of the item                                                                      installation test would be without it being installed and in use; or                                                                                                  chosen as the method for
: b. the item requires an integrated system checkout or test with                                                                            acceptance of an item. This other items to verify its quality characteristics; or                                                                                      is left to the implementing
: c. the item cannot demonstrate its ability to perform its intended                                                                        program to determine when function except when in use.                                                                                                              to use this testing.
Post installation test requirements and acceptance documentation should be mutually established by the Purchaser and Supplier.
Reg. Guide 1.123 Regulatory Position C.6 In addition to the requirements of the standard, the guidelines (indicated by the verb "should") identified below are considered to have sufficient safety importance to be treated the same as the requirements of the standard. - e. Section 10.3.4 - The guidelines concerning the establishment of post-installation test requirements and acceptance documentation.
8.3 Acceptance of Services Only N45.2.13 &sect; 10.3.5 Acceptance of Services Only. The guidelines            In certain cases involving procurement of services only, such as  Similar requirement.
outlined in Section 10.3 above primarily deal with hardware              third party inspection; engineering and consulting services; and items and related services. In certain cases involving                  installation, repair, overhaul, or maintenance work, the procurement of services only, such as third party inspection;            Purchaser shall accept the service by any or all of the following engineering and consulting services; and installation, repair,          methods:
overhaul or maintenance work; the Purchaser may accept the              (a) technical verification of data produced; service by any or all of the following methods:                          (b) surveillance and/or audit of the activity;
: a. Technical verification of data produced.                              (c) review of objective evidence for conformance to the
: b. Surveillance and/or audit of the activity,                            procurement document requirements such as certifications,
: c. Review of objective evidence for conformance to the                  stress reports, etc.
procurement document requirements such as certifications, stress reports, etc.
N45.2.13 &sect; 8. CONTROL OF NONCONFORMANCES                                9 CONTROL OF SUPPLIER NONCONFORMANCES N45.2.13 &sect; 8.1 General - The Purchaser and Supplier shall                The Purchaser and Supplier shall establish and document          Similar requirement. NQA-establish and document measures for the identification, control,        methods for disposition of items and services that do not meet    1 also addresses and disposition of items and services that do not meet                  procurement documentation requirements.                          Nonconformances under procurement document requirements.                                                                                                        Basic Requirement 15 and Supplement 15S-1.
8.2 Disposition                                                          These methods shall contain provision for (a) through (e)        Similar requirement.
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CRITERION 7                                                        BASIC REQUIREMIENT 7                            COMMENTS
                .AN SI1N45.2 1971 - ANSI N4.21-17                                                        NQA-1 1994 ANSI  N.NI.7  1.9,76                        ________________________
These measures shall contain provision for the following:              below:
: a. Review of nonconforming items.                                      (a) evaluation of nonconforming items;                          Similar requirement.
: b. Submittal of nonconformance notice to Purchaser by                  (b) submittal of nonconformance notice to Purchaser by          Similar requirement.
Supplier as directed by the Purchaser. These submittals shall          Supplier as directed by the Purchaser. These subnmittals shall include Supplier recommended disposition (i.e., "use-as-is" or          include Supplier-recommended disposition (e.g., use-as-is or "repair") and technical justification. Nonconformances to the          repair) and technical justification. Nonconformances to the procurement requirements or Purchaser approved documents                procurement requirements or Purchaser-approved documents, and which consist of one or more of the following shall be              which consist of one or more of the following, shall be submitted to the Purchaser for approval of the recommended              submitted to the Purchaser for approval of the recommended disposition:                                                            disposition:
: 1) Technical or material requirement is violated                        (1) technical or material requirement is violated;
: 2) Requirement in Supplier documents, which have been                  (2) requirement in Supplier documents, which has been approved by the Purchaser, is violated,                                approved by the Purchaser, is violated;
: 3) Nonconformance cannot be corrected by continuation of the            (3) nonconformance cannot be corrected by continuation of the original manufacturing process or by rework.                            original manufacturing process or by rework;
: 4) The item does not conform to      the original requirement even    (4) the item does not conform to the original requirement even though the item can be restored to a condition such that the            though the item can be restored to a condition such that the
.... -..      ..                                      iontro" 01 rucnse Niteal              nqipt,* ...      ...s ano' z~ric                      " rage":*,*IOO  ...
capacity of the item to function is unimpaired.                        capability of the        item to function    is unimpaired;
: c. Purchaser disposition of Supplier recommendation.                    (c) Purchaser disposition of Supplier recommendation;          Similar requirement.
: d. Verification of disposition.                                        (d) verification of the implementation of the disposition;    Similar requirement.
: e. Maintenance of records of Supplier nonconformances.                  (e) maintenance of records of Supplier-submitted                Similar requirement.
nonconformances.
10 COMMERCIAL GRADE ITEMS Where the design utilizes commercial grade items, the          New requirement in NQA-following requirements are an acceptable alternate to other    1. Not previously in the requirements of this Supplement, except as noted in (b) below  N45 .2 series standards.
and the requirements of Supplement 4S-1.
(a) The commercial grade item is identified in an approved design output document. An alternate commercial grade item may be applied, provided the cognizant design organization provides verification that the alternate commercial grade item will perform the intended function and will meet design requirements applicable to both the replaced item and its application.
(b) Source evaluation and selection, where determined necessary by the Purchaser based on complexity and
_____________________________________________importance to safety, shall be in accordance with para. 3.1 of      _____________
I U//.ZS/.U IU                                        Control of Purchased Material, hquipment, titems) and Services                                  r-age 16ot oi
 
CRITERION 7                                                        BA~SIC'REQUIREMENT 7                                                    COMMENTS ANI N45.2 1971  - ANIN45.2.13-197                                                    NQA-1 1994 ANSI N18.7 - 1976                          ______________________
this Supplement.
(c) Commercial grade items shall be identified in the purchase order by the manufacturer's published product description (for example, catalog number).
(d) After receipt of a commercial grade item, the Purchaser shall determine that:
(1) damage was not sustained during shipment; (2) the item received was the item ordered; (3) inspection and/or testing is accomplished, as required by the Purchaser, to assure conformance with the manufacturer's published requirements; (4) documentation, as applicable to the item, was received and is acceptable.
N45.2.13 &sect; 1.2 Responsibility                                                                                                                                  NQA- 1 addresses 1.2.1 General                                                                                                                                                  responsibilities in a general The responsibilities for Purchaser and Supplier are identified                                                                                                  sense within the with recognition that an organization can be either a Purchaser                                                                                                Introduction, &sect;3, of Part L.
10/28/20.:* 10    * .*:: C I .E IO        -. .    **Control
                                                          " of'Purchased
                                                                ,          Material,
                                                                                  ** '..:* Equipment, (Items).
                                                                                                              .... and, Services  ...              :.... ,                Page....
17 of22 or a Supplier depending upon the level of procurement.
However, for any given procurement action the organization is one or the other and this standard applies accordingly. For example, an organization may be a supplier but may have to purchase items or services from a subtier level._____________________________
N45.2.13 &sect; 1.2.2 Purchaser's Responsibility                                                                                                                    NQA- 1 addresses
: a. Establishment and implementation of a procurement control                                                                                                    responsibilities in a general process consistent with the requirements and guidelines of this                                                                                                sense within the standard.                                                                                                                                                      Introduction, &sect;3, of Part 1.
: b. Incorporation of quality assurance program requirements, appropriate to the scope of work, into procurement documents.
: c. Evaluation of Supplier's quality assurance program to assure that it is appropriate and satisfies the requirements for the items or services being purchased.
: d. Where interfacing, but separate, procurement actions are initiated by a single Purchaser to purchase the design, manufacture, shop assembly and test, field installation and field test of equipment or a system, the single Purchaser shall assure that the quality assurance requirements incorporated in separate procurement documents, in conjunction with the Purchaser's          _________________________________________
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CRITERION 7                                                BASIC REQUIREMENT 7                                    CONMMNTS ANSI N45.2 1971 -ANSI N45.2.13.-1976                                              NQA-1 19 ANSI N18.7 - 1976                            _____________                              _______
quality assurance program, will collectively satisfy the requirements of ANSI N45.2 and applicable supplementary standards as applicable to the total items and services procured.
An example of this is the case where one Supplier has responsibility for design, manufacture, shop assembly and test; another Supplier has responsibility for field assembly; and a third Supplier has responsibility for field tests.
N45.2.13 &sect; 1.2.3 Supplier's Responsibility                                                                                            NQA-1 addresses
: a. Establish and implement a documented quality assurance                                                                            responsibilities in a general program that complies with procurement document                                                                                      sense within the requirements.                                                                                                                        Introduction, &sect;3, of Part I.
: b. Permit Purchaser review of Supplier's quality assurance program and its implementation.
: c. Incorporate appropriate quality assurance program requirements in subtier procurement documents.
N45.2.13 &sect; 1.3 Definitions                                          The following definitions are from NQA-1, Part I, Introduction    NQA- 1 contains definitions The following definitions are provided to assure a uniform                                                                            in the Introduction to Part I.
understanding of selected terms as they are used in this standard. Other terms and their definitions are contained in ANSI N45.2.l10.
N45.2.13 Designated Representative - An individual or                                                                                Not defined in NQA-I.
organization authorized by the Purchaser to perform functions in the procurement process.
N45.2.13 Procurement Document - Purchase requisitions,              Procurement document - purchase requisitions, purchase            Same definition.
purchase orders, drawings, contracts, specifications or            orders, drawings, contracts, specifications, or instructions used instructions used to define requirements for purchase.              to define requirements for purchase N45.2.13 Purchaser - The organization responsible for              Purchaser - the organization responsible for establishment of    Similar definition.
establishment of procurement requirements and for issuance,        procurement requirements and for issuance or administration, administration, or both, of procurement documents.                  or both, of procurement documents N45.2.13 Quality Assurance Program Requirements - Those                                                                              Not defined in NQA-1.
individual requirements listed in ANSI N45.2 which when invoked in total or in part establish the requirements of a quality assurance program.
N45.2.13 Quality Assurance Records - Those records which            Quality assurance record - a completed document that furnishes    Similar definition.
furnish documentary evidence of the quality of items and of        evidence of the quality of items and/or activities affecting activities affecting quality.                                      quality 10/28/2010                                        Control of Purchased Material, Equipment, (Items) and Services                                    Page 18 of 22
 
C..TE.ON 7..                                                        BASIC REQUIREMENT 7                                COMMENTS ANSI N45.2 1971 - ANSI1 N45.2.13-1976                                                    NQA-1 1994 ANSI N18.    - 1976                        ________________________
N45.2.13 Right of Access - The right of a Purchaser or              Right of access - the right of a Purchaser or designated              Similar definition.
designated representative to enter the premises of a Supplier for    representative to enter the premises of a Supplier for the the purpose of inspection, surveillance, or quality assurance        purpose of inspection, surveillance, or quality assurance audit audit.                                                              __________________________
N45.2.13 Services - The performance by a Supplier of activities      Service - the performance of activities such as design,              Similar definition.
such as design, fabrication, inspection, non-destructive            fabrication, inspection, nondestructive examination, repair, or examination, repair, or installation,                                installation N45.2.13 Subtier Procurement - Procurement by a Supplier                                                                                  Not defined in NQA-1.
from a subsupplier of items or services                                                                                                    Covered by the definition of
_____________________________________________Supplier.
N45.2.13 Supplier - Any individual or organization who              Supplier - any individual or organization who furnishes items        Similar definition.
furnishes items or services to a procurement document. It            or services in accordance with a procurement document. An all-includes the terms Vendor, Seller, Contractor, Subcontractor,        inclusive term used in place of any of the following: vendor, Fabricator, Consultant, and subtier levels,                          seller, contractor, subcontractor, fabricator, consultant, and their subtier levels.
N45.2.13 Surveillance - The physical presence to monitor by          Surveillance - the act of monitoring or observing to verify          Similar definition.
observation the designated activities to assure that they are        whether an item or activity conforms to specified requirements performed in a specified manner.
N45.2.13 &sect; 1.4 Referenced Documents                                                                                                        Applicability of other Documents that are required to be included as part of this                                                                                standards and Regulatory standard are identified at the point of reference and described in                                                                        Guides is addressed in the Section 13 of this standard. The issue or edition of the                                                                                  QAPD.
referenced document that is required will be specified either at the point of reference or in Section 13 of this standard unless otherwise specified in the procurement document.
Reg. Guide 1.t123 Regulatory Position C.t. Section 1.4 of ANSI N45.2.13-1976 states that other documents that are required to be included as part of this standard will be identified at the point of reference and described in Section 13 of the standard. The specific applicability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations where appropriate.
N45.2.13 10/2/201  &sect; 7.3.1t 2 - When conformance to procurement pitoreeeeandecbeinS                      ctontrolof PucaetaeiaEupethItm)adSricsPge9o2                                              Auditing requirements are requirements is verified by audit, such audits shall be conducted                                                                          addressed in NQA-1, Basic in accordance with established methods.                                                                                                    Requirement 18, and Supplement 18S-1.
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CRITERION 7                                                      BASIC REQUIREMENT 7                              COMMEWNTS ASI N45.2 1971 - ANSI N45.2.13-1976                                                NQA-1~ 1994 ANSI N18.7 -1976 N45.2.13 &sect; 7.4 Measuring and Test Equipment                                                                                            NQA- I addresses 7.4.1 Selection. Inspection, examination, and testing equipment                                                                        measuring and test utilized to implement the requirements of this standard shall be                                                                        equipment in Basic selected to have accuracy and tolerance sufficient to determine                                                                        Requirement 12, conformance to specified requirements.                                                                                                  Supplement 12S-1, and 7.4.2 Calibration and Control. As appropriate, measuring and                                                                            Subpart 2.16.
test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards. If no standards exist, the basis for calibration shall be documented. Records shall be maintained and equipment suitably marked to indicate calibration status or the records shall be traceable to the equipment. When inspection, measuring and test equipment are found to be out of calibration, an evaluation shall be made and documented of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested. _____________________________
10/2/201                                              +'
Control...:*
of:,:**:,*::
Puchse Maeil Eqimet      (Items).ad Se..ice          .                    Page.. 20.of..22 N45.2.13    &sect; 7.5 Personnel Qualifications                                                                                            NQA-1 addresses    personnel Personnel responsible for performing verification activities                                                                            qualifications in Basic shall be qualified in accordance with ANSI N45.2.6 as                                                                                  Requirement 2, Supplement applicable.                                                                                                                            2S-1 (inspection and test personnel), and Supplement
___________________________________________2S-3 (audit personnel).
N45.2.13 &sect; 7.6 Reporting                                                                                                                NQA-l does not Measures shall be established to provide for the reporting of                                                                          specifically address the activities performed to verify' conformance to requirements of                                                                          reporting of these items in a procurement documents. These measures shall include                                                                                    separate paragraph of this reporting of source surveillances and inspections, audits,                                                                              section (Basic Requirement receiving inspections, nonconformances, dispositions, waivers,                                                                          7 and Supplement 7S-1).
and corrective actions.                                                                                                                However, reporting of these In addition, the Purchaser shall assure that these reports are                                                                          type documents are evaluated to determine the Supplier's quality assurance program                                                                        addressed under the effectiveness.                                                                                                                          respective sections of the Supplement. Reporting is also addressed in the Requirement and
___________________________________________ _____________________________Supplemental_                upplmentlisetionttha 10/28/2010                                                Control of Purchased Material, Equipment, (Items) and Services                              Page 20 of 22
 
CRITERION 7                                                          BASIC REQUIREMENT 7        COMMENTS ANSI N45.2 1971 - ANSI N45.2.13-1976                                                    NQA-1 1994 SANSI N18.7 - 1976                            _________________________
would govern these programs, such as Inspections, Tests, and Audits that relate to NQA-1 Requirements 10, 11, and 18.
N45.2.13 &sect; 9. CORRECTIVE ACTION                                                                                    NQA-1 addresses corrective 9.1 General                                                                                                        action in Basic Requirement The Purchaser shall establish and document measures that                                                          16.
describe the method for the identification of and timely corrective action for conditions adverse to quality which occur during the procurement process and are the responsibility of the Purchaser.
9.2 Significant conditions In the case of significant conditions adverse to quality which may arise during the procurement process, the Purchaser's measures shall describe the method used to:
: a. Identify and document deviations and nonconformances.
: b. Review and evaluate the conditions to determine the cause, extent, and measures needed to correct and prevent recurrence.
: c. Report the conditions and corrective action to the appropriate levels of management.
: d. Assure corrective action is implemented and maintained as necessary.
9.3 Verification - The Purchaser's corrective action measures shall include verification of implementation of Supplier corrective action system. These measures shall determine that conditions adverse to quality such as deficiencies, deviations, defective items and nonconformances have had corrective action implemented and maintained as necessary.
Reg. Guide 1.123 Regulatory Position C.3 Section 9.3 of ANSI N45.2.13-1976 states, "The Purchaser's Corrective action measures shall include verification of implementation of Supplier's corrective action system." The Purchaser should verify the implementation of the Supplier's corrective action system when such a system is required, but this verification need not be included as part of the Purchaser's 10/28/2010                                          Control of Purchased Material, Equipment, (Items) and Services                Page 21 of 22
 
CRITERION 7 ..                :,BASIC                              REQUIREMENT 7                COMME ANSI N45.2 1971 - AS1,N45.2.13-1976                                              NQA-1 1994 corrective action measures. While Section 9.0 of ANSI N'45.2.13-1976 addresses elements of the Purchaser's corrective action system, these same elements are applicable to the Supplier's corrective action system when one is required.
N45.2.13 &sect; 12. AUDIT OF PROCUREMENT PROGRAM                                                                        NQA-1 addresses all Periodic or random audits shall be performed to verify                                                            Quality Assurance auditing compliance with procurement activities described in this                                                          under Basic Requirement standard. The scope of planned auditing activity may cover                                                        18 and Supplement 18S-1.
individual operations, events, processes, or the complete quality assurance program. When deemed necessary by the Purchaser, audits of subtier Suppliers shall be carried out to assure that their quality assurance programs on procurement adequately translate the necessary requisites of the governing procurement documents to the items or services involved. The audits shall be conducted in accordance with established methods.
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                          'CR ERION8.                                                    BASIC REQUIREMENT 8                                      COMMENTS ANSI..45.2-1971 &sect; i"N18.7-19.6 &sect; 5..113.3          .NQA-1                                      1994"...
N45.2 - Measures shall be established and documented for the          Controls shall be established to assure that only correct and      Similar requirement.
identification and control of materials, parts, and components        accepted items are used or installed.
including partially fabricated subassemblies.
N18.7 - Measures shall be provided for the identification and control of materials, parts, and components including partially fabricated subassemblies.
N45.2 - When codes, standards, or specifications require              Identification shall be maintained on the items or in documents    Similar requirement. The traceability of materials, parts, or components to specific            traceable to the items, or in a manner which assures that          additional information in inspection or test records, the program shall be designed to          identification is established and maintained,                      the Basic Requirement is provide such traceability,                                                                                                                similar to that contained N18.7 - When codes, standards or specifications require                                                                                    later in the N45.2 and traceability of materials, parts or components to specific                                                                                N 18.7 text.
inspection or test records, the program shall be designed to provide such traceability.
SUPPLEMENT 8S-1 SUPPLEMENTARY REQUIREMENTS FOR IDENTIFICATION AND CONTROL OF ITEMS 1 GENERAL This Supplement provides amplified requirements for identification and control of items.
It supplements the requirements of Basic Requirement 8 of this Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
2 IDENTIFICATION METHODS 2.1 Item Identification N45.2 These measures shall provide for assuring that only              Items of production (batch, lot, component, part) shall be          Similar requirements.
correct and accepted items are used and installed, and relating        identified from the initial receipt and fabrication of the items up an item of production (batch, lot, component, part) at any stage,      to and including installation and use. This identification shall from initial receipt through fabrication, installation, repair or      relate an item to an applicable design or other pertinent modification, to an applicable drawing, specification, or other        specifying document.
pertinent technical document.
N18.7 - These procedures shall be implemented to provide insurance that only correct and accepted items are used and installed, and relating an item of production (batch, lot, component, part) at any stage, from initial receipt through fabrication, installation, repair or modification, to an applicable drawing, specification, or other pertinent technical document.
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                    *  .. CRITERIONS8                                                  BASIC REQUIREMN              8                        COMENTS ANSI 45.2-1971-4 9/N18.7-19V6&sect; 5.2.13.3                                              NQA-ti1994 2.2 Physical Identification N45.2.- Physical identification shall be used to the maximum        Physical identification shall be used to the maximum extent        Same requirement.
extent possible.                                                    possible.
N18.7 - Physical identification shall be used to the maximum extent possible.
N45.2 - Where physical identification is either impractical or      Where physical identification on the item is either impractical    Same requirement.
insufficient, physical separation, procedural control, or other      or insufficient, physical separation, procedural control, or other appropriate means shall be employed,                                appropriate means shall be employed.
N18.7 - Where physical identification is either impractical or insufficient, physical separation, procedural control or other appropriate means shall be employed.
N45.2 - Identification may be either on the item or on records      Identification markings, when used, shall be applied using        Similar requirement.
traceable to the item, as appropriate. Where identification          materials and methods which provide a clear and legible            NQA-l includes affect on marking is employed, the marking shall be clear, unambiguous,        identification and do not detrimentally affect the function or    service life of the and indelible, and shall be applied in such a manner as not to      service life of the item.                                          component as well as affect the function of the item.                                                                                                        function. (Note: Markings N18.7 - Identification may be either on the item or on records                                                                          are covered in more detail traceable to the item, as appropriate. Where identification                                                                            in NQA-1, Subpart 2.2 that marking is employed, the marking shall be clear, unambiguous                                                                            corresponds with ANSI and indelible, and shall be applied in such a manner as not to                                                                          N45.2.2. Addressed in affect the function of the item.                                                                                                        NQA-l Subpart 2.2 Table.)
2.3 Markings N45.2 - Markings shall be transferred to each part of an item        Markings shall be transferred to each part of an identified item  Similar requirement.
when subdivided and shall not be obliterated or hidden by            when subdivided and shall not be obliterated or hidden by surface treatment or coatings unless other means of                  surface treatment or coatings unless other means of identification are substituted.                                      identification are substituted.
N18.7 - Markings shall be transferred to each part of an item when subdivided and shall not be obliterated or hidden by surface treatment or coatings unless other means of identification are substituted.
3 SPECIFIC REQUIREMENTS 3.1 Identification and Traceability of Items N45.2, 3 - When codes, standards, or specifications require          When specified by codes, standards, or specifications that        Similar requirement.
traceability of materials, parts, or components to specific          include specific identification or traceability requirements (such NQA-1 provides examples inspection or test records, the program shall be designed to        as identification or traceability of the item to applicable        "such as identification or provide such traceability,                                          specification and grade of material; heat, batch, lot, part, or    traceability.... test, or other N18.7, 3 - When codes standards or specifications require            serial number; or specified inspection, test, or other records),  records."
traceability of materials, parts or components to specific          the program shall be designed to provide such identification and inspection or test records, the program shall be designed to        traceability control.
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  .                      CRITERION8      "                                        BASIC REQUIREMENT 8.                                COMM."ENTS ANSI 45.2-1971 &sect; 9/N18.7-1976&&sect; 5.2.13.3            .    ...                    NQA" 1994 provide such traceability.
3.2 Limited Life Items Where specified, items having limited calendar or operating life New requirement addressed or cycles shall be identified and controlled to preclude use of  in administrative items whose shelf life or operating life has expired.            procedures.
3.3 Maintaining Identification of Stored Items Provisions shall be made for the control of item identification  Similar requirement to consistent with the planned duration and conditions of storage,  N45.2.2, &sect; 6.4.1 in that an such as:                                                        inspection would identify (a) provisions for maintenance or replacement of markings and    the need to correct these identification records due to damage during handling or aging;  types of deficiencies.
(b) protection of identifications on items subject to excessive deterioration due to environmental exposure; (c) provisions for updating existing plant records.
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CRITERON 9                              .BASIC                REQUIREMENT 9                                        COMMENTS
        .ANSI N45.2-1971 &sect;10/ANSI N18.7% 1976 &sect; 5.2.18                                  NQA-1-1994                          __.___,.....______              ......
General Notes:
NQA 1983 and 1994 do not use the word "Special" out of the title. The text addresses "Special Processes."
The requirements of N45.2 and ANSI N18.7 are similar in nature to that discussed in Supplement 9S-1.
Therefore, the specific wording from these standards is not repeated next to the similar statements of NQA-1.
N45.2 Measures shall be established and documented to          Processes affecting quality of items or services shall be A similar requirement for controlling assure that special processes, ... are accomplished under      controlled.                                              processes, but NQA-1 doesn't limit the controlled conditions in accordance with applicable codes,                                                              processes at this point to those that are standards, specifications, criteria, and other special                                                                  deemed special processes.
requirements, ...
N18.7 5.2.18 Measures shall be established and documented to assure that special processes, accomplished under controlled conditions in accordance with applicable codes, standards, specifications, criteria, and other special requirements, ... _
N45.2 Measures shall be established and documented to          Special processes that control or verify quality, such as ANSI N18.7 defines special processes assure that special processes, including welding, heat        those used in welding, heat treating, and nondestructive  and includes chemical cleaning as a treating, cleaning, and nondestructive examination, are        examination, shall be performed by qualified personnel    special process. This is addressed in the accomplished under controlled conditions in accordance        using qualified procedures in accordance with specified  QAPD Part H, Sections 9 and 13.
with applicable codes, standards, specifications, criteria,    requirements.
and other special requirements, using qualified personnel and procedures.
N18.7 5.2.18 Special processes are those that require interim inprocess controls in addition to final inspection to assure quality including such processes as welding, heat treating, chemical cleaning, and nondestructive examination.
SUPPLEMENT 9S-1 SUPPLEMENTARY REQUIREMENTS FOR CONTROL OF PROCESSES 1 GENERAL 10/28/2010                                                Control of Special Processes / Control of Processes                                          Page I of 3
 
CRITE.R.ION 9                                          BAS .IC RE.QUIRE.MIE-.N9                                  COMME..NT ,S ANSIN45.2-1971 &sect;10/ANSI N18.7        -1976    5.2.18                              NQA-1-1994 This Supplement provides amplified requirements for control of processes.
It supplements the requirements of Basic Requirement 9 of this Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
2 PROCESS CONTROL N45.2 Measures shall be established and documented to          Processes shall be controlled by instructions, procedures,  Similar requirements.
assure that special processes, ... are accomplished ...        drawings, checklists, travelers, or other appropriate using qualified ... procedures.                                means.
N18.7 5.2.18 Measures shall be established and documented to assure that special processes, ... use qualified ... procedures.
N45.2 Measures shall be established and documented to          These means shall assure that process parameters are        Similar requirements.
assure that special processes, ... are accomplished under      controlled and that specified environmental conditions controlled conditions ....                                    are maintained.
N18.7 5.2.18 Measures shall be established and documented to assure that special processes, accomplished under controlled conditions ... use qualified personnel and procedures.
3 SPECIAL PROCESSES Each special process shall be performed in accordance      Procedure adherence is addressed in with appropriate instructions which include or reference    Section 5 of the QAPD.
procedure, personnel, and equipment qualification requirements.
3.1 Responsibility It is the responsibility of the organization performing the Procedure adherence is currently special process to adhere to the approved procedures and    addressed in the QA Standards related to processes.                                                  Criterion 5. Similar requirements exist.
N45.2 Qualification of personnel, procedures, and              3.1.1 Qualification of personnel, procedures, and          Similar requirements.
equipment shall comply with the requirements of                equipment shall comply with specified requirements.
applicable codes and standards.
N18.7 5.2.18 Qualification of personnel, procedures, and equipment shall comply with the requirements of applicable codes and standards.
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CRITERION                                              BASIC REQUIREMENT 9 B.                                                      COMMENTS ANSI_ N45. -19,71 &sect;10/ANSI Nt8.7&#xfd;,    - 1976 &sect;.18NQA-1-1,994 N45.2 Measures shall be established and documented to          3.1.2 Conditions necessary for accomplishment of the      Similar requirements.
assure that special processes, ... are accomplished under    process shall be included in procedures or instructions.
controlled conditions ....                                    These conditions shall include proper equipment, N18.7 5.2.18 Measures shall be established and                controlled parameters of the process, and calibration documented to assure that special processes, accomplished requirements.
under controlled conditions ...
3.2 Acceptance Criteria The requirements of applicable codes and standards,        Acceptance criteria currently addressed including acceptance criteria for the process, shall be    in the QA Standards related to Criterion specified or referenced in the procedures or instructions. 5. Similar requirements exist.
3.3 Records N45.2 - Documentation shall be maintained for currently      Records shall be maintained as appropriate for the          Similar requirements.
qualified personnel, processes, or equipment in accordance    currently qualified personnel, processes, and equipment with the requirements of pertinent codes and standards.        of each special process N18.7 - 5.2.12 requires provisions "be made for preparation and retention of plant records as appropriate."
3.4 Special Requirements N45.2 For special processes not covered by existing codes    For special processes not covered by existing codes and    Similar requirements.
or standards, or where item quality requirements exceed      standards or where quality requirements specified for an the requirements of established codes or standards, the      item exceed those of existing codes or standards, the necessary qualifications of personnel, procedures, or        necessary requirements for qualifications of personnel, equipment shall be defined,                                  procedures, or equipment shall be specified or N18.7 For special processes not covered by existing codes    referenced in the procedures or instructions.
or standards, or where item quality requirements exceed the requirements of established codes or standards, the necessary qualifications of personnel, procedures, or equipment shall be defined.
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CRITERION 10                                                  BASIC REQUIREM-ENT 10                                    COMIMENTS        .
ANSI N45.2-1971 /ANSI N18-.7-1976                                                NQA-1 1994                              ___________
N45.2 &sect; 11, N18.7 &sect; 5.2.17 N45.2&sect; 11, &#xb6; 1 A program for inspection of activities affecting      Inspections required to verify conformance of an item or          Similar requirement.
quality shall be established and executed by or for the              activity to specified requirements shall be planned and executed.
organization performing the activity to verify conformance to the documented instructions, procedures, and drawings for accomplishing the activity.
N45.2&sect; 11, &#xb6; 2 Examinations, measurements, or tests of items processed shall be performed for each work operation where necessary to assure quality.
N18.7 &sect; 5.2.17, &#xb6; 1 A program for inspection of activities affecting safety shall be established and executed by or for the organization performing the activity to verify conformance with applicable documented instructions, procedures, and drawings.
N18.7 &sect; 5.2.17, &#xb6; 2 Inspections, examinations, measurements, or tests of material, products, or activities shall be performed for each work operation where necessary to assure quality.
N18.7 &sect; 5.2.17, &#xb6; 4 Inspections of safety-related activities shall  Characteristics to be inspected and inspection methods to be      Similar requirement.
be performed in accordance with approved written procedures,        employed shall be specified.
which set forth the requirements and acceptance limits and specify the inspection responsibilities.
N18.7, &sect; 5.3.10, &#xb6;1 Test and inspection results shall be            Inspection results shall be documented.                          Similar requirement.
documented ...
N45.2&sect; 11, &#xb6; 1 Inspection activities to verify the quality of work  Inspection for acceptance shall be performed by persons other    Similar requirement. NQA-shall be performed by persons other than those who performed        than those who performed or directly supervised the work being    1 and Nl18.7 both specify the activity being inspected,                                        inspected,                                                        that it should not be those N18.7 &sect; 5.2.17, &#xb6; 2 Such inspections shall be performed by                                                                            who performed the activity qualified individuals other than those who performed or directly                                                                      or directly supervised the supervised the activity being inspected,                                                                                              activity (work) being These independent inspections, i.e., those performed by                                                                                inspected.
individuals not assigned first-line supervisory responsibility for the conduct of the work, are not intended to dilute or replace the clear responsibility of first-line supervisors for the quality of work performed under their supervision.
N18.7 &sect; 5.2.17, &#xb6; 6 - The owner organization shall evaluate                                                                            Not specifically addressed inspection results along with test results (see Section 5.2.19) to                                                                    by NQA- 1, but is addressed determine whether the individual inspection and test programs                                                                          in QAPD Sections 10.1 and demonstrate that the plant can be operated safely and as                                                                              11.
designed.
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                      ...CRITERION 10                                                BASIC REQUIREMENT 10                                    COMMENTS
                .ASI N45.2-19711ANSI N18.7-1976                                                NQA-1 199 SUPPLEMENT lOS-1 SUPPLEMENTARY REQUIREMENTS FOR INSPECTION 1 GENERAL This Supplement provides amplified requirements for inspection of items and activities.
It supplements the requirements of Basic Requirement 10 of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
2 INSPECTION REQUIREMENTS N18.7 &sect; 5.2.17, &#xb6; 4 Information concerning inspection shall be    Inspection requirements and acceptance criteria shall include      Similar requirement.
obtained from the related design drawings, specifications and/or  specified requirements contained in the applicable design other controlled documents.                                        documents or other pertinent technical documents approved by the responsible design organization.
N18.7 &sect; 5.2.17, &#xb6; 4 Inspections of safety-related activities shall Inspection activities shall be documented and controlled by        Similar requirement.
be performed in accordance with approved written procedures,      instructions, procedures, drawings, checklists, travelers, or other NQA-1 allows use of
...                                                                appropriate means.                                                  documents other than N18.7, &sect; 5.3.10, &#xb6; 1 Test and inspection results shall be                                                                              procedures to control the documented ...                                                                                                                        inspection.
3 PERSONNEL 3.1 Reporting Independence N45.2&sect; 11, &#xb6; 1 - Such persons shall not report directly to the    Inspection personnel shall not report directly to the immediate    Similar requirement, but immediate supervisors who are responsible for the work being      supervisors who are responsible for performing the work being      NQA- 1 adds a requirement inspected,                                                        inspected.                                                          for inspectors to not report N18.7 &sect; 5.2.17, &#xb6; 2 - Inspection of operating activities (work                                                                        to the immediate supervisor functions associated with normal operation of the plant, routine                                                                      for the work. (consistent maintenance, and certain technical services routinely assigned                                                                        with N45.2) to the onsite operating organization) may be conducted by second-line supervisory personnel or by other qualified personnel not assigned first-line supervisory responsibility for conduct of the work.
3.2 Qualification N18.7 &sect; 5.2.17, &#xb6; 4 - When inspection techniques require          Each person who verifies conformance of work activities for        Similar requirement.
specialized qualifications or skills, personnel performing the    purposes of acceptance shall be qualified to perform the inspection shall meet applicable licensing requirements, codes,    assigned inspection task.
and standards appropriate to the discipline involved (see also Sections 5.2.7, 5.2.6 and 5.3.10).
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CRITER ION  N 1U                                      'BAI B I**    . .EQUIREM        .NT
                                                                                                                  .10                    COM NTS...
ANI N45.2-1971/ANSI NIS7-&#xfd;1976                                            NQA-i 1994..
Inspections by persons during on-the-job training for            New requirement to this qualification shall be performed under the direct observation    standard, but consistent with and supervision of a qualified person and verification of        those of the standards for conformance shall be by the qualified person until certification  training and qualification.
is achieved.
4 INSPECTION HOLD POINTS N45.2&sect; 11, &#xb6; 4 - If mandatory inspection hold points, which    If mandatory inspection hold points are required beyond which    Similar requirement.
require witnessing or inspecting by the purchaser's designated  work shall not proceed without the specific consent of the representative and beyond which work shall not proceed          designated representative, the specific hold points shall be without the consent of the purchaser's designated              indicated in appropriate documents.
representative, are required, the specific hold points shall be indicated in appropriate documents.
N18.7 &sect; 5.2.17, &#xb6; 4 - If mandatory inspection hold points are required, the specific hold points shall be indicated in appropriate documents.
N45.2&sect; 11, &#xb6; 4 - Such consent shall be documented prior to the  Consent to waive specified hold points shall be recorded prior to Similar requirement.
continuation of work beyond the designated hold point,          continuation of work beyond the designated hold point.
5 INSPECTION PLANNING
_5.1                                                                  Planning Planning for inspection activities shall be accomplished and      New requirement.
documented. The documentation shall identify characteristics,    This currently is met methods, and acceptance criteria, and shall provide for          through the development of recording objective evidence of inspection results.              inspection documents.
5.2 Sampling N45.2&sect; 11, &#xb6; 2 - Where a sample is used to verify acceptability Where a sample is used to verify acceptability of a group of      Similar requirement.
of a group of items, the sampling procedure shall be based on  items, the sampling procedure shall be based on recognized recognized standard practices and shall provide adequate        standard practices.
justification for the sample size and selection process.
6 IN-PROCESS INSPECTION 6.1 Inspection Inspection of items in-process or under construction shall be    New requirement performed for work activities where necessary to verify quality,  addressing items in-process or under construction. This is consistent with current practice.
N45.2&sect; 11, &#xb6; 3 -If inspection of processed items is impossible  If inspection of processed items is impossible or                Similar requirement.
or disadvantageous, indirect control by monitoring of          disadvantageous, indirect control by monitoring of processing processing methods, equipment, and personnel shall be            methods, equipment, and personnel shall be provided.
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CRITERION 10                                            BASIC REQ.UIR.M.NT 0                                COMMENTS
              .ANSI N45.2-I971IANSI N18-7-1976                                              NQA-l 1994 provided.
N18.7 &sect; 5.2.17, &#xb6; 5 - If inspection is impossible or disadvantageous, indirect control by monitoring processing methods, equipment and personnel shall be provided.
N45.2&sect; 11, &#xb6; 3 - Both inspection and process monitoring shall  Both inspection and process monitoring shall be provided when  Similar requirement.
be provided when control is inadequate without both.            control is inadequate without both.
N18.7 &sect; 5.2.17, &#xb6; 5 - Both inspection and process monitoring shall be provided when control is inadequate without both..
6.2 Combined Inspection and Monitoring N18.7 &sect; 5.2.17, &#xb6; 5 - In cases where documented verification of 6.2.1 A combination of inspection and process monitoring        NQA-1 meets the intent of quality implied by the above requirements is not possible or    methods, when used, shall be performed in a systematic manner  NI 8.7. NQA-1 is more feasible, the extent of inspection or performance testing to    to assure that the specified requirements for control of the    descriptive of how to verify adequacy of structures, systems, or components for      process and quality of the item are being achieved throughout  combine inspection and service should be, in general, greater than otherwise required. the duration of the process.                                    monitoring that is not addressed in N45.2 or specifically addressed in N18.7.
6.2.2 Controls, where required, shall be established and documented for the coordination and sequencing of these activities at established inspection points during successive stages of the conducted process or construction.
7 FINAL INSPECTIONS                                            Requirements carried 7.1 Resolution of Nonconformances                              forward from the N45.2.4 Final inspections shall include a records review of the results and N45.2.8 standards on and resolution of nonconformances identified by prior          Electrical/I&C and inspections.                                                    Mechanical Installations.
These are also addressed in comparing NQA- 1, Subparts 2.4 and 2.8 to the N45.2 series standards.
The final inspection shall be planned to arrive at a conclusion regarding conformance of the item to specified requirements.
7.2 Inspection Requirements Completed items shall be inspected for completeness, markings, calibration, adjustments, protection from damage, or other characteristics as required to verify the quality and conformances of the item to specified requirements.
Quality records shall be examined for adequacy and 10/28/2010                                                                Inspection                                                              Page 4 of 6
 
CR,. .TE.....ON10                                            BAS.IC RMENT                  10. ......    .........        COMMENTS ASI N45.2-1971/ANSI N18.7-191                                                  NQA-1 1994                                  ___________
completeness if not previously so examined.
7.3 Acceptance The acceptance of the item shall be documented and approved by authorized personnel.
7.4 Modifications, Repairs, or Replacements N18.7 &sect; 5.2.17, &#xb6; 3 - For modifications and nonroutine              Modifications, repairs, or replacements of items performed            Similar requirement.
maintenance, inspections shall be conducted in a manner similar    subsequent to final inspection shall require reinspection or          NQA-1 uses the term (frequency, type, and personnel performing such inspections) to    retest, as appropriate, to verify acceptability.                      "reinspection or retest, as that associated with construction phase activities (see also                                                                              appropriate," in lieu of "in a Section 5.2.7).                                                                                                                          manner similar to ...
construction phase activities." NQA-l also applies to construction.
8 INSERVICE INSPECTION 8.1 Planning and Performance N45.2&sect; 11, &#xb6; 5 - A program for required inservice inspection of    Required in-service inspection or surveillance of structures,        Similar requirement.
completed systems, structures, and components shall be planned      systems, or components shall be planned and executed by or for and executed by or for the organization responsible for            the organization responsible for operation.
operation of the nuclear plant.
N18.7, &sect; 5.2.8, &#xb6; 1 Provisions shall be made for performing required surveillance testing and inspections, including inservice inspections. Additional control procedures shall be instituted, as necessary, to assure timely conduct of surveillance tests and inspections and appropriate documentation, reporting, and evaluation of the results.
8.2 Methods Inspection methods shall be established and executed to verify        NQA-1 addresses that the characteristics of an item continue to remain within        requirements of the specified limits. Inspection methods shall include evaluations of inservice inspection/testing performance capability of essential emergency and safety              program that were not systems and equipment, verification of calibration and integrity      addressed in the previous of instruments and instrument systems, and verification of            Quality Standards. Not a maintenance, as appropriate.                                          new requirement above the existing ASME in-service inspection requirements.
9 RECORDS N18.7 &sect; 5.2.17, &#xb6; 6 - Records shall be kept in sufficient detail to Records shall, as a minimum, identify (a) through below:              Similar requirement.
permit adequate confirmation of the inspection program. The        (a) item inspected                                                    Requirement to identify the 10/28/2010                                                                    Inspection                                                                    Page 5 of 6
 
SCRITERI ON 10                                                  BASIC REQUIREMENT 10            .CQMMFNTS ANSI N45.i2-'1'9&#xfd;7 1&#xfd;/ANSI'NI 8.7-1976                                        NQA-1 1994 person recording the data as well as the person approving the    (b) date of inspection                                          person recording data is inspection results shall be identified. Deviations, their cause,  (c) inspector                                                  eliminated. Requirement for and any corrective action completed or planned as a result of the (d) type of observation                                        inspection records to be deviations shall be documented. Inspection records shall be      (e) results or acceptability                                    specifically identified as identified as such and shall be retrievable (see also Section    (f) reference to information on action taken in connection with such is not included in 5.2.12).                                                          nonconformances                                                NQA-1. This allows for inspections being documented within maintenance and test procedures.
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                .ASI      CRITERION1                                                BASI REQUIREMENT411CM                                      NT ANIN45.2-1971/ANSI      N18.7-4976                      .NQA-1                    1994                    ____________
N45.2 &sect;12 / N18.7 &sect; 5.2.19                                        BASIC REQUIREMENT N45.2, &#xb6; 1 A test program shall be established to assure that all Tests required to verify conformance of an item or computer  NQA-l adds requirement testing required to demonstrate that the item will perform        program to specified requirements and to demonstrate        for test of computer satisfactorily in service is identified and documented, ...      satisfactory performance for service shall be planned and    software. This is addressed N18.7, &#xb6; 1 A test program shall be established to assure that    executed.                                                    in the QAPD Part II, testing required to demonstrate that the item will perform                                                                    Section 3.3.
satisfactorily in service is identified and documented, ...
N18.7, &sect; 5.2.19.2 Tests Prior to and During Initial Plant Operation.
&#xb6; 1 Prior to placing a nuclear power plant into operation, a preoperational test program shall be performed to demonstrate the functional adequacy of plant components, systems and structures. Following fuel loading an initial start-up test program shall be conducted to evaluate plant performance as the start-up progresses.
&#xb6; 2 Responsibilities The ultimate responsibility for the preparation and execution of adequate preoperational and initial start-up test programs rests with the owner organization. If design or construction is performed by other than the owner organization, design organizations involved should participate in definition of the programs, and the construction organization involved may supply manpower or supervision for execution of part or all of the program, but the owner organization shall determine that the program is adequate and that the results are satisfactory.
&#xb6; 3 Scheduling A schedule shall be provided and maintained to provide assurance that all necessary tests are performed and properly evaluated on a timely basis. Testing shall be scheduled so that the safety of the plant is never dependent on the performance of an untested system (see also Section 5.2.8).
N45.2, &#xb6; 1 ... and that the testing is performed in accordance    Characteristics to be tested and test methods to be employed Similar Requirement.
with written test procedures which incorporate or reference the  shall be specified.
requirements and acceptance limits contained in applicable design documents N18.7, &#xb6; 1 ... and that the testing is performed in accordance with written test procedures which incorporate or reference the requirements and acceptance limits contained in applicable design documents.
N45.2, &#xb6; 2 Test results shall be documented and evaluated by      Test results shall be documented and their conformance with  Similar Requirement.
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CRITERION 11                                              BASIC REQUIREMENT 11                                      COMMENTS ASI N4$.i-1971/AS N1 -1976                      .                          NQA41 1994 responsible authority to assure that test requirements have been  acceptance criteria shall be evaluated.
satisfied.
N18.7, &sect; 5.3.10, &#xb6; 1 Test and inspection results shall be documented and evaluated by responsible authority to assure that test and inspection requirements have been satisfied.
N18.7, &sect; 5.2.17, &#xb6; 6 The owner organization shall evaluate inspection results along with test results (see Section 5.2.19) to determine whether the individual inspection and test programs demonstrate that the plant can be operated safely and as designed.
N18.7, &sect; 5.2.8, &#xb6; 1 Provisions shall be made for performing required surveillance testing and inspections, including inservice inspections.... Additional control procedures shall be instituted, as necessary, to assure timely conduct of surveillance tests and inspections and appropriate documentation, reporting, and evaluation of the results.
Tests required to collect data, such as for siting or design input, NQA- 1 adds requirement shall be planned, executed, documented, and evaluated,              for siting and design input to address new construction and design changes.
SUPPLEMENT 11S-1 SUPPLEMENTARY REQUIREMENTS FOR TEST CONTROL 1 GENERAL This Supplement provides amplified requirements for test control.
It supplements the requirements of Basic Requirement 11 of this Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
2 TEST REQUIREMENTS N45.2, &#xb6; 1 Test requirements and acceptance criteria shall be      Test requirements and acceptance criteria shall be provided or      Similar Requirement.
provided by the organization responsible for the design of the    approved by the organization responsible for the design of the item under test, unless otherwise designated.                      item to be tested unless otherwise designated.
N45.2, &#xb6; 1 The test program shall cover all required tests,        Required tests, including, as appropriate, prototype qualification  NQA-1 includes production including, as appropriate, prototype qualification tests, proof    tests, production tests, proof tests prior to installation,        tests that are not addressed tests prior to installation, preoperational tests, and operational construction tests, pre-operational tests, and operational tests    by ANSI N45.2 or N 18.7.
tests to verify continued satisfactory performance during          shall be controlled.
operation.                                                                                                                            ANSI N 18.7 gives more N18.7, &#xb6; 1-5 The test program shall cover all required tests                                                                          detail on the purpose and 10/28/2010                                                                  Test Control                                                                Page 2 of 10
 
CRITERIONS119                  '                    BA.CREUIEMNT11CO.ET**S BA..*.. I      E              COMMENTS ANSI N4S.2-&#xfd;19071l/ANSI ,N18.7-1976                [NQA-1                1994        ___________
including:                                                                                          extent of the described tests.
(1) Tests during the preoperational period to demonstrate that                                      This is addressed in the performance of plant systems is in accordance with design                                            QAPD Part II, Section 11.
intent and that the coordinated operation of the plant as a whole is satisfactory, to the extent feasible.
(2) Tests during the initial operational phase to demonstrate the performance of systems that could not be tested prior to operation and to confirm those physical parameters, hydraulic or mechanical characteristics that need to be known, but which could not be predicted with the required accuracy, and to confirm that plant behavior conforms to design criteria. The initial start-up test program shall be planned to permit safe fuel loading and start-up; to increase power in safe increments; and to perform major testing at specified power plateaus. If tests require the variation of operating parameters outside of their normal range, the limits within which such variation is permitted shall be prescribed. Prerequisites and record keeping shall be given attention and the scope of the testing shall demonstrate insofar as practicable that the plant is capable of withstanding the design transients and accidents. The suitability of plant operating procedures should be checked to the maximum extent possible during the preoperational and initial start-up test programs.
(3) Surveillance tests during the operational phase to provide assurance that failures or substandard performance do not remain undetected and that the required reliability of safety-related systems is maintained (see Section 5.2.8).
(4) Tests during design, fabrication and construction activities associated with plant maintenance and modifications during the operational phase and the demonstration of satisfactory performance following plant maintenance and modifications or procedural changes (see Section 5.2.7).
NRC Reg. Guide 1.33, Regulatory Position C.5.f- The guidelines (indicated by the verb "should") of ANSI N 18.7-1976/ANS-3.2 contained in the following sections have sufficient safety importance to be treated the same as the requirements (indicated by the verb "shall") of the standard: f.
Section 5.2.19(2) - The guideline for checking plant operating procedures during the testing program.
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:CRITERION 11.o                                            BASICREQUIREMNT 11tME                                    CNTS ANSI N452.-1971/ANSI N18.7-1976.                                              NQA-1 1994 "_..''_..."___..                                  "'._.
N45.2, &#xb6; 1 ... and that the testing is performed in accordance    Test requirements and acceptance criteria shall be based upon      NQA-1 addresses other with written test procedures which incorporate or reference the    specified requirements contained in applicable design or other    pertinent documents other requirements and acceptance limits contained in applicable        pertinent technical documents.                                    than design documents that design documents                                                                                                                      may be a source of technical N18.7, &#xb6; 1 ... and that the testing is performed in accordance                                                                        requirements or acceptance with written test procedures which incorporate or reference the                                                                      limits.
requirements and acceptance limits contained in applicable design documents.
3 TEST PROCEDURES N45.2, &#xb6; 2 Test procedures shall include provisions for assuring  Tests procedures shall include or reference test objectives and    Similar requirement.
that prerequisites for the given test have been met, that adequate provisions for assuring that prerequisites for the given test have ANSI Ni18.7 contains more instrumentation is available and used, and that necessary          been met, that adequate instrumentation is available and used,    detail on the objectives of monitoring is performed.                                          that necessary monitoring is performed, and that suitable          preoperational and N18.7, &sect; 5.3.10, &#xb6; 1 Test and inspection procedures shall          environmental conditions are maintained.                          operational tests. This is contain a description of objectives; acceptance criteria that will                                                                    addressed in the QAPD Part be used to evaluate the results; prerequisites for performing the                                                                    II, Sections 5 & 11.
tests or inspections including any special conditions to be used to simulate normal or abnormal operating conditions; limiting conditions; and the test or inspection procedure. These procedures shall also specify any special equipment or calibrations required to conduct the test or inspection.
ANSI N18.7, &sect; 5.3.10, &#xb6; 2 Where tests and inspections are to be witnessed, the procedure shall identify hold points in the testing sequence to permit witnessing. The procedure shall require appropriate approval for the work to continue beyond the designated hold point.
N18.7, &sect; 5.2.19.1 Preoperational Tests
&#xb6; 1 Preoperational tests are generally performed sequentially in accordance with written procedures.
&#xb6; 4 A component test is a functional, operational or performance test of an individual piece of equipment or unit system under prescribed conditions. Typical parameters to be examined are direction of rotation, bearing temperatures, vibration, time delays, and ability to operate with remote and local controls. The procedure should list checks to be made and provide acceptance criteria. Consideration should also be given to providing a run-in period to minimize early failures during operation of the plant.
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CRITERION 11                6                              BASIC REQUIREM.ENT I I                                    COMM,,NTS ANSI N45.2-1971/ANSI N187-"1976                    J.NQA-1                              1994                          ___________
&#xb6; 5 Individual system tests establish the functional adequacy by operation under prescribed conditions. The tests shall be designed to permit evaluation of system performance including, for example, the measurement of flow, temperature, pressure, response time and vibration, transfer of power supply to emergency power and accuracy and response of control devices.
&#xb6; 6 The preoperational testing program should demonstrate, as nearly as can be practicably simulated, the overall integrated operation of the plant systems at rated conditions, including simultaneous operations of auxiliary systems. It may be necessary to defer portions of these tests until nuclear heat is available. The procedures used should be similar to those discussed in 5.3.3 and 5.3.4, and they should be modified to require variation in control parameters, such as pump stops and restarts, cycling valves and varying flows so that system performance can be evaluated. For additional requirements in matters relating to preoperational test programs, American National Standard N45.2.8-1975 is generally applicable. [8]
NRC Reg. Guide 1.33, Regulatory Position C.5.g - The guidelines (indicated by the verb "should") of ANSI N 18.7-1976/ANS-3.2 contained in the following sections have sufficient safety importance to be treated the same as the requirements (indicated by the verb "shall") of the standard: g.
Section 5.2.19.1 - The guideline for preoperational tests, except the guideline that refers to a run-in period for equipment. In addition to these guidelines, the prerequisite steps for each equipment test should be completed prior to the commencement of the preoperational test.
N45.2, &#xb6; 2 Prerequisites include such items as calibrated          Prerequisites shall include the following, as applicable:        Basic requirements are instrumentation, appropriate equipment, trained personnel,          calibrated instrumentation, appropriate equipment, trained        similar.
condition of test equipment and the item to be tested, suitable    personnel, condition of test equipment and the item to be tested, ANSI N 18.7 provides more environmental conditions, and provisions for data acquisition.      suitable environmental conditions, and provisions for data        detail on the nature and N18.7, &sect; 5.3.10, &#xb6; 1 Test and inspection procedures shall          acquisition.                                                      content of prerequisites.
contain a description of objectives; acceptance criteria that will                                                                    This is addressed in the be used to evaluate the results; prerequisites for performing the                                                                    QAPD Part II, Section 11.
tests or inspections including any special conditions to be used to simulate normal or abnormal operating conditions; limiting conditions; and the test or inspection procedure. These 10/28/2010                                                                  Test Control                                                              Page 5 of 10
 
CRITERION 11                                                  BASIC RIEQUIREMENT 11                                  CONMMENTS.
ANSI N45.2-1071/ANSI*N18.7r19760                                                NQA-1 199"4 procedures shall also specify any special equipment or calibrations required to conduct the test or inspection.
N18.7, &sect; 5.2.19.1 Preoperational Tests
&#xb6; 2 Procedures should ensure that prerequisite steps for equipment testing, such as completion of necessary construction, prior testing, safety precautions, and measures to preserve equipment status have been or will be performed (see also Sections 5.2.17 and 5.3.10).
&#xb6; 3 A detailed prescribed physical inspection of equipment components and facilities should be performed to ensure readiness for operation. Typical items to be covered include cleanliness, lubrication, setting of limit switches, calibration of instruments and presence of safety devices. The test procedure should list the checks to be made and include acceptance criteria and reference sources, such as vendor's literature, engineering drawings or plant specifications.
NRC Reg. Guide 1.33, Regulatory Position C.5.g - The guidelines (indicated by the verb "should") of ANSI N 18.7-1976/ANS-3.2 contained in the following sections have sufficient safety importance to be treated the same as the requirements (indicated by the verb "shall") of the standard: g.
Section 5.2.19.1 - The guideline for preoperational tests, except the guideline that refers to a run-in period for equipment. In addition to these guidelines, the prerequisite steps for each equipment test should be completed prior to the commencement of the preoperational test.
In lieu of specially prepared written test procedures, appropriate NQA- 1 addresses using sections of related documents, such as ASTM methods, Supplier      standard test methods or manuals, equipment maintenance instructions, or approved          other forms of instructions.
drawings or travelers with acceptance criteria, can be used. Such documents shall include adequate instructions to assure the required quality of work.
4 TEST RESULTS N45.2, &#xb6; 2 Test results shall be documented and evaluated by        Test results shall be documented and evaluated by a responsible    Similar requirement.
responsible authority to assure that test requirements have been    authority to assure that test requirements have been satisfied.
satisfied.
N18.7, &sect; 5.3.10, &#xb6; 1 Test and inspection results shall be documented and evaluated by responsible authority to assure 10/28/2010                                                                  Test Control                                                              Page 6 of 10
 
CRITERION.11.                                              BASIC REQUIREMENT I I B1                                                COMMENTS ANSI. N45.2-971I/ANSI .N18 .7-19'76                            ..              NQA-1 1994    .,
that test and inspection requirements have been satisfied.
5 TEST RECORDS ANSI N18.7, &sect; 5.3.10, &#xb6; 2 The test and inspection procedures      Test records shall, as a minimum, identify (a) through (g)    Similar requirement.
shall require recording the date, identification of those        below:
performing the test or inspection, as found condition, corrective (a) item tested actions performed, if any, and as-left condition.                (b) date of test (c) tester or data recorder (d) type of observation (e) results and acceptability (f) action taken in connection with any deviations noted (g) person evaluating test results SUPPLEMENT 1IS-2 SUPPLEMENTARY                                NQA- l-1994 adds REQUIREMENTS FOR COMPUTER PROGRAM                              requirements in this TESTING                                                        Supplement for QA for Computers and Software.
Additional requirements are contained in Basic Requirement 3 with Supplement 3S-1 and Subpart 2.7 of NQA-1.
These quality assurance requirements were not specifically addressed in the previous standards.
However, the NRC required licensees to commit to controlling computer software in their QA Programs.
1 GENERAL This Supplement provides amplified requirements for testing of SCE&G establishes and computer programs and associated computer systems.            implements provisions to assure that computer software used in applications affecting safety is prepared, documented, verified and tested, and used such that the expected output is obtained and 10/28/2010                                                                  Test Control                                                          Page 7 of 10
 
        ... * .IT.    .,.
* i    , " : C~T~~N 1*    ..    ' .* * " .    . : .BASIC*
                                                                    "1              . . .            .... * :
REQUIREMENT        1.1. .:.'                      C2OMMENTS ANSI N45.2-1971/ANSI<'Nl8.7-1&#xfd;976.,                                      NQA-1 1994                                ___________
configuration control maintained. To this end SCE&G commits to compliance with the requirements of NQA                                                                                                                                        1994, Supplement 11 S-2 and Subpart 2.7 to establish the appropriate provisions.
It supplements the requirements of Basic Requirement 11 of this Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
2 TEST REQUIREMENTS Test requirements and acceptance criteria shall be provided or approved by the organization responsible for the design of the item to be tested unless otherwise designated.
Required tests including (as appropriate) verification tests, hardware integration tests, and in-use tests shall be controlled.
Test requirements and acceptance criteria shall be based upon applicable design or other pertinent technical documents.
2.1 Verification Tests Verification tests shall demonstrate the capability of the computer program to produce valid results for test problems encompassing the range of permitted usage defined by the program documentation.
Acceptable test problem solutions are as follows:
(a) hand calculations; (b) calculations using comparable proven programs; or (c) empirical data and information from technical literature.
For programs used for operational control, testing shall demonstrate required performance over the range of operation of the controlled function or process.
Depending on the complexity of the computer program being tested, testing may range from a single test of the completed computer program to a series of tests performed at various stages of computer program development to verify correct translation between stages and proper working of individual modules, followed by an overall computer program test.
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CRITERION 11                              BASIWC REQUIREMET 11                          COMMENTS ANSI N45.2-1971/ANSIN18.7-19,76                              NQA-1 19.94 Regardless of the number of stages of testing performed, verification testing shall be sufficient to establish that test requirements are satisfied and that the computer program produces a valid result for its intended function.
2.2 In-Use Tests Test problems shall be developed and documented to permit confirmation of acceptable performance of the computer program in the operating system.
Test problems shall be run whenever the computer program is installed on a different computer, or when significant hardware or operating system configuration changes are made.
Periodic in-use manual or automatic self-check routines shall be prescribed and performed for those applications where computer failures or drift can affect required performance.
3 TEST PROCEDURES Test procedures or plans shall specify the following, as applicable:
(a) required tests and test sequence (b) required ranges of input parameters (c) identification of the stages at which testing is required (d) criteria for establishing test cases (e) requirements for testing logic branches (f) requirements for hardware integration (g) anticipated output values (h) acceptance criteria (i) reports, records, standard formatting, and conventions.
4 TEST RESULTS Test results shall be documented.
Verification test results shall be evaluated by a responsible authority to assure that test requirements have been satisfied.
5 TEST RECORDS (a) Verification test records shall identify (1) through (10) below.
(1) computer program tested (2) computer hardware used (3) test equipment and calibrations, where applicable (4) date of test (5) tester or data recorder 10/28/2010                                          Test Control                                              Page 9 of 10
 
CRITERION~i. I 1C.Q.1M-OMMENTSEN*                                                                                .C ANSI N45.2-1971./ANSI N18.7-19176        "__"_"__
______  "1"99"4_*_-'-
(6) simulation models used, where applicable (7) test problems (8) results and acceptability (9) action taken in connection with any deviations noted (10) person evaluating test results.
(b) in-use test results shall identify (1) through (6) below:
(1) computer program tested (2) computer hardware used (3) test equipment and calibrations, where applicable (4) date of test (5) tester or data recorder (6) acceptability.
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CRITERION 12                                                  BASWCREQUIREMENT 12,                                    COMMENTS ANSI N45.2-1'71/ANSI-N"8.7.1976                                                  NQA-1 1994"__..                      .        _..      _..____.__
N45.2 &sect;13 / N18.7 &sect; 5.2.16 N18.7 &#xb6; 2 Tools, instruments, testing equipment and measuring      Tools, gages, instruments, and other measuring and test          Similar requirement.
devices used for measurements, tests and calibration ... shall be  equipment used for activities affecting quality shall be controlled, calibrated and adjusted and maintained at specified    controlled and at specified periods calibrated and adjusted to intervals or prior to use to assure the necessary accuracy of      maintain accuracy within necessary limits.
calibrated devices.
SUPPLEMENT 12S-1 SUPPLEMENTARY                                  Additional M&TE REQUIREMENTS FOR CONTROL OF MEASURING                            requirements are contained AND TEST EQUIPMENT                                                in NQA-l, Subpart 2.16, a standard not previously committed to at VCSNS.
1 GENERAL This Supplement provides amplified requirements for control of measuring and test equipment.
N18.7 &#xb6;1 The method and interval of calibration for each            It supplements the requirements of Basic Requirement 12 of      NQA-1 applicability is installed instrument and control device shall be defined and        this Part (Part 1) and shall be used in conjunction with that    discussed in the shall be based on the type of equipment, stability and reliability  Basic Requirement when and to the extent specified by the        Introductions to Parts I and characteristics, required accuracies and other conditions          organization invoking this Part (Part 1).                        II. It likewise applies to the affecting calibration,                                                                                                              operations phase. However, N18.7 &#xb6; 4 Special calibration shall be performed when the                                                                            NQA-1 doesn't specifically accuracy of... installed ... equipment is questionable.                                                                              state that the M&TE N18.7 &#xb6; 4 American National Standard N45.2.4-1972 shall be                                                                          program is applicable to applied to those activities occurring during the operational                                                                        installed instrument and phase that are comparable in nature and extent to related                                                                            control devices. Installed activities occurring during construction.                                                                                            instrument and control devices are calibrated and adjusted in accordance with the maintenance and testing programs and the controls are addressed in the QAPD, Part  II, Section 12.1.
2 SELECTION N45.2 &sect;13 &#xb6; 1 Measures shall be established and documented          Selection of measuring and test equipment shall be controlled to ANSI N45.2.5 contains to assure that tools, gages, instruments, and other inspection,    assure that such items are of proper type, range, accuracy, and  additional information on measuring, and testing equipment and devices used in activities    tolerance to accomplish the function of determining              the selection of M&TE.
affecting quality are of the proper range, type, and accuracy to    conformance to specified requirements.                            This is addressed in NQA-1 verify conformance to established requirements.                                                                                      Subpart 2.5.
N18.7 &#xb6; 2 Tools, instruments, testing equipment and measuring_
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RITERO1N 12 81BASIC                                              REQUIREMENT 12          COMMENTS*
ANSI N45.2-19.71/ANSi N18.7-4976.                                            NOA 1994      ___________
devices used for measurements, tests and calibration shall be of the proper range and type and shall be controlled, calibrated and adjusted and maintained at specified intervals or prior to use to assure the necessary accuracy of calibrated devices.
N45.2.1 &sect; 2.5 Test Equipment 2.5.1 Selection. Inspection and test equipment used to implement the requirements of this standard shall be selected to have sufficient accuracy and sensitivity tolerance to determine conformance to specified requirements.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.1 Selection. Inspection, examination, and testing equipment utilized to implement the requirements of this standard shall be selected to have accuracy and tolerance sufficient to determine conformance to specified requirements.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.1 Selection Inspection and testing equipment with acceptable accuracy for performing the required function shall be selected. When general voltage levels, flow directions, or other parameters are checked, an instrument without high precision may be used.
When characteristics, efficiencies, capabilities, or other properties are measured to appraise compliance with specifications, the instrument must have adequate accuracy to determine the measured quantity to the precision required by the stated limits of the specifications. Use shall be made of approved industry standards relating to measuring procedures.
Test equipment and/or apparatus supplying electrical, mechanical, or other test inputs shall have adequate capacity and be compatible with items under test so that the results will not be distorted.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.1 Selection.
Measuring and test equipment used to implement the requirements of this standard shall be selected on the basis of accuracy sufficient to determine conformance to specified requirements.
These measuring devices shall include but not to be limited to thermometers, balances, scales, air entrainment meters, Page 2 of 8 10/28/2010 10/28/2010                                                    Control of Measuring and Test Equipment Control of Measuring and Test Equipment                    Page 2 of 8
 
              *,, ~~~~  .. IE IO .2    121      ~--- **.!*.,*.,"  T..
o      .CRITERIONBASIC... -..
                                                                                            ... REQUIREMENT
                                                                                                      ........        12                  'ICOMMENT.S.. COMMENTS      .,
ANSI N45.2-197l/ANSISN18.7-1976                                                      NQA-1 &deg;1994                      .......      _____".....              _
humidity meters, volumetric buckets, field soil density measuring devices, pressure gages, and torque wrenches.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.1 Selection. Measuring and test equipment used to implement the requirements of this standard shall be selected to have range, type and accuracy sufficient to determine conformance to specified requirements.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.1 Selection. Inspection, examination, and testing equipment utilized to implement the requirements of this standard shall be selected to have accuracy and tolerance sufficient to determine conformance to specified recuirements.
                                                                      +
3 CALIBRATION AND CONTROL                                            1 4.
3.1 Calibration N45.2 &sect;13 &#xb6; 1 To assure accuracy, inspection, measuring, and            Measuring and test equipment shall be calibrated, adjusted, and        Similar requirements.
test equipment shall be controlled, calibrated, adjusted, and            maintained at prescribed intervals or, prior to use, against maintained at prescribed intervals or prior to use against              certified equipment having known valid relationships to certified equipment having known valid relationships to                  nationally recognized standards.
nationally recognized standards.
N18.7 &#xb6; 2 Tools, instruments, testing equipment and measuring devices used for measurements, tests and calibration shall be of the proper range and type and shall be controlled, calibrated and adjusted and maintained at specified intervals or prior to use to assure the necessary accuracy of calibrated devices.
ANSI N45.2.1 &sect; 2.5 Test Equipment 2.5.2 Calibration and Control. Test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally known standards.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. As appropriate, measuring and test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. Measuring and test equipment used to determine compliance with specifications, shall be adjusted and calibrated at orescribed intervals anainst certified Page 3 of 8 10/28/2010 10/28/2010                                                        Control  of Measuring and Test Equipment Control of Measuring and Test Equipment                                                        Page 3 of 8
 
CRITTERIO..
                                  .I.ON. 12:                                          BASIC REQUIREMENT 11                                      COMMENTS
              .ANSI N45.2-I9711ANSIN18.741976                .                                N"A-1. 1994 . "_
N                          ...... ........          ____"
equipment having known valid relationships to nationally recognized standards. If no national standards exist, the basis for calibration shall be documented. Records of the calibrations shall be maintained and equipment suitably marked to indicate date of next required calibration. When inspection and testing equipment are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested. Test equipment found to be out of calibration shall be clearly identified as such.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. The equipment shall be adjusted or calibrated or both at prescribed intervals against certified standards having known valid relationships to national standards, where such exists.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 Calibration and Control. Measuring and test equipment used to determine compliance with Specifications, shall be adjusted and calibrated at predetermined intervals, based on equipment stability and use, against certified equipment having known valid relationships to nationally recognized standards.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. As appropriate, measuring and test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards.
N45.2 &sect;13 &#xb6; 1 If no national standards exist, the basis for          If no nationally recognized standards exist, the bases for            Similar requirement.
calibration shall be documented.                                      calibration shall be documented.
ANSI N45.2.1 &sect; 2.5 Test Equipment 2.5.2 Calibration and Control. If no national standards exist, the basis of calibration shall be documented.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. If no national standards exist, the basis for calibration shall be documented.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. If no national standards exist, the basis for calibration shall be documented.
N45.2.5 6 2.5 Measurine and Test Eauipment.
Equipment                                                    Page 4 of 8 10/28/2010                                                      Control of Measuring and Test 10/28/2010                                                      Control of Measuring and Test Equipment                                                      Page 4 of 8
 
ANI.....IN1.                                                  BASIC REQUIREMNT 12                                COMMENTS, ANSI      N4&#xfd;2497/ANS N187-1976.NQA-1                                                1994' 2.5.2 Calibration and Control. If no national standards exist, the basis for the adjustment or calibration shall be documented.
Records shall be maintained and equipment suitably marked to indicate calibration status. Measures shall be taken to assure proper handling, storage and care of installation of inspection and testing equipment after calibration in order to maintain the required accuracy of such equipment.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 If no national standards exist, the basis for calibration shall be documented.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. If no standards exist, the basis for calibration shall be documented.
3.2 Control N45.2 &sect;13 &#xb6; 2 The method and interval of calibration for each        The method and interval of calibration for each item shall be  Similar requirement.
item shall be defined and shall be based on the type of              defined, based on the type of equipment stability equipment, stability characteristics, required accuracy, and          characteristics, required accuracy, intended use, and other other conditions affecting measurement control.                      conditions affecting measurement control.
N45.2 &sect;13 &#xb6; 2 When inspection, measuring, and test equipment          When measuring and test equipment is found to be out of        Similar requirement.
are found to be out of calibration, an evaluation shall be made      calibration, an evaluation shall be made and documented of the and documented of the validity of previous inspection or test        validity of previous inspection or test results and of the results and of the acceptability of items previously inspected or    acceptability of items previously inspected or tested.
tested.
N18.7 &#xb6; 2 When calibration, testing, or other measuring devices are found to be out of calibration, an evaluation shall be made and documented concerning the validity of previous tests and the acceptability of devices previously tested from the time of the previous calibration.
ANSI N45.2.1 &sect; 2.5 Test Equipment 2.5.2 Calibration and Control. When inspection and testing equipment is found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and acceptability of items previously inspected or tested.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. When inspection and testing equipment are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested.
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CRITERION 12                                                  BASIC REQUIREMNT 12                                  COMMENTS ANSI N45,      g,-71/ANSI N18.7-1976..........                  . .                NQA-1 1994 N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. Test equipment found to be out of calibration shall be clearly identified as such. When discrepancies, malfunctions, or inaccuracies in inspection and testing equipment are found during calibration, all items inspected with that equipment since the last previous calibration shall be considered unacceptable until an evaluation has been made by the responsible authority and appropriate action taken.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 Calibration and Control. When measuring and test equipment is found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and the acceptability of mechanical items inspected or tested since the last calibration check. Where necessary to determine the acceptability of items or data, the required original inspections or tests or applicable portions thereof shall be repeated using properly calibrated equipment. In the event that the status of equipment precludes using the originally specified methods, equipment or procedures, alternate inspections or tests agreeable to the responsible organizations may be used.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. When inspection, measuring and test equipment are found to be out of calibration, an evaluation shall be made and documented of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested.
N45.2.4 &sect; 2.5 Measuring and Test Equipment                            Out-of-calibration devices shall be tagged or segregated and not Similar requirement.
2.5.2 Calibration and Control. Test equipment found to be out        used until they have been recalibrated.
of calibration shall be clearly identified as such.
N45.2 &sect;13 &#xb6; 2 If any inspection, measuring, or test equipment is      If any measuring or test equipment is consistently found to be  Similar requirement.
consistently found to be out of calibration, it shall be repaired    out of calibration, it shall be repaired or replaced.
or replaced.
N18.7 &#xb6; 2 If any calibration, testing or measuring device is consistently found to be out of calibration, it shall be repaired or replaced.
N45.2 &sect;13 &#xb6; 2 Special calibration shall be performed when            A calibration shall be performed when the accuracy of the        Similar requirement.
accuracy of the equipment is suspect.                                equipment is suspect.
N18.7 &#xb6; 4 Special calibration shall be performed when the 10/28/2010                                                      Control of Measuring and Test Equipment                                                Page 6 of 8
 
CRITERION,12                                                BASIC REQURMENT 2COMMETS
              'ANSI N45.2-971/ANSIVN18.74.976                                                  NQA-1 1994 -,..            ....    ,  ..  ,.      ..      ,.      ..
accuracy of... calibrating equipment is questionable.
3.3 Commercial Devices N45.2 &sect;13 &#xb6; 1 This requirement is not intended to imply a need      Calibration and control measures may not be required for          Similar requirement.
for special calibration and control measures on rulers, tape        rulers, tape measures, levels, and other such devices, if normal measures, levels, and such other devices, if normal commercial      commercial equipment provides adequate accuracy.
practices provide adequate accuracy.
N18.7 &#xb6; 3 It is not the intent of this Standard to imply a need for special calibration and control measures on rulers, tape measures, levels and other such devices if normal commercial practices provide adequate accuracy.
4 HANDLING AND STORAGE N45.2.5 &sect; 2.5 Measuring and Test Equipment.                          Measuring and test equipment shall be properly handled and        Similar requirement.
2.5.2 Calibration and Control. Measures shall be taken to assure    stored to maintain accuracy.
proper handling, storage and care of installation of inspection and testing equipment after calibration in order to maintain the required accuracy of such equipment.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 Calibration and Control.
Measures shall be taken to assure proper handling, storage, and care of the measuring and test equipment after calibration in order to maintain the required accuracy of such equipment.
5 RECORDS N45.2 &sect;13 &#xb6; 3 Records shall be maintained and equipment              Records shall be maintained and equipment shall be suitably      Similar requirement.
suitably marked to indicate calibration status.                      marked to indicate calibration status.
N18.7 &#xb6; 4 Records shall be made and equipment suitably marked to indicate calibration status.
ANSI N45.2.1 &sect; 2.5 Test Equipment 2.5.2 Calibration and Control. Records shall be maintained and equipment suitably marked to indicate calibration status.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. Records shall be maintained and equipment suitably marked to indicate calibration status.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. Records of the calibrations shall be maintained and equipment suitably marked to indicate date of next required calibration.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. Records shall be maintained and 10/28/2010                                                    Control of Measuring and Test Equipment                                                  Page 7 of 8
 
          "i*:."        CRITERION
* ANSI N45*2*I      7I*
JANTIIN 12 187-97 I .- 9 6      *      *:
                                                                      ...**": ....* : *....:BASIC  REQUIJRMLENT
                                                                                                '""&deg;&deg;    ... ** ..'* 12 NQ "- 1994....                COMMENTS equipment suitably marked to indicate calibration status.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 Calibration and Control. Records of calibrations shall be maintained and equipment suitably marked so that the calibration status can be determined. Records of calibration shall be included in inspection and test results where applicable.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. Records shall be maintained and equipment suitably marked to indicate calibration status or the records shall be traceable to the equipment.
N45.2.8 &sect; 2.8 Measuring and Test Equipment                                                                                N45.2.8 addresses inclusion 2.8.2 Calibration and Control. .... Records of calibration shall                                                          of records of calibration in be included in inspection and test results where applicable.                                                              with inspection and test results where applicable.
This level of detail is not specifically addressed in NQA- 1, but the intent is met through the standard for QA records.
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CRITERION 13                                              BASIC REQUIREMENT 13                              -COMMENTS ANSI N45.2-1971 &sect; 1,4/ANSI N18:7I976          5.2.13.4 ,    '.:".1994 N45.2 &#xb6;1 Measures shall be established and documented to        Handling, storage, cleaning, packaging, shipping, and          Similar requirement.
control handling, storage, and shipping, including cleaning,    preservation of items shall be controlled to prevent damage or packaging, and preservation of material and equipment in        loss and to minimize deterioration.
accordance with established instructions, procedures, or drawings, to prevent damage, deterioration, and loss.
N18.7 &#xb6; 1 Measures shall be provided to control handling, storage and shipping, including cleaning, packaging and preservation of material and equipment in accordance with established instructions, procedures or drawings, to prevent damage, deterioration and loss.
SUPPLEMENT 13S-1 SUPPLEMENTARY REQUIREMENTS FOR HANDLING, STORAGE, AND SHIPPING 1 GENERAL This Supplement provides amplified requirements for handling, storage, and shipping.
It supplements the requirements of Basic Requirement 13 of this Part (Part 1) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
2 INSTRUCTION N45.2 &#xb6; 1 Measures shall be established and documented to      Handling, storage, and shipping of items shall be conducted in  Similar requirement.
control handling, storage and shipping including cleaning,      accordance with established work and inspection instructions, packaging, and preservation of material and equipment in        drawings, specifications, shipment instructions, or other accordance with established instructions, procedures, or        pertinent documents or procedures specified for use in drawings to prevent damage, deterioration, and loss.            conducting the activity.
N18.7 &#xb6; 1 Measures shall be provided to control handling, storage and shipping, including cleaning, packaging, and preservation of material and equipment in accordance with established instructions, procedures or drawings, to prevent damage, deterioration and loss.
3 REQUIREMENTS 3.1 General N45.2 &#xb6; 1 When necessary for particular items, special          When required for particular items, special equipment (such as  Similar requirement.
coverings, special equipment, and special protective            containers, shock absorbers, and accelerometers) and special environments such as inert gas atmosphere, specific moisture    protective environments (such as inert gas atmosphere, specific 10/28/2010                                                    Handling, Storage, and Shipping                                                Page I of 3
 
13                                        BASIC REQUIREMENT13                  .CRITERION        COMMENTS ANSI NSI .-. 971 14/..SI. NA 7-176, &sect; 5.2.13.4                                        NQA-1 1994          .
content levels, and temperature levels shall be specified,        moisture content levels, and temperature levels) shall be provided, and their existence verified,                          specified, provided, and their existence verified.
N18.7 &#xb6; 1 When necessary for particular items, special coverings, special equipment and special protective environments, such as inert gas atmosphere, specific moisture content levels and temperature levels shall be specified, provided, and their existence verified.
3.2 Procedures N45.2 &#xb6; 2 For critical, sensitive, perishable, or high-value      When required for critical, sensitive, perishable, or high-value  Similar requirement.
articles, specific written procedures for handling, storage,      articles, specific procedures for handling, storage, packaging, packaging, shipping, and preservation should be used.            shipping, and preservation shall be used.
N18.7 &#xb6; 2 For critical, sensitive, perishable or high-value articles, specific written procedures for handling, storage, packaging, shipping and preservation should be used.
3.3 Tools and Equipment N45.2 &#xb6; 2 Special handling tools and equipment should be          Special handling tools and equipment shall be utilized and        Similar requirement but provided and controlled as necessary to ensure safe and          controlled as necessary to ensure safe and adequate handling,      changed from guidance to a adequate handling,                                                                                                                  requirement of NQA N18.7 &#xb6;2 Special handling tools and equipment should be                                                                              1994.
provided and controlled as necessary to ensure safe and adequate handling.
N45.2 &#xb6; 3 Special handling tools and equipment shall be          Special handling tools and equipment shall be inspected and        Similar requirement.
inspected and tested, in accordance with written procedures and  tested in accordance with procedures and at specified time at specified times to verify that the tools and equipment are    intervals to verify that the tools and equipment are adequately adequately maintained,                                            maintained.
N18.7 &#xb6; 3 Special handling tools and equipment shall be inspected and tested in accordance with written procedures and at specified times, to verify that the tools and equipment are adequately maintained.
3.4 Operators Operators of special handling and lifting equipment shall be      Similar requirement experienced or trained in use of the equipment.
4 MARKING N45.2 &#xb6; 4 Special attention shall be given to providing adequate  Instructions for marking and labeling for packaging, shipment,    Similar requirement.
instructions for marking and labeling for packaging, shipment,    handling, and storage of items shall be established as necessary and storage of items. Marking shall be adequate to identify,      to adequately identify, maintain, and preserve the item, 10/28/2010                                                      Handling, Storage, and Shipping                                                    Page 2 of 3
 
CRITERION1*3                                                BASIC REQUIREMENT 13                          ,."        CO**.
ANSI N45 2-971        14/ANSI N18J.4976 &sect;,5.2.13.4                                          A 1 9&#xfd;94-  ...-.
maintain, and preserve the shipment, including indication of the  including indication of the presence of special environments or presence of special environments or the need for special control. the need .for special controls.
N18.7 &#xb6; 4 Attention shall be given to providing adequate instructions for marking and labeling of items for packaging, shipment and storage. Marking shall be adequate to identify, maintain and preserve the shipment, including indication of the presence of special environments or the need for special control.
N18.7 &#xb6; 5 American National Standard for Packaging,                                                                                    ANSI N45.2.2 is addressed Shipping, Receiving, Storage and Handling of Items for Nuclear                                                                        as NQA-l-1994, Subpart Power Plants (During the Construction Phase), N45.2.2-1972,                                                                            2.2. A separate Table for shall be applied to those activities occurring during the                                                                              NQA-1 Subpart 2.2 is used operational phase that are comparable in nature and extent to                                                                          to compare these two related activities occurring durinn construction.                                                                                      documents.
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TEIN 4BASIC                                        REQUIRMENT 14                                COAMMNTS
                ;'ANSI N45.2-1971/ANSI N18.7-1976                                                WNQA, 11994 N45.2 &sect; 15 / N18.7 &sect; 5.2.6 Unless otherwise noted.
N45.2, &#xb6; 1 Measures shall be established and documented to          The status of inspection and test activities shall be identified  Similar requirement.
identify inspection and test status. Such measures shall provide    either on the items or in documents traceable to the items where means for assuring that required inspections and tests are          it is necessary to assure that required inspections and tests are performed and that the acceptability of items with regard to        performed and to assure that items which have not passed the inspections and tests performed is known throughout                  required inspections and tests are not inadvertently installed, manufacturing, installation, and operation.                          used, or operated.
N45.2, &#xb6; 2 The measures shall provide for assuring that only items that have passed the required inspections and tests are used, installed, or operated.
N18.7, &sect; 5.2.6, &#xb6; 5 Procedures shall also provide for the identification of items which have satisfactorily passed required inspections and tests, where necessary to preclude inadvertent bypassing of such inspections and tests. In cases where required documentary evidence is not available, the associated equipment or materials must be considered nonconforming in accordance with Section 5.2.14. Until suitable documentary evidence is available to show the equipment or material is in conformance, affected systems shall be considered to be inoperable and reliance shall not be placed on such systems to fulfill their intended safety functions.
N18.7, &sect; 5.2.7, &#xb6; 4 Measures shall be established and documented to identify the inspection and test status of items to be used in maintenance and modification activities. Normally, the point of control for such items should be the plant storage area.
N45.2, &#xb6; 1 Nonconforming items shall be clearly identified.          Status shall be maintained through indicators, such as physical  Similar requirement.
N45.2, &#xb6; 2 The inspection and test status of items shall be          location and tags, markings, shop travelers, stamps, inspection  Nonconforming items from maintained through the use of status indicators such as physical    records, or other suitable means.                                N45.2 are further addressed location and tags, markings, shop travelers, stamps, or                                                                                by NQA- 1 under Basic inspection records.                                                                                                                    Requirement 15 and N18.7, &sect; 5.2.6, &#xb6; 2 Equipment and systems in a controlled status                                                                      Supplement 15S-1.
shall be clearly identified. Strict control measures for such equipment shall be enforced.
N18.7, &sect; 5.2.6, &#xb6; 5 The procedures shall also require that the status of inspections and tests performed upon individual items on the nuclear power plant be indicated by the use of markings such as stamps, tags, labels, routing cards, or other suitable means. Suitable means include identification numbers which are 10/28/2010                                                      Inspection, Test, and Operating Status                                                Page I of 3
 
                        `CRJTRION 14                                                  BASIC REQUI          MENT 4COM                                    M ENTS ANSI. N45.2-1971 /ANSIN18.7-14976                      .                        . NQA-1 1994          '              '__"_____..__.._.
traceable to records of the status of inspections and tests.
N45.2, &#xb6; 2 These measures shall include procedures for control      The authority for application and removal of tags, markings,          Similar requirement.
of status indicators, including the authority for application and    labels, and stamps shall be specified.                                NQA-1 doesn't add the removal of tags, markings, labels, and stamps.                                                                                            detail regarding operating N18.7, &sect; 5.2.6, &#xb6; 1 Permission to release equipment or systems                                                                            personnel verifying that for maintenance shall be granted by designated operating                                                                                  equipment can be released personnel. Prior to granting permission, such operating                                                                                    and determining how long it personnel shall verify that the equipment or system can be                                                                                can be released, or the released, and determine how long it may be out of service.                                                                                return to service Granting of such permission shall be documented.                                                                                          requirements.
N18.7, &sect; 5.2.6, &#xb6; 6 When equipment is ready to be returned to service, operating personnel shall place the equipment in operation and verify and document its functional acceptability.
N45.2, &#xb6; 3 Measures shall also provide for indicating the            Status indicators shall also provide for indicating the operating    Similar requirement.
operating status of systems and components of the nuclear            status of systems and components of the nuclear facility, such as Procedure requirements are power plant, such as by tagging valves and switches, to prevent      by tagging valves and switches, to prevent inadvertent                addressed by NQA-1 in inadvertent operation.                                              operation.                                                            Basic Requirement 5.
N18.7, &sect; 5.2.6, &#xb6; 4 Procedures shall be provided for control of                                                                            SCE&G is committed to equipment, as necessary, to maintain personnel and reactor                                                                                having procedures of the safety and to avoid unauthorized operation of equipment. These                                                                            type stated in Reg. Guide procedures shall require control measures such as locking or                                                                                1.33, Appendix A.
tagging to secure and identify equipment in a controlled status.
The procedures shall require independent verifications, where appropriate, to ensure that necessary measures, such as tagging equipment, have been implemented correctly.
N18.7, &sect; 5.2.6, &#xb6; 1 Attention shall be given to the potentially                                                                            NQA- 1 does not provide degraded degree of protection when one subsystem of a                                                                                      guidance on this aspect of redundant safety system has been removed for maintenance.                                                                                  controlling equipment.
Addressed in QAPD Part V, Section 4 N18.7, &sect; 5.2.6, &#xb6; 2 After permission has been granted to remove                                                                            NQA- 1 does not provide the equipment from service, it shall be made safe to work on.                                                                              guidance on this aspect of Measures shall provide for protection of equipment and                                                                                    controlling equipment.
workers.                                                                                                                                  Addressed in QAPD Part V, Section 4 N18.7, &sect; 5.2.6, &#xb6; 3 Conditions to be considered in preparing                                                                              NQA-1 does not provide equipment for maintenance include, for example: shutdown                                                                                  guidance on this aspect of margin; method of emergency core cooling; establishment of a                                                                              controlling equipment.
path for decay heat removal; temperature and pressure of the                                                                              Addressed in QAPD Part V, 10/28/2010                                                      Inspection, Test, and Operating Status                                                      Page 2 of 3
 
S CRITERION.14                                                  BASIC REQUIREMIENT 14        COMMENTS A SN45.2-197VIANSI N187-1976..                                                  NQA-1 1994    Section 4 system; valves between work and hazardous material; venting,                                                Section 4 draining and flushing; entry into closed vessels; hazardous atmospheres; handling hazardous materials; and electrical hazards. When entry into a closed system is required, control measures shall be established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed.
N18.7, &sect; 5.2.6, &#xb6; 5 Temporary modifications, such as temporary                                              NQA- 1 does not provide bypass lines, electrical jumpers, lifted electrical leads, and                                              guidance on this aspect of temporary trip point settings, shall be controlled by approved                                              controlling equipment.
procedures which shall include a requirement for independent                                                Addressed in QAPD Part V, verification. A log shall be maintained of the current status of                                            Section 4 such temporary modifications.
N18.7, &sect; 5.2.6, &#xb6; 6 Attention shall be given to restoration of                                              NQA- 1 does not provide normal conditions, such as removal of jumpers or signals used                                                guidance on this aspect of in maintenance or testing or such as returning valves, breakers                                              controlling equipment.
or switches to proper start-up or operating positions from "test"                                            Addressed in QAPD Part V, or "manual" positions. When placed into service, the equipment                                              Section 4 should receive additional surveillance during the run-in period.
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          *CRITERION                    15                                            BASIC REQUIREMENT 15                                  CO    WN$
N4.2..        /.ANSI 45.2-1971/ANSI N18.7-1976                                                NQA-1 1994 N45.2 &sect; 16 N18.7 &sect; 5.2.14 Unless otherwise noted.
N45.2, &#xb6;1 Measures shall be established and documented to          Items that do not conform to specified requirements shall be        Similar requirement.
control items, services, or activities which do not conform to    controlled to prevent inadvertent installation or use.
requirements.
N18.7, &#xb6; 1 Measures shall be provided to control items, services or activities which do not conform to requirements (Note in N 18.7 text: see also Section 5.2.6).
N45.2, &#xb6; 1 These measures shall include, as appropriate,          Controls shall provide for identification, documentation,          Similar requirement.
procedures for identification, documentation, segregation,        evaluation, segregation when practical, and disposition of disposition, and notification to affected organizations.          nonconforming items, and for notification to affected N18.7, &#xb6; 1 These procedures shall include as appropriate,          organizations.
instructions for identification, documentation, segregation, disposition and notification to affected organizations.
SUPPLEMENT 15S-1 SUPPLEMENTARY REQUIREMENTS FOR THE CONTROL OF NONCONFORMING ITEMS 1 GENERAL This Supplement provides amplified requirements for the control of nonconforming items.
It supplements the requirements of Basic Requirement 15 of this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part I).
2 IDENTIFICATION N45.2, &#xb6; 2 Measures which control further processing, delivery,    (a) Identification of nonconforming items shall be by marking,      Similar requirement.
or installation of a nonconforming or defective item pending a    tagging, or other methods which shall not adversely affect the decision on its disposition shall be established and maintained,  end use of the item. The identification shall be legible and easily
... Such measures shall provide assurance that the item is        recognizable.
identified as nonconforming and controlled.                        (b) If identification of each nonconforming item is not practical, N45.2, &#xb6; 3 As a guideline, control of nonconforming items by      the container, package, or segregated storage area, as tagging, marking, or other means of identification is acceptable  appropriate, shall be identified.
where physical segregation is not practical, although physical segregation and marking are preferred.
N18.7, &#xb6; 2 Measures which control further processing, delivery or installation of a nonconforming or defective item pending a decision on its disposition shall be established and maintained.
... Such measures shall provide assurance that the item is identified as nonconforming and controlled.
N18.7, &#xb6; 2 As a guideline, control of nonconforming items by 10/28/2010                                              Nonconforming Materials, Parts, or Components (Items)                                          Page I of 4
 
CRITERION 15                                              BASIC REQUIREMENT 15                                  CONMMENTS ANSI. 45.2-1971/A"NSI N18.7-1976                                            NQA-1 1:994 tagging, marking or other means of identification is acceptable where physical segregation is not practical, although physical segregation and marking are preferred.
3 SEGREGATION N45.2, &#xb6; 3 As a guideline, control of nonconforming items by      (a) Nonconforming items shall be segregated, when practical,    Similar requirement.
tagging, marking, or other means of identification is acceptable  by placing them in a clearly identified and designated hold area where physical segregation is not practical, although physical    until properly dispositioned.
segregation and marking are preferred.                            (b) When segregation is impractical or impossible due to N18.7, &#xb6; 3As a guideline, control of nonconforming items by      physical conditions such as size, weight, or access limitations, tagging, marking or other means of identification is acceptable  other precautions shall be employed to preclude inadvertent use where physical segregation is not practical, although physical    of a nonconforming item.
segregation and marking are preferred.
4 DISPOSITION 4.1 Control N45.2, &#xb6; 1 Nonconforming items shall be reviewed and              Nonconforming characteristics shall be reviewed and              Similar requirement.
accepted, rejected, repaired, or reworked in accordance with      recommended dispositions of nonconforming items shall be        The four types of documented procedures.                                            proposed and approved in accordance with documented              dispositions are addressed N18.7, &#xb6; 1 Nonconforming items shall be reviewed and              procedures.                                                      in 4.4 of the NQA-1 accepted, rejected, repaired or reworked in accordance with                                                                        standard.
documented procedures.
N45.2, &#xb6; 2 Measures which control further processing, delivery,  Further processing, delivery, installation, or use of a          Similar requirement.
or installation of a nonconforming or defective item pending a    nonconforming item shall be controlled pending an evaluation decision on its disposition shall be established and maintained,  and an approved disposition by authorized personnel.
... Such measures shall provide assurance that the item is identified as nonconforming and controlled.
N18.7, &#xb6; 2 Measures which control further processing, delivery or installation of a nonconforming or defective item pending a decision on its disposition shall be established and maintained.
... Such measures shall provide assurance that the item is identified as nonconforming and controlled.
4.2 Responsibility and Authority N45.2, &#xb6; 1 The responsibility and authority for the disposition  The responsibility and authority for the evaluation and          Similar requirement.
of nonconforming items shall be defined.                          disposition of nonconforming items shall be defined.
N18.7 - The responsibility and authority for the disposition of nonconforming items shall be defined.
4.3 Personnel Personnel performing evaluations to determine a disposition      This requirement from shall have demonstrated competence in the specific area they    NQA-1 was not specifically are evaluating, have an adequate understanding of the            addressed in the 10/28/2010                                            Nonconforming Materials, Parts, or Components (Items)                                          Page 2 of 4
 
CRITERION415..                                            BASIC REQUREMENT 15                                    COM'"NTS ANSI 45.2-1971/ANSI N18.7-197              '..                                NQA-1 1994 "                      .
requirements, and have access to pertinent background            corresponding sections of information,                                                      the ANSI Standards, but is a requirement of the training and qualification standard.
QAPD Part II, Section 2 4.4 Disposition N45.2, &#xb6; 2 Nonconforming items may be disposed of by              The disposition, such as use-as-is, reject, repair, or rework, of Similar requirement.
acceptance "as is," by scrapping or repairing the defective item, nonconforming items shall be identified and documented.
or by rework to complete or correct to a drawing or specification.
N18.7, &#xb6;2 Nonconforming items may be disposed of by acceptance "as is," by scrapping or repairing the defective item, or by rework to complete or correct to a drawing or specification.
N45.2, &#xb6; 2 The measures shall require documentation verifying    Technical justification for the acceptability of a nonconforming  Similar requirement.
the acceptability of nonconforming items which have the          item, dispositioned repair, or use-as-is shall be documented. NQA- 1 is more specific that disposition of repair or use as is.                                                                                                the content of the N18.7, &#xb6; 2 The measures shall require documentation verifying                                                                      documentation include the acceptability of nonconforming items which have the                                                                            technical justification.
disposition of "repair" or "use as is."
Nonconformances to design requirements dispositioned              This requirement from use-as-is or repair shall be subject to design control measures  NQA-1 was not specifically commensurate with those applied to the original design.          addressed in the corresponding sections of the ANSI Standards, but is in line with requirements of the design and procurement standards. QAPD Part H Sections 3 and 7 address this.
N45.2, &#xb6; 2 A description of the change, waiver, or deviation      The as-built records, if such records are required, shall reflect Similar requirement.
that has been accepted shall be documented to record the change  the accepted deviation.
and denote the as-built condition.
N18.7, &#xb6; 2 A description of the change, waiver or deviation that has been accepted shall be documented to record the change and denote the as-built condition.
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CRITERION 15          :BASIC                                        R*U*'.RENMNT 15                              C OMM.ENTS ANSI5.2N49,74        siS.7-19706 q*                                                    NQA-1 1994        ,              .,:,.
4.5 Repaired or Reworked Items N45.2, &#xb6; 1 Repaired and reworked items shall be reinspected in Repaired or reworked items shall be reexamined in accordance      Similar requirement.
accordance with applicable procedures.                          with applicable procedures and with the original acceptance      NQA-1 further addresses N18.7, &#xb6; 1 Repaired and reworked items shall be reinspected in criteria unless the nonconforming item disposition has            the acceptance criteria to accordance with applicable procedures.                          established alternate acceptance criteria.                      use in the I_inspection/examination.
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CRTRO,6ASIC                                              REQLUIRENENT 16                                COMMENTS
    , ,,: ... AN SI N,45.'2;.1971/AN Sl N 18.7-1976
:.,-                                                    *      .. ..              *,.........A. .....
N.. 1.......
19.........9.4.........
_N45.2 &sect; 17 / N18.7 &sect; 5.2.11 N45.2, &#xb6; 1 Measures shall be established and documented to              Conditions adverse to quality shall be identified promptly and    Similar requirement.
assure that conditions adverse to quality, such as failures,            corrected as soon as practical.                                    NQA-A defines "Condition malfunctions, deficiencies, deviations, defective material and                                                                            adverse to quality" as equipment, and nonconformances, are promptly identified and                                                                                "failures, malfunctions, corrected as soon as practicable.                                                                                                          deficiencies, deviations, N18.7, &#xb6; 1 The program shall provide measures to ensure that                                                                              defective items, and conditions adverse to plant safety, such as failure, malfunctions,                                                                        nonconformances."
deficiencies, deviations, defective material and equipment, abnormal occurrences, and nonconformances are promptly identified and corrected.
N45.2, &#xb6; 1 In the case of significant conditions adverse to            In the case of a significant condition adverse to quality, the    Similar requirement.
quality, the measures shall assure that the cause of the condition      cause of the condition shall be determined and corrective action is determined and corrective action taken to preclude repetition.      taken to preclude recurrence.
N18.7, &#xb6; 1 In the case of significant conditions adverse to safety, the measures shall assure that the cause of the condition is determined and corrective action taken ....
N45.2, &#xb6; 1 The identification of significant conditions adverse        The identification, cause, and corrective action for significant  Similar requirement.
to quality, the cause of the condition, and the corrective action      conditions adverse to quality shall be documented and reported    Ni18.7 addresses the need taken shall be documented and reported to appropriate levels of        to appropriate levels of management.                              for independent review.
management.                                                                                                                                This is addressed N18.7, &#xb6; 1 - In the case of significant conditions adverse to                                                                              under the requirements for safety, the measures shall assure that the cause of the condition                                                                          independent review within is determined and corrective action taken shall be documented                                                                              the QAPD, Part V, Section and reported to appropriate levels of management and for                                                                                  2.
independent review in accordance with Section 4.3.
Follow-up action shall be taken to verify implementation of this  New stated requirement corrective action.                                                from NQA-1. This is in line with the intent of the current standards regarding corrective action precluding recurrence.
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ANS                  CRITERION 17              N    "8.                          BASIC REQUIREMENT 17                              COMMENTS.
    'ASI 45.2-19071/ANSI N45.19-1974/ANSI N.8,7-19/6..:                                        NQA-1 1994 N45.2 &sect; 18 / N18.7 &sect; 5.2.12 unless otherwise noted.
N45.2, &#xb6; 1 Sufficient records shall be prepared as work is          Records that furnish documentary evidence of quality shall be  Similar requirement.
performed to furnish documentary evidence of the quality of        specified, prepared, and maintained.
items and of activities affecting quality.
N18.7, &#xb6; 1 Provisions shall be made for preparation and retention of plant records as appropriate.
N45.2, &#xb6; 2 Required records shall be legible, identifiable, and    Records shall be legible, identifiable, and retrievable.      Similar requirement.
retrievable.                                                                                                                      N18.7 refers to N45.2.9 for N18.7, &#xb6; 1 American National Standard Requirements for                                                                            management of records.
Collection, Storage and Maintenance of Quality Assurance                                                                          N45.2.9 is compared with Records for Nuclear Power Plants, N45.2.9-1974, shall be used                                                                      NQA-1 Basic and for management of plant records during the operational phase.                                                                      Supplementary Requirements of 17S-1 below.
N45.2, &#xb6; 4 These records shall be indexed, filed, and maintained    Records shall be protected against damage, deterioration, or  Similar requirement.
in facilities that provide suitable environment to minimize        loss.
deterioration or damage and to prevent loss.
N45.2, &#xb6; 3 Requirements and responsibilities for record            Requirements and responsibilities for record transmittal,      Similar requirement.
transmittal, retention, and maintenance subsequent to              distribution, retention, maintenance, and disposition shall be completion of work shall be established and documented              established and documented.
consistent with applicable codes, standards, and procurement documents.
N18.7, &#xb6; 1 The responsibility for maintaining records and storing them at a specified location or locations shall be assigned. Retention periods of sufficient duration to assure the ability to reconstruct significant events and satisfy any statutory requirements which apply shall be specified.
N45.2.9 &sect; 2. GENERAL REQUIREMENTS This section sets forth general requirements for the control of quality assurance records. The requirements include collection, filing, storing, maintenance and disposition of records that are required by other codes, standards, specifications, or regulatory requirements. The procedures to be employed to perform the required activities shall be planned and documented.
SUPPLEMENT 17S-1 Supplementary Requirements for Quality Assurance Records 1 GENERAL N45.2.9 &sect; 1. INTRODUCTION                                          This Supplement provides amplified requirements for quality    NQA- 1 further addresses 10/28/2010                                                            Quality Assurance Records                                                Page I of 15
 
S CRITERION 17                                                  BASIC REQUIREMENT 17                                  COMMENTS,-
ANSI 45.2-,1971/ANSION,45.2.91974I/ANSINI8.,7-1976:                                          NQA"1 1994 1.1 Scope                                                            assurance records. It supplements the requirements of Basic      applicability in the This standard provides general requirements and guidelines for      Requirement 17 of this Part (Part I) and shall be used in        Introduction to Part I.
the collection, storage, and maintenance of quality assurance        conjunction with that Basic Requirement when and to the extent records associated with the design, manufacture, construction,      specified by the organization invoking this Part (Part I).
and operation phase activities of nuclear power plants. It is not    The requirements of this Supplement apply to quality assurance intended to cover the preparation of the records, nor to include    records Which have been completed.
working documents not yet designated as quality assurance            The term records, used throughout this Supplement, is to be records.                                                            interpreted as Quality Assurance Records.
2 RECORDS ADMINISTRATION 2.1 Records System N45.2.9 &sect; 2.1 Quality Assurance Record System                        A records system(s) shall be established by the organization    Similar requirement.
A quality assurance records system shall be established by the      responsible at the earliest practicable time consistent with the organization responsible at the earliest practicable time,          schedule for accomplishing work activities and in compliance consistent with the schedule for accomplishing work activities      with the general requirements of this Supplement. The records and in compliance with the general requirements of this              system(s) shall be defined, implemented, and enforced in standard. The quality assurance records system shall be defined,    accordance with written procedures, instructions, or other implemented and enforced in accordance with written                  documentation.
procedures, instructions and other documentation.
N45.2.9 &sect; 3. TECHNICAL REQUIREMENTS                                                                                                  Introductory statement, no 3.1 General                                                                                                                          requirements specified.
This section provides requirements for the retention and control of those records generated during the various phases of the project.
2.2 Generation of Records N45.2, &sect; 18, &#xb6; 1 Records shall be consistent with applicable        The applicable design specifications, procurement documents,    Similar requirement.
codes, standards, specifications, and contracts and shall be        test procedures, operational procedures, or other documents adequate for use in management of the program.                      shall specify the records to be generated, supplied, or N45.2.9 &sect; 3.2.1 Generation of Quality Assurance Records. It          maintained by or for the Owner.
is not the intent of this standard to specify the preparation of the quality assurance records to be generated. The applicable design specifications, procurement documents, test procedures, operational procedures or other documents shall specify the quality assurance records to be generated by, supplied to, or held for the owner.
N45.2, &sect; 18, &#xb6; 2 The records shall include the results of            Documents that are designated to become records shall be        Similar requirement.
reviews, inspections, tests, audits, monitoring of work              legible, accurate, and completed appropriate to the work        NQA-1 identifies performance, materials analyses, and power plant operating          accomplished.                                                    appropriate related data in logs. The records shall also include, as appropriate, closely                                                                        the sections governing related data such as qualifications of personnel, procedures, and                                                                    specific activities.
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CRITERION 17                                                BASCMEQURNTS...
Q A-.l.1994*
ANSI 452-1971/ANSIN45*1974/NSI        _____,__      _____,__N N18.71976          ........ BASIREQUIREMENTA17  t994 : ... .            ........    :_........__"___'"
equipment and other documentation required by the applicable parts of this standard. Inspection and test records shall, as a minimum, identify the date of inspection or test, the inspector or data recorder; the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted.
N45.2.9 &sect; 3.2.1 All such quality assurance records shall be legible, completely filled out and adequately identifiable to the item involved.
2.3 Record Validation N45.2.9 &sect; 3.2.1 The applicable quality assurance records shall    Documents shall be considered valid records only if stamped,            Similar requirement. NQA-be considered valid only if stamped, initialed, signed, or        initialed, or signed and dated by authorized personnel or              1 further describes otherwise authenticated and dated by authorized personnel.        otherwise authenticated.-This authentication may take the form          authentication that allows These records may be either the original or a reproduced copy. of a statement by the responsible individual or organization.          for electronic processing of Handwritten signatures are not required if the document is              records.
clearly identified as a statement by the reporting individual or organization. These records may be originals or reproduced copies.
2.4 Index N45.2.9 &sect; 3.2.2 Index. The quality assurance records shall be      The records shall be indexed.                                          Similar requirement.
listed in an index.
N45.2, &sect; 18, &#xb6; 4 These records shall be indexed, filed, and        The records shall be indexed                                            Similar requirement.
maintained in facilities that provide suitable environment to minimize deterioration or damage and to prevent loss.
N45.2.9 &sect; 3.2.2 The index shall indicate, as a minimum, record    The indexing system(s) shall include, as a minimum, record              Similar requirement.
retention times, where the records are to be stored and the        retention times and the location of the record within the record        N45.2.9 contains location of the records within the storage area. The index should system.                                                                  information for records on a be established prior to receipt of the records. Index systems used                                                                        construction project and by organizations for the retention of project records should                                                                              compatibility with the include sufficient identifying information to be compatible with                                                                          owner's record system. This the index system used by the owner for final storage of records.                                                                          requirement would be addressed by the purchase and interface requirements of other related standards.
NQA-1 incorporates current technological advances (computer databases, etc.)
2.5 Distribution N45.2.9 &sect; 3.2.3 Distribution. The quality assurance records        The records shall be distributed, handled, and controlled in            Similar requirement.
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CRITERION17      17SIC                .....                                                1                            COMMENTS ANSI 45.27-1971/ANSI N45.2.9r1974/ANSI N18.7-71976                                                      94 shall be distributed and handled in accordance with written            accordance with written procedures.
procedures.
2.6 Identification N45.2.9 &sect; 3.2.4 Identification. Quality assurance records shall        Records and/or indexing system(s) shall provide sufficient            Similar requirement.
provide sufficient information to permit identification between        information to permit identification between the record and the the record and the item, items, or activity to which it applies,      item(s) or activity(ies) to which it applies.
2.7 Classification N45.2.9 &sect; 2.2 Categories                                              Records shall be classified as Lifetime or Nonpermanent by the        Similar requirement.
Two categories of quality assurance records are established -          Owner, or his agent when authorized, in accordance with the lifetime and nonpermanent.                                            criteria given in paras. 2.7.1 and 2.7.2 below.
N45.2.9 &sect; 3.2.5 Classification. Quality assurance records shall be classified as "Lifetime" or "Nonpermanent" in accordance with Section 2 of this standard.
2.7.1 Lifetime Records.
N45.2, &sect; 18, &#xb6; 4 In general, records which correctly identify the      Lifetime records are those that meet one or more of the              Similar requirement.
"as-built" conditions of items in the plant should be maintained      following criteria:
for the life of the plant by or for the owner. These records          (a) those which would be of significant value in demonstrating should include material certification and test data for                capability for safe operation; traceability and quality verification; reports of inspections,        (b) those which would be of significant value in maintaining, examinations, and test results for conformance verification;          reworking, repairing, replacing, or modifying an item; drawings, specifications, procedures, and instructions for use in      (c) those which would be of significant value in determining the control of configuration; and records of nonconformances, and          cause of an accident or malfunction of an item; their resolution.                                                      (d) those which provide required baseline data for in-service N45.2.9 &sect; 2.2.1 Lifetime Quality Assurance Records.                    inspections.
Lifetime records are those which meet one or more of the following criteria:
: 1. Those which would be of significant value in demonstrating capability for safe operation.
: 2. Those which would be of significant value in maintaining, reworking, repairing, replacing, or modifying the item.
.3. Those which would be of significant value in determining the cause of an accident or malfunction of an item.
: 4. Those which provide required baseline data for inservice inspection.
N45.2.9 &sect; 2.2.1 Lifetime quality assurance records are required        Lifetime records are required to be maintained by or for the          Similar requirement.
to be maintained by or for the plant owner for the life of the        plant owner for the life of the particular item while it is installed particular item while it is installed in the plant or stored for      in the plant or stored for future use.
future use.
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CRITERION 17                                              BASIC REQUIREM            T 17                      COMMENTS ANSI 45.2-1971/ANSI N45.2.94I974/ANSI N18.7-1976                                          NQA*.1994" 2.7.2 Nonpermanent Records.
N45.2.9 &sect; 2.2.2 Nonpermanent Quality Assurance Records.          Nonpermanent records are those required to show evidence that    Similar requirement.
Nonpermanent records are those which meet all of the following    an activity was performed in accordance with the applicable      NQA- I eliminated the use criteria:                                                        requirements but need not be retained for the life of the item  of this list by referring to
: 1. Those of no significant value in demonstrating capability for because they do not meet the criteria for lifetime records.      records that do not meet the safe operation.                                                                                                                    criteria for lifetime records.
: 2. Those of no significant value in maintaining, reworking, repairing, replacing, or modifying the item.
: 3. Those of no significant value in determining the cause of an accident or malfunction of an item.
: 4. Those which do not provide baseline data for inservice inspection.
Nonpermanent records are required to show evidence that an activity was performed in accordance with the applicable requirements but need not be retained for the life of the item.
2.8 Retention of Records N18.7 &sect; 5.2.12 Retention periods of sufficient duration to        Records shall be retained in accordance with the above          Similar requirement as far assure the ability to reconstruct significant events and satisfy  classifications. The retention period for nonpermanent records  as establishing retention any statutory requirements which apply shall be specified,        shall be established in writing.                                periods.
N45.2.9 &sect; 3.2.7 Retention of Records. Types of quality assurance records with recommended minimum retention              NRC Reg. Guide 1.28, Rev. 3, Regulatory Position C.2.            NQA-1 doesn't contain a periods are listed in Appendix A of this standard. It should be  Section 2.8, "Retention of Records," of Supplement 17S-1,        mandatory Appendix listing recognized that the nomenclature of these records may vary. For  "Supplementary Requirements for Quality Assurance Records,"      record types and retention records not listed in Appendix A, the type most nearly            states that the retention period for nonpermanent records is    periods. It does contain a describing the record in question should be followed with        required to be established in writing. Programmatic              nonmandatory appendix respect to its retention period.                                  nonpermanent records 4 should be retained for at least 3 years  with this type of For records generated prior to commercial operation, the          and product nonpermanent records 5 should be retained for at    information as Appendix retention period begins on the date of commercial operation. For  least 10 years. For programmatic nonpermanent records, the        17A-1.
records generated on items installed after commercial operation,  retention period should be considered to begin upon completion  NRC Reg. Guide 1.28 does the retention period begins on the date upon which satisfactory  of the activity. For product nonpermanent records generated      establish a regulatory operation of the item, as part of a system, has been              before commercial operation begins, the retention period should  position on the types of demonstrated. For periodic maintenance, inspection and test      be considered to begin upon completion of delivery. In addition, records and the duration or records, such as calibration records, generated after the date of product and programmatic nonpermanent records should be          retention.
commercial operation, the retention time begins on the date of    retained at least until the date of issuance of the full-power  The QAPD commits to their generation. When a record is generated as a result of an    operating license of the unit. Table 1 provides a list of        meeting the record operational phase activity, the classification of those records  nonpermanent and lifetime records and their respective retention requirements of Reg. Guide will be the same as those types of records generated during the  times. Although Table I is intended to be a comprehensive list,  1.28, Revision 3 in Part IV.
initial construction period.                                      it is the responsibility of the owner to assure itself, in The organization responsible shall establish in writing the      accordance with Criterion 17 of Appendix B to 10 CFR 50, that 10/28/2010                                                            Quality Assurance Records                                                    Page 5 of 15
 
CRITERIONJ17T                                                BASIC REQUIREMENT 17...M                                          NT ANSI 45.2-1971/ANSI N45.2/9-19741ANSIN18.7-1976                .      ,,NQA,,                    1994 ...                        _,____l    ______._____
retention times of records not listed in Appendix A.              sufficient records are maintained to furnish evidence of (Note: The content of Appendix A is inserted at the end of this    activities affecting quality. It should be recognized that the comparison table.)                                                nomenclature of these records may vary. For records not listed in Table 1, the type most nearly describing the record in question should be followed with respect to its retention period.
Footnote 4 - Programmatic nonpermanent records are those documents that were used to prescribe activities affecting quality but that are not considered permanent records. Such records include documents prescribing the planning, execution, and auditing of activities affecting quality. Records such as audit checklists, audit results, and actual examinations used to qualify inspection and test personnel are included in this category.
Footnote 5 - Product nonpermanent records document that specific structures, systems, and components of a nuclear power plant have been designed and constructed in accordance with applicable requirements but are such that it is not necessary to retain them as lifetime records. These records include design verification data, receiving records, calibration records, maintenance records, inspection records, radiographs not associated with inservice inspection, and test records that are not otherwise designated as lifetime records.
2.9 Corrected Information in Records N45.2.9 &sect; 3.2.6 Supplemental Information to Quality                Records may be corrected in accordance with procedures which      Similar requirement.
Assurance Records. Quality assurance records may be                provide for appropriate review or approval by the originating corrected or supplemented in accordance with procedures which      organization. The correction shall include the date and the provide for appropriate review or approval by the originating      identification of the person authorized to issue such correction.
organization. The correction or supplement shall include the date and the identification of the person authorized to issue such corrections or supplements.
3 RECEIPT 3.1 Responsibility N45.2, &sect; 18, &#xb6; 4 These records shall be indexed, filed, and        The individual or organization responsible for receiving records  Similar requirement.
maintained in facilities that provide suitable environment to      shall provide protection from damage or loss during the time minimize deterioration or damage and to prevent loss.              that the records are in their possession.
N45.2.9 &sect; 1.3 Responsibility The organization or organizations responsible for establishing 10/28/2010                                                            Quality Assurance Records                                                    Page 6 of 15
 
CRITERION 17                                                  BASIC REQUIREENT 17                                        COMMENTS ANSI 45.2-1971/ANSI N45.2.9;-1974/ANSI N18.7-4976              J                          N.QA-l 1994                                ___________
the applicable requirements for the activities covered by this standard shall be identified and the scope of their responsibilities shall be documented. The work of establishing practices and procedures and providing the resources in terms of personnel, facilities, and services necessary to implement the requirements of this standard may be delegated to other organizations and such delegation shall also be documented. It is the responsibility of each organization performing work covered by this standard to comply with requirements of this standard applicable to its work.
N45.2.9 &sect; 4. RECEIPT OF RECORDS 4.1 General This section defines requirements for receipt of documentation during the design, procurement, manufacturing, installation, startup and operation of a nuclear power plant.
The designated authority or authorities for receiving quality assurance records shall be aware of the value of such records and shall control their safety during the time that the records are in their possession.                                                I                                                                  1*
3.2 Receipt Control N45.2.9 &sect; 4.3 Receipt Control                                        Each organization responsible for the receipt of records shall      Similar requirement.
Each organization responsible for the receipt of quality              designate a person or organization responsible for receiving the assurance records shall designate a person or agency responsible      records.
for receiving the records.
N45.2.9 &sect; 4.3 The designated authority shall be responsible for      The designee shall be responsible for organizing and                Similar requirement.
organizing and implementing a system of receipt control of            implementing a system of receipt control of records for quality assurance records.                                            permanent and temporary storage.
N45.2.9 &sect; 4.3 As a minimum, a receipt control system shall            As a minimum, a receipt control system shall include the            Similar requirement.
include:                                                              following:
N45.2.9 &sect; 4.3 - 1. A records check list designating the required      (a) a method for designating the required records;                  Similar requirement.
quality assurance records.
N45.2.9 &sect; 4.3 - 2. A record of quality assurance records              (b) a method for identifying records received;                      Similar requirement.
received.
N45.2.9 &sect; 4.3 - 3. Procedures for receipt and inspection of          (c) procedures for receipt and inspection of incoming records;      Similar requirement.
incoming records.
N45.2.9 &sect; 4.2 Timeliness                                              (d) a method for submittal of completed records to the storage      NQA- 1 broadens the To assure their availability, a specific submittal plan shall be      facility without unnecessary delay.                                requirement by not limiting established for quality assurance records by agreement between                                                                            it to just a supplier.
the purchaser and supplier.
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CRITERION 17                                                  BASIC REURM N 17                                      COMMENTS ANSI 45.2-1971/ANSI N45.2.9-14/A.SI N18.7-1976                .        . .                  NQA1 1994 3.3 Status N45.2.9 &sect; 4.3 This system shall apply to the receipt of records      Each receipt control system shall be structured to permit a      Similar requirement.
into a temporary working file and the permanent storage file.        current and accurate assessment of the status of records during N45.2.9 &sect; 4.4 Status Each receipt control system shall be            the receiving process.
structured to permit a current and accurate assessment of the status of quality assurance records during the receiving process.
N45.2.9 &sect; 5. STORAGE, PRESERVATION AND                              4 STORAGE, PRESERVATION, AND SAFEKEEPING                          Lead in statement, no SAFEKEEPING                                                                                                                            requirements.
5.1 General This section establishes storage requirements for the maintenance, preservation and protection of quality assurance record files from the time of receipt until their ultimate disposal.
4.1 Storage N45.2, &sect; 18, &#xb6; I Records shall be consistent with applicable        The records shall be stored in predetermined location(s) that    Similar requirement.
codes, standards, specifications, and contracts and shall be        meet the requirements of applicable standards, codes, and adequate for use in management of the program.                      regulatory agencies.
N45.2.9 &sect; 5.2 Location of Facilities The quality assurance record files shall be stored in predetermined locations as necessary to meet the requirements of applicable standards, codes, and regulatory agencies.
N45.2.9 &sect; 5.3 Storage - Prior to storage of records in a quality    Prior to storage of records, a written storage procedure shall be Similar requirement.
assurance record file, a written storage procedure shall be          prepared and responsibility assigned for enforcing the prepared and a custodian shall be designated with the                requirements of that procedure.
responsibility to enforce the procedure.
N45.2.9 &sect; 5.3 This procedure shall include the following as a        This procedure shall include, as a minimum, (a) through (g)      Similar requirement.
minimum:                                                            below:
: 1. A description of the storage area.                                (a) a description of the storage facility;
: 2. The filing system to be used.                                    (b) the filing system to be used;
: 3. A method for verifying that the records received are in          (c) a method for verifying that the records received are in agreement with the transmittal document and that the records        agreement with the transmittal document and that the records are in good condition.                                              are legible;
: 4. A method of verifying that the records agree with the pre-        (d) a method of verifying that the records are those designated established records check list (see paragraph 4.3).                  (see para. 3.2 above);
: 5. The rules governing access to and control of the files.          (e) the rules governing access to and control of the files;
: 6. A method for maintaining control of and accountability for        (f) a method for maintaining control of and accountability for records removed from the storage facility,                          records removed from the storage facility; 10/28/2010                                                              Quality Assurance Records                                                  Page 8 of 15
 
        ..                CRIT'ERION 17                                              BASIC REFQUIREMENT 17                      ~COM'MENTS ANI45.2-1971/ANSI.N45.2.9-I9-74/AN-SI N187-1976                                      NQA-1 1994
: 7. A method for filing supplemental information (see paragraph    (g) a method for filing supplemental information (see para. 2.9 3.2.6) and disposing of superseded records.                      above) and disposing of superseded records.
4.2 Preservation N45.2.9 &sect; 5.4 Preservation                                        Records shall be stored in a manner approved by the              Similar requirement.
Records shall be stored in a manner approved by the              organization or organizations responsible for storage.
organization or organizations responsible for the files. _
N45.2.9 &sect; 5.4 In order to preclude deterioration of the records  In order to preclude deterioration of the records, the          Similar requirement.
the following requirements shall apply:                          requirements of (a) through (c) below shall apply.
N45.2.9 &sect; 5.4 - 1. Condensation. Provisions shall be made in the  (a) Provisions shall be made in the storage arrangement to      Similar requirement.
storage arrangement to prevent damage from condensation.          prevent damage from moisture, temperature, and pressure.
N45.2.9 &sect; 5.4 - 2. Loose Records. Records shall not be stored    (b) Records shall be finrly attached in binders or placed in    Similar requirement.
loosely. They shall be firmly attached in binders or placed in    folders or envelopes for storage in steel file cabinets or on folders or envelopes for storage on shelving in containers. Steel shelving in containers.
file cabinets are preferred.
N45.2.9 &sect; 5.4 - 3. Special Processed Records. Special processed  (c) Provisions shall be made for special processed records (such Similar requirement.
records (such as radiographs, photographs, negatives, and        as radiographs, photographs, negatives, microform, and microfilm) which are light-sensitive, pressure sensitive or      magnetic media) to prevent damage from excessive light, temperature sensitive shall be packaged and stored as            stacking, electromagnetic fields, temperature, and humidity.
recommended by the manufacturer of these materials.
4.3 Safekeeping N45.2.9 &sect; 5.5 Safekeeping                                        Measures shall be established to preclude the entry of          NQA-I reduced the need for A full time security system shall be established to preclude the  unauthorized personnel into the storage area.                    a "full-time security entry of unauthorized personnel into the storage area.                                                                            system" to measures to "preclude the entry of unauthorized personnel."
N45.2.9 &sect; 5.5 - This system shall guard against larceny and      These measures shall guard against larceny and vandalism.        Similar requirement.
vandalism.
Measures shall be taken to provide for replacement, restoration, New requirement that was or substitution of lost or damaged records.                      not addressed in N45.2.9.
4.4 Storage Facilities N45.2.9 &sect; 5.6 Facility                                            Records shall be stored in facilities constructed and maintained Similar requirements.
Permanent and temporary record storage facilities shall be so    in a manner which minimizes the risk of damage or destruction constructed or located as to protect contents from possible      from the following:
destruction by causes such as fire, flooding, tornadoes, insects, (a) natural disasters such as winds, floods, or fires; rodents and from possible deterioration by a combination of      (b) environmental conditions such as high and low temperatures 10/28/2010                                                            Quality Assurance Records                                                  Page 9 of 15
 
CRITERION 17                                                BASIC REQUIREMENT 17                                    COMMENTS ANSI 45.2-1971/ANSI.N45.2.9-19?4/ANSI N1I-1976                                            NQA-I 1994 extreme variations in temperature and humidity conditions.          and humidity; N45.2.9 &sect; 5.6 - For storage of film and other special processed    (c) infestation of insects, mold, or rodents.
records, humidity and temperature controls shall be provided to maintain an environment as recommended by the manufacturer.
N45.2.9 &sect; 5.6 - A satisfactory alternative to the establishing of a There are two satisfactory methods of providing storage            Similar requirement.
record storage facility is maintenance of duplicate records        facilities, single or dual.
stored in a separate remote location.
N45.2.9 &sect; 5.6 - Records discussed in this standard are                                                                                  Not a requirement. This is appropriately classified for fire protection purposes as National                                                                      consistent with the NQA-1 Fire Protection Association Class 1 and as such should be                                                                              standard as shown below.
afforded the equivalent protection of a NFPA Class A, four hour minimum rated facility.
4.4.1 Single Storage Facility.
N45.2.9 &sect; 5.6 - Where a single record storage facility is          Design and construction of a single record storage facility shall  Similar requirement.
maintained, at least the following features should be considered    meet the criteria of (a) through (i) below:
in its construction:
N45.2.9 &sect; 5.6 - 1. Reinforced concrete, concrete block,            (a) reinforced concrete, concrete block, masonry, or equal          Similar requirement.
masonry, or equal construction.                                    construction; N45.2.9 &sect; 5.6 - 2. Concrete floor and roof with sufficient slope,  (b) floor and roof with drainage control; if a floor drain is      Similar requirement.
for drainage; if a floor drain is provided, a check valve (or      provided, a check valve (or equal) shall be included equal) shall be included.
N45.2.9 &sect; 5.6 - 3. Structure, doors, frames and hardware should    (c) doors, structure and frames, and hardware shall be designed    Requirement revised to a 2-be Class A fire-rated with a recommended four hour minimum          to comply with the requirements of a minimum 2 hr fire rating;      hour fire rating rather than 4 rating.                                                                                                                                hours. FSAR Exception /
Clarification, Chapter 3 Page 3A-54 states that the Nuclear Operations Building Records Vault is designed to meet a 4 hour fire rating, which exceeds the NQA-1I requirement.
N45.2.9 &sect; 5.6 - 4. Sealant applied over walls as a moisture or      (d) sealant applied over walls as a moisture or condensation        Similar requirement.
condensation barrier.                                              barrier; N45.2.9 &sect; 5.6 - 5. Surface sealant on floor providing a hard-      (e) surface sealant on floor providing a hard wear surface to      Similar requirement.
wear surface to minimize concrete dusting.                          minimize concrete dusting; N45.2.9 &sect; 5.6 - 6. Foundation sealant and provision for            (f) foundation sealant and provisions for drainage;                Similar requirement.
drainage.                                                                                                                            II 10/28/2010                                                              Quality Assurance Records                                                      Page 10 of 15
 
4 5 *~
1 7    R,1ITERION117                                              BASIC REQUIREMENT            17                        COMMENTS AS145.2-1971ANS A                          5,9-I4/NSIN518.7-2976                                          .          ...        .
N45.2.9 &sect; 5.6 - 7. Forced-air circulation with filter system.      (g) forced air circulation with filter system;                    Similar requirement.
N45.2.9 &sect; 5.6 - 8. Adequate fire protection system.                (h) fire protection system;                                        Similar requirement.
N45.2.9 &sect; 5.6 - 9. No pipes other than those providing fire        (i) only those penetrations used exclusively for fire protection,  NQA-1 clarifies the protection to the storage facility are to be located within the    communication, lighting, or temperature/humidity control are      construction of the facility facility,                                                          allowed; all such penetrations shall be sealed or dampered to      to allow other penetrations.
comply with the minimum 2 hr fire protection rating.
The construction details shall be reviewed for adequacy of        New requirement for review protection of contents by a person who is competent in the        of the facility design.
technical field of fire protection and fire extinguishing.
If the storage facility is located within a building or structure, New allowance when within the environment and construction of that building can provide a    another facility.
portion or all of these criteria.
4.4.2 Alternate Single Storage Facility.
NRC Reg. Guide 1.88, Regulatory Position C. 2. Two methods        The following are acceptable alternatives to the criteria of para. This alternative is similar to for protection of quality assurance records from the hazards of    4.4.1 above for a single storage facility:                        NRC Reg. Guide 1.88, fire are described in Subdivision 5.6 of ANSI N45.2.9-1974.        (a) 2 hr fire rated vault meeting NFPA 232-1986 or NFPA            Regulatory Position C.2.
NFPA No. 232-1975, "Standard for the Protection of                232AM-1986 or both;'
Records,"(2) also contains provisions for records protection      (b) 2 hr fire rated Class B file containers meeting the equipment and records handling techniques that provide            requirements of NFPA 232-1986 or NFPA 232AM-1986 or protection from the hazards of fire. This standard, within its    both;' or scope of coverage, is considered by the NRC staff to provide an    (c) 2 hr fire rated file room meeting the requirements of NFPA acceptable alternative to the fire protection provisions listed in 232-1986 or NFPA 232AM- 1986 or both' with the following Subdivision 5.6 of N45.2.9-1974. When NFPA No. 232-1975 is        additional provisions:
used, quality assurance records should be classified as NFPA      (1) early warning fire detection and automatic fire suppression Class 1 records (NFPA No. 232-1975, Chapter 5, Section 5222).      capability with electronic supervision at a constantly attended central station; (2) records storage in fully enclosed metal cabinets; (3) adequate access and aisle ways; (4) prohibition in the room of work not directly associated with record storage or retrieval; (5) prohibition in the room of smoking, eating, or drinking; (6) 2 hr fire rated dampers or doors in all boundary penetrations.
4.4.3 Temporary Storage.
When temporary storage of records (such as for processing,        NQA- 1 1994 Added review, or use) is required by an organization's procedures, the  flexibility to allow records shall be stored in a 1 hr fire rated container.            temporary storage when The procedures shall specify the maximum allowable time limit      archiving immediately is for temporary storage.                                            not practical.
The container shall bear a UL label (or equivalent) certifying 1 10/28/2010                                                            Quality Assurance Records                                                      Page I11 of 15
 
CRITERION 17                                                    BASIC REQUIREMNT1N 17                                        CM U T
,,ANSI 45.2-197ANSI .N45.2.9.1974/ANSI.N18.7-19,76                ,.                            NA-1,9.94                                _.______,_____________
hr fire protection or be certified by a person competent in the technical field of fire protection.
4.4.4 Dual Storage Facilities.
N45.2.9 &sect; 5.6 - A satisfactory alternative to the establishing of a  If dual storage facilities for each record are provided, the          Similar requirement.
record storage facility is maintenance of duplicate records          storage facilities shall be at locations sufficiently remote from stored in a separate remote location,                                each other to eliminate the chance of exposure to a simultaneous hazard.
Each storage facility is not required to satisfy the requirements    Clarification to the above of para. 4.4.1, para. 4.4.2 or para. 4.4.3 above, but shall meet the requirement that is other requirements of this Part (Part I).                            consistent with the requirement of N45.2.9 &sect; 5.6 for duplicate storage.
5 RETRIEVAL N45.2.9 &sect; 6. RETRIEVAL                                                Storage systems shall provide for retrieval of information in        Similar requirement.
6.1 General                                                          accordance with planned retrieval times based upon the record This section is intended to establish requirements for the            type.
retrieval of documents that are stored within the quality assurance record files.
6.2 Accessibility Storage systems shall provide for the accurate retrieval of information without undue delay.
N45.2.9 &sect; 6.2 - A list shall be generated designating those          A list shall be maintained designating those personnel who shall    Similar requirement.
personnel who shall have access to the files.                        have access to the files.
N45.2.9 &sect; 6.2 - Quality Assurance records maintained by a            Records maintained by a Supplier at his facility or other            Similar requirement.
manufacturer at his facility or other location shall be accessible    location shall be accessible to the Purchaser or his designated to the Buyer or Owner, in the case of lifetime records for the life  alternate, e.g., the Owner.
of the items involved or for the designated retention periods for nonpermanent records.
6 DISPOSITION N45.2.9 &sect; 7. DISPOSITION                                              Records accumulated at various locations, prior to transfer, shall    Similar requirement.
7.1 General                                                          be made accessible to the Owner directly or through the This section is intended to provide requirements for the transfer    procuring organization. The custodian shall inventory the of quality assurance records to the Owner, who has ultimate          submittals, acknowledge receipt, and process these records in responsibility for these documents, and their disposition.            accordance with this Part (Part I).
7.2 Accumulation and Transfer of Records.
Quality assurance records accumulated at various locations prior to final transfer to the Owner shall be made accessible to the Owner directly, or through the procuring organization.
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CRITERION 17 ANSI 45.2-197/:ANSI:N45.2.9-19.74/ANSI N49.7-1976                                                                                                                I Examples of such records are vendor manufacturing records, construction documentation, and startup data. Upon final transfer, the Owner shall inventory the submittals, acknowledge receipt and process these records in accordance with this Standard.
N45.2.9 &sect; 7.3 Disposition of Nonpermanent Records                    Various regulatory agencies have requirements concerning            Similar requirement.
Records classified as nonpermanent should be retained for at        records that are within the scope of this Part (Part I). The most least the minimum period of time as recommended in Appendix          stringent requirements shall be used in determining the final A. After this time, these records may be disposed of by or with      disposition.
concurrence of the Owner.
The Supplier's nonpermanent records shall not be disposed of        NQA-1 provides additional until the applicable conditions listed in (a) through (e) below are detail on disposition of satisfied:                                                          nonpermanent records from (a) items are released for shipment, a Code Data Report is          a supplier. N45.2.9 &sect; 4.2 signed, or a Code Symbol Stamp is affixed;                          only addresses controlling (b) regulatory requirements are satisfied;                          timely turnover of records.
(c) operational status permits; (d) warranty consideration is satisfied; (e) Purchaser's requirements are satisfied.
N45.2.9 &sect; 1.2 Applicability                                          NQA-1 addresses applicability in the Introduction to Part I.        Similar requirement.
The requirements of this standard apply to the work of any individual or organization that participates in collection, storage, or maintenance of quality assurance records associated with nuclear power plants. The extent to which the individual or total requirements of this standard apply will depend upon the nature and scope of the work to be performed and the importance of the item or service involved, and shall be specified in the procurement documents. The requirements are intended to assure that records are available when needed for their intended purpose.
The ASME Boiler and Pressure Vessel Code (Here-after referred to as the Code) as well as other ANSI Standards, has been considered in the development of this standard, and this standard is intended to be compatible with their requirements.
However, this standard does not apply to activities covered by Section III Division 1 and 2 and Section XI of the Code for those activities covered by the Code.
This standard is intended to be used in conjunction with ANSI N45.2.
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CRITERION 17                                                BASICAREQUIREMENT 17                                    COMMENTS ANSI 45.2-191 /A NSI N45.-                """1.4"ANSI N18.7-1976                                NQA-I 194" N45.2.9 &sect; 1.4 Definitions                                            Definition from Introduction to Part I - quality assurance record Similar requirement.
The following definition is provided to assure a uniform            - a completed document that furnishes evidence of the quality    NQA-1 contains definitions understanding of select terms as they are used in this standard. of items and/or activities affecting quality                      in the Introduction to Part I, Quality Assurance Records - Those records which furnish                                                                                &sect; 4.
documented evidence of the quality of items and of activities affecting quality. For the purposes of this standard a document is considered a quality assurance record when the document has been completed.
Other terms and their definitions are contained in ANSI N45.2. 10.
N45.2.9 &sect; 1.5 Referenced Documents                                                                                                    The QAPD addresses the Other documents that are required to be included as a part of                                                                          standards for the program.
this standard are either identified at the point of reference or described in Section 8 of this standard. The issue or edition of the referenced document that is required will be specified either at the point of reference or in Section 8 of this standard.
Reg. Guide 1.88, Regulatory Position C. 1. Subdivision 1.5 of ANSI N45.2.9-1974 states, "Other documents that are required to be included as part of this standard are either identified at the point of reference or described in Section 8 of this standard."
The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations where appropriate.
N45.2.9 &sect; 8. REVISIONS OF REFERENCED ANSI                                                                                              The QAPD addresses the STANDARDS                                                                                                                              standards for the program.
When any of the following standards referred to in this document is superseded by a revision approved by the American National Standards Institute, the revision is not mandatory until it has been incorporated as a part of this standard.
Revisions to the referenced standards, and revisions to this standard issued after the date of a specific contract invoking this standard may be used by mutual consent of the purchaser and the supplier.
N45.2 Quality Assurance Program Requirements for Nuclear Power Plants N45.2. 10 Quality Assurance Terms and Definitions N45.2.9 &sect; 5.7 Audits                                                                                                                  NQA- 1 addresses audits 10/28/2010                                                              Quality Assurance Records                                                    Page 14 of 15
 
AN. I                CRITERION 17l,                                        BASIC RQUIREMENT 17,      COMMENTS ANI45.2-1971/ANSI N45.2.9-1974/ANSI N18.7-19,76                                &#xfd;NQA-I 1994.
An audit system shall be established to assure that the quality                                      under Basic Requirement 18 assurance records storage system is effective. The following                                        and Supplement 18S-1.
shall be performed as a minimum:
1 Periodic surveys to assure that records logged in are available and have been placed in their proper location within the files, and to assure that the control system is adequate.
: 2. Periodic audits to assure that the facilities are in good condition and that the temperature/humidity controls and protective devices are functioning properly.
: 3. Periodic audits of the records to assure that the documents are not deteriorating due to improper storage practices or rough handling.
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CRITERION 18                                  ........      BASIC REQUIRE N.T 18                .    .... .......        CO.M..TS        T...    .
ANSI N45.2-19711N4 .2.12-1977/ANSI N18.7-1976                                            NQA-1 1994          .__.                            ___,  __..."__..      . _
N45.2 &sect; 19 / N18.7 &sect; 4.5, unless noted otherwise.
Reg. Guide 1.144, C. Regulatory Position - The requirements                                                                                  N45.2.12 requirements that are include in ANSI/ASME N45.2.12-1977 for auditing                                                                                      are now addressed in quality assurance programs for nuclear power plants are                                                                                      NQA-1-1994, Supplement acceptable to the NRC staff and provide an adequate basis for                                                                                  18S-1.
complying with the pertinent quality assurance requirements of Appendix B to 10 CFR 50.
N45.2 &sect; 19 &#xb6; 1 A comprehensive system of planned and                Planned and scheduled audits shall be performed to verify                Similar requirements.
documented audits shall be carried out to verify compliance with    compliance with all aspects of the quality assurance program and all aspects of the quality assurance program.                        to determine its effectiveness.
N18.7 A comprehensive system of planned and documented audits shall be carried out to verify compliance with all aspects of the administrative controls and quality assurance program.
N45.2.12 &sect; 3. AUDIT SYSTEM - 3.1 General - This section establishes requirements for a comprehensive audit system which shall be planned, documented, and implemented to verify compliance with the elements of a quality assurance program.
N45.2.12 &sect; 3.4 Audit Planning - The audit system, including both internal and external audits, shall be planned, documented, and conducted to assure coverage of the applicable quality assurance program, and overall coordination and scheduling of audit activities.
Reg. Guide 1.144 Exceptions and Clarifications Applicability (Paragraph 1.2)
SCE&G imposes on its suppliers by way of procurement documents, the QA system audit requirements necessary for the item or service being supplied. Requirements for the audit elements of executing procedures, checklists, auditor qualifications, documented reporting of results, follow-up, and corrective action verification and evaluation are imposed.
N45.2 &sect; 19 &#xb6; 1 The audits shall be performed in accordance with      These audits shall be performed in accordance with written              Similar requirements. Nl18.7 written procedures or check lists by appropriately trained          procedures or checklists by personnel who do not have direct            is more prescriptive personnel not having direct responsibilities in the areas being      responsibility for performing the activities being audited.              regarding use of line audited.                                                                                                                                      personnel to perform audits.
N18.7 &#xb6; 3 Those performing the audits may be members of the audited organization; however, they shall not audit activities for which they have immediate responsibility. While performing the 10/28/2010                                                                        Audits                                                                            Page 1 of 18
 
                        ,CRITERION      18                                              BASIC REQUIRE          NT 18g                          COMMENTS SI N45.2-1971145.2.1.72-
          .A.                            719ANSI N18-7,197.                                      NQA..1994 audit, they shall not report to a management representative who has immediate responsibility for the activity being audited.
N45.2.12 &sect; 3. AUDIT SYSTEM - 3.1 General - ... The audit system shall be described in approved, written policies, plans, procedures, instructions, or such other documents as appropriate.
N45.2.12 &sect; 4. AUDIT IMPLEMENTATION- 4.1 General -
Individual audits shall be implemented as scheduled and planned in Section 3.
N45.2 &sect; 19 &#xb6; 1 Audit results shall be documented and reviewed        Audit results shall be documented and reported to and reviewed      Similar requirements. N 18.7 by management having responsibility in the area audited.            by responsible management.                                          adds requirement for review N18.7 &#xb6; 2 Written reports of such audits shall be reviewed by the                                                                        by independent review independent review body and by appropriate members of                                                                                    body. Independent review is management including those having responsibility in the area                                                                            addressed in Part V, Section audited.                                                                                                                                2.0 of the QAPD.
N45.2 &sect; 19 &#xb6; 1 Responsible management shall take necessary          Follow-up action shall be taken where indicated.                    Similar requirements.
action to correct the deficiencies revealed by the audit.
N18.7 &#xb6; 3 Appropriate and timely followup action, ... , shall be taken.
SUPPLEMENT 18S-1 SUPPLEMENTARY REQUIREMENTS                        ANSI N45.2.12-1977 FOR AUDITS                                                          provides much of the supplemental information for audits found in N45.2, QAPD and NQA-1.
1 GENERAL N45.2.12 This standard provides requirements and guidance for        This Supplement provides amplified requirements for quality establishing and implementing a system of internal and external      assurance audits.
audits of quality assurance programs for nuclear power plants, including the preparation, performance, reporting, and follow-up of audits by both the auditing and audited organizations.
N45.2.12 This standard amplifies the audit requirements of ANSI      It supplements the audit requirements of Basic Requirement 18 of N45.2 and shall be used in conjunction with that standard.          this Part (Part I) and shall be used in conjunction with that Basic Requirement when and to the extent specified by the organization invoking this Part (Part 1).
N45.2.12 &sect; 3.5 Scheduling                                            2 SCHEDULING N45.2 &sect; 19 &#xb6; 5 Audits should be conducted periodically or on a      Internal or external quality assurance audits, or both, shall be    Similar requirement.
random, unscheduled basis, or both.                                  scheduled in a manner to provide coverage and coordination with N45.2.12 &sect; 3.5.1 Auditing shall be initiated as early in the life of ongoing quality assurance program activities.                      NQA-1 uses the term 10/28/2010                                                                      Audits                                                                    Page 2 of 18
 
CRITERION"1                                                BASIC REQUIREMENT 18                                COMMENTS ANSIN45.2-19711N45.2.42-19O77/,NSI          N18.7497                                  -NQA-1 194IM,_________
the activity as practicable, consistent with the schedule for                                                                      schedule in place of the term accomplishing the activity, to assure timely implementation of                                                                    "plan" used by the ANSI quality assurance requirements. In any case, auditing shall be                                                                    standards to address the initiated early enough to assure effective quality assurance during                                                                overall audit plan (not to be the design, procurement and contracting activities,                                                                                confused with the individual N45.2.12 &sect; 3.4 Audit Planning - The audit system, including both                                                                  audit plans).
internal and external audits, shall be planned, documented, and conducted to assure coverage of the applicable quality assurance program, and overall coordination and scheduling of audit activities....
N45.2.12 &sect; 3.5.2 Audits shall be regularly scheduled on the basis  Audits shall be scheduled at a frequency commensurate with the NQA-1 doesn't establish a of the status and importance of the activities to assure the        status and importance of the activity.                        minimum frequency.
adequacy of, and conformance with, the program.                                                                                    Frequency commensurate N18.7 &#xb6; I Audits of selected aspects of operational phase                                                                          with the Reg. Guides and activities shall be performed with a frequency commensurate                                                                        previous alternatives is with their safety significance and in such a manner as to assure                                                                  addressed in Part II, that an audit of all safety-related functions is completed within a                                                                Sections 7 and 18 of the period of two years.                                                                                                              QAPD.
Alternative from current FSAR Chapter 3, Appendix 3A, Conformance with Regulatory Guides                                                                                                The grace period for the ANSI N18.7-1976, paragraph 4.5, states in part, 'Audits of                                                                        frequencies is addressed in selected aspects of operational phase activities shall be performed                                                                Part II, Section 18.2 of the with a frequency commensurate with their safety significance and                                                                  QAPD.
in such a manner as to assure that an audit of all safety-related functions is completed within a period of two years.'                                                                              Alternatives are addressed VCSNS takes exception to paragraph Regulatory Guide 1.33 C.4                                                                      in Part II, Section 18 of the regarding the increased frequencies required for the performance                                                                  QAPD. Additional of the Nonconformance, Surveillance Testing, and Unit Staff                                                                        information is contained in audits. The specified frequencies in C.4 are six months, twelve                                                                    NQA-1 as nonmandatory months, and twelve months respectively. The plant will audit                                                                      guidance of Appendix 18A-these areas at a minimum frequency of" ... within a period of (2)                                                                  1 &sect; 2.3.
two years." using the guidance of the Standard Review Plan 17.2.
This change allows more flexibility in the scheduling of audits and allocation resources. Also, since previous audits have not identified any significant deficiencies in the stated programs, the frequency change will not decrease the effectiveness of the audits. The plant will audit these areas every two years. Audits shall be performed at the intervals designated for each audit area.
Schedules shall be based on the month in which the audit starts.
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CRITERION 18                                                  BASIC REQUIREMENT 18                                  COMMENTS
      ..ANSI N45.2-19711N452.,12-1V77ANSI N8.7-1976                                              ..NQA 1994 Two year audits may be extended not to exceed 25 percent of its interval. The maximum time between audits will not exceed 30 months. When an audit interval extension greater than one month is used, the next audit for that particular audit area will be scheduled from the original anniversary month rather from the month of the extended audit.
VCSNS has programmatic control requirements in place that make the biennial review process redundant. These programmatic controls were affected in an effort to ensure that plant instructions and procedures are reviewed for possible revision when pertinent source material is revised, therefore maintaining the procedures current. In addition to these controls, the Quality Systems group will perform a biennial Quality Assurance Audit of the procedural development program utilizing a representative sampling process, thereby providing verification that the controls are effective in maintaining procedures current. SCE&G believes that this approach better addresses the intent of the biennial review process and is more acceptable from both a technical and a practical perspective than a static two-year review process.
N45.2.12 &sect; 3.4 Audit Planning - ... The audit system shall be        The audit schedule shall be reviewed periodically and revised as Similar requirement.
periodically reviewed, and revised as necessary, to assure that      necessary to assure that coverage is maintained current.
coverage and schedule reflect current activities.                                                                                      N 18.7 assigns the review N18.7, &#xb6; 4 Periodic review of the audit program shall be                                                                              responsibility to the performed by the independent review body or by a management                                                                            independent review body or representative at least semiannually to assure that audits are being                                                                  a management accomplished in accordance with requirements of technical                                                                              representative and specifies specifications and of this Standard.                                                                                                  the review to be at least semiannually. Addressed in Part V, Section 2.0 of the QAPD.
N45.2 &sect; 19 &#xb6; 5 Audits should be conducted periodically or on a        Regularly scheduled audits shall be supplemented by additional  Similar requirement, but random, unscheduled basis, or both. It is desirable to conduct        audits of specific subjects when necessary to provide adequate  NQA-I is not as specific as audits when one or more of the following conditions exist:            coverage,                                                        to when additional audits are (1) When it is necessary to determine the capability of a                                                                              necessary.
subcontractor's quality assurance program prior to awarding of contract or purchase order.                                                                                                            The list of conditions for (2) When, after award of contract, sufficient time has elapsed for                                                                    conducting supplemental the implementation of the quality assurance program, and it is                                                                        audits is contained in 10/28/2010                                                                        Audits                                                                  Page 4 of 18
 
CRITERION 18                                    BASIC REQUIREMENT 18                  COMMENT:S ANSI N45.2-1971/N45.2.12.-.1977/.ANSIN*...7-19.                          NQA..          .1994 _______________________
appropriate to determine that the organization is performing the                                      NQA-1, Appendix 18A-l, functions as defined in the quality assurance program description,                                    &sect; 2.4, as nonmandatory codes, standards, and other contract documents.                                                      guidance.
(3) When significant changes are made in functional areas of the quality assurance program, including significant reorganizations and procedure revisions.
(4) When it is suspected that safety, performance, or reliability of the item is in jeopardy due to deficiencies and nonconformances in the quality assurance program.
(5) When a systematic, independent assessment of program effectiveness or item quality or both is considered necessary.
(6) When it is considered necessary to verify implementation of required corrective actions.
N45.2.12 &sect; 3.5.3 Regularly scheduled audits should be supplemented by audits for one or more of the following conditions:
3.5.3.1 When it is necessary to assess the capability of a contractor's quality assurance program prior to awarding a contract or purchase order.
Alternative from the FSAR Chapter 3, Appendix 3A.
1.144 Auditing of Quality Assurance Programs for Nuclear Power Plants (Revision 0; 1/79)
Virgil C. Summer Nuclear Station complies with the recommendations of Regulatory Guide 1.144 except as stated herein. The triennial period as specified in the Reg. Guide is defined by SCE&G as three (3) years plus or minus three (3) months from the date of the previous audit. The effect of a three month extension will not be cumulative, and the long term average will be maintained as close as possible to a three year interval. The annual period as specified in the Reg. Guide is defined by SCE&G as one (1) year plus or minus one (1) month from the date of the previous audit or annual evaluation. The effect of a one month extension will not be cumulative and the long term average will be maintained as close as possible to a one year interval. Annual evaluations will not be performed during the years that triennial audits are performed, provided the audit is performed within the three years plus or minus three months interval. Audits and evaluations may be performed earlier and/or 10/28/2010                                                          Audits                                                  Page 5 of 18
 
CRITERION 18            NBASIC                                        EQU                1.8                      COM.MENTS$
S FN45.2-1971/N45.2.12-1977/ANSI N18.7_197_                      _    _      _        _    _      _    _      _      _
more often even though the periodicity definition for triennial and annual have minus tolerances applied.
Applicability (Paragraph 1.2)
SCE&G imposes on its suppliers by way of procurement documents, the QA system audit requirements necessary for the item or service being supplied. Requirements for the audit elements of executing procedures, checklists, auditor qualifications, documented reporting of results, follow-up, and corrective action verification and evaluation are imposed.
N45.2.12 &sect; 4. AUDIT IMPLEMENTATION - 4.1 General -                                                                                    Not a requirement.
... The mechanics involved in implementation of an audit are preparation, performance, reporting, and follow-up.
N45.2.12 &sect; 4.2 Preparation - Preparation includes the              3 PREPARATION                                                      Not a requirement.
development of a written audit plan, the selection and orientation of the auditor(s), and notification of the organization to be audited.
3.1 Audit Plan N45.2 &sect; 19 &#xb6; 4 An audit plan should be developed to provide        The auditing organization shall develop and document an audit      Similar requirement.
information about the audit, such as the functional areas to be    plan for each audit. This plan shall identify the audit scope, audited, the names and assignments of those who will perform        requirements, audit personnel, activities to be audited, the audit, the scheduling arrangements, and the method of          organizations to be notified, applicable documents, schedule, and reporting findings and recommendations.                            written procedures or checklists.
N45.2.12 &sect; 4.2.1 Written Plan. An individual audit plan describing the audit to be performed shall be developed and documented by the auditing organization. This plan shall identify the audit scope, the requirements, the activities to be audited, organizations to be notified, the applicable documents, a schedule, and written procedures or checklists.
3.2 Personnel N45.2 &sect; 19 &#xb6; 1 The audits shall be performed in accordance with    The auditing organization shall select and assign auditors who are Similar requirement.
written procedures or check lists by appropriately trained          independent of any direct responsibility for performance of the personnel no having direct responsibilities in the areas being      activities which they will audit.
audited.
N18.7, &#xb6; 3 Those performing the audits may be members of the audited organization; however, they shall not audit activities for which they have immediate responsibility.
N45.2.12 &sect; 2. PERSONNEL - 2.1 General - The responsible 10/28/2010                                                                      Audits                                                                  Page 6 of 18
 
CRITERION 18                                                  BAStt                                                            cs
                                                                        *. .. ...... BAS:..IC= REQIREEN..        18 **..".........  ........          COMMENT.S*..      .=
ANSI N45.2-19711N45.2.12-1977/ANSI N18,.-1976                                              NQA-1 1994          -.            ,        __.._"""_,__    '..        . "...
auditing organization shall select and assign auditors who are independent of any direct responsibility for performance of the activities which they will audit. ...
N45.2.12 &sect; 2. PERSONNEL - 2.1 General - ... In the case of          In the case of internal audits, personnel having direct                  Similar requirement.
internal audits, the persons having direct responsibility for        responsibility for performing the activities being audited shall not performance of the activities being audited shall not be involved    be involved in the selection of the audit team.
in the selection of the audit team.
N18.7, &#xb6; 3 While performing the audits they shall not report to a    Audit personnel shall have sufficient authority and organizational      Similar requirement.
management representative who has immediate responsibility for      freedom to make the audit process meaningful and effective.
the activity being audited.
3.3 Selection of Audit Team An audit team shall be identified prior to the beginning of each        New requirement. This is audit.                                                                  met in current programs.
N45.2.12 &sect; 4.2.2 Team Selection. One or more auditors comprise      This team shall contain one or more auditors and shall have an          Similar requirement.
an audit team. A Lead Auditor shall be appointed team leader.        individual appointed to lead the team who organizes and directs His responsibilities include orientation of the team, coordinating  the audit, coordinates the preparation and issuance of the audit the audit process, establishing the pace of the audit, assuring      report, and evaluates responses.
communications within the team and with the organization being audited, participation in the audit performance, and coordinating the preparation and issuance of reports.
N45.2.12 &sect; 2.3.1 Orientation to provide a working knowledge          The audit team leader shall ensure that the audit team is prepared      Similar requirement to and understanding of ANSI N45.2, this standard, and the auditing    prior to initiation of the audit.                                        prepare the team. However, organization's procedures for implementing audits and reporting                                                                              some of the specifics from results.                                                                                                                                      N45.2.12 &sect; 4.2.3 have been N45.2.12 &sect; 4.2.3 Team Orientation. The team leader shall assure                                                                              changed to nonmandatory that the audit team is prepared prior to initiation of the audit.                                                                            guidance in NQA-1, Pertinent policies, procedures, standards, instructions, codes,                                                                              Appendix 18A-1 &sect; 3.2.
regulatory requirements and prior audit reports, shall be made available for information and review by the auditors. Each auditor shall be provided with the audit plan. The procedures or checklists shall be prepared to assure orderly accomplishment of the audit. During the familiarization phase of the audit, particular attention shall be directed toward an understanding of internal and external organization and contractual interfaces and responsibilities of the organization to be audited.                    4 _P ERF OR MANCE
_______________________________4 PERFORMANCE                                                                                _________
N45.2.12 &sect; 4.3.2 Audit Process - 4.3.2.1 Checklists or              Audits shall be performed in accordance with written procedures          Similar requirement.
procedures shall be used to ensure depth and continuity of audits. or checklists.                                                        I 10/28/2010                                                                        Audits                                                                              Page 7 of 18
 
4 .CRITERION 18                              .                  BASIC REQU.IREMNT 18                                        COMMENTS ANSI N45.2-1971*N45.212-1977/ANSI N18.7-1976                          .                    NQA- *1994        "_.._.._..._...'_....
The audit checklist is intended for use as a guide and should not restrict the audit investigation when findings raise further questions that are not specifically included in checklist.
N45.2.12 &sect; 3.5 Scheduling - 3.5.1 Auditing shall be initiated as        Auditing shall begin as early in the life of the activity as practical Similar requirement.
early in the life of the activity as practicable, consistent with the  and shall be continued at intervals consistent with the schedule schedule for accomplishing the activity, to assure timely              for accomplishing the activity.
implementation of quality assurance requirements. In any case, auditing shall be initiated early enough to assure effective quality assurance during the design, procurement and contracting activities.
N45.2 &sect; 19 &#xb6; 4 Audits should include an evaluation of quality          Elements that have been selected for audit shall be evaluated          Similar requirements assurance practices, procedures, and instructions; the                  against specified requirements. Objective evidence shall be            between N45.2.12 and effectiveness of implementation; and conformance with policy            examined to the depth necessary to determine if these elements        NQA-1. ANSI N 18.7 directives. In performing this evaluation, the audits should            are being implemented effectively,                                    requirements addressed in include evaluation of work areas, activities, processes, and items;                                                                            Part II, Section 18 of the and review of documents and records.                                                                                                          QAPD.
N45.2 &sect; 19 &#xb6; 2 Audits should be performed: (1) to provide an objective evaluation of compliance with established requirements, methods, and procedures; (2) to assess progress in assigned tasks; (3) to determine adequacy of quality assurance program performance; and (4) to verify implementation of recommended corrective action.
N45.2.12 &sect; 4.3.2.2 Objective evidence shall be examined for compliance with quality assurance program requirements.
N18.7, &#xb6; 2 Audits shall include as a minimum verification of compliance and effectiveness of implementation of internal rules, procedures (for example, operating, design, procurement, maintenance, modification, refueling, surveillance, test, security and radiation control procedures and the emergency plan),
regulations and license provisions; programs for training, retraining, qualification and performance of operating staff; corrective actions taken following abnormal occurrences; and observation of performance of operating, refueling, maintenance and modification activities, including associated record keeping.
N45.2.12 &sect; 4.3.2.3 Selected elements of the quality assurance program shall be audited to the depth necessary to determine whether or not they are being implemented effectively.
N45.2 &sect; 19 &#xb6; 1 Audit results shall be documented and reviewed          Audit results shall be documented by auditing personnel and shall      Similar requirements. N 18.7 10/28/2010                                                                          Audits                                                                      Page 8 of 18
 
                          "CRITERION18                                                    BASIC REQUIREMENTk18                                      comM.NTs ANSI N45.2-197VN45.2*.2-1977/            SI.N18.7-0976 .NQA-1            "..                .*... 1994                    ,      . .*.......
by management having responsibility in the area audited.              be reviewed by management having responsibility for the area          adds requirement for review N18.7 &#xb6; 2 Written reports of such audits shall be reviewed by the audited.                                                                  by independent review independent review body and by appropriate members of                                                                                        body. Addressed in Part V, management including those having responsibility in the area                                                                                Section 2.0 of the QAPD.
audited.
N45.2.12 &sect; 4.3.2.6 Conditions requiring immediate corrective          Conditions requiring prompt corrective action shall be reported        Similar requirement.
action shall be reported immediately to management of the            immediately to management of the audited organization.
audited organization.
5 REPORTING N45.2.12 &sect; 4.4 Reporting                                              The audit report shall be signed by the audit team leader and          Similar requirement.
An audit report, which shall be signed by the audit team leader,      issued, and it shall include the following information, as shall provide:                                                        appropriate:                                                          NQA-l does not require the N45.2.12 &sect; 4.4.1 Description of the audit scope.                      (a) description of the audit scope;                                    reporting on N45.2.12 &sect; 4.4.2 Identification of the auditors.                      (b) identification of the auditors;                                    recommendations for N45.2.12 &sect; 4.4.3 Persons contacted during pre-audit, audit, and      (c) identification of persons contacted during audit activities;      correcting program post-audit activities.                                                (d) summary of audit results, including a statement on the            deficiencies or improving N45.2.12 &sect; 4.4.4 A summary of audit results, including an            effectiveness of the quality assurance program elements which          the quality assurance evaluation statement regarding the effectiveness of the quality      were audited;                                                          program.
assurance program elements which were audited.                        (e) description of each reported adverse audit finding in sufficient N45.2.12 &sect; 4.4.5 Description of each quality assurance program        detail to enable corrective action to be taken by the audited deficiency  in sufficient detail to assure that corrective action can organization.
be effectively carried out by the audited organization.
N45.2.12 &sect; 4.4.6 Recommendations for correcting program deficiencies or improving the quality assurance program as appropriate.
6 RESPONSE N45.2 &sect; 19 &#xb6; 1 Responsible management shall take necessary            Management of the audited organization or activity shall              Similar requirements to action to correct the deficiencies revealed by the audit.            investigate adverse audit findings, schedule corrective action,        ensure the objective of N18.7, &#xb6; 3 Appropriate and timely followup action, ... , shall be    including measures to prevent recurrence, and notify the              correcting deficiencies are taken.                                                                appropriate organization in writing of action taken or planned.        achieved. NQA-1 uses the N45.2.12 &sect; 4.3.2.4 When a nonconformance or quality assurance                                                                                terms "adverse audit program deficiency is identified as a result of an audit, further                                                                            findings" as opposed to "a investigation shall be conducted by the audited organization in an                                                                          nonconformance or quality effort to identify the cause and effect and to determine the extent                                                                          assurance program of the corrective action required.                                                                                                          deficiency."
N45.2.12 &sect; 4.5 Follow-up - 4.5.1 By Audited Organization.
Management of the audited organization or activity shall review                                                                              NQA-1 doesn't specify a and investigate any adverse audit findings to determine and                                                                                  time period for the response 10/28/2010                                                                        Audits                                                                      Page 9 of 18
 
CRITERION 18                                              BASIC REQUIREMENT 18                                        COMMENTS ANSI N45.2-4971/N45.2.12-197/AS1 N18.7-1976                                          NQA-1 1994                                ___________
schedule appropriate corrective action including action to prevent                                                                    and this will be specified in recurrence and shall respond as requested by the audit report,                                                                        the implementing program.
giving results of the review and investigation. The response shall                                                                    Appendix 18A- I of NQA- I clearly state the corrective action taken or planned to prevent                                                                        provides nonmandatory recurrence. In the event that corrective action cannot be                                                                              guidance related to the completed within thirty days, the audited organization's response                                                                      follow-up by the audited shall include a scheduled date for the corrective action. The                                                                          organization recommending audited organization shall provide a follow-up report stating the                                                                      that the organization corrective action taken and the date corrective action was                                                                            respond prior to the completed. They shall also take appropriate action to assure that                                                                      requested date. Also, the corrective action is accomplished as scheduled.                                                                                        guidance recommends that the organization provide a follow-up report on corrective action, but this is not required.
NQA- 1 does not specify the performance of further investigation, and even when the "needed corrective action" is "virtually 'obvious"' that would still include some level of investigation into the condition in order to determine corrective action.
N45.2.12 &sect; 4.5.2.2 Evaluate the adequacy of the response.          The adequacy of audit responses shall be evaluated by or for the    Similar requirement.
auditing organization.
7 FOLLOWUP ACTION N45.2 &sect; 19 &#xb6; 2 Deficient areas should be re-audited until          Follow-up action shall be taken to verify that corrective action is Similar requirement. NQA-1 corrections have been accomplished,                                accomplished as scheduled.                                          does not contain as much N18.7, &#xb6; 3 Appropriate and timely followup action, including re-                                                                      detail on how to accomplish audit of deficient areas, shall be taken.                                                                                              the follow-up in the N45.2.12 &sect; 4.5.2 By Auditing Organization. When necessary,                                                                            requirements section.
follow-up actions shall be performed by the audit team leader or management of the auditing organization to:                                                                                            Details of performing 4.5.2.1 Obtain the written response when required by the audit                                                                        follow-up is considered report.                                                                                                                                nonmandatory guidance in Appendix 18A-1 &sect; 7.
10/28/2010                                                                    Audits                                                                  Page 10 of 18
 
CRITERION818                                                  BASIC REQUIREMENT 18                                CO.MM.NTS ANSI N45.2-197!/N45.2.12-*19-77/ANSI N18.7-1976.                                          NQA-1 1994, 4.5.2.3 Assure that corrective action is identified and scheduled for each adverse, finding.
4.5.2.4 Confirm that corrective action is accomplished as scheduled.
Reg. Guide 1.144 Exceptions and Clarifications Follow-up (Paragraph 4.5.2)
SCE&G will utilize other qualified team leaders at the direction of management to follow-up audits. This is an option to the existing requirement that the team leader performing the audit or management of the auditing organization perform the follow-up.
8 RECORDS N45.2.12 &sect; 5.2 Audit Records - Records shall be generated and        Audit records shall include audit plans, audit reports, written Similar requirement.
retained for all audits. Records shall include the audit system      replies, and the record of completion of corrective action.
plan, individual audit plans, audit reports, written replies, and the record of completion of corrective actions.
Reg. Guide 1.144, C.7 - The requirements of ANSI/ASME N45.2.12-1977 contained in the second sentence of Section 5.2, "Audit Records," read "Records shall include ... [see above text]." Additionally, these records should include documents associated with the conduct of audits that support audit findings (for example, audit checklists or procedures).
N18.7 &#xb6; 5 Further guidance on requirements for auditing of                                                                            Not a requirement.
quality assurance programs for nuclear power plants exists in ANSI N45.2.12, "Requirements for Auditing Quality Assurance Programs for Nuclear Power Plants."
N45.2.12 &sect; 1.2 Applicability - The requirements of this standard                                                                      Applicability is addressed in apply to both internal and external audits performed by or for the                                                                    the Introduction to NQA- 1, plant owner, contractors, and other organizations participating in                                                                    Part I. The requirements are activities affecting the quality of structures, systems, and                                                                          similar.
components of nuclear power plants in accordance with requirements of ANSI N45.2. This standard is not applicable to                                                                        The limitation regarding surveillance or inspections for the sole purpose of process control                                                                  surveillance or inspections or product acceptance.                                                                                                                of N45.2.12, &sect; 1.2, The ASME Boiler and Pressure Vessel Code (here after referred                                                                        Sentence 2 is addressed in to as the Code) as well as other American National Standards,                                                                        the NQA-I definition for have been considered in the development of this standard, and                                                                        audit. The applicability of this standard is intended to be compatible with their                                                                                the QAPD includes using its requirements. However, a standard does not apply to activities                                                                        provisions to supplement 10/28/2010                                                                      Audits                                                              Page 11 of 18
 
              .                      .....                ..              SIC  Q U IREM E8 .,              O:,      SBA ANSI N4 7.4071/N45-.2.12-1977iANS1N8717                                  NQA-1 1994 covered by Section Im1, Div. I and 2, and Section XI of the Code                                the ASME Code QA for those activities covered by the Code.                                                        requirements..
Reg. Guide 1.144, C.2. - The Foreword and Section 1.2, "Applicability," of ANSI/ASME N45.2.12-1977 state: "The ASME Boiler ... [See above text]" While Section III, Divisions 1 and 2, and Section XI of the ASME Boiler and Pressure Vessel Code address general requirements for quality assurance program audits, these sections do not explicitly address all the activities described in ANSI/ASME N45.2.12-1977. ANSI/ASME N45.2.12-1977, subject to the exceptions of the regulatory position, should be used in conjunction with Section III, Divisions 1 and 2, and Section XI of the ASME Boiler and Pressure Vessel Code for auditing quality assurance programs where the ASME Code does not address the activities covered by N45.2.12-1977.
N45.2.12 &sect; 1.3 Responsibility - The organization or organizations                                Responsibility is addressed responsible for implementation of the applicable requirements of                                by NQA-I in the this standard shall be identified and the scope of their                                        Introduction to Part I. The responsibilities and authorities shall be documented. The work of                                requirements are similar to establishment practices and procedures and providing the                                        the first paragraph of resources in terms of personnel, equipment and services                                          N45.2.12. The second necessary to meet the requirements of this standard may be                                      paragraph of N45.2.12 is delegated to other organizations and such delegation shall also be                              essentially addressed in documented. It is the responsibility of each organization                                        NQA-1, Basic Requirement performing any activity covered by this standard to comply with                                  1 and Supplement 1S-1 the requirements of this standard applicable to its work.                                        dealing with the The organizational structure, functional responsibilities, levels of                            Organization.
authority, and lines of internal and external communication for management direction of audits of the quality assurance program shall be documented. Where multiple organizational arrangements exists, the interface responsibilities of each organization shall be clearly defined and documented. In no way shall the performance of audits by an organization diminish the responsibility of the audited organization or contractor for audit of his designated portion of the quality assurance program or the quality of his product or services.
Reg. Guide 1.144, C.5 - Regulatory Position C.3 provides                                        QAPD Section 7 addresses guidance on scheduling internal and external audits. Section 1.3,                                the use of audits conducted "Responsibility," of ANSI/ASME N45.2.12-1977 states: "The                                        by outside organizations and 10/28/2010                                                          Audits                                        Page 12 of 18
 
CRITERION 18'.                                              BASIC REQUIREMEENT 18                                    COMMENTS ANSI N45.-19711N4521-97AS                  N1.4-976                                      NA119                                  ___________
work of... [see above text]." Where more than one purchaser                                                                          where more than one buys from a single supplier, a purchaser may perform an audit of                                                                      purchaser buys from a single the supplier on behalf of more than one purchaser in order to                                                                        supplier (NUPIC).
reduce the number of external audits of the supplier. The results of this audit should be distributed to all purchasers for whom the audit was conducted.
N45.2.12 &sect; 1.4 Definitions - The following definitions are          The following definitions are taken from NQA-1, Part I,          Definitions are addressed by provided to assure a uniform understanding of select terms as      Introduction.                                                    NQA-1 in the Introduction to they are used in this standard:                                                                                                      Part I.
N45.2.12 Audit - A documented activity performed in accordance      Audit - a planned and documented activity performed to            Similar definition.
with written procedures or checklists to verify, by examination    determine by investigation, examination, or evaluation of and evaluation of objective evidence, that applicable elements of  objective evidence the adequacy of and compliance with the quality assurance program have been developed, documented      established procedures, instructions, drawings, and other and effectively implemented in accordance with specified            applicable documents, and the effectiveness of implementation.
requirements. An audit should not be confused with surveillance    An audit should not be confused with surveillance or inspection or inspection for the sole purpose of process control or product    activities performed for the sole purpose of process control or acceptance.                                                        product acceptance.
N45.2.12 Internal Audits - Audits of those portions of an          Audit, internal - an audit of those portions of an organization's Similar definition.
organization's quality assurance program retained under its direct  quality assurance program retained under its direct control and control and within its organizational structure.                    within its organizational structure N45.2.12 External Audits - Audits of those portions of an          Audit, external - an audit of those portions of another          Similar definition.
organization's quality assurance program not retained under its    organization's quality assurance program not under the direct direct control and not within its organizational structure.        control or within the organizational structure of the auditing organization N45.2.12 Auditor - Any individual who performs any portion of                                                                        Not defined in NQA-1, but an audit, including lead auditors, technical specialists and others                                                                  described in Supplement 2S-such as management representatives and auditors in training.                                                                          3 in a way that is similar to the definition of N45.2.12.
N45.2.12 Lead Auditor - An individual qualified to organize and                                                                      Not defined in NQA- 1, but direct an audit, report audit findings and evaluate corrective                                                                        described in NQA-1, actions.                                                                                                                              Supplement 18S-1 (subsection 3.3) and Supplement 2S-3 in a way that is similar to the definition of N45.2.12.
N45.2.12 Program Deficiencies - Failure to develop, document or                                                                      Not defined in NQA-1.
implement effectively any applicable element of the quality                                                                          NQA-1 uses the term assurance program required by ANSI N45.2.                                                                                            adverse findings, but does 10/28/2010                                                                      Audits                                                                Page 13 of 18
 
CU WN18BASIC                      REQUIREMENT 18        COMMENT.S:
ANSI N45.2-107,11N45.2.1.2-19771A`NS1 N18.771976                      NA119 not define that.
N45.2.12 Other terms and their definitions are contained in ANSI                            Definitions are addressed by N45.2.10.                                                                                  NQA-1 in the Introduction to Part I. This is comparable to N45.2. 10.
N45.2.12 &sect; 1.5 Referenced Documents - Documents that are                                    There are no referenced required to be included as a part of this standard are identified at                        documents for this section the point of reference or described in Section 6 of this standard.                          of NQA-1. The QAPD The issue or edition of the referenced document that is required                            addresses VCSNS's will be specified either at the point of reference or in Section 6 of                      position on referenced this standard unless otherwise specified in the contract document.                          documents and the Reg.
Reg. Guide 1.144, C. 1. - Section 1.5, "Referenced Documents,"                              Guides and Standards that of ANSFASME N45.2.12-1977 states that documents that are                                    apply to the QA program.
required to be included as a part of the standard are identified at the point of reference or described in Section 6 of the standard.
The specific applicability of these listed documents has been addressed in the latest revision of the following regulatory guides:
ANSI Standard              Regulatory Guide N45.2                      1.28 N45.2.9                    1.88 N45.2.10                    1.74 N45.2.12 &sect; 2.2 Personnel Qualification - The responsible auditing                          Personnel Qualification is organization shall establish the audit personnel qualifications and                        addressed in NQA-1 Basic the requirements for the use of technical specialists to assist in                          Requirement 2 and the auditing of the quality assurance programs. Personnel selected                          Supplement 2S-3.
for quality assurance auditing assignments shall have experience or training commensurate with the scope, complexity or special nature of the activities to be audited.
N45.2.12 &sect; 2.3 Training - Auditors shall have, or be given,                                Training requirements are appropriate training or orientation to develop their competence                            addressed in NQA- 1 Basic for performing required audits. Competence of personnel for                                Requirement 2 and performance of the various auditing functions shall be developed                            Supplement 2S-3.
by one or more of the following methods:
N45.2.12 &sect; 2.3.2 Training programs to provide general and                                  Training requirements are specialized training in audit performance. General training shall                          addressed in NQA-1 Basic include fundamentals, objectives, characteristics, organization,                            Requirement 2 and performance and results of quality assurance program auditing.                              Supplement 2S-3.
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                                '.CRITERION 18                              BASI  EURMNT1CO                  ANS
        *siN45.&#xfd;29719/N45..12-ANSIiii)                          77NSI Ni8.7976.IC.REQUIREMENT                    18        COMMENTS
____________________________6                                                  NQA&#xfd;-! 1994 Specialized training shall include methods of examining, questioning, evaluating, and documenting specific audit items and methods of closing out audit findings.
N45.2.12 &sect; 2.3.3 On-the-job training, guidance, and counseling                                  Training requirements are performed under the direct supervision of a Lead Auditor. Such                                  addressed in NQA-l Basic training shall include planning, performing, reporting, and                                      Requirement 2 and follow-up action involved in conducting audits.                                                  Supplement 2S-3.
N45.2.12 &sect; 2.4 Maintenance of Proficiency                                                        Requirements to maintain Lead Auditors shall maintain their proficiency through one or                                    proficiency are addressed in more of the following methods:                                                                  NQA-l Basic Requirement 2 2.4.1 Regular, active participation in the audit process.                                        and Supplement 2S-3.
2.4.2 Review and study of codes, standards, procedures, instructions, and other documents related to quality assurance programs and program auditing.
2.4.3 Participation in training programs as described in Section 2.3.
N45.2.12 &sect; 3.2 Objectives                                                                        Addressed as nonmandatory The objectives of the audit system are:                                                          guidance in NQA-1, 3.2.1 To determine that a quality assurance program has been                                    Appendix 18A-l, &sect; 2.1 developed and documented in accordance with specified requirements; 3.2.2 To verify by examination and evaluation of objective evidence that the documented quality assurance program has been implemented; 3.2.3 To assess the effectiveness of the quality assurance program; 3.2.4 To identify nonconformances and quality assurance program deficiencies; and 3.2.5 To verify correction of identified quality assurance program deficiencies.
N45.2.12 &sect; 3.3 Essential Elements of the Audit System                                            Addressed as nonmandatory An effective audit system shall be established and maintained and                                guidance in NQA-1, shall include the following essential elements:                                                  Appendix 18A-l, &sect; 2.2.
3.3.1 A management policy statement or procedure which establishes organizational independence and authority of the auditors and commits the organization to an audit system meeting the requirements of a standard.
3.3.2 Manpower, funding, and facilities to implement the audit 10/28/2010                                                              Audits                                  Page 15 of 18
 
        ...........      CRITERION 18 :                                  BASIC REQUIRE.MENT 18            CO.MMNTS
    ==.ANSI N45.2-1971/N45.2.12-1977/AN*        1 N18.7-1976                  NQA-! 1M994    _____=_'______'_,,=...
system.
3.3.3 Identification of those responsible for the audit system, including a delineation of their authorities, responsibilities, and organizational independence.
3.3.4 Provisions for reasonable and timely access of audit personnel to facilities, documents, and personnel necessary in the planning and performance of the audits.
3.3.5 Provisions for reporting on the effectiveness of a quality assurance program to the responsible management of both the audited and auditing organizations.
N45.2.12 &sect; 4.2.2 Team Selection.... In selecting personnel for                                  NQA-1 addresses auditing assignments, consideration shall be given to special                                  considerations for personnel abilities, specialized technical training, prior pertinent                                      selection as nonmandatory experience, personal characteristics, and education.                                            guidance in Appendix 18A-I
                                                                                                &sect; 3.1.
N45.2.12 &sect; 4.2.4 Audit Notification. Involved organizations shall                              NQA-1 addresses the audit be notified of a scheduled audit a reasonable time before the audit                            notification as is to be performed. This notification should be in writing and                                  nonmandatory guidance in include such information as the scope and schedule of the audit                                Appendix 18A-1 &sect; 3.3.
and the name of the audit team leader. With prior agreement of the parties involved, unannounced audits may be performed.
N45.2.12 &sect; 4.3 Performance - 4.3.1 Pre-Audit Conference. A                                      NQA-1 addresses the brief preaudit conference shall be conducted with cognizant                                    preaudit conference as organization management. The purpose of the conference shall be                                nonmandatory guidance in to confirm the audit scope, present the audit plan, introduce                                  Appendix 18A-1 &sect; 4.1..
auditors, meet counterparts, discuss audit sequence and plans for the post-audit conference, and establish channels of communication.
N45.2.12 &sect; 4.3.2.5 Nonconformances or quality assurance                                        Not a requirement and not program deficiencies should be acknowledged by a member of                                      addressed in NQA-1.
the audited organization.
N45.2.12 &sect; 4.3.2.7 Specific attention should be given to                                        Requirement not addressed corrective action on program deficiencies identified during                                    in NQA-1.
previous audits.
Reg. Guide 1.144, C.4.b. - The guideline [indicated by the verb                                Corrective action is an "should"] concerning corrective action on program deficiencies                                  element evaluated in each identified during previous audits ... [have sufficient safety                                  audit as stated in Part H, importance to be treated the same as the requirements (indicated                                Section 18 of the QAPD.
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* CRITERION 18 -BASIC                                ,REQUIRLEMENT 18        CONMMENTS ANSI52-971N.. .2.12-1977ANSI N18.7-1976                              NQA-119 by the verb "shall") of the standard.] In this regard, corrective action on program deficiencies identified during previous audits is construed to mean "corrective action on program deficiencies in the area that is being audited.
N45.2.12 &sect; 4.3.3 Post-Audit Conference. At the conclusion of the                              NQA-l addresses the post audit process, a post-audit conference shall be held with                                      audit conferences as management of the audited organization to present audit findings                              nonmandatory guidance in and clarify misunderstandings.                                                                Appendix 18A-1 &sect; 4.3 Internal procedures provide guidance in directing the post-audit conference.
N45.2.12 &sect; Distribution of the report shall include responsible                                NQA-I requires reporting management of both the audited and auditing organizations. The                                audit results to management audit report shall be issued within thirty days after the post-audit                          in Basic Requirement 18.
conference.                                                                                    The details of report Reg. Guide 1.144 Exceptions & Clarifications                                                  distribution are addressed as Reporting (Paragraph 4.4)                                                                      nonmandatory guidance in SCE&G meets the requirement to issue audit reports within thirty                              Appendix 18A-1 &sect; 5.
days after the post-audit conference for all internal audits and for external audits when there are identified deficiencies (findings) requiring response and corrective action from the audited organization. In the case of external audits where no deficiencies requiring response are identified, normal practice is to issue audit reports within sixty days after the post-audit conference.
Relaxation of strict adherence to the thirty day requirement in the case of external audits with no identified findings is seen as an aid in the prioritization of quality resources to those areas where problems or issues exist.
N45.2.12 &sect; Follow-up action can be accomplished through                                        Not a requirement.
written communication, re-audit, or other appropriate means.
N45.2.12 &sect; 5. RECORDS - 5.1 General - Records shall be                                        NQA-I addresses general retained by the auditing organizations responsible for activities                              records requirements, associated with implementation of this standard. These records                                including those for audits, in shall be collected, stored, and maintained in accordance with                                  Basic Requirement 17 and ANSI N45.2.9.                                                                                  Supplement 17S-1 along with other records.
N45.2.12 &sect; 5.3 Personnel Records - Records shall include            7                        NQA-I addresses 10/28/2010                                                            Audits                                  Page 17 of 18
 
CRITERION                            ..        A SC REQUI REMENT!8 'S        C.MNIEP.
A[NSI N45.-1971IN45.2.12-1977/ANSI NI8.7-1976                          NQAO* 1"4..
9 documentary evidence of the qualifications and training of                                    qualification and training auditors and shall be retained for the same period of time as                                  records for audit personnel required for the audit report with which the auditors are                                      in Basic Requirement 2 and associated.                                                                                    Supplement 2S-3.
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Cleaning of Fluid Systems and Associated Componenits                  Quait Assuurance Reqgirements for Cleaning of Fluid                Comments During Construction Phase of Nuclear Power Plants                  Systems and Associated Components for Nuclear Power ANSI N.45.2.1 .1973                                                        Plants.......................
_________________________________________                        NQA-1-1994, Subpart.2.1___________
: 1. INTRODUCTION                                                        1 GENERAL 1.1  Scope This standard covers on-site cleaning of materials and                Subpart 2.1 provides amplified requirements for the            N45.2.1 was applicable for components, cleanness control, and pre-operational cleaning          management of cleaning and cleanness control of fluid systems  construction. NQA-1 is and layup of important nuclear power plant fluid systems              and associated components for nuclear power plants during      applicable for during construction. These systems include those whose                manufacturing, construction, repairs, and modifications. It    "manufacturing, satisfactory performance is required for safe and reliable            supplements the requirements of Part I and shall be used in    construction, repairs, and operation of the plant. The requirements may also be extended        conjunction with applicable Basic and Supplementary Sections  modifications."
to other parts of nuclear power plants when specified in              of Part I when and to the extent specified by the organization contract documents. The standard covers requirements                  invoking Subpart 2.1.
necessary to ensure an adequately clean system upon completion of construction activities, and covers the period from which the materials and equipment are removed from storage or receiving for installation at the construction site until the systems are ready for preoperational testing. The intent of this standard is to require close attention to cleanness control during erection of a nuclear power plant so that only water flushing or rinsing of an installed system is required to render it ready for service. When more than a water flush or rinse is needed to produce the specified cleanness, additional cleaning, in accordance with this standard may be necessary. This standard is intended to be used in conjunction with ANSI N45.2 Quality Assurance Requirements for Nuclear Power Plants.
1.2 Applicability The requirements of this standard apply to the work of any            See NQA-1, Introduction, Section 2 for Applicability          NQA- 1 is similar but refers individual or organization that participates in the construction                                                                    to Operating Units also.
phase cleaning of items to be incorporated into nuclear power plants as discussed in Subsection 1.1. The extent to which the individual requirements of this standard will apply will depend upon the nature and scope of work to be performed and the importance of the item or service involved. The requirements are intended to ensure that only proper cleaning materials, equipment, processes and procedures are utilized during the construction of power plants and that the quality of items is 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                Page I of 35
 
Cleaning of FluidiSystems and Associated Components                      Qualitj&#xfd; surance'Requirements for Cleaning of Fluid                  Comments During Construction Phase of Nuclear Power Plants .                  Systems and Associated Components for Nuclear Power AN SI N45.2.1 1973                                                                        fP r Nucle
_________________________________________                            QA 1194, Subpart 2.1                    ___________
maintained as a result of the use of proper cleaning practices and techniques during construction.
Reg. Guide 1.37-3/73 Position C.2 states: Although subdivision 1.2 of ANSI N45.2.1-1973 states that the requirements promulgated apply during the construction phase of a nuclear power plant, many of the requirements and recommendations contained in the standard are also appropriate to cleaning of fluid systems and associated components during the operation phase of a nuclear power plant, and they should be used when applicable. In this regard, however, it should be particularly noted that decontamination and cleanup of radioactively contaminated systems and components are not addressed by ANSI N45.2.1-1973. These operations will be considered separately in future regulatory guides.                              4 1.3 Resnonsibilitv                                                  +                                                            I The organization or organizations responsible for the activities        See NQA-1, Subpart 2, Introduction, Section 3 for            ANSI N45.2.1 focuses on covered by this standard shall be identified and the scope of          Responsibility and NQA-1, Subpart 2, Section 4 for General  construction phase.
their responsibility shall be documented. Such responsibility          Planning and Procedures.                                    Otherwise, similar should be assigned at the earliest practical point in time so as to                                                                  requirements if considering facilitate incorporation of cleaning requirements in design                                                                          other parts of NQA- 1 (e.g.
drawings and purchase specifications. The establishment of                                                                            Basic Requirements 1, 5, practices and procedures and provision of resources, in terms of                                                                      etc.).
personnel, equipment, and services necessary to implement the requirements of this standard, may be delegated to other organizations and such delegations shall also be documented.
Each organization participating in site construction activities shall comply with procedures and instructions issued for the project and with those requirements of this standard applicable to his work. The organization responsible for performing the cleaning shall identify and document detailed cleaning procedures unless they are specified in the procurement documents. Requirements for review and/or approval of such procedtires shall be specified in the procurement documents.
1*
1.4 Definitions                                                        1.1 Definitions Page 2 of 35 Cleaning of Fluid Systems and Associated Components 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                  Page 2 of 35
 
Cleaning of Fluid Systems and Associated Components                  Quality Assurance Requirements foCleaning of Fluid                    Cmni.m nts During Construction Phase of Nuclea Power.Plants                  Sys.m.ns and Associated Components: for Nuclear Power
                ..      ANSI N45.2.1 -1973                                                          Plants                        ..    '
NQA-1-1994, Subpart 2.1 The following definitions are provided to assure a uniform          The following definitions are provided to assure a uniform        No change except reference understanding of select terms as they are used in this standard. understanding of unique terms as they are used in Subpart 2.1. to standard.
Acid Cleaning - The removal of metal oxides by either                acid cleaning - the removal of metal oxides by either            No change dissolution of the oxide or undercutting the oxide by dissolution    dissolution of the oxide or undercutting the oxide by dissolution of the base metal with an acid solution.                            of the base metal with an acid solution Alkaline Cleaning - The removal of organic contaminants by          alkaline cleaning - the removal of organic contaminants by        No change converting them to an emulsion with an alkaline solution such        converting them to an emulsion with an alkaline solution such as trisodium phosphate.                                              as trisodium phosphate Chelate Cleaning - The removal of slightly soluble compounds        chelate cleaning - the removal of slightly soluble compounds      No change such as iron oxide, by complexing the metallic ions with            such as iron oxide, by complexing the metallic ions with organic chelating compounds such as ethylene diamine tetra-          organic chelating compounds such as ethylene diamine tetra-acetic acid (EDTA).                                                  acetic acid (EDTA)
Chemical Conditioning - The addition of chemicals in low            chemical conditioning - the addition of chemicals in low          No change concentration to flush, rinse, or layup water to prevent            concentration to flush, rinse, or layup water to inhibit precipitation of dissolved solids, inhibit corrosion, etc.          precipitation of dissolved solids, corrosion, and other detrimental effects Cleaning - The removal of any contaminants that might have a        cleaning - the removal of any contaminants that might have a      Similar requirement deleterious effect on plant safety and reliable operation.          deleterious effect on operation of the plant Contractor - Any individual or organization entering into a          NQA-I, INTRO, Terms and Definitions:                              NQA-1, Terms and contract to furnish items or services to a purchaser. The term      Supplier - any individual or organization who furnishes items    Definitions, describes contractor includes the terms Vendor, Supplier, and                  or services in accordance with a procurement document. An all-    "Supplier" similar to Subcontractor or sub-tier levels of these where appropriate.        inclusive term used in place of any of the following: vendor,    N45.2.1 "Contractor" (each seller, contractor, subcontractor, fabricator, consultant, and    references other term) their subtier levels.
Contamination - Any undesirable foreign material on the              Contamination - any unwanted or undesirable foreign material      Similar requirement surface of an item, in the atmosphere, or in process liquids or      on the surface of an item, in the atmosphere, or in process gases.                                                              liquids or gases Corrosion Resistant Alloy - Materials, such as stainless steel,      corrosion-resistant alloys - materials that inherently resist    Similar requirement nickel-base, or cobalt-base alloys, that inherently resist          oxidation or chemical attack in water, air, and the operating oxidation or chemical attack in water, air, and the operating        environment, such as stainless steel, nickel-base alloys, or environment,                                                        cobalt-base alloys Crevice - Any narrow opening in a surface or any open                crevice - a narrow opening in a surface or an open juncture      Similar requirement juncture between mating surfaces in which solutions can be            between mating surfaces in which solutions or contaminants trapped and not readily removed during rinsing or flushing          can be trapped and not readily removed during rinsing or 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 3 of 35
 
        .Cleamnng of Fluid Systems and Associated Components                  Quality Assurance Requirements for CleaningofFluid                        Comm..ents During Construction Phase of Nuclear Power Plants                    Systems and Associated Comronents for Nuclear Power ANSI N45..      197                                                            Plant NQA-1-1994,.Subpart 2.1 operations; for example, the annular spaces in threaded                flushing operations (for example, the annular spaces in threaded connections and socket assemblies, tube-to-tube sheet joints,          connections and socket assemblies, tube-to-tubesheet joints, and and tube-to-tube support joints.                                      ___________________support____joints)___
Dead Leg - Any area that does not have flow during the                dead leg - an area that does not have flow during the cleaning    Similar requirement cleaning operation or which cannot be drained without special          operation or that cannot be drained without special provisions provisions.fli-angaoriqd Documentation - Any written or pictorial information                  NQA-1 INTRO Definition:                                          N45.2. 1 definition for describing, defining, specifying, reporting, or certifying            document - any written or pictorial information d scribing,      "Documentation" is similar activities, requirements, procedures or results.                      defining, specifying, reporting, or certifying activities,      to definition in NQA-lI requirements, procedures, or results. A document i s not          INTRO definition for considered to be a Quality Assurance Record until it satisfies    "document."
the definition of a Quality Assurance Record as defined in this Supplement.
Flushing - Flowing water through a component or system at            flushing - flowing fluid through a component or system at        No change adequate velocity to suspend and carry away anticipated                adequate velocity to suspend and carry away anticipated contaminants, 10/28/2010,            ..  .3,*.:    :,..,.,:,    .. ,.*  :.,,*. contaminants Cleaning* of..
Fluid Systems
                                                                            *.*****,*  .:  and..*:.*.
: Associated Components            .. ,                      Page*:"*
4      "f3 Fluid - any gas or liquid                                        New Definition Inhibitor - A chemical additive which retards some specific            inhibitor - a chemical additive that retards some specific        Similar requirement chemical reaction.                                                    chemical reaction Inaccessible Area - An area or opening in an item which is not        inaccessible area - an area or opening in an item that is not    Similar requirement directly accessible for cleaning or inspection,                        directly accessible for cleaning or inspection                  _____________
Item - Any level of unit assembly, including structure, system,      NQA-1 INTRO Definition:                                          Similar requirement to subsystem, subassembly, component, part or material.                  item - an all-inclusive term used in place of any of the          definition in NQA- 1 following: appurtenance, assembly, component, equipment,          INTRO definition material, module, part, structure, subassembly, subsystem, system, or unit.
Lay up - The protection of an item after it has been cleaned, to      lay-up - the protection of an item after it has been cleaned to    Same requirement prevent corrosion of interior surfaces while the item is out of      prevent corrosion of interior surfaces while the item is out of service or awaiting subsequent operations.                            service or awaiting subsequent operations Mechanical Cleaning - A method in which contaminant                  mechanical cleaning - a method in which contaminant removal      Similar requirement removal is accomplished solely by mechanical means, including        is accomplished solely by mechanical means, including wiping, wiping, abrasive blasting, brushing, grinding, sanding,              abrasive blasting, high pressure water jetting, brushing, chipping,          ______________etc._____                            sanding,_grinding,_and chipping____________
Pitting - Localized corrosion resulting in surface defects.          pitting - surface defects resulting from localized corrosion      Similar requirement 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                        Page 4 of 35
 
Cleaning"of Fluid Systems, and. Associated Components                        Q l Assurance:Requiremes for.Claning"of Fuid                            Comments o.m During Construction Phase of Nuclear Power Plants                          Systems and Associated Components for Nuclear Po~wer ANSI N45.2.1 -1973                                                                  Plants
______________________________________NQA-1-W994,                                        Subpart:2.1 Purchaser - The agency responsible for issuance and                          NQA-1 INTRO Definition:                                            Similar requirement administration of a contract, subcontract, or purchase order                  Purchaser - the organization responsible for establishment of imposing this standard or portions hereof.                                    procurement requirements and for issuance or administration, or both, of procurement documents Rinsing - (1) Filling and draining an item with water until                  rinsing: (a) filling and draining an item with water until soluble Similar requirement contaminants in the effluent water are reduced to some                        contaminants in the effluent water are reduced to some predetermined concentration, or (2) flowing water through the                predetermined concentration; or (b) flowing water through the system or component at low velocity until contaminants in the                system or component until water soluble contaminants in the effluent water are reduced to some predetermined                              effluent water are reduced to some predetermined concentration concentration.
Rust - Corrosion products, consisting largely of iron oxide.                  rust - corrosion products consisting largely of iron oxide. Such  Same requirement Such oxides may vary in color from red to black and may form                  oxides may vary in color from red to black and may form a loosely adherent heavy covering to a tightly adherent light                anything from a loosely adherent heavy covering to a tightly film. Pitting or general surface roughening, may or may not be                adherent light film. Pitting or general surface roughening may present.                                                                      or may not be present.
Sensitized Corrosion Resistant Alloy - Any alloy which has                    sensitized corrosion-resistant alloy - a corrosion-resistant      Similar requirement been subjected to heating that causes intergranular precipitation            alloy that has been subjected to heating that causes of chromium carbides in quantities sufficient to be detected by              intergranular precipitation of chromium carbides in sufficient methods of ASTM A262-68, Recommended Practices for                            quantities to be detected by Practice B, C, D, E, or F of ASTM Detecting Susceptibility to Intergranular Attack in Stainless                A 262, Practices for Detecting Susceptibility to Intergranular Steel or ASTM A393-63, Recommended Practices for                              Attack in Austenitic Stainless Steels Conducting Acidified Copper Sulfate Test for Intergranular Attack in Austentic Stainless Steel.
Solvent Cleaning - Dissolving organic contaminants with an                    solvent cleaning - removing contaminants with an organic          Similar requirement organic solvent.                                                              solvent 1.5 Referenced Documents Other documents that are required to be included as part of this              See Part 11, INTRODUCTION, Section 7 which refers to the          The QAPD addresses standard are either identified at the point of reference or                  NQA-I Table entitled "Codes, Standards, and Specifications        VCSNS's position on described in Section 10 of this standard. The issue or edition of            Referenced in Text" for information regarding referenced          referenced documents and the referenced document that is required will be specified either            documents in NQA-I                                                the Reg. Guides and at the point of reference or in Section 10 of this standard. Other                                                                              Standards that apply to the terms and definitions are contained in ANSI N45.2.10                                                                                            QA program.
Reg. Guide 1.37-3/73 Position C. I states: Subdivision 1.5 of ANSI N45.2.1-1973 states that other documents required to be 10/28/2010                                                              Cleaning of Fluid Systems and Associated Components                                    Page 5 of 35
 
Cleaning of Fluid Systemsand A:ssciatedComponents                          " Assur.n. .. .luid                      'n.nk    Fl                Com ment Construction Phase of Nuclear Power Plants
        .During                                                        Systems and Associated Components for Nuclear Power ANSI N45.2.1 -1973                                                          Plants  "~
NQA--94 Subpart:2.1                        ___________
included as a part of the standard are either identified at the point of reference or described in Section 10 of the standard.
The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations, where appropriate..
2.0 GENERAL REQUIREMENTS                                            2 GENERAL REQUIREMENTS This section contains requirements that are to be fulfilled by the                                                                      Not requirement.
contractor who is responsible for performing any segment of work described in paragraphs 3 through 9 of this standard.
Cleanness classification for an item shall be specified in accordance with paragraph 3.1 of this standard.
The work and quality assurance requirements for the cleaning        The work and quality assurance requirements for the cleaning        Similar requirement of items and systems to be incorporated in the nuclear power        of components and systems and for the control of their plant and control of cleanness thereof shall be established in      cleanness shall be established in order to:
order to (1) ensure the removal of any deleterious contaminants,              (a) ensure the removal of deleterious contaminants;                Same requirement (2) minimize recontamination of cleaned surfaces, and                (b) minimize recontamination of cleaned surfaces; and              Same requirement (3) minimize the cleaning required after installation.              (c) minimize the cleaning required after installation, repair, or  Similar requirement- NQA-modification.                                                      1 includes "repair or modification" while N45.2.1 was for construction.
The cleanness classification of each item shall be specified in accordance with para. 3.2 of Subpart 2.1 2.1 Planning                                                        2.1 Planning The cleanness and cleanness control activities shall be planned      Cleaning and cleanness control activities for each phase            Similar requirement - with and outlined to define cleaning and inspection operations to be      (manufacturing, construction, modification, repair, etc.) shall be  NQA-1 expanded to used. It shall detail the systematic, sequential progression of      planned in accordance with the requirements of the Introduction    additional activities cleaning operations for each item or system, the responsibilities    to this Part (Part 11). The plan(s) shall define the cleaning and  (modification, repair, etc.)
of parties concerned for each operation, and measures to be          inspection operations to be used, the system, the responsibilities employed to preserve the cleanness of cleaned surfaces.              of the parties concerned for each operation, and the measures to be employed to preserve the cleanness of cleaned surfaces.
10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                      Page 6 of 35
 
Cleaning of Fluid Systems and Associated'Components,                  Quait Assurane Requirements for Cleaning of Fluid                      Comments During Construction Phase of Nuclear PowerPlants                    Systems and Associated Coimnents forNuclear Powr ANS.*N45.2.1 -1973                                                            Plants              .
NQA-1-1994, Sub"part 2.1 Planning for cleaning activities shall include a review of the                                                                          Covered in Subpart 2 system and component design specifications and drawings and                                                                            Introduction, 4.1 - Planning of the construction work plans and schedules to ensure that provisions for cleaning have been incorporated; that they can be accomplished as specified; and that time and resources are sufficient to accomplish the required actions.
This review shall consider the following items as appropriate:        In addition, planning shall consider the following factors, as    Similar requirement appropriate, recognizing that this list may not be complete nor applicable to each phase covered by this Part (Part 11):
: 1. Adequacy of vents and drains, inspection access points,          (a) adequacy of vents, drains, inspection access points, and      Similar requirement bypass or recirculation lines;                                        bypass or recirculation lines;
: 2. Facilities for filters, and flushing and/or drain connections, in  (b) facilities for filters and flushing and drain connections in  Similar requirement locations where dead legs are unavoidable;                            locations where dead legs are unavoidable;
: 3. Piping system design and installation in a manner which            (c) design and installation of piping in a manner that minimizes  Similar requirement minimizes the necessity for installation of temporary piping          the necessity for installing temporary piping during the cleaning during the cleaning operations; (Where possible, divide the          operations, such as dividing the system into a number of system into a number of separate cleaning circuits to facilitate      separate cleaning circuits to facilitate cleanability; cleaning);
: 4. Sequencing of the installation operations to provide for          (d) sequencing of installation operations to provide for visual  Similar requirement.
visual inspection (crawl through) of the inside surfaces of large    inspection of inside surfaces of large diameter piping; diameter piping;
: 5. Control of the installation operations so that piping and          (e) control of installation operations so that piping and        Same requirement components which have already been installed are not subject          components that have already been installed are not subject to to contamination when subsequent installation operations are          contamination when subsequent installation operations are performed;                                                            performed;
: 6. Adequate pumping and heating capacities when these are            (f) adequacy of pumping and heating capacities when these are    Same requirement important factors in the cleaning operations.                        important factors in the cleaning operations; (g) disposal of cleaning solutions and waste water;              Added to NQA-1 (Environmentally correct)
(h) safety, fire protection, and other hazards.                  Added to NQA-1 (Env./Safety concerns) 2.2 Procedures and Instructions                                      2.2 Procedures and Instructions 2.2.1 Cleaning procedures as well as procedures or work instructions        Written procedures and instructions for cleaning, cleanness      Similar requirement 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 7 of 35
 
Cleaning of Fluid Systems and Associate6Components                  Qulty"              R                fo C          gof Fluid            Comments During Construction Ph.ase of Nuclear Poer Plants                  Systems and Associated Components forNuclear Power ANSI N45.2.1 -1973                                                          Plants NQ A-i-9-i, ~Subpart 2.1 for cleanness control practices and inspections, examinations or    control, inspections, and tests to verify cleanness of items shall tests to verify cleanness of items shall be prepared.                be prepared in accordance with the requirements of the Introduction to this Part (Part I1).
These documents shall include as appropriate:                                                                                            List covered in introduction of NQA-1 regarding procedures.
: 1. Detailed cleaning-cleanness control procedures
: 2. Personnel safety considerations
: 3. Structure or facility protection consideration
: 4. Inspection and test equipment requirements
: 5. Sequence of work activities, inspections and tests
: 6. Sequential steps for a given activity
: 7. Acceptance criteria including methods for verifying cleanness
: 8. Preparatory checks
: 9. Approvals
: 10. Responsibilities
: 11. Data report forms 2.2.2 The preparation of the actual working procedures or                  Preparation of the actual cleaning procedures or instructions      Similar requirement instructions to be used should consider:                            shall consider the following:
: 1. Work practices, housekeeping, access control, and prevention      (a) work practices, housekeeping, access control, and              Same requirement of contamination and recontamination;                                prevention of contamination and recontamination;
: 2. Effectiveness of cleaning procedures for removal of the          (b) effectiveness of cleaning methods for removal of the            Same requirement contaminants;                                                        contaminants; (c) effects of residual quantities of cutting fluids, liquid        Added to NQA- 1 penetrants, weld fluxes, precleaning solutions, engineering test fluids, and other process compounds that may have been intentionally or advertently applied to the surface of the item during prior steps of manufacture, installation, or use;
: 3. Corrosiveness of cleaning solutions in contact with the          (d) corrosiveness of cleaning solutions in contact with the        Similar requirement material of an item, particularly in the case of dissimilar metals;  material of an item, particularly in the case of dissimilar metals and entrapment of cleaning* solutions;                            .I 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                      Page 8 of 35
 
Cleaning of Fluid. Systems and Associated Components.                              Quality Assurance Requirements for.Ce~aning of Fluid                        Comments During Construction Phase of Nuclear Power Plants                                  Systems and Associated Components for Nuclear Power.............................................
ANSI N45.2.1 -1973                                                                          Plants.
___________________________________________NQA-1-19.94,                                            Subpart 2.1                  ___________
: 4. Chemical composition, concentration, and temperature limits                      (e) chemical composition, concentration, and temperature limits    Similar requirement of cleaning solutions to avoid deleterious effects;                                of cleaning solutions to avoid deleterious effects;
: 5. Proposed solution and metal temperatures, solution                              (f) solution and metal temperatures, solution concentrations,      Similar requirement concentrations, velocity, and contact times during cleaning;                        velocity, and contact times during cleaning;
: 6. Methods for monitoring cleaning solution concentration and                      (g) methods for monitoring cleaning solution concentration,        Similar requirement temperatures during cleaning operations;                                            temperatures, and velocities during cleaning operations;
: 7. Identification of the systems and subsystems with which the                      (h) identification of the items for which the procedures are to be  Similar requirement procedures are to be used;                                                          used;
: 8. Proposed sequence of operations and methods of filling,                          (i) sequence of operations and methods of filling system            Same requirement system circulation, draining, and flushing;                                        circulation, draining, and flushing;_____________
: 9. Proposed equipment isolation, location of temporary piping                      ()(1) equipment isolation                                          Similar requirement and valves, location of strainers and where possible, the                                (2) location of:
location of temporary equipment;                                                          (a) temporary piping and valves (b) strainers (c) temporary equipment 102/0.0Cenigo                                                                            (d) connections for filling,
                                                                                                .FudSstm.n            flushing, Assoiate        rinsing, and draining Comonnt.Pae..o.3
____________________________________________                          equipment;_____________
: 10. Construction operations prohibited during cleaning                              (k)activities to be prohibited or constrained before, during, and  Similar requirement operations;                                                                        after cleaning operations                                          _____________
: 11. Methods for rinsing and neutralizing including number of                        (I) methods for rinsing and neutralizing, including estimated      Same requirement rinses;                                                                            number of rinses;____________
: 12. Methods for verifying cleanness;                                                (in)  methods for verifying cleanness;                              Same requirement
: 13. Methods of drying and lay-up of the system;                                    (n) methods for drying and lay-up;                                  Similar requirement
: 14. Methods for protecting installed equipment which are not                        (o) methods for protecting installed items which are not            Similar requirement used in the cleaning operations;                                                    involved in the cleaning operation;                                ______________
: 15. Methods for disposal of cleaning solutions.                                    (p) method of disposal of cleaning solution.                        Similar requirement 2.3 Results                                                                                                                                            _____________
Inspection and test results shall be documented in a suitable test                                                                                    NQA- I does not repeat report or data sheet. Each report shall identify the item to which                                                                                      information across sections-it applies, the procedures or instruction followed in performing                                                                                        this is covered under the task and the identification of the following:                                  ____________________________isection                                              and test sections
: 1. Conditions encountered which were not anticipated,___________________________________________
10/28/2010                                                                    Cleaning of Fluid Systems and Associated Components                                        Page 9 of 35
 
Cleaning ofFluid Systems and Associated Components6                      Quality AsuranceRquiruements f6r;Cleaning of Fluid                      Comments Duritn Construction Phase of Nuclear Power Plants                    Systems and Associated. Components for Nuclear Power ANSI N745.2.1 -1973                                                          Plants
________.._...____"____          _.....o                      QA-1-1994, Subpart 2.1                      __.......
including nonconformance.
: 2. Identity of inspector or tester.
: 3. Completion date.
Test reports and data sheets shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation.
2.3 Rectification of Unacceptable Cleanness If indications of contamination in excess of specified limits are Added to NQA-1 observed at the end of a cleaning operation or at any subsequent inspections for cleanness, the item shall be recleaned using an approved procedure. If such indications are observed at the anticipated end of a cleaning operation, continued cleaning shall be performed to reduce the level to the specified limit.
If necessary, an evaluation shall be made to determine the cause  Added to NQA-1 of the unacceptable cleanness and the actions required to preclude recurrence.
7.4 Control of Cleaning Solutions                                      2.4 Control of Cleaning Solutions Cleaning solutions should be prepared in accordance with the            Cleaning solutions shall be prepared in accordance with the      Similar requirement, but applicable cleaning procedure and shall be checked for proper          applicable cleaning procedure and shall be checked for proper    changed from chemical composition and effectiveness of inhibitors (if used).        chemical composition and effectiveness of inhibitors, if used. recommendations to Solution temperatures must be maintained and controlled to              Solution temperatures shall be maintained and controlled to      requirements in NQA-1.
assure adequate cleaning and to prevent decomposition and              ensure adequate cleaning and to prevent cleaning agent possible damage to the system.                                          decomposition and possible damage to the item.
2.4 Personnel Qualifications Those personnel who perform inspection, examination or                                                                                    Covered in PART 2 testing activities required by this standard shall be qualified in                                                                        Introduction, Basic /
accordance with ANSI N45.2.6 Qualifications of Inspection,                                                                                Supplementary Examination, and Testing Personnel for the Construction Phase                                                                            Requirements 2 of NQA- 1, of Nuclear Power Plants.                                                                                                                  and Part H, Section 2 of the QAPD.
2.5 Test Equipment 2.5.1 Selection.
Inspection and test equipment used to implement the                                                                                      Covered in NQA-1 PART II requirements of this standard shall be selected to have sufficient                                                                        Introduction, Basic 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 10 of 35
 
Cleaning ofFluid'Systems and Associated Components                  :Quality Assurance Requirements for'Cleaning ofFluid          Comments During Construction, Phase of Nuclear Power Planti                Systems and Associated Components for Nuclear Powe~r ANSI N4.5.2.1 -1973          ...      ..                                Plants
______________________________________NQA-1-1994,,Subpart                              2.1 accuracy and sensitivity tolerance to determine conformance to                                                                Requirements 2 and 12, and specified requirements.                                                                                                      Supplement 12S-1, as well as other sections relating to inspection and test.
2.5.2 Calibration and Control.
Test equipment shall be adjusted and calibrated at prescribed                                                                Covered in Subpart 2.16 of intervals against certified equipment having known valid                                                                      NQA-1. NQA-1 doesn't relationships to nationally known standards.                                                                                  generally repeat information If no national standards exist, the basis of calibration shall be                                                            that is common between documented. Records shall be maintained and equipment                                                                        requirements and Subparts.
suitably marked to indicate calibration status.
When inspection and testing equipment is found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and acceptability of items previously inspected or tested.
2.6 Housekeeping In areas, facilities and environments where the cleanness                                                                    Note - See NQA-1 Subpart controls of this standard are required, the housekeeping                                                                      2.3 for comparison with requirements shall be in accordance with ANSI N45.2.3,                                                                        ANSI N45.2.3.
Housekeeping During Construction Phase of Nuclear Power Plants.
3.0 CRITERIA FOR CLEANING                                              3 CLEANNESS CRITERIA It is intended that systems that have been cleaned in accordance                                                              Note - See NQA- I Subpart with this standard should require only water flushing or rinsing                                                              2.3 and QAPD Part II, as a final cleaning step in preparing them for service. However,                                                              Section 13 for additional where more than normal water flushing or rinsing is required to                                                              information regarding produce the specified cleanness, additional cleaning in                                                                      VCSNS Housekeeping and accordance with this standard may be necessary.                                                                              External Cleanliness commitments and clarifications.
While this standard is primarily concerned with the cleaning                                                                  Not a requirement.
and cleanness of internal surfaces, external surface cleanness may be of equal importance in some cases and should be recognized during the cleaning operations. Internal and external 10/2 8/2 010                                                      Cleaning of Fluid Systems and Associated Components                        Page I11 of 35
 
Cleaning of Fluid Systems and Associated Components                Quality Assurance Requirements for Cleaning of Fluid                    CommenI          ...
DurnaCng        utinPhase of Nuclear Power Plants                Systems and: Associated Comnponents for Nuclear Power.
ANSI N45.2.1 -1973              "    .      ""nts
                                                -                                        NQA-4-1,994, .Subpart 2.1 surfaces may have different cleaning and cleanness requirements.
3.1 Cleanness Classifications                                      3.1 Cleanness Classification The degree of cleanness required is a function of the particular    The level of cleanness required for any particular application is  Similar requirement item under consideration.                                          a function of the particular item under consideration.
The assignment of a cleanness classification shall consider the    The assignment of a cleanness classification shall consider the    Similar requirement NQA-1 susceptibility to corrosion of the material, the consequences of    following: (a) the function of the item to be cleaned;(b) the      expanded - covers storage, malfunction or failure of the item and the probability of          susceptibility of its materials of construction to various forms  operation, repairs, etc) and contaminants contributing to or causing such malfunction or        of corrosion, including intergranular cracking, or stress          with additional specificity.
failure.                                                            corrosion cracking under fabrication, installation, or operating conditions; (c) the consequences of malfunction or failure of the item; (d) the possibility of contaminants (introduced during fabrication, storage, installation, repairs, or service) contributing to or causing such malfunction or failure.
This standard does not establish the cleanness classification of    Four classes of surface cleanness (Classes A, B, C, and D) with    The commitment to Subpart any specific item. However, typical examples are presented as a    criteria for each are provided in Subpart 2.1.                    2.1 cleanness classifications guide. The specification for the required cleanness class shall                                                                        is described in Part II, be the responsibility of the purchaser.                                                                                                Section 13.2 of the QAPD.
The class of cleanness required for any given application shall    The cleanness class or classes applicable to the item or specific  Similar requirement be specified in design drawings or specifications associated        parts of the item shall be established and specified in the with the cleaning of items, and the method of verification of      applicable drawings, specifications, or other appropriate cleanness shall be documented.                                      documents.
NOTE The following cleanness classifications are not directly      Different cleanness classes may be assigned to internal and        Similar requirement related to component classifications assigned by the ASME          external surfaces, or to different parts of the same item based on Boiler and Pressure Vessel Code for design and inspection or        the cleanness needs of the specific item. Guidelines for for other purposes                                                  assigning cleanness classifications are listed in Part mI, Subpart 3.2, Appendix 2.1 3.2 Cleanness Class Criteria 3.1.1 Class A -                                                    3.2.1 Class A.
A very high level of cleanness in which there is no evidence of    A very high level of cleanness as evidenced by the freedom        Similar requirement contamination of a surface either under visual examination,        from all types of surface contamination, according to the with or without magnification, or with the aid of sensitive        acceptance criteria of the inspection methods specified in the 10/28/2010                                                    Cleaning of Fluid Systems and Associated Components                                    Page 12 of 35
 
Cleaning of Fluid Systems and Associated. .mpo'n'ents          *.Quality Assurance Requirements for Clenn.a g of;Flud.                      id              Commets During Construction Phase of Nuclear Power Plants                Systems and Associated Components for Nuclear Poower
                      .:    N45.2.1 -1973      .
                                                                                *~~~~~~~~~~~~~~...............
ANSI Plants NPA44994,                      Subpart 2A1 detection methods. Class A cleanness applies to special items      procedures required by para. 2.2.1. If close control of such as fuel elements, control rod drive mechanisms, delicate      particulate contamination is required, a clean room, in instruments, and other close tolerances or carefully controlled    accordance with para. 8.5.5 of ASTM A 380-78, Practice for surfaces or assemblies. Such items should receive their required  Cleaning and Descaling Stainless Steel Parts, Equipment, and level of cleanness at the point of manufacture and cleanness      Systems, shall be employed during the manufacturing, must be maintained at the construction site. For these reasons,    assembly, and installation operations when particulate requirements of this level of cleanness are considered to be      contamination could occur. Gross and precision inspection outside of the scope of this document.-:                          methods applicable to Class A are described in paras. 7.2 and 7.3 of ASTM A 380-78; other special tests shall be specified as necessary.
Where the cleanness of internal surfaces is evaluated by                          NQA-1 added requirement.
flushing, criteria shall be specified in the cleaning procedure.
3.1.2 Class B                                                      3.2.2 Class B.
A high level of cleanness applicable to reactor coolant systems,  A high level of cleanness as evidenced by the following                            Similar requirement components, and other items, such as the reactor coolant          characteristics.
purification system, which have similar cleanness requirements.
Piping and components in systems which are designed as requiring Class B cleanness shall meet the following requirements (a) Corrosion-Resistant Alloys (1) The surface shall appear metal clean and free of organic                      NQA-1 provides similar films and contaminants when examined in accordance with                            guidance as N45.2. 1, but para. 7.2.1 of ASTM A 380-78, Practice for Cleaning and                            breaks it down to Corrosion Descaling Stainless Steel Parts, Equipment, and Systems,                          Resistant Alloys and except light deposits of atmospheric dust are permissible and                      Carbon and Low Alloy shall show no evidence of deleterious contamination when                          Steels.
subjected to the wipe test of para. 7.2.2 of ASTM A 380-78.
When visual inspection is impossible but surfaces are accessible for wipe tests, sufficient wipe tests in different areas of the item shall be made to evaluate the general cleanness level of the surface. Scattered areas of rust are permissible, provided the aggregate area does not exceed 2 sq in. in any 1 sq ft area (14 cm2 per 1000 cm2). Temper films and discolorations resulting from welding are acceptable.
10/28/2010                                                    Cleaning of Fluid Systems and Associated Components                                                          Page 13 of 35
 
Cleaning of Fluid Systems and.Associated Components                  Quality Msurance'Requirements for Cleaning 6f Fluid              .....    .. Comments During Construction Phase of Nuclear Power.Plants                  Systems-and Associted Components forNuclear Power ANSI. N4.2. 173        ..                      SsesadAsc~                    oPonents    frNcerPwr...
NQA-171994, SiahPart 2.1                      __________
(2) If flushing is the only practical means for evaluating the cleanness of internal surfaces, a 20mesh (850 rim, ASTM E 11, Specification for Wire Filter Cloth Sieves for Testing Purposes) or finer filter (or the equivalent) shall be installed and the item flushed with water or other fluid meeting the requirements of para. 3.4. The item shall be flushed at the design velocity (or other flow velocity if specified in the procedure) until the screen shows no more than slight speckling (as specified in the procedure in qualitative or quantitative terms, such as the number of particles per unit surface area of the screen) and no more than slight rust staining. There shall be no particles larger than 1/32 in. x 1/16 in. long (0.8 mm x 1.6 mm). In water flushed systems there shall be no visual evidence of contamination (e.g., oil, discoloration) of the effluent flush water or screen.
NOTE Localized rusting may indicate pitting of the surface and should be evaluated metallurgically. Thin temper films resulting from welding or post-weld heat treatment are acceptable.
: 1. The surface shall appear "metal clean" when examined without magnification under a lighting level (background plus supplementary lighting) of at least 100 foot candles. Scattered areas of rust are permissible provided the aggregate area of rust does not exceed 2 square inches in any one square foot area.
: 2. The surface shall be free of particulate contaminants such as sand, metal chips, weld slag, etc
: 3. The surface shall be free of organic films and contaminants such as oils, paint, and preservatives as determined by a visual examination or an organic solvent-dampened white cloth or an equivalent alternate method.
: 4. When a visual inspection is not possible and the surfaces are accessible, a dry white-cloth wipe, followed by a solvent-dampened white cloth wipe, may be used to evaluate the cleanness of the surface. If either cloth exhibits indications of contamination, the system shall either be recleaned or the 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                      Page 14 of 35
 
Cleaning of Fluid Systems and Associated Components                              Quality Assurance Requirements'for Cleaning of Fluid                  -Comments During Construction Phase of Nuclear Power Plants                              Systems and Associated Components for Nuclear Power ANSI
                          .N45.2...      -1973                .....                                              Plants
_._*_      ._._....... _*_... .. _.. _.. _.._....    ..... i..'N                          QA-  -19994, Subpart 2J.1                  __ _'"_  _"
specific contaminant shall be determined and evaluated as to its potential deleterious effect.
: 5. If flushing is the only practical means for determining system cleanliness, the system shall be evaluated by examining a 20-mesh (ASTM E 11-70, Specifications for Wire Cloth Sieves for Testing Purposes) or finer filter, or the equivalent, installed on the outlet of the cleaning circuit. The system shall be flushed at its normal design velocity (or other velocity if specified by procurement documents) until the screen shows no more than slight particle speckling and no more than slight rust staining.
There shall be no particles larger than 1/32 inch in any dimension, except fine hairline slivers of less than 1/32 inch thickness are permissible up to 1/16 inch long. There shall be no evidence of organic contamination in the effluent water or on the filter (b) Carbon and Low Alloy Steels (1) The surface shall appear metal clean when examined in accordance with para. 7.2.1 of ASTM A 380-78, except light deposits of atmospheric dust are permissible, and shall show no deleterious contamination when subjected to the wipe test of para. 7.2.2 of ASTM A 380-78. Wipe tests shall be made prior to the application of any preservative film (some type of protective film may be required in order to maintain a clean carbon or low alloy steel surface at Class B level). When visual inspection is impossible, but surfaces are accessible for a wipe test, sufficient wipes of different areas of the item shall be made to evaluate the general cleanness of the surface. Scattered areas of rust are permissible, provided the aggregate area does not exceed 2 sci in. in any 1 sc ft area (14 cm2 per 1000 cm 2 ).
(2) If flushing is the only practical means for evaluating the cleanness of internal surfaces, a 20mesh (850 lim, ASTM E 11, Specification for Wire Cloth Sieves for Testing Purposes) or finer filter (or the equivalent) shall be installed and the item flushed with water or other fluid meeting the requirements of Page 15 of35 Cleaning of Fluid Systems and Associated Components 10/28/2010 10/28/2010                                                                    Cleaning of Fluid Systems and Associated Components                                  Page 15 of 35
 
Cleaning of Fluid Systems and Associated Components                    Quality Assurance Requiements for Cleaning ofFluid                          Comments
        .During Construction Phase of Nuclear Power Plants                Systems and Associated Component* for Nuclear Power
                      'I." ,            1..
                                      * -1973              ....                                      Plants                            .
NQA71-1094,,Subpart 2.1j              ~        .~
para. 3.4. The item shall be flushed at the design velocity (or other flow velocity if specified in the procedure) until the screen shows no more than slight speckling (as specified in the procedure in qualitative or quantitative terms, such as the number of particles per unit area of the screen) and no more than slight rust staining. There shall be no particles larger than 1/32 in. x 1/16 in. long (0.8 mm X 1.6 mm). In water flushed systems there shall be no visual evidence of contamination (e.g., oil, discoloration) of the effluent flush water or screen NOTE: Class B cleanness should be specified for carbon steel and low alloy steel surfaces only in special cases because of the difficulty in maintaining such surfaces in that condition after they have been cleaned.
3.1.3 Class C -                                                      3.2.3 Class C.
An intermediate level of cleanness generally applicable to            An intermediate level of cleanness in which the surfaces meet        Similar requirement -
closed service water systems that cool components containing          the requirements for Class B except:                                  Differences in NQA- 1 reactor coolant, engineered safety systems, and other high                                                                                  recognize additional alloys, integrity systems. Surfaces shall meet the requirements for                                                                                etc., not recognized in the Class B cleanness, except:                                                                                                                  older N45.2.1 standard.
: 1. Thin uniform rust films are acceptable on carbon steel            (a) Corrosion-Resistant Alloys. Scattered areas of rust are          Similar requirement surfaces.                                                            permissible, provided the aggregate area does not exceed 15 sq in. per 1 sq ft area (100 cm 2 per 1000 cm 2).
: 2. Scattered areas of rust are permissible provided that the area    (b) Carbon and low Alloy Steels. A uniform light rust bloom          Similar requirement of rust does not exceed 15 square inches in any 1 square foot on      which can be removed by brushing or wiping is acceptable.
corrosion resistant alloys.
: 3. Flush-test filters may exhibit considerable rust staining.        (c) Corrosion-Resistant Alloys and Carbon and Low Alloy              Similar requirement Steels. Screens installed for evaluation of internal surfaces by flushing may exhibit considerable particle speckling (as specified in the procedures in qualitative or quantitative terms, such as the number of particles per unit area of the screen) and considerable rust staining.
3.1.4 Class D -                                                      3.2.4 Class D.
The level of cleanness applicable to fire protection, open            A nominal level of cleanness in which the following are              Similar requirement service water, and similar systems requiring only a nominal          acceptable:
10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                      Page 16 of 35
 
Cleaning of Fluid Systems and Associated Components                  Quaity Assurance Requirementsfor cleaning of Fluid                      Comments During Construction Phase of Nuclear Power Plants                  Systems and Associated Components for Nuclear Power
                        . ANSI N45.2.1 -1973                                                        Plants degree of cleanness. The following are acceptable on items which meet Class D cleanness:
: 1. Tightly adherent mill scale on carbon steel surfaces.              (b) tightly adherent mill scale on nonmachined carbon and low      Similar requirement alloy steel surfaces that resist removal by hand scrubbing with a stiff wire brush;
: 2. Paint or preservative coatings on carbon steel surfaces that      (c) paint or preservative coatings on carbon or low alloy steel    Similar requirement will not peel or flake when exposed to cold-water flushing.          surfaces that will not peel or flake when subjected to cold water flushing
: 3. Rust films on carbon steel and stainless steel surfaces that      (a) rust films on both corrosion-resistant alloys and carbon and  Similar requirement resist removal by scrubbing with a bristle brush.                    low alloy steel surfaces;
: 4. If flushing is the only practical means of determining system      (d) particles no larger than 1/16 in. x 1/8 in. long (1.6 mm x 3.2 Similar requirement, but not cleanness, the system shall be evaluated by examining a 14-          mm) on a 14-mesh (1.4 jim, ASTM E 11), or finer filter (or the    as specific.
mesh (ASTM E 11-70, Specification for Wire Cloth Sieves for          equivalent).
Testing Purposes) or fine filter, or the equivalent, installed on the outlet of the cleaning circuit. The system shall be flushed at its normal velocity until the screen shows no more than occasional particle speckling. There shall be no particles larger than 1/16 inch in any dimension, except hairlike slivers of less than 1/16 inch thickness are permissible up to 1/8 inch long.
There shall be no evidence of organic contamination on the screen; considerable rust-staining is acceptable.
3.2.5 Summary.
The cleanness classes are summarized in Table 3.2 of Subpart 2.1. See Table at end of document 3.3 Hydraulic, Instrument Control, and Lubrication Lines and Systems The preceding cleanness classifications and criteria in para. 3.2 are primarily applicable to relatively large items which are generally amenable to visual inspection of internal surfaces at some time during manufacture and installation operations.
Interior surfaces of hydraulic, instrument control, and lubrication systems are generally not accessible for visual inspection during manufacture and installation, and may have much more stringent requirements on particulate contamination 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 17 of 35
 
Cleaning of Fluid Systems and Associated Components                  Qualit Assurance Requirements for Cleaning' of Fluid                    Comments Construction Phase of Nuclear Power Plants
        .During                                                      Saystems and AssoeiteaComponents forNuclear Power' ANSI N45.2-4 -1973                              SspsadAocteCmPonents                      foNuea        we NQA 1 1994, Suhbpart 2.1 than those specified in the preceding cleanness classes. Where special characteristics and specific requirements are needed for such systems, they shall be specified. Guidelines for classifying hydraulic, instrument, and lubrication cleanness are presented in Part mI, Subpart 3.2, Appendix 2.1.
3.4 Cleaning and Flushing Fluid Quality Requirements 3.2 Water Quality Requirements                                      3.4.1 Water.
The selection of the water quality for a specific application      The water quality for mixing cleaning solutions, rinsing, and      Similar requirement. The shall be made by the organization responsible for the cleaning      flushing shall be specified by the organization responsible for    guidance in the Reg. Guide operations unless otherwise specified in the purchase document. cleaning unless otherwise stipulated in procurement documents      and the level of detail is In cases where the water quality for operating systems is lower    or approved procedures. Table 3.4.1 lists water quality            addressed in the than that specified below (e.g., open service water systems), the  requirements commonly used for such purposes in nuclear            administrative controls for water used for cleaning can be equivalent to the quality of the    cleaning operations.                                                cleaning.
operating system water. When cleaning water quality is not otherwise specified, it shall comply with the following specifications:
Reg. Guide 1.37-3/73 Position C.3 states: Subdivision 3.2 of ANSI N45.2.1-1973 states that the selection of the water quality for a specific application shall be made by the organization responsible for the cleaning operations unless otherwise specified in the purchase document. The water quality for final flushes of fluid systems and associated components should be at least equivalent to the quality of the operating system water.
Fresh Water Fresh water shall meet the following requirements:                  When fresh water is used on components or systems containing        Similar requirement. Table pH at 25 C (77 F) 5.5 to 8                                          austenitic stainless steel, attention shall be given to methods for from NQA-1 contains this Chloride Less than 100 ppm                                          minimizing the possible effects of chlorides,                      information.
Fluoride Less than 5 ppm Sulfide Less than 1 ppm Total Dissolved Solids Less than 500 ppm Turbidity Less than 5 Jackson Turbidity Units 10/28/2010                                                    Cleaning of Fluid Systems and Associated Components                                    Page 18 of 35
 
Cleaning of Fluid Sys'ted            ondt mponents          Qualiy AsranceRequimerntsfor Cleaning of Fluid                  Con ments During Construction Phaseofuclear Po    Pltsyst                    and Assciated Compoentn for Nuclear' Power ANSI N45.2.1 -1973                                                      Plants .                    .
NQA 1w9~4;Subpart 2.1 TABLE 3.4.1 WATER REQUIREMENTS Fnah Water ~lat (1)j - Mhlumi Requlrements pH atk2SC (770F)                          5.5t8.0 COodde                                    Less dion M ppm Fluoride                                  LM am 5 ppM sulwde                                    Less don I ppm Total d&molv soid                              si=
Loss *R a    ppM Hig, Quakity Water-      MIntumim Reqiresenms at Point ot Entry Into lIm pHa 256C 076FJ                            5.5 to a.0 Chlokid                                    Less tam I ppm Fluoride                                  Less dun I pPM SuIfde                                    LM tham I ppm Conductlvity at 250C (7791                  M) u3pumh/ctn Silica                                    Ltm than 0.05 ppm Total sumpewed solids                      Lem tm 3 ppm NOTE-(1) PoNable wae that meow U.S. Public Health Service re-quime*ents imay be utlized fr any appilkiaon whem frsh w      bs spectfied.
1 Table copied from NQA- 1-1994, Subpart 2.1.                      1 10/28/2010                                          Cleaning of Fluid Systems and Associated Components                          Page 19 of 35
 
:":len
    .leaningg'of Fluid F    ,Systems an and .A scae *Compon Asociated  omp nents*
s +        .. .. "+:Assurance Quality            ':: Requirements
* for:"Cleanmig
                                                                                                                        ...... of(Fluid
                                                                                                                                    ... ". ..          Comments, During Construction Phase of Nuclear Power Plants,            Systems and Associated Components for Nuclear.Power ANSI N45.2.1 -1973                                                        &#xfd;Plants NQA.-1.994, Subpart 2.1+ +...
Demineralized Water Demineralized water shall meet the following requirements:                                                                                    Similar requirement. Table pH at 25 C (77 F) 5.5 to 8                                                                  TABLE 3.4.1                                      from NQA-I contains this Chloride Less than 1 ppm                                                            WATER REQUIREMENTS                                      information.
Fluoride Less than 1 ppm                                                      r- h Water PIota (11- Mfianimumi            relei ts Sulfide Less than 1 ppm Conductivity at 25 C (77 F) Less than 3 micro mho/cm                pH at 25C V7700                          5.5 to    8.0 Silica Less than 0.05 ppm                                            Flu*                                      L      d 250 ppm Turbidity Less than 1-Jackson Turbidity Unit                                                                  L_ul__a am 5 "
Totl dhiaMov    soids                    Lesa *on 500 ppom High Qualey Water- Mfhmm Requlremenas at Po1at of Entry Into Urns p" at 250C VTFJ                          5.5      08.0 Chlorid&                                  L= don I ppm Fluoidde                                  Less dwn I ppm Suirde                                    Less dun I ppm Conductivity at 250C (770F)              Lm, Ihw 3 pnhm16uan Silica                                    Lm thun 0.05 ppm Tot    sipwnded tolids                    LM am 3 ppm NOR:
(1) Potale waa thai meets U.S. Public Health Service re-quirmnents may be ullized for any appllctkaon wh        fresh wa    isspemed.
Is Table copied from NQA-l-1994, Subpart 2.1.
3.4.2 Gaseous Fluids.
The requirements for gaseous fluids used for flushing are                    NQA- I additional dependent upon the particular item being flushed. The                        requirements /
requirements for any given item shall incorporate restrictions              clarifications.
on particulate Contaminants, organic contaminants, water soluble contaminants, and water content as appropriate for the item.
3.4.3 Organic Fluids.
Requirements for organic fluids used for flushing are dependent              NQA- 1 additional upon the particular item being flushed. The requirements for                requirements/clarifications.
10/28/2010                                                  Cleaning of Fluid Systems and Associated Components                                              Page 20 of 35
 
Cleaning of Fluid Systems and Associated Components          Quality Assurance Requirements for Cleaning of Fluid                                                Comme During Construction Phase of Nuclear Power Plants        Systems and Associated Components for Nuclear Power ANSI N45.2.1 -1973      ..                                                        Plants
                                                                                        -NQA-1-1994, Subpart 2.1 any given item shall incorporate restrictions on particulate contaminants, water soluble contaminants, and water content as appropriate for the item.
3.4.4 Fluids for Hydraulic, Instrument Control, and Lubrication Systems.
In addition to the requirements of para. 3.4.1, 3.4.2, or 3.4.3, as                            NQA-1 additional applicable for the system being flushed, fluids used for final                                requirements /
flushing or rinsing of components and installed systems covered                                clarifications.
by this paragraph shall meet the particulate contamination limits specified in Table 3.4.4 for the system class specified.
TABLE 3.4.4 FLUSHING REQUIREMENTS FOR IIYDRAUUC, INSTRUMeNT CONTROL, AND LUBRICATION SYSTEMS Generic sy~n                Maulmuf Number of Pmklas per 10 cc hPmde Sie clam            Desvptkan      5-10 O=    11-25 "am      25io-0 PMan      100        100OWp a        5-&#xfd;er dem              2.700        670          93 l        MIL4"6                  4,600      1.310          210            16 28          31 2        HIg rdla*ity            91700      2,40          38W            56          5 I        CuIc                  2400        5,360          78O          110 1          1 4        Lep 9i                32ADO      107W          1.510          225          21 S      "M e rdate,Uiy          97A0      21,400      3,130            430          41 6        Indisitl              120000      24A          6W*50          iO0            92 CENERAL  N07M W Adlped fromASrM SIP 491, MadbsAm of ClaaUnin            ph*Au FNuds    aqd Sytome.Cams 2 and 5 oftrbelajiaha STP 491 are dmaed as Good Ufale and Pbr MisU respei, *. Whae huse ailed am bnWane    i a qiufxd vswaclume o 1      0ea(1 o ftaycan aho be ajapled tsprowkftjduS.
V!mn wed n faismane^ the dcmkarpmeeaet d*adl        s the luahlnj "ngoctd      and    ni upon 4kh #A teanalodn dia be hbe" 20 7he above qActam  Cdakn twm do not dreedly emsend to "e deummi dim ata          dm of
                                                              -subix* 2.-t.
3.4.5 If acid cleaning is used, particular attention shall be given                            NQA-1 additional to:                                                                                            requirements and (a) avoidance of entrapment of acids in crevices;                                              clarifications.
(b) effects on either welded or sensitized corrosion-resistant alloys and nonferrous materials; (c) complete removal of any residual acid solution from the item; (d) neutralization treatment followed by thorough rinsing or flushing.
3.4.6 The use of contaminated tools shall be avoided. Tools                                    NQA-1 additional 10/28/2010                                            Cleaning of Fluid Systems and Associated Components                                                                Page 21 of 35
 
Cleaning of.Fluid Systemsand Associated Compnonents        Quality Assurance Requ ire.ments.... for.leaning.
r C..        f Fluid.              C Du gConstr'uctionPhase ofNuclear PowerPlants            Systems andAssociatedComponents for Nuclear    uea Power....
or
                                                              *.' '*          QA-l-1994,Subp"art
* 2.1\        ??*.*,*,,,, .*%:. ,*        ......
which contain, or which may become contaminated with,                  requirements and materials that could contribute to stress-corrosion or                  clarifications.
intergranular cracking shall not be used on corrosion-resistant alloys.
4 MANUFACTURING PHASE CLEANNESS The cleanness of an item at the point of manufacture is critical        New section for to the final cleanness level ultimately attained after installation,    manufacturing phase, Where practicable, the cleanness classification of an item listed      contains similar in the purchase specification shall be the same as that for final      requirements to installation service. The capability of construction site cleaning operations        phase.
may not be sufficient to upgrade the cleanness level of a complex item since a much wider variety of cleaning facilities and procedures are generally available for use at the manufacturer's shops than are available at the construction sites.
Purchase specifications shall specify the required as-shipped cleanness level for the item. Shop cleaning procedures shall be in accordance with para. 2.2, and inspection and test results shall be documented, as appropriate, in accordance with approved procedures.
Listed below are cleaning considerations that are appropriate to all manufacturing operations. Additional information is presented in ASTM A 380-78; where applicable, they shall be considered.
(a) Operations which generate chemical or particulate contaminant such as welding and grinding shall be controlled during fabrication steps, after which removal of such contaminants becomes difficult because of limited access.
Under such conditions, protection of openings shall be provided to prevent entry of contaminants, especially particulate contaminants. If practical, manufacturing sequence shall be based on considerations related to cleaning of individual items as the component is assembled, unless the component is readily cleanable in its final assembled state.
(b) Cleaning methods and materials used during manufacture 10/28/2010                                          Cleaning of Fluid Systems and Associated Components                                          Page 22 of 35
 
Cleaning of Fluid Systems and Associated components                      ..... Quality AssuranceRequirements for Cleaning of Flud                                      Comment During Construction Phase of Nuclear Power Plants                            Systems and Associated Components for Nuclear Power ANSI N45.2.1 -1973                                                                            Plants
______________________________________NQA-1-1994,                                                    Subpart 2.1 shall be compatible with the materials of construction of the item being cleaned (see para. 2.2.2). Cutting fluids, lubricants, liquid penetrants, marking materials, precleaning solutions, engineering test fluids, tools, and other materials and process compounds to be used on surfaces of items made from austenitic stainless steel or corrosion-resistant alloy during manufacture shall be evaluated from the standpoint of potentially harmful contaminants. Such contaminants include chlorides, fluorides, and low melting point materials such as sulfur, lead, zinc, copper, and mercury. Where potentially harmful quantities of such contaminants can be leached or are in a form that they could be released by breakdown of the compound during subsequent manufacturing, installation, or operation, they shall not be used. Paint, chalk, scribing inks, and other temporary marking materials shall be removed from the affected surfaces prior to heat treatment or welding.                    _____________
10/28/2010 :=** .    *IN4
                      ..... .... ..            9i"        *=...
                                                          .....      .==;Clann      of=Fluid...
(c) Use            *,such .and....
Systems....
of tools,        as .those Associ,*
P used anted
                                                                                                                      .. for Components grinding,      * .,*.. ..=* * %
polishing,                        Pag 23 of
                                                                                                                                                                                      .. $3 filing, deburring, and brushing during manufacture shall be controlled when surface contamination of the item from such
___________________________________________tools is Considered an important factor.
(d) The quality of fluid used for final flushing or rinsing shall be equivalent to the quality of the operational fluid of the item, unless otherwise specified in approved procedures (see para.
3.4. 1). Particular attention shall be paid to flushing of pockets, crevices, or dead legs to assure that cleaning solutions are not trapped in such areas.
(e) Fresh water may be used for midxing oil cleaning solutions and for initial rinsing and flushing when permitted by approved procedures.
(f) The final cleaned item shall be sealed in a dried condition to prevent subsequent recontamination and then packaged in accordance with the requirements established in the procurement documents.                                                      ____________
4.0 PRE-INSTALLATION CLEANNESS                                                5 CLEANNESS PRIOR TO INSTALLATION                                            _________
10/28/2010                                                              Cleaning of Fluid Systems and Associated Components                                                  Page 23 of 35
 
Cleaning of Fluid Systems F1*and Associated Components                uli Assurances Quality  Assurance Reu.ments Require entsfor:  .or Cleaning leanng'of    Fluid. ;. *,'.. *.omes..
of*F"luidoments                            ...
During Construction Phbase of Nuclear Power Plants              Systems and Associated Comnponents for Nuclear Powe~r ANSI N45.2.1 -1973                                                              Plants              .
NQA          0194,,Subpart 2.1:        ~      .    . .
Items should not be delivered to the point of installation site      From a cleanness standpoint, consideration shall be given as to            Similar requirement sooner than necessary unless the installation location is            whether items should be delivered to the point of installation considered a better storage area. Inspections, examinations, and sooner than necessary, i.e., whether the installation location is a tests as appropriate shall be performed immediately prior to          better storage area [see Subpart 2.2 of this Part (Part 11)].
installation to determine the cleanness of the item. If              Inspections and tests, as appropriate, shall be made immediately contaminants are detected, they shall be removed if it is judged      prior to installation to determine the cleanness of the item. If that they will not be removed in subsequent cleaning                  potentially harmful contaminants are detected, they shall be operations. Items having surfaces to which temporary paint or        removed if they will not be removed in subsequent cleaning preservative coatings have been applied shall be identified, the      operations. Items having surfaces to which temporary paint or composition of the coating and methods for its removal shall be preservative coatings have been applied shall be identified; the determined and removal of coatings, where required, recorded          composition of the coating and methods for its removal shall be in the inspection report. Unless otherwise required by the job        determined and removal of coatings, when required, recorded in specifications, the temporary coatings shall be removed prior to the inspection report. Unless otherwise required by the job installation of items.                                                specifications, the temporary coatings shall be removed prior to installation of items.
5.0 INSTALLATION CLEANING                                            6 CLEANNESS DURING INSTALLATION 10/28/2010.&deg;              ""    ' ' . "*+'". : '* '*:;.*<.**    -,,*.
Cleaning
* of Flui
                                                                              "'  Syse"s.nd.Asocited"ompo entsPag'." % -* *<                          24...of* 35:".,...
The installation process represents an opportunity for the            The installation process represents an opportunity for the                  Similar requirement introduction of contaminants into a cleaned item and care            introduction of contaminants into a cleaned item, and care shall should be taken to minimize contamination. Operations which          be taken to minimize contamination. Operations that generate generate particulate matter, such as grinding and welding,            particulate matter, such as grinding and welding, shall be should be controlled. Local cleanup of contaminated areas is          controlled. Cleanup of locally contaminated areas as installation recommended as installation progresses, rather than one              progresses is recommended (rather than one cleanup operation cleanup operation when installation is completed.                    when installation is completed).
Consideration should be given to sequencing installation and          Consideration shall be given to sequencing of installation and              Similar requirement erection operations, when practical, to facilitate cleaning and      erection operations to facilitate cleaning, cleanness control, and cleanness control. Where visual inspection of internal surfaces      inspection. Insofar as practicable, internal surfaces of a portion of a portion of a system can be blocked, that part of the system      of a system that can be blocked or obscured by subsequent should be fabricated as a complete unit and a visual inspection      operations shall be visually inspected and verified as being should be performed just before the access points are closed,        clean before the access points are closed.
Openings and pipe ends shall be sealed at all times except when Openings and pipe ends shall be sealed at all times except when Similar requirement they must be unsealed to carry out necessary operations. Fitted      they must be unsealed to carry out necessary operations.
and tack-welded joints (which will not be immediately sealed by welding) shall be wrapped with polyethylene or other nonhalogenated plastic film until the welds can be completed.        ___________________________                                                  ____________
10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                              Page 24 of 35
 
Cleaning of Fluid Systems and Associated Components                Quality AssuranceRequirements: for Cleaning of Fluid                            Comments DuringConstrctionPhase.,fNuclear Power Plants                    System.:,,:s and Associated Components for Nuclear Power During              Ph9se N4.. ofNuleraontslat NQA-1-1994, Subpart 2.1 Precautions shall be taken to avoid contamination of crevices,      Precautions shall be taken to avoid contamination of crevices,        Similar requirement blind boles, dead legs, undrainable cavities, and inaccessible      blind boles, dead legs, undrainable cavities, and accessible areas. When grinding, sanding, chipping or wire brushing, the      areas. When grinding, sanding, chipping, or wire brushing, the item shall be so oriented that chips fall away from the openings    item shall be so oriented that chips fall away from the openings, or covers shall be provided for the openings..                      or covers shall be provided for the openings.
Marking materials containing sulfur, lead, zinc, mercury and        The use of cleaning methods and materials, cutting fluids,            Similar requirement.
other low melting alloys as a basic chemical constituent shall      lubricants, liquid penetrants, marking materials, precleaning not be brought into contact or shall not be used on the surfaces    solutions, engineering test fluids, tools, and other materials and of corrosion resistant alloys. Low-sulfur, low-fluorine, and/or    process compounds used during installation of items made from low-chlorine compounds may be used on austenitic stainless          austenitic stainless steel or other corrosion-resistant alloys shall steels. Low-sulfur, low-lead compounds may be used on              be subject to the limitations on such methods and materials nickelbase alloys. Paints, chalk and other temporary marking        specified in Section 4.
materials shall be removed by solvent-wiping or mechanical means._____________
Surfaces should be cleaned after completion of work on them,        Surfaces shall be visually inspected upon completion of work          Similar requirement before proceeding to the next installation or construction step. on them, and obvious contamination removed before 10/28/201                  Cleaningof Fluid.ystems.an
_____________________________________________proceeding                          Associatd to the next installation or Componets construction step._____________            Page.2 of35 The use of mineral acids and organic acids on austenitic            The use of mineral acids and organic acids to clean austenitic        Similar requirement stainless steels and nickel alloys should be avoided except when stainless steel and nickel alloys shall be evaluated and approved the material is in the solution annealed condition. Pre-cleaning    prior to use. Precleaning and post-cleaning of weld joint areas and post-cleaning of weld joint areas and welds shall be            and welds shall be performed by wire brushing and scrubbing performed by wire brushing and scrubbing with a solvent-            with a solvent-moistened clean cloth unless otherwise specified.
moistened clean cloth unless specified otherwise.
Local rusting on corrosion resistant alloys should be removed                                                                              This guidance not contained by mechanical methods.                                                                                                                    in NQA-l1.
Large openings, such as the open reactor vessel shall be            Large openings, such as the open reactor vessel, shall be              Similar requirement.
protected against falling  and windblown  contaminants,            protected    against  falling and windblown  contaminants.
Reg. Guide 1.37-3/73 Position C.4 states: Section 5 of ANSI N45.2.1-1973 states, in part, that low sulfur, low fluorine, and/or low chlorine compounds may be used on austenitic stainless steels and that low sulfur and low lead compounds may be used on nickel-base alloys. Chemical compounds that could contribute to intergranular cracking or stress-corrosion cracking should not be used with austenitic stainless steel and    ______________________________                                          _____________
10/28/2010                                                    Cleaning of Fluid- Systems and Associated Components                                        Page 25 of 35
 
Cleaning of Fluid Systems and Associated Components                Quality AssuranceRequirements for Cleaning offluid                        Conmment During Construction Phase of Nuclear Power Plants                Systems and AssociatedComponents for Nuclear Poqwer**ower ANSI N45.2.1 -1973                                                          Plants
______________________________________________NQA-1-1994,                        Subpart 2.1                ____________
nickel-base alloys. Examples of such chemical compounds are those containing chlorides, fluorides, lead, zinc, copper, sulfur, or mercury where such elements are leachable or where they could be released by breakdown of the compounds under expected environmental conditions (e.g., by radiation). This limitation is not intended to prohibit the use of trichlorotrifluoroethane which meets the requirements of Military Specification Mil-C-81302b for cleaning or degreasing of austenitic stainless steel provided the precautions of subdivision 7.3(4) of ANSI N45.2.1-1973 are observed.
Reg. Guide 1.37-3/73 Position C.5 states: Section 5 of ANSI N45.2.1 1973 states, in part, that operations such as grinding and welding which generate particulate matter should be controlled. Adequate control of tools used in abrasive work operations such as grinding, sanding, chipping, or wire brushing should be provided. Specifically, tools which contain materials that could contribute to intergranular cracking or stress-corrosion cracking or which, because of previous usage, may have become contaminated with such materials should not be used on surfaces of corrosion-resistant alloys. Examples of such materials are listed in Regulatory position 4. 6. Subdivision 1.4 of ANSI N45.2.1-1973 suggests the use of ASTM A 262-68 or ASTM A 393-63 for detection of intergranular precipitation of chromium carbides in corrosion-resistant alloys. ASTM A 393-63 has been withdrawn by ASTM and is no longer considered a valid test.
6.0 MAINTENANCE OF INSTALLATION CLEANNESS                          7 MAINTENANCE OF INSTALLATION CLEANNESS After any isolable system has been installed in a clean condition After any isolable item has been installed in a clean condition,    Similar requirement and cleanness control measures have been established, access        cleanness control measures and access control shall be control into the system is essential to minimize the introduction established to minimize the introduction of contaminants of contaminants between the time of system isolation and pre-      between the time of system isolation and preoperational testing.
operational testing. Access control shall be established to        Where environmental contamination could cause degradation of exclude personnel and contaminants. Where environmental            quality, seals shall be installed to prevent contamination of contamination could cause degradation of quality, seals must be interior surfaces. Materials used for sealing items made from 10/28/2010                                                    Cleaning of Fluid Systems and Associated Components                                    Page 26 of 35
 
of Fluid Systems
        .Cleaning                    and
                                      ...... Associated
                          "'"""*:...Dl~g'"  .. * *,..**..., Components
                                                              .. *..* . *. ...'.."  Quality      Assrance Requirements f6r Clein
                                                                                          ..............                            nn ig of Fluid              Coments o
During Construction Phase of Nuclear P~OWer P.lants                            Systemsanud.4ssociated:Componen~ts for Nuclear Power ANSI N45.2.1 -1973                                                                        Plants NQA-1-1994, Subpart,2.1 installed which must be hermetically tight and difficult to                        austenitic stainless steel or other corrosion-resistant alloys shall remove                                                                            be subject to the limitations specified in Section 4. Seals shall be installed in a manner to prevent accidental removal.
Gasketed metal seals with welded metal strap closures, or seal                    Removal shall be only with proper authorization. If access to        Similar requirement welded metal caps are recommended for Class B systems and                          such sealed items is required, precautions shall be taken to components. Items in this condition shall be tagged with                          prevent introduction of contaminants. Such precautions include identifications and instructions for seal removal. If access to a                masking and tenting of surrounding areas with plastic film or sealed system is required, precautions shall be taken to prevent                  tape, cleanup of the immediate surroundings to remove introduction of contaminants. Prior to opening the seals, the                    particulate matter that can be introduced into the opening, immediate surroundings should be cleaned to remove solid                          requiring personnel to wear clean outer clothing and shoe contaminants which might be introduced in the system.                            covers, etc. Control of tools, loose items, and access shall be Personnel entering the system should wear clean outer clothing                    maintained in accordance with applicable requirements. When and shoe covers. When the necessary work is completed, the                        the necessary work is completed, the interior surface shall be interior surface shall be locally cleaned to its original condition              locally cleaned, if necessary, to its original condition and the and the system should be resealed.                                                item resealed.
7.0 PRE-OPERATIONAL CLEANING                                                      8 PREOPERATIONAL CLEANING 7.1 Preparations                                                                  8.1 Preparations Cleaning and flushing operations shall be scheduled so as to                      Insofar as practicable, cleaning and flushing operations shall be    Similar requirement minimize interference from other plant operations. Areas in                      scheduled so as to minimize interference from other plant which cleaning operations are being performed shall be isolated                  operations. Areas in which cleaning operations are being to the extent that personnel performing other construction phase                  performed shall be isolated and marked to the extent that operations are aware that the cleaning operations are being                      personnel performing other construction phase operations are conducted.                                                                        aware that the cleaning operations are being conducted.
Personnel shall be familiarized with the intended procedure and                  Personnel shall be familiarized with the intended procedure and      Same requirement associated hazards. Means for communicating shall be provided                    associated hazards. Means for communicating shall be provided between the local areas in which the cleaning is performed and                    between the local areas in which the cleaning is performed and any remote areas (e.g., control rooms) that may be related to the                any remote areas (e.g., control rooms) that may be related to the cleaning operations.                                                              cleaning operations.
Loose tools should be attached to either the workman or the                      Tools and other loose items in controlled areas shall be              Similar requirement exterior of the system with a lanyard. The actual circulating                    controlled as specified in Section 7. The actual circulating flow flow path shall be checked for agreement with specified                          path shall be checked for agreement with specified requirements in regard to location, position and Status of all                    requirements with regard to location, position, and status of all components.                                                                      components.
Critical valves, controls and switches shall be tagged to prevent                Critical valves, controls, and switches shall be tagged to prevent    Similar requirement 10/28/2010                                                              Cleaning of Fluid Systems and Associated Components                                          Page 27 of 35
 
Cleaning of Fluid Systems and Associated Components                  Quality Assurance.Requirements for Cleaning of Fluid                    Comments During Construction Phase of Nuclear Power Plants                  Systems and Associated Components-for Nuclear Power                                .
            .....      ANSI N45.2.1 -1973                                          ,Plants        '                                  ,
NQA,1-1994, Subpart 231            .
inadvertent actuation during the cleaning operation. The interior inadvertent actuation during the cleaning operation. The interior of all accessible components (e.g., tanks) and large diameter        of all accessible components (i.e., tanks) and large diameter piping shall be inspected for cleanness; all debris and              piping shall be inspected for cleanness; all debris and contamination shall be removed. Demineralizers, filters,              contamination shall be removed. Demineralizers, filters, instruments, valve internals and other items that may be              instruments, valve internals, and other items that may be damaged by the cleaning process shall be blanked off, bypassed damaged by the cleaning process shall be blanked off, or removed.                                                          bypassed, or removed.
Protective screens shall be installed on the suction side of all      Protective screens shall be installed on the suction side of all    Similar requirement pumps and other components that may be subject to damage              pumps and other components that may be subject to damage during the cleaning operations. Instrumentation (e.g., pressure,      during the cleaning operations. Instrumentation (e.g., pressure, temperature and flow) shall be used where possible to monitor        differential pressure temperature, and flow) shall be used as the cleaning operations. All other permanently installed              necessary to monitor flushing and recirculatory cleaning instrumentation shall be isolated where possible.                    operations. Instrumentation installed in the system but not used to monitor the cleaning operations shall be isolated where necessary.
Cleaning should be completed before installation of fuel,            Cleaning of the reactor vessel and reactor vessel internals shall  Similar requirement reactor vessel internals and control rods. Provisions shall be        be completed before installation of fuel and control rods.
made to collect leakage and to protect insulation from being          Provisions shall be made to collect liquid leakage and to wetted. Where the use of installed plant components, such as          prevent wetting of insulation. Where the use of installed plant pumps, may be affected by the cleaning operations,                    components such as pumps may be affected by the cleaning recommendations shall be obtained from the component                  operations, recommendations shall be obtained from the manufacturers regarding the use of their components.                  component manufacturers regarding precautions to be taken for Procedures used to protect installed components which are not        the use of their components. Procedures shall be established to used in the cleaning operations but which are included in the        protect or isolate installed components that could be adversely cleaning circuit should be reviewed,                                  affected by cleaning or flushing operations.
7.2 Flushing and Cleaning Methods                                    8.2 Flushing and Cleaning Methods 7.2.1 Water Flushing..                                                8.2.1 Flushing.
If the intended level of cleanness has been maintained during        If the intended level of cleanness has been maintained during      Similar requirement erection of the plant, only water flushing will be required. The      erection of the plant, only flushing or rinsing will normally be system shall be filled with water of the quality specified and        required. The system shall be filled with fluid of the type and flushed in accordance with approved procedures. Completion of quality specified and flushed in accordance with approved flushing shall be determined by filter, turbidimetric or chemical procedures. Completion of flushing shall be determined by analyses                                                              filter, turbidimetric or chemical analysis, or any combination of these, as applicable.
10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 28 of 35
 
Cleaning of Fluid Systems and Associated ComPonents                  Quality Assurance Requirements for Cleaning of Fluid                  Comments During Construction Phase of Nuclear Power Plants                  Systems and Associated Corpon            for}ucl.r Power.
ANSI N45.2.1 -1973.                                                        Plants      for.Nuclea..Power
____,___,          ________NQA-1-19%9,                                                                Subpart 2.1 If the final flushes for removal of particulate contaminants are    If flushes are directed toward the large components, provisions  Similar requirement directed toward the reactor vessel, soluble contaminants shall      shall be made to prevent contaminants from collecting in areas be removed from the system by first flushing away from the          where they cannot be removed in subsequent cleaning reactor vessel until a specified water quality is achieved on the    operations. Provisions shall be made to assure that organics do effluent from the system. At this time, high velocity flushes        not remain on the surfaces.
may be made toward the reactor vessel. This procedure is not recommended unless reactor vessel internal surfaces are accessible for subsequent mechanical cleaning and inspection, or unless provisions are made to collect particulate contaminants at some accessible location within the reactor vessel by filtration or other technique.
After system flushing is completed, but before system drain, all    After system flushing is completed, but before draining, all      Similar requirement pockets and dead legs shall be flushed through their drain          pockets and dead legs shall be thoroughly flushed. Where connections. If conditioned water is used, particular attention      conditioned water is used, particular attention should be given should be given to assure that large volumes of solution do not      to assure that large volumes of solvent do not remain trapped in remain trapped in the system. Care shall be taken to assure that    the system.
organics do not remain on the surfaces.
A final flush with demineralized water is desirable but is not      After cleaning, the item shall be sealed where appropriate to    Similar requirement necessarily required at this time. The system shall be sealed to    prevent the subsequent entry of contaminants. If no further prevent the subsequent entry of contamination. If no further        cleaning is required, system lay-up shall be performed if cleaning is required, system layup may be performed.                specified.
7.2.2 Alkaline Cleaning.                                            8.2.2 Alkaline Cleaning.
Although it shall be the intent of those involved in erecting the    Although it is the intent of those involved in erecting the      Similar requirement nuclear plant to install piping systems in a clean condition, this  nuclear plant to install piping systems and components in a may not be achieved. One relatively common source of organic        clean condition, this may not be fully achieved. Common contamination in piping systems is lubricating oils from air        sources of organic contamination in items are lubrication oils tools. When local cleanup is not performed following grinding        from air tools, preservative films, and valve lubricants. When operations on internal surfaces of piping welds, full system        immediate local cleanup is not performed, full item cleaning to cleaning to remove organic contaminants may be necessary,            remove such organic contaminants may be necessary.
If required, the cleaning shall be performed according to the        Such cleaning shall be performed according to the cleaning        Similar requirement cleaning procedures established for the operation and the            procedures established for the operation, and the procedure procedure shall assure that quantities of organics do not remain    shall assure that quantities of organic contaminants do not on the surfaces.                                                    remain on the surfaces.
Alkaline cleaning should consist of the circulation of an            Alkaline cleaning consists of the circulation of an appropriately Similar requirement 10/28/2010                                                    Cleaning of Fluid Systems and Associated Components                                  Page 29 of 35
 
SCleaning of Fluid Systems and Associated Components                            .Quality Assurance Requirements for Cleaning of Fluid                          Comments During ConstructionP~hase of Nuclear Power Plants,                              Systems and Associated Components for Nuclear Power AN.SI N.45.2.1 -1973                                                                      P~lants.
___________________________________________NQA-1-1994,                                          Subpart 2.1                      ___________
appropriately heated solution until a selected area or a coupon                  heated solution until a selected area represented by the worst contaminated with the expected contamination is cleaned by the                    contamination or a coupon contaminated with the expected cleaning solution.                                                                contamination is cleaned by the cleaning solution to the specified cleanness level.
After system cleaning is completed, a flush with water of a                      After item cleaning is completed, the item shall be flushed with    Similar requirement quality consistent with the system requirements shall be                          water of the specified quality to remove the cleaning agents. In performed to remove the cleaning agents. In particular, all                      particular, all pockets and dead legs shall be flushed and pockets and dead legs should be flushed and attention should be                  attention given to assure that large volumes of solution do not given to assure that large volumes of solution do not remain in                  remain.
the system.
The system should be sealed to prevent the subsequent entry of                    Where appropriate, the item shall be sealed to prevent              Similar requirement contamination. If no further cleaning is required, system layup                  subsequent contamination. If no further cleaning is required, may be performed. Precautions related to the use of alkaline                      system lay-up shall be performed, if specified. Precautions cleaning solutions are listed in paragraph 7.3.                                  related to the use of alkaline cleaning solutions are listed in Part I1,Subpart 3.2, Appendix 2.1.
7.2.3 Chelate Cleaning.                                                          8.2.3 Chelate Cleaning.
Chelate cleaning of carbon or low-alloy steel surfaces to                        If chelate cleaning is used, attention shall be given to all        Similar requirement, but remove light corrosion product films is not a required cleaning                  pockets and dead legs to ensure that large volumes of solution      changed from operation. If chelating cleaning is used, flushing with water of a                do not remain in the item. Unless it is considered desirable to      recommendations to quality consistent with the system requirements should be                        leave a film of chelating agent on the surfaces as a protective      requirements of NQA-performed to remove the chelating agents. All pockets and dead                    film, the item shall be flushed with water of a quality consistent    1where determined to be legs in particular should be flushed and attention should be                      with the item requirements to remove residual chelating agents.      appropriate.
given to assure that large volumes of the chelating solution do not remain in the system.
The system should be sealed to prevent the subsequent entry of                    Where appropriate, items shall be sealed to prevent subsequent      Similar requirement, but contaminants. If no further cleaning is required, layup may be                    contamination. If no further cleaning is required, lay-up shall be  changed from performed. Precautions related to the use of chelating agents are                performed, if specified. Precautions related to the use of          recommendations to listed in paragraph 7.3.                                                          chelating agents are listed in Part IMI, Subpart 3.2, Appendix      requirements of NQA-1 2.1.                                                                where determined to be appropriate.
7.3 Cleaning Precautions There are a number of precautions that should be observed                                                                                              Recommendations, not during cleaning operations. The following should be considered                                                                                        requirements.
as appropriate.
10/28/2010                                                                  Cleaning of Fluid Systems and Associated Components                                      Page 30 of 35
 
cCi ning of FluidaSystemsnandAssocited Components',                Quality a      Assince aequiirementsvfor Clauing of Fluid              Comments ... ""
During Construction Phase of Nuclear Power Plants                Systems and Associated Components for NuclearPowe.r ANSI N45.2.1 -1973                                                        KPlants
_______________________________________NQA-1-1994,                              Subpart.2.1__________
: 1. The addition of a suitable chloride stress cracking inhibitor is                                                                QAPD Part H, Section 13.2 recommended if fresh water flushing of systems containing                                                                          and Part IV, Regulatory austenitic stainless steels is planned.                                                                                            Guides presents VCSNS' commitment to using a suitable chloride stress-corrosion cracking inhibitor when using fresh water to flush systems containing austenitic stainless steel components.
: 2. The use of alkaline cleaning compounds which contain free caustic is not recommended on components or systems in which cleaning solutions may be entrapped. Cleaners based on compounds which produce hydroxyl ions by hydrolysis, such as trisodium phosphate, are recommended. If heavy organic solids are present, the addition of an emulsifier and a wetting agent may be considered.
: 3. The use of acid-chelating agents on welded or furnace sensitized stainless steels and nickel base alloys is not recommended.
: 4. The use of halogenated organic solvents is not recommended        Precautions related to the use of halogenated organic solvents except upon crevice-free, open, freely-evaporating surfaces.        are presented in Part III, Subpart 3.2, Appendix 2.1.
This recommendation is not intended to prohibit the use of such solvents under other conditions, providing adequate removal is assured prior to any subsequent operations.
: 5. Acid cleaning of installed systems is not recommended.
However, if used, particular attention shall be given to:
(a) Avoiding the entrapment of acids in the crevices.
(b) Avoiding contact with either welded or furnace sensitized corrosion resistant alloys, and non-ferrous materials.
(c) Complete removal of any residual acid solution from the system.
(d) Neutralization treatment as a final operation.
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Cleaning of Fluid Systems and Associated Components'                  Qualty Assurance&#xfd;RequirementsforClan-ing.of.Fluid                        Com ments During Construction Phase of Nuclear Power Plants*,                Systems and Associated Com.ponentsfor Nuclear Power AkNSI N45.2.1 -1973                                                          Plants NQArl-1994, Subpart 2.1 8.0 LAYUP AND POST-LAYUP CLEANING                                    9 LAYUP AND POST-LAYUP CLEANING 8.1 Upon completion of pre-operational cleaning, unless the          Upon completion of preoperational cleaning, unless the item is      Similar requirement system is to be released for the next series of operations or        to be released for the next series of operations or tests, the item tests, the system should be placed in layup condition, if            shall be placed in lay-up condition by filling with dry, required, by filling with dry inert gas, the process fluid that will  contaminant-free inert gas or dry air; the process fluid that will be used in the system during operation, water of purity              be used in the system during operation; fluid of purity equivalent to that used to make up the system, or chemically-        equivalent to that used to make up the system; chemically conditioned water.                                                    conditioned fluid; or other specified method.
8.2 Prior to the next series of operations or tests residual          Prior to the next series of operations or tests, residual cleaning  Similar requirement cleaning solutions or layup chemicals shall be removed from          solutions or lay-up media shall be removed, if required, from the system by flushing, or draining and filling until the effluent    the item by flushing or by draining and filling until the effluent water from the system meets the pre-operational test water            fluid from the item meets the preoperational test fluid quality quality requirements for the system.                                  requirements for the system.
10 POST-OPERATIONAL REPAIRS AND MODIFICATIONS Subpart 2.1 does not address radioactive decontamination            New requirements to operations that may be required prior to post-operational repairs  address operations phase or system modifications, although some of its requirements may      activities.
be applicable to such decontamination Operations. For the purposes of maintenance of cleanness as defined in Subpart 2.1, post-operational repairs or system modifications shall be considered identical to preoperational installation procedures and treated in accordance with Sections 5, 6, and 7.
If system cleaning following repair or modification operations is deemed necessary, such cleaning shall be performed in accordance with Section 8, except that flushes directed toward the reactor vessel shall, to the extent possible, first be preceded with flushes directed away from the reactor vessel until expected contamination is removed and the specified water quality level is achieved. If lay-up is deemed necessary, it shall be performed in accordance with Section 9.
9.0 RECORDS                                                          11 RECORDS Record copies of completed procedures; reports; personnel            The following shall be prepared:                                    Similar requirement qualification records; test equipment calibration records, test      (a) record copies of procedures;(b) reports;(c) test equipment 10/28/2010                                                      Cleaning of Fluid Systems and Associated Components                                    Page 32 of 35
 
Cleaning of Fluid:Systems and Associated components                                    QualityAssurance Requirements for Cleaning of Fluid                    Comments During Construction Phase of Nuclear Power Plants                                    Systems. and Associated Components for Nuclear Power ANSI N45.2.1 -1973                                                                            Planuts
________________________________________NQA44-994,_Subpart                                                  2J1___________
deviation or exception records; inspection and examination                            calibration records;(d) test deviation or exception records;(e) records shall be prepared.                                                            inspection and examination records; (f) other records necessary to document the cleaning and cleanness history of the items during manufacture, shipment, storage, installation, preoperational cleaning, modifications, and repairs.
These shall be placed with other project records as required by                        These records shall be retained with other project records as    Similar requirement code, standard, specification, or project procedures. Collection,                      required by code, standard, specification, or project procedures.
storage and maintenance records shall be in accordance with ANSI N45.2.9.
10.0 REVISION OF ANSI STANDARDS REFERRED TO IN THIS DOCUMENT When the following standards referred to in this document are                                                                                            Commitment to specific superseded by a revision approved by the American National                                                                                              standards will be controlled Standards Institute, the revision shall apply.                                                                                                          through compliance with the regulations regarding QA programs.
N45.2 Quality Assurance Program Requirements for Nuclear Power Plants N45.2.3 Housekeeping During the Construction Phase of Nuclear Power Plants N45.2.6 Qualification of Inspection, Examination, and Testing Personnel for the Construction Phase of Nuclear Power Plants N45.2.9 Requirements for Collection, Storage and Maintenance of Quality Assurance Records
*N45.2.10 Terms and Definitions.
*These Standards are being approved by The American National Standards Institute and they should (will) be available in 1973 Regulatory Guide 1.37, Revision 1, March 2007, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants" Regulatory Guide 1.37, Regulatory Position 3 states that          QAPD Part II, Section 13.2 licensees should follow the precautions in ASME NQA-1-1994,      and Part IV, Regulatory Page 33 of 35 10/2      10 8/2 010 10/28/20 Cleaning of Fluid Systems and Associated Components Cleaning of Fluid Systems and Associated Components                                    Page 33 of 35
 
Cleaning of Fluid Systems and Associated Components                      Quality Assurance Requirements "or.Cleaning            of Fluid          Comments' During  ConstructionPhase
        *.ANSI
            *N..4*: ..,,..*    l.15.2.1of Nuclear
                                          -1973    Power Plants      . Systems    andAssociated
                                                                              **":*: ***              Components Plants        for Nuclear  Power
____________________________________________                    KNQA-4t-199.4,Subpar-t,,2 1 Part 1H, Subpart 3.2, Nonmandatory Appendix 2. 1, "Guidance      Guides presents VCSNS' on Cleaning of Fluid Systems and Associated Components for      commitment to Regulatory Nuclear Power Plants."                                          Guide 1.37.
7.3 Cleaning Precautions, Item 1. The addition of a suitable            Regulatory Guide 1.37, Regulatory Position 3 recommends          QAPD Part H, Section 13.2 chloride stress cracking inhibitor is recommended if fresh water        using a suitable chloride stress-corrosion cracking inhibitor    and Part IV, Regulatory flushing of systems containing austenitic stainless steels is            when using fresh water to flush systems containing austenitic    Guides presents VCSNS' planned.                                                                stainless steel components.                                      commitment to using a suitable chloride stress-corrosion cracking inhibitor when using fresh water to flush systems containing austenitic stainless steel components.
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TABLE 3,2
 
==SUMMARY==
TAILE FOR CLEANNESS CtASS de" A L~o~f41,0s rondag1o4rwam                      41 4                              Ha                    pims  NR *v    ~              Nit    SpcI~d ins A
II ckan4wow 4Jqt Ovck          M4IA do=u                          HR                    No paiblfeflu                  A$f*          in If      fedw                        pn*od                z Ck, B C~AMMI~hew~ 4c"                    MewiI df    6w
* SQ ds/1eq*                        NR                      HR      No PmAcfrt          Q (14 CnOMW      W6*                                                I% X 1*    IM a IM )c 1.6 ama 310 Catx3. jM kww AJw Ot              tvWdu        but          2 to      64~ ftqf            No P~nMi                      H&    No pMakk'S N~OW (II                            woth .w.w Urb              &fk    ft                      -fatdw                            Wse ihm bii          -4.
awl/ODO n                I SPe"                              ir*
K. x Ins in, I"      2 M    x 3.6 nvw dew C Ounto        mow      akwbw.          is Sq WA~ #q A*                      MM                            No paetkim          ol Mn. x 1I    mail oI Catmo and low aloy swds            Nw *M~e                  uOaiw    Wh                    H p~in ka                            MR    bb pmc 9 spa'drkd                          RLX16 W WTA MRax I[6 awo CUMwD qWedfioby                                                                                      Lv anuIm 1/16 IO In. X ia 6L. (1,6 mm x 1. nmw CuAAW NJd IGW alykeM'              MRos UN&M                          KAh~H                Ae~~                      AaVPUji4Pl  Wopasddes wftl*d by                                                                          If aM1rtMe Larw iMi 111 NR -    o nq        t NOTE; (11VWblte C1,9 A aid 6 &mftvu fr-s ttcise I* "Ond on twiadwo ad bw dio* ttoel swiax. umalitaiwfu dhfrku-" Aui~anw of Oaim A aid R lev# tb bwh w~wos iiimi bo, ei,4. aiih 40c~utln of Owwkeieleis k wy I
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Packaging, Shipping, Receiving, Storage And Handling_.            Qualiy Assurance Requirements for Packaging, Shiping,                    Com. ents Of Items For Nuclear Power Plants                        Receiving, Storage, and Hanlg ofIesfo                ula uring The Construction 'Phase)                                              P      ndlingofItems PNuclear      for N45.2.2 1972          "                                      NQA4 19"    4 Subpart 2.2.
: 1. INTRODUCTION                                                      1 GENERAL 1.1 Scope This standard defines requirements for packaging, shipping,          Subpart 2.2 provides amplified requirements for packaging,      Similar requirement.
receiving, storage, and handling of nuclear power plant items.      shipping, receiving, storage, and handling of nuclear power      NRC position is that the These items include the parts of structures, systems, and            plant items. It supplements the requirements of Part I and shall ANSI standard applies to components whose satisfactory performance is required for the        be used in conjunction with applicable Basic and                the operations phase in plant to operate reliably, to prevent accidents that could cause    Supplementary Sections of Part I when and to the extent          addition to construction.
undue risk to the health and safety of the public, or to mitigate    specified by the organization invoking Subpart 2.2.              NQA-1 makes this Subpart the consequences of such accidents if they were to occur. The                                                                        applicable to all phases of requirements stated herein deal with the protection and control                                                                      the facility's life, from necessary to assure that the requisite quality of those important                                                                    siting and design through parts of the plant arc preserved from the time items are                                                                              decommissioning.
fabricated until they are incorporated in the plant.
This standard is intended to be used in conjunction with ANSI N45.2, Quality Assurance Program Requirements for Nuclear Power Plants. The requirements may also be extended to other appropriate parts of nuclear power plants when specified in contract documents.
NRC Regulatory Guide 1.38 Regulatory Position C. 1. The requirements for the packaging, shipping, receiving, storage, and handling of items for water-cooled nuclear power plants that are included in ANSI N45.2.2-1972, "Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants During the Construction Phase,"(2) are acceptable to the NRC staff and, when supplemented by the guidelines identified in Regulatory Position 2, provide an adequate basis for complying with the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50, subject to the following:
: d. Although ANSI N45.2.2-1972 is entitled "Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants During the Construction Phase," the requirements included in the standard are considered to be applicable during the operation phase and should be used, where applicable, consistent with the recommendations of this regulatory guide.
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Packaging, Shipping, Receiving, Storage And Handling                Quality Assurance Requirements for Packnagin. Shipping,          Commen        ""ts Of Items For Nuclear-Power Plants                          Receiving, Storage, and Handlingof Items for Nuclear                              .
(During The Construction Phase)                    .                          Power Plants N45.2.2 1972                                                  NQA-1 14,Subpart 2.2 1.2 Applicability The requirements of this standard apply to the work of any            See NQA-1-1994 Part II Introduction for Applicability. Similar requirement.
individual or organization that participates in the packaging, shipping, receiving, storage and handling of items to be incorporated into nuclear power plants as discussed in Subsection 1.1 of this standard. The extent to which the individual requirements of this standard shall apply will depend upon the nature and scope of the work to be performed and the importance of the item or service involved. The requirements are intended to assure that the quality of items is not degraded as a result of packaging, shipping, receiving, storage, and handling practices and techniques.
1.3 Responsibility The organization or organizations responsible for establishing        See NQA1-1994 Part II Introduction for Responsibility. Similar requirement.
the applicable requirements for the activities covered by this standard shall be identified and the scope of their responsibilities shall be documented. The work of establishing practices and procedures and providing the resources in terms of personnel, equipment and services necessary to implement the requirements of this standard may be delegated to other organizations and such delegation also shall be documented.
However, it is the responsibility of each organization performing work covered by this standard to comply with the procedures and instructions issued for the project and to conform to the requirements of this standard applicable to his work.
The following shall be used as a guide in determining those                                                                    Guidance in NQA-I is not responsibilities which shall be established and documented:                                                                    as specific to this subpart.
: 1. Classification of items (protection level)
: 2. Packaging design and methods                                                                                                Packaging, Shipping,
: 3. Shipping requirements and methods                                                                                          Receiving, Storage and
: 4. Receiving requirements and methods                                                                                          Handling Of Items For
: 5. Storage requirements and procedures                                                                                        Nuclear Power Plants is
: 6. Handling requirements and procedures                                                                                        addressed in QAPD, Part II,
: 7. Records                                                                                                                    Section 13.
1.4 Definitions                                                      1.1 Definitions 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                Page 2 of 43
 
Packaiging, shiaiigeceiaing Storage      a AndHandling          Quality Assurance Requirements for Packaging, Shipping,                  Conmments Of Items For Nuclear Power.Plants                      Receiving, Storage, and Handling of itemsf.f.Nuclear (During The Construction.Phase)                                                Power Plants........        ....
N45.2.2 1972.                                              NQA-1 1994:Subpart 2.2 The following definitions are provided to assure a uniform          The following definitions are provided to assure a uniform        See NQA-1, Part I understanding of select terms as they are used in this standard. understanding of unique terms as they are used in Subpart 2.2. Introduction for additional definitions.
Barrier - A flexible material designed to withstand the            barrier - a flexible material designed to withstand the          Similar requirement.
penetration of water, water vapor, grease, or harmful gases.        penetration of water, water vapor, grease, or harmful gases Carrier - The transporting agency.                                  carrier - the transporting agency                                Similar requirement.
Classification - The organization of items according to their      classification - the organization of items according to their    Similar requirement.
susceptibility to damage during shipping, receiving and storage    susceptibility to damage during shipping,, receiving, and storage only. It does not relate to the function of the item in the        only. It does not relate to the function of the item in the completed system.                                                  completed system.
Documentation - Any written or pictorial information                Definition in Part I is similar in wording.                      Similar requirement.
describing, defining, specifying, reporting, or certifying activities, requirements, procedures or results.
Dynamic Load Test - A test to demonstrate the ability of            dynamic load test - a test wherein designated loads are hoisted,  Similar requirement.
hoisting equipment to safely handle its rated load by exercising    rotated, or transported through motions and accelerations the equipment through vertical and horizontal movement along        required to simulate handling of the intended item its lines of travel, using a load of specified weight.
Handling - The act of physically moving items by hand or by        See Subpart 2.15 for this definition. 2.15 limits the term to use The handling information mechanical machinery, not including transport modes.                of equipment for handling,                                        from this standard has been added to Subpart 2.15.
Item - Any level of unit assembly, including system, subsystem,    Definition in Part I is similar in wording.                      Similar requirement.
subassembly, component, part, or material.
Nonconformance - A deficiency in characteristic,                    Definition in Part I is similar in wording.                      Similar requirement.
documentation, or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformance include: physical defects, test failures, incorrect or inadequate documentation, and deviation from prescribed processing, inspection or test procedures.
Package - The shipping container plus the contents of the                                                                            Not defined in NQA- 1 container.
Package Unit - Any assembly of mechanical and/or electrical                                                                          Not defined in NQA-I components and parts which can be disassembled without destroying the integrity of the individual parts.
Receiving - To take delivery of material at the construction site  Definition in Part I is similar in wording.                      Similar requirement.
or other location designated by the purchaser.
Storage - The act of holding items at the construction site or in  storage - the act of holding items in storage facilities          Similar requirement.
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Packaging, Shipping, Receiving, Storage Ad Handling                Quality Assurance Reuiements for Packaging, Shipping,                    Comnments Of Items For Nuclear Por.Plan.                            Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)I.                                                Power Plants.......
N45.2.2 1972                                                    N -A-i1994    Subpart 2.i2.
an area other than its permanent location in the plant.
Storage Facilities - Warehouse or yard area designated and            storage facilities - warehouse, yard, or other areas designated  Similar requirement.
prepared for holding of items.                                        and prepared for holding of items Transit Carrier (Open) - Trucks, Trailers, Railroad cars,                                                                              Not defined in NQA-1 Barges, Aircraft, or Ships which do not provide protection of items from the environment.
Transit Carrier (Closed) - Trucks, Trailers, Railroad cars,                                                                            Not defined in NQA-1 Barges, Aircraft or Ships which do provide protection of items from the environment by nature of their inherent design.
Transportation Mode - A method identified by the conveyance            transportation mode - a method identified by the conveyance      Similar requirement.
used for transportation of items and includes any motor                used for transportation of items and includes any motor vehicles, ships, railroad cars, or aircraft. Each cargo-carrying      vehicles, ships, railroad cars, or aircraft. Each cargo carrying body (trailer, van, box car, etc.) is a separate vehicle.              body (trailer, van, boxcar, etc.) is a separate vehicle.
Wrap - A flexible material, formed around the item or package          wrap - a flexible material formed around the item or package to  Similar requirement.
to exclude dirt and to facilitate handling, marking or labeling.      exclude dirt and to facilitate handling, marking, or labeling Other terms and their definitions are contained in ANSI                Not stated in this subpart, but note that other definitions are N45.2.10.                                                              contained in Part I, Introduction and other Subparts.
1.5 Referenced Documents Other documents that are required to be included as a part of                                                                          The QAPD addresses the this standard are either identified at the point of reference or                                                                        standards for the program.
described in Section 9 of this standard. The issue or edition of the referenced document that is required will be specified either at the point of reference or in Section 9 of this standard.
NRC Regulatory Guide 1.38 Regulatory Position C. .a. Subdivision 1.5 of ANSI N45.2.2-1972 states that other documents required to be included as a part of this standard are either identified at the point of reference or described in Section 9 of the standard. The specific acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations where appropriate.
: 2. GENERAL REQUIREMENTS                                                2 GENERAL REQUIREMENTS This section contains requirements that are to be fulfilled by the    Measures shall be established and implemented for the            Similar requirement.
organization or organizations responsible for performing any          packaging, shipping, receiving, storage, and handling of segment of work described in Sections 3 through 8 of this              specified items to be incorporated in the nuclear power plant, standard,                                                              and for the inspection, testing, and documentation to verify 10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                      Page 4 of 43
 
Packaging, Shipping, Receiving Storage And Handling'              QQuality Ass1urance Requirements for Packagi
            .Of Items For Nuclear Power Plants                          Receiving, Storage, andHanidlinggof Items I (During The Construction Phase)                                              'Power Plants.
j%445.2.2..1972.                                          NOA-I1 994.Suboart 2.2 Measures shall be established and implemented for the                conformance to specified requirements.
packaging, shipping, receiving, storage and handling of specified items to be incorporated in the nuclear power plant and for the inspections, examinations, testing and documentation to verify conformance to specified requirements.
2.1 Planning                                                        2.1 Planning and Procedures The specific items to be governed by this standard shall be          Planning and procedure preparation shall be in accordance with Similar requirements in the identified. Planning shall take into account the need for the        the requirements of the introduction to this Part (Part II). referenced section of NQA-preparation and control of procedures and work instructions as                                                                      1.
necessary to comply with specified requirements. Planning shall                                                                    Procedures are addressed in include a review of the design specifications and drawings for                                                                      QAPD Part II, Section 5.
the items covered by this standard to assure that packaging, shipping, receiving, storage, and handling activities have been incorporated and that they can be accomplished as specified.
2.2 Procedures and Instructions Procedures and instructions shall be generated, used, and            See NQA-1-1994 Part II Introduction for Procedures.            Similar requirements in the maintained current; these shall contain sufficient detail to                                                                        referenced section of NQA-provide for the listed items (See Subsection 2.1 of this                                                                            1. Procedures are addressed Standard) a basis for packaging design, shipping requirements,                                                                      in QAPD Part II, Section 5.
receiving, storage and handling procedures, implementation thereof, and inspection, in accordance with this standard.
2.3 Results Inspection and test results shall be documented in a suitable test                                                                  Documentation of report or data sheet.                                                                                                              inspection and test results is Each report shall identify the item to which it applies, the                                                                        addressed in Part I of NQA-procedures or instruction followed in performing the task and                                                                        1, Basic Requirements 10 the identification of the following:                                                                                                and 11.
(1) Conditions encountered which were not anticipated, including nonconformance.
(2) Identity of inspector or tester.
(3) Completion date.
Test reports and data sheets shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation.
2.4 Personnel Qualifications Those personnel who perform inspection, examination or testing                                                                      Qualification is covered by 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                      Page 5 of 43
 
Packaging, Ship ping, Receiving, Storage And Handling              Qualit&#xfd; Assurance Requirementsfor Packiging, Shipping,R                      Commeuts]
Of Itemrs For Nuclear Power Plants                        Receiving, Storage, and Handling of ftems for Nuclear.
(During The Construction Phase)                                                  Iower Planrts N45.2.2 1972                                                  N1A71.194 SubprtaZ22 activities at the job site shall be qualified in accordance with                                                                          NQA-1, Part I, Supplement N45.2.6. Off-site inspection, examination or testing shall be                                                                              2S-1, and Part III, Appendix audited and monitored by personnel who are qualified in                                                                                    2A-1.
accordance with N45.2.6.
2.5 Measuring and Test Equipment                                                                                                          M&TE is covered by NQA-I Part I, Requirement 12, and Part II, Subpart 2.16, and contain similar requirements to N45.2.2.
2.5.1 Selection.
Inspection, examination, and testing equipment utilized to implement the requirements of this standard shall be selected to have accuracy and tolerance sufficient to determine conformance to specified requirements.
2.5.2 Calibration and Control.
As appropriate, measuring and test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards. If no national standards exists, the basis for calibration shall be documented. Records shall be maintained and equipment suitably marked to indicate calibration status.
2.6 Housekeeping In job-site areas, facilities, and environments where packaging,                                                                          Housekeeping is covered by shipping. receiving, storage and handling of items is performed                                                                            NQA-1, Part II, Subpart 2.3 in accordance with the requirements of this standard, the housekeeping requirements shall be in accordance with N45.2.3.
2.7 Classification of Items                                          2.2 Classification of Items The requirements for activities covered by this standard              Requirements are divided into four levels with respect to            Similar requirement.
(packaging, shipping, receiving, storage and handling) are            protective measures to prevent damage, deterioration, or divided into four levels with respect to protective measures to      contamination of the items based upon the important physical prevent damage, deterioration or contamination of the items,          characteristics, and not upon the important functional based upon the important physical characteristics and not upon        characteristics of the item with respect to safety, reliability, and the important functional characteristic of the item with respect      operation.
to safety, reliability and operation.
It should be recognized, however, that within the scope of each      It should be recognized, however, that within the scope of each      Similar requirement.
level there may be a range of controls and that the detailed          level there may be a range of controls, and that the detailed 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                            Page 6 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                "Quality Assurance Requirenmetnts for Pack            ng Shipping              Commen Of Items For Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear...........
(During The Construction Phase)                                                    Power Plants N45.2.2,1972                                                    NQA-1 19941 Sbpart2.42 requirements for an item are dependent on the importance of the        requirements for an item are dependent on the importance of the item to safety or reliability. For example, even though a reactor      item to safetyreliability. For example, even though a reactor vessel and structural steel are classified as level D, the degree of  vessel and structural steel are classified as Level D, the degree protection and control over the reactor vessel should exceed that      of protection and control over the reactor vessel should exceed of the structural steel. Each of the specific items governed by        that of the structural steel. Each of the specific items governed this procedure (See Subsection 2.1 of this standard) shall be          by Subpart 2.2 shall be classified into one of these four levels classified into one of these four levels by the buyer or              by the buyer or the contractor.
contractor.
The manufacturer's documented standard or minimum                      The manufacturer's documented standard or minimum                    Similar requirement.
requirements shall be considered when classifying the items.          requirements shall be considered when classifying the items.
Items, once classified, shall be restricted to the level or higher    Items, once classified at a level, shall be restricted to that level for each of the packaging, shipping, receiving, storage and            or a higher level for each of the packaging, shipping, receiving, handling operations. Items shall not be classified according to        storage, and handling operations. Any package unit or assembly the requirements of one level, then packaged, shipped, received,      made up of items of different levels shall be classified to the stored or handled according to a level of lower grade. Any            highest level designated for any of the respective items. If the package unit or assembly made up of items of different levels          unit is disassembled, a level shall be indicated for each part.
shall be classified to the highest level designated for any of the respective parts. If the unit is disassembled, a level shall be indicated for each part. When the unit cannot be physically disassembled, special rules are contained herein.
Items covered by this standard shall be categorized under the          Items covered by Subpart 2.2 shall be categorized under the          Similar requirement.
following levels:                                                      following levels.
2.7.1 Level A -Items classified to level A are those that are          2.2.1 Level A. Items classified to Level A are those that are        Similar requirement.
exceptionally sensitive to environmental conditions and require        exceptionally sensitive to environmental conditions and require special measures for protection from one or more of the                special measures for protection from one or more of the following effects:                                                    following effects:
temperatures outside required limits,                                  (a) temperatures outside required limits                              Similar requirement.
sudden temperature changes,                                            (b) sudden temperature changes                                        Similar requirement.
humidity and vapors,                                                  (c) humidity and vapors                                              Similar requirement.
gravitational (g) forces,                                              (d) accelerating forces                                              Similar requirement.
physical damage                                                        (e) physical damage                                                  Similar requirement.
and airborne contamination (e.g. rain, snow, dust, dirt, salt          (f) airborne contamination (e.g., rain, snow, dust, dirt, salt spray, Similar requirement.
spray, fumes).                                                        fumes)
The following shall be used as a guide for classifying items          Types of items to be categorized under this classification level      Similar requirement.
intended for this level classification:                                are:
(1) Special electronic equipment and instrumentation.                  (a) special electronic equipment and instrumentation                  Similar requirement.
10/2/200            PckagngShiping ReeivngStorgeandHandingof temsPag                                              7 f4 10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                            Page 7 of 43
 
Packaging, Shipping, Receiving, Storage And Handling              QualityAss* uranc"  "e      e""                    'fo..,Shippin,              Comments
              -OfItems.For Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear (Durig The Construction Phase)                                                  Power Plants..........
N45.2.2 1972                                                  NQA-. 1994 Subpart 2.2,        ,. ....      *.....          _____.
(2) Special materials, such as chemicals that are sensitive to      (b) special materials, such as chemicals, that are sensitive to          Similar requirement.
environment,                                                        environment (3) Special nuclear material (fuel) and sources. The                (c) special nuclear material and sources.                                Similar requirement.
requirements of the AEC fuel license and conditions and other        The requirements of the NRC fuel license and conditions and of governmental agencies shall be met.                                  other governmental agencies shall be met.
2.7.2 Level B -Items classified to level B are those that are        2.2.2 Level B. Items classified to Level B are those that are            Similar requirement.
sensitive to environmental conditions and require measures for      sensitive to environmental conditions and require measures for protection from the effects of temperature extreme, humidity        protection from the effects of temperature extremes, humidity and vapors, g-forces, physical damage and airborne                  and vapors, accelerating forces, physical damage, and airborne contamination and should not require special protection required    contamination, and do not require special protection required for for level A items.                                                  Level A items.
The following shall be used as a guide for classifying items        Types of items to be categorized under this classification level          Similar requirement.
intended for this level classification:                              are (1) Instrumentation                                                  (a) instrumentation                                                      Similar requirement.
(2) Electrical penetrations                                          (b) electrical penetrations                                              Similar requirement.
(3) Batteries                                                        (c) batteries                                                            Similar requirement.
(4) Welding electrode and wire                                      (d) welding electrode and wire (Welding electrodes hermetically NQA- 1 added clarifying sealed in metal containers may be stored under conditions                information in parentheses.
described for Level C, unless other storage requirements are specified by the manufacturers.)
(5) Control rod drives                                              (e) control rod drives                                                    Similar requirement.
(6) Motor control centers, switchgear and control panels            (f) motor control centers, switchgear, and control panels                Similar requirement.
(7) Motors and generators                                            (g) motors and generators                                                Similar requirement.
(8) Precision machined parts                                        (h) precision machine parts                                              Similar requirement.
(9) Erection spares, such as gaskets, "0" rings                      (i) spares, such as gaskets, O-rings                                      Similar requirement.
(10) Air handling filters                                            (j) air handling_filters                                                  Similar requirement.
(11) Computers                                                      (k) computers                                                            Similar requirement.
2.7.3 Level C - Items classified to level C are those that require  2.2.3 Level C. Items classified to Level C are those that require        Similar requirement.
protection from exposure to the environment, airborne                protection from exposure to the environment, airborne contaminants, g-forces and physical damage. Protection from          contamination, acceleration forces, and physical damage.
water vapor and condensation is not so important as that for        Protection from water vapor and condensation is not as Level B items.                                                      important as for Level B items.
The following shall be used as a guide for classifying items        Types of items to be categorized under this classification level          Similar requirement.
intended for this level classification:                              are                                                                  t'_I 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                                  Page 8 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                  Qualit*Assurance Requirements for Packaging, ShippCg,                                C.omments        .
Of items For Nuclear Power Plants                              Receiving, Storage, and Handling of Items for Nuclear igThe Construction Phase'),
(D                                                                                Power Plan~ts            ~.:*
N45.2.2 1972                                                        NQA-4 194 Subpart 2.2            ..    .~
1)Pumps                                                                (a) pumps                                                              Similar requirement.
(2) Valves                                                              (b) valves                                                              Similar requirement.
(3) Fluid filters                                                        (c) fluid filters                                                      Similar requirement.
(4) Reactor internals                                                  (d) reactor internals                                                  Similar requirement.
(5) Compressors                                                          (e) compressors                                                        Similar requirement.
(6) Auxiliary Turbines                                                  (f) auxiliary turbines                                                  Similar requirement.
(7) Instrument cable                                                    (g) instriunent cable (unjacketed)                                      NQA-l adds unjacketed.
(8) Refueling equipment                                                  (h) refueling equipiment                                                Similar requirement.
(9) Thermal insulation                                                  (i) thermal insulation                                                  Similar requirement.
(10) Fans and blowers                                                    ()fans and blowers                                                      Similar requirement.
(11) Cement                                                              (k) cement                                                              Similar requirement.
________________________________________(1) fabricated fuel rods and assemblies                                                Added in NQA-lI -1994.
2.7.4 Level D - Items classified to Level D are those that are          2.2.4 Level D. Items classified to Level D are those that are less      Similar requirement.
less sensitive to the environment than level C. These items              sensitive to the environment than those for Level C. These items require protection against the elements airborne contamination,          require protection against the weather, acceleration forces, and physical damage.                                                    airborne contamination, and physical damage.                            ____________
The  following shall be used as 10/28/201                        a guide*."....**,,*,.'*"
                              *"::        for classifying items
                                                            ..          Types    of itemsRecivig, Packaging,'**:.&deg;..*.,
                                                                  '.*:,        Shipping,!*"*to be': categorized torge under this classification an Handlin    of Items.. level Similar requirement.
Page 9 of..43 intended for this level classification:                                  are:                                                                    _____________
(1) Tanks                                                                (a) tanks                                                              Similar requirement.
(2) Heat exchangers and parts                                            (b) heat exchangers and parts                                          Similar requirement.
(3) Accumulators                                                        (c) accumulators                                                        Similar requirement.
(4) Demnineralizers                                                      (d) demnineralizers                                                    Similar requirement.
(5) Reactor vessel                                                      (e) reactor vessel                                                      Similar requirement.
(6) Evaporators                                                          (f) evaporators                                                        Similar requirement.
(7) Steam generators                                                    (g) steam generators                                                    Similar requirement.
(8) Pressurizer                                                          (h) pressurizers                                                        Similar requirement.
(9) Piping                                                              (i) piping _Similar                                                                  requirement.
(10) Electrical cable                                                    (I) electrical cable (jacketed)                                        NQA-l adds jacketed.
(11) Structural items                                                    (k) structural items                                                    Similar requirement.
(12) Reinforcing steel                                                  (1)reinforcing steel.                                                  Similar requirement.
(13) Aggregates                                                          (mn)aggregates                                                          Similar requirement.
: 3. PACKAGING                                                            3 PACKAGING 3.1 General                                                              3.1 General_____________
This section contains the requirements for packaging of items            This Section contains the requirements for packaging of items          Similar requirement.
for protection against corrosion, contamination, physical                for protection against corrosion, contamination, physical_____________
10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                                    Page 9 of 43
 
Packaging,, Shippi g, Receiving, StorageAnd"Handling                    Quality Assurance Requiremeints for Packaging, Shipping,                "      9mments Of Items For Nuclear Power Plants                            Receiving, Storage, and Hadln of Items for Nuclear
              .(During The Construcetion Phase).PwrPat N45.2.2: 1972                                                    NA119.upr                  .
damage or any effect which would lower the quality or cause              damage, or any effect that would lower the quality or cause the the item to deteriorate during the time it is shipped, handled and      items to deteriorate during the time they are shipped, handled, stored. The degree of protection specified will vary according to        and stored. The degree of protection specified will vary storage conditions and duration, shipping environment, and              according to conditions and duration of storage, shipping handling conditions.                                                    environment, and handling conditions.
Implementation of this packaging section is accomplished by              Implementation of this Section is accomplished by identifying          Similar requirement.
identifying the item and the appropriate packaging level, and            the item and the appropriate packaging level, and then applying then applying the appropriate criteria contained herein                  the appropriate criteria contained herein concerning cleaning, concerning cleaning, preservatives, desiccants, inert gas                preservatives, desiccants, inert gas blankets, cushioning, caps blankets, cushioning, caps and plugs, barrier and wrapping              and plugs, barrier and wrapping materials, tapes, blocking and materials, tapes, blocking and bracing, containers, marking,            bracing, containers, marking, other quality assurance provisions, other quality assurance provisions and documentation.                    and documentation.
Appendix A-3 contains additional requirements generally not                Note: NQA-l places the equivalent information from                  Similar requirement.
available in other documents. These requirements are a                      N45.2.2, Appendix within the text section and doesn't use an        Wording from N45.2.2 mandatory part of this standard.                                            Appendix. To provide consistent comparison, Appendix A-3            regarding additional Appendix A3* Packaging                                                  information in the N45.2.2 column is placed in order of the          requirements found in The following are additional minimum requirements to be                paragraphs similar to the layout of NQA-1. Those sections in        Appendix.
used with the rules of Section 3, of N45.2.2: "Packaging,              the N45.2.2 column starting with an A are the Appendix Shipping, Receiving, Storage and Handling of Items for                  paragraphs.
Nuclear Power Plants".
NOTE: *The paragraph numbers contained herein are not sequential but correspond to the respective paragraph of section 3 of this standard where they are referenced.
3.2 Levels of Packaging                                                  3.2 Levels of Packaging The packaging requirements are based on the protection the              The packaging requirements shall be based on the protection            Similar requirement.
items should receive during shipping, handling, and storage.            that is necessary during shipping, handling, and storage of the The requirements of this standard are intended to be in addition        item to satisfy Levels A, B, C, and D protection requirements to industry classification or tariff rules for rail, truck, air and      set forth below. The requirements herein are intended to be in water shipments and regulatory agency rules already established          addition to industry classifications or tariff rules for rail, truck, in the transportation industry and in no way are they intended to        air, and water shipments and regulatory agency rules already reduce the minimum standards established by these regulatory            established in the transportation industry; and in no way are agency rules.                                                            they intended to reduce the minimum standards established by these regulatory agency rules.
The following packaging criteria are divided into four levels            The following packaging criteria are divided into four levels          Similar requirement.
corresponding to the categories of Subsection 2.7 of this                corresponding to the classification categories of para. 2.2 of Standard.                                                                Subpart 2.2                                                          1 10/28/2010                                                        Packaging, Shipping, Receiving, Storage, and Handling of Items                              Page 10 of 43
 
Packaging, Shipping, Receiving, Storage And Hadling                        Quality AssurnceRequirementsafor Packagng, Shipping,                        Comments Of Items For Nuclear Power Plants                                  Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase'                                                        Power Plants N45.2.2 1972                                                          NQA- U1994-Subpart 2.2 3.2.1 Level A Items. (See Paragraph 2.7. 1). Level A items                  3.2.1 Level A Items. (See para. 2.2. 1.) Level A items require    Similar requirement.
require the highest degree of protection and shall conform to the            the highest degree of protection and shall conform to the followini criteria:                                                          following criteria (1) Package design requirements are for extraordinary                        (a) Package design requirements shall be for extraordinary        Simlilar requirement.
environmental protection to avoid the deleterious effects of                environmental protection to avoid the deleterious effects of shock and vibration, to control temperature or humidity within              shock and vibration, to control temperature or humidity within specified limits, or for any other special requirements.                    specified limits, or for any other special requirements.
(2) Items shall have been inspected for cleanness immediately                (b) Items shall have been inspected for cleanness immediately      Sim-ilar requirement.
before packaging. Dirt, oil residue, metal chips or other form of            before packaging. Dirt, oil residue, metal chips, or other forms contamination shall have been removed by approved cleaning                  of contamination shall have been removed by approved cleaning methods. Any entrapped water shall have been removed,                        methods. Any entrapped water shall have been removed.
(3) Items which are not immediately packaged shall be                        (c) Items which are not immediately packaged shall be protected    Similar requirement.
protected from contamination,                                                from contamination_____________
(4) All Items shall be packaged with a barrier (See Subsection              (d) Items requiring protection from water vapor, salt air, dust,  Similar requirement.
3.6 of this Standard) so that water vapor, salt air, dust, dirt and          dirt, and other forms of contamination penetrating the package other forms of contamination do not penetrate the package.                  shall be packaged with a barrier (see para. 3.6).
(5) Items shall be packaged in containers of crates (See                    (e) Items which require protection from damage during shipping    Similar requirement.
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Subsection 3.7 of this Standard).                                            and handling shall be packaged in containers or crates (see para.
3.7).
(6) Items which can be damaged by condensation trapped within (f) Items which can be damaged by condensation trapped within                    Similar requirement.
the package shall be packaged with approved desiccant (See                  the package shall be packaged with approved desiccant (see Paragraph 3.6.3) inside the sealed water-vapor-proof barrier or              para. 3.6.3) inside the sealed water- and vapor-proof barrier or by an equivalent method (for example, see paragraph 3.6.2).                  by an equivalent method (for example, see para. 3.6.2).
(7) All openings into items shall be capped, plugged or scaled              (g) All openings into items shall be capped, plugged, or sealed    Similar requirement.
(See Subsection 3.5 of this Standard). Weld end preparations                (see para. 3.5). Weld end preparations shall be protected against shall be protected against corrosion and physical damage.                    corrosion and physical damage (8) Items packed in containers shall be blocked, anchored,                  (h) Items packed in containers shall be blocked, anchored,        Similar requirement.
braced and/or cushioned (See Subsection 3.8 of this Standard)                braced, or cushioned (see para. 3.8) to prevent physical damage to prevent physical damage to the item or barrer.                            to the item or barrier.
(9) Items and their containers shall be identified by marking                (i) Items and their container shall be identified by marking (see  Similar requirement.
(See Subsection 3.9 of this Standard).                                      para. 3.9).
3.2.2 Level B Items. (See Paragraph 2.7.2) Level B items                    3.2.2 Level B Items. (See para. 2.2.2.) Level B items require a    Similar requirement require a high degree of protection and the package shall be                high degree of protection, and the package shall be designed to designed to avoid the deleterious effects of shock, vibration,              avoid the deleterious effects of shock, vibration, physical physical damage, water vapor, salt spray, condensation and                  damage, water vapor, salt spray, condensation, and weather weather durnn shipping, handling and storage.                                during shipping, handling, and storage.                          ____________
10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                                Page I11 of 43
 
            .Packaging, Shipping, Receiving, Storage And Handling            Qualt"      ssurance Requirements for Packaging, Shipping,                        Comments Of Items For Nuclear Power Plants                          Rec~eiving, Storage, and Handlin~g of Items for Nuclear
                  .(During Th. Construction Phase)                                                      Power Plants
                  -          N0.2.241972                                                      NQA-1 1994 Subpart 2.2 This packaging shall be equivalent to that for Level A except            This packaging shall be equivalent to that for Level A, except        Similar requirement.
that the extremes of paragraph 3.2.1 (1) need not apply.                  that the package design requirements need not be equivalent to satisfy the level of extraordinary environmental protection indicated in para. 3.2.1(a) where such protection is not justified.
Level B items such as control panels or similar special items            Shipment of Level B items in fully enclosed vehicles or              Similar requirement.
may be shipped with a minimum of protection when transported equivalent protective enclosure or packaging is acceptable, in a fully enclosed furniture type van with special suspension,          provided the above-stated high degree of protection for Level B provided the shipment goes through to destination in the                  items is maintained throughout shipment, and the shipment goes original vehicle and Level B storage facilities are available at          through to destination in the original vehicle and Level B the site.                                                                storage facilities are available on site. If transfer becomes necessary to transit, transfer procedures shall be subject to purchaser acceptance.
3.2.3 Level C Items. (See Paragraph 2.7.3) Level C items                  3.2.3 Level C Items. (See para. 2.2.3.) Level C items require        Similar requirement.
require protection from exposure to salt spray, rain, dust, dirt,        protection from exposure to salt spray, rain, dust, dirt, and other and other airborne and windblown contaminants. Protection                contaminants. Protection from water vapor and condensation is from water vapor and condensation is less important than for              less important than for Level B items.
Level    B  items.
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The following criteria shall apply:                                      The following criteria shall apply.                                  Similar requirement.
(1) Criteria (2) (3) (5) (7) (8) and (9) for Level A items (See          (a) Criteria (b), (c), (e), (g), (h), and (i) for Level A items (see Similar requirement.
Paragraph 3.2. 1) shall apply to Level C items.                          para. 3.2. 1) shall apply to Level C items._____________
(2) Items shall be packaged with a waterproof enclosure so that          (b) Items shall be packaged with a waterproof enclosure so that      Similar requirement.
water, salt spray, dust, dirt, and other forms of contamination do        water, salt spray, dust, dirt, and other forms of contamination do not penetrate to the item.                                                not penetrate to the item..
(3) Items subject to detrimental corrosion, either intemnal or            (c) Items subject to detrimental corrosion, either internal or        Similar requirement.
extemnal, shall be suitably protected.                                    external, shall be suitably protected 3.2.4 Level D Items. (See paragraph 2.7.4) Level D items                  3.2.4 Level D Items. (See para. 2.2.4.) Level D items require        Similar requirement.
require protection from physical and mechanical damage.                  protection from physical and mechanical damage.
The following criteria shall apply:                                      The following criteria shall apply                                  Similar requirement.
(1) Items, just before packaging, shall have been inspected for          (a) Items, just before packaging, shall have been inspected for      Similar requirement.
cleanness according to the requirements specified in the                  cleanness according to the requirements specified in the purchasing document. Dirt, oil residue, metal chips or other              purchasing document. Dirt, oil residue, metal chips, or other forms of contamination shall have been removed by approved                forms of contamination shall have been removed by approved cleaning methods. Any entrapped water shall have been                    cleaning methods. Any entrapped water shall have been removed.                                                                  removed.                                                            ____________
(2) All openings into items shall be capped, plugged and sealed          ()All openings into items shall be capped, plugged, and sealed      Similar requirement.
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                                  Page 12 of 43
 
Packag..ig, Shipping, Receivin, Sr.            And"Handling          Quaity Assurance Requirements frPackaging, Shipping,                    Comments Of Items For Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                  Power Plants N4$.2.2 1972                                        .NQA-A              199,4,Sbpart 2.2..
(See Subsection 3.5 of this Standard). Weld end preparations          (see para. 3.5). Weld end preparations shall be protected from shall be protected from corrosion and physical damage.                corrosion and physical damage.
(3) Items subject to detrimental corrosion, either internal or        (c) items subject to detrimental contamination or corrosion,    Similar requirement.
external, shall be suitably protected.                                either internal or external, shall be suitably protected.
(4) Items packed in containers shall be blocked, braced and/or        (d) items packed in containers shall be blocked, braced, or      Similar requirement.
cushioned to prevent physical damage (See Subsection 3.8 of          cushioned to prevent damage (see para. 3.8).
this Standard).
(5) Items such as aggregate and reinforcing steel shall be                                                                            Addressed in NQA-I, Part suitably protected against detrimental contamination or                                                                                II, Subpart 2.5.
corrosion.
(6) The identity of the item shall be maintained by marking (See      (e) The identity of the item shall be maintained by marking (see Similar requirement.
Subsection 3.9 of this Standard) or other appropriate means.          para. 3.9) or other appropriate means.
3.3 Cleaning                                                          3.3 Cleaning Cleaning includes the preparation of items for preservation or        Cleaning includes the preparation of items for preservation or  Similar requirement.
packaging, or both, to minimize the requirements for site            packaging, or both, to minimize the requirements for site cleaning. Items shall be inspected for cleanness immediately          cleaning, items shall be inspected for cleanness immediately before packaging according to the cleaning requirements              before packaging according to the cleaning requirements specified in the purchase document. Any dirt, oil residue, metal      specified in the procurement documents. Any dirt, oil residue, chips or other forms of contamination shall be removed by            metal chips, or other forms of contamination shall be removed documented cleaning methods. Any entrapped water shall be            by documented cleaning methods. Any entrapped water shall be removed. Any item which is not immediately packaged shall be          removed.
protected from further contamination. (See Appendix section A3.3 for additional requirements.)
A3.3 Cleaning Specific cleaning procedures are considered to be part of the        The following general criteria shall apply as part of the        Similar requirement.
manufacturing specifications. The following general criteria          manufacturing specifications specific cleaning procedures shall apply:
(1) The cleaning process including cleaning compounds chosen          (a) The cleaning process, including cleaning compounds chosen,  Similar requirement.
shall in no way damage the item during cleaning or subsequent        shall in no way damage the item during cleaning or subsequent service when considering the composition, surface finish,            service when considering the composition, surface finish, complexity or other inherent features or other interface              complexity, or other inherent features, or other interface equipment after installation.                                        equipment after installation.
(2) The cleaning process or processes chosen shall remove loose      (b) The cleaning process or processes chosen shall remove loose  Similar requirement.
mill and heat scale, oil, rust, grease, paint, welding fluxes,        mill and heat scale, oil, rust, grease, paint, welding fluxes, chalk, abrasives, carbon deposits, coatings used for                  chalk, abrasives, carbon deposits, coatings used for nondestructive testing process and other contaminants which          nondestructive testing processes, and other contaminants that 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                        Page 13 of 43
 
Packaging, Shipping, Receiving, Storage And'Handling                                Quality Assurance Requirements for Packaginghi                                            Comments
                .Of-Items For Nuclear Power Plants"                        -            Receiving, Storage,and Handlng oIlems for Nucear'.
(During The Construction Phase)                                                              Power Plants N01..2 1972                                                      NQA-1 1994 Subpart 2.2 would render ineffective the method of preservation and                              would render ineffective the method or preservation and packaging, or other specified requirements.                                          packaging or other specified requirements._____________
(3) Item surfaces after cleaning shall be free of cleaning media,                    (c) item surfaces after cleaning shall be free of cleaning media,              Similar requirement.
such as aluminum oxide, silica, grit, lint, chemical cleaning                        such as aluminum oxide, silica, grit, lint, chemical cleaning residue, petroleum solvent residue, etc.                                            residue, and petroleum solvent residue, etc.
(4) After cleaning, the item shall be protected from                                (d) After cleaning, the item shall be protected from                          Similar requirement.
contamination until preservation or packaging is complete.                          contamination until preservation or packaging is complete.
3.4 Methods of Preservation                                                          3.4 Methods of Preservation Items subject to deleterious corrosion shall be protected by                        Items subject to deleterious corrosion shall be protected by                  Similar requirement.
using either contact preservatives, inert gas blankets, or vapor-                    using either contact preservatives, inert gas blankets, or vapor-proof barriers with desiccants (See Subsection 3.6 of this                          proof barriers with desiccants. (See para. 3.6 for vapor-proof Standard for vapor-proof barriers and desiccants.)                                  barriers and desiccants.)
3.4.1 Contact    Preservatives.____________                                          3.4.1 Contact Preservatives.
Contact preservatives are compounds applied to bare metal                            Contact preservatives are compounds applied to bare metal                      Similar requirement.
surfaces to prevent surface corrosion during shipping and                            surfaces to prevent surface corrosion during shipping and storage and generally require removal prior to installation. (See                    storage and generally require removal prior to installation.
Appendix 10/28/2010::*,  (uig'*"*:'"A3.4.1 Section        ":h*ostutp':*. for additional  requirements.)
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A3.4.1 Contact Preservatives.
The following criteria shall be used when considering the type                      The following criteria shall be used when considering the type                Similar requirement.
of contact preservative to be used.                                                  of contact preservative to be used.                                            _____________
(1) The contact preservative shall be compatible with the                            (a) The contact preservative shall be compatible with the                      Similar requirement.
material on which it is applied.                                                    material on which it is applied.                                              _____________
(2) Contact preservatives which are nondrying shall require a                        (b) Contact preservatives which are nondrying shall require a                  Similar requirement.
neutral-grease-proof protective wrap when packaged.                                  neutral grease-proof protective wrap when packaged,_____________
(3) The procedure for applying contact preservatives shall not                      (c) The procedure for applying contact preservatives shall not                Similar requirement.
require disassembly of the item nor shall it be necessary to                        require disassembly of the item nor shall it be necessary to disassemble the item at the site for complete removal. An                            disassemble the item at the site for complete removal. An exception would be for long time storage protection to be                            exception would be for long-term storage protection to be agreed upon by the owner, buyer and manufacturer.                                    agreed upon by the owner, buyer, and manufacturer.
(4) The method of contact preservative removal shall be                              (d) The method of contact preservative removal shall be                        Similar requirement.
accomplished with approved solvents and wiping cloths or by                          accomplished with approved solvents and wiping cloths or by flushing internal cavities with solvents which are not deleterious                  flushing internal cavities with solvents which are not deleterious to the item or other interconnecting material. However,                              to the item or other interconnecting material. However, preservatives for inaccessible inside surfaces of pumps, valves                      preservatives for inaccessible inside surfaces of pumps, valves, and pipe for systems containing reactor coolant water shall be                      and piping for systems containing reactor coolant water shall be the water flushable type.                                                            the water flushable type.____________
10/28/2010                                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                                          Page 14 of 43
 
Packagmig, Shipping, Receiving, Storage And.Handhng                Quality Assurance Requirements for            acaing So          .      .
Of Items For Nuclear Power Plants;                        Receiving, Storage, and .iandling of Items for Nuclear (During The Cntucto Phase)..                                                    Power Plant N45.2.2 1972                                                  NQA-I:494 Subpart 2.2                          ___________
(5) The name of the preservative used shall be indicated to          (e) The name of the preservative used shall be provided to          Similar requirement.
facilitate touchup.                                                  facilitate touch-up.._____________
(6) When motors, pumps, turbines, etc., are shipped with oil        (f) When motors, pumps, turbines, etc., are shipped with oil        Similar requirement.
reservoirs and bearings cavities filled with preservative oil the    reservoirs and bearing cavities filled with preservative oil, the item shall be so tagged and instructions for draining, flushing,    item shall be so tagged and instructions for draining, flushing, refilling and periodic rotation shall be included with the item. refilling, and periodic rotation shall be included with the item.
(7) When it is anticipated that the item might require an            (g) When it is anticipated that the item might require an          Similar requirement.
extended storage period, six (6) months or longer, a preservative    extended storage period (6 months or longer), a preservative needed for the long term protection of the item shall be applied    needed for the long-term protection of the item shall be applied or arrangements shall be made to periodically reapply the            or arrangements shall be made to periodically reapply the presrvatves.preservatives.
3.4. Inrt as Bankts.3.4.2                                Inert Gas Blankets.
Purging and pressurizing the interior of an item or its container    Purging and pressurizing the interior of an item or its container,  Similar requirement.
or both with a dry inert gas provides a means of preventing          or both, with a dry inert gas provides a means of preventing moisture or corrosive atmospheres from acting on sensitive bare moisture or corrosive atmospheres from acting on sensitive, 10/2/200 PckagngShiping ReeivngStorgeandHandingof temsPag 15of metal surfaces or other materials. The item or its container shall bare metal surfaces or other materials. The item or its container be either evacuated prior to filling with the inert gas or adequately purged with the same gas prior to applying the gas shall be either evacuated prior to filling with the inert gas or adequately purged with the same gas prior to applying the gas blanket. (See Appendix section A3.4.2 for additional                blanket.
requirements.)_______________________________
A3.4.2 Inert Gas Blankets.                                          __________________________
When inert gas blankets are used, the following criteria shall      When inert gas blankets are used, the following criteria shall      Similar requirement.
apply:                                                              apply.
(1) Inert gas blankets shall be used only when the exterior shell    (a) Inert gas blankets shall be used only when the exterior shell  Similar requirement.
of the item or its container can be tightly sealed to form a        of the item or its container can be tightly sealed or an inert gas leakproof barrier.                                                  blanket can otherwise be maintained, (2) Only a commercial grade of dry, oil-free, inert gas shall be    (b) Only dry, oil free, inert gas shall be used.                    Similar requirement.
used.                                                                __________________________
(3) Provisions shall be made for measuring and maintaining the (c) Provisions shall be made for measuring and maintaining the            Similar requirement.
blanket pressure within the required range within each              blanket pressure within the required range and within each pressurized purged item or container. Closures and seals shall      pressurized purged item or container. Closures and seals, when be tightly secured so that the absolute (by mass) pressure after    used to maintain a static pressure, shall be tightly secured so final seal is maintained for 24 hours without adding gas, prior to that the absolute pressure (by mass) after final seal is shipping the item from the manufacturer's plant.                    maintained for 24 hr, without adding gas, prior to shipping the
______________________________________________item from the manufacturer's plant.                                    _____________
(4) The item or container shall be marked in bold letters            (d) The item or container shall be marked in bold letters          Similar requirement.
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 15 of 43
 
Packaging, Shipping, Receivng, Storage And Handling                Quality Assurance Requirements for Packaging, Shipping,                          Comments Of Items For Nuclear Power Plants                          Receiving, Storage, and.Handling of Items for Nuc.ear (During The Construction Phase)                                                  Pow"erPlants..........
                        ....N45.2.2 1972  .NQA-1                                                  1994 .Subpart 2.2                        ___________
cautioning that an inert gas blanket has been used. The required      cautioning that an inert gas blanket has been used. The required pressure range also shall be marked on the item or container,        pressure range also shall be marked on the item or container.
3.5 Caps, Plugs, Tapes, and Adhesives                                3.5 Caps, Plugs, Tapes, and Adhesives These items shall be of materials which enable them to perform        These items shall be of materials that enable them to perform        Similar requirement.
their intended function adequately without causing deleterious        their intended function adequately, without causing deleterious effects on items or systems operation.                                effects on the items or system operation.
3.5.1 Caps and Plugs.                                                3.5.1 Caps and Plugs.
Caps and Plugs shall be used to seal openings in items having        Caps and plugs shall be used to seal openings in items having        Similar requirement.
sensitive internal surfaces, and to protect threads and weld end      sensitive internal surfaces and to protect threads and weld end preparations. (See Appendix section A3.5.1 for additional            preparations.
requirements.)
A3.5.1 Caps and Plugss.
Caps and plugs shall conform to the following criteria:              Caps and plugs shall conform to the following criteria.              Similar requirement.
(1) Nonmetallic plugs and caps shall be brightly colored. Clear      (a) Nonmetallic plugs and caps shall be brightly or contrastingly    Similar requirement.
plastic closures are not to be used except when specified for a      colored. Clear plastic closures are not to be used except when special purpose; for example, as a window for humidity                specified for a special purpose: for example, as a window for indicator cards. Special attention shall be given in the control of  humidity indicator cards. Special attention shall be given in the these closures,                                                      control of these closures.
(2) Metallic plugs and caps contacting metal surfaces shall not      (b) Metallic plugs and caps contacting metal surfaces shall not      Similar requirement.
cause galvanic corrosion at the contact areas. Gasketing or other    cause galvanic corrosion at the contact areas. Gasketing or other nonmetallic materials used in conjunction with metallic caps or      nonmetallic materials used in conjunction with metallic caps or plugs shall exhibit no corrosive effect on the material.              plugs shall exhibit no corrosive effect on the material.
(3) Simplicity of installation, inspection, and removal without      (c) Simplicity of installation, inspection, and removal without      Similar requirement.
damage to the item shall be considered.                              damage to the item shall be considered.
(4) Provisions shall be made to preclude the plug or cap from        (d) Provisions shall be made to preclude the plug or cap from        Similar requirement.
falling into or being pushed into the opening after its              falling into or being pushed into the opening after its installation,                                                        installation.
(5) Plugs or caps shall be secured with tape (See Paragraph          (e) Plugs or caps shall be secured with tape (see para. 3.5.2) or    Similar requirement.
A3.5.2 of this Appendix) or other means as necessary to prevent      other means as necessary to prevent accidental removal.
accidental removal.
(6) All plugs and caps shall be clean and free of visible            (f) All plugs and caps shall be clean and free of visible            Similar requirement.
contamination such as, but not limited to dust, dirt, stains, rust,  contamination such as, but not limited to, dust, dirt, stains, rust, discoloration or scale.                                              discoloration, or scale.
(7) Plugs and caps used in contact with austenitic stainless steel    (g) Plugs and caps used in contact with austenitic stainless steel  Similar requirement.
shall be made from non-halogenated materials or stainless steel.      shall be made from non-halogenated materials or stainless steel 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                              Page 16 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                                          'Qualit Assurance Requirements for Packa ing, Shipping, Of Items For Nuclear Power Plants.                                                      Receiving, Storage, and Handling of Items for Nuclear (D .uring The tionstruct on Phase)                                                                      .Power . Plants N45.2.2 1972                                                I NO4 -I 1994.SubDart 2.2 3.5.2 TaDes and Adhesives.                                                                      3.5.2 Tapes and Adhesives.
Pressure sensitive, removable, tape should be used in lieu of                                  Pressure-sensitive, removable tape shall be used in lieu of        Similar requirement, use adhesives in contact with bare metal surfaces. Tapes or                                        adhesives in contact with bare metal surfaces. Tapes or            changed from should to adhesives which could have damaging effects on the item or                                      adhesives that could have damaging effects on the item or          shall in NQA-1.
system shall not be used. Tapes near a weld shall be removed                                    system shall not be used. Tapes near a weld shall be removed completely immediately prior to performing a weld or closure,                                  completely, immediately prior to performing a weld. Tapes used Tapes used for identification rather than sealing which are not                                for identification rather than sealing that are not near a welding near a welding operation may remain until system testing. (See                                  operation may remain until system testing is complete, but shall Appendix section A3.5.2 for additional requirements.)                                          be removed before plant operations unless qualified for operating conditions.
A3.5.2 Tapes and Adhesives.
Tapes and adhesives shall conform to the following criteria:                                    Tapes and adhesives shall conform to the following criteria.      Similar requirement.
(1) When contacting austenitic stainless steel and nickel alloy                                (a) When contacting austenitic stainless steel and nickel alloy    Similar requirement.
surfaces:                                                                                      surfaces:
(a) The halogen and sulfur contents of tapes should not be in                                  (1) tapes shall not be compounded from or treated with            Additional detail regarding excess of 0.10% by weight each. Paperbacked (masking) tape                                      chemical compounds containing elements in such quantities that    tape in NQA- 1-1994.
shall not be used.                                                                              harmful concentrations are leachable, or that they could be        Addresses Regulatory NRC Regulatory Guide 1.38, Regulatory Position C.2.c:                                          released by breakdown under expected environmental                Position from RG 1.38.
Subdivision A.3.5.2(l)(a)-This guideline states that the halogen                                conditions and could contribute to intergranular cracking or and sulfur content of tapes should not be in excess of 0.10% by                                stress corrosion cracking, such as those containing fluorides, weight when used in contact with austenitic stainless steel and                                chlorides, sulfur, lead, zinc, copper, and mercury [paperbacked nickel alloy surfaces. In lieu of this guidelines, tapes, when used                            (masking) tape shall not be used];
with austenitic stainless steel or nickel alloy materials, should not be compounded from or treated with chemical compounds containing elements in such quantities that harmful concentrations could be leached or be released by breakdown of the compound under expected environmental conditions (e.g.,
by radiation). Examples of such compounds are those containing fluorides, chlorides, sulfur, lead, zinc, copper, and mercury.
(b) Upon removal of tape, all residual adhesive shall be                                        (2) upon removal of tape, all residual adhesive shall be removed  Similar requirement.
removed by a non-halogenated solvent (acetone, alcohol or                                      by wiping with a non-halogenated solvent (acetone, alcohol, or equal) wiping.                                                                                  equal);
(c) Starch, silicone and epoxy type material may be used for                                    (3) starch, silicone, and epoxy tape material may be used for      Similar requirement.
tape adhesives.                                                                                tape adhesive.
10/28/2010                                                                  Packaging, Shipping, Receiving, Storage, and Handling of Items                                      Page 17 of 43
 
PackagingShipping, Receiving, Storage Ad Handling                  Quality Assurance Reqirenents fogrPackaging, Shipping,                    Comments Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase*                                                  Power Plants .
N45.2.2 1972                                                  N A-i 1994 Sub at 2.2 (2) When contacting other surfaces and containers:                  (b) When contacting other surfaces and containers:                Similar requirement.
(a) Tapes and adhesives used to seal non-austenitic materials or    (1) tapes and adhesives used to seal non-austenitic materials or  Similar requirement.
containers are not subject to the above restrictions,                containers are not subject to the above restrictions; (b) Tape shall be impervious to water and not subject to            (2) tape shall be impervious to water and not subject to cracking  Similar requirement.
cracking or drying out if exposed to sunlight, heat or cold.        or drying out if exposed to sunlight, heat, or cold.
(3) Tapes should be brightly colored to preclude their loss into a  (c) When used on surfaces of items, tapes shall be visibly        Similar requirement.
system.                                                              distinguishable from the materials on which they are used.        NQA-1 addresses NRC NRC Regulatory Guide 1.38, Regulatory Position C.2.d:                                                                                  position in RG 1.38.
Subdivision A.3.5.2(3)-This guideline states that tapes should be brightly colored to preclude their loss into a system. In lieu of this guidelines, tapes should be colored to contrast with the materials on which they are used.
3.6 Barrier and Wrap Materials and Desiccants                        3.6 Barrier and Wrap Materials and Desiccants A barrier generally is a flexible material designed to withstand    Material thickness shall be selected on the basis of type, size,  Similar requirement.
the penetration of water, water vapor, grease, or harmful gases. and weight of equipment or item to be protected, such that the A wrap is a flexible material, formed around the item or            barrier or wrap will not easily be damaged by puncture, package to exclude dirt and to facilitate handling, marking or      abrasion, weathering, cracking, temperature extremes, wind labeling. Material thickness shall be selected on the basis of      conditions, and the like.
type, size and weight of equipment or item to be protected, such that the barrier or wrap will not easily be damaged by puncture, abrasion, weathering, cracking, temperature extremes, wind conditions, and the like.
Barrier and wrap materials shall be non-halogenated when used        Barrier and wrap materials shall be non-corrosive and shall not    Similar requirement.
in direct contact with austenitic stainless steel, shall be          be otherwise harmful to the item packaged. When barrier and noncorrosive, shall not readily support combustion and shall not    wrap materials are used in direct contact with austenitic be otherwise harmful to the item packaged. Vapor-proof barrier      stainless steels, the total and water leachable content of halogen material, used with desiccants constitutes another preservation      shall not be harmful to the item packaged. Also, barrier and system (See Subsection 3.4 of this Standard); it protects against    wrap materials shall not readily support combustion. Vapor-potential damage by water vapor condensate.                          proof barrier materials used with desiccants constitute another preservation system that protects against potential damage by water vapor condensate.
3.6.1 Water-proof Barrier Material.                                  3.6.1 Waterproof Barrier Material.
Water-proof barrier material shall be resistant to grease and        Waterproof barrier material shall be resistant to grease and      Similar requirement.
water; it shall protect items from airborne and windblown soils. water; it shall protect items from airborne and windblown soils.
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                        Page 18 of 43
 
Packaging,.Shipping, Receiving, Storage And Handling              Q.uality Assurance Requiements for Packagng, Shipig,                      Comne.
Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear (D~uring T-he Constrction Phase)                                              Power Plants N45.2.2 1.972..        ..        .        .                    NQA-1 1994..ubpart 2.2.
3.6.2 Vapor Barrier Material.                                      3.6.2 Vapor-proof Barrier Material.
Vapor-proof barrier materials shall be sealable and the edge of      Vapor-proof barrier materials shall be sealable, and the edge of  Similar requirement.
the barrier which normally will be opened at destination shall be    the barrier that normally will be opened at destination shall be of sufficient area to permit at least two subsequent sealing        of sufficient area to permit at least two subsequent sealing operations. (See Appendix A3.6.2 for additional requirements).      operations.
A3.6.2 Vapor Barrier Material.
When maximum vapor protection is required, barrier material          When maximum vapor protection is required, barrier material        Similar requirement.
shall meet the maximum water vapor transmission rate of 0.05        shall meet the maximum water vapor transmission rate of 0.05      NQA-1 addresses the NRC grams per 100 square inches per 24 hours per ASTM E96 Tests          g/100 sq in. per 24 hr required by ASTM E 96, Test Methods        position from RG 1.38.
for Water Vapor Transmission Of Materials In Sheet Form,            for Water Vapor Transmission of Materials, Procedure E, and Procedure E and shall be packaged with an approved desiccant.        shall be packaged with an approved desiccant. Vapor-proof The barrier material should be brightly colored to preclude loss    barrier material should be colored to contrast with the material within a system.                                                    on which it is used.
NRC Regulatory Guide 1.38, Regulatory Position C.2.e:
: e. Section A.3.6.2-This guidelines states that the vapor barrier material should be brightly colored to preclude loss within a system. In lieu of this guidelines, vapor barrier material should be colored to contrast with the materials on which they are used.
3.6.3 Desiccants.                                                    3.6.3 Desiccants.
Desiccants may be used within a vapor-proof barrier when            Desiccants shall be used within a vapor-proof barrier when        Change from may to shall in condensation or high humidity could damage an item by                condensation or high humidity could damage an item by              NQA-1.
corrosion, mold, or mildew. (See Appendix A3.6.3 for                corrosion, mold, or mildew.
additional requirements).
A3.6.3 Desiccants.
Desiccants shall consist of nondeliquescent, nondusting,            Desiccants shall consist of nondeliquescent, non-dusting,          Similar requirement.
chemically inert, dehydrating agents. The following criteria        chemically inert, dehydrating agents. The following criteria apply when they are used.                                            shall apply.
(1) When used with austenitic stainless steel, the desiccant and    (a) The desiccant bag shall be made of puncture-, tear-, and      NQA- 1 splits the statements the bag material shall not have a halogen content over 0.25%.        burst-resistant material                                          from A3.6.3. (1) into two The desiccant bag shall be made of puncture, tear and burst          (b) When used with austenitic stainless steel and nickel alloy    parts. It also addresses the resistant material.                                                  materials, tapes, desiccants, and the materials for the desiccant  NRC position from RG NRC Regulatory Guide 1.38, Regulatory Position C. L.c:              bag shall not be compounded from or treated with chemical          1.38.
Subdivision A.3.6.3(I) of ANSI N45.2.2-1972 permits                  compounds containing elements in such quantities that harmful desiccants and desiccant bag materials containing not more than      concentrations are leachable, or they could be released by 0.25% halogens to be used with austenitic stainless steels. In      breakdown under expected environmental conditions and could lieu of this requirement, desiccants and the materials for the      contribute to intergranular cracking or stress corrosion cracking, 10/28/2010                                                  Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 19 of 43
 
Shipping, Receiving,. Storage And Handling
        .Packaging,                                                    Quality
                                                                        .      Assurance Requiements for Packaging, Shippmg,                        Comments Of Items For Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear
              *(During The Construction Phase)                                                  Power Plants N45.2.2 1972.                                                  NQA-1 1994 Subpart 2.2 desiccant bags, when used with austenitic stainless steel or          such as those containing fluorides, chlorides, sulfur, lead, zinc, nickel alloy materials, should not be compounded from or              copper, and mercury.
treated with chemical compounds containing elements in such quantities that harmful concentrations could be leached or be released by breakdown of the compounds under expected environmental conditions (e.g., by radiation). Examples of such compounds are those containing fluorides, chlorides, sulfur, lead, zinc, copper, and mercury.___________________________________________
(2) The reactivation temperature and time shall be marked on          (c) The reactivation temperature and time shall be marked on        Similar requirement.
the desiccant container,                                              the desiccant container..                                          _____________
(3) Canisters used to contain desiccants shall be placed so as to    (d) Canisters used to contain desiccants shall be placed so as to  Similar requirement.
cause no deleterious effects such as galvanic corrosion, even        cause no deleterious effects such as galvanic corrosion, even when the desiccant has reached its absorptive capacity for water      when the desiccant has reached its absorptive capacity for water vapor,                                                                vapor.                                                            _____________
(4) Desiccant bags and canisters, when used, shall be secured to      (e) Desiccant bags and canisters, when used, shall be secured to    Similar requirement.
prevent movement, rupture of the bags, or damage to the item          prevent movement, rupture of the bags, or damage to the item being protected.                                                      being protected._______________
10/28/2010.Packagng,-Shipping,                    Reeiving, Storage, nd Handling.of Iems                              Page.20:of,4 (5) Water-vaporproof flexible barriers shall be used to seal          (f) Water- and vapor-proof flexible barriers shall be used to seal  Similar requirement.
items containing desiccants. The included air volume within the      items containing desiccants. The included air volume within the flexible barrier shall be kept to a minimum,                          flexible barrier shall be kept to a minimum.                      ____________
(6) Items which contain desiccants shall have all openings            (g) Items that contain desiccants shall have all openings          Similar requirement.
securely scaled. When flange connections are a part of the            securely sealed. When flange connections are a part of the barriers, 0-rings or gaskets shall be used with all bolts in place    barriers, 0-rings or gaskets shall be used with all bolts in place and tightened sufficiently to insure a water-vapor-proof seal.        and tightened sufficiently to ensure a water- and vapor-proof Weld end preparations, after capping, shall be covered with a        seal. Weld end preparations, after capping, shall be covered water-vapor proof seal.                                              with a water- and vapor-proof seal (7) Packages and items containing desiccant shall be marked.          (h) Packages and items containing desiccants shall be marked.      Similar requirement.
The total number of separate bags and/or containers in the            The total number of separate bags or containers of desiccants in package shall be indicated,                                          the package shall be indicated.
(8) The minimum quantity of desiccant for use in each package        (i) The minimum quantity of desiccant for use in each package      Similar requirement.
shall be determined in accordance with Formula I or Formula II,      shall be determined in accordance with Formula I or Formula 11, as applicable.                                                        as applicable.
Formula I: To determine minimum of desiccant for use with            Formula I To determine minimum units of desiccant for use          Similar requirement.
other than sealed rigid metal barrier:                                with other than sealed rigid metal barrier:
U= 1.6A plus XCD.                                                    U    =l.6A +XD                                                      _    _      _  _  _  _    _
Formula 11: To determine minimum units of desiccant for use          Formula 11 To determine minimum units of desiccant for use          Similar requirement.
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Packaging, Shipping, Receiving, Storage And Handling              Quality Assurance Requirements fo&#xfd;r"Packagingi, Shipping,                  co* ments Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear
                .(During The Construction Phase)                                                  Power Plants N45.2.2 1972                                                    NQA-1 1994,Subpart 2.2.
within sealed rigid metal barrier:                                    with sealed rigid metal barrier:
U= KV plus XD.                                                        U=KV+XD In the above formulas:                                                Where                                                              Similar requirement, NQA-A= Areas of barrier in square feet                                    A = area of barrier, sq ft (m2 x 0.0929)                            1 adds K factors for U= Number of units* of desiccant to be used                          U = number of units of desiccant to be used (see Note)              volumes in cubic D= Pounds of dunnage (other than metal) within barrier                D = dunnage (other than metal) within barrier, lb. (kg x 2.2)      centimeters and cubic K= 0.0007 when volume is given in cubic inches                        K = 0.0007 when volume is given in cu in.                          meters.
K= 1.2 when volume is given in cubic feet                            K = 1.2 when volume is given in cu ft V= Volume within barrier in cubic inches or cubic feet                K = 0.0000425 when volume is given in cm 3(42.5 in m3)
X= 8 for hair felt, cellulosic material (including wood) and          V = volume within barrier in CU in. or CU ft (cm 3 or in 3) other material not categorized below                                  X = 8 for hair felt, cellulosic material (including wood), and X= 6 for bound fibers (animal hair, synthetic fiber or vegetable      other material not categorized below fiber bound with rubber)                                              X = 6 for bound fibers (animal hair, synthetic fiber, or vegetable X= 2 for glass fiber                                                  fiber bound with rubber)
X= 0.5 for synthetic foams and rubber                                X = 2 for glass fiber
*A desiccant unit is that quantity of desiccant, as received,        X = 0.5 for synthetic foams and rubber which will absorb at equilibrium with air at 25 C at least the        NOTE: A desiccant unit is that quantity of desiccant, as following quantities of water vapor: 3.00 grams at 20% relative      received, that will absorb at equilibrium with air at 780 F (25'C) humidity and 6.00 grams at 40% relative humidity.                    at least the following quantities of water vapor: 3.00 g at 20%
relative humidity and 6.00 g at 40% relative humidity.
(9) A humidity indicator shall be included in every water-vapor-      (j) A humidity indicator shall be included in every water- and      Similar requirement.
proof envelope containing desiccant. As applicable, the              vapor-proof envelope containing desiccant. As applicable, the indicator shall be located behind inspection windows or              indicator shall be located behind inspection windows or immediately within the closing edge, face, or cover of the            immediately within the closing edge, face, or cover of the barrier, and as far as practical from the nearest unit of desiccant. barrier and, as far as practical, from the nearest unit of desiccant.
3.7 Container, Crating and Skids                                      3.7 Containers, Crating, and Skids 3.7.1 Containers.                                                    3.7.1 Containers.
Containers are used when maximum protection for the item or          Containers shall be used when maximum protection for the item      Similar requirement.
its barrier is required. Domestic types used shall be limited to:    or its barrier is required. Domestic types used shall be limited to the following:
(1) Cleated, sheathed boxes (500 lb. maximum net weight).            (a) cleated, sheathed boxes [500 lb. (227 kg) maximum net          Similar requirement.
weight]
(2) Nailed wood boxes.                                                (b) nailed wood boxes                                              Similar requirement.
(3) Wood-cleated solid fiberboard boxes.                              (c) wood-cleated solid fiberboard boxes                            Similar requirement.
(5) Metal or fiber drums.                                            (d) metal or fiber drums                                            Similar requirement.
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Packaging, Shipping, Receiving, Storage And Handling              Quality Assurance Requirements for Packaglng,'Shipping,                  Comment Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                Power Plants N45.2.2 1972.                                                  NQA-l199.4 Subpart 2.2.
(6) Crates (See Paragraph 3.7.2).                                    (e) crates (see para. 3.7.2)                                      Similar requirement.
(7) Wire bound boxes (200 lb. maximum net weight).                  (f) wire bound boxes [200 Lb. (91 kg) maximum net weight]        Similar requirement.
(8) Other specially designed containers for special equipment.      (g) other specially designed containers for special equipment    Similar requirement.
(4) Fiberboard boxes (120 lb. maximum net weight. See                (h) fiberboard boxes [120 lb. (54.5 kg) maximum net weight].      NQA-1 changed the order Appendix A3.7.1 for additional requirements).                                                                                          of the list to coincide with the additional information below for fiberboard boxes.
Cleated boxes in excess of 50 lb. shall be bound with steel                                                                            Addressed in item 5 below strapping or equivalent around the container at not less than two                                                                      for NQA-I.
places. (See Appendix A3.7.1 for additional requirements.)
A3.7.1 Fiberboard Boxes.
The following criteria apply for fiberboard boxes used as            The following criteria shall apply for fiberboard boxes used as  Similar requirement.
exterior containers:                                                exterior containers.
(1) Boxes shall be weather-resistant fiberboard preferably from      (1) Boxes shall be weather-resistant fiberboard preferably from  Similar requirement.
the following grade types (or compliance symbol): V2 s, V3 s,        the grade types (or compliance symbol): V2 s, V3 s, or V3 c or V3 c. (Federal Specification PPP-B-636.)                          (Federal Specification PPP-B-636).
(2) Box style shall be RSC - Regular slotted box, (Outer flaps      (2) Box style shall be RSC regular slotted box (outer flaps meet, Similar requirement.
meet, inner flaps and outer flaps are of equal length).              inner flaps and outer flaps are of equal length).
(3) Fiberboard boxes shall be securely closed with a water          (3) Fiberboard boxes shall be securely closed with a water-      Similar requirement.
resistant adhesive applied to the entire area of contact between    resistant adhesive applied to the entire area of contact between the flaps. All seams, and joints shall be further sealed with not    the flaps. All seams and joints shall be further sealed with not less than two inch wide, water resistant tape                        less than 2 in. (5 cm) wide, water-resistant tape.
(4) Boxes shall be strapped with pressure-sensitive reinforced      (4) Boxes shall be strapped with pressure-sensitive reinforced    Similar requirement.
tape, length-wise (top, bottom and ends), girthwide (top, bottom    tape, lengthwise (top, bottom, and ends), girthwise (top, bottom, and sides) and horizontal sides and ends.                            and sides), and horizontal sides and ends.
(5) Wood cleating on fiberboard boxes shall be fabricated from      (5) Wood cleating on fiberboard boxes shall be fabricated from    Similar requirement, 2nd sound, well-seasoned lumber.                                        sound, well-seasoned lumber. Cleated boxes in excess of 50 lb    sentence also compares to (22.7 kg) shall be bound with steel strapping, or equivalent,    N45.2.2 (See section 3.7.1) around the container at not less than two places.
3.7.2 Crates and Skids.                                              3.7.2 Crates and Skids.
Crates and skids shall be used for equipment in excess of 500        Crates and skids shall be used for equipment in excess of 500    Similar requirement.
lb. Skids and runners shall be used on boxes with a gross weight    lb. (227 kg). Skids and runners shall be used on boxes with a of 100 lb. or more, allowing a minimum floor clearance for          gross weight of 100 lb. (45.5 kg) or more, allowing a minimum forklift tines as provided by 4 inch lumber.                        floor clearance for forklift tines as provided by 4 in. (10 cm)
I lumber.
10/28/2010                                                  Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 22 of 43
 
Packaging, Shipping, Re~ceiving, Storage And Handling              Quality Assurance Requirements for Packaging, Shipping,                        come*
Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear'............
(During The Construction Phase)                                                Power Plants .              .*...,    ...
N45.2.2 1972                                                  NQA-I 1994.Subpart 2.2          ..        ,..
3.8 Cushioning, Blocking, Bracing and Anchoring                      3.8 Cushioning, Blocking, Bracing, and Anchoring 3.8.1 Cushioning                                                    3.8.1 Cushioning.
Cushioning shall be used where protection from shock and            Cushioning shall be used where protection from shock and                Similar requirement.
vibration is required; the cushioning materials shall have          vibration is required. The cushioning materials shall have sufficient strength to perform this function. (See Appendix          sufficient strength to perform this function.
A3.8.1 for additional requirements.)
A3.8.1 Cushioning.
Selection of cushioning materials shall be based on the              Selection of cushioning material shall be based on the                  Similar requirement.
following:                                                          following.
(1) It shall exhibit no corrosive effect when in contact with the    (a) It shall exhibit no corrosive effect when in contact with the      Similar requirement.
item being cushioned.                                                item being cushioned.
(2) It shall have low moisture content and exhibit low moisture      (b) It shall have low moisture content and exhibit low moisture        Similar requirement.
absorption properties; or if the cushioning material has some        absorption properties, or if the cushioning material has some moisture absorbing capacity, the item shall be protected with a      moisture absorbing capacity, the item shall be protected with a water-vapor-proof barrier.                                          water-vapor-proof barrier.
(3) It shall have negligible dusting characteristics.                (c) It shall have negligible dusting characteristics.                  Similar requirement.
(4) It shall not readily support combustion.                        (d) It shall not readily support combustion.                            Similar requirement.
3.8.2 Blocking and Bracing.                                          3.8.2 Blocking and Bracing.
Blocking and bracing used for protection of the load to be          Blocking and bracing used for protection of the load to be              Similar requirement.
supported, shall be compatible with the size, shape, and strength supported shall be compatible with the size, shape, and strength of bearing areas of the shipment. The blocking and bracing used of bearing areas of the shipment. The blocking and bracing used to prevent item movement shall withstand thrust and impact          to prevent item movement shall withstand thrust and impact applied in any direction. Blocking and bracing used in direct        applied in any direction. Blocking and bracing used in direct contact with the item being blocked shall not have a corrosive      contact with the item being blocked shall not have a corrosive effect on the item.                                                  effect on the item.
3.8.3 Anchoring.                                                    3.8.3 Anchoring.
Anchoring of the item within a crate or on a skid shall              Anchoring of the item within a crate or on a skid shall                Similar requirement.
adequately fasten the item during shipment and protect the item      adequately fasten the item during shipment and protect the item from potential damage due to rough handling. To facilitate          from potential damage due to rough handling.
disassembly and minimize damage when removing container contents, bolting is preferred. (See Appendix A3.8.3 for additional requirements).
A3.8.3 Anchoring.
When bolts are used for anchoring the following criteria shall      When bolts are used for anchoring, the following criteria shall        Similar requirement.
apply                                                                apply.
(1) If precision bolt holes in the item are used for anchoring,      (a) If precision bolt holes in the item are used for anchoring,        Similar requirement.
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                              Page 23 of 43
 
  .Packaging, Shipping,Receiving, Storage And Hakdhlng"              Quality Assurance Requiremnts for Packagjig, Shpping,                      Comments        '
Of Items For Nuclear P.wer Plants                        Receiving, Storage, and Handling of Items for Nuclelr            ....
(During The Const:ruction Phase)                      .                        Power Plants N45.2.2 1972                                                  NQA,.*994 Subpart 2.2                        ___""_"""__,._.._""        _""
precaution shall be taken to insure that properly fitting bolts of  precaution shall be taken to ensure that properly fitting bolts of the correct dimension and characteristics are used to prevent        the correct dimension and characteristics are used to prevent marring or elongation of the holes.                                  marring or elongation of the holes.
(2) Holes bored through containers or mounting bases shall          (b) Holes bored through containers or mounting bases shall        Similar requirement.
provide a snug fit.                                                  provide a snug fit.
(3) When mounting items to container bases equipped with            (c) When mounting items to container bases equipped with          Similar requirement.
skids, bolts shall be extended through the skids whenever            skids, bolts shall be extended through the skids whenever practical. In such instances counter-sinking of the bolt in the      practical. In such instances, countersinking of the bolts in the sliding surface of the skid is necessary.                            sliding surface of the skid shall be done.
(4) Washers shall be used under the nuts to decrease the            (d) Washers shall be used under the nuts to decrease the          Similar requirement.
possibility of the bolt pulling through the wood.                    possibility of the bolt pulling through the wood.
(5) Nuts shall be properly torqued. To prevent their loosening      (e) Nuts shall be properly tightened. To prevent their loosening  Similar requirement.
during shipment, lock nuts, lock washers, cotter pins, or staking    during shipment, lock nuts, lock washers, cotter pins, or staking shall be employed,                                                  shall be employed.
(From 3.8.3, not the appendix.) Temporary cushioning,                Temporary cushioning, blocking, bracing, or anchoring placed      Similar requirement.
blocking, bracing or anchoring placed within an item for            on an item for shipping protection that needs to be removed shipping protection that must be removed prior to operation of      prior to operation of the item shall be identified by warnings the item shall be identified by warnings placed in a conspicuous    placed in a conspicuous manner to effect proper removal of the manner to effect proper removal of the packing material.            packing material.
3.9 Marking                                                          3.9 Marking To maintain proper identification and instructions or both          To maintain proper identification and instructions, or both,      Similar requirement.
during shipping, receiving and storage, and to provide for          during shipping, receiving, and storage and to provide for identification after the outside of the container has been          identification after the outside of the container has been removed, the item and the outside of containers shall be marked. removed, the item and the outside of the containers shall be (See Appendix 3.9 for additional requirements.)                      marked. If equipment does not lend itself to marking, records shall be maintained that are uniquely identifiable to the item.
A3.9 Marking Items shall be marked to preserve identity in accordance with        Items shall be marked to preserve identity in accordance with      Similar requirement.
the following criteria                                              the following criteria.
(1) The specified identification shall be stamped, etched,          (a) The specified identification shall be stamped, etched,        Similar requirement.
stenciled or otherwise marked on the item or on tags to be          stenciled, or otherwise marked on the item or on tags to be affixed securely to the item in plain, unobstructed view. When      affixed securely to the item in plain, unobstructed view. When metal stamps are employed, low stress rounded bottom type            metal stamps are employed, low stress, rounded bottom type stamps shall be used when the item proper is marked. When            stamps shall be used when the item proper is marked. When vibrating marking tools are used they shall be fitted with a        vibrating marking tools are used, they shall be fitted with a carbide marking tip or equivalent; and shall be designed to          carbide marking tip or its equivalent, and shall be designed to 10/28/2010                                                  Packaging, Shipping, Receiving, Storage, and Handling of Items                            Page 24 of 43
 
Packagng, Shipping, Receiving,' StorageAnd Handling                  Quality ssurances''...met.. .r.ckaging,' Shipping,                            'Comments Of Items For Nuclear Power Plants                            Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                    Power Plants~
N45.2.2 19,72                                                    NQA-4 19,4 Subpart 2.2 provide a rounded impression not to exceed 0.0 10 inches in            provide a rounded impression not to exceed 0.0 10 in. (0.25 mun) depth. Etching shall not be used on nickel alloys or on weld          in depth. Etching shall not be used on nickel alloys, weld areas, areas or sensitized areas of stainless steel. Electric arc marking    or sensitized areas of stainless steel. Electric-arc marking pencils shall not be used.                                            pencils shall not be used.
(2) The marking shall not be deleterious to the material nor          (b) The marking shall not be deleterious to the material nor        Similar requirement.
violate any other section of this standard.                            violate any other Section of Subpart 2.2.
(3) When tags are employed, they shall be of a material which          (c) When tags are employed, they shall be of a material which      Similar requirement.
will retain the marking, withstand weathering deterioration, and will retain the marking, withstand weathering deterioration, and other normal shipping and handling effects and shall not be            other normal shipping and handling effects, and shall not be detrimental to the item.                                              detrimental to the item.
(4) The English language shall be used. Duplicate marking may (d) The English language shall be used. Duplicate marking may                Similar requirement.
be made in other languages.                                            be made in other languages.
(5) References to weights shall be in avoirdupois units.              (e) References to weights shall be in avoirdupois units.          Similar requirement.
Duplicate markings in other systems may also be indicated.            Duplicate markings in other systems may also be indicated Markings on the outside container shall be in accordance with          Markings on the outside container shall be in accordance with      Similar requirement.
the following criteria:                                                the following criteria.
(1) Container markings shall appear on a minimum of two sides (a) Container markings shall appear on a minimum of two sides                Similar requirement.
10/28/2010***:*,**,
of                            *one side the container, preferably on      o* and *',*,*
one end. ,.. Packaging,....
                                                                *    ''of aShipinRceiing container, preferably Strae    and* and on one side    Hadln    of"Items one end.                            Page25of.4 (2) The English language shall be used. Duplicate marking may (b) The English language shall be used. Duplicate marking may                Similar requirement.
be made in other languages or in pictorial markings according to be made in other languages or in pictorial marking according to ISO Recommendation R780 Pictorial Markings For Handling of ISO Recommendation R780, Pictorial Markings for Handling of Goods (general symbols) or ANSI MH*6. 1.                              Goods (general symbols) or ANSI MH6. 1.
(3) References to weights shall be in avoirdupois units.              (c) References to weights shall be in avoirdupois units.            Similar requirement.
Duplicate marking in other systems may also be indicated.              Duplicate markings in other systems may also be indicated.
(4) Container markings shall be applied with waterproof ink or        (d) Container markings shall be applied with waterproof ink or    Modified requirement in paint in characters no less than 3/4 inch high, container size        paint in characters that are legible. When information relative to NQA- 1.
permitting.                                                            handling, and special instructions is required, such information shall be preceded by the word CAUTION in letters that are at least 1/2 in. (1 2.7 mm), as permitted by container size.
(5) Where tags or labels are used, they shall be affixed to the        (e) Where tags or labels are used, they shall be affixed to the    Similar requirement.
container using a waterproof adhesive, tacks where practical, or container using a waterproof adhesive, tacks where practical, or a corrosion resistant wire.                                            a corrosion-resistant wire.
(6) Container marking shall include the following information:        (f) Container markings shall include the following information      Similar requirement.
(a)Destination                                                          (1) destination (b) Return address                                                      (2) return address (c) Package numbers showing the purchase order number,                  (3) package numbers showing the purchase order number,        ____________
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                              Page 25 of 43
 
Packaging, Shipping, Receiving, Storage Aud Handling                Quality Assurance Requirements forkPackagng, Shipping,                    Commens Of ItemsFor Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                  Power Plants N45.2.2:1972                                                  NQA-.199.4 Subpart .2.2 followed by the package number and the total number of              followed by the package number and the total number of packages.                                                            packages (d) Material identification number                                  (4) material identification number (e) Handling instructions - Fragile, Center of Gravity, Keep        (5) handling instructions (e.g., Fragile, Center of Gravity, Dry, This Side Up, Sling Here, Do Not Freeze, stacking              Keep Dry, This Side Up, Sling Here, Do Not Freeze) and limitations as appropriate.                                          stacking limitations, as appropriate (f) Weight of package (in excess of 100 pounds).                    (6) weight of package [in excess of 100 Lb. (45.5 kg)
(g) Special Instructions. Desiccant Inside, Special Inspection,      (7) special instructions (Desiccant Inside, Special Inspection, Storage, Unpacking Restrictions, etc. as appropriate.                Storage, Unpacking Restrictions, etc.) as appropriate Marking of items not within a container, such as pipe, tanks and    Marking of items not within a container, such as pipe, tanks,      Similar requirement.
heat exchangers, shall exhibit specified information in a location  and heat exchangers, shall exhibit specified information in a which is in plain unobstructed view, but not directly applied to    location which is in plain unobstructed view. Marking may be bare austenitic stainless steel and nickel alloy metal surfaces of  applied directly to bare metal surfaces provided it has been the item.                                                            established that the marking material is not deleterious to the item.
4.0 SHIPPING                                                        4 SHIPPING 4.1 General                                                          4.1 General This section covers the requirements for loading and shipment        This Section covers the requirements for loading and shipment      Similar requirement.
of items as defined in Subsection 2.7 of this standard. Described    of items as defined in para. 2.2. The mode of transportation used are environmental protection during transit, procedures to          shall be consistent with the protection classification of the item minimize damage in transit, precaution required when handling        (see para. 2.1) and with the packaging methods employed (see items during loading and transit, and identification and            para. 3.2).
inspection on overseas shipments.
The mode of transportation used shall be consistent with the protection classification of the item (See Subsection 2.7 of this Standard) and with the packaging methods employed (See Subsection 3.2 of this Standard).
NRC Regulatory Guide 1.38, Regulatory Position C.l.e:
Notwithstanding the provisions of subdivision 1.2 of ANSI N45.2.2-1972 with respect to the applicability of this standard and the definition of carrier contained in subdivision 1.4 of ANSI N45.2.2-1972, nothing contained in Section 4, "Shipping," of ANSI N45.2.2-1972 should be deemed to require a common or contract carrier transporting or shipping byproduct, source, or special nuclear material in the ordinary 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                        Page 26 of 43
 
  *Packaging, Shipping, Receiving, Storage And Handling                  Quality Assurance Requrements for Packang, Shippig, Of Items For Nuclear Power Plants                          Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                  Power Plants N45.23.2 1972                                                  NOA-1 1994 SubDart 2.2 course of its business to comply with the provisions set forth in this section of the standard. In this situation these carriers are exempt from NRC regulation under the provisions of 10 CFR
[SECTIONS] 30.13, 40.12, and 70.12. Therefore, the provisions of Section 4 of ANSI N45.2.2-1972 apply only to the extent that they affect the activities of an NRC licensee (e.g., requirements related to shipping contained in 10 CFR Part 71) or a private carrier subject to NRC regulations.
4.2 Transportation Requirements                                        4.2 Transportation Requirements 4.2.1 Open Carriers.                                                  4.2.1 Open Carriers.
For shipment on open carriers where items may be exposed to            For shipment on open carriers where items may be exposed to        Similar requirement.
adverse environmental conditions, the following shall apply:          adverse environmental conditions, the following shall apply.
(1) Level A, B, and C items shall be covered for protection from      (a) Levels A, B, and C items shall be covered for protection      Similar requirement.
environmental conditions. Tarpaulins, when used, shall be fire        from environmental conditions. Tarpaulins, when used, shall be retardant; and they shall be installed in a manner to provide          fire retardant, and they shall be installed in a manner to provide drainage and to insure air circulation to prevent condensation.        drainage and to ensure air circulation to prevent condensation.
(2) Barrier and wrapping materials (See Subsection 3.6 of this        (b) Barrier and wrapped materials (see para. 3.6) subject to      Similar requirement.
Standard) subject to transportation damage shall be covered            transportation damage shall be covered with waterproof with waterproof shrouds such as tarpaulins, so that they are not      shrouds, such as tarpaulins, so that they are not exposed directly exposed directly to the environment,                                  to the environment.
4.2.2 Closed Carriers.                                                4.2.2 Closed Carriers.
For shipment on closed carriers the following shall apply:            For shipment on closed carriers the following shall apply.        Similar requirement.
(1) When level A, B, and C items cannot be adequately                  When Levels A, B, and C items cannot be adequately protected      Similar requirement.
protected from weather or environment on open carriers, closed        from weather or environment on open carriers, closed carriers or carriers shall be used.                                                fully enclosed vehicles shall be used.
(2) Use of fully enclosed furniture vans is recommended when                                                                              Not a requirement.
shipping large delicate items such as control panels.
4.2.3 Special Shipments.                                              4.2.3 Special Shipments.                                          Similar requirement.
NRC Regulatory Guide 1.38, Regulatory Position C.2.a                                                                                      NRC position is that the
: 2. The guidelines (indicated by the verb "should") of ANSI                                                                                term should be treated as N45.2.2-1972 contained in the following section are considered                                                                            shall. Position is to have sufficient safety importance to be treated the same as the                                                                        incorporated into NQA-1.
requirements of the standard, subject to any exceptions noted:
: a. Section 4.2.3-The guidelines concerning special shipments.
Items that exceed established weight or size limitations for          Items that exceed established weight or size limitations for      Similar requirement.
railroads or highways, or require special handling should be          railroads or highways or require special handling shall be given 10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 27 of 43
 
Packaging, Shipping, Receiving,*    Storage. adHadling          QualiyoAssuranceRequirements for Packagng, ShipjpingCommen Of Items For Nuclear Power Plant                          R~eeving, Storage, and Ha~ndling of Items fo Nuclear (During The Construction Phase)                                                    Power Plants
  ...      ....        ......... 1972                                                  NQA-1 1.994Subpart 2.2.
given additional consideration in the following areas:                additional consideration in the following areas.
(1) The type of bracing and tie down methods to be used with          (a) The type of bracing and tie down methods to tie used with      Similar requirement.
the mode of transportation selected for special shipment shall be the mode of transportation selected for special shipments shall specified.                                                            be specified.
(2) "NO HUMPING" shall be specified on rail shipments of              (b) NO HUMPING shall be specified on rail shipments of these      Similar requirement.
these items, and "NO HUMPING" signs shall be prominently              items, and NO HUMPING signs shall be prominently displayed.
displayed.
(3) Use of impact recording meters should be specified on              (c) Use of impact recording meters shall be specified on          Similar requirement.
shipments of heavy or relatively large items incorporating            shipments of heavy or relatively large items incorporating delicate factory installed instrumentation. Meters, when              delicate factory-installed instrumentation. Meters, when specified, shall be installed prior to loading (to record any rough specified, shall be installed prior to loading (to record any rough handling during loading). Procedures shall be established to          handling during loading). Procedures shall be established to interpret recorded data, and to thoroughly check the integrity of interpret recorded data and to thoroughly check the integrity of an item when there is evidence of rough handling. A notice that an item when there is evidence of rough handling. A notice that impact recording meters are being used shall be prominently            impact recording meters are being used shall be prominently displayed. Special recording meters with operating time limits        displayed. Special recording meters with operating time limits greater than the expected transit time shall be specified or, if the greater than the expected transit time shall be specified or, if the expected transit time exceeds the operating time limit of the          expected transit time exceeds the operating time limit of the recorders being used, provisions shall be made to service the          recorders being used, provisions shall be made to service the meters during transit.                                                meters during transit.
(4) The use of "Escorts" may be specified to accompany                                                                                    Not a requirement.
shipments, when additional surveillance is required during transit of certain items.
(5) For special shipments, the conveyance used for transport          (d) For special shipments, the conveyance used for transport      Similar requirement.
shall be certified to be structurally adequate to take the loads      shall be certified to be structurally adequate to take the loads imposed during loading while enroute, and during unloading,            imposed during loading, while enroute, and during unloading.
Prior to shipment the route shall have been investigated to            Prior to shipment the route shall have been investigated to assure safe transit.                                                  assure safe transit.
4.3 Precautions During Loading and Transit                            4.3 Precautions During loading and Transit 4.3.1 Loading.                                                        4.3.1 Loading.
The weight, lifting points, or center of gravity indicated on the      The weight, lifting points, or center of gravity indicated by the  Similar requirement.
crate, skid, or package by the shipper (See Subsection 3.9 of this shipper on the crate, skid, or package by the shipper (see para.
Standard) shall be utilized to insure proper handling during          3.9) shall be utilized to ensure proper handling during loading, loading, transfer between carriers, and unloading (See Section 7 transfer between carriers, and unloading (see Section 7).
of this Standard).                                                  I                                                                                              I 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 28 of 43
 
Packaging,$Shippig, Receiving, Storage And Handling                Quality..ssurance  Assuanc
                                                                                  .qui.ement.. Requireents"formePa rr'.ackaging, Shipping,              Comments Of Items For Nuclear Power Plantsi                        Receiving, Storage, and Handling of Items for Nuclear (During The Constr uction Phase).                                                Power Plants N45....2.1972                                                    NQAl71994 Sunpart 2.2.
4.3.2 Rigging.                                                      4.3.2 Rigging.
Carbon steel rigging equipment shall not come in direct contact      Carbon steel rigging equipment shall not come in direct contact      Similar requirement.
with stainless steel except when attached to lifting lugs, eyes, or  with stainless steel, except when attached to lifting lugs, eyes, or pads, in order to avoid surface damage.                              pads in order to avoid surface damage.
4.3.3 Handling Precautions.                                          4.3.3 Handling Precautions.
All Austenitic Stainless steel and nickel base alloy materials      All austenitic stainless steel and nickel-base alloy materials      Similar requirement.
shall be handled in such a manner that they are not in contact      shall be handled in such a manner that they are not in contact with lead, zinc, copper, mercury, or other low melting elements,    with lead, zinc, copper, mercury, or other low melting point alloys, or halogenated material,                                    elements, alloys, or halogenated material.
4.3.4 Package/Preservative Coatings.                                4.3.4 Package and Preservative Coatings.
Packages and/or preservative coatings shall be visually              Package or preservative coatings shall be visually inspected        Similar requirement.
inspected after loading, and damaged areas repaired prior to        after loading and damaged areas repaired prior to shipment.
shipment. Items shipped with desiccants shall be inspected after    Items shipped with desiccants shall be inspected after loading to loading to assure that sealed areas are intact,                      assure that sealed areas are intact.
4.3.5 Sealed Openings.                                              4.3.5 Sealed Openings.
Sealed Openings shall be visually inspected after loading to        Sealed openings shall be visually inspected after loading to        Similar requirement.
assure closures are intact. Materials used for resealing shall be    assure closures are intact. Materials used for resealing shall be in accordance with Section 3 of this Standard.                      in accordance with Section 3.
4.3.6 Stacking.                                                      4.3.6 Stacking.
Written instructions covering the location and stacking limits of    Where special care is deemed necessary to avert damage,              Similar requirement.
the crates or boxes on the transport vehicle shall be specified;    written instructions concerning the location or stacking limits      NRC position is that the these should be marked on the container,                            for crates or boxes shall be marked on the containers,              term should be treated as NRC Regulatory Guide 1.38, Regulatory Position C.2.b:                                                                                    shall. Position is
: 2. The guidelines (indicated by the verb "should") of ANSI                                                                                incorporated into NQA-1.
N45.2.2-1972 contained in the following section are considered to have sufficient safety importance to be treated the same as the requirements of the standard, subject to any exceptions noted:
: b. Section 4.3.6-The guideline that addresses written instruction on stacking.
4.3.7 Theft and Vandalism.                                          4.3.7 Theft and Vandalism.
Precautions shall be taken to minimize the possibility of theft      Precautions shall be taken to minimize the possibility of theft      Similar requirement.
and vandalism during shipment of items.                              and vandalism during shipment of items.
4.4 Identification and Marking                                      4.4 Identification and Markings Identification and markings on the outside of all packages, skids    Identification and markings on the outside of all packages,          Similar requirement.
or protective covering shall be maintained in accordance with        skids, or protective covering shall be maintained.
Subsection 3.9 of this standard.
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adling            Qualit Assurance.Requirements for Packaging, Shippilg,                          Comm4e    ....
Of Items For Nuclear Power PlnsReceiving,                                      Storage, and Handling of Item~s for Nuclear (D~urinig The Construction Phase)                                                        Power Plants                      ..
N45.2.2 1972                                                          NQA-l 1994 Subpart 2.2                      . .
4.5 Shipments From Countries Outside United States                          4.5 Shipments From Countries Outside the United States 4.5.1 Overseas Shipment.                                                    4.5.1 Overseas Shipment.____________
When overseas shipments are involved, use of deck cargo                      When overseas shipments are involved, use of deck cargo              Similar requirement.
facilities shall be avoided unless necessary due to physical                facilities shall be avoided unless necessary due to physical dimensions. Shipments utilizing approved watertight containers              dimensions. Shipments utilizing approved watertight containers may be carried on deck.                                                      may be carried on deck.                                              _____________
4.5.2 Inspection at Point of Shipment.                                      4.5.2 Inspections at Point of Shipment.
For Special shipments, items shall be inspected to insure                    Items shall be inspected to ensure integrity of packaging or        Similar requirement.
integrity of packaging or protective enclosures after being                  protective enclosures after being loaded aboard ship.
loaded aboard ship.                                                                                                                              ____________
4.5.3 Inspection at Port of Entry.                                          4.5.3 Inspection at Port of Entry.                                  ____________
For special shipments, items shall be inspected to insure                    Items shall be inspected to ensure integrity of packaging or        Similar requirement.
integrity of packaging or protective enclosures when items are              protective enclosures when items are off-loaded at the port of off loaded at the port of entry.                                            entry.____________
4.5.4 Identification and Markings.                                          4.5.4 Identification and Markings.____________
Identification and markings shall follow the procedure outlined              Identification and markings shall follow the procedure outlined      Similar requirement.
in          "'fItm~rNula Subsection
*10/28/2010    3.9 of
                    .. this
* standard.
:*. The. .owrP*ns English
                                                *.      * .........and language        Packaging,
                                                                      .:''" in para.
                                                                                *
* 3.9.
* R~eevng, Strg, Shippig,                        nan    dlinfgga of**::,'*.
Items                    . Page* 30%of 43i:. !
avoirdupois weight shall be used for all identification and marking. Duplicate markings and identification in other languages or weight systems may be used.
4.5.5 Transportation Requirements.                                          4.5.5 Transportation Requirements.
Requirements outlined in Subsection 4.2 (Transportation) and in Requirements outlined in para. 4.2 and Section 7 shall be                        Similar requirement.
Section 7 of this standard shall be followed where applicable,              followed where applicable.
4.6 Nuclear Material Shipment                                                4.6 Nuclear Material Shipments                                      ____________
Special nuclear material and sources shall be shipped as                    Special nuclear material and sources shall be shipped as            Similar requirement.
specified in the AEC fuel license and by other regulatory                    specified in the NRC fuel license and by other regulatory agencies.                                                                    agencies.
: 5. RECEIVING                                                                5 RECEIVING 5.1 General                                                                  5.1 General_____________
This section contains requirements that are to be fuilfilled by the The requirements that shall be fulfilled by the organization(s)              Similar requirement, but organization or organizations responsible for the receiving of              responsible for the receiving of items. Receiving starts when the    examples of items included items. Receiving starts when the items arrive at a storage facility items arrive at a storage facility or construction site before                in receiving have not been or construction site before unloading or unpacking. Included are unloading or unpacking.                                                          included in this paragraph procedures, inspections, marking, identification and                                                                                              of NQA- I documentation prior to placing the item in storage or directly in its final location. Shipping damage claims, transfer of_________________________________________
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* Packaging,
:..,:ping,. Ship&#xfd;ing,
                    ..      R~eeiving,
                          ....ece ........ Storage
:, . And"Handling
                                                    .*...          *Asuanemre QualityY. ssurancefe
                                                                  %..Quit          ...    *..or.Pac.kaging, Rq u eents    .. for1ac      1g"g;SShi" in apmig,."
* Co.men Cm es"          .!
Of Items For Nuclear Power Plants                        -Receiving, Storage, and Hndling of Items for Nuclear (During Th* Construction Phase)                                                Powef Plants N45.*2.1972                                                    NQA-1 1994. Subpart .2 ownership, financial responsibility and contractual obligations are commercial obligations which are not included in the scope of this standard.
5.2 Receiving Inspection Requirements                                5.2 Receiving Inspection Requirements 5.2.1 Shipping Damage Inspection.                                    5.2.1 Shipping Damage Inspection.
Preliminary visual inspection or examination shall be performed Preliminary visual inspection shall be performed prior to or              Similar requirement.
prior to unloading to determine if any damage occurred during        immediately after unloading to determine if any damage shipping.                                                            occurred during shipping.
Observations for unusual conditions shall include:                    Observations for unusual conditions shall include:                  Similar requirement.
(1) Fire - Charred paper, wood or paint, indicating exposure to      (a) fire - charred paper, wood, or paint, indicating exposure to    Similar requirement.
fire or high temperature.                                            fire or high temperature; (2) Excessive Exposure - Weather-beaten, frayed, rusted, or          (b) excessive exposure - weather-beaten, frayed, rusted, or          Similar requirement.
stained containers indicating prolonged exposure during transit.      stained containers, indicating prolonged exposure during transit; (3) Environmental Damage - Water or oil marks, damp                  (c) environmental damage - water or oil marks, damp                  Similar requirement.
conditions, dirty areas, or salt film (indicating exposure to sea    conditions, dirty areas, or salt film, indicating exposure to water or winter road salt chemicals).                                seawater or winter road salt chemicals; (4) Tie Down Failure - Shifted, broken, loose or twisted              (d) tie down failure - shifted, broken, loose, or twisted shipping  Similar requirement.
shipping ties, and worn material under ties, indicating improper      ties, and worn material under ties indicating improper blocking blocking and tie down during shipment.                                and tie down during shipment; (5) Rough Handling - Splintered, torn, or crushed containers          (e) rough handling - splintered, torn, or crushed containers,        Clarified by separating into indicating improper handling. Review of impact recording              indicating improper handling;                                        two separate checks in instrument readings.                                                  (f) review of impact recording instrument readings against          NQA-1.
established criteria. See para. 4.2.3(c).
5.2.2 Item Inspection.                                                5.2.2 Item Inspection.
Unless the package marking prohibits unpacking, the content of        Unless the package marking prohibits unpacking, the contents        Similar requirement.
all shipments shall be visually inspected to verify that the          of all shipments shall be visually inspected to verify that the specified packaging and shipping requirements have been              specified packaging and shipping requirements have been maintained. When items are contained in transparent separate          maintained. When items are contained in transparent, separate moisture-proof bags or envelopes, visual inspection without          moisture-proof bags or envelopes, visual inspection without unpacking the contents is acceptable.                                unpacking the contents shall be acceptable.
Statistical sampling methods may be used for groups of similar        Where specific inspection requirements can be achieved,              Similar requirement.
items. Care shall be taken to avoid contamination of the items        statistical sampling methods may be used for groups of similar during inspection. The inspections shall be performed in an          items. Care shall be taken to avoid contamination of the items area, equivalent to the level of storage requirement for the item    during inspection. The inspections shall be performed in an area (See Section 6 of this Standard).                                    equivalent to the level of storage requirement for the item (see 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 31 of 43
 
Pickag g,.Shipping, Of Items ForReevig      Stor. g Plants Nuclear Power      A            "adl"    Quality  AssuranceRequirements Receiving,  Storage, and Handling  forofPackaging,  Shipping, items for Nuclear                omments.
(DUring The Construction Phase)Power                                                      Plants N4i.. 17                                            NQA-I 1994 Subpart 2.2,.
Section 6).
These inspections and examinations shall include the following        These inspections and examinations shall include the following, Similar requirement.
as appropriate:                                                        as appropriate:
(1) Identification and Marking. Verification that identification      (a) identification and marking - verification that identification    Similar requirement.
and markings are in accordance with applicable codes,                  and markings are in accordance with applicable codes, specifications, purchase orders, drawings, and this standard.          specifications, purchase orders, and drawings, and with requirements in this Part (Part II);
(2) Manufacturing Documentation - Assurance that the item              (b) manufacturing documentations - assurance that the item            Similar requirement.
received was fabricated, tested and inspected prior to shipment        received was fabricated, tested, and inspected prior to shipment in accordance with applicable code, specification, purchase            in accordance with applicable code, specification, purchase order and/or drawings.                                                order, or drawings; (3) Protection Covers and Seals - Visual inspection to assure          (c) protective covers and seals - visual inspection to assure that    Similar requirement.
that covers and seals meet their intended function.                    covers and seals meet their intended function; (4) Coatings and Preservatives - Verification that coatings and        (d) coatings and preservatives - verification that coatings and      Similar requirement.
preservatives are applied in accordance with specifications,          preservatives are applied in accordance with specifications, purchase orders or manufacturer's instructions.                        purchase orders, or manufacturer's instructions; (5) Inert Gas Blanket - Verification that the inert gas blanket        (e) inert gas blanket - verification that the inert gas blanket      Similar requirement.
pressure is within the acceptable limits,                              pressure is within the acceptable limits; (6) Desiccant - Verification that the desiccant is not saturated,      (f) desiccant - verification that the desiccant is not saturated, as  Similar requirement.
as indicated through the use of humidity indicators. Desiccants        indicated, through the use of humidity indicators. Desiccants shall be regenerated or replaced as necessary in accordance with      shall be regenerated or replaced as necessary in accordance with special instructions,                                                  special instructions.
(7) Physical Damage - Visual inspection to assure that parts of        (g) physical damage - visual inspection to assure that parts of      Similar requirement.
items are not broken, cracked, missing, deformed or misaligned        items are not broken, cracked, missing, deformed, or and rotating parts turn without binding. Accessible internal and      misaligned, and that rotating parts turn without binding.
external areas shall be free of detrimental gouges, dents,            Accessible internal and external areas shall be free of scratches and bums.                                                    detrimental gouges, dents, scratches, and bums.
(8) Cleanness - Visual inspection to assure that accessible            (h) cleanness - visual inspection to assure that accessible          Similar requirement.
internal and external areas are within the specification              internal and external areas are within the specification requirements for dirt, soil, mill scale, weld splatter, oil, grease,  requirements for dirt, soil, mill scale, weld splatter, oil, grease, or stains. If inspection for cleanness was performed prior to          or stains. If inspection for cleanness was performed prior to sealing and shipping, and inspection upon receipt indicates that      sealing and shipping, and inspection upon receipt indicates that there has been no penetration of the sealed boundary, then            there has been no penetration of the sealed boundary, then inspection for internal cleanness is optional.                        inspection for internal cleanness is optional.
Unless the completed item was inspected or examined at the            Unless the completed item was inspected at the source, it shall      Similar requirement.
source, it shall be inspected or examined at the point of              be inspected at the point of receiving to verify that the following II 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                            Page 32 of 43
 
Packaging, Shipping, Receiving, Storage And Hadling                Quality Assurance Requirements for Packagng, Shipping,                      Comments SReceivig                                  ckagig Nummentr Shppo.r.
Of Items For Nuclear Power Plants %R                                  g, Storage, and Handlin of Items rfouclear (During The Construction Phase)                                                  Power Plants            . 3/4.
N45.2.2 19-72.                                                  NQA-I 1994 Subpart 22 receiving to verify that the following characteristics conform to    characteristics conform to the specified requirements. These the specified requirements. These inspections or examinations        inspections shall include such items as:
shall include such items as:
(1) Physical Properties - Assurance that physical properties          (a) physical properties - assurance that physical properties        Similar requirement.
conform to the specified requirements and that chemical and          conform to the specified requirements and that chemical and physical test reports, if required, meet the requirements.            physical test reports, if required, meet the requirements; (2) Dimensions - Random visual inspection to assure that              (b) dimensions - random visual inspection to assure that            Similar requirement.
important dimensions conform with drawings and                        important dimensions conform with drawings and specifications. Examples are; base plate mounting holes, overall      specifications, i.e., baseplate mounting holes, overall external external size, configuration and orientation of parts.                size, and configuration and orientation of parts; (3) Weld Preparations - Random verification that weld                (c) weld preparations - random verification that weld              Similar requirement.
preparations are in accordance with applicable drawings and          preparations are in accordance with applicable drawings and specifications.                                                      specifications; (4) Workmanship - Visual inspection of accessible areas to            (d) workmanship - visual inspection of accessible areas to          Similar requirement.
assure that the workmanship is satisfactory to meet the intent of    assure that the workmanship is satisfactory to meet the intent of the requirements.                                                    the requirements; (5) Lubricants and Oils - Verification of presence of proper          (e) lubricants and oils - verification of presence of proper        Similar requirement.
lubricants and oils, if required, by either specification, purchase  lubricants and oils, if required, by either specification, purchase order, or manufacturers' instructions,                                order, or manufacturer's instructions; (6) Electrical Insulation - Performance, of insulation resistance    (f) electrical insulation - performance of insulation resistance    Similar requirement.
tests for motors, generators, control and power cable, to ensure      tests for motors, generators, and control and power cable to conformance with specifications.                                      ensure conformance with specifications.
5.2.3 Special Inspection -                                            5.2.3 Special Inspection.
Where receiving inspection in addition to that described above        Where receiving inspection in addition to that described above      Similar requirement.
is required, the "Special Inspection" procedure, complete with        is required, the special inspection procedure, complete with documentation instructions, shall be attached to the item or          documentation instructions, shall be attached to the item or container (See Section 3 of this Standard); this is in addition to    container. This is in addition to the copy sent through normal the copy sent through normal channels. The special inspection        channels. The special inspection shall be performed, and the shall be performed and the results of the inspection shall be        results of the inspection shall be documented.
documented.
5.3 Disposition of Received Items                                    5.3 Disposition of Received Items 5.3.1 Acceptable - Containers and items inspected or examined        5.3.1 Acceptable. Containers and items inspected and found in      Similar requirement.
and found in conformance with specified requirements shall be        conformance with specified requirements shall be identified as identified as acceptable in accordance with the status indicating    acceptable (see para. 5.4) and placed in a storage area for system employed (See Subsection 5.4 of this Standard) and            acceptable items, or moved to the final location for installation placed in a storage area for acceptable items or moved to the        or use.
10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 33 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                    Quality Assurance Requirements for&#xfd; Packaging, Shipping,                            Comments Of Items For Nuclear Power Plants                              Reeiing, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                      Power Plants N45.2.2 1972                                                      NQA-1 1994 Subpart 2.2                              _      _________
final location for installation or use.                                  _____________________________
5.3.2 Nonconforming - Items which do not conform to the                  5.3.2 Nonconforming. Items which do not conform to the                  Similar requirement when specified requirements shall be identified as nonconforming in            specified requirements shall be controlled in accordance with          taking into consideration the accordance with the system employed (See Subsection 5.4 of                Part 1.                                                                information addressed in this Standard) and when practical the item shall be placed in a                                                                                  NQA-l, Part 1.
segregated storage area or removed from the project site to                                                                                        Similar requirement.
prevent inadvertent installation or use.
5.3.3 Conditional Release - If the nonconformance which                  5.3.3 Conditional Release. If the nonconformance that caused            Similar requirement.
caused the item to be classified "unacceptable" can be corrected          the item to be classified unacceptable can be corrected after after installation, the item may be released for installation on a        installation, the item may be released for installation on a conditional release basis. A statement documenting the                    conditional release basis. A statement documenting the authority and technical justification for the conditional release        authority and technical justification for the conditional release of the item for installation shall be prepared, and made part of          of the item for installation shall be prepared and made part of the documentation.                                                        the documentation.                                                      ____________
5.4 Status Indicating System                                              5.4 Status Indicating System A system or method for identifying the status of items (e.g. an          A status indicating system is a system or method for identifying Similar requirement.
inventory 10/2/201 system,  tagging, labeling, color code) shall be
:.**.**Packag..
the status of items (e.g., an inventory Handling.of.,tems.Pag
                                                                      .. ing,.. Shipping Receiving, Storage, and,system,
                                                                                                                    . tagging,.. labeling,
                                                                                                                                        .= ...  .                        34.*:..
of..43 employed that clearly indicates whether items are acceptable or color code) that clearly indicates whether items are acceptable unacceptable for installation. A controlled physical separation is or unacceptable for installation. A controlled physical an acceptable equivalent method. The system shall indicate the            separation is an acceptable equivalent method. The system shall date the item was placed in the acceptable or unacceptable                provide for indication of the date the item was placed in the installation status. The use of the system shall be regulated by          acceptable or unacceptable installation status and the the Quality Control program. The system shall provide for the            conditional release of the items for installation pending the conditional release of items for installation pending subsequent          subsequent correction of the nonconformance. When tags are correction of the nonconformance. When tags are used the stock used, the stock shall be made from material that will not shall be made from material which will not deteriorate during            deteriorate during storage. The stock used shall not be storage; tags shall be securely affixed to the items and displayed deleterious to the item.Tags shall be securely affixed to the in an area that is readily accessible. The stock used shall not be        items and di splayed in an area that is readily accessible.
deleterious to the item._____________
5.5 Correction of Nonconformances                                                                                                                ____________
Items designated nonconforming or unacceptable for installation                                                                                  Similar requirement.
or use shall be corrected using authorized procedures, to meet                                                                                    See NQA-1, Part I, Basic specified requirements, or accepted "As is". If this is not                                                                                      Requirement 15 and possible, the item shall be scrapped or otherwise discarded                                                                                      Supplement 15S-l.
__________________________________________________________________________Wording___                          Wordngiimsimlar 5.5.1 Reinspection -Items that have been corrected shall be              _______________________________Similar requirement.
10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                                      Page 34 of 43
 
Packaging, Shipping, Receiving, Storage And Handling .                Qualit*,y Assurance Requirements for Packaging, S4ijpg,                          Comments Of Items For Nuclear Power Plants                              .. * ...
* Receiving,  ......
Storage,,.***
Po.w~erPlants.,*..
and  Handling of Items,for .Nuclear 0: o,,.,&#xf7;..,  ...  :...."-*
(During The Construction Phase)              .                                              Plants N45.2.2 1972                              ..                        NQA-1 1994 Subpart 2.2 reinspected. The area of inspection may be confined to the area of the nonconformance. When it has been determined that the                                                                                        See NQA-1, Part I, Basic corrected item is satisfactory, the status of the item as denoted                                                                                  Requirement 15 and by the system shall be changed to acceptable. An appropriate                                                                                      Supplement 15 S-1.
entry shall be made in the documentation after acceptance is                                                                                      Wording is similar.
determined.
5.6 Marking                                                              5.5 Marking Required marking shall be verified to provide positive                                                                                            NQA-1, Subpart 2.2 does identification during receiving, storage, and installation. Items                                                                                  not present the same detail not properly identified at receiving may be marked using the                                                                                      as N45.2.2.
method in the appendix (See Appendix A 3.9 of this Standard).
Changing, correcting or any other marking on Code Stamp                  Changing, correcting, or any other marking on Code stamp                  Similar requirement.
name plate is prohibited, unless authorized by the manufacturer          nameplate shall be prohibited, unless authorized by the whose serial number is applied,                                          manufacturer of the item.
5.7 Documentation                                                        5.6 Documentation A written record of the receiving inspection, package                    A written record of the receiving inspection, package                    Similar requirement.
identification, tagging, corrective actions, and justification for      identification, tagging, corrective actions, and justification for conditional acceptance shall be prepared. These records shall be        conditional acceptance shall be prepared made a part of the permanent records provided for in Section 8 of this standard.
: 6. STORAGE                                                              6 STORAGE 6.1 General                                                              6.1 General 6.1.1 Scope. This section contains requirements that are to be          6.1.1 Scope. This Section contains requirements that shall be            Similar requirement.
fulfilled by the organization responsible for performing the            fulfilled by the organization responsible for performing the storage of items. Levels and methods of storage necessary are            storage of items. Levels and methods of storage are defined to defined to minimize the possibility of damage or lowering of            minimize the possibility of damage or lowering of quality due to quality due to corrosion, contamination, deterioration or                corrosion, contamination, deterioration, or physical damage physical damage from the time an item is stored upon receipt            from the time an item is stored upon receipt until the time the until the time the item is removed from storage and placed in its        item is removed from storage and placed in its final location.
final location.
6.1.2 Levels of Storage. Environmental conditions for items              6.1.2 Levels of Storage. Environmental conditions for items              Similar requirement.
classified as Levels A, B, C, and D described in Subsection 2.7          classified as Levels A, B, C, and D described in para. 2.2 shall of this standard shall meet requirements as described in the            meet the requirements as described in the following paragraphs.
following paragraphs:
(1) Level A items shall be stored under special conditions              (a) Level A items shall be stored under special conditions                Similar requirement.
similar to those described for Level B items but with additional        similar to those described for Level B items but with additional 10/28/2010                                                      Packaging, Shipping, Receiving, Storage, and Handling of Items                                  Page 35 of 43
 
        .Packaging, Shipping, Receiving, St6rage AdHanding                Quality Assurance Requir.ements orofPacking,.
Items for N....ipping, uclear:      :    Comments Of IteM's For Nuclear Power Plants                          Receiving,, Storage, and*Handling (During The Construction Phase)                                                  Power Plants N4$.2.2 1972                                                  NQAm-1194" Subpart 2.2 requirements such as temperature and humidity control within          requirements such as temperature and humidity control within specified limits, a ventilation system with filters to provide an    specified limits, a ventilation system with filters to provide an atmosphere free of dust and harmful vapors, and any other            atmosphere free of dust and harmful vapors, and any other appropriate requirements.                                            appropriate requirements.
(2) Level B items shall be stored within a fire resistant, tear      (b) Level B items shall be stored within a fire-resistant, tear-    Similar requirement.
resistant, weather-tight, and well-ventilated building or            resistant, weather-tight, and well-ventilated building or equivalent enclosure. Precautions shall be taken against              equivalent enclosure. Precautions shall be taken against vandalism. This area shall be situated and constructed so that it    vandalism. This area shall be situated and constructed so that it will not be subject to flooding, the floor shall be paved or equal,  will not be subject to flooding; the floor shall be paved or equal, and well drained. Items shall be placed on pallets or shoring to      and well drained. Items shall be placed on pallets or shoring to permit air circulation. The area shall be provided with uniform      permit air circulation. The area shall be provided with uniform heating and temperature control or its equivalent to prevent          heating and temperature control or its equivalent to prevent condensation and corrosion. Minimum temperature shall be 40          condensation and corrosion. The minimum temperature shall be F and maximum temperature shall be 140 F or less if so                40'F (5&deg;C), and the maximum temperature shall be 140&deg;F stipulated by a manufacturer.                                        (60'C) or less if so stipulated by the manufacturer.
(3) Level C items shall be stored indoors or equivalent with all      (c) Level C items shallbe stored indoors or in an equivalent        Similar requirement.
provisions and requirements as set forth in Level B items except      environment with all provisions and requirements as set forth that heat and temperature control is not required.                    for Level B items, except that heat and temperature control is not required.
(4) Level D items may be stored outdoors in an area marked and        (d) Level D items may be stored outdoors in an area marked and      Similar requirement.
designated for storage, which is well drained, preferably gravel      designated for storage that is well drained, preferably gravel covered or paved and reasonably removed from the actual              covered or paved, and reasonably removed from the actual construction area and traffic so that possibility of damage from      construction area and traffic so that the possibility of damage construction equipment is minimized. Items shall be stored on        from construction equipment is minimized. Items shall be stored cribbing or equivalent to allow for air circulation and to avoid      on cribbing or equivalent to allow for air circulation and to trapping water.                                                      avoid trapping water.
6.2 Storage Areas                                                    6.2 Storage Areas Periodic inspections shall be performed to assure that storage        Periodic inspections shall be performed to assure that storage      Similar requirement.
areas are being maintained in accordance with these                  areas are being maintained in accordance with applicable requirements. The housekeeping requirements shall be in              requirements.
accordance with N45.2.3.
6.2.1 Access to Storage Areas.                                        6.2.1 Access to Storage Areas.
Access to storage areas shall be controlled and limited only to      Access to storage areas for Levels A, B, and C items shall be      Similar requirement.
personnel designated by the responsible organization.                controlled and limited only to personnel designated by the responsible organization. Access to storage areas involving Level D items shall be controlled as designated by the 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 36 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                Quality Assrnce Requirements for Packaging, Shipping              *,Comments I~~~                        ,adln~Storage, and Handlingof      Iteafog&#xfd;hip ofprnc OfItems ForNuclear Power Plants                          Receiving,                                tems.for Nuclear (During T.he Constr.uction Phase)                                                Power Plants NW5t2; 61i7                                                    NQA-4 1994:SubpartU22____________
responsible  organization.
6.2.2 Cleanliness and Housekeeping practices.                        6.2.2 Cleanness and Housekeeping Practices.
Cleanliness and good housekeeping practices shall be enforced        Cleanliness and good housekeeping practices shall be enforced      Similar requirement.
at all times in the storage areas. The storage areas shall be        at all times in the storage areas. The storage areas shall be cleaned as required to avoid the accumulation of trash,              cleaned as required to avoid the accumulation of trash, discarded packaging material and other detrimental soil.            discarded packaging materials, and other detrimental soil.
6.2.3 Fire Protection.                                              6.2.3 Fire Protection Fire protection commensurate with the type of storage area and      Fire protection commensurate with the type of storage area and    Similar requirement.
the material involved shall be provided and maintained,              the material involved shall be provided and maintained.
6.2.4 Storage of Food and Associated Items.                          6.2.4 Storage of Food and Associated Items.
The use or storage of food, drinks, and salt tablets dispensers in  The use or storage of food, drinks, and salt tablet dispensers in  Similar requirement.
any storage area shall not be permitted.                            controlled storage areas shall not be permitted.
6.2.5 Measures to Prevent Entrance of Animals.                      6.2.5 Measures to Prevent Entrance of Animals.
Measures shall be taken to prevent the entrance of rodents and      Measures shall be taken to prevent the entrance of rodents and    Similar requirement.
other animals into indoor storage areas or equipment to              other animals into indoor storage areas or equipment to minimize possible contamination and mechanical damage to            minimize possible contamination and mechanical damage to stored material.                                                    stored material.
6.3 Storage Methods                                                  6.3 Storage Methods Storage methods and procedures shall comply with the                Storage methods and procedures shall comply with the              Similar requirement.
requirements described in the following paragraphs.                  requirements described in the following paragraphs.
6.3.1 Ready Access to Stored Items.                                  6.3.1 Ready Access to Stored Items.
All items shall be stored in such a manner as to permit ready        All items shall be stored in such a manner as to permit ready      Similar requirement.
access for inspection or maintenance without excessive              access for inspection or maintenance without excessive handling handling, to minimize risk of damage.                                to minimize risk of damage.
6.3.2 Arrangement of Items.                                          6.3.2 Arrangement of Items.
Items stacked for storage shall be arranged so that racks,          Items stacked for storage shall be arranged so that racks,        Similar requirement.
cribbing or crates are bearing the full weight without distortion    cribbing, or crates are bearing the full weight without distortion of the item.                                                        of the item.
6.3.3 Storage of Hazardous Material.                                6.3.3 Storage of Hazardous Material.
Hazardous chemicals, paints, solvents, and other materials of a      Hazardous chemicals, paints, solvents, and other materials of a    Similar requirement.
like nature shall be stored in well ventilated areas which are not  like nature shall be stored in well-ventilated areas and not in in close proximity to important nuclear plant items.                close proximity to important nuclear plant items.
6.3.4 Identification                                                6.3.4 Identification.
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Packaging, Shipping, Receiving, Storage And Handling                Quality Assurance Requirements for Packaging, Shipping,                      Comments
              .. OfItems For.Nuclear Power Plants                        Receiving, Storage, and Handling ofItemos for Nuclear (During The Constructioni Phase)                                                Power Plants.
N45.2.2 1972                                                  NQA-1 1994 Subpart 2.2.                      ., _...    .... __... .____.
All items and their containers shall be plainly marked so that        Items and their containers shall be plainly marked so that they        Similar requirement.
they are easily identified without excessive handling, or            are easily identified without excessive handling or unnecessary unnecessary opening of crates and boxes.                              opening of crates and boxes.
6.3.5 Coverings.                                                      6.3.5 Coverings.
Weatherproof covering, when used for outdoor storage, shall be        Weatherproof Coverings, when used for outdoor storage, shall          Similar requirement.
flame resistant type of sheeting or tarpaulins. They shall be        be the flame-resistant type of sheeting or tarpaulins. They shall placed so as to provide drainage and to insure air circulation to    be placed so as to provide drainage and to ensure air circulation minimize condensation. They shall be tied down to prevent            to minimize condensation, They shall be tied down to prevent moisture from entering laps and to protect the coverings from        moisture from entering laps and to protect the coverings from wind damage.                                                          wind damage.
6.3.6 Outdoor Storage.
Items stored outdoors shall be positioned or covered to avoid          Added in NQA-l -1994.
trapping moisture in pockets or internally. For example, valves shall be positioned such that water does not collect under the bonnet but can drain from the valve packing area.
6.4 Control of Items in Storage                                      6.4 Control of Items in Storage Control of items in storage is described in the following            Control of items in storage is described in the following            Not a requirement paragraphs.                                                          paragraphs.
6.4.1 Inspections and Examinations. Inspections and                  6.4.1 Inspections. Inspections shall be performed and                  Similar requirement.
examinations shall be performed and documented on a periodic          documented on a periodic basis to assure that the integrity of the basis to assure that the integrity of the item and its container as  item and its container, as provided for under Section 3, is being provided under Section 3 of this standard is being maintained,        maintained. Deficiencies noted shall be corrected and Deficiencies noted shall be corrected and documented.                documented.
The characteristics verified during this inspection or                The characteristics verified during this inspection shall include      Similar requirement.
examination shall include such items as:                              such items as:
(1) Identification and marking (See Subsection 3.9 of this            (a) identification and marking (see para. 3.9)                        Similar requirement.
Standard).
(2) Protective covers and seals (See Subsection 3.9 of this          (b) protective covers and seals (see para. 3.6)                        Similar requirement.
Standard).
(3) Coatings and preservatives (See Paragraph 3.4.1).                (c) coatings and preservatives (see para. 3.4.1)                      Similar requirement.
(4) Desiccants and inert gas blankets (See Paragraph 3.6.3 and        (d) desiccants and inert gas blankets (see paras. 3.6.3 and 3.4.2)    Similar requirement.
3.4.2).
(5) Physical damage.                                                  (e) physical damage                                                    Similar requirement.
(6) Cleanness.                                                        (f) cleanness                                                          Similar requirement.
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Packaging, Shipping,Receiving, StorageAnd Handling"                Quality Assurance                    fRequirementsfor Packagng, Shippmng,              Comments Of iteig s    omrNuclear Power Plan                          Receiving Storage and Handling of Items for Nuclear (During The Construction Phase)                                                  Power Plants N45.2. 1972.                                                    NQA-1 1994 Subpart 2.2 6.4.2 Care of Items. Care of items in storage shall be exercised      6.4.2 Care of Items. Requirements for proper maintenance            Similar requirement.
in accordance with the following. Requirements for proper            during storage shall be documented. Care of items in storage maintenance during storage shall be documented and written            (includes storage in place) shall be exercised in accordance with procedures or instructions shall be established,                      the following.
(1) Items in storage shall have all covers, caps, plugs or other      (a) Items in storage shall have all covers, caps, plugs, or other  Similar requirement.
closures intact. Methods used to seal openings shall be in            closures intact. Methods used to seal openings shall be in accordance with Section 3 of this standard. Covers removed for        accordance with Section 3. Covers removed for internal access internal access at any time for any reason shall be immediately      shall be immediately replaced and resealed after completion of replaced and resealed after completion of the purpose for            the purpose for removal.
removal.
(2) Temporary preservatives shall be left intact during storage.      (b) Temporary preservatives shall be left intact during storage. Similar requirement.
Should reapplication of preservatives be required at the site,        Should reapplication of preservatives be required at the site, only those previously approved shall be used.                        only those previously approved shall be used.
(3) Items pressurized with inert gas shall be monitored at such a    (c) Items pressurized with inert gas shall be monitored at such a  Similar requirement.
frequency as to insure that the gas pressure is maintained within    frequency as to ensure that the gas pressure is maintained within specified limits during storage. Desiccant humidity indicators        specified limits during storage. Desiccant humidity indicators shall also be monitored and desiccants shall be changed or            shall also be monitored, and desiccants shall be changed or reprocessed when specified.                                          reprocessed when specified.
(4) Instrumentation racks shall be energized as specified by the      (d) Instrumentation racks shall be energized as specified by the    Similar requirement.
manufacturer                                                          manufacturer.
(5) Space heaters enclosed in electrical items shall be energized.    (e) Space heaters enclosed in electrical items shall be energized. Similar requirement.
(6) Rotating electrical equipment shall be given insulation          (f) Rotating electrical equipment shall be given insulation        Similar requirement.
resistance tests on a scheduled basis.                                resistance tests on a scheduled basis.
(7) The shafts of rotating equipment shall be rotated on a            (g) The shafts of rotating equipment shall be rotated on a          Similar requirement.
periodic basis. The degree of turn shall be established so that the  periodic basis. The degree of turn shall be established so that the parts receive a coating of lubrication where applicable, and so      parts receive a coating of lubrication, where applicable, and so that the shaft does not come to rest in a previous position. (90      that the shaft does not come to rest in a previous position (90 degree and 450 degree rotations are examples.)                        deg. and 450 deg. rotations are examples).
(8) Other maintenance requirements specified by the                  (h) Other maintenance requirements specified by the                Similar requirement.
manufacturer's instruction for the item shall be performed.          manufacturer's instructions for the item shall be performed.
6.4.3 Post Fire Evaluation.                                          6.4.3 Post-Fire Evaluation.
In the event a fire should occur in the storage area or at any        In the event a fire should occur in the storage area at any time,  Similar requirement.
time, each item known to have been heated to an ambient              each item known to have been heated to an ambient temperature ,_I 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items                          Page 39 of 43
 
Packaging, Shipping, Receiving, Storage And Handling                'QOuality Assurance Requirements for Packaging, Shipping,:                        Comments Of Items 'For Nuclear Power Plants                          Receiving, Storage, and: H ndling of Items for Nucler..        .........                        ,
(During The'Conistruction Phase)                                                  Power Plants N45.2.2 19,72                                                    tNQA-1. 1994 Subpart2.
temperature of over 150 F or subjected to smoke contamination          of over I150'F (65'C) or subjected to smoke contamination shall shall be withheld from installation or use until it has been          be withheld from installation or use until it has been thoroughly thoroughly examined and the item has been verified to be in            examined, and the item has been verified to be in conformance conformance with specified requirements.                              with specified requirements.
6.5 Removal of Items from Storage                                      6.5 Removal of Items From Storage Only items which have been inspected and are considered                Only items which have been inspected and are considered              Similar requirement.
acceptable for installation or use in accordance with the              acceptable for installation or use in accordance with the receiving inspection procedure shall be removed from storage          receiving inspection procedure shall be removed from storage for installation or use. (See Section 5 of this Standard.) Items      for installation or use (see Section 5). Items released from released from storage and placed in their final locations within      storage and placed in their final locations and items stored in the power plant, shall be inspected and cared for in accordance        place within the power plant shall be inspected and cared for in with the requirements of Section 6 of this standard, and other        accordance with the requirements of paras. 6.4.1 and 6.4.2 and applicable standards.                                                  other standards, as applicable.
6.6 Storage Records                                                    6.6 Storage Records Written records shall be prepared that include such pertinent          Written records shall be prepared that include such pertinent        Similar requirement.
information as storage location, inspection  results, protection, 10/8/010Pakaing                    information  as storage location, inspection Sippng.Rceiin,.Sorge                      results, protection, an.HndlngofItes                                  ag 40.'%*.:
of 43 .
and personnel access.                                                  and personnel access.
: 7. HANDLING                                                            7 HANDLING                                                          ________
7.1 General                                                            7.1 General This section contains requirements that are to be fulfilled by the    The requirements that shall be fulfilled by the organizations        Subpart 2.15 requirements organizations responsible for handling items. This section            responsible for handling items are contained in subpart 2.15.        are compared to these covers the requirements for the handling of items in Subsection                                                                            requirements of N45.2.2 in 2.7 of this standard utilizing appropriate equipment in                                                                                    the table for Subpart 2.15.
accordance with methods and procedures specified to minimize damage and preserve the quality of the item and container.                                                                                  _____________
7.2 Methods and Procedures                                                                                                                  ____________
Detailed handling instructions and procedures shall be prepared for all items that require special handling instructions because of weight, size, susceptibility to shock damage, high nil ductility transition temperatures, or any other conditions that warrant special instructions. Such instructions or procedures shall be made available prior to the time the item is to be handled and shall give weights, sling locations, balance points, methods of attachment, maximum hoist line speeds and other pertinent            _______________________________________
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PackagiSgeShiAping,"ReceivingStorage"AndHandling    Hmequirements  Qualityieu                  mnfo  for Packaging, aa      ghShipping,.......Cmnet Of Items For Nuclear Power Plants                        Receiving, Storage, and Handling of Items for Nuclear (During The Construction Phase)                                                Power Plants N45.2.2 1972                                                        Power Suparts 12 features to be considered as necessary for safe handling.
Items not specifically covered above shall be handled in accordance with sound material handling practices.
7.3 Hoisting Equipment All equipment for handling items shall be used and maintained in accordance with the following:
7.3.1 Hoisting equipment used for handling shall be certified by the manufacturer. The certification shall indicate the various parameters for the maximum load to be handled.
7.3.2 Hoisting equipment shall not be loaded beyond its rated load, as certified by the manufacturer, except for test purposes.
7.3.3 The requirements of ANSI B30.2.0, Safety Standard for Overhead and Gantry Cranes, ANSI B30.5, Safety Standard for Crawler, Locomotive and Truck Cranes, ANSI B30.6, Safety Standard for Derricks, and ANSI A 10.5, Safety Requirements for Material Hoists shall be followed.
7.3.4 For special lifts, hoisting equipment may be re-rated, or modified and re-rated, upon approval by the manufacturer or if the manufacturer's specifications are not available, the limitations assigned to the equipment shall be based on the determinations of a qualified engineer competent in this field and such determination shall be documented and recorded appropriately. Re-rated equipment shall be given a dynamic load test over the full range of the lift using a test weight at least equal to the lift weight. A dynamic test includes raising, lowering and traversing the load in contrast to a static test where the test weight may be increased incrementally with no movement.
NRC Regulatory Guide 1.38, Regulatory Position C. L.b:
: b. Subdivision 7.3.4 of ANSI N45.2.2-1972 delineates requirements for re-rating hoisting equipment for special lifts.
This subdivision requires that re-rated equipment be given a dynamic load test over the full range of the lift, using a test weight at least equal to the lift weight. In lieu of this requirement, the test weight used in temporarily re-rating hoisting equipment for special lifts in accordance with the 10/28/2010                                                    Packaging, Shipping, Receiving, Storage, and Handling of Items              Page 41 of 43
 
SPackagi g S". ippi      ..eceiving, Storage And Handling        Qualit Assurance Requirements for Packaging, Shipping,                            Comm,.t..
Of Items For N        gucleor Power PlAnts                    Receiving, Stora.ge, A Handling of Items for N"clear (During The Construction Phase)                                              Power Plants N4512.2 1972                                                  NQA- 11994 Subpart 2.2 provisions of subdivision 7.3.4 should be at least equal to 110%
of the lift weight.                                                                                                                        _____________
7.4 Inspection of Equipment and Rigging                                                                                                    ____________
An inspection program shall be established for equipment and rigging. A system shall be established that will indicate acceptability of all equipment and rigging after each inspection.
This system shall specify control of nonconforming lifting equipment.                                                          __________________________
Periodic inspections shall be supplemented with special visual and non-destructive examinations and dynamic load tests prior to handling of items described in Subsection 7.2 of this standard __________________________
7.4.1 Rigging that is frayed, worn or otherwise deteriorated shall not be used.                                                  _____________________________
7.4.2 Hoisting equipment that does not meet manufacturer's specifications shall not be used.                                    _____________________________
7.4.3 Equipment and rigging shall be kept clean and free of contaminants that are detrimental to the material being handled.____________________________
10/28/2010...,. ,...              . ......          .. .*. Packging
                                                                ,... Shppn, Receiving**,, Storage,... and Handingof IemsPag. .......                        42..of,.,.
43....
7.4.4 Rigging items such as hooks, shackles and turnbuckles that appear to have yielded or are distorted shall not be used.      ____________________________
7.5 Personnel                                                        __________________________
The responsible organization shall determine that the personnel engaged in operating material handling, equipment are competent and have demonstrated satisfactory ability in operating similar lifting equipment.                                __________________________
: 8. RECORDS                                                          8 RECORDS Record copies of completed procedures: reports; personnel            Record copies of procedures, reports, personnel qualification        Similar requirement.
qualification records; test equipment calibration records; test      records, test equipment calibration records, test deviation or deviation or exception records; and inspection and examination      exception records, and inspection records shall be prepared as records shall be prepared as required by this standard. These        required by this Subpart. These records shall be retained with records shall be placed with other project records as required by other project records as required by code, standard, code, standard, specification or project procedures.                specification, or project procedures.
: 9. AMERICAN NATIONAL STANDARDS REFERRED TO IN THIS DOCUMENT                                                  __________________                                                    ________
When the following standards referred to in this document are                                                                              The QAPD addresses the superseded by a revision approved by the American National                                                                                standards for the program.
Standards Institute the revision shall apply:                        _____________________________
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SPackaging,eShi        'Receiving, Storage Md Hakilin            Quality Assurance Requirements'for Packaging,'hipping,              o*oments "OfrItems'ForNuclearPower Phants                        Receieving, Storage, andHandling of Items for'Nuclear (DurNing T                                                                    Power Pla*t  *-..
N45    ...                              *.NQA-1                    1994Subpart 2.2    .    .... ..... . ...
N45.2 Quality Assurance Program Requirements for Nuclear Power Plants
*N45.2.3 Housekeeping During the Construction Phase of Nuclear Power Plants
*N45.2.6 Qualifications of Quality Assurance Personnel for the Construction Phase of Nuclear Power Plants
*N45.2.10 Quality Assurance Terms and Definitions M H 6.1 Pictorial Markings for Handling of Goods B30.2.0 Safety Code for Overhead and Gantry Cranes B30.5 Safety Code for Crawler, Locomotive, and Truck Cranes B30.6 Safety Code for Derricks A 1 0.5 Safety Requirements for Material Hoists These Standards are being approved by the American National Standards Institute and they should be available early in 1973.
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Housekeeping During the Construction Phase of Nuclear                Quality Assurance Requirements for Housekeeping for                    COMMENTS Power .Plants
                                        .... ...                        .Nuclear                Power Plants.
N45.2.3-1973                                              NQA-1 1994,,Subpart 213                      _____________,____-__I
: 1. INTRODUCTION                                                    1 GENERAL 1.1 Scope This standard defines the housekeeping requirements for the        Subpart 2.3 provides housekeeping requirements for the control  Similar introductory control of work activities, conditions, and environments that      of work conditions and environments that can affect the quality statement.
can affect the quality of important parts of a nuclear power      of important parts of a nuclear power plant.
plant during the construction phase.
NRC Regulatory Guide 1.39, Position C.3 Although ANSI N45.2.3-1973 is entitled "Housekeeping During the Construction Phase of Nuclear Power Plants," the requirements included in the standard, subject to the provision of Regulatory Position C.2, are considered to be applicable for housekeeping activities occurring during the operations phase that are comparable to those occurring during the construction phase.
These parts include the structures, systems, and components                                                                        No similar statements in whose satisfactory performance is required for the plant to                                                                        NQA-1, Subpart 2.3, but operate reliably, to prevent accidents that cause undue risk to                                                                    these items are addressed the health and safety of the public, or to mitigate the                                                                            within the NQA-I.
consequences of such accidents if they were to occur.
Housekeeping encompasses all activities related to control of cleanness of facilities, cleanness of material and equipment, fire prevention and fire protection including disposal of combustible materials and debris, control of access, and protection of equipment not denoted in other standards.
The requirements may also be extended to other appropriate        It supplements the requirements of Part I and shall be used in  Similar introductory parts of nuclear power plants when specified in contract          conjunction with applicable Basic and Supplementary Sections    statement. NQA-1, Part I is documents. This standard is intended to be used in conjunction    of Part I when and to the extent specified by the organizations comparable to ANSI N45.2 with ANSI N45.2, Quality Assurance Requirements For                invoking Subpart 2.3.                                          as referenced in N45.2.3.
Nuclear Power Plants.
1.2 Applicability The requirements of this standard apply to the work of any        See Intro to NQA-1-1994, Part II, for general information      NQA-1 addresses similar individual or organization that participates in housekeeping      regarding Applicability.                                        application statements in activities during construction activities of nuclear power plants                                                                  the Introduction to Part II as discussed in paragraph 1.1. The extent to which the                                                                            and in Section 2 of Subpart individual requirements of this standard apply will depend upon                                                                    2.3 below.
the nature and scope of the work to be performed and the 10/28/2010                                                          Housekeeping for Nuclear Power Plants                                                Page I of 10
 
Housekeeping During the Construction Phase of Nuclear                    Quality Assurance Reuirements for HousekeepgforCO                            NTS Power Plants                                                    Nuclear PowerPat
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importance of the item or service involved. The requirements are intended to assure that only proper materials, equipment, processes, and procedures are utilized in the maintenance of housekeeping during the construction of power plants and that the quality of items is not degraded as a result of housekeeping practices and techniques during construction processing.
1.3 Responsibility The organization or organizations responsible for establishing          See Intro to NQA-1-1994, Part II, for general information Similar requirements for the applicable requirements for the activities covered by this          regarding Responsibility.                                responsibility are addressed standard shall be identified and the scope of their                                                                              in the Introduction to Part II responsibilities shall be documented. The work of establishing                                                                    of NQA-1.
practices and procedures and providing the resources in terms of personnel, equipment, and services necessary to implement the requirements of this standard may be delegated to other organizations, and such delegations shall also be documented.
However, it is the responsibility of each organization performing work covered by this standard to comply with the procedures and instructions issued for the project and to conform to the requirements of this standard applicable to his work.
It is the responsibility of the organization performing these activities to specify the detailed methods and procedures unless they are specified in the contract documents.
1.4 Definitions The following definition is provided because it is used uniquely                                                                  Definitions are addressed in in this standard:                                                                                                                the Introduction to Part I of NQA-1.
Construction Phase - The period of time beginning with the start of construction activity and ending as each plant area is turned over to the plant operator.
Other terms and their definitions are contained in ANSI N45.2. 10 1.5 Referenced Documents Other documents that are required to be included as a part of                                                                    The QAPD addresses this standard are either identified at the point of reference or                                                                  referenced documents.
identified in paragraph 5 of this standard.
10/28/2010                                                                Housekeeping for Nuclear Power Plants                                          Page 2 of 10
 
Housekeeping Du6ing the*e.Construction Phase of Nuclear            Q    Ity Ass'u'rance Requi.ements fo Hue            pi  fo            COMMENTS Power Plants                                                  Nuclear Power Plants N45.2.3-1973.                                        "    ,.NQA-1    1994 Subpart 2.3 NRC Regulatory Guide 1.39, Position C. I Subdivision 1.5 of ANSI N45.2.3-1973 states that other documents that are required to be included as a part of this standard are either identified at the point of reference or identified in Paragraph 5 of the standard. The specific acceptability of these listed documents has been or will be covered separately in other regulatory guides and in Commission regulations, where appropriate.
: 2. GENERAL REQUIREMENTS                                            2 GENERAL REQUIREMENTS This paragraph contains requirements that are to be fulfilled by  Housekeeping activities shall include documented methods and      Similar requirements.
the contractor who is responsible for performing any segment      techniques for control of the site area, the plant, and the of work described in paragraphs 3 and 4 of this standard.          materials and equipment being incorporated in the plant to Measures shall be established and implemented for                  preserve the requisite quality of the items being constructed or documenting housekeeping operations to verify conformance to      installed.
specified requirements.
2.4 Personnel Qualifications                                      Personnel working in zone controlled areas shall be familiar      Similar requirements.
All personnel working in zone controlled areas shall be familiar  with the necessities and requirements for cleanness control with the necessities and requirements for cleanness control        applicable to the various zones. Training programs shall be applicable to the various zones. Training programs shall be        utilized for this purpose, where appropriate.
utilized for this purpose where appropriate.
2.1 Planning                                                      2.1 Planning and Procedures The work and the quality assurance requirements for the            Planning and procedure preparation shall be in accordance with    Similar requirements. NQA-housekeeping activities at the nuclear power plant site shall be  the requirements of the Introduction to this Part (Part II);      1 combines planning and delineated. The planned activities shall include the methods and  procedures and instructions shall contain sufficient detail to    procedures and contains techniques for control of the site area, the facilities, and the  provide for control of the site area, the plant, and the materials less detail in this section, materials and equipment being incorporated in the plant to        and equipment being incorporated in the plant to preserve the      but addresses procedures preserve the requisite quality of the items being constructed or  requisite quality of the item being constructed or installed,      for all the subparts in the installed. Necessary procedures and work instructions that are                                                                        Introduction to Part II.
needed to assure compliance with the specified requirements shall be identified and provisions shall be made for their preparation, approval, release, and control. Methods to be used for the collection, handling, and disposition of records, data, and reports shall be designated.
N45.2.1, &sect; 2.1, &#xb6;&#xb6; 2-7 -The second paragraph of this section,                                                                        The Zone descriptions and the descriptions of the 5 Zones, and the Restriction List table is                                                                    Restriction List are part of inserted following &sect; 2.2, Procedures and Instructions to align                                                                        2.1 Planning in N45.2.3.
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Houiisekeeping During the Construction Phase of Nuclear              Quality Assurance Requirements for Housekeeping for                      COMMNTS, Power Plants...      ...                                      Nuclear Power Plants N45.2.3-1973                                                  NQA      -i99  ubpart 2.3                  ___________
with the text of NQA-1.                                                                                                              NQA-1 addresses these in 2.2 Classification of Cleanness.
N45.2.1, &sect; 2.1, &#xb6; 8 regarding recording entry and exit of personnel and material is moved down to &sect; 3.1 to align with the text of NQA-1.
2.2 Procedures and Instructions The procedures and instructions for housekeeping practices          Procedures and instructions providing for the control of site    Similar requirements.
shall be prepared and may be issued in segments to conform          areas, site preparation, fire prevention and protection, and with the project construction schedule. The first segment            records shall be in force with the start of the construction establishing regulations for control of site area, site preparation, activity. Other procedures and instructions shall be prepared fire prevention and protection, and records shall be in force        and approved no later than the start of equipment installation with the start of construction activity. The remaining segments      work.
shall be prepared and approved no later than the start of equipment installation work.
2.2 Classification of Cleanness N45.2.3, &sect; 2.1, &#xb6;2 - Cleanness requirements for housekeeping        Cleanness requirements for housekeeping activities shall be      Similar requirements.
activities shall be established on the basis of the following zone  established on the basis of the following zone designations. The designations. Time for implementation of the zone designations      timing for implementation of the zone designations shall be as shall be as required by the construction progress.                  required by the need for cleanness.
Zones                                                                Zones                  Similar requirements. Zone Restriction List                1    lI III IV          V          Restriction List                  I  lI III IV          V      Restriction H requires Clothing change                Yes No No No No                      Clothing change                  Yes No No No No                Material precleaning under Clean gloves, shoe covers Yes Yes No No No                          Clean gloves, shoe covers Yes Yes No No No                      NQA- 1-1994.
head covering                                                        head covering Filtered air                  Yes No No No No                      Filtered air                    Yes No No No No Material precleaning          Yes No No No No                      Material precleaning            Yes Yes No No No Material accountability        Yes Yes Yes No No                    Material accountability          Yes Yes Yes No No Personnel accountability      Yes Yes Yes No No                    Personnel accountability        Yes Yes Yes No No No use of tobacco or eating Yes Yes Yes Yes No                      No use of tobacco or eating Yes Yes Yes Yes No Zone I - Areas requiring the highest order of cleanness and shall    Zone I Areas requiring the highest order of cleanness shall be  Similar requirements.
be equipped with a clean clothing change facility at the            equipped with a clean clothing change facility at the vestibule vestibule or entrance, preferably with toilet facilities            or entrance. Such areas shall provide for complete outer change immediately adjacent so that personnel working in the                of clothing by personnel, including the use of shoe covers, head controlled area do not have to wear the special clothing in other    covers, and gloves to protect all equipment surfaces from areas. Such areas shall provide for complete outer change of        outside contamination. Material entering this zone shall have 10/28/2010                                                            Housekeeping for Nuclear Power Plants                                          Page 4 of 10
 
Housekeping During the Construction Phase of Nuclear                Quality Assurance Requirements for Housekeeping for:                    ; COMMENTS'.
                        .. Power Plants        .                  .        .Nuclear                Power Plants N45.2.3-1973                                                  NQA-1 1994 Subpart 2.3                          ___________
clothing by personnel, including use of shoe covers, head            been appropriately cleaned prior to entry.
covers, and gloves to protect all equipment surfaces from outside contamination. Material entering this zone shall have been appropriately cleaned prior to entry as specified in ANSI N45.2.1.
Zone II - Intermediate cleanness requirements less restrictive      Zone 11. Intermediate cleanness requirements less restrictive        Similar requirements.
than Zone I but where foreign matter may have detrimental            than Zone I, but where foreign matter may have detrimental effects.                                                            effects.
Zone Ill - Areas less restrictive than Zones I and H but requiring  Zone III. Areas less restrictive than Zones I and II, but requiring  Similar requirements.
access control over personnel and materials.                        access control over personnel and materials.
Zone IV - Areas where it is desired to regulate the use of          Zone IV. Areas where it is desired to regulate the use of            Similar requirements.
tobacco and eating for material and equipment protection or for      tobacco and eating of food for material and equipment health and fire hazards.                                            protection or for health and fire hazards.
Zone V - Unrestricted construction areas requiring good              Zone V. Unrestricted construction areas requiring good              Similar requirements.
construction site housekeeping practices only.                      construction site housekeeping practices only.
2.3 Results Inspection and test results shall be documented in a suitable test                                                                      Similar requirements report or data sheet. Each report shall identify the item to which                                                                      addressed in NQA-1, Part I it applies, the procedures or instruction followed in performing                                                                        and the Introduction to Part the task, and the identification of the following:                                                                                      11.
: 1. Conditions encountered which were not anticipated,                                                                                  Similar requirements including nonconformance.                                                                                                                addressed in NQA-1, Part I
: 2. Identity of inspector or tester.                                                                                                      and the Introduction to Part
: 3. Completion date.                                                                                                                      H.
Test reports and data sheets shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation.
: 3. REQUIREMENTS                                                      3 REQUIREMENTS 3.1 Control of Site Area                                            3.1 Control of Site Area Areas for specific activities shall be assigned and regulated.      Areas for specific activities shall be assigned and regulated.      Similar requirements.
Areas which shall be designated include where appropriate            Areas that shall be designated include, where appropriate, refuse and garbage dumps, refuse burning sites, storage              refuse and garbage dumps, refuse burning sites, storage locations, parking lots, eating places, non-smoking areas,          locations, parking lots, eating places, nonsmoking areas, subcontractor work areas, common areas, and waste collection        subcontractor work areas, common areas, and waste collection container locations. Personnel entrance to controlled areas,        container locations. Personnel entrance to controlled areas, admission of visitors to the work site, and identification of all    admission of visitors to the work site, and identification of all 10/28/2010                                                            Housekeeping for Nuclear Power Plants                                            Page 5 of 10
 
Housekeeing During the ConstructionPhase *ofNuclear .'                Quality Assurance Requirements for Housekeeping for                    tOMMENTS"'.
Power, lats                                                    Nuclear P.ower Plants.........                    .
N45.2.3-1973                              .                  NQA-1 1994 Subpart 2-3 personnel shall be regulated in accordance with established        personnel shall be controlled in accordance with established procedures and regulations,                                        procedures and instructions.
N45.2.1, &sect; 2.1, &#xb6; 8 - For Zones 1, 1I, and III a written record of  For Zones I, 11, and II a written record of the entry and exit of  Similar requirements.
the entry and exit of all personnel and material shall be          all personnel and material shall be established and maintained established and maintained.
Grading, drainage, roads, construction facilities, plant fencing,  Grading, drainage, roads, construction facilities, plant fencing,  Similar requirements.
and utilities shall be provided in accordance with specified        and utilities shall be provided in accordance with specified requirements and shall be maintained as required in good            requirements and shall be maintained as required in good condition throughout the construction phase or until replaced      condition throughout the construction phase or until replaced with the permanent facilities.                                      with the permanent facilities.
3.2 Control of Facilities                                          3.2 Control of Facilities Control of work and storage areas where important items are        Control of work and storage areas where important items are        Similar requirements.
handled shall be established and maintained to conform to the      handled shall be established and maintained to conform to the appropriate zone defined in paragraph 2.1 of this standard.        appropriate zone defined in para. 2.2 of this Subpart.
Atmospheric control shall be provided where necessary.              Atmospheric control shall be provided where necessary.
The control of all tools, equipment, materials, and supplies that The control of tools, equipment, materials, and supplies that are    Similar requirements.
are used in Zones I, II, and III shall be maintained to prevent the used in Zones I, II, and 1II shall be maintained to prevent the inadvertent inclusion of deleterious materials or objects in        inadvertent inclusion of deleterious materials or objects in critical systems. Appropriate control measures shall be            critical systems. Appropriate control measures shall be provided through utilization of such items as log books and        provided through utilization of such items as log books and tethered tools.                                                    tethered tools.
3.2.1 Cleanness.                                                    3.2.1 Cleanness.
The work areas shall be kept sufficiently clean and orderly that The work areas shall be kept sufficiently clean and orderly so        Similar requirements.
construction activity can proceed in an efficient manner that      that construction activity can proceed in an efficient manner will produce and maintain quality in conformance with              that will produce and maintain quality in conformance with specified requirements. Where large accumulations of materials specified requirements. Where large accumulations of materials occur on a non-routine basis, such as the stripping of concrete    occur on a nonroutine basis, such as the stripping of concrete forms, the material shall be promptly removed or stored neatly. forms, the material shall be promptly removed or stored neatly.
Garbage, trash, scrap, litter, and other excess materials shall be  Garbage, trash, scrap, litter, and other excess materials shall be collected, removed from the job site, or disposed of in            collected, removed from the job site, or disposed of in accordance with specified requirements or planned practices.        accordance with specified requirements or planned practices.
Such excess material shall not be allowed to accumulate and        Such excess material shall not be allowed to accumulate and create conditions that will adversely affect quality. The disposal create conditions that will adversely affect quality. The disposal of cleaning chemicals shall be accomplished so additional          of cleaning chemicals shall be accomplished so additional hazards are not created at the disposal site.                      hazards are not created at the disposal site.
10/28/2010                                                            Housekeeping for Nuclear Power Plants                                          Page 6 of 10
 
Housekeeping During the Construction Phase of Nuclear                Quality Assurance Reqirements for Housekeeping for                    COMMENTS Power Plants                                                    Nuclear Power Plants N45.2 341973                                                  NQA-1 1994 Subpart.2.3, 3.2.2 Environment.                                                  3.2.2 Environment.
Areas of activity shall be adequately lighted, ventilated,          Areas of activity shall be adequately lighted, ventilated,        Similar requirements.
protected, and accessible as appropriate for the work being          protected, and accessible as appropriate for the work being performed. Temporary lighting may be utilized but shall be          performed. Temporary lighting may be utilized but shall be installed and maintained to provide good visibility. Ventilation    installed and maintained to provide good visibility. Ventilation shall be provided where necessary to prevent accumulation of        shall be provided where necessary to prevent accumulation of dust, noxious fumes, and temperature extremes. Adequate              dust, noxious fumes, and temperature extremes. Adequate working space for construction personnel shall be provided          working space for construction personnel shall be provided utilizing proper work stages and platforms having accessibility      utilizing proper work scaffolds and platforms having by stairs or ladders. Barriers, screens, shields, restricted access, accessibility by stairs or ladders. Barriers, screens, shields, or other protection shall be provided as necessary for isolation    restricted access, or other protection shall be provided as of areas where noise, welding arcs, dust, inclement weather, or      necessary for isolation of areas where noise, welding arcs, dust, other conditions exist that may affect the quality of work being    inclement weather, or other conditions that may affect the performed.                                                          quality of work being performed.
3.2.3 Fire Protection and Prevention.                                3.2.3 Fire Protection and Prevention.
Equipment and instructions for the protection from and              Equipment and instruction for the protection from, and            Similar requirements.
prevention of, damage by fire shall be provided in accordance        prevention of, damage by fire shall be provided in accordance with the NFPA National Fire Codes, Volume 4, Building                with the requirements of the NFPA National Fire Codes.
Construction Facilities. Procedures or instructions for fire        Procedures or instructions for fire protection shall include protection shall include provisions for fighting fires involving    provisions for fighting fires involving the use of available the use of available community fire departments, trained project    community fire departments, trained project brigades, and brigades, and others. Procedures or instructions shall include      others. Procedures or instructions shall include plans for plans for provision of water supplies, hydrants, automatic          provision of water supplies, hydrants, automatic sprinklers, sprinklers, access for fire fighting, and distribution of            access for fire fighting, and distribution of extinguishers and extinguishers and fire fighting equipment.                          firefighting equipment.
NRC Regulatory Guide 1.39, Position C.2 Subdivision 3.2.3 of ANSI N45.2.3-1973 includes general guidelines and requirements for fire protection and prevention.
The requirements and guidelines of Subdivision 3.2.3 are not considered a part of this regulatory guide, since this subject is addressed separately in more detail in other NRC documents.
Thus, a commitment to follow this regulatory guide does not imply a commitment to follow the guidelines and requirements of Subdivision 3.2.3.
Fire watches during and immediately following welding                Fire surveillance during and immediately following operations    Similar requirement. Fire operations should be specified,                                      such as welding and heat treating shall be provided when          watch / surveillance 10/28/2010                                                            Housekeeping for Nuclear Power Plants                                            Page 7 of 10
 
H.ousekeeping During the Construction Phas of N                    Quality Assurance Requirements for Housekeeping for                  COMMENTS Power Plants                                                Nuclear Power Plants
:'N45.2 .341973                                              NQA-1 1994 Subpart 2.3 materials are located such that flames, flying sparks, weld      requirements are clarified in spatter, or excessive heat resulting from the operation could    NQA-1 -1994.
cause combustion, with resulting damage to items of the nuclear plant.
Fire protection facilities shall be in service beginning with the  Fire protection facilities shall be in service beginning with the Similar requirements.
initial stages of permanent construction. Pre-fire planning        initial stages of permanent construction. Pre-fire planning shall should be considered as a requirement of the fire protection      be conducted as a requirement of the fire protection procedures procedures or instructions which shall include evacuation of      or instructions, which shall include evacuation of confined confined areas.                                                    areas.
3.3 Materials and Equipment                                        3.3 Material and Equipment Materials and equipment delivered to the work area shall be        Materials and equipment delivered to the work area shall be so    Similar requirements.
placed so that they are accessible but do not hinder construction  positioned, or protected when necessary, to assure that the      N45.2.2 is replaced with progress. However, material and equipment shall be so              quality of the item will not be degraded by the construction      Subpart 2.2 of NQA-1.
positioned that it will not be damaged by construction activity,  activity. The cleaning of important materials and equipment for the plant that is necessary during receiving, storage, and The receiving, storage, and handling activities required by this  handling activities shall be in accordance with applicable standard shall be performed as specified in ANSI N45.2.2. The      requirements.
cleaning of important parts for the plant that is necessary during these activities shall he performed as specified in ANSI N45.2. 1.
3.4 Construction Tools, Supplies, and Equipment                    3.4 Construction Tools, Supplies, and Equipment The use, location, and deployment of construction tools,          The use, location, and deployment of construction tools,          Similar requirements.
supplies, and equipment shall be regulated to keep access and      supplies, and equipment shall be controlled to keep access and work areas clear and prevent conditions that will adversely        work areas clear and to prevent conditions that will adversely affect quality. These provisions shall include, but are not        affect quality. These provisions shall include, but are not limited to such items as the movement of materials to the work    limited to, such items as the movement of materials to the work area, welding and stress relieving leads, power leads, temporary  area, welding and stress relieving leads, power leads, temporary heating equipment, pumps, air and water hoses, welding            heating equipment, pumps, air and water hoses, welding machines, air compressors, hoisting equipment, air tools,          machines, air compressors, hoisting equipment, air tools, grinding tools and burning tools.                                  grinding tools, and burning tools.
3.5 Surveillance, Inspections, and Examinations                    3.5 Surveillance and Inspections Periodic inspection and examination of the work areas and the      Periodic inspection of work areas and construction practices      Similar requirements.
construction practices shall be performed at scheduled intervals  shall be performed at scheduled intervals to assure adequacy of  Throughout subsection 3.5, to assure adequacy of cleanness and housekeeping practices.        cleanness arid housekeeping practices. These inspections shall    the term examination is not These inspections and examinations shall include the following    include the following, as appropriate:                            used in NQA- 1 since it is a as appropriate:                                                                                                                      part of inspection. The term 10/28/2010                                                          Housekeeping for Nuclear Power Plants                                            Page 8 of 10
 
Housekeeping During tfhiConstruction Phase of Nuclear.-              Quality Assurance Requirements for Housekeeping for                    COM      NTS Power Plants              7. .............                      Nuclear Power Plants....          ........
N05.2.3-19.7.3        -NQA-1                                            1994 Subpart 2.3 inspection is favored by the standard.
: 1. Examination of construction site roads, access ways, and        (a) inspection of construction site roads, access ways, and        Similar requirements.
ramps for conditions that may result in damage to items being        ramps for conditions that may result in damage to items being transported or handled.                                              transported or handled;
: 2. Examination of storage area for conformance to procedures        (b), inspection of storage and work areas for conformance to        Similar requirements.
and instructions in the following categories:                        procedures and instructions in the following categories:            Slightly more detail (a) adequacy of access control.                                      (1) adequacy of access control                                      regarding hazardous (b) evidence of damage or deterioration.                            (2) evidence of damage or deterioration                            materials in NQA-1.
(c) adequacy of protection from fires, weather, movement of          (3) adequacy of protection from fires, weather, movement of equipment, and other factors that may result in damage to            equipment, and other factors that may result in damage to stored items.                                                        stored and installed items (d) adequacy of solvent storage facilities.                          (4) adequacy of hazardous chemicals, paints, and solvent storage facilities
: 3. Inspection of work areas for maintenance of environmental        (c) inspection of work areas for maintenance of environmental      Similar requirements.
conditions within specified limits,                                  conditions within specified limits;
: 4. Surveillance over installed items to assure the adequacy of:      (d) surveillance over installed items to assure the adequacy of:    Similar requirements.
(a) maintenance of protection.                                      (1) maintenance of protection (b) preservation of precautionary signs.                            (2) preservation of precautionary signs (c) preservation of item identity.                                  (3) preservation of item identity (d) protection from fire, weather, movement of materials or          (4) protection from fire, weather, movement of materials or equipment and other factors which may result in damage to            equipment, and other factors which may result in damage to installed items.                                                    installed items.
Where these requirements duplicate the requirements of other                                                                            Not a requirement.
standards such as ANSI N45.2. 1, duplicate activities and reports are not required.
: 4. RECORDS                                                          4 RECORDS Copies of approved procedures, reports; personnel training and      Record copies of procedures, reports, personnel qualification      Similar requirements. ANSI qualification records; controlled zone registry, fire and accident  records, zone control registries, fire and accident investigations, N45.2.9 is replaced with investigations; and inspection and examination records shall be      surveillance, and inspection records shall be prepared as          Basic Requirements 17 and prepared and placed with other project records.                      required in this Part (Part 11). These records shall be retained    Supplemental Requirements Final disposition of records shall be in accordance with ANSI        with other project records as required by code, standard,            17S-1 for NQA-1 with N45.2.9.                                                            specification, or project procedures.                              regulatory guidance of Regulatory Guide 1.28 Rev.
3.
10/28/2010                                                            Housekeeping for Nuclear Power Plants                                            Page 9 of 10
 
Housekeeping Duri ng the Constru'ction'Phase of Nuclear.        Quality Asrance Require"s for Hoi    for        COMMENTS, Power Plants                                          Nuclear Power Plants N45.,23-19_73                                        NQA-1 l994 ubpart2.3
: 5. REVISIONS OF AMEERICAN NATIONAL STANDARDS REFERRED TO              IN  THIS DOCUMENT        __________________
When the following Standards referred to in this document are                                              The QAPD addresses the superseded by a revision approved by the American National                                                standards for the program.
Standards Institute, the revision shall apply.
A 10.2-1944 Safety Code for Building Construction N45.2 Quality Assurance Program Requirements for Nuclear Power Plants N45.2. 1 Cleaning of Fluid Systems and Associated Components During the Construction Phase of Nuclear Power Plants N45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants (During the Construction Phase)
N45.2.9 Requirements for Collection, Storage and Maintenance of Quality Assurance Records N45.2.10 Quality Assurance Terms and DefinitionsA 10/28/2010                                                      Housekeeping for Nuclear Power Plants                    Page 10 of 10
 
N45.2.4-1972/IEEE Std 336-1971 Installation, Inspection, and                NQA-1 1994 Subpart..4/ANSI            EE Std 336-1985                COMMENTS .
Testing of Requirements: for Instrumentation and Electric                Installation, Inspection, and Testing Re uirementssfor Equipment During the Construction of Nuclear Power_                Power, Instrumentation, and Control Equipment at Nuclear GeneratlngiStations                                                        Facilities.
Reg. Guide 1.30 8/72 Position C.l states: .ANSI N45.2.4-1972          From NQA-I 1994, SUBPART 2.4, Installation, Inspection, and        Part I of NQA-I-1994 is should be used in conjunction with ANSI N45.2-1971, "Quality          Testing Requirements for Power, Instrumentation, and Control        comparable to the Quality Assurance Program Requirements for Nuclear Power Plants." (It          Equipment at Nuclear Facilities: "Subpart 2.4 consists of          Assurance Program is expected that future revisions of ANSI N45.2.4-1972 will            ANSI/IEEE Std. 336-1985 IEEE Standard Installation,                requirements ofN45.2-1971.
include this provision.)                                              Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment at Nuclear Facilities."
(quoted below)
: 1. INTRODUCTION                                                        1. Introduction 1.1 Scope                                                              1.1 Scope This standard sets forth the requirements for installation,            This standard sets forth the requirements for installation,        Similar requirements.
inspection and testing of Class I and Class IE electric power,        inspection, and testing of power, instrumentation, and control      Regulatory Position instrumentation and control equipment and systems during the          equipment and systems during the construction phase of a            incorporated into the construction phases of a nuclear power generating station. These nuclear facility. These requirements also cover modifications            standard.
requirements are intended to assure that only materials and            and those operating phase activities that are comparable in equipment of acceptable quality are incorporated into the plant,      nature and extent to related initial construction activities of the that quality is maintained and quality workmanship prevails            facility.
throughout the construction process, and that completed                The intent of this standard is to establish requirements for installations conform to specified requirements, so as to promote safety systems equipment. (Safety systems equipment is defined public safety, prevent accidents and mitigate the consequences of in IEEE Std 603-1980 [5]') However, this standard may also be accidents if they occur, and provide a high degree of plant            applied to non-safety systems equipment.
reliability.
Reg. Guide 1.30 8/72 Position C.3 states: Although subdivision 1.1 of ANSI N45.2.4-1972 states that the requirements promulgated apply during the construction phase of a nuclear power plant, these requirements are also to be considered              The numbers in brackets correspond to those of the references applicable for the installation, inspection, and testing of            listed in Section 2.
instrumentation and electric equipment during the operation phase of a nuclear power plant.
1.1.1 In addition to the Class I and Class IE systems, the requirements                                                                          This specific list is not also apply to the following auxiliary equipment that are a part                                                                            included in the 1985 edition, thereof.                                                                                                                                  but the above paragraph
: 1) Connecting cables and raceways                                                                                                          addresses safety systems
: 2) Electric and instrumentation containment penetrations                                                                                  equipment that, based on the
: 3) Instrumentation sensing lines from the process root valves to                                                                          definition referenced, would 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                        Page I of 22
 
N45.2.4-1972/IEEE Std 336-1971 Installation, Inspection, and                NQA-1 1994 Subpart 2.4/ANSISTlEgE        Std 336-1985            .COMMENTS
  'Testing of Requirements for Instrumentation and Electric              Installation, Inspection, and Testing Requirements for Equipment During the Construction of'NuclearlPowe&#xfd;r              Power, Instrumentation, and Control Equipment at Nuclear Generating Stations........                                          .. Facilities and including input transducers                                                                                                        include the items in this list.
: 4) Primary sensing devices (for example, orifices, flow nozzles, venturi tubes, and reference columns)
: 5) Pneumatic instrumentation
: 6) Output control transducers including tubing and piping
: 7) Fluid systems associated with standby generators and transformer cooling systems
: 8) Switchgear fluid systems
: 9) Panels, enclosures, and mountings 1.1.2 These requirements may also be extended to other appropriate                                                                          Not a requirement.
parts of nuclear power generating stations when specified in contract documents.
1.1.3                                                                1.1.1 This standard does not set forth specific requirements for the        This standard does not set forth specific requirements for the  Similar exclusions, these following, though related to the above equipment and systems:        following, though they are related to the above equipment and    items are addressed by other
: 1) Inspection or testing, or both, of welds                          systems                                                          standards or the QAPD.
: 2) Cleaning and flushing of instrument sensing lines                  1) Installation, inspection, and testing of welds
: 3) Aligning or verifying alignment, or both, of Class I rotating      2) Cleaning and flushing of instrument sensing lines equipment                                                            3) Aligning or verifying alignment, or both, of rotating
: 4) Verifying structural integrity of support for Class I or Class IE  equipment electric equipment                                                    4) Verifying structural integrity of supports for equipment For applicable codes on the above refer to Section 9.                5) Activity governed by Section III of [6]
: 6) Preoperational tests of the integrated systems and equipment
: 7) Periodic testing and maintenance after initial operation
: 8) Receiving inspection and test
: 9) Non-destructive examination when required 1.1.2 During the construction phase and when modifications are        New requirement. NQA                                                                      being performed, this standard shall be used in conjunction with  1994 replaces NQA- 1-1983 the applicable portions of ANSI/ASME NQA-l-1983 [1] and          and NQA-2-1983 for the ANSIIASME NQA-2-1983 [2]. During the operations phase this      basis for the QAPD.
standard shall be used with the applicable portions of ANSI/ANS 3.2-1982 [3].
1.2 Applicability                                                    1.2 Applicability 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                    Page 2 of 22
 
N45.2.4-1972/1EEEIStd 336-1971 Installation, Inspection, and                        NQA.A-1 1994 Subpartd2.4/ANSI/IEEE Std .336-1985 .::                CO ME        S SNT.
Testing of Requirements for Instrumentation and Electric                        Installation, Inspection, and Testing Requirements for Equipment During the Construction of Nuclear Power                    Power, Instrumentation, and ControlEquipment at Nuclear Stations.............          ........... renerating            Facilities The requirements set forth in this standard apply to the work of            The requirements set forth in this standard apply to the work of    Similar requirements.
any organization that participates in the construction phase of            any organization that participates in the installation, inspection,  Supplementary requirements electric and instrumentation equipment and systems from the                testing, or modification of power, instrumentation, and control      for construction of multi-unit time that the equipment is turned over to the installers until the          equipment and systems in a nuclear facility from the time that      stations and operating plants time it is integrated into systems in a condition to commence              the equipment is turned over for installation until it is integrated is addressed in Section 10 of system performance testing. The requirements of this standard              into a system. The extent to which the individual requirements      the 1985 edition.
are basic minimum requirements which relate to nuclear power                of this standard apply either wholly or in part depends upon the generating stations during construction or construction phases of          nature and scope of the work to be performed and the modification or expansion. For supplementary requirements                    importance of the item or service involved.
applicable to the construction phase of multi-unit stations, including expansions to existing stations, refer to Appendix A.
1.3 Responsibility                                                          1.3 Responsibility The organization or organizations responsible for establishing the          It is the responsibility of the organization invoking this standard Similar requirements.
applicable requirements for the activities covered by this standard        to identify the equipment and systems to which this standard is shall be identified, and the scope of their responsibilities shall be      applicable. The planning operations stipulated in Section 3.2 documented. The work of establishing practices and procedures              shall specify the inspections and tests to be performed on the and providing the resources in terms of personnel, equipment and            identified equipment and systems consistent with this standard.
services necessary to implement the requirements of this                    The work of establishing practices and procedures and standard, may be delegated to other organizations, and such                providing the resources, in terms of personnel, equipment, and delegation also shall be documented. It is the responsibility of            services, to implement the requirements of this standard, may be each organization participating in site construction activities to          delegated to other organizations. Such delegation shall be comply with procedures and instructions issued for the project.            documented. In any case, the organization invoking this standard shall retain responsibility for overall program effectiveness.
1.4 Definitions The following definitions are provided to assure a uniform                                                                                      The definitions presented in understanding of select terms as they are used in this standard.                                                                                N45.2.4-1972/IEEE Std 336-1971 Section 1.4 are not presented in NQA- 1.
Class I Equipment - Equipment that is essential to the safe shutdown and isolation of the reactor or whose failure or damage could result in significant release of radioactive material.
Class IE Electric Systems - The systems that provide the electric power used to shut down the reactor and limit the release of radioactive material following a design basis event.
10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                            Page 3 of 22
 
,N45.2.4-1972/IEEF Std 336-1971 Installation, Inspection, and                NQA-I 1994gSubpart 2.4/NSJ/IEEE: Std 336-1985                "        OMMENTS Testing~of Requirements for Instrumentation and Electric              Igstallationlnspection andTestingRequirements for Eq"upment During the Construction of Nuclear Power                Power, Instumentaton, adCnot              Equipment atuclearac.litie, Generating Stations                          Po.e....      uzenatinFacilities
                                                                                        ,ns                      q p.en..a.
System Performance Testing - Tests performed on completed systems, including all their electric, instrumentation, controls, fluid and mechanical subsystems under normal or simulated normal process conditions of temperature, flow, level, pressure, etc.
Set Point - A predetermined level at which a bistable device changes state to indicate that the quantity under surveillance has reached the selected value.
Lay-Up - Idle condition of equipment and systems during and after installation, with protection measures applied as appropriate.
1.5 Referenced Documents                                              2. References Other documents that are required to be included as a part of this When the following standards referred to in this document are          Commitment to specific standard, as well as the issue or edition of such documents, are      superseded by a revision approved by the American National          editions of standards is either identified at the point of reference or described in Section Standards Institute, the revision is not mandatory until it has        controlled through the 9 of this standard.                                                    been incorporated as part of this standard.                        QAPD.
[1] ANSI/ASME NQA-l-1983, Quality Assurance Program Requirements for Nuclear Power Plants.
[2] ANSI/ASME NQA-2-1983, Quality Assurance Requirements for Nuclear Power Plants.
[3] ANSI/ANS 3.2-1982, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.
[4] IEEE Std 498-1985, IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in the Construction and Maintenance of Nuclear Power Generating Stations.
[5] IEEE Std 603-1980, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.
[6] 1984 ASME Boiler and Pressure Vessel Code.
: 2. GENERAL REQUIREMENTS                                                3. General Requirements Measures shall be established and implemented for documenting          Measures shall be established and implemented for planning          Similar requirement.
installation, inspection, and testing operations to verify            and control of installation, inspection, and testing activities to conformance to specified requirements.                                verify conformance to specified requirements.
2.2 Prerequisites                                                      3.1 Prerequisites The following conditions shall have been met as required by                                                                                Not specifically addressed in 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                      Page 4 of 22
 
N45.2.4-19721EEE.........
Std
                        ~ 336-1971
                            ~~      ~Installation,
                                      '"""' ~    ~ Inspection,&#xfd;and  .~~~&#xfd;Pn
                                                      "'"~ ~ " ~"... *;.. NQA-1 1994 Subpart 2.4/ANSI/IEEE.Std i*ntla*Inspcton,                            336-1985 "*E*...........
nd T.stint! Requir*ent*:6*,          "    O        NTS Testing of Requirements for lnstrumentation and Electric                Instao#n, Iseto        and.Tesrments for Equipment During the Co.st ru.ton      . f Nuclear Power        Power, Instrumentation, and Control Equipment at Nuclear Generating Stations                                                    Facilities other standards before the requirements set forth in this standard                                                                  the 1985 standard.
are applied.
: 1) Qualification of personnel assigned to the construction phase                                                                    Section 3.7 of the 1985 has been in accordance with the requirements of appropriate                                                                          standard covers Personnel codes and standards.                                                                                                                Qualification. Personnel qualification is addressed as NQA 1 1994, Basic Requirement 2. A separate Table for NQA-1 Basic Requirement 2 discusses personnel qualification.
: 2) Systems have been designed and engineered and equipment                                                                          Not specifically addressed in has been specified in accordance with the published applicable                                                                      the 1985 standard. Design standards and specifically within the framework of the Quality                                                                      control is addressed as NQA Assurance program described in the Safety Analysis Report.                                                                            1 1994, Basic Requirement
: 3. A separate Table for NQA-1 Basic Requirement 3 discusses design control.
: 3) Materials have been selected, and equipment has been                                                                              Not specifically addressed in fabricated and shop assembled, in accordance with the                                                                                the 1985 standard. Control of specifications and the applicable published codes and standards,                                                                    purchased items is addressed the conformance to which has been demonstrated by the                                                                                as NQA 1 1994, Basic manufacturer.                                                                                                                        Requirement 7. A separate Table for NQA-1 Basic Requirement 7 discusses control of purchased items.
: 4) Materials and equipment have been shipped, received, handled                                                                      Not specifically addressed in and stored in accordance with the requirements of applicable                                                                        the 1985 standard. Handling, codes, standards, and manufacturers' recommendations to                                                                              storage, and shipping is preserve their integrity and prevent physical, mechanical, and/or                                                                    addressed as NQA 1 1994, electrical damage.                                                                                                                  Basic Requirement 13. A separate Table for NQA-1 Basic Requirement 13 discusses handling, storage, and shipping.
10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                  Page 5 of 22
* 745ti.4-1972oEEk`Stdn,
                                                        -i I.  . andd      N      1199S 12*194*5    it.
b0 p.... AN2to StEEninspection, St 3A36-1985 3QA7- .S          COMMENTS' O TesineofReqirmens fr Istumetaton ndElectric                  Installation, Inspecti~on,.and Testing Requiirements for Equipment During the Construction of Nuclear Power                  Power, Instrumentation, and Control Equipment a* Nuclear
                                                                          .Generating
                                                                                    .... Sao ..        Facilities
: 5) The following documents relating to the specific equipment to The following applicable documents relating to the specific                Similar requirement.
be installed are available at the construction site                      equipment to be installed shall be available in legible form at a predetermined retention area or area of usage.
a) The latest applicable approved-for construction drawings                1) The latest applicable approved-for-construction drawings      Similar requirement.
b) Installation specifications                                            2) Installation specifications c) Manufacturers' instructions                                            3) Manufacturers' instructions d) Evidence of compliance by manufacturer with purchase                  4) Evidence of compliance by manufacturer with purchase requirements including quality assurance requirements                    requirements, including quality documentation e) Records of inspections and tests during on-site storage and            5) Records of inspections and tests during receiving and on-site handling,                                                                storage, handling, and maintenance.
2.1 Planning                                                              3.2 Planning The installation, inspection, and testing activities shall be            The installation, inspection, and testing activities shall be    Similar requirement.
planned and outlined to define the operations to be used and the          performed in accordance with documented plans that define the systematic, sequential progression of operations for each item or        operations to be used, the systematic, sequential progression of system, the responsibilities of parties concerned for each                operations for each item or system, the responsibilities of operation, and the measures employed to preserve the quality of          parties concerned for each operation, and the measures equipment. Planning shall take into account the need for the              employed to preserve the quality of equipment. Planning shall preparation and control of procedures and work instructions as            take into account the need for the preparation and control of necessary to comply with the requirements for installation,              procedures and work instructions necessary to comply with the inspection, and testing of components and systems. Planning              requirements for installation, inspection, and testing of shall include a review of the system, and component design                equipment and systems. Planning shall include a review of the specifications and drawings, and of the construction work plans          system and equipment specifications and drawings and of the and schedules, to assure that installation, inspection and testing        construction work plans and schedules to assure that activities have been incorporated, and that they can be                  installation, inspection, and testing activities have been accomplished as specified, and that time and resources are                incorporated and that they can be accomplished as specified.
sufficient to accomplish the required actions.
2.3 Procedures and Instructions                                          3.3 Procedures and Instructions Installation, inspection, and test procedures and work instructions      Procedures shall be prepared and documented as determined by Similar requirement.
shall be prepared and documented for those activities falling            the planning in 3.2. These procedures and instructions may be within the scope of this standard.                                        in the form of manuals or drawings.
These documents shall be kept current and revised as necessary            These documents shall be kept current by controlled              Similar requirement.
to assure that installation, inspections, and tests are performed in      supervision so that installation, inspections, and tests are accordance with latest information and shall include as                  performed in accordance with the latest approved design and appropriate:                                                              manufacturers' instructions. The documents shall include or reference:
10/28/2010                          Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                    Page 6 of 22
 
N4,.2.4-1972IIEE Stdi336-1971 Installation, Inspection, and                  NQA.-1 1994 Su.part...4/AN.. .EEE Std 336-1485-                      C.MMENT
  .Testing of Requirements for Instrumentation and Electric                Instalation,.Inspection, and Testing Requiremennts for
    .Equipment During the Construction of Nuclear Power                Power, Instrumentation,-and. Control Equipment at Nuclear
                      ..Generatin2 Stations                                                        Facilities (1) Installation specifications                                        1) Installation specifications                                    Similar requirement, (2) Inspection and test objectives                                    2) Inspection and test objectives                                  references and other (3) Precautions to avoid component or system damage during            3) Precautions to avoid equipment or system damage during          pertinent items are added to testing or inspection                                                  installation, testing, or inspection                              the list.
(4) Inspection and test equipment required                            4) Inspection and test equipment required (5) Sequence of tests (if applicable)                                  5) Sequence of tests (6) Sequential actions to be followed                                  6) Sequential actions to be followed (7) Frequency of inspection or test                                    7) Frequency of inspection or test (8) Prerequisites                                                      8) Test prerequisites (9) Approvals                                                          9) Appropriate approvals (10) Data report form                                                  10) Suitable form for reporting data (11) Identification of test equipment and date of required            11) Provision for identification of test equipment and date of recalibration where required for interpretation of test results        next required recalibration (where required) for interpretation of (12) Inspection and test acceptance limits                            test results
: 12) Inspection and test acceptance limits
: 13) References
: 14) Other pertinent items The above items shall be included as a checklist and shall be      New requirement.
marked as required or not appropriate when preparing              Alternative proposed to procedures or instructions,                                        administrative controls in procedures and instruction in lieu of a checklist.
2.4 Results                                                            3.4 Results Inspection and test results shall be documented in a suitable test    Inspection and test results shall be documented in a suitable test Similar requirement.
report or data sheet. Each report shall identify the item to which    report or data sheet. Each report shall identify the item to which it applies, the procedures or instruction followed in performing      it applies, the procedures or instructions and its revision number the task, and the identification of the following:                    used in performing the task, and the identification of the following:
: 1) Conditions encountered which were not anticipated, including      1) Conditions encountered that were not anticipated, including Similar requirement.
nonconformance                                                        nonconformance
: 2) Identity of inspector or tester                                    2) Identity of inspector or testor
: 3) Completion date                                                    3) Completion date Test reports and data sheets shall include an evaluation of the        Test reports or data sheets shall include an evaluation of the    Similar requirement.
acceptability of inspection and test results and provide for          acceptability of the results and provide for identifying the identifying the individual who performed the evaluation,              individual who performed the evaluation.
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.N45.2.4-1972/IEEE Std 1971Insta!latlon, Inspection, and          .    'NQA-1 1994 Subpart 2.4/ANSIAEE*Std 336-1985 ':COMMENTS for Instrumentation and Eletric 9Testingof Requirements""Installation,                                                Inspection, andTestingoRquireents for.                                ~l
:..EquipmentDuring the onstuction of Nuclear Power                    Power, Instrumentation, and.Controd EauNpmenatuclear                  .
t< Generating Stations i              .1I                                    Fac~itles, 2.5 Measuring and Test Equipment                                      3.5 Measuring and Test Equipment 2.5.1 Selection Inspection and testing equipment with acceptable accuracy for          Measuring and test equipment used to determine compliance      NQA- 1 addresses M&TE in performing the required function shall be selected. When general      with specifications shall be controlled in accordance with the Subpart 2.16 (IEEE Std 498-voltage levels, flow directions, or other parameters are checked,      requirements of IEEE Std 498-1985 [4].                        1985).
an instrument without high precision may be used. When characteristics, efficiencies, capabilities, or other properties are measured to appraise compliance with specifications, the instrument must have adequate accuracy to determine the measured quantity to the precision required by the stated limits of the specifications. Use shall be made of approved industry standards relating to measuring procedures. Test equipment and/or apparatus supplying electrical, mechanical, or other test inputs shall have adequate capacity and be compatible with items under test so that the results will not be distorted.
2.5.2 Calibration and Control Measuring and test equipment used to determine compliance with                                                                        NQA-l addresses in Subpart specifications, shall be adjusted and calibrated at prescribed                                                                        2.16.
intervals against certified equipment having known valid relationships to nationally recognized standards. If no national standards exists, the basis for calibration shall be documented.
Records of the calibrations shall be maintained and equipment suitably marked to indicate date of next required calibration.
When inspection and testing equipment are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested. Test equipment found to be out of calibration shall be clearly identified as such.
2.6 Nonconforming Items                                                3.6 Nonconforming Items Defects, deficiencies, discrepancies, or other nonconforming          Defects, deficiencies, discrepancies, or other nonconforming  Similar requirement.
situations shall be resolved in accordance with established            situations shall be resolved in accordance with established procedures. These procedures shall provide for identifying,            procedures. These procedures shall provide for identifying, documenting, and obtaining authorization for resolving each            documenting, and obtaining authorization for resolving each nonconforming situation.                                              nonconforming situation.
13.7 Personnel Qualification 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                Page 8 of 22
 
N45.2.4- 9721NEEE Std .A336-1971                                and        N.A-1994 Subpart 2A4/ANSI.IEEE Std 336-1985                              COMMENTS Testing of Requirements foir Instrumentation andEeti                    Installation, Inspection, and Testing R~equiremnents for...
During the. Construction of N uclear Power
        .Equipment                                                    Power, Instrumentation, and Control Equipment at Nuclear Generating SttosFacilties......                                                                          ..........
Personnel performing the verifications required by this standard Qualification is a shall be qualified in accordance with an approved quality              prerequisite under N45.2.4, assurance program.                                                    Subsection 2.2, item 1.
Personnel qualification is addressed as NQA 1 1994, Basic Requirement 2. A separate Table for NQA-l Basic Requirement 2 discusses personnel qualification.
: 3. PRECONSTRUCTION VERIFICATION                                        4. Preinstallation Verification While it is recognized that the requirements for initial receipt      Verifications shall be performed just prior to installation.          Similar requirements.
inspections and storage are covered by another standard, ANSI N45.2.2, it is necessary to verify that the quality of an item has not suffered during the interim period. It is not intended to duplicate inspections but rather to verify that items are in a satisfactory condition for installation. The verification shall include:
: 2. Verification that approved procedures, instruction manuals,        1) The following, relating to the specific equipment to be            Similar requirements, 1985 and/or any special work instructions if required for specific          installed, shall be available at the construction site in legible      edition includes construction equipment are available                                                form:                                                                  drawings and removes a) The latest applicable approved-for-construction drawings            approved instruction b) Installation specifications, procedures, or any special work        manuals.
instructions
: 1. Verification that materials and equipment received by the          2) Identification of materials and equipment in accordance with        Similar requirements.
installers are identified in accordance with the latest approved-for the latest approved-for-construction drawings, equipment lists, construction drawings, equipment lists, and specifications            and specifications
: 3. Checking of records of protective measures maintained during 3) Documentation of protective measures taken during storage                  Similar requirements.
storage for conformance to storage requirements
: 4. Visual examination of materials and equipment to assure            4) Physical integrity by visual examination of materials and          Similar requirements.
physical integrity such as absence of physical damage, rust or        equipment for damage, corrosion, contamination, and corrosion, contact contamination, and condensation                    condensation
: 4. INSTALLATION                                                        5. Installation 5.1 Equipment Placement Equipment shall be located, installed, assembled, and/or              Equipment shall be located, installed, assembled, and connected Similar requirements.
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:N45.2.4-197211EEE Std. 3316-1971 Instailation, Inspecin an                          4z:'11994 Subpart 2.4/ANSWlEEE Std 316-1985                    COMMENT-S Testing of Requirements for Instrumentation and Electric                I"&#xfd;Jnstallation, Inspection, and Testing Requirements for Equipment.During the Construction of Nuclear Power                Power, Instrumentation, and Control Equipment at uclear Generatiug Stations                                                          Facilities                        ___________
connected in strict accordance with the following as applicable:      in strict accordance with the following:
: 1. Latest approved-for-construction drawings                          1) Latest approved-for-construction drawings                      Similar requirements.
: 2. Manufacturers' instructions                                        2) Installation specifications and procedures, where required by
: 3. Installation specifications and procedures                          the planning of 3.2 5.2 Precautions Care shall be especially exercised in following the provisions of      Care shall be exercised in following the provisions of the        Similar requirements, but the the above documents for operations such as:                            documents listed in 5.1 for operations such as:                  1985 edition has been
: 1. Cable pulling                                                      1) Cable pulling                                                  updated to include additional
: 2. Cable splicing                                                      2) Cable splicing                                                appropriate items based on
: 3. Cable terminating                                                  3) Cable terminating                                              operating experience and
: 4. Cable routing including maintaining required separation            4) Cable and instrument sensing line routing, including          regulatory requirements.
between redundant systems                                              maintenance of required separation between redundant systems
: 5. Tagging and/or identifying various items including cable            5) Tagging or identifying, or both, various items, including
: 6. Installing electric and instrumentation penetration assemblies      cable, and temporary conditions and assuring the integrity of the containment seals                    6) Installing electric and instrumentation penetration assemblies and assuring the integrity of the containment seals
: 7) Installation of fire stops and fire barriers
: 8) Installation of instrumentation piping or tubing
: 9) Mounting and supporting of equipment
: 10) Removal of temporary shipping supports and holddown bolts
: 11) Installa~tion of environmental and pressure seals
: 5. VERIFICATION DURING CONSTRUCTION                                    6. Verification During Installation Verification during installation shall include inspections and    In context with the below tests performed in accordance with the QA program                subsections, this is similar to requirements.                                                    the N45.2.4 standard.
5.1 Inspections                                                        6.1 Inspections Surveillance of construction activities shall include inspections of Inspections performed during installation shall include the        Similar requirement, the work areas in progress to assure conformance to applicable        following:                                                        reference to surveillance is requirements. Inspections shall include the following, as                                                                                omitted and just the term appropriate:                                                                                                                            inspection is used.
5.1.1 Inspections to Verify Correctness of Installation                6.1.1 Inspections to Verify Correctness of Installation Inspection shall be made to verify, that equipment is being            Inspections shall be performed to verify that equipment is being  Similar requirement.
located, installed, assembled, and/or connected to comply with        located, installed, assembled, and connected to comply with latest approved-for-construction drawings, manufacturers'              latest approved-for-construction drawings and installation 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                    Page 10 of 22
 
N45.2.4-1972/11EE Std 336-1971 Installation, Inspection, and.              NQA-1.1994%Subpart 2.4/ANS          .EER Std 336-1098 5..M...S Testing of Requirements for Instrumentation and Elecctri              Installation, Inspection, and Testing Requirements for During~th Construction of Nuclear Power
        .Equipmen~t                                                  Power, Instrumnetation, and Control Equipment at Nuclear
                    .. Generatiijg&#xfd; Stations                                                      Facilities instructions, and installation specifications.                        specifications and procedures.
Such inspections shall include, as appropriate, verification of:      Inspections shall include such items as verification of:        Similar requirement, but the (1) Leveling and alignment                                            1) Leveling and alignment (nonrotating equipment)              1985 edition includes (2) Clearances and tolerances                                        2) Clearances and tolerances                                    additional items that are (3) Proper location and routing of cables and sensing lines          3) Location, support, and routing of cables and sensing lines    representative of industry (4) Tightness of connections and fastenings                          4) Tightness of connections and fastenings and use of proper    operating experience.
(5) Freedom of movement                                              tools (6) Correct polarity                                                  5) Freedom of movement (7) Proper grounding                                                  6) Polarity (8) Terminations                                                      7) Grounding and shielding (9) Fluid levels and pressures                                        8) Terminations (10) Absence of leaks                                                9) Fluid levels and pressures (11) Physical integrity                                                10) Absence of leaks (12) Identifications                                                  11) Physical integrity
: 12) Identifications
: 13) Circuit fusing
: 14) Equipment rating
: 15) Fire stops and fire barriers
: 16) Installation of mountings and supports
: 17) Lubrication of bearings
: 18) Environmental and pressure seals 5.1.2 Inspections to Verify Housekeeping                              6.1.2 Inspections to Verify Housekeeping and Protective Measures Inspections shall be made to verify adequacy of housekeeping, in      Inspections shall be performed to verify the adequacy of        Similar requirement, the work areas. Adequacy of barriers and protection covers shall be      housekeeping in work areas [2]. Inspections shall be performed  1985 standard contains more evaluated to assure that items will not be damaged as a result of    on a regular schedule and properly documented to verify that    detail on the inspection adjacent construction activity. Adequacy of protection measures      the following protective measures are adequate.                  requirements.
shall be evaluated to assure that equipment being used for testing    1) Protective measures applied for lay-up during construction will not be damaged.                                                  are in accordance with procedures or specifications
: 2) Protective measures to prevent damage as a result of adjacent activity
: 3) Protective measures to prevent damage to measuring and test equipment during field use 5.1.3 Inspection of Temporary Conditions                              6.1.3 Inspections of Temporary Conditions Inspections shall be made to verify adequacy of protective          IInspections shall be performed to verify that all temporary      Similar requirement, 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                  Page I11 of 22
 
N45.2.4-1972/IEEE Std 336-1971 Installation, Inspection, and                  NQA-1 1994 Subpart 2.4/ANSI/IEEE Std 336-1985                        COMMENTS Testing of Requirempents for Instrumentation and Electric                Installation, Inspection, and Testing Requirements for Equipment During the Construction of Nuclear Power                Power, Instrumentation, and Con*ro! Equipment at Nuclear Fa.cilities measures applied for lay-up during construction. All temporary          connections, such as jumpers and bypass lines and temporary        protective measures connections, such as jumpers and bypass lines, and temporary set        setpoints of control equipment, are clearly identified and        addressed in 6.1.2 above for points of control equipment shall be clearly identified and            documented so that subsequent restoration can be ascertained      the 1985 standard.
documented so that subsequent restoration can be ascertained            prior to placing the item in service.
prior to placing the item in service.
5.2 Tests                                                              6.2 Tests Surveillance of construction activities shall include tests            Manufacturers' tests on fabricated items may be accepted for      The 1985 standard is not as performed in accordance with written test procedures to verify          equipment not disturbed during the construction phase. Tests      specific about the tests; that items being installed comply with specified quality and            performed during installation shall be those specified in the      rather it refers back to those performance requirement. These tests should be performed at            planning in 3.2 and shall include a selection of the following,    identified during planning.
appropriate points in the construction phase as access permits or when questions arise as to the quality of components or workmanship. Where preliminary operation of equipment, during construction, is utilized for a testing function, the purpose of the test, its scope, and results shall be clearly established and documented. Tests shall be repeated if construction or associated activity affects the results of the tests. The need to repeat a test shall be ascertained at the time of preparing for post construction testing in accordance with 6.2. Tests during construction shall include the following:
5.2.1 Electrical Tests                                                  6.2.1 Electrical Tests The following electrical tests shall be performed:                      1) Tests to ascertain circuit continuity, absence of improper    Similar requirement.
: 1. Tests to ascertain circuit continuity, absence of short circuits,  grounds and short circuits, correct polarity and correct direction correct polarity and correct direction of rotation                      of rotation
: 2. Tests to ascertain proper functioning of systems, including          2) Tests to ascertain proper phasing and functioning of indicating meters, recorders, transducers, targets and lamps,          equipment, including indicating meters, recorders, transducers, enunciators and alarms, controls and interlocks                        targets and lamps, annunciators and alarms, controls, interlocks,
: 3. Voltage breakdown tests on liquid insulation                        protective relays and breakers
: 4. Over-potential tests as specified                                    3) Voltage breakdown tests on fluid insulation
: 5. Insulation resistance measurements as specified When over-          4) Overpotential tests as specified potential tests are performed, the values shall conform to the          5) Insulation resistance measurements as specified applicable codes and standards. The manufacturers                      When overpotential tests are performed, the manufacturers' recommendations shall always be considered.                            recommendations shall be considered.
5.2.3 Physical and Chemical Tests                                      6.2.2 Physical and Chemical Tests These tests shall include, as appropriate:                              1) Chemical analysis of fluids for oxygen or moisture content    Similar requirement.
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N45.2.4-1972/IEEE Std 336-1971 Installation, Inspection, and                NQA-I 1994 Subpart 2.4/ANSIIEEE Std 336-1985:..
* OMVENTS Testing of Requirements for Instrumentation and Electric                Installation, Inspection, and Testing Requirements for During the Construction of Nuclear Power
          .Eqipment                                                  Power, Instrumentation, and Control Equipment at Nuclear                  .
Generating Stations                                                        Facilities                          ____"____'_______""'"_
: 1. Chemical analyzing of fluids for oxygen or moisture content        and purity and purity                                                            2) Radiation testing to confirm that radiation sensors and
: 2. Radiation sensitivity testing to confirm that radiation sensors    controlling devices are properly functioning.
and controlling devices are properly functioning These tests shall be in accordance with the applicable codes in Appendix B.
5.2.2 Mechanical Tests                                                6.2.3 Mechanical Tests Mechanical tests shall be performed to ascertain that electric        Leak or flow tests shall be performed to demonstrate the        Similar requirement.
and/or instrumentation components or systems can withstand            operation of electric instrumentation equipment or systems. As  Manufacturers test statement systems pressure ratings. As a minimum, such tests shall be            a minimum, such tests shall be applied to pressure sensing and  is addressed in Section 6.2 of applied to pressure sensing and transmitting devices operating in      transmitting devices operating in steam, hydraulic, or pneumatic the 1985 standard.
steam, hydraulic, and vacuum systems and their hydraulic or            interconnecting piping or tubing and associated instruments to pneumatic interconnecting piping or tubing and associated              ascertain that they can withstand systems pressure ratings.
instruments. Pressurized equipment which is a part of electric        Pressurized equipment that is a part of electric apparatus, such apparatus such as heat exchangers, circulating systems, actuating      as heat exchangers, circulating systems, actuating systems, and systems, and electric and instrumentation containment                  electric and instrumentation containment penetrations, shall be penetrations shall likewise be tested if site assembled or            tested.
fabricated. Manufacturer's tests on fabricated items may be accepted for equipment not disturbed during the construction phase. These tests shall be in accordance with the applicable codes and standards. If equipment is assembled at the construction site, tests shall be conducted after the assembly is completed even though the components may have been previously tested.
: 6. POST-CONSTRUCTION VERIFICATION                                      7. Post-Installation Verification 6.1 Inspection                                                        7.1 Inspections Installed equipment and systems shall be inspected to verify the      Installed equipment and systems shall be inspected to verify    Similar requirement.
following:                                                            that:
: 1. That equipment and materials have not sustained damage              1) Equipment and materials have not sustained damage during during installation                                                    installation
: 2. That good and proper workmanship has prevailed                      2) Good and proper workmanship has prevailed
: 3. That the installation has been made in accordance with              3) The installation has been made in accordance with specified specified requirements                                                requirements
: 4. That all nonconforming items have been satisfactorily resolved      4) All nonconforming items have been satisfactorily resolved
: 5. That appropriate protective measures are applied for lay-up        5) Appropriate protective measures are applied for lay-up after after installation                                                    installation 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                          Page 13 of 22
 
N45.2.4*1972*E;EE StO 336-1971 Installation, Inspection, and                  NQA-1 1994 Subpart 2.4/ANSIEEE Std 336-1985                              MME.NT Testing of Req uirements for Instrumentation and Electric                Installation, Inspection, and Testing Requirements for Equipment 1)Du rmg nthe Construction of.Nuclear. Power:            Power, Instrumentation, and Control Equipment at Nuclear Generating Stations                    .        .                          Facilities.
: 6. That all temporary conditions such as jumpers, bypass lines          6) All temporary conditions, such as jumpers, lifted leads, and temporary set points have been clearly identified so that          bypass lines, and temporary setpoints, have been clearly subsequent restoration can be ascertained prior to placing the          identified so that subsequent restoration can be ascertained items in service                                                        prior to placing the items in service.
To satisfy the above objectives, inspections defined in 5.1 shall      To satisfy the above objectives, it may be necessary to repeat be repeated, as appropriate.                                            some of the inspections defined in 6.1.
6.2 Tests                                                              7.2 Tests Installed equipment and systems shall be tested to demonstrate          Installed equipment and systems shall be tested to demonstrate    Similar requirement.
that the installation has been made in accordance with design          that they have been installed in accordance with design requirements and that the operation gives the desired result.          requirements and that the operation gives the desired result.
Temporary electrical connections, temporary piping sections,            Temporary electrical connections, temporary piping sections, abnormal chemical solutions, unspecified setting of devices, the        abnormal chemical solutions, unspecified setting of devices, the fixing of a moving component, or the effecting of any other            temporary blocking or the effecting of any other abnormality abnormality if made previously shall be rectified before final          previously made shall be rectified before final testing except in testing except in cases where fuel loading or other critical            cases where fuel loading or other operations prevent using the operations prevent using the complete assembly for the test. In        complete assembly for the test. In these instances, a documented these instances, a documented notice shall be prepared stating the      notice stating the temporary test conditions shall be prepared substitutions that existed for the test. In final testing that precedes and be referenced to the appropriate test report or data sheet. In system performance testing, normal system readout devices and          final testing that precedes preoperational testing, normal system installed transducers shall be used as far as possible to monitor      readout devices and installed transducers shall be used as far as the operation. Where the installed equipment is not adequate for        possible to monitor the operation. Where the installed the purpose of conducting tests, special measuring instruments          equipment is not adequate for the purpose of conducting tests, and simulating devices shall be used. Test equipment used shall        special measuring instruments and simulating devices shall be have adequate capacity and be compatible with system under test        used. Test equipment used shall have adequate capacity and so that the results will not be distorted.                              tolerance and be compatible with the system under test.
6.2.1 Equipment Tests                                                  7.2.1 Equipment Tests Tests shall be performed to verify that the quality of installed        Tests shall be performed to demonstrate that the installed        Similar requirement.
equipment has not deteriorated during the construction phase.          equipment is in an acceptable condition to be energized where      Alternative for labeling Tests and shakedown runs shall be made on energized systems            manufacturers' tests or calibrations cannot be accepted (see 6.2). installed measuring and test where necessary to evaluate operations and to properly condition        Tests and shakedown runs shall be made on energized systems        equipment addressed in the for service (for example, the seating of brushes or bearings, the      where necessary to evaluate operation and to properly condition    QAPD Part II, Section 12.2.
stabilization of instrumentation and bum-in of electronic              for service (for example, the seating of brushes or bearings, the devices). Tests shall be made to assure that instrumentation and        stabilization of instrumentation and burn-in of electronic control channels are properly calibrated. In addition, specific        devices). Tests shall be made to assure that instrumentation and tests shall be made at critical levels such as "set points" in a        control channels are properly calibrated. If the calibration is 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                    Page 14 of 22
 
N45.2.4-1t972/IEEE Std.336-1971 Installation, In'spection, and              NQA-1 1994 Subpart 2.4/ANSI/IEEE S.td 336-1985                      CO      IMENTS Testing of Requirements for instrumentation and Electric                Installation, Inspection, and Testing R~equirements for Equipment During the Construction of Nuclear Power                Power, Instrumentation, and Control Equipment at Nuclear Generating~Stations,                                                        Facilities manner simulating the approach toward the set point. These            dependent upon location or orientation, then calibrations shall calibrations shall be made with these devices in their normal          be made with these devices in their normal positions. Tests shall positions if the calibration is dependent upon location or attitude. be made to determine that proper operation is obtained over the Tests shall be made to determine that proper response is obtained      range of the device. Particular attention shall be given to over the operating range of the device. Particular attention shall    verifying independence and dependence, as appropriate, of the be given to verifying independence and dependence, as                  elements of the systems. Items requiring calibration shall be appropriate, of the elements of the systems. Items requiring          identified by tags or labels indicating the identity of the person calibration shall be tagged or labeled on completion indicating        who performed the calibration and the date of the next required date of calibration and identity of person that performed the          calibration.
calibration.
6.2.2 System Tests                                                    7.2.2 System Tests These tests shall be made to verify that all parts of a system        Tests shall be made to verify that all parts of a system properly  Similar requirement.
properly coordinate with each other. Tests shall be made with          coordinate with each other. Tests shall be made with attention attention given to demonstrating required independence and            given to demonstrating required independence and dependence dependence of subsystems. Consideration shall be given to              of subsystems. Consideration shall be given to the need for demonstrating freedom from unwanted or harmful effects of              demonstrating freedom from unwanted or harmful effects of conducted or induced electrical noise. A review shall be made of      Conducted or induced electrical noise. A review shall be made all testing that has preceded the final integrated system testing      of testing that has preceded the final integrated system testing, including both the tests made on assemblies and components with        including the tests made on equipment with particular attention particular attention given to those that demonstrate functional or    given to those that demonstrate functional or operational operational results. When these tests serve as a prerequisite or a    results. When these tests serve as a prerequisite or a part of the part of the final system test, a review of construction activity      test of the completed system, a review of construction activity which may have affected the results shall be made. The final          that may have affected the results shall be made. The final construction-phase testing shall be made with all assemblies and      construction-phase testing shall be made with all equipment of components of subsystems complete except where a critical              subsystems complete except where an operation requires that operation requires that temporary, electrical connections, piping      temporary electrical connections, piping sections, or structural sections, or structural supports be installed to make the tests.      supports be installed to make the tests.
: 7. DATA ANALYSIS AND EVALUATION                                        8. Data Analysis and Evaluation Procedures shall be established for processing inspection and test    Procedures shall be established for processing inspection results Similar requirement.
data and their analysis and evaluation. These procedures shall        and analyzing and evaluating test data. These procedures shall include acquisition and reduction of inspection and test data for      include requirements for reduction of inspection and test data prompt evaluation against acceptance criteria, operating limits        for review or evaluation against acceptance criteria.
and performance standards.
The data processing procedures shall provide for "on-the-spot"        The data shall be analyzed and evaluated to verify                Similar requirement, but evaluation to determine the validity of the inspection and test        completeness, achievement of objectives, and correct operation    does not require "on-the-10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                    Page 15 of 22
 
N45.2.4-1972/11EEE Std 336-1971.Installation, Inspection, and .....          QA-1 1994 S p.art 2".4/ANS EEE Std .36-1985.........                    OMME.NTS Testing of Requirementsfor Instrumentation and Electric                Installation, Inspection, and Testing Requirements for, Equipment During the Construction of Nuclear Power:              Power, Instrumentation, and.Control Equipment at Nuclear Generating Stations                                                      Facilities ...                            _...___..__._______
results, the appropriateness of continuing the inspection or test. of equipment and systems, and to identify any additional          spot" evaluation.
The data shall be analyzed and evaluated to verify completeness inspection or tests required.
of results, achievement of inspection and test objectives, and operational proficiency of equipment and systems; to identify additional inspection and/or tests required; and to identify necessary changes to the installation inspection or test procedures. Inspection and test results that include inspection and test data, together with a report of data analysis and evaluation, shall be provided as specified in Section 8.
: 8. RECORDS                                                            9. Records Record copies of completed procedures, reports, personnel            Copies of construction records such as approved procedures,        Similar requirement.
qualification records, test equipment calibration records, test      personnel qualifications, test equipment calibration records, deviation or exception records, and inspection and examination        deviation or exception records, and inspection and test records records shall be prepared. These shall be placed with other          shall be prepared. These shall be placed with other project project records as required by code, standard, specification, or      records as required by codes, standards, specification, or project project procedures.                                                  procedures.
: 9. APPLICABLE CODES, STANDARDS AND GUIDES The applicable published codes, standards, and guides shall be                                                                          The QAPD establishes the used. In cases where codes or standards were intended to cover                                                                          quality assurance standards the manufacturing phase of an item, these codes shall be used as                                                                        to be applied to the activities.
guides. Refer to Appendix B for a listing, not necessarily complete, of additional codes, standards, and guides that should be considered during the construction phase. The following guides or standards refer specifically to nuclear power generating stations and their construction and shall be considered applicable.
: 1) IEEE Std 279-1971, Criteria for Protection Systems for                                                                                Reg. Guide will be met with Nuclear Power Generating Stations                                                                                                        NQA-1-1994 in lieu of
: 2) IEEE Std 308-1971, Criteria for Class IE Electric Systems for                                                                        N45.2 and other criteria as Nuclear Power Generating Stations                                                                                                        defined in NQA-I-1994.
: 3) IEEE Std 317-1971, Electric Penetration Assemblies in Containment Structures for Nuclear Fueled Power Generating Stations
: 4) IEEE Std 323-1971, Guide for Qualification of Class I Electric Equipment for Nuclear Power Generating Stations
: 5) ANSI 18.2-1965, Nuclear Safety Criteria for the Design of 10/28/2010                      Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment                            Page 16 of 22
 
N45.2.4-1972/IEEE*Std 336-1971lnstallIation, Inspection, and: . NQA-1994 Subpart 2.4/ANSI/IEEECStd336-1985                                    COMMENTS
&#xfd;'RTesting of Requirements for Instrfumentation and Electric              Installation, Inspection, and Testing Requirements for Equipment During the Construction of Nuclear Power                Power, Instrumentation, and Control Equipment at Nuclear Generating Stations                                                        Facilities Stationary Pressurized Water Reactor Plants
: 6) ANSI B331.7-1969, Nuclear Power Piping
: 7) IEEE Std 334-1971, Guide for Type Tests of Continuous-Duty Class I Motors Installed Inside the Containment of Nuclear Power Generating Stations
: 8) IEEE Std 336-1971, Installation, Inspection and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations
: 9) IEEE Std 338-1971, Trial-Use Criteria for the Periodic Testing of Nuclear Power Generating Station Protection Systems
: 10) IEEE Std 344-1971, Trial-Use Guide for Seismic Qualification of Class I Electric Equipment for Nuclear Power Generating Stations Reg. Guide 1.30 8/72 Position C.2 states: Section 9 of ANSI N45.2.4-1972 lists additional guides and standards made applicable by ANSI N45.2.4. The specific applicability or acceptability of these listed guides and standards has been or will be covered separately in other safety guides or in appropriate Commission regulations.
Appendixes (The Appendixes are not a part of IEEE Standard Installation,                                                                          Not a requirement.
Inspection, and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations.)
Appendix A Supplementary Provisions for Multi-Unit Stations                      10. Supplementary Provisions for Multiunit Stations and Operating Plants For construction activity in nuclear power generating stations        For construction activity in nuclear facilities where one or more Similar requirement.
where one or more units are already operating or have reached a      units are already operating or have reached a stage in their stage in their own construction where the fuel has been loaded in    construction where the fuel has been loaded in the reactor and the reactor and associated systems energized for whatever            associated systems energized for whatever purpose, the purpose, the following measures shall be taken in addition to the    following measures shall be taken in addition to the provisions provision defined in the body of this document.                      defined elsewhere in this standard.
Al Planning and Preparation                                          10.1 Planning and Preparation Instructions, procedures or drawings shall be prepared to control    Instructions, procedures, or drawings shall be prepared to        Similar requirement.
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N45 2.4-1972/IEEE Std 336-1971 Installation, Inspection, and                NQA-1 1994 Subpart 2.4/ANSI/IEEE Std 336-1985                        COMMENTS Testing of Requirements for Instrumentation and Electric .                nstallation, Inspection, and Testing Requirements for.....
Equipment During the Construction of Nuclear Power                Power, Instrumentation, and Control Equipment at Nuclear Generating~ Stations                                                        Facilities installation, inspection and testing activities at areas of interface  control installation, inspection, and testing activities at areas of between the new and existing units.                                    interface between the new and existing units.
These instructions and procedures or drawings shall define:            These instructions and procedures or drawings shall define the Similar requirement.
: 1) The areas of interface between the new and existing units          following:
: 2) Access control and authority for work at these interface areas      1) The areas of interface between the new and existing units
: 3) Nature of potential hazards to and/or from the existing            2) Access control and authority for work at these interface areas equipment                                                              3) Nature of potential hazards to or from the existing equipment
: 4) Precautions required to be taken during installation                4) Precautions required to be taken during installation
: 5) Supplementary objectives for inspection and testing                5) Supplementary objectives for inspection and testing A2 Documentation                                                      10.2 Documentation A2.1 The instructions, procedures or drawings described in            10.2.1 The instructions, procedures, or drawings described in        Similar requirement.
Section Al shall be documented and shall be kept current by            10.1 shall be kept current by revisions.
revisions as necessary.
A2.2 The equipment and/or systems which are associated with            10.2.2 The equipment or systems which are associated with            Similar requirement.
existing unit(s) that are electrically energize or charged with        existing unit(s) that are electrically energized or charged with pressurized and/or radioactive fluids and which are in the vicinity    pressurized or radioactive fluids and which are in the vicinity of of the construction activity associated with the new unit shall be    the construction activity associated with the new unit shall be properly tagged or identified.                                        properly tagged or identified.
A2.3 The documentation associated with installation described in      10.2.3 The documentation associated with installation described Similar requirement.
Section 2.2 of the main document shall additionally include:          in 10.2.2 shall also include:
A2.3.1 The identification of the equipment and/or system defined      1) The identification of the equipment or system defined in          Similar requirement.
in 2.2 above, which poses a potential hazard in the vicinity of        10.2.2 which poses a potential hazard in the vicinity of current current construction activity,                                        construction activity A2.3.2 Level of potential hazard from such neighboring                2) Identification of the potential hazard of such neighboring        Similar requirement.
energized systems, such as: voltage, radiation level, fluid            energized systems as voltage, radiation level, fluid pressure, or pressure and/or temperatures.                                          temperatures A2.4 Authorizations for access to and work at the areas of            10.2.4 Authorizations for access to and work at the areas of        Similar requirement.
interface between the new and existing units shall be                  interface between the new and existing units shall be documented.                                                            documented.
10.2.5 Provisions of Section 9 shall be implemented to              New requirement regarding supplement or supersede documents or records as required            records.
A3 Installation                                                        10.3 Installation A3.1 Suitable protective barriers shall be erected to prevent          10.3.1 Suitable protective barriers shall be erected, where          Similar requirement.
damage to equipment and/or systems associated with the existing needed, to prevent damage to equipment or systems associated unit(s).                                                              with the existing unit(s).
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N45.2.4-1972/IEEE Std 336-.1971 Installation, Inspection, and              NQ,..-. 1994 Subpart.2.4ANSI/IEEE Std 336-1985 "O                          MN.
Testing of Requirements forInstrumentation and Electric                Installation, Inspection, and Testing Requirements, for Equipment During the Construction of Nuclear Power              Power, Instru.mentation, and Control Equipment at Nuclear Generating Stations                                                      ".Facilities A3.2 Spare capacities available in existing facility such as in      10.3.2 Spare capacities available in the existing facility, such as Similar requirement. Adds cable raceways or in panelboards shall not be used unless            in cable raceways or in panelboards, shall not be used unless      allowance for approved expressly indicated on the latest applicable approved for            expressly indicated on the latest applicable approved-for-          temporary use of spare construction drawings or installation specification,                  construction drawings or installation specification. This does      capacities.
not prohibit authorized temporary use of such spare capacities.
A3.3 When working in an area common to the new and the                10.3.3 When working in an area common to the new and the            Similar requirement.
existing units, such as the cable spreading room, control room,      existing units, such as the cable spreading room, control room, radioactive waste building or the battery room, care shall be        or radioactive waste building, care shall be especially exercised especially exercised to avoid interference with existing facilities  to avoid interference with existing facilities and to maintain and to maintain required separation, where appropriate, between      required separation, where appropriate, between the systems the systems associated with existing and new units.                  associated with existing and new units.
A4 Inspection                                                        10.4 Inspection A4.1 Inspection shall be performed to verify that existing            10.4.1 Inspection shall be performed to verify that the            Similar requirement.
equipment and/or systems neighboring current construction            requirements of 10.2 and 10.3 have been satisfied.
activity are properly tagged and identified, and potential hazards therefrom identified and documented.
A4.2 Inspection shall be performed to verify that the existing        10.4.2 Inspection shall be performed to verify that the existing    Similar requirement.
facilities are properly protected from current construction          facilities are properly protected from construction activity.
activity.
A5 Testing                                                            10.5 Testing A5.1 In testing integrated electrical control and/or                  In testing integrated electrical control or instrumentation        Similar requirement.
instrumentation systems where the plant design calls for              systems, or both, where the plant design calls for interconnection between the existing and new systems, care shall      interconnection between the existing and new systems, care be especially exercised to prevent tripping or otherwise              shall be exercised to prevent tripping or otherwise disturbing dislocating the operation of equipment and/or systems associated      the operation of equipment or systems associated with the with the existing unit(s).                                            existing unit(s).
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N45.2.4-197211EEE Std 336-1971i Installation, Inspectionuand                              part r4/.SI/EEE St..336-1985                  CON*W...
Testing of Requirements for InstruImentation and Electric            Installation, Inspection, and Testing, Requirements for EquipmentDuringthe Construction of.NuclearPower                Power, Instrumentation, and Control Equipment at Nuclear "eneratingzStatiins                                                      Facilitiwes ...  ._...      ..      "....."  _..
Appendix B                                                          I                                                            I Additional Codes, Standards and Guides
: 1. ANSI C 1-1963, National Electrical Code (NFPA 70-1968) (to be used as a guide when appropriate)
: 2. ANSI C29.1-1961, Test Methods for Electrical Power Insulators
: 3. ANSI Appendix C57.93, Guide for Installation and Maintenance of Oil-Immersed Transformers
: 4. ANSI Appendix C57.94, Guide for Installation and Maintenance of Dry-Type Transformers
: 5. ANSI C96.1-1969, Temperature Measurement Thermocouples
: 6. API RP550-1965, Manual on Installation of Refinery Instruments and Control Systems. Part I - Process Instrumentation and Control
: 7. API RP550-1965, Manual on Installation of Refinery Instruments and Control Systems, Part II - Process Stream Analyzers
: 8. ASME Boiler and Pressure Vessel Code, Section mI, Nuclear Power Plant Components, 1971
: 9. IEEE Std 4-1968, Techniques for Dielectric Tests (ANSI C68.1- 1968)
: 10. IEEE Std 43-1961, Recommended Practice for Testing, Insulation Resistance of Rotating Machinery 11. IEEE Std 51 -
1955, Guiding Principles for Dielectric Tests
: 12. IEEE Std 56-1958, Guide for Insulation Maintenance for Large AC Rotating Machinery
: 13. IEEE Std 62-1958, Guide for Making Dielectric Measurements in the Field
: 14. IEEE Std 64-1969, Guide for Acceptance and Maintenance of Insulating Oil in Equipment
: 15. IEEE Std 81-1962, Guide for Measuring Ground Resistance and Potential Gradients in the Earth
: 16. IEEE Std 95-1962, Guide for Insulation Testing of Large AC Rotating Machinery with High Direct Voltage
: 17. IEEE Std 112A-1964, Test Procedure for Polyphase 10/28/2010                    Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment            Page 20 of 22
 
            *5,A,9"]/IEE:St*33191.*hsalltinInspection, and N45.2. 4-1972/IEEEStd                                                    "Q-NQA.. 199 1994.S"u b Subpart      ... ..
2.4/ANSIIEEE    Std 336-1985....."...  *...
                                                                                                                                      .COMME.NTS.
Testing o Requirements for instrumentation and-Electric              Instalationspection, and Testing Requirements for Equipment During the Construction of Nuclear Power              Power,                    and Control, Equipment at Nuclear
                                                                                              .Instrumentation, Generating Stations                                                      Facilities Induction Motors and Generators
: 18. IEEE Std 114-1969, Test Procedure for Single-Phase Induction Motors
: 19. IEEE Std 115-1965, Test Procedure for Synchronous Machines
: 20. IEEE Std 118-1949, Master Test Code for Resistance Measurement
: 21. IEEE Std 120-1955 (withdrawn), Master Test Code for Electrical Measurement in Power Circuits
: 22. IEEE Std 262-1968, Test Code for Distribution, Power and Regulating Transformers, and Shunt Reactors (ANSI C57.12.90-1968)
: 23. IEEE Std 283-1968, Guide for Installation of Oil-Immersed Transformers
: 24. ISA-RP3. 1, Flowmeter Installations, Seal and Condensate Chambers, 1960
: 25. ISA-S5.1, Instrumentation Symbols and Identification, 1968
: 26. ISA-RP7. 1, Pneumatic Control Circuit Pressure Test, 1956
: 27. ISA-RP7.2, Color Code for Panel Tubing, 1957
: 28. ISA-RP8. 1, Instrument Enclosures for Industrial Environments
: 29. ISA-RP25.1, Materials for Instruments in Radiation Service, 1957
: 30. ISA-S26, Dynamic Response Testing of Process Control Instrumentation, 1968
: 31. ISA-$37. 1, Electrical Transducers Nomenclature and Terminology, 1969
: 32. ISA-RP42. 1, Nomenclature for Instrument Tubing Fittings (Threaded), 1965
: 33. NEMA ICS-1970, Industrial Controls and Systems
: 34. NEMA IS 1.1-1969, Enclosures for Industrial Controls and Systems
: 35. NEMA SG 3-1965, Low-Voltage Power Circuit Breakers
: 36. NEMA SG 5-1971, Power Switchgear Assemblies
: 37. NEMA VE 1-1965, Ventilated Cable Trays 10/28/2010                    Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment          Page 21 of 22
 
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Supplementary Quality Assurance Requirements for                            Quality*Assurance Requirements for Installation,                        COMMENTS Installation, Inspection, and Testing of Structural Concrete              Inspection, and Testing of Structural Concrete, Structural Structural Steel During the Construction Phase of
        .and                                                                  Steel, Soils, and Foundations for.Nuclear Power Plants Nuclear Power Plants                      ...    ..  "        .,      NQA-1 194 SUBPART 2.5            .      '., : ..
N451.2.5 1974                                                                                                        ___________
: 1. INTRODUCTION                                                          1 GENERAL 1.1 Scope This standard sets forth the supplementary quality assurance              Subpart 2.5 provides amplified requirements for installation,        Similar requirement requirements of installation, inspection and testing of structural        inspection, and testing of structural concrete, structural steel, concrete and structural steel for nuclear power plant                    soils, and foundations.
construction.
It is intended for application to those structures from which            It supplements the requirements of Part I and shall be used in        This is an overall objective satisfactory performance is required.                                    conjunction with applicable Basic and Supplementary Sections          of NQA-1, Basic
: 1. For the plant to operate reliably                                      of Part I when and to the extent specified by the organization        Requirement 2, related to
: 2. To prevent accidents that could cause undue risk to the health        invoking Subpart 2.5.                                                providing control over and safety of the public                                                                                                                        activities affecting quality
: 3. To mitigate the consequences of such accidents if they were                                                                                  consistent with their to occur.                                                                                                                                      importance to safety.
Included are the following:                                              See Section 2 of NQA-1-1994, Subpart 2.5 below
: 1. Formwork
: 2. Steel Reinforcement
: 3. Embedded Items
: 4. Foundation Preparation
: 5. Concrete
: 6. Structural Steel The requirements may also be extended to other appropriate parts of nuclear power plants when specified in contract documents.
This standard is intended to be used in conjunction with ANSI N45.2.
1.2 Applicability The requirement of this standard apply to the work of any                See NQA-1, Part II, Introduction for Applicability                    Similar requirement organization or individual participating in the production,                                                                                    between both standards.
preparation, placement, inspection and testing of structural concrete and the erection, inspection and testing of structural steel as identified in section 1.1.
The extent to which the individual requirements of this standard apply will depend upon the nature and scope of the work to be performed and the importance of the item or service involved.
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Supplementary Quality Assuran'e Requirements for                        Quality Assurance Requirements for Intalatio,"                      'CO M.S.
Installation, Inspection, andTestingof Structural Concrete            inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Construction Phase of                Steel, Soils, and Foundations for Nuclear Power Plants.
Nu.clear Power Plants                                              NQA-1 14SUBPART 2.5 N45.2.5 197.4 The requirements are intended to assure that only specified materials and workmanship are incorporated into the plant; that quality of materials and quality of workmanship are maintained throughout the construction process; that the work is performed in accordance with applicable construction procedures; and that the completed installation conforms to the specified requirements.
The ASME Boiler and Pressure Vessel Code, Section III, Divisions I and 2, as well as other American National Standards, have been considered in the development of this standard; and this standard is intended to be compatible with their requirements. This standard applies to structural concrete and structural steel components of nuclear power plants not covered by the Code. For items covered by the Code, it is intended that the requirements of this standard shall supplement the requirements of the Code. In cases where conflict may exist, the requirements of the Code shall govern.
1.3 Responsibility                                                -I                                                                    I The organization or organizations responsible for establishing        See NQA-1, Part II, Introduction for Responsibility                Similar requirement the applicable requirements for the activities covered by this                                                                            between both standards.
standard shall be identified and the scope of their responsibilities shall be documented. The work of establishing practices and procedures and providing the resources in terms of personnel, equipment and services necessary to implement the requirements of this standard may be delegated to other organizations and such delegation also shall be documented. It is the responsibility of each organization performing work covered by this standard to comply with the procedures and instructions issued for the project and to conform to the requirements of this standard applicable to their work. It is the responsibility of the organization performing these activities to specify the detailed methods and procedures unless they are specified in the procurement documents.
10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 2 of 30
 
Supplementary Quality Assurance Requirements for.......Quality Assurance Requirenents for Installation',
Inistallation, Inspection,and Testing of Structural Concrete            Inspection, and Testing of Structural Concrete Structural
    **and Structural Steel During the ,onstructn Phase of                Steel, Soils, and Fondations for.Nuclear Power.Plants Nuclear Power Plants                                              NQA-. 1994,SUBPART 2.5 N45.2.5_1974                              _________________________
1.4 Definitions                                                        1.1 Definitions The following definitions are provided to assure a uniform            The following definitions are provided to assure a uniform        Similar requirement. For understanding of select terms as they are used in this standard.      understanding of unique terms as they are used in Subpart 2.5. NQA-1, additional Additional definitions of terms are included in ANSI N45.2.10.                                                                          definitions are contained in the Introduction to Part I.
Class of Concrete - Identifies each individual design mix.            Class of concrete - identifies each individual design mix        Similar requirement Curing - The process of maintaining a satisfactory moisture            Curing - the process of maintaining a satisfactory moisture      Similar requirement content and a favorable temperature in concrete during                content and a favorable temperature in concrete during hydration of the cementitious materials so that desired                hydration of the cementitious materials so that desired properties of the concrete are developed,                              properties of the concrete are developed.
Correlation testing - a form of in-process testing accomplished  New definition in NQA-1 consistent with established procedures, which provides for the    (Not in N45.2.5 or comparison of results of specified tests of concrete samples      N45.2. 10) taken of corresponding batches from two different points to establish to what extent the conditions and method of transit have impacted on specified requirements for plastic concrete at the placement point Delivery point - the point of discharge in the case of a truck    New definition in NQA-1 agitator unit, or non-agitating unit when another conveying      (Not in N45.2.5 or device is to be used to transport the plastic concrete to the    N45.2. 10) - clarifies placement point. Where a truck agitator unit is used in the      "Sampling point" from transit of concrete, the delivery point and the mixing point are  N45.2.5 considered coincident when:
(a) the delivery point is not more than a distance of 2 mi (3.22 km) and a maximum time of /2 hr in transit from the mixing point, and (b) the delivered concrete commences to be placed within a maximum time of 1/22 hr from the time the transporting vehicle arrives at the delivery point.
When a non-agitating unit is used, the delivery point and the mixing point shall not be considered coincident.
Finishing - The process of obtaining specified surface                Finishing - the process of obtaining specified surface            Similar requirement characteristics of hardened concrete.                                  characteristics of hardened concrete Qualified Procedures - Procedures which incorporate                    NQA-1-1994 defines "Qualified Procedure" as "an approved          Not in Subpart but in applicable codes and standards, manufacturer's parameters and          procedure that has been demonstrated to meet the specified        Definition section of NQA-10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 3 of 30
 
Supplementary Quali'tyAssurance Requemements for                        Quality Assurance Requirements- for Installation,                CO MENTS Installation, Inspection, and Testing of Structural Concrete .Inspection,.and Testing of Structural Concrete, Structural and Structural SteelDuring the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                                                NQA-1 1994 SUBPART 2.5 N45.2.5 1974                              __________________________
engineering specifications.                                            requirements for its intended purpose"                            1-1994 Qualification Tests - Tests performed to qualify the basic            Qualification tests - tests performed to qualify the basic        Definition shortened, still material source or manufacturer. These tests are mandatory            material source or manufacturer to assure conformance to          same basic intent.
unless current documentary test data are available to establish        specification requirements complete confidence in conformance to specification requirements In-Process Tests - Tests performed during the course of                Inprocess tests - tests performed during the course of            NQA-l Definition expands construction to maintain control of structural materials. These        construction to determine compliance with specified              on who may perform the tests may be performed by the manufacturer or supplier, but            requirements and maintain control of materials. These tests may  tests but under same samples for these tests must be taken from the lot or batch of        be performed by the purchaser (or his agent), constructor,        requirements.
materials supplied to the site for use.                                manufacturer, or supplier, but samples for these tests must be taken from the lot or batch of materials supplied and used at the site of construction.
Sampling Point - The point at which the concrete leaves the                                                                              Clarified in NQA-l by use last piece of mixing or agitating equipment prior to being                                                                              of "Delivery Point" and discharged to conveying equipment systems.                                                                                              "Mixing Point" Mixing point - the point of discharge of plastic concrete from a New definition in NQA-l central mix plant. For truck mixed concrete, the mixing point    (Not in N45.2.5 or and delivery point are defined as coincident.                    N45.2. 10) - clarifies "Sampling point" from N45.2.5 Placement point - the point of discharge of plastic concrete into New definition in NQA-l the forms. Except for pumped concrete, the placement point and (Not in N45.2.5 or the delivery point are considered coincident when 5 min or less N45.2. 10) - clarifies is used in transit of the concrete from the delivery point to the "Sampling point" from placement point.                                                  N45.2.5 1.5 Referenced Documents Other documents that are required to be included as a part of                                                                            The QAPD addresses the this standard are identified at the point of reference and listed in                                                                    standards for the program.
Section 8 and the Appendix of this Standard. The issue or edition of the referenced document that is required is specified in the Appendix.
Regarding this subdivision, NRC Regulatory Guide 1.94-4/76 states: "The specific applicability or acceptability of documents listed in Section 8 has been covered separately in other 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 4 of 30
 
Supplementary QualityAssurance                          for              Ququ6ements ality Assurance Requrements for Instalationa                    COMMENTS Installation*, Inspection, and ,Testlgof Structural Concrete            Inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Costruction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                                                NQA-I1 i94 SUBPAR.T 2.5 N.45.2.5 1974 regulatory guides. Other standards and codes listed in ANSI N45.2.5-1974 provide useful guidance for the installation, inspection, and testing of structural concrete and structural steel.
Prior to use of these other referenced codes and standards, however, the suitability of the standard or code should be reviewed for the particular application under consideration."
: 2. GENERAL REQUIREMENTS                                                2 GENERAL REQUIREMENTS The requirements of Subpart 2.5 apply to any organization or      Similar requirement to 1.2 individual participating in work relating to production,          of N45.2.5.
preparation, placement, installation, inspection, and testing of structural concrete, structural steel, soils, and foundations, and applies to the following N45.2.5 covers this in Section 1.1 as follows:                          (a) formwork                                                      NQA-1 Subpart 2.5 adds:
(Included are the following:                                        (b) steel reinforcement                                            (g) soils and earthwork
: 1. Formwork                                                          (c) embedded items                                                (h) special foundations
: 2. Steel Reinforcement                                              (d) foundation preparation                                        (i) foundation underpinning
: 3. Embedded Items                                                    (e) concrete
: 4. Foundation Preparation                                            (f) structural steel
: 5. Concrete                                                          (g) soils and earthwork
: 6. Structural Steel)                                                (h) special foundations (i) foundation underpinning 2.1 Planning                                                            3 REQUIREMENTS Measures shall be established and implemented for                      Measures shall be established and implemented for                  Similar requirement documenting installation, inspection, and testing operations to        documenting installation, inspection, and testing activities to verify conformance to specified requirements.                          verify conformance to specified requirements.
3.1 Planning and Procedures Planning shall take into account the need for the preparation and      Planning and procedure preparation shall be in accordance with    The Introduction to NQA-1, control of procedures and work instructions as necessary to            the Introduction to this Part (Part II).                          Part II addresses these items comply with specified requirements for installation, inspection                                                                            from N45.2.5 for Planning.
and testing.
Planning shall include a review of the structure, system, or component design and procurement specifications, materials lists, drawings, construction work plans, procedures, and schedules to assure that installation, inspection and testing activities have been incorporated and that they can be 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 5 of 30
 
Supplementa      Quality`AssuiranceRe                  for              QualityasAfr  unra    equirements for Instaaion,                  CM ENTS Installation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Structural .oncrete,Suctural...
and Structural Steel During the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants Nuclea. Power Plants.        ...                .        .'              1..... .994.SUBPART'2.5 N45.2.5 19.74 accomplished as specified; and that time and resources are sufficient to accomplish the scheduled construction without degradation of quality.
Regarding this subdivision, NRC Regulatory Guide 1.94-4/76 states: "The provisions of Subdivision 2.1 ... should be used in conjunction with Regulatory Guide 1.55, 'Concrete Placement in Category 1 Structures."' Note that Reg. Guide 1.55 has been withdrawn by the NRC.
2.2 Procedures and Instructions Installation, inspection and test procedures, and work                                                                                  The Introduction to NQA-1, instructions shall be prepared and documented for those                                                                                  Part H addresses these items activities falling within the scope of this standard.                                                                                    from N45.2.5 for Procedures These documents shall be kept current and revised as necessary                                                                          Addressed in NQA-1, Part I, to assure that installation, inspections and tests are performed in                                                                      Basic Requirement 6.
accordance with latest information and shall include as appropriate:
: 1. Installation specifications.                                                                                                          Item 4 of N45.2.5 is similar
: 2. Inspection and test objectives and requirements.                                                                                      to NQA-l-1994, Part II
: 3. Precautions to avoid component or system damage during                                                                                Introduction, Section 4.2 installation, inspection and following inspection but prior to use.                                                                      "Procedures", "(g) special
: 4. Inspection and test equipment required.                                                                                              equipment required."
: 5. Sequence of tests (if applicable).
: 6. Sequential actions to be followed.                                                                                                    Item 12 of N45.2.5 is
: 7. Frequency of inspections and tests.                                                                                                  similar to NQA- 1-1994,
: 8. Prerequisites.                                                                                                                        Part H Introduction, Section
: 9. Approval.                                                                                                                            4.2 "Procedures", "(j)
: 10. Data report form.                                                                                                                    acceptance criteria and
: 11. Identification of test equipment and date of required                                                                                methods for verifying."
recalibration where required for interpretation of test results.
: 12. Inspection and test acceptance limits.                                                                                              NQA-l-1994, Part II Introduction, Section 4.2 "Procedures", adds the following:
(a) personnel safety 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 6 of 30
 
SupplementariyQuality AssuranceRequirements for                        Quality Assurance Requirements foNrInstallation,0'                    COMMENTS Installation, Inspection, and Testing of Structural Concrete          Inspection, and Testing of Structural Concrete, Structural                      .
and StructuralSteel During the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Poier'Plants
                ...... Nuclear Power Plants.                      .                    NQA-I I99 SUBPART 2.5 N45.2.5_1974                                                                                                  ___________
(k) responsibility and required qualifications of personnel 2.3 Results Inspection and test results shall be documented in a suitable test    Covered in Supplement 10S-1 for Inspection requirements          NQA-1 contains equivalent report or data sheet. Each report shall identify the item to which    and Supplement 11S-I, Section 4 for documenting test              requirements in Part I.
it applies, the procedures or instructions followed in performing      results. These are written as general requirements for all the task, and the identification of the following:                    quality activities.
: 1. Pertinent inspection and test data such as identification of location where testing was performed or where test samples were taken.
: 2. Significant dates and times.
: 3. Inspection acceptance and test completion signatures.
: 4. Conditions encountered which were not anticipated, including nonconformance.
Test reports and data, sheet shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation.
2.4 Personnel Qualifications Personnel performing tests and inspections required by this            For NQA-1, qualification of inspection and test personnel is      NQA-1 contains equivalent standard shall be qualified in accordance with ANSI N45.2.6.          not repeated in this subpart. They are contained in              requirements in Part 14-.
Personnel performing field inspections and testing activities          Supplement 2S-1, 2; Supplement 10S-1, Section 3.2; and shall be certified for Level I capability.                            Appendix 2A-1.
On-site supervisors of Level I personnel shall be certified for Level II capability and shall be responsible for the proper performance of onsite inspections and tests. Persons charged with engineering managerial responsibility of the inspection and testing organization at the site in either a resident or nonresident capacity shall be certified for Level III capability.
Personnel performing nondestructive examinations shall be qualified to appropriate levels of capability as specified in American Society for Nondestructive Testing Recommended Practice SNT-TC- 1A.
2.5 Measuring and Test Equipment.                                      3.2 Measuring and Test Equipment 2.5.1 Selection.
10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 7 of 30
 
Supplementary Instaltion*,          Quality Aurance Inspection,.and    T tn o Requirements for "                  Qualit "T*. Assurance d...... es *:''*''.Requirements o"n an.....                    ..... * *i for Iistallation,
                                                                                                                                          ... : * *.*..      COMMENTS
                                                                                                                                                            ..... "'*i::*
esting ofStructural Concrete        Inspection,..nd Testing of Structural"Concrete, Structural and Structural Steel During the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                                                NQ.A-I 1994 SUBPART 2.5 N45.2.5_974                                                                                                              ___________
Measuring and test equipment used to implement the                      Further details for M&TE is contained in Supplement 12S-1                  Similar requirement requirements of this standard shall be selected on the basis of        and Subpart 2.16 rather than repeated in this Subpart (2.5).              The overall requirements of accuracy sufficient to determine conformance to specified                                                                                          NQA-1 are equivalent to requirements.                                                                                                                                      those of N45.2.5.
These measuring devices shall include but not to be limited to          Measuring and test equipment used to implement the                        Similar requirement thermometers, balances, scales, air entrainment meters,                requirements of Subpart 2.5 shall include (but not be limited to)          Addressed in NQA-1, Part I humidity meters, volumetric buckets, field soil density                thermometers, balances, scales, air entrainment meters,                    and Subpart 2.16.
measuring devices, pressure gages, and torque wrenches.                volumetric buckets, field measuring devices, pressure gages, and torque wrenches.
2.5.2 Calibration and Control The equipment shall be adjusted or calibrated or both at                                                                                          Similar requirement prescribed intervals against certified standards having known                                                                                      Addressed in NQA-1, Part 1 valid relationships to national standards, where such exists. If                                                                                  and Subpart 2.16.
no national standards exists, the basis for the adjustment or calibration shall be documented. Records shall be maintained and equipment suitably marked to indicate calibration status.
Measures shall be taken to assure proper handling, storage and care of installation of inspection and testing equipment after calibration in order to maintain the required accuracy of such equipment.
Test equipment found to be out of calibration shall be clearly                                                                                    Similar requirement identified as such. When discrepancies, malfunctions, or                                                                                          Addressed in NQA- 1, Part I inaccuracies in inspection and testing equipment are found                                                                                        and Subpart 2.16.
during calibration, all items inspected with that equipment since the last previous calibration shall be considered unacceptable until an evaluation has been made by the responsible authority and appropriate action taken.
3.3 Laboratory Testing Laboratory operations and testing associated with concrete and            New requirement in soils shall be controlled using a Quality Assurance Program.              NQA-1.
2.6 Housekeeping In job-site areas, facilities, and environments where installation,    Note: See NQA-1, Subpart 2.3 for Housekeeping Standards                    Similar requirement. Refer inspection, and testing of structural steel items are performed in                                                                                to table comparing the accordance with the requirements of this standard, the                                                                                            stated standards.
housekeeping requirements shall be in accordance with ANSI 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                          Page 8 of 30
 
Supplementary Quality AssurancetRequirements for                          Quality Assurance Requirements for Installation,                    COMMENTS installation, Inspection, and Testingof StructuralConcrete              Inspection, and Testing of Structural Concrete, Structural......
and Structural Steel During the Construction Phase of                  Steel, Soils,,and Foundations for Nuclear Power Plants.....        ......          .
              ..      Nuclear Power Plants                                                NQA-1 1994 SUB-PART 2.5 LN45.2.5 1974 45.2.3.
: 3. PRECONSTRUCTION VERIFICATION                                        PRECONSTRUCTION VERIFICATION 3.1 General                                                            4.1 General While it is recognized that the requirements for initial receipt        Receipt and interim storage inspections shall be used to verify  Similar requirement.
inspections and storage are covered by another standard, ANSI          that items are in a satisfactory condition for installation.      Subpart 2.2 of NQA-1 N45.2.2, it is necessary to verify that the quality of an item has                                                                        addresses receipt and not suffered during the interim period. It is not intended to                                                                            storage requirements.
duplicate inspections but rather to verify that items are in a                                                                            N45.2.2 and Subpart 2.2 are satisfactory condition for installation,                                                                                                  compared in a separate matrix.
The verification shall include:                                        The verification shall include the following:                    Similar requirement.
: 1. Visual examination of materials for proper identification,          (a) visual inspection of material for proper identification, physical damage, and contamination,                                    physical damage, and contamination;
: 2. Review of manufacturer's documentation, test reports, or            (b) review of manufacturer's documentation, test reports, or other evidence of quality conformance for correctness and              other evidence of quality conformance for correctness and compliance with specifications if not reviewed at time of              compliance with specifications if not reviewed at time of receipt.                                                                receipt.
3.2 Materials Suitability                                              4.2 Materials Suitability Verification that materials meet specified requirements shall be        To assure that materials meet specified requirements,            Similar requirement.
accomplished through qualification tests and in-process tests.          preconstruction qualification tests and inspections of the materials to be used and in-process tests of materials being used shall be conducted.
3.2.1 Qualification Tests.
Qualification tests shall be performed and the results evaluated        Qualification tests shall be performed and the results evaluated  Similar requirement, NQA-prior to the initial use of the materials to establish conformance      prior to the initial use of the material to establish conformance 1 does not contain an of the materials to the specified requirements. A list of              of the materials to the specified requirements. These tests are  equivalent to Table A, minimum required qualification tests or certifications is              mandatory unless current documentary test data are available to  rather, the subpart refers to contained in Table A. This list contains tests necessary to            establish complete confidence in conformance to specification    other equivalent standards qualify materials for normal application,                              requirements. The specifications shall identify the required      that would control this qualification tests and the frequency for their repetition. The  testing.
tests required for concrete, concrete constituents, materials for reinforcing systems, materials for prestressing systems and welding materials shall be in accordance with the ASME Boiler and Pressure Vessel Code, Section III, Division 2 (ACI Standard 359). Lightweight concrete mix designs shall be made 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 9 of 30
 
Sup lementary Quality Assurance Requirements for:.                      Quality Assurance Requirements for Installation,                  COMMENTS Installation, Inspection, and Testing of Structural Concrete        .nspection, and Testing of Structural Cocrte, Structural and Structural Steel During the Construction Phase of                Steel, Soils, and Foundations for Nuclear Power Plants..
Nuclear Power Plants                                              NQA.. 1994 SUBPART 2.5 N45.2.5 197.4                                                      .
in accordance with AC1 21 1.2. Lightweight concrete aggregates shall be qualified by tests for conformance with ASTM C 330: When splitting tensile strengths are required for lightweight concrete mix, the methods given in ASTM C 330 shall be used.
Additional tests may be required to qualify materials for special    Additional tests may be required to qualify materials for special Similar requirement.
applications.                                                        application.
See Table A At the end of the Matrix 3.3 Construction Processes                                            4.3 Construction Processes Inspections shall be performed to verify that the prerequisites      Inspections shall be performed to verify that the prerequisites  Similar requirement.
for control of construction processes such as welding, bolting,      for control of construction processes such as welding, structural structural reinforcement splicing, and concrete measuring,            bolting, mechanical splicing of reinforcement, and concrete mixing, transporting, placing, and curing have been                  measuring, mixing, transporting, placing, and curing have been accomplished,                                                        accomplished.
These inspections shall include:                                      These inspections shall include verification of the following:    Similar requirement.
: 1. Verification that the process has been qualified as required.      (a) the process has been qualified as required;
: 2. Verification that process controls are in effect.                  (b) process controls are in effect;
: 3. Verification that qualified procedures, instruction manuals, or    (c) approved procedures, instruction manuals, or both, if both, if required for specific equipment, are available for use      required for specific equipment, are available for use during during construction.                                                  construction;
: 4. Verification that the process is suitable for the particular      (d) the process is suitable for the particular application; application.                                                          (e) manpower, equipment (including measuring and testing
: 5. Verification that manpower, equipment, and materials are          equipment),. and materials are readily available and adequate to readily available and adequate to perform the work in                perform the work in accordance with drawing and specification accordance with drawing and specification requirements.              requirements.
5 INSPECTION OF SOILS AND EARTHWORK                              NQA-1 adds requirements for Soils and Earthwork that were not included in N45.2.5-1974. Since there is no N45.2.5-1974 code to compare to, the large volume of NQA- 1 text is omitted.
6 INSPECTION OF FOUNDATION PILE AND CAISSON                      Not addressed in N45.2.5-CONSTRUCTION                                                      1974. Since there is no 10/28/2010                      Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 10 of 30
 
Supplementary Quality Assurance Requirements fr                            Quality Assurance Requirements for Installation,                        COMMENTS Installation, Inspection, and Testing of Structural Concrete              Inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Construction Phase..o..........Soils", a Foundations for Nuclear.Power Plants Nucler Poer.PantsNQA-1                                    1994 SUBPART 2.5 N45.2.541974 N45.2.5-1974 code to compare to, the large volume of NQA-1 text is omitted.
4.0 INSPECTION OF CONCRETE CONSTRUCTION                                  7 INSPECTION OF CONCRETE CONSTRUCTION 4.1 General                                                              7.1 General_____________
Inspection of concrete construction shall include inspections of        Inspection of concrete construction shall include inspection of      Similar requirement, preparation for concreting, as well as in-process inspections of        preparations for concreting, as well as in-process inspections of    updated reference to concrete measuring, mixing, transporting, placement, curing,            concrete measuring, mixing, transporting, placement, curing,        applicable standards.
and protection to assure confornance to specified requirements.          and protection to assure conformance to specified requirements.
The inspection shall follow the Recommended Practice for                The inspection of pretensioning or post-tensioning systems shall Concrete Inspection, ACT 311.                                            be included, if applicable. The inspection shall follow ACT 311A.R, Guide for Concrete Inspection, and PCI MI'L- 116 and
______      ______        ______    ____      NWL-l 17.                                                        _    _    _    _ _  _  _  _  _
4.2 Protection of Materials                                              7.2 Protection of Materials_____________
Inspections shall be performed to verify the adequacy and                Inspections shall be performed to verify the adequacy and            Similar requirement.
proper maintenance of material storage conditions and handling          proper maintenance of material storage conditions and handling techniques.                                                              techniques.                                                        _____________
These inspections shall include the following:                          These inspections shall include the following:                      Similar requirement
: 1. Inspection of cement storage facilities to verify weather            (a) inspection of cement storage facilities to verify weather        Similar requirement tightness, cement temperature and the absence of lumps, and              tightness, cement temperature and the absence of lumps, and review of records to verify type and age of cement.                      review of records to verify type and age of cement;
: 2. Inspection of aggregate stockpiles to verify: handling                (b) inspection of aggregate stockpiles to verify that:              Similar requirement techniques are not resulting in segregation; storage and handling            (1) handling techniques are not resulting in segregation; adequately prevent contamination with deleterious substances;                (2) storage and handling adequately prevent contamination proper temperature and uniform moisture control; and use of                  with deleterious substances; frozen materials is prevented.                                              (3) specified temperature and uniform moisture control are maintained; and (4) use of frozen materials is prevented;
: 3. Inspection of admixture storage and handling facilities to            (c) inspection of admixture storage and handling facilities to      Similar requirement verify that deterioration and contamination are prevented,              verify that deterioration and contamination are prevented;
: 4. Inspection of water sources and cooling and heating facilities        (d) inspection of water sources and cooling and heating facilities  Similar requirement to verify the specified water quality and assure that the                to verify the specified water quality and to assure that the specifications for concrete temperature are met.                        specifications for concrete temperatures are met;
__________________________________________(e) inspection of reinforcing material, embedments, and                          New requirements for 10/28/2010                          Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                    Page I11 of 30
 
Supplementary Quality Assurance Requirements for Installation,                                                              Quality Assurance Requirements for Installation,                    COMMENTS Inspection, and Testing of Structural Concrete          Inspection, and Testing of Structural Concrete, Structural and Strcra Ste uigteCntuction Phase of                              Steel,.Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                                              NQA-1 194 SUBPART 2.5 N45.2.5 1974:
prestressing systems materials (wire, strand, tendons, tendon      NQA-1.
tubes, and temporary or permanent anchor hardware) to verify protection against excessive corrosion, contamination, and Physical damage.
4.3 Measuring, Mixing, and Transporting Equipment                    7.3 Measuring, Mixing, and Transporting Equipment Inspections shall be performed prior to and during the                Inspections shall be performed prior to and during the              Similar requirement production of concrete to verify the adequacy and proper              production of concrete to verify the adequacy and proper operation of measuring, mixing, and transporting equipment in        operation of measuring, mixing, and transporting equipment in accordance with ACI 304, ASTM C94, and National Ready Mix accordance with AC1 304, ASTM C 94, and National Ready Concrete Association - Concrete Plant Standard and Truck              Mix Concrete Association Concrete Plant Standard and Truck Mixer and Agitator Standard.                                          Mixer and Agitator Standard.
These inspections shall include the following:                        These inspections shall include the following:                      Similar requirement
: 1. Inspection of measuring facilities for the specified accuracy    7.3.1 Inspection of measuring facilities for the specified          Similar requirement of measuring, weighing, and weight recording devices to control accuracy of measuring, weighing, and weight recording devices the following:                                                        to control the following:
: a. Proportions of cement, water and aggregates                        (a) proportions of cement, water, and aggregates                    Similar requirements, NQA-
: b. Quantities of admixtures                                          (b) quantities of admixtures                                        I adds requirement
: c. Aggregate moisture compensation                                    (c) aggregate moisture compensation                                concerning lightweight
: d. Mixing time                                                        (d) mixing time                                                    aggregates.
: e. Temperature control: Heating or cooling of concrete                (e) temperature control, heating or cooling of concrete (f) method of adding water when batching lightweight aggregates in accordance with AC 1 301.
: 2. Inspection of central mix plant and truck mixers for wear of      7.3.2 Inspection of central mix plant and truck mixers for wear    Similar requirement drum blades, function of revolution counter and water                of drum blades, availability of revolution counter and water measuring device, proper speed of rotation, and ability to mix        measuring devices, proper speed of rotation, and ability to mix concrete completely in the specified time.                            concrete completely in the specified time 4.4 Preplacement Preparations                                        7.4 Preplacement Preparations Inspection of preparations for concrete placement shall include      Inspection of preparations for concrete placement shall include    Similar requirement.
the following:                                                        the following
: 1. Inspection of compacted structural fill during placement to        (a) inspection of the compacted structural fill or undisturbed soil Similar requirement when verify correct material, condition of material, gradation,            to verify correct condition;                                        considering these two items moisture content, in place density, and compliance with                                                                                  together. NQA-1 separated compaction procedures.                                                                                                                    the requirements a little 10/28/2010                      Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 12 of 30
 
Supplementary Quality Assurance Requirements for                        Quality Assurance Requirements for Installation,                  COMMEINTS
,Installation, Inspection, and Testing of Structural Concrete          Inspection, and Testing of S.'u"cturanl Concrete, Structural and Structural Steel During the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                '1994                            NQA1          SUBPART 2.5 N45.2.5 1974            "_        '______
: 2. Inspection of rock surfaces which will be in contact with          (b) inspection and field testing, in accordance with the          different than N45.2.2.
structural concrete to verify surface cleanness, removal of loose      specifications of all structural fill, undisturbed soil, and rock rock and free water, correct contour, and specified subgrade          surfaces which will be in contact with structural concrete to condition                                                              verify surface cleanness, removal of loose rock and free water, correct contour, and specified subgrade condition;
: 3. Inspection of previously placed concrete to verify proper          (c) inspection of previously placed concrete to verify proper      Similar requirement.
preparation for the next lift.                                        preparation for the next lift;
: 4. Inspection of formwork, reinforcing and embedded items to          (d) inspection of formwork to verify:                              Similar requirement.
verify: correct location and configuration of formwork;                (1) correct location and configuration, dimensional accuracy, installation and integrity of water stops and membrane                and proper line and grade of formwork; waterproofing; condition of form material to produce the              (2) installation and integrity of water stops and membrane specified concrete finish; installation of ties, anchors, bracing,    waterproofing; shoring and supports; correct size, orientation, and installation      (3) condition of form material to produce the specified concrete of reinforcing steel and embedded items; correct location and          finish, installation of ties, anchors, bracing, shoring, and dimension of control joints, expansion joints, construction            supports to prevent movement during concrete placement; joints, blockouts, and waterstops; proper form coating; and            (4) correct location and dimensions of block-outs, proper form cleanness,                                                            coating, and cleanness inspection of forms for tightness and placement of grout and vent pipes when preplaced aggregate concrete is used; (e) inspection of reinforcing steel, prestressing components (if  New requirements in NQA-applicable), and other embedded items to verify:                  1.
(1) correct size, number, location, position, cleanness, and leak tightness, if applicable; (2) proper stringing and absence of physical damage to pretensioning strands or tendons;
: 5. Inspection of mechanical reinforcing bar splicing operations        (f) inspection of mechanical reinforcing bar splicing operations  Similar requirement.
to verify conformance to the requirements of Section 4.9              to verify conformance to the requirements of para. 7.12; (g) inspection by use of a mandrel or similar device to ensure    New requirements in NQA-that the tendon conduits are open and remain open during the      1.
concrete placing operation; (h) inspection of pretensioning load cells and pressure gages for  New requirements in NQA-accuracy and calibration, if applicable;                          1.
(i) inspection of pretensioning system strand vises for cleanness, New requirements in NQA-proper lubrication, wear, distortion, and cracking, if applicable; 1.
__) inspection of the pretensioning operation, if applicable, to  New requirements in NQA-10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 13 of 30
* Supplementary
      .                Quality Assurance Requirements for,                      Quality Assurance Requirements. forlInstallation,        .COMMENTS Installation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Constru~ction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants
                      ..... Nuclear Power..Plants...        .    .      .......              NQA-1 1994 SUBPART 2.5 N45.2.54 974                              _____________________________________________,___"__
verify:                                                              1 (1) initial tensioning of each strand to eliminate slack and to provide a uniform initial stress condition in all strands prior to final stressing; (2) proper measurement and correlation of jack pressure (or load cell reading) and strand or tendon elongation; (3) proper correction for elongation losses due to strand slippage in the rises and movement of anchorage abutments; (k) inspection of groundwater control, as specified; (1) inspection for embedments.                                      New requirements in NQA-S1.
: 6. Documentation of inspections (1) through (5) above shall be        Documentation of the inspections required by steps                  Similar requirement, but verified as being complete and indicate that all results are          (a) through (1) above shall be verified as being complete and        expanded to cover the satisfactory.                                                          indicating that all inspection results are satisfactory.            additional activities above.
4.5 Concrete Placement                                                7.5 Concrete Placement Inspection of concrete placement shall be performed to verify          Inspection of concrete placement shall be performed to verify        Similar requirement.
the following                                                          the following:
: 1. Specified tests of concrete have been performed.                    (a) specified tests of concrete have been performed;                Similar requirement
: 2. Adherence to specified requirements for: class of concrete,        (b) adherence to specified requirements for class of concrete,      Similar requirement age, rate of placement, lift height, placing sequence, and hot or      age, rate of placement, lift height, placing sequence, concrete cold weather concreting practice. (ACI 305-72 or ACI 306-66            temperature, and hot or cold weather concreting practice (AC 1 respectively)                                                          305 or AC 1 306, respectively);
: 3. Proper use of adequate conveying and placing equipment.            (c) proper use of adequate conveying and placing equipment;          Similar requirement.
(d) harmful materials are not used in covering or placing            New requirement in equipment;                                                          NQA-1.
: 4. Adequate concrete consolidation equipment and technique of          (e) adequate concrete consolidation equipment and technique of      NQA- I incorporates the operation.                                                            operation (AC 1309);                                                reference to the ACI Reg. Guide 1.94-4/76, Position C.3 indicated that ACI 309-72                                                                                standard mentioned in the "should be used as a basis for determining the adequacy of the                                                                              NRC Reg. Guide, but equipment for concrete consolidation and of the technique of                                                                                doesn't limit to a specific operation."                                                                                                                                year. (Ref. NQA-1, Part IT, Introduction, Section 7)
: 5. Embedded items are not distributed nor forms displaced.            (f) embedded items are not disturbed nor forms displaced.            Similar requirement 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 14 of 30
 
      '*Supplementary QUaitytAssurance Reqruiremeatsfor .                      QualityAssuranceRequ&#xfd;ements for Installation,"                    '    O      .NTS.
Instaation, Inspection, andTesting of4Structural Concrete            Inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Co nstruction Phase of                Steel, Soils, and Foundations for Nucler. Power Plants Nuclear Power Plants                                                NQA-1 1994 SUBPART .5 N45.2.5 1974".
4.6 Finishing and Repair                                                7.6 Finishing and Repairs Inspections shall be performed to verify that specified finishes,      Inspections shall be performed to verify that specified finishes      Similar requirements.
i.e., wood float, steel trowel, as cast, or other type, are obtained,  are obtained, i.e., wood float, steel trowel, as cast, or other type.
After forms have been removed, inspections shall be performed          After forms have been removed, inspections shall be performed to verify that the formed surfaces have been repaired and              to verify that the formed surfaces have been repaired and finished in accordance with specified requirements.                    finished in accordance with specified requirements.
Any indications of voids or contamination, such as at a                Any indication of voids or contamination, such as at a                Similar requirement.
construction joint, shall be explored, by physical removal of          construction joint, shall be explored by physical removal of concrete if necessary, to determine the extent of such voids or        concrete, if necessary, to determine the extent of such voids or contamination. Appropriate repairs shall be made.                      contamination. Appropriate repairs shall be made.
4.7 Curing                                                              7.7 Curing Qualification tests shall be performed on liquid membrane            New requirement in forming curing compounds and sheet materials for concrete            NQA-1.
curing for compliance with ASTM C 309 in accordance with test methods given therein or ASTM C 171, as applicable.
Inspections shall be performed throughout the specified curing          Inspections shall be performed throughout the specified curing        Similar requirements.
period to verify the following:                                        period to verify the following:
: 1. Correct curing method is used, i.e., use of ponding, fog spray, (a) correct curing method is used, i.e., use of ponding, fog spray,      Similar requirement wet burlap, curing compound, or other method in accordance              wet burlap, curing compound, or other methods in accordance with specified requirements.                                            with specified requirements
: 2. Concrete is kept continuously, i.e., not periodically, wet          (b) concrete is kept continuously, i.e., not periodically, wet        Similar requirement during the entire curing period, if one of the wet curing methods during the entire curing period, if one of the wet curing methods is used.                                                                is used;
: 3. Membrane curing compounds are specifically approved for              (c) membrane curing compounds are specifically approved for          Similar requirement use prior to application.                                              use prior to application;
: 4. Curing temperatures is maintained within specified limits            (d) curing temperature is maintained within specified limits          Similar requirement during the entire curing period.                                        during the entire curing period;
: 5. Shoring and forms are left in place until concrete has reached (e) shoring and forms are left in place, and precast concrete              Similar requirement, NQA-the specified strength necessary to preclude the possibility of        members are left in the forms until concrete has reached              1 addresses precast damage from construction loads.                                        specified strength necessary to preclude the possibility of          members.
damage from construction loads; (f) concrete test cylinders are subjected to the same curing          New requirement in NQA-1 process as the concrete when field cured cylinders are required to evaluate curing methods Subsections 7.8 through 7.10 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                    Page 15 of 30
 
Suppl'ementary QutiAlity Assuran Requirements for                                              eQality AsurceReqiements            O*r*dstaliati6fn,-          COMMENTS Instal*ation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Structural Concrete, Structural and Struictural SteelbDuring the Construction Phase of                Steel, Soils, and Foundations for Nuclear Power Plants NuclearPower Plants                                                NQA-1 1994 SUBPART 2.5 N45.2.5 1974._________________________
NQA-1 adds new requirements for:                                  Not addressed in N45.2.5-Stress Transfer of Pretensioned Members (Subsection 7.8),        1974. Since there is no Post-Tensioning (Subsection 7.9), and Shipping and Handling      N45.2.5-1974 code to of Precast Concrete Members (Subsection 7. 10)                    compare to, the large volume of NQA-1 text is omitted.
4.8 In-Process Tests on Concrete and Reinforcing Steel                7.11 In-Process Tests on Concrete and Reinforcing and Prestressing Steel In-process tests shall be performed during the course of              In-process tests shall be performed during the course of          Similar requirement, but construction to maintain control of structural concrete. A list of    construction to maintain control of structural, prestressed, and  NQA- 1 includes the the required in-process tests is contained in Table B. The test        precast concrete. The tests which are required and the frequency additional items from the frequencies given shall be considered minimums. In-process            shall be in accordance with the ASME Boiler and Pressure          above new sections and tests shall be performed more frequently if test results are erratic  Vessel Code, Section HI, Division 2 (AC 1 Standard 359) except refers to an equivalent ACI or if the trend of results or an apparent change in material          as follows,                                                      standard rather than characteristics indicate that the frequency should be increased.      The ASME Boiler and Pressure Vessel Code, Section III,            including a table like Samples for in-process tests of concrete shall be taken at the        Division 2 (ACI Standard 359) test frequencies for the            N45.2.5.
sampling point in accordance with ASTM C 172. This point may          following tests shall be considered minimum, unless current be at the truck mixer discharge if the last piece of conveying        documentary test data are available to establish adequate equipment is a chute, bucket, conveyor system, or similar              confidence in conformance of materials to specified equipment. Pumped concrete must be sampled from the pump              requirements.
line discharge. No water or other ingredients may be added to          (a) for concrete materials - unit weight/yield any concrete batch at the sampling point for inprocess tests.          (b) for aggregate materials Samples shall not be taken from concrete after it has been                (1) unit weight of aggregate deposited in the form.                                                    (2) fixed water and iron content of aggregate only for radiation-shielding concrete (3) organic impurities (4) flat and elongated particles (5) lightweight particles (6) soft fragments (7) specific gravity and absorption (8) Los Angeles abrasion (9) potential reactivity (10) soundness The reduction of frequency of testing must be documented, and New requirement in NQA- 1 referenced documentation must be representative of the material II 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 16 of 30
 
Su-pplemnentary Quality Assurance Requirements for                              Assiuirance Req'u*i.remen's' fr Installation.,
tQualiy                                                CO.MMNTS Installation, Inspection, and Testing of Structural Concrete          Inspection, and Testing of Structural Concrete, Structural and Structural Steel During the Construction Phase of                Steel, Soils, and Foundations for Nuclear P!ower Plants Nuclear Power Plants        ..                                    NQA-1        4 SUBPART 2.5 N45.2517______________________1 currently being certified with the results of prior testing.
In-process tests shall be performed more frequently if test results are erratic, or if the trend of results or an apparent change in material characteristics indicates that the frequency should be increased.
Samples for in-process tests of concrete shall be taken following the procedures of ASTM C 172, except as defined herein regarding location of sampling. No water or other ingredients may be added to any concrete batch after making the in-process tests. Samples shall not be taken from concrete deposited in the form. Except as noted below, the sampling point for taking in-process test samples of plastic concrete shall be performed at the placement point or other points coincident thereto.
When concrete is pumped during its movement from the delivery point to the placement point, in-process strength samples shall be taken at the placement point, unless correlation tests of air content, slump, and temperature are performed.
When correlation testing is in effect, in-process strength samples may be taken at the delivery point.
In-process strength testing conducted at the mixing point is permitted, but unless the mixing point and the delivery point are considered coincident, correlation strength tests between samples taken at the mixing point and the delivery point are required. In this case, the frequency of the correlation of strength samples taken at the delivery point shall be taken each 500 CU yd (382 m3) of concrete or twice each week, whichever provides the greater number of samples.
If sampling is not accomplished at the placement point and if the delivery point and the placement point are not considered coincident, correlation tests will be established and performed for air content, slump, and temperature. The frequency of the correlation tests shall be at an interval of four times greater than the required test frequency. When any of the specified limits and tolerances on loss of air content, slump, or temperature are exceeded at the placement point, correlation strength tests 10/28/2010                    Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations        Page 17 of 30
 
SupplementarY Quality Assurance Requirements for                        Quality'Assurance RequirementsforInstallation, .                      COMMENS Installation, Inspection, and Testing of Structural Concrete          "Inspection, andTesting of Structural Concrete, Structural, and Structural Steel During the Construction Phase of                  Steel, Soils, and Foundations for Nuclear Power Plants            ,
Nuclear Power Plants                                                NQA-1 1994 SUBPART 2.5                      ... .
N-45.2.5 1974                              ______________________________________
between the delivery point and the placement point shall be accomplished for each 100 CU yd (76.5 m3) of concrete places as long as limits and tolerances are exceeded. If no limits and tolerances are specified, ASTM C 94 shall apply Table B, "Required In-Process Tests," is reproduced at the end of the matrix for readability Exceptions in the Current VCS FSAR:
Cadweld Testing: Item 4.9.4 Tensile Test Frequency) and Item 6.2.2 (Evaluation of Mechanical Splice Test Results). The testing program is based upon that set forth in Section III Division 2 of the ASME Boiler and Pressure Vessel Code.
Concrete: Table B "Required In-Process Tests" for compressive strength since the test frequency of concrete indicates 28-day strength tests and on 28 or 90 day strength tests is used.
Admixture: Table B "Required In-Process Tests" for Admixtures. Test by Infrared spectrophotometry analysis is not used.
4.9 Mechanical (Cadweld) Splice Testing                                7.12 Mechanical (Sleeve With Ferrous Filler Metal) Splice            NQA-l refers to equivalent Testing                                                              ACI standard rather than stating all the requirements in the subpart.
The mechanical (sleeve with ferrous filler metal) splice testing shall be done in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section HI, Division 2 (ACI Standard 359).
4.9.1 Qualification of Operators Prior to the production splicing of reinforcing bars, each 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                      Page 18 of 30
 
Supplementary. Quality Assurance Requireme                                                          ements for Installation,                COMMENTS Installations,  Inspection, and Testing of Structural Concrete        Inspection, and T-Iesting of Structural Concrete, Structural and Structural Steel During the Construction Phase of                Steel, Sois, and Foundations for Nuclear Power Plants Nuclear Power Plants                                            NQA-I 1994 SUBPART 2.5                                      .
N45.2.5_1974                              _________________________                                          ___________
member of the splicing crew (or each crew if the members work as a crew) shall prepare two qualification splices for each of the splice positions (e.g., horizontal, vertical, diagonal) to be used.
The qualification splices shall be made using the same materials (e.g., bar, sleeve, powder) as those to be used in the structure.
To qualify, the completed splices must meet the specified visual inspection acceptance requirements and meet the tensile test requirements of Section 4.9.3.
Each member of the splicing crew (or each crew if the members work as a crew) is subject to requalification (1) if the specific splice position (e.g., horizontal, vertical, diagonal) has not been used by member or crew for a period of three months or more or (2) if there is another reason to question their ability, such as the completed splices not passing visual inspection or tensile testing. The requalification procedure should be identical to the original qualification procedure.
4.9.2 Visual Inspection.
All completed mechanical splices shall be inspected at both ends of the splice sleeve and at the tap hole in the center of the splice sleeve for longitudinal centering of sleeve on the spliced ends, permissible gap between rebar ends, allowable voids in filler metal, extent of leaking of filler metal, gas blowout, amount of packing and slag at the tap hole. All visual inspections on completed splices shall be performed only after the splices have cooled to ambient temperatures. Splices that fail to pass visual inspection shall be discarded and replaced and shall not be used as tensile test samples.
4.9.3 Tensile Testing Splice samples may be production splices (i.e., those cut directly from in-place reinforcing) or sister splices (i.e., those removable splices made in place next to production splices and under the same conditions). A record shall be kept of all splices tested, showing the splice location, splice identification number, and whether the tested splice was a production or sister splice.
10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations              Page 19 of 30
 
Supplementary Quality Assurance Requirements for                        QualityAssurance Requirements for Instaation,                  COM  NS.
Installation,wInspection, and Testingeof Structural Concrete            Inspection, and Testing of StructurallConcrete, Structural and Structural Steel During the Construction Phase of                Steeli Soils, and Foundations for Nuclear Power Plants''
Nuclear Power Plants...                                      ....... QA-l 1.94 SUBPART 25.
N-45.2.5.1974 Splice samples shall be subjected to tensile tests in accordance with the sampling frequency specified in Section 4.9.4 to determine conformance with the following acceptance standards:
: 1. The tensile strength of each sample tested shall equal or exceed 125 percent of the minimum yield strength specified in ASTM A615 using loading rates set forth in ASTM A370.
: 2. The average tensile strength of each group of 15 consecutive samples shall equal or exceed the ultimate tensile strength specified for the reinforcing bar.
Since curved reinforcing bars will not tensile test accurately, production splice samples should not be removed from curved reinforcing bars for tensile testing. Straight sister splice samples should be made for each of the required curved reinforcing bar production splices. Production samples should also not be cut from the structure where the mechanical splicing sleeve is welded to an anchorage in a region of high stress concentration, or at a leak tight barrier (e.g., embedded structural steel sections or liner plate). Representative sister splice samples shall be used in such cases. The sampling frequency specified in Section 4.9.4(2) should then be followed, except that all splices tested shall be sister splices.                                            -4                                                                  +
4.9.4 Tensile Test Frequency.                                                                                                            I.
Separate test cycles shall be established for mechanical splices in horizontal, vertical, and diagonal bars, for each bar size, and for each splicing crew as follows:                                  -4                                                                  J.
: 1. Test Frequency For Production Splice Test Samples.                                                                                    4.
If only production splices are tested, the sample frequency shall be:
: a. One of the first 10 splices
: b. One of the next 90 splices
: c. Two of the next and subsequent units of 100 splices              -I                                                                  4.
: 2. Test Frequency for Combination of Production and Sister Splices.
If production and sister splices are tested, the sample freciuencv 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations        Page 20 of 30
 
Supplementary Quality Assurance Reurmet orQaiquirements for                                        urmnsfrItaltoCOMM.ENTS&#xfd; Installation, Inspection, andTestiing of Structural Concrete            Inspection, and Testing of Structural Concrete, Structural anidStructuralSteel During the Construction, Phase of                  Steel, Sols and Foundations for Nuclear Power Plants Nuclear Power Plants                                                NQA-.1 1994 SUBPART 2.5 N&#xfd;45.2.5 1974                            __________________________
shall be:
: a. One production splice of the first 10 production splices
: b. One production and three sister splices for the next 90 production splices
: c. Three splices, either production or sister splices for the next and subsequent units of 100 splices. At lease 1/4 of the total number of splices tested shall be production splices.
4.10 Welded Reinforcing Bar Splices                                    7.13 Welded Reinforcing Bar Splices Welded reinforcing bar splices shall be subject to the                Welded reinforcing bar splices shall be subject to the            NQA-1 addresses the code requirements of Section 5.5, except that provisions of AWS            requirements of para. 8.5, except that provisions of the ASME    the NRC Reg. Guide makes D12.1 shall apply.                                                    Boiler and Pressure Vessel Code, Section III, Division 2 (AC I    reference too.
Reg. Guide 1.94-4/76, Position C.4 states: "In addition, the          Standard 359) shall also apply.
provisions of Articles CC4334 and CC4330 of the 'Code for Concrete Reactor Vessels and Containments' (ASME Boiler and Pressure Vessel Code, Section III, Division 2, 1975 Edition) for testing of welded reinforcing bar splices should be used as guidance pending endorsement of that code by the NRC staff."
: 5. INSPECTION OF STEEL CONSTRUCTION                                    8 INSPECTION OF STEEL CONSTRUCTION 5.1 General                                                            8.1 General Inspection of steel construction in accordance with the AISC          Structural steel qualification shall be documented by            Similar requirement, but Manual of Steel Construction shall include inspection of              manufacturer's certification showing conformance to              NQA-I gives examples of assembly and erection operations, fastening or connecting              specifications such as ASTM A 36, A 441, or as otherwise          specifications to be used.
operations such as high strength bolting, and welding and              specified. Inspection of steel construction in accordance with finishing operations to include cleaning and protective painting      the AISC S326, Specification for the Design, Fabrication, and or coating.                                                            Erection of Structural Steel for Buildings shall include Inspection of steel construction shall include inspection of          inspection of assembly and erection operations, fastening or related items, such as anchor bolts and base plates, which may        connecting operations such as high strength bolting and be part of the supporting structure and installed as part of          welding,. and finishing operations to include cleaning and structural concrete work.                                              protective painting or coating. Inspection of steel construction shall include inspection of related items, such as anchor bolts and baseplates, which may be part of the supporting structure and installed as part of the structural concrete work.
5.2 Supporting Structures                                              8.2 Supporting Structures Prior to erection of steel, anchor bolts and base plates and other    Prior to erection of steel, anchor bolts, baseplates, and other  Similar requirement.
structural embedments shall be checked for correct orientation,        structural embedments shall be checked for correct orientation, 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 21 of 30
 
Supplementary QualityAssurance Requirements for                          QualityAssurance Requr ements for Instaation,C                          OMMENTS
.Installation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Structural Concrete, Structural                4-and Structural Steel Durig the Construction Phase of                  Ste Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants *...QA-.                                                1994 SUBPART 2.5          .
                          .N45.2.5 1974                              _________________________                                          ___________
spacing, and elevation. Base plate surfaces and supporting            spacing, and elevation. Baseplate surfaces and supporting concrete surfaces shall be checked to verify satisfactory              concrete surfaces shall be checked to verify satisfactory condition for grouting.                                                conditions for grouting. Grouting of baseplates, beam pockets, Grouting of base plates, beam pockets, etc., shall be controlled      etc., shall be controlled and inspected to verify that only to assure that only specified materials are used, proportioned        specified materials are used, proportioned properly, placed properly, placed correctly, and cured properly to achieve the          correctly, and cured properly to achieve the specified specified compressive strength                                        compressive strength 5.3 Assembly and Erection                                              8.3 Assembly and Erection Assembly and erection operations shall be inspected to verify          Assembly and erection operations shall be inspected to verify    Similar requirement.
compliance with installation procedures and work instructions,        compliance with installation procedures and work instructions.
Alignment operations shall be carried out early enough and as          Alignment operations shall be carried out early enough and as often as is necessary as erection progresses to insure that            often as is necessary as erection progresses to ensure that specified requirements are met.                                        specified requirements are met. Particular attention shall be Particular attention shall be given to verification of the            given to verification of the condition of contact surfaces of condition of contact surfaces of friction type connections and        friction type connections and bolt hole alignment. Correction of bolt hole alignment. Correction of fabrication errors shall be        fabrication errors shall be closely controlled to prevent closely controlled to prevent correction of misaligned holes by        correction of misaligned holes by reaming in excess of AISC reaming in excess of AISC tolerances. Burning of bolt holes is        tolerances. Burning of bolt holes is not permitted. Equipment not permitted. All equipment used in connecting operations            used in connecting operations shall be inspected to verify shall be inspected to verify conformance with specification            conformance with specification requirements. For example, air requirements. For example, air compressors must be of                  compressors shall be of sufficient capacity to maintain the sufficient capacity to maintain the required operating pressure        required operating pressures for impact tools.
for impact tools.
5.4 High Strength Bolting                                              8.4 High Strength Bolting Bolt tightening shall be in accordance with the specified              Bolt tightening shall be in accordance with the specified        Similar requirement.
method, i.e., automatic cut-off impact wrench or turn-of-nut          method, e.g., automatic cut-off impact wrench, turn-of-nut        NQA-1 adds allowance for method. If the turn-of-nut method is used, inspections shall be        method, or direct-tension indicator. If the turn-of-nut method is direct-tension indicator and made to verify that the bolting crews understand the meaning of        used, inspections shall be made to verify that the bolting crews  requires manufacturer "snug tight" condition before the nut is turned through the            understand the meaning of snug tight condition before the nut is  certification of bolt required angle. If an automatic cut-off impact wrench is used, it      turned through the required angle. If an automatic cutoff impact  qualification or other shall be calibrated at least twice daily. The calibration of          wrench is used, it shall be calibrated at least twice daily. The  specified assurance of automatic cut-off impact wrenches shall be performed by                calibration of automatic cut-off impact wrenches shall be        qualification.
tightening in a device capable of indicating actual bolt tension,      performed by tightening in a device capable of indicating actual using no less than three typical bolts of each diameter from the      bolt tension, using no less than three typical bolts of each bolts being installed. Installation of bolts shall be done in          diameter from the bolts being installed. Installation of bolts 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 22 of 30
 
Supplementary Quality Assurance Requirements for                        Quality Assurance Requirements for istallation, -                  COMMENTS Installation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Stuctural Concrete, Structural and Structural Steel During the Construction Phase ofS..t...              eel, Soils, and Foundations for Nuclear Power Plants
                  ... Nclear u.. Power Plants                                              NQA-1 1994SUBPART 2.5 N45.2.5 1974.                            _ _ _ _ _ _ _ _ __......                            .......                    ....
accordance with "Specifications for Structural Joints Using            shall be done in accordance with AISC 5329, Specifications for ASTM A325 or A490 Bolts."                                              Structural Joints Using ASTM A 325 or A 490 Bolts.
Qualification of bolts shall be documented by manufacturer's certification or as otherwise specified.
8.4.1 Inspection of Bolting.
Inspection of bolting shall include visual inspections of bolting      Inspection of bolting shall include visual inspection of bolting    Similar requirement, but operations and torque wrench inspection of completed                  operations and torque wrench inspection of completed                NQA-1 revised minimum connections. All connection points shall be visually inspected        connections: Connection points shall be visually inspected for      bolt length requirement.
for the following items:                                              the following items:
: 1. Bolts are the correct length as indicated by at least two          (a) bolts are long enough as indicated by the point of the bolts threads extending beyond the nut.                                      being flush with or outside the face of the nuts;
: 2. Correct type bolt is used as indicated by the manufacturer's        (b) correct type bolt is used as indicated by the manufacturer's marking on the head.                                                  marking on the head;
: 3. Torque has been applied as indicated by the burnishing or          (c) torque has been applied as indicated by the burnishing or peening of the corners of the nut.                                    peening of the corners of the nut;
: 4. Turning elements are on the correct face; washers are used          (d) turning elements are on the correct face; properly sized when required.                                                        washers are used when required.
The schedule of bolt tension inspection shall be as specified      Bolt tension inspection shall be as specified in AISC S329, in the latest edition of "Specification for Structural Joints Using    Specification for Structural Joints Using ASTM A 325 or A 490 ASTM A325 or A490 Bolts." In addition, at the beginning of            Bolts. In addition, during the initial phase of bolting operations, tightening operations, all bolts tightened by each bolting crew        all bolts tightened by each bolting crew shall be checked until shall be checked until the results are consistently acceptable.        the results are consistently acceptable.
8.4.2 Inspection Tools and Procedure.
Hand torque wrenches used for inspection shall be controlled in        Hand torque wrenches used for inspection shall be controlled in    Similar requirement, NQA-accordance with Section 2.5.2 and must be calibrated at least          accordance with Part I, Basic and Supplementary Requirements,      1 adds requirement to weekly and more often if deemed necessary. Impact torque              and shall be calibrated at least weekly, more often if deemed      control feeler gauges used wrenches used for inspection must be calibrated at least twice        necessary. Impact torque wrenches used for inspection shall be      for inspections.
daily.                                                                calibrated at least twice daily. Feeler gauges used for inspection  AISC S329 of direct-tension indicators shall be controlled.
5.5 Welding                                                            8.5 Welding Inspection of structural steel welding shall be performed in          Inspection of structural steel welding shall be performed in        NQA-1 adds requirement accordance with the provisions of AWS Dl. 1, Section 6,                accordance with the provisions of Section 6.0 of AWS Dl. 1,        for NDE when deemed entitled "Structural Welding Code" and supplemental addenda.          Structural Welding Code - Steel. This inspection shall include      necessary.
This inspection shall include visual examination of preparations,      visual examination of preparations, welding processes, post-welding processes, and post-welding operations. Prior to              welding operations, and if deemed necessary, some NDE 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 23 of 30
 
Supplementary Qualit Assurance Requirements for                          QualityAssurance Requirements for Installation,                    COM        NS Installation, Inspection, and Testing of Structural Concrete            Inspection, and Testing of Structural Concrete,.Structural.................
and Structural Steel During the Construction Phase .of                  Stee, Soils, and Foundations for Nuclear.oweroPlantsf Nuclear Power Plants...1994                                          NQA-.        SUBP.ART 2.5'                                        ...  .
:N45*.2.5 1974 ..                                                                                                _____.. __.._. ___'
welding, verification of welding procedure and welder                  inspections which are appropriate to the application. Prior to qualification shall be documented and shall include all essential      welding, verification of welding procedure and welder variables identified in the procedure.                                  qualification shall be documented and shall include all essential variables identified in the procedures.
In-process inspections shall include joint fit up prior to start of    In-process inspections shall include acceptability of            NQA- I added inspection welding, preheat and interpass temperature requirements, filler        environmental conditions, joint fit-up prior to start of welding, point for environmental metal, control of distortion, and post-weld heat treatment and          preheat and interpass temperature requirements, filler metal,    conditions.
cleaning requirements. Procedures shall be established to              control of distortion, post-weld heat treatment, and cleaning control the purchase, receiving, distribution, storage and use of      requirements. Procedures shall be established to control the welding electrode.                                                      purchase, receiving, distribution, storage, and use of welding electrodes.
Weld repairs necessitated by visual or nondestructive                  Weld repairs necessitated by visual or nondestructive            Similar requirement.
examinations shall be made in accordance with the procedure            examinations shall be made in accordance with the procedure used to perform the original weld or a qualified repair procedure      used to perform the original weld or a qualified repair procedure and reinspected by the same method which disclosed the                  and reinspected by the same method that disclosed the repairable defect. All weld repairs necessitated by                    repairable defect. All weld repairs necessitated by nondestructive examinations shall be documented.                        nondestructive examination shall be documented.
: 6. DATA ANALYSIS AND EVALUATION                                        9 DATA ANALYSIS AND EVALUATION 6.1 General                                                            9.1 General Procedures shall be established for processing inspection and          Procedures shall be established for processing inspection and    Similar requirement.
test data and their analysis and evaluation. These procedures          test data and their analysis and evaluation. These procedures shall provide for acquisition and preparation of inspection and        shall provide for acquisitions and preparation of inspection and test data for prompt evaluation against acceptance criteria,            test data for prompt evaluation against acceptance criteria, operating limits, and performance standards.                            operating limits, and performance standards.
The data processing procedures shall provide for "on-the-spot"          The data processing procedures shall provide for on-the-spot      Similar requirement.
evaluation to determine the validity of the inspection and test        evaluation to determine the validity of the inspection and test results, and the appropriateness of continuing the inspection or        results and the appropriateness of continuing the inspection or test. The data shall be analyzed and evaluated to verify the            test. The data shall be analyzed and evaluated to verify completeness of results, achievement of inspection and test            completeness of results and achievement of inspection and test objectives, and to identify additional inspection and tests            objectives; and to identify additional inspection and tests required; and necessary changes to the installation inspection or      required, and necessary changes to the installation inspection or test procedures. Inspection and test results that include              test procedures. Inspection and test results that include inspection and test data, together with a report of data analysis      inspection and test data, together with a report of data analysis and evaluation, shall be prepared as specified in Section 7.            and evaluation, shall be provided as specified in Section 10.
6.2 Concrete and Mechanical (Cadweld) Splice Test Data                  9.2 Concrete and Mechanical (Sleeve With Ferrous Filler 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 24 of 30
 
Supplementary'Quality Assurance Requirements for'                        'Quality Assurance'Requirements for,Installation, Installation, Inspection, and-Testing of Structural Concrete              Inspection, and Testing of Structural Concrete, Structural I
and Structural Steel During the Construction Phase of                    Steel,.Soils, and Foundations for Nuclear Power Plants Nuclear Power Plants                                                  NQA-1 1994 SUBPART 2.5 N45.2.51974 Evaluation and Analysis                                                  Metal) Splice Test Data Evaluation and Analysis 6.2.1 Evaluation of Concrete Test Results.                              9.2.1 Evaluation of Concrete Test Results.
Standard deviation data shall be developed, evaluated, and              Standard deviation data shall be developed, evaluated, and        Similar requirement.
maintained for permanent records in accordance with ACI 214.            maintained for permanent records in accordance with ACI 214.
Concrete quality and acceptance criteria shall conform to the            Concrete quality and acceptance criteria shall conform to the requirements of ACI 318, Chapter 4.                                      requirements of ACI 318, Chapter 4.
6.2.2 Evaluation of Mechanical (Cadweld) Splice Test Results.            9.2.2 Evaluation of Mechanical Splice Test Results.
The following procedure shall be used for substandard tensile            The evaluation of mechanical splice test results shall be in      Similar requirement.
test results.                                                            accordance with ASME Boiler and Pressure Vessel Code, Section III, Division 2 (ACI Standard 359).
: 1. If any production of sister splice tested fails to meet the tensile test specification of Section 4.9.3(1) and the observed rate of splices that fail the tensile test at that time does not exceed one for each 15 consecutive test samples, the sampling procedure shall be started anew. If any production or sister splice used for testing fails to meet the tensile test specification in Section 4.9.3(1) and the observed rate of splices that fail the tensile test exceeds one for each 15 consecutive test samples, mechanical splicing shall be stopped. In addition, the adjacent production splices on each side of the last failed splice and four other splices distributed uniformly throughout the balance of the 100 production splices under investigation shall be tested, and an independent laboratory analysis shall be made to identify the cause of all failures. The results of these tests shall be evaluated by the responsible engineering organization to determine the required corrective action. The responsible engineering organization shall specify the extent of repairs necessary and the actions required to prevent further failures from the identified causes. If two or more splices from any of these six additional splice samples fail to meet the tensile test specification of Section 4.9.3(1), the balance of the 100 production splices under investigation shall be rejected and replaced. When mechanical splicing is resumed, the sampling procedure shall be started anew.
: 2. If the average tensile strength of the 15 consecutive samples 10/2 8/2 010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 25 of 30
 
Supplementary Quality Assurarnce Requireiments, for                    Quality A&#xfd;ssuranie' Require'ments1fo nstalltion,                  COMMENTS, Installation, Inspection, and Testing of Stractural Concrete          Inspection, and Testmig of Structural Concrete&#xa2;,Structural and Structural Steel During the Construction Phase of                Stee, Soils, and Foundations for Nuclear Power Plants Nuclear Pow~er Plants        .        .NQA-1                              1994 SUBPART 2.5 N45.2.5 1974                            _________________________
fails to meet the provisions of Section 4.9.3(2), the responsible engineering organization shall evaluate and assess the acceptability of the reduced average tensile strength with respect to the required strength of the location from which the samples were taken.
9.2.3 Evaluations of Aggregate Test Results.
When any aggregate tests specified fail to meet the specified      New requirement in requirements, two additional tests shall be made from samples      NQA-1.
of the same lot of aggregate. If one or both of the two additional tests fails to meet the specified requirements, the data shall be submitted to the responsible engineering organization for evaluation and corrective action 6.3 Steel Construction Test Data Evaluation and Analysis              9.3 Steel Construction Test Data Evaluation and Analysis These data shall be evaluated for conformance to project              This data shall be evaluated for conformance to project            Similar requirement.
specifications, the AISC Manual of Steel Construction and            specifications of the AISC MOI 1, Manual of Steel Construction AWS D1. 1 and supplemental addenda.                                  and AWS Dl.1, Structural Welding Code - Steel.
9.4 Soils Test Data Evaluation and Analysis This data shall be evaluated daily during progress of the work    New requirement in NQA- 1 for conformance to project specifications. The control techniques given in the specifications, such as specific test methods for the type of soil compacted, shall be verified. Data shall include determination of parameters specified, including use of proper materials, amounts and uniformity of soil moisture, and thickness of layers being placed. In-place compacted fill density shall be determined using standard approved methods and the results evaluated for compliance to specified requirements. Data shall include verification that the soils are fully compacted or consolidated to contours and the grades specified. When statistical methods are required by the specification, the desired level of confidence shall be specified.
: 7. RECORDS                                                            10 RECORDS Record copies of completed procedures, reports, personnel            Record copies of procedures, reports, personnel qualification      Similar requirement qualification records, test equipment calibration records, test      records, test equipment calibration records, test deviation or deviation or exception records, and inspection and examination        exception records, and inspection and examination records shall records shall be prepared. These shall be placed with other          be prepared. These shall be retained with other project records 10/28/2010                      Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                Page 26 of 30
 
Supplem~ientary Quality Assurance ReqUirements for, , 1 " "Quality                    Assurance Requiriements for Installation,                                  COMMENTET        ,
ilation, Inspectionl SItfiatdo*
Insta.          ns Steel i    and . Testingkof Sructura~lConcrete iStructu          Phaset        IsetoadTCM Inspeceti0n, and sting of Structural Concrete, Stiuctural                            .
* andStuctra StelDuring the Construction Paeof                    Steel, Soils''n Fonain                          for Nuclear Power Plants Nuclear Power Plants                          ~NQA-1                                    1994 SUBPART 2.5 N45.2.5,4974, project records as required by code, standard, specification, or      as required by code, standard, specification, or project project procedures.                                                    procedures.
Collection, storage and maintenance of records shall be in                                                                                                    N45.2.9 is similar to accordance with ANSI N45.2.9.                                                                                                                                NQA-l, Supplement 17S-1 (mandatory) and Appendix 17A-l (non-mandatory),
additional requirements are addressed in Part 11, Section
____________________________________                          17.0 of the QAPD.
: 8. REVISIONS OF AMERICAN NATIONAL STANDARD REFERRED TO IN THIS DOCUMENT                                          __________________
When the following standards referred to in this document are                                                                                                The QAPD addresses the superseded by a revision approved by the American National                                                                                                    standards for the program.
Standards Institute the revision shall apply:
N45.2 Quality Assurance Program Requirements for Nuclear Power Plants N45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants N45.2.3 Housekeeping During the Construction Phase of Nuclear Power Plants N45.2.6 Qualifications of Inspection, Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants N45.2.9 Requirements for Quality Assurance Records for Nuclear Power Plants N45.2.l10 Quality Assurance Terms and Definitions                    _______________________                                                                  __________
K~~~~~ ~ANSI                    N  4S.2.541974,          Table A                      ___________________
                                  *.                                      ~~~~~~~~~~~Qualification Tests:______________________
Material                                                    Test__________For,          ______                                  Test Method, Concrete Aggregates                                        Compliance with ASTM C33                                                  As referenced in ASTM C33 Cement                                                    Compliance with ASTM C 150                                                As referenced in ASTM C150 10/28/2010                        Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                                    Page 27 of 30
 
                              *.  ."*, '*. '    .:'?"*            :"'ASN4ANSI N 45.2.54974, Tab.leA A__:....                                      __'  _  _"
                                                            ......      **';    ualification Tests Test For                          "MateriA1e. Test Method Admixtures                                            Compliance with ASTM C260 or C494 whichever            Manufacturer's Certification is applicable Fly Ash & Pozzolans                                    Compliance with ASTM C618                              As referenced in ASTM C618 Water & Ice                                            Compliance with AASHO T-26 for effect on:
Compressive Strength:                                  ASTM C109 Setting Time:                                          ASTM C191 Soundness ASTM C 15 1:                                  ASTM C 151 Liquid Membrane Forming Curing Compound                Compliance with ASTM C309                              As referenced in ASTM C309 Sheet Materials for Concrete Curing                    Compliance with ASTM C 171                              As referenced in ASTM C 171 Concrete Mixes                                        Compliance with ACI 211                                As referenced in ACI 211 Reinforcement                                          *Physical properties of full section test specimen      *One full section test in accordance with ASTM per ASTM A615                                          A370 for each bar size Structural Steel                                      Compliance with appropriate specifications such        Manufacturer's certification as ASTM A36, A440, etc.
High Strength Bolts                                    Compliance with ASTM A325 or A490                      Manufacturer's certification
                                                                                                              *Reduced section test specimen may be used for determination of the percentage of elongation.
10/28/2010                    Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 28 of 30
 
ANSI N45.2.5-974 Table                      ..
Reqire In-Process Tests                        ~
material                          Requirement                              TatMethod                                  Test Frequencyi Sampling method                          ASTM C 172 Compression cylinders                    ASTM C31                                  2 cylinders for 28-day test from each Compressive strength                      ASTM C39                                  100 cu yd or a minimum of Iset/day for each class of concrete First batch produced each day and Slump                                    ASTM C143                                  every 50 cu yd placed First batch produced each day and Air content                              ASTM C 173 or C231                        every 50 cu yd placed First batch produced each day and every 50 cu yd placed Temperature Daily during production Unit weight/yield                        ASTM C138 Grout                          Compressive strength                      ASTM C 109                                Daily during production Aggregate                      Compliance with requirements for:
Gradation                                ASTM C 136                                Daily during production Moisture content                          ASTM C566                                  Daily during production Material finer than No. 200 sieve        ASTM C 117                                Daily during production Organic impurities                        ASTM C40                                  Weekly during production*
Friable Particles                        ASTM C142                                  Monthly during production*
Lightweight pieces                        ASTM C 123                                Monthly during production*
10/28/2010          Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 29 of 30
 
AJNSI N4 .1974Y~      Table  B                        .
      *    .:.....  ....... ..                  . .. Requirement...                  .  .... Test Method                              Test Fr4e n.cy,        .  ".
Soft fragments                            ASTM C235                                  Monthly during production*
Los Angeles abrasion                      ASTM C1 31 or C535                        Every 6 months*
Flat and elongated particles              CRD C1 19                                  Every 6 months*
Potential reactivity                      ASTM C289                                  Every 6 months*
Soundness                                ASTM C88                                  Every 6 months*
Water & Ice                                Compliance with AASHO T26 for effect on:
Every 6 months Compressive strength                      ASTM C109 Every 6 months Setting time                              ASTM C191 Every 6 months Soundness                                ASTM C 151 Admixtures                                Chemical Composition                      Infrared spectrophotometry analysis        Composite of each shipment Fly Ash & Pozzolans                        Chemical & physical properties per        ASTM C311                                  Each 200 tons ASTM C618 Cement                                    Standard physical and chemical            ASTM C150                                  Each 1200 tons ASTM C183 properties Reinforcing Steel                          **Physical properties of full section    ASTM A370                                  **One full section test for each bar test specimen per ASTM A615                                                          size for each 50 tons or fraction hereof from each heat Cadweld Reinforcing Bar Splices            Section 4.9.3                            Section 4.9.3                              Section 4.9.4
* These test frequencies shall be considered minimum unless current documentary test data are available to establish complete confidence in conformance to specification requirements.
"*Reducedsection test specimen may be used for determination of the percentage of elongation 10/28/2010                      Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations                  Page 30 of 30
 
Supple+mentary Quali*yMssurance Requirements For                        Quality Assurance RequirementsTfor Instaflation,                  I2ONIMETS Installation, Inspection And Testing Of Mechanical                  Inspection, and Testin.g of Mechanical EquPnpment and.
Equipment And Systems For The Construction Phase Of                              Systems for Nuclear Power Plants Nuclear Power Plants                                                NQA-1 1994 Subpart 2.8 ANSI N45.2.8    &#xfd;- 1975:-____________
1.1 Scope                                                              1 GENERAL This standard contains requirements and guidelines to assure the      Subpart 2.8 provides amplified requirements for installation,    Similar requirement quality of important items of nuclear power plants including          inspection, and testing of mechanical equipment and systems. It structures, systems and components. The requirements and              supplements the requirements of Part I and shall be used in guidelines are intended to assure that these important items are      conjunction with applicable Basic and Supplementary Sections installed, inspected and tested in a manner that will provide          of Part I when and to the extent specified by the organization adequate confidence that they will perform satisfactorily in          invoking Subpart 2.8.
service. The requirements and guidelines for installation, inspection and testing activities during construction are intended to assure the quality of mechanical items not covered by Section
.III of the ASME Boiler and Pressure Vessel Code. The requirements of this standard deal with the protection and control necessary to assure that the requisite quality of mechanical items of the plant are preserved from the time items are removed from storage or receiving until they are incorporated into the plant up to but not including, fuel loading of PWR plants and the completion of cold functional testing of BWR and HTGR plants. This standard is intended to be used in conjunction with ANSI N45.2. If any conflict exists, ANSI N45.2 shall govern.
1.2 Applicability The requirements and guidelines of this standard apply to the          Applicability is discussed in NQA- I-1994, Part II, Introduction. The NQA-1, Part II, work of any individual or organization that participates in                                                                              Introduction section on installation, inspection or testing of mechanical equipment                                                                              applicability does not during construction activities of nuclear power plants as                                                                                contain as much detail as discussed in Subsection 1.1. The extent to which the individual                                                                          N45.2.8, but it does address requirements of a standard apply will depend upon the nature                                                                            the substance of N45.2.8 and scope of the work to be performed and the importance of                                                                              regarding assuring use of the item or service involved. Important mechanical items to be                                                                          proper materials, covered and the extent of coverage shall be identified by the                                                                            equipment, processes, and individual or organization invoking this standard. The                                                                                  procedures.
requirements are intended to assure that only proper materials, equipment, processes and procedures are utilized during the construction of power plants and that the quality of items is not degraded as a result of installation, inspection and testing 10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page I of 23
 
Supplementary Quality Ass*&#xfd;rnce Requirements For                        Quality Ass'urance Requirements for Installation,  .    ."COMMENTS Installation, Inspection And Testing Of Mechanical                  Inspection, and Testing of Mechanical Equipm~ent and Equipment And Systenms For The                                                    Synstrtctmst for Nuclear, Power Plants f**efstems Nuclear Power Plants                                              NQA-1 1994 Supr 2.8.......
              ...... ANS N451-2.8 - 1975                                                              upr practices and techniques during construction. The ASME Boiler and Pressure Vessel Code (herewith referred to as the Code), as well as other American National Standards has been considered in the development of this standard, and this standard is intended to be compatible with their requirements. However, this standard does not apply to activities covered by Section Ill Division 1 and 2 and Section XI of the Code for those activities covered by the Code.
Reg. Guide 1.116, 5/77 Position C.2 states:. Although ANSI N45.2.8-1975 is entitled "Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants," the requirements included in the standard are considered to be applicable during the operations phase as well as the construction phase and should be followed for those applicable operations phase activities that are comparable to activities occurring during the construction phase. In this regard, it should be noted that N45.2.8-1975 does not address radiological considerations associated with installation, inspection, and testing of mechanical components in radioactively contaminated systems.
1.3 Responsibility The organization or organizations responsible for establishing        Responsibility is discussed in NQA-1 -1994, Part II,        The combination of the the applicable requirements for the activities covered by this        Introduction, and programmatically in NQA-1, Part I, Basic  requirements from NQA- 1 standard shall be identified and the scope of their                  Requirement 1 with Supplement 1S-1.                          is equivalent to the responsibilities shall be documented. The work of establishing                                                                    requirements stated by practices and procedures and providing the resources in terms of                                                                  N45.2.8.
personnel, equipment and services necessary to implement the requirements of this standard may be delegated to other organizations and such delegation shall also be documented. It is the responsibility of each organization performing work covered by this standard to comply with the procedures and instructions issued for the project and to conform to the requirements of this standard applicable to this work. It is the responsibility of the organization performing these activities to 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                      Page 2 of 23
 
Supplementary Quality Assurance Requirements Forr                      Quality As'urauce Requirements for Installation,                      COMME""S Installation, Inspection And Testing Of Mechanical                  Inspection, and Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                Systems for Nuclear Power Plants Nuclear Power Plants                                                NQA-1 1994 Subpart 2.8."....                ...            .      .
ANSIjN45.2.8    - 1975 specify the detailed methods and procedures unless they are specified in the procurement documents.
1.4 Definitions                                                      1.1 Definitions The following definitions are provided to assure a uniform            The following definitions are provided to assure a uniform          NQA-1 defines the common understanding of select terms as they are used in this standard. understanding of unique terms as they are used in Subpart 2.8.        terms used throughout the standard in Part I, Introduction &sect; 4.
Acceptance Criteria - A limit or limits placed on the variation      (From Part I) acceptance criteria - specified limits placed on      Similar requirement, but permitted in the characteristics of an item expressed in            characteristics of an item, process, or service defined in codes,    doesn't list the examples.
definitive engineering terms such as dimensional tolerances,          standards, or other requirement documents.
chemical composition limits, density and size of defects, temperature ranges, time limits, operating parameters, and other similar characteristics.
Checks - The tests, measurements, verifications or controls          Checks - The tests, measurements, verifications, or controls          Similar requirement placed on an activity by means of investigations, comparisons,      placed on an activity by means of investigations, comparisons, or examinations to determine satisfactory condition, accuracy,      or examinations to determine satisfactory condition, accuracy, safety or performance.                                              safety, or performance Engineering Limitations - Restrictions which, if disregarded,        Engineering limitations - restrictions which, if disregarded, may    Similar requirement may result in damage to the item, shortening the life of the item,  result in damage to the item, shortening the life of the item, or or preventing the item from functioning as intended,                preventing the item from functioning as intended Examination - An element of inspection consisting of                Examination - an element of inspection consisting of                  Similar requirement investigation of materials, components, supplies and services to    investigation of materials, components, supplies, and services to determine conformance to those specified requirements which          determine conformance to those specified requirements which can be determined by such investigation. Examination is usually      can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation,            nondestructive and includes simple physical manipulation, gaging and measurement.                                              gaging, and measurement.
Inspection - An element of quality control which by means of        (From Part I) inspection - examination or measurement to verify      Similar requirement examination, observation or measurement determines the              whether an item or activity conforms to specified requirements.
conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.
Mechanical Items - Parts, components, or systems that function      Mechanical items - parts, components, or systems that function        Similar requirement primarily for pressure retaining, mass moving, or heat exchange      primarily for pressure retaining, mass moving, or heat exchange purposes. Examples of mechanical items are rotating equipment        purposes. Examples of mechanical items are rotating equipment (motors, pumps, blowers), handling equipment (cranes, hoists,        (motors, pumps, blowers), handling equipment (cranes, hoists, 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                              Page 3 of 23
 
  -,Suppllementary Quality Assurance Requirements Fo r                        *."QualityAssuranceR~equirements for,Installation, Installation, Inspection And Testing OfMechanical                    Inspection, and Testing of Mechanical Equipment and Equipment And Systems F*or The Construction.Phase Of...                            Systems for Nuclear Power Plants Nuclear Power Plants                                                  NQA- 1 1994 Subpart 2.8 ANSI N45.2.8 -.1975.
conveyors), piping systems (pipe, valves, hangers), fuel                conveyors), piping systems (pipe, valves, hangers), fuel handling systems, and waste effluent systems.                          handling systems, and waste effluent systems.
Testing - The determination or verification of the capability of        (From Part I) testing - an element of verification for the      Similar requirement an item to meet specified requirements by subjecting the item to        determination of the capability of an item to meet specified a set of physical, chemical, environmental or operating                requirements by subjecting the item to a set of physical, conditions.                                                            chemical, environmental, or operating conditions Verification - An act of confirming, substantiating and assuring        (From Part I) verification - the act of reviewing, inspecting,  NQA-1 definition that an activity or condition has been implemented in                  testing, checking, auditing, or otherwise determining and      encompasses the N45.2.8 conformance with the specified requirements.                            documenting whether items, processes, services, or documents    definition in substance, but conform to specified requirements.                              not using the same terminology.
Other terms and their definitions are contained in ANSI                                                                                Other terms for NQA- 1 are N45.2. 10.                                                                                                                              defined in Part I, Introduction &sect; 4.
1.5 Referenced Documents Documents that are required to be included as a part of this                                                                            Similar requirement exists standard are identified at the point of reference and described in                                                                      in NQA-1, Part 11, Section 8 of this standard. The issue or edition of the referenced                                                                      Introduction, &sect; 7. The document that is required will be specified either at the point of                                                                      QAPD addresses the reference or in Section 8 of this standard unless otherwise                                                                            standards for the program.
specified in the contract document.
Reg. Guide 1.116 5/77 Position C.1 states: Subdivision 1.5 of ANSI N45.2.8-1975 states: "Documents that are required to be included as a part of this standard are identified at the point of reference and described in Section 8 of this standard." The specific acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations where appropriate.
: 2. GENERAL REQUIREMENTS                                                2 GENERAL REQUIREMENTS This section contains requirements that are to be fulfilled by the Measures shall be established and implemented for                    Similar requirement.
organization or organizations responsible for performing any            documenting the necessary installation, inspection, and testing segment of work described in Section 3 through 5 of this                to verify conformance to specified requirements.
standard. Measures shall be established and implemented for documenting the necessary installation, inspection and testing to verify conformance to specified requirements 10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                        Page 4 of 23
 
  *Sn'ppleme .nta.*.rQuali*Assu~ranceRequ Say Qments                        mntik':*For ....  *o... Quality
                                                                                ... . Assurance
                                                                                            .. ... Requirements. for
                                                                                                                    ,.*...Installation,
                                                                                                                              .*....          COMME.NTS Installation, Inspection And Testing Of Mechanical                    Inei              Testing o    e...        E ie                :n                      '.
Equipment And Systems For The Construction Phase Of                      !Sy.spcn,    stean TortNugMear PoweqruP ments"a"'.
Nuclear Power Plants                                                NQA-1 1994 Subpa2.8 ANSI N,45.2.8 - 1975N                                                        199. Subpart..8.....
2.1 Planning                                                            2.1 Planning and Procedures Activities shall be planned and documented to be consistent            Planning and procedure preparation shall be in accordance with  NQA-1, Part II, with engineering and design requirements including those                the requirements of the Introduction to this Part (Part II). Introduction, &sect; 4.1 which define the degree of importance to safety and reliability                                                                        addresses Planning and of the item. Planning shall define the operations to be used and                                                                        contains similar the systematic, sequential progression of operations, the                                                                              requirements to N45.2.8.
personnel responsibilities for each activity and the measures employed to preserve the quality of the item. Planning shall take into account the need for the identification, preparation and control of procedures and work instructions necessary to comply with requirements for installation, inspection and testing of components and systems; and the need for trained personnel necessary to comply with these procedures, work instructions, and requirements. Planning shall include a review of the system and component design specifications, procurement documents and drawings and of the construction work plans and schedules to assure that applicable installation, inspection, and testing activities have been identified; that they can be accomplished as specified; and that time and resources are sufficient to accomplish the required actions. Deficiencies identified during reviews shall be brought to the attention of the responsible organization for action.
2.2 Procedures and Instructions Installation, inspection and test procedures and work                                                                                  NQA-1, Part II, instructions identified during planning shall be prepared and                                                                          Introduction, &sect; 4.2 documented for those activities falling within the scope of this                                                                        addresses Procedures and standard. Where the planning review identifies new procedures                                                                          contains similar and inspections that are necessary, appropriate target dates and                                                                        requirements to N45.2.8.
effort shall be scheduled for their preparation and approval.                                                                          The specific list of items in These documents shall be kept current and revised as necessary                                                                          N45.2.8 is all encompassed to assure that installation, inspections, and tests are performed in                                                                    by the list in NQA-1.
accordance with latest approved information and shall include as appropriate:.
: a. Prerequisites identified in Subsection 2.9.
: b. Precautions to be observed.
10/28/2010                                            Installation, Inspection, and-Testing of-Mechanical Equipment and Systems                        Page 5 of 23
 
Supplementary Quali;t    AssuranceReqirementsO For                =    Quality Assurance Requirements for Inst ali;on,          COMMENTS Installation, inspection And Testing Of Mechanical                  Inspection, and Testing of Mechanical Equipment and Nuclear For Equipment And Systems                Construction Phase.Of ThePlants Power                                                Systems NQA-for1 Nuclear Power2.8Plants 1994 Subpart
              ...... ANSI N45.2.    -1975                .
: c. Installation requirements.
: d. Sequential actions to be followed.
: e. Test objectives.
: f. Special equipment required for installation, inspection and test.
: g. Identification of inspection and test equipment.
: h. Frequency of inspection or test.
: i. Inspection and test acceptance criteria.
: j. Specific document references where required.
: k. Data report forms.
1.Approvals 2.3 Results Inspection and test results shall be documented in a suitable test                                                              NQA-1 addresses these report or data sheet. Each report shall identify the item to which                                                              requirements under the it applies, the procedures or instruction followed in performing                                                                programmatic controls of the task and include the following:                                                                                            Basic Requirements 10 and
: a. Pertinent inspection and test data.                                                                                          11, and Supplements 10S-1
: b. Significant dates and times.                                                                                                and 11S-1.
: c. Signature or stamp of inspector or tester.
: d. Measuring and test equipment used where required.
: e. Identification of nonconformances and action taken on other conditions that were not anticipated.
Test reports and data sheets shall include an evaluation of the acceptability of inspection and tests results and provide for identifing the individual who performed the evaluation.
2.4 Cleaning Cleaning activities required by this standard shall be performed                                                                NQA-1, Part II addresses in accordance with ANSI N45.2.1 and Section 4 of this                                                                          cleaning activities under standard.                                                                                                                      Subpart 2.1.
2.5 Receiving, Storage and Handling Receiving, storage and handling activities required by this                                                                    NQA-1, Part II addresses standard shall be performed in accordance with ANSI N45.2.2                                                                    receiving, storage, and handling activities under Subpart 2.2.
2.6 Housekeeping 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                  Page 6 of 23
* Supplementary Quality Assurance Requirements For                        Quali Assurance s        Requirements for Installation,        COMMENTS Installation, Inspection And Testing Of Mechancal .                  Inspectin,adTesting of MechanicalEquipment and Equipen.t And Systems ForThe Construction Phase Of                                Systems for Nuclear Power Plants Nuclear Powe Plants                                          . NQA-1 1994 Subpart 28>
9ANSIN45.28.- 1975 In areas, facilities, and environments where installation,                                                                      NQA-1, Part II addresses inspection and testing of mechanical items is performed in                                                                      housekeeping activities accordance with the requirements of this standard, the                                                                          under Subpart 2.3.
housekeeping requirements shall be in accordance with ANSI N45.2.3.
2.7 Personnel Qualifications Those personnel who perform inspection and testing activities                                                                  NQA-1, Part I addresses required by this standard shall be qualified in accordance with                                                                inspection and testing ANSI N45.2.6.                                                                                                                  qualifications under Supplements 2S-1 and 2S-2.
2.8 Measuring and Test Equipment                                                                                                NQA-1 addresses Measuring and Test Equipment under Basic Requirement 12, Supplement 12S-1, and Subpart 2.16.
2.8.1 Selection.
Measuring and test equipment used to implement the requirements of this standard shall be selected to have range, type and accuracy sufficient to determine conformance to specified requirements.
2.8.2 Calibration and Control.
Measuring and test equipment used to determine compliance with Specifications, shall be adjusted and calibrated at predetermined intervals, based on equipment stability and use, against certified equipment having known valid relationships to nationally recognized standards, If no national standards exist, the basis for calibration shall be documented. Records of calibrations shall be maintained and equipment suitably marked so that the calibration status can be determined. Records of calibration shall be included in inspection and test results where applicable. Measures shall be taken to assure proper handling, storage, and care of the measuring and test equipment after calibration in order to maintain the required accuracy of such equipment. When measuring and test equipment is found to be 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                Page 7 of 23
 
Supplementary Quality Assurance Requiremeti.s For                          *Quality Assurance'Requirements for Installation, Installation, Inspection And Testing Of Mechanical                    Inspectioni and Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                  Systems~ forNuclear Power Plants.
Nuclear Power Plants.                                                  NQA&#xfd;-l 1994 Subpart 2.8 ANSI N45.2.8 -19,75 out of calibration, an evaluation shall be made of the validity of previous inspection or test results and the acceptability of mechanical items inspected or tested since the last calibration check. Where necessary to determine the acceptability of items or data, the required original inspections or tests or applicable portions thereof shall be repeated using properly calibrated equipment. In the event that the status of equipment precludes using the originally specified methods, equipment or procedures, alternate inspections or tests agreeable to the responsible organizations may be used.
1~
2.9 Prerequisites                                                        2.2 Prerequisites The following minimum conditions shall have been met or                  The following minimum conditions shall have been met, or            Similar requirement.
evidence thereof shall be available as applicable before the            evidence thereof shall be available as applicable, before the      ANSI N45.2.8 refers to requirements set forth in this standard are applied:                    requirements set forth in Subpart 2.8 are applied.                  "construction site" and
: a. Qualification of individuals, organizations and procedures            (a) Qualification of individuals, organizations, and procedures    NQA- I -1994 uses "work have been completed in accordance with the requirements of              have been completed in accordance with the requirements of          site." This is in line with the applicable codes and standards.                                          applicable codes and standards.                                    standard being applicable to
: b. Systems have been designed and engineered in accordance              (b) Systems have been designed and engineered in accordance        construction and operational with applicable codes, standards and specifications.                    with applicable codes, standards, and specifications.              activities.
: c. Materials have been selected and equipment has been                  (c) Materials have been selected and equipment has been fabricated and assembled in accordance with the design                  fabricated and assembled in accordance with the design specifications and the applicable published codes and standards,        specifications and the applicable published codes and standards, the conformance to which has been demonstrated by the                    the conformance to which has been demonstrated by the responsible organization.                                                responsible organization.
: d. Engineering limitations, as applicable, have been                    (d) Engineering limitations, as applicable, have been incorporated in the procedures and instructions. These                  incorporated in the procedures and instructions. These limitations and requirements shall include, as a minimum,                limitations and requirements shall include, as a minimum, installation, testing, and on-site fabrication processes such as        installation, testing, and on-site fabrication processes such as cleaning, welding, nondestructive examination and parameters            cleaning, welding, nondestructive examination, and parameters such as pressure, flow, speed, load limits (static and dynamic),        such as pressure, flow, speed, load limits (static and dynamic),
travel limits, physical clearances, control and alarm settings,          travel limits, physical clearances, control and alarm settings, and environmental and thermal limits which are included in design            environmental and thermal limits, which are included in design specifications, manufacturers data sheets, instruction manual            specifications, manufacturer's data sheets, instruction manual, and design reports.                                                      and design reports.
: e. To substantiate (b) and (c) above, the following documents            (e) To substantiate (b) and (c) above, the following documents 10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                                Page 8 of 23
 
Supplementary Quali.y Assurance Requirements For                            Quality Assurance .Requirements f6r Installation,                        COMMENTS InstallationlInspection And Testings Of Mechanical                    InWspetion, and Testing of Mechanical Equipment and, Equipment And Systeqms For The Construction Phase Of                                  Systems for*Nuclear Power Plants".
Nuclear Power Plants .... ,NQA-                                                1 1994 Sub.part 2,8..........
ANSIJN45.2.3 1975-                                                                                                      ___________
relating to the specific stage of installation activity for the item    relating to the specific stage of installation activity for the item shall be available at the construction site:                            shall be available at the work site:
(1) The latest applicable approved-for-construction drawings.            (1) the latest applicable approved-for-construction drawings (2) Equipment specifications.                                            (2) equipment specifications (3) Manufacturers installation instructions.                            (3) manufacturer's installation instructions (4) Installation procedures.                                            (4) installation procedures (5) Evidence of compliance by manufacturer with purchase                (5) evidence of compliance by manufacturer with purchase requirements, including quality assurance requirements.                  requirements, including quality assurance requirements (6) Evidence that engineering or design changes are                      (6) evidence that engineering or design changes are documented documented and approved prior to installation,                          and approved prior to installation (7) Records of inspections and tests during onsite receiving,            (7) records of inspections and tests during on-site receiving, storage and handling.                                                    storage, and handling (8) Release of mechanical items for installation.                        (8) release of mechanical items for installation (9) Evidence that nonconformances have been satisfactorily              (9) evidence that nonconformances have been satisfactorily resolved or controlled.                                                  resolved or controlled
: 3. PRE-INSTALLATION VERIFICATION                                        3 PREINSTALLATION VERIFICATION 3.1 General                                                              3.1 General Prior to the actual installation of mechanical items, there are          Prior to the actual installation of mechanical items, there are      Similar requirement.
certain preliminary inspections, checks and similar activities          certain preliminary inspections, checks, and similar activities that shall be completed to verify that the item and the                  that shall be completed to verify that the item and the installation area conform to specified requirements and the              installation area conform to specified requirements, and the necessary resources are available to assure that the quality of the      necessary resources are available to assure that the quality of the mechanical item will be maintained as the installation proceeds.        mechanical item will be maintained as the installation proceeds.
The quality requirements and quality assurance actions that are          The quality requirements and quality assurance actions that are necessary during installation shall be reviewed and planned so          necessary during installation shall be reviewed and planned so that they are understood by responsible individuals,                    that they are understood by responsible individuals.
3.2 Identification                                                      3.2 Identification Checks shall be made to verify that the identity of received            Checks shall be made to verify that the identity of received          Similar requirement.
mechanical materials and equipment has been maintained and is            mechanical materials and equipment has been maintained and is in accordance with the latest approved-for-construction                  in accordance with the latest approved-for-construction drawings, equipment lists, specifications and established                drawings, equipment lists, specifications, and established procedures. If these checks disclose apparent loss of                    procedures. If these checks disclose apparent loss of identification, the identity shall be reaffirmed prior to release for    identification, the identity shall be reaffirmed prior to release for installation.                                                            installation.
Checks shall be made to verify that a control system for                Checks shall be made to verify that a control system for 10/28/2010                                              Installation, Inspection, and Testing of Mechanical Equipment and Systems                              Page 9 of 23
 
.. Sspplementary Quaty Assurnce Requirements F**or                            Quality Assurance Requirements for Installation,                    COMMENTS Installation, Inspection And Testing Of Mechanical                  Inspection, andTesting of Mechanical E'"uip""et                *and Equipment.And Systems For The Constction Phase Of                                    Systems for Nuclear Power Plants Nuclear Power Plants                                                  NQA-I 1994 Subpart 2.8 ANSI N45.2.8 - 1975 maintaining identification of mechanical items throughout              maintaining identification of mechanical items through installation has been established including provisions for control    installation has been established, including provisions for of substitution or exchange of equipment or materials. The            control of substitution or exchange of equipment or materials.
procedures for control of identification shall provide a system of    The procedures for control of identification shall provide a traceability to drawings, specifications or other records when        system of traceability to drawings, specifications, or other identification or markings must be destroyed, hidden or                records when identification or markings must be destroyed, removed from an item.                                                  hidden, or removed from an item.
3.3 Processes and Procedures                                          3.3 Processes and Procedures Consistent with the construction activities schedule, inspections      Consistent with the construction activities schedule, inspections,  Similar requirement.
or checks shall be performed to verify that processes and              or checks shall be performed to verify that processes and procedures are ready when needed for use in the installation of        procedures are ready when needed for use in the installation of mechanical items. These inspections or checks shall include, but      mechanical items. These inspections or checks shall include, but not be limited to the following verifications:                        not be limited to, the following verifications.
: a. Approved procedures, drawings, manuals or other work                (a) Approved procedures, drawings, manuals, or other work instructions are provided to the installer at the construction site. instructions are provided to the installer at the work site.
: b. Special instructions and check lists as required are available      (b) Special instructions and checklists as required are available at the installation area or attached to the item.                      at the installation area or attached to the item.
: c. Approved procedures and instructions for special processes          (c) Approved procedures and instructions for special processes such as coating, welding, heat treating and nondestructive            such as coating, welding, heat treating, and nondestructive examination are available at the site.                                examination are available at the site.
: d. Where applicable, personnel, procedures and instructions            (d) Where applicable, personnel, procedures, and instructions shall have been qualified through the preparation of                  shall have been qualified through the preparation of workmanship standards, samples, or mockups that simulate              workmanship standards, samples, or mockups that simulate actual job conditions.                                                actual job conditions.
: e. Installation preparations have been completed, including such      (e) Installation preparations have been completed, including tasks as removal of packaging, conditioning, cleaning, and            such tasks as removal of packaging, conditioning, cleaning, and preliminary positioning.                                              preliminary positioning.
: f. Jigs, fixtures and equipment for special processes, if required,    (f) Jigs, fixtures, and equipment for special processes, if are available at the site and conform to specified requirements.      required, are available at the site and conform to specified
: g. Equipment for handling and placement of mechanical items is        requirements.
available at the site and is adequate to perform the work in          (g) Equipment for handling and placement of mechanical items accordance with specified requirements.                                is available at the site and is adequate to perform the work in
: h. Warnings and safety notices, appropriate to the activity, are      accordance with specified requirements.
posted.                                                                (h) Warnings and safety notices appropriate to the activity are posted.
10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 10 of 23
 
Su                ulity      uran Rquirements Fo                                li AssranRequrements for installation,                        COMMENTS Installation, Inspection And Testing Of Mechanical                      Inspection, and Testing of 'Mechanical Equipment and' Equipment And Systems For The Construction Phase Of                                        Systems for Nuclear Power Plants Nuclear Power Plants                                                      NQA-1 1994 Subpart 2.8 ANSI N45.2j8r 1975          ...........                            .....                                                                      ,:
3.4 Physical Condition                                                    3.4 Physical Condition Inspections or checks as appropriate shall be performed to                Inspections or checks, as appropriate, shall be performed to      Similar requirement.
verify that mechanical items at the installation are in accordance        verify that mechanical items at the installation are in accordance with the specified requirements and that quality has been                  with the specified requirements and that quality has been maintained. These inspections or checks shall include, but not            maintained. These inspections or checks shall include, but not be limited to, the following verifications:                                be limited to, the following verifications.
: a. Protective measures and physical integrity during storage              (a) Protective measures and physical integrity during storage have been maintained in conformance with specified                        have been maintained in conformance with specified requirements.                                                              requirements.
: b. Nonconformances have been satisfactorily dispositioned or              (b) Nonconformances have been satisfactorily dispositioned or controlled.                                                                controlled.
: c. Items have been cleaned in accordance with specified                    (c) Items have been cleaned in accordance with specified requirements.                                                              requirements.
3.5 Site Conditions                                                        3.5 Site Conditions Inspections or checks as appropriate shall be performed to                Inspections or checks, as appropriate, shall be performed to      Similar requirement.
verify that conditions of the installation area conform to                verify that conditions of the installation area conform to specified requirements and precautions have been taken to                  specified requirements and precautions have been taken to prevent conditions that will adversely affect the quality of the          prevent conditions that will adversely affect the quality of the item during installation. These inspections or checks shall                items during installation. These inspections or checks shall include, but not be limited to, the following to verify that:              include, but not be limited to, verification of the following.
: a. Protection from adjacent construction activities is being              (a) Protection from adjacent construction activities is being provided including, implementation of appropriate exclusion                provided, including implementation of appropriate exclusion and area cleanness requirements.                                          and area cleanness requirements.
: b. Protection from inclement weather and other ambient                    (b) Protection from inclement weather and other ambient conditions adverse to quality is being provided,                          conditions adverse to quality is being provided.
: c. Materials that may be deleterious to the mechanical items              (c) Materials that may be deleterious to the mechanical items being installed, are controlled,                                          being installed are controlled.
: d. Installation of the mechanical item will not adversely affect          (d) Installation of the mechanical item will not adversely affect the subsequent installation of materials and equipment and that            the subsequent installation of materials and equipment, and repair or rework on any nonconforming items can be performed              repair or rework on any nonconforming items can be performed satisfactorily.                                                            satisfactorily.
: e. Nonconformances for adjacent items have been dispositioned              (e) Nonconformances for adjacent items have been or controlled.                                                            dispositioned or controlled.
: f. Adequate permanent or approved temporary supports and                  (f) Adequate permanent or approved temporary supports and mountings have been installed that will properly interface with            mountings have been installed that will properly interface with 10/28/2010                                                Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page I11 of 23
 
Supplementary Quaty Assurance-Requirements For.                          Quality Assurance Requirements for Installation,                    COMMKENTS Installation, inspection And Testing Of Mechan'ica)                  Inspection,"and Testing of Mechanical Equipment and' Equipme.nt And Systems For The Construction Phas Of                                Systems ,for Nuclear Power Plants Nuclear Power.Plants                                                'NQA-. 1994 Subpart 2.8 ANSI N45.2.8 - 1975 the mechanical item.                                                  the mechanical item.
: g. Mating parts such as couplings and flanges are properly            (g) Mating parts such as couplings and flanges are properly positioned and conditioned.                                            positioned and conditioned.
: h. Servicing or maintenance activity related to installation has      (h) Servicing or maintenance activity related to installation has been performed.                                                        been performed.
: 4. CONTROL DURING INSTALLATION PROCESS                                4 CONTROL DURING INSTALLATION PROCESS 4.1 General                                                            4.1 General Checking, inspection, examination or testing activities shall be      Checking, inspection, and examination of testing activities shall  Similar requirement.
performed during the installation of mechanical items to assure        be performed during the installation of mechanical items to that the required quality is being obtained in accordance with        assure that the required quality is being obtained in accordance prescribed procedures. These activities shall be performed in a        with prescribed procedures. These activities shall be performed systematic manner to assure surveillance throughout the                in a systematic manner to assure surveillance throughout the installation process. A procedure shall be provided for the            installation process. A procedure shall be provided for the coordination and sequencing of these activities at established        coordination and sequencing of these activities at established inspection points in successive stages of installation. A method      inspection points in successive stages of installation. A method shall be implemented to assure that engineering and design            shall be implemented to assure that engineering and design changes are documented and controlled during installation.            changes during installation are documented and controlled.
4.2 Process and Procedure Control                                      4.2 Process and Procedures Control Checks shall be made to verify that a system of controls has          Checks shall be made to verify that a system of controls has        Similar requirement.
been established and is being maintained at the construction site      been established and is being maintained at the construction site to assure the following:                                              to assure the following.
: a. The applicable revision of approved procedures, drawings            (a) The applicable revision of approved procedures, drawings, and instructions are being followed,                                  and instructions is being followed.
: b. Qualified and approved processes, materials, tools and other        (b) Qualified and approved processes, materials, tools, and other equipment are being, used by qualified personnel.                      equipment are being used by qualified personnel.
: c. The status of installation, inspections, examinations or tests is  (c) The status of installation, inspections, examinations, or tests clearly indicated or identified in inspection records.                is clearly indicated or identified in inspection reports.
: d. The installation, inspection and testing sequence is being          (d) The installation, inspection, and testing sequences are being maintained,                                                            maintained.
: e. Identification, appropriate segregation, and disposition of        (e) Identification, appropriate segregation, and disposition of nonconforming items are being controlled.                              nonconforming items are being maintained.
: f. "As-built" information is being processed.                          (f) As-built information is being processed.
: g. Inspection and test reports are current, accurate and complete.    (g) Inspection and test reports are current, accurate, and complete.
4.3 Examination 10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 12 of 23
 
Supplementary Quality Assurance Requirements For                      ..Quality.Assurance Requiremeen.ts for Installatiom Installation, Inspection And Testing Of Mechanical                  Inspection, and Testing of Mechanical Equipment Equipment And Systems For The Construction* Ihase Of                                Systems for Nuclear Power Plants        ,
Nuclear Power Plants                                                  NQA-1 1994 Subpart 2.8 91ANSI N45.1.8 - 1975-,
Nondestructive examinations, when required, shall be                                                                                    NQA-I doesn't contain this performed to approved applicable procedures. Examples of                                                                                wording, but NDE is these examinations are liquid penetrant, magnetic particle,                                                                            programmatically controlled ultrasonic, eddy current and radiography.                                                                                              under Basic Requirements 10 and 11 and Supplements 10S-1 and I IS-1.
4.4 Inspection                                                        4.3 Inspection Inspections of the work areas and the work in progress shall be      Inspections of the work areas and the work in progress shall be  Similar requirement.
performed to verify that mechanical items are being located,          performed to verify that mechanical items are being located, installed, assembled or connected in compliance with the latest      installed, assembled, or connected in compliance with the latest approved-for-construction drawings, manufacturers instructions,      approved-for-construction drawings, manufacturer's codes, installation instructions and procedures. Inspections          instructions, and procedures. Inspections performed shall performed shall include as appropriate, but not be limited to the      include as appropriate, but not be limited to, the following:
following:                                                            (a) identification
: a. Identification.                                                    (b) location and orientation of components
: b. Location and orientation of components.                            (c) leveling and alignment
: c. Leveling and alignment.                                            (d) clearances and tolerances d..Clearances and tolerances.                                          (e) tightness of connections and fastenings
: e. Tightness of connections and fastenings.                            (f) fluid levels and pressures
: f. Fluid levels and pressures.                                        (g) absence of leakage
: g. Absence of leakage.                                                (h) physical integrity
: h. Physical integrity.                                                (i) cleanness
: i. Cleanness.                                                          (j) welding operations, including materials and process controls,
: j. Welding operations including materials and process controls,        adequate purging, and the removal of purge dams on completion adequate purging, and the removal of purge dams on                    (k) adequacy of protective measures to assure that the item will completion.                                                            not be damaged during installation
: k. Adequacy of protective measures to assure that the item will        (1)adequacy of housekeeping, barriers, and protective not be damaged during installation,                                    equipment to assure that items will not be damaged or
: 1. Adequacy of housekeeping, barriers and protective equipment        contaminated as a result of adjacent construction activities to assure that items will not be damaged or contaminated as a result of adjacent construction activities 4.5 Installation Checks                                                4.4 Installation Checks Checks shall be performed to verify that mechanical items have        Checks shall be performed to verify that mechanical items have    Similar requirement.
been correctly installed and will function properly so that the        been correctly installed and will function properly so that the initial starting of items and preoperational testing can proceed      initial starting of items and preoperational testing can proceed 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                        Page 13 of 23
 
Supplementary Quality Assurance Requirements For,.                        Quality Assurance Requirements r "Installation,                    COMMENTS Installation, Inspection And Testing Of Mechanical,                    Inspeclion, an..d Testing of Mechanical Equipmentand Equipment An~d Systems For The Construction Phase Of                                Systems for Nuclear Power, Plants Nuclear*Power Plants                                                  NQA- 1 1994 Subpart 2.8 ANSI.N45.2.8 - 1975 with a minimum amount of problems and delays. If construction          with a minimum amount of problems and delays. If construction or associated activity affects the results of these checks, the        or associated activity affects the results of these checks, the checks shall be repeated if necessary to assure that the quality        checks shall be repeated, if necessary, to assure that the quality has not been adversely affected.                                        has not been adversely affected.
These activities shall include as appropriate, but not be limited      These activities shall include as appropriate, but not be limited to the following:                                                      to, the following.
: a. Checkout procedures are prepared and approved to verify              (a) Checkout procedures are prepared and approved to verify correctness of installation and ability to function.                    correctness of installation and ability to function.
: b. Proper greasing or lubrication has been completed.                  (b) Proper greasing or lubrication has been completed.
: c. Lubricating and cooling water systems are in service.                (c) Lubricating and cooling water systems are in service.
: d. Protection strainers are installed where necessary.                  (d) Protection strainers are installed where necessary.
: e. Rotation of prime movers is correct.                                (e) Rotation of prime movers is correct.
: f. Electrical circuits, controls and relay settings are correct.        (f) Electrical circuits, controls, and relay settings are correct.
: g. Phasing of electrical busses is correct.                            (g) Phasing of electrical buses is correct.
: h. Instrumentation is calibrated and in service as required.            (h) Instrumentation is calibrated and in service as required.
: i. Item is correctly valved and isolated.                              (i) Item is correctly valved and isolated.
: j. Casings, reservoirs, etc. are primed, vented and filled.            (j) Casings, reservoirs, etc., are primed, vented, and filled.
: k. Proper communications are established for control.                  (k) Proper communications are established for control.
: 1. Tags are issued, where appropriate, for isolation and control.      (I) Tags are issued, where appropriate, for isolation and control.
: m. Piping system alignment is correct.                                  (m) Piping system alignment is correct.
: n. Pipe hanger placement is correct and hangers will function          (n) Pipe hanger placement is correct and hangers will function properly.                                                              properly.
: o. Seismic anchors and restraints are properly installed.              (o) Seismic anchors and restraints are properly in stalled.
: p. Valve glands and packing are installed.                              (p) Valve glands and packing are installed.
: q. Pneumatic lines have been blown.                                    (q) Pneumatic lines have been blown.
: r. Valve stroking, actuation and settings are proper.                  (r) Valve stroking, actuation, and settings are proper.
: s. Pump seals and packing are properly installed.                      (s) Pump seals and packing are properly installed.
: t. Limit switches, interlocks and stops are properly adjusted and      (t) Limit switches, interlocks, and stops are properly adjusted set.                                                                    and set.
4.5.1 Cleaning.                                                        4.4.1 Cleaning.
Installed systems and components shall be cleaned, flushed and          Installed systems and components shall be cleaned, flushed, and    Similar requirement.
conditioned according to the requirements of ANSI N45.2. 1.            conditioned according to applicable requirements. Special          As noted previously, NQA-Special attention shall be given to the following requirements:        attention shall be given to the following requirements.            1 addresses cleaning and
: a. Chemical Conditioning. Procedures shall be prepared                  (a) Chemical Conditioning. Procedures shall be prepared            flushing of components and including the scope, acceptance criteria, sequence, temperatures,      including the scope, acceptance criteria, sequence, temperatures,  systems in Subpart 2.1.
10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 14 of 23
 
Supplementary-Quality Assurance Requirements For                          Quality AssuranceRequirements for Installation,                    COMMENTS Installation, Inspection And Testing Of Mechanical                    Inspection, and Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                    Systems for Nuclear Power Plan"ts NuclearNP.oower AN    P1*97 SI -N15....5 1975**                                            , N A1It*: 4.SS b
* 18. *.* ' .... * .' * *
* i.:"              *, ,/ " '". f<*
soak periods and neutralizing solutions to be used. Checks shall        soak periods, and neutralizing solutions to be used. Checks shall be made to verify that the proper chemicals at the designated          be made to verify that the proper chemicals at the designated strength and temperature are being used in the conditioning              strength and temperature are being used in the conditioning operations. Other operations shall be performed as specified in          operations. Other operations shall be performed as specified in Paragraph 4.5.1 .c.                                                      (c) below.
: b. Flushing. Procedures shall be prepared including routes,              (b) Flushing. Procedures shall be prepared including routes, boundaries, velocities and acceptance criteria, restoration, and        boundaries, velocities and acceptance criteria, restoration, and lay-up for high integrity systems where appropriate. Checks              lay-up for high integrity systems, where appropriate. Checks shall be made to verify that mechanical items are being flushed          shall be made to verify that mechanical items are being flushed in accordance with specified requirements so that contaminants          in accordance with specified requirements so that contaminants or flow velocities will not adversely affect subsequent                or flow velocities will not adversely affect subsequent operations. Other operations shall be performed as specified in        operations. Other operations shall be performed as specified in Paragraph 4.5.1.c.                                                      (c) below.
: c. Process Controls. Checks shall be performed to verify that            (c) Process Controls. Checks shall be performed to verify that controls are functioning for the following:                            controls are functioning for the following:
(1) Removal and installation of parts or components such as                (1) removal and installation of parts or components such as metering devices, orifice plates and valve internals that are              metering devices, orifice plates, and valve internals that are removed from the system to facilitate flushing.                            removed from the system to facilitate flushing; (2) Installation and removal of temporary strainers, blind                (2) installation and removal of temporary strainers, blind flanges, and piping.                                                      flanges, and piping; (3) Isolation of sensitive instrumentation.                                (3) isolation of sensitive instrumentation; (4) Water and chemical quality.                                            (4) water and chemical quality; (5) Acceptance data, specimens, or progressive samples if                  (5) acceptance data, specimens, or progressive samples, if required.                                                                  required.
Where appropriate for disassembly and reassembly of                    Where appropriate for disassembly and reassembly of components, procedures or instructions shall be prepared or            components, procedures or instructions shall be prepared or manufacturers technical manuals shall be used to assure                manufacturer's technical manuals shall be used to assure adherence to match marks, protection of seats and proper                adherence to match marks, protection of seats, and proper reassembly and to preclude damage to the component.                    reassembly and to preclude damage to the component.
4.5.2 Pressure Testine.                                                4.4.2 Pressure Testing.
Checks shall be made to verify that mechanical items are being          Checks shall be made to verify that mechanical items are being      Similar requirement. NQA-pressure tested in accordance with specified requirements to            pressure tested in accordance with specified requirements to      1 adds requirement for assure that the strength and integrity of the installed systems or      assure that the strength and integrity of the installed systems or  verifying evidence of portions thereof conform to specified requirements. The purpose        portions thereof conform to specified requirements. The purpose    calibration of test gages.
of the test, scope, test boundary, duration for inspection,            of the test, scope, test boundary, duration for inspection,        I 10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                            Page 15 of 23
 
Supplementary Qualit Assurance Req            ementsFor                    Quality Assurance Requirements for*Installti on,                    COMMENTS Installation, Inspection And Testing Of Mechanical                    Inspection, and Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                  Systems for Nuclear Power Plants.            ..          -.
Nuclear Power Plants                          ..      .      .    .NQA-1    19    uprt2.8:
ANSI N45.2.8 -_1975                                                                                                  ___________
acceptance criteria, restoration, and lay-up shall be clearly            acceptance criteria, restoration, and lay-up shall be clearly established and documented. Checks shall include, but not be            established and documented. Checks shall include, but not be limited to, the following:                                              limited to, the following.
: a. Appropriate pressures, temperatures, water chemistry, and            (a) Appropriate pressures, temperatures, water chemistry, and pressure test cycles are established,                                    pressure test cycles are established.
: b. Sufficient time at test pressure is specified to determine            (b) Sufficient time at test pressure is specified to determine acceptance.                                                              acceptance.
: c. Provisions are available to protect and isolate instrumentation      (c) Provisions are available to protect and isolate during hydrostatic testing.                                              instrumentation during hydrostatic testing.
: d. Items external to test boundary are protected to prevent              (d) Items external to test boundary are protected to prevent inadvertent over-pressurization,                                        inadvertent over-pressurization.
: e. Relief devices are controlled to prevent system over-                (e) Relief devices are controlled to prevent system over-pressurization.                                                          pressurization.
: f. Gagging and ungagging of relief valves.                              (f) Gagging and ungagging of relief valves.
: g. Piping and equipment supports have hydrostatic pins installed        (g) Piping and equipment supports have hydrostatic pins where applicable for testing and removed upon completion of              installed where applicable for testing and are to be removed testing.                                                                upon completion of testing.
(h) Evidence of calibration of test gages 4.6 Care of Items                                                        4.5 Care of Items Items on which inspection and testing activities are being              Items on which inspection and testing activities are being        Similar requirement.
performed shall be protected from personnel traffic, weather,            performed shall be protected from personnel traffic, weather, and adjacent construction activities such as sandblasting, acid          and adjacent construction activities such as sandblasting, acid cleaning, welding, jack hammering, chipping, burning and                cleaning, welding, jack hammering, chipping, burning, and stress relieving that would adversely affect the quality of the          stress relieving, which would adversely affect the quality of the item or test results. Such protection shall be provided through          item or test results. Such protection shall be provided through good cleanliness and housekeeping practices, temporary                  good cleanliness and housekeeping practices, temporary packaging, erection of barriers, protective covers, and                  packaging, erection of barriers, protective covers, and walkways, as required in accordance with Subsection 2.6.                walkways, as required.
Temporary use of equipment or facilities to which this standard          Temporary use of equipment or facilities to which this Part applies that are to become part of the completed project may be          applies that are to become part of the completed project may be desirable. Authorization for such usage shall be as provided for        desirable. Authorization for such usage shall be as provided for in the contract or by written approval from the responsible              in the contract or by written approval from the responsible organization. Such temporary use shall not subject the                  organization. Such temporary use shall not subject the equipment or systems to conditions for which they were not              equipment or systems to conditions for which they were not designed.                                                                designed.
10/28/2010                                            Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 16 of 23
 
    ..Supplementary Qua~yAssurance Requirements For:..                      'Quality    Assurance Requirements for Intalation,                    COMMENS Installation,., Inspection And Testing Of Mechanical                  Inspection, a'ndTeti~ng of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                    Systems fourTNi~lear Power Plants Nuclear Power Plants                                                  NQA-1 1994 Suibpart 2.8 ANSI N45.2.8 - 1975 The temporary use authorization shall include:                          The temporary use authorization shall include:
(1) conditions of use or operation;                                      (a) conditions of use or operation; (2) maintenance requirements; and                                        (b) maintenance requirements; and (3) inspections and tests as required to maintain operability and        (c) inspections and tests as required to maintain operability and quality during period of temporary use of the item.                      quality during the period of temporary use of item.
When temporary use is completed, conditions of temporary use            When temporary use is completed, conditions of temporary use shall be evaluated to verify that the permanent plant equipment          shall be evaluated to verify that the permanent plant equipment continues to satisfy the specified requirements.                        continues to satisfy the most specified requirements.
: 5. INSTALLED SYSTEMS INSPECTION AND TESTS                                5 INSTALLED SYSTEMS INSPECTION AND TESTS 5.1 General                                                              5.1 General Following the installation of mechanical items, the checking,            Following the installation of mechanical items, the checking        Similar requirement.
inspection, and testing activities shall be performed to verify,        inspection and testing activities shall be performed to verify that that the completed systems are in conformance with specified            the completed systems are in conformance with specified requirements. This is a final verification that the requirements        requirements. This is a final verification that the requirements defined by licensing commitments, drawings, specifications and          defined by licensing commitments, drawings, specifications, other contract documents are reflected in the completed                  and other contract documents are reflected in the completed installation. It is also a time to verify that field modifications      installation. It is also a time to verify that field modifications and other changes made and controlled during installation                and other changes made and controlled during installation activities have been incorporated in the "as-built" documents.          activities have been incorporated in the as-built documents.
Controls shall be provided for the identification, documentation,        Controls shall be provided for the identification, documentation, and resolution of nonconformances disclosed by inspections or            and resolution of nonconformances disclosed by inspections or tests. Tests shall be conducted on completed plant systems. Test        tests.
procedures shall identify prerequisites for system testing              Tests shall be conducted on completed plant systems. Test including required completed construction activities. The test          procedures shall identify prerequisites for system testing, procedure shall identify and describe any temporary or                  including required completed construction activities. The test simulated condition or equipment. If not previously planned, a          procedures shall identify and describe any temporary or documented notice shall be prepared and issued with approval            simulated condition or.equipment. If not previously planned, a of the responsible organization stating the substitutions that          documented notice shall be prepared and issued with approval existed for the test. Written verification shall also be provided        of the responsible organization stating the substitutions that that temporary installations have been satisfactorily replaced by        existed for the test. Written verification shall also be provided the permanent installations.                                            that temporary installations have been satisfactorily replaced by Checks and inspections shall be performed to verify the                  permanent installations.
operational readiness and completeness of components and                Checks and inspections shall be performed to verify the systems. These systems or partial systems shall be identified,          operational readiness and completeness of components and tagged and released for operational testing. These checks and            systems. These systems or partial systems shall be identified, 10/28/2010                                              Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 17 of 23
 
Supplementary Qu ality Assurance Requirements For                  ... Quality Assurance Requirementsfor In iallation, Installation, Inspection And Testing Of Mechanical                    Inspection, And Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                Systems for Nuclear Power Plants
                  ..... Nuclear Power Plants                                                NQA-I 19~94 Subpart 2.8
                        .,ANSI N45,2.8 - 1975 inspections shall be performed to verify the following as a            tagged, and released for operational testing. These checks and minimum:                                                              inspections shall be performed to verify the following, as a
: a. Equipment and materials have not sustained external physical        minimum.
damage.                                                                (a) Equipment and materials have not sustained external
: b. The installation has been made in accordance with specified        physical damage.
requirements.                                                          (b) The installation has been made in accordance with specified
: c. All nonconforming items have been satisfactorily                    requirements.
dispositioned.                                                        (c) All nonconforming items have been satisfactorily
: d. Internal and external restrictions and obstructions to flow and    dispositioned.
full travel have been removed.                                        (d) Internal and external restrictions and obstructions to flow
: e. Supports and restraints are properly installed.                    and full travel have been removed.
: f. Interfacing connections with adjacent systems are compatible.      (e) Supports and restraints are properly installed.
: g. Original material and component identification has been              (f) Interfacing connections with adjacent systems are preserved with provisions for traceability throughout the              compatible.
installed systems.                                                    (g) Original materials and component identification have been
: h. Safety features such as interlocks, cable separation, guards,      preserved with provisions for traceability throughout the warning devices, and lockouts have been installed, are being            installed systems.
used and comply with applicable codes and regulations.                (h) Safety features such as interlocks, cable separations, guards,
: i. Temporary, connections such as jumpers and bypass lines and        warning devices, and lockouts have been installed, are being temporary trip points of control equipment are identified and,        used, and comply with applicable codes and regulations.
documented so that their final condition can be verified.              (i) Temporary connections, such as jumpers and bypass lines,
: j. System water chemistry is appropriate for operational testing.      and temporary trip points of control equipment are identified
: k. External surface chemistry requirements have been                  and documented so that their final condition can be verified.
maintained.                                                            (i) System water chemistry is appropriate for operational testing.
: 1. Permits and authorizations have been obtained.                    (k) External surface chemistry requirements have been maintained.
(I) Permits and authorizations have been obtained.
5.2 Preoperational Testing                                            5.2 Preoperational Testing This testing involves the operation of all items in a system,          This testing involves the operation of all items in a system(s) or  Similar requirement.
partial systems or systems to assure that operation is in              partial system(s) to assure that operation is in accordance with accordance with the design criteria and functional requirements.      the design criteria and functional requirements.
The testing shall include, but not be limited to the following:        The testing shall include, but not be limited to, the following:
: a. Systems integrity.                                                  (a) systems integrity;
: b. In-line instrument installation is consistent with specified        (b) in-line instrument installation is consistent with specified flow directions.                                                      flow directions; 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 18 of 23
 
Supplementary Quality ssurance Requirements For                        QuafityjAssurance Requirements for nstallation,                  COMMENTS7' Installation, Inspection And Testing Of Mechanical                Inspection, an.d Testing of Mechanical Equipm"en*t and EquipmentAnd Systems For The Construction Phase Of                                Systems for Nuclear Powr                          "Plants Nuclear Power Plants                                                NQA-1 1994 Subpart 2.8 ANSI N45.2.8 - 1975.
: c. Sensing lines are phased correctly to in-line elements and        (c) sensing lines are phased correctly to in-line elements and sensors.                                                              sensors;
: d. Service requirements for initial operation such as flow            (d) service requirements for initial operation such as flow alignments, limiting flow orificing and relief devices have been      alignments, limiting flow orificing, and relief devices have been performed.                                                            performed;
: e. Operation of controls, valves, dampers, operators, and load        (e) operation of controls, valves, dampers, operators, and load limiting devices,                                                    limiting devices;
: f. Rotating equipment (motors, pumps, blowers) - rotation,            (f) rotating equipment (motors, pumps, blowers),
speed, vibration, noise, and no-load operation.                      rotation, speed, vibration, noise, and no-load operation;
: g. Handling equipment - load tests of cranes, hoists, conveyors,      (g) handling equipment (load tests of cranes, hoists, conveyors, hooks, and handling adapters, and accessories,                        hooks, handling adapters, and accessories);
: h. Containment systems.                                              (h) containment systems;
: i. Air handling systems.                                              (i) air handling systems;
: j. Fuel storage and handling systems.                                () fuel storage and handling systems;
: k. Reactor components handling systems.                              (k) reactor component handling systems;
: 1. Instrument air systems.                                          (1)instrument air systems;
: m. Fluid service systems.                                            (in) fluid service systems;
: n. Waste effluent systems.                                            (n) waste effluent systems;
: o. Auxiliary building systems.                                        (o) auxiliary building systems.
Where mechanical equipment and systems interface with, and            Where mechanical equipment and systems interface with, and        Similar requirement.
their operation must coordinate with, non-mechanical                  their operation must coordinate with, nonmechanical equipment    Additional information on equipment or systems, the test performed shall include verifying      or systems, the test performed shall include verifying the        inspections and tests is the compatibility of interfacing equipment and functions. For        compatibility of interfacing equipment and functions.            addressed in NQA- 1, Basic additional information on inspections, tests and procedures, see                                                                        Requirements 10 and 11, Section 6 of ANSI N18.7.                                                                                                                and Supplements lOS-l and 11S-1.
5.3 Cold Functional Tests                                            5.3 Cold Functional Tests These tests follow preoperational testing of individual systems      These tests follow preoperational testing of individual systems,  Similar requirement.
including reactor coolant systems. This testing shall be              including reactor coolant systems. This testing shall be performed to obtain operational data of equipment with                performed to obtain operational data of equipment and maximum allowable simultaneous operation of interfacing              maximum allowable simultaneous operation of interfacing systems and equipment and final verification of functional            systems and equipment, the final verification of functional performance of these systems..                                        performance of these systems.
5.3.1 Reactor Coolant System Hydrostatic Tests.                      5.3.1 Reactor Coolant System Hydrostatic Tests.
As applicable to the reactor system type, hydrostatic tests to        As applicable to reactor system type, hydrostatic tests to verify Similar requirement.
10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                        Page 19 of 23
 
Supplementary Quality Assurance Requirements For                        Quality Assurance Requirements for Installation,                    COM E      S Installation, Inspection And Testing Of Mechanical                  Inspection, and.Testing of Mechanical Equipment and Equipment And Systems For The Construction Phase Of                                Systems for Nuclear Power Plants
                . Nuclear Power Plants                                                  NQA-1 1994 Subpart.2.8 S ANSI N45.2.8 - 1975                                                                                                ___________
verify conformance to specified requirements when performed            conformance to specified requirements, when performed on the on the reactor coolant system, shall include all or parts of          reactor coolant system, shall include all or parts of connected connected systems which cannot be isolated from the test              systems which cannot be isolated from the test pressure. The pressure. The applicable test requirements are contained in            applicable test requirements are contained in Section Ill of the Section III of the Code.                                              ASME Boiler and Pressure Vessel Code.
5.3.2 Functional and Flow Testing.                                    5.3.2 Functional and Flow Testing.
The required individual systems shall be tested to demonstrate        The required individual systems shall be tested to demonstrate    Similar requirement.
cold functional operability of individual components,                  cold functional operability of individual components, subsystems and systems, and to demonstrate compatibility with          subsystems, and systems, and to demonstrate compatibility with other systems. These tests, where appropriate, shall demonstrate      other systems. These tests, where appropriate, shall demonstrate the following:                                                        the following:
: a. System pressure drop.                                              (a) system pressure drop
: b. Flow rate.                                                          (b) flow rate
: c. Controls and throttling device settings.                            (c) controls and throttling device settings
: d. Function of interlocks, alarms and automatic features.              (d) function of interlocks, alarms, and automatic features
: e. Instrument calibration.                                            (e) instrument calibration
: f. Setting of meter biases.                                            (f) setting of meter biases
: g. Systems stability.                                                  (g) system stability
: h. Adequacy of pipe and equipment support settings.                    (h) adequacy of pipe and equipment support settings I. Heat runs on rotating equipment.                                    (i) heat runs on rotating equipment
: j. Adequacy of ventilation, lubrication and cooling systems            (j) adequacy of ventilation, lubrication, and cooling systems under sustained operating conditions.                                  under sustained operating conditions
: k. Ability to meet water chemistry requirements                        (k) ability to meet water chemistry requirements 5.4 Hot Functional Tests                                              5.4 Hot Functional Tests These tests are not applicable to BWR and HTGR nuclear plants          These tests are not applicable to BWR and HTGR nuclear plants    Similar requirement.
because these plants use nuclear heat to produce the system            because these plants use nuclear heat to produce the system temperatures. Hot functional tests for PWR plants follow cold          temperatures. Hot functional tests for PWR plants follow cold functional tests and simulate plant operating conditions at            function tests and simulate plant operating conditions at elevated temperatures and pressures. All auxiliary and support        elevated temperatures and pressures. All auxiliary and support systems exclusive of those required for pre-criticality testing        systems exclusive of those required for precriticality testing must be available for these tests. If any of these systems are not    must be available for these tests. If any of these systems is not available, the responsible organization shall specifically            available, the responsible organization shall specifically authorize exclusion of these systems or subsystems from testing        authorize exclusion of these systems from testing and document and document those exceptions.                                        those exceptions.
These systems shall include the following as a minimum:                These systems shall include the following as a minimum:
10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                        Page 20 of 23
 
Supplementary:Qualit        ssurance Requirements For                  QualityASsurance      Requirements for
                                                                                            .nstallation,                                          COM  ENTS Insta..at"oneInpectia          Testing Of Mechac al                Insp~ection and Testing of Mechanical.EquipmentutAn.dt and Equipment And Systems For The Construction Phase Of                                Systems for Nuclear Power Plants Nuclear Power Plhnts                                                  NQA-i 1994 Subpart 2.. 8 ANSI N45.2 '8 - 1975                                                                                              ___________
: a. System pressure drop.                                              (a) system pressure drop
: b. Flow rate.                                                          (b) flow rate
: c. Controls and throttling device settings.                            (c) controls and throttling device settings
: d. Function of interlocks, alarms and automatic features.              (d) function of interlocks, alarms, and automatic features
: e. Instrument calibration.                                            (e) instrument calibration
: f. Setting of meter biases.                                            (f) setting of meter biases
: g. Systems stability.                                                  (g) system stability
: h. Adequacy of pipe and equipment support settings.                    (h) adequacy of pipe and equipment support settings I. Heat runs on rotating equipment.                                    (i) heat runs on rotating equipment
: j. Verification of heat exchanger performance.                        (j) verification of heat exchanger performance
: k. Verification of boron control system performance.                  (k) verification of boron control system performance
: 1. Thermal insulation effectiveness.                                  (1)thermal insulation effectiveness
: m. Set points of temperature, pressure and level devices.              (in) set points of temperature, pressure, and level devices
: n. System heatup tests.                                                (n) system heatup tests
: o. System cooldown tests.                                              (o) system cooldown tests
: p. Hot flow tests.                                                    (p) hot flow tests
: q. Setting protective devices.                                        (q) setting protective devices
: r. Hot clearances.                                                    (r) hot clearances
: s. Vibration measurements of major equipment and piping, as            (s) vibration measurements of major equipment and piping, as applicable,                                                            applicable
: 6. DATA ANALYSIS AND EVALUATION                                        6 DATA ANALYSIS AND EVALUATION Procedures shall be established for processing inspection and          Procedures shall be established for processing inspection and    Similar requirement.
test data and their analysis, evaluation, and final acceptance.        test data and their analysis, evaluation, and final acceptance.
These procedures shall identify individuals or organizations          These procedures shall identify individuals or organizations responsible for the acquisition and reduction of inspection and        responsible for the acquisitions and reduction of inspection and test data and evaluation against acceptance criteria, operating        test data, and evaluation against acceptance criteria, operating limits, and performance standards. The data processing                limits, and performance standards. The data processing procedure should provide for preliminary evaluation to                procedure shall provide for preliminary evaluation to determine determine the validity of the inspection and test results, and the    the validity of the inspection and test results and the appropriateness of continuing the inspection or test. The data        appropriateness of continuing the inspection or test. The data shall be analyzed and evaluated to verify completeness of              shall be analyzed and evaluated to verify completeness of results, achievement of inspection and test objectives, and            results, achievement of inspection and test objectives, and operational proficiency of equipment and systems; to identify          operational proficiency of equipment and systems; to identify additional inspection or test requirements or both; and to            additional inspection or test requirements or both; and to identify necessary changes to the installation inspection or test      identify necessary changes to the installation inspection or test 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                        Page 21 of 23
 
Supplementary Quali4y Assurance. Requirements For                        Quality    S'surance Requirem~ents for Install i Installation, Inspection And Testing Of Mechanical                  Inspection, and Testing of Mechanical E-quipnii Equipment And Systems For The Construction Phase Of                                Systems for Nuclear Power Plants.
Nuclear Power Plants                                                NQA-1 1994 Subpart 2.8-ANSI N45.2..8  - 1975 procedures. Inspection and test results supported by the              procedures. Inspection and test results supported by the inspection and test data, together with a report of data analysis    inspection and test data, together with a report of data analysis and evaluation, shall be provided as specified in Section 7.          and evaluation, shall be provided as specified in Section 7.
: 7. RECORDS                                                            7 RECORDS Record copies of completed procedures; reports; required              Record copies of procedures, reports, required qualification      Similar requirement. NQA-qualification records, test equipment calibration records; test      records, test equipment calibration records, test deviation or    1 establishes requirements deviation or exception records; and inspection, examination and      exception records, and inspection, examination, and check        for collection, storage, and check records shall be prepared. These shall be placed with          records shall be prepared. These records shall be retained with  maintenance of records in other project records as required by code, standard, specification    other project records as required by code, standard,              Part I, Basic Requirement or project procedures. Collection, storage and maintenance of        specification, or project procedures.                            17 and Supplement 17S-1.
quality assurance records shall be in accordance with ANSI N45.2.9.
: 8. REVISION OF AMERICAN NATIONAL STANDARDS                                                                                              See the comment associated REFERRED TO IN THIS DOCUMENT                                                                                                            with N45.2.8 &sect; 1.5 When the following, standards referred to in this document are                                                                          regarding referenced superseded by a revision approved by the American National                                                                              standards. The QAPD Standards Institute, the revision is not mandatory until it has                                                                        addresses the standards for been incorporated as a part of this standard. Revisions of the                                                                          the program.
referenced standards, and revisions to this standard issued after the date of a specific contract invoking this standard may be used by mutual consent of the purchaser and the supplier.
N 18.7-1972 Administrative Controls for Nuclear Power Plants N45.2-1971 Quality Assurance Program Requirements for Nuclear Power Plants N45.2.1-1973 Cleaning of Fluid Systems and Associated Components During the Construction Phase of Nuclear Power Plants N45.2.2-1972 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants (During the Construction Phase)
N45.2.3-1973 Housekeeping During the Construction Phase of Nuclear Power Plants N45.2.6-1973 Qualifications of Inspection, Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants 10/28/2010                                          Installation, Inspection, and Testing of Mechanical Equipment and Systems                          Page 22 of 23
 
    , SupplementaryQuality Assurance R~jirements For .                '"Quality Assurance Requirements forInstalation,* f COM E    S Installation, Inspection Andl Testing Of Mechanical              Inpcin andTesting of MechanicalEquipmnent and Equipment And Systems For TheConstruction Phase Of                    .      Systems for Nuclear -oe*er Plants Nuclear Power Plants                                            NA4 194Subpart 2.8~
AiNSI N45.2.8 -419 75k N45.2.9-1974 Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants N45.2.10-1973 Quality Assurance Terms and Definitions 10/28/2010                                      Installation, Inspection, and Testing of Mechanical Equipment and Systems    Page 23 of 23
 
ANSI N45.2.2-1972, Section 7. Handling                Quality Assurance Requirements f              tig, Rii.'.gging, and        C.OMME.NTS Transporting Items for Nuclear Power Plants
                                                                        .            .. NQA-, 1994 Subpart 2.15 Note: Some of this information was previously addressed in ANSI N45.2.2-1972 and endorsed by NRC Regulatory Guide 1.38-Rev. 2. Applicable sections are shown below.
1 GENERAL Subpart 2.15 provides requirements for the design, manufacture, acceptance, testing, and use of hoisting, rigging, and transporting equipment to maintain the quality of designated nuclear power plant items which require special handling. It supplements the requirements of Part I and shall be used in conjunction with applicable Basic and Supplementary Sections of Part I when and to the extent specified by the organization invoking Subpart 2.15.
1.4 Definitions                                                    1.1 Definitions The following definitions are provided to assure a uniform        The following definitions are provided to assure a uniform          NQA- 1 Subpart 2.15 understanding of select terms as they are used in this standard. understanding of unique terms as they are used in Subpart 2.15.      includes additional definitions above what was in N45.2.2.
accepted industry standard - a standard established by a group      New definition not representing individual members from various facets of an            presented in N45.2.2.
industry who normally are those engaged in manufacturing.
This standard is accepted by the responsible organization.
Examples are:
AGMA - AmericanGear Manufacturers Association AISC - American Institute of Steel Construction AISE - Association of Iron and Steel Engineers consensus standard - a standard established by a group              New definition not representing a cross section of a particular industry or trade, or  presented in N45.2.2.
a part thereof. A cross section includes those who purchase or use a product of the industry or trade, as well as those who produce these products.
Dynamic Load Test - A test to demonstrate the ability of          dynamicload test - a test wherein designated loads are hoisted,      Similar definition hoisting equipment to safely handle its rated load by exercising  lowered, rotated, or transported through motions and the equipment through vertical and horizontal movement along      accelerations required to simulate handling of the intended item its lines of travel, using a load of specified weight.
equipment - manufactured assemblies which are used for the          New definition not handling of items                                                    presented in N45.2.2.
10/28/2010                                                      Hoisting, Rigging, and Transporting Items                                              Page I of 21
 
ANSI N45.2.2-1972, Section 7. Handling                  Quality Assurance Requirements for Hoisting, Rigging, and                COMME Transporting Items for Nuclear Power 'Plants
                      .......___ "_"_"___""  ___: ____*______        :NQA-711994                        Subpart 2.15 ...
failure stress - that stress at which failure is imminent due to  New definition not direct loads, excessive deflections or vibrations, or permanent    presented in N45.2.2.
deformations that may lead to unsafe conditions handled load - the weight of the item to be lifted plus the weight New definition not of any required rigging, such as lifting beam, slings, hooks, and  presented in N45.2.2.
blocks Handling- The act of physically moving items by hand or by          handling - hoisting, rigging, or transporting of items for nuclear Similar definition intent, mechanical machinery, not including transport modes.                power plants                                                      but NQA-1 Subpart 2.15 includes transport as part of handling.
person-in-charge (PIC) - the person who has overall                New definition not responsibility for handling operations for his organization        presented in N45.2.2.
principal load carrying members - those components of a            New definition not system whose structural integrity must be maintained to ensure    presented in N45.2.2.
a safe operation principal structural welds - those welds which join or affect the  New definition not integrity of principal load carrying members                      presented in N45.2.2.
responsible organization - a company which is in direct charge    New definition not of the equipment and manpower actually engaged in a handling      presented in N45.2.2.
operation system - a combination of components arranged for a handling      New definition not operation                                                          presented in N45.2.2.
7.1 General                                                          2 GENERAL REQUIREMENTS This section contains requirements that are to be fulfilled by the  The requirements of Subpart 2.15 apply to any organization or      Similar requirement, but organizations responsible for handling items. This section          individual participating in work relating to hoisting, rigging,    addresses the added scope covers the requirements for the handling of items in Subsection      and transporting. Hoisting equipment used for handling shall be    of NQA- 1 Subpart 2.15.
2.7 of this standard utilizing appropriate equipment in              certified by the manufacturer. The certification shall indicate    Includes relevant general 10/28/2010                                                        Hoisting, Rigging, and Transporting Items                                            Page 2 of 21
 
          . *..*ANS.IN45.2.2-1972, Section.7. Handlig*    ..... Qualit Assurance lequirements for Hoisting,.Rigging, and                          CM        E    S
                                                                              .Transporting
                                                                                  ........................ Items
                                                                                                              ........ for Nuclear Power Plants
__.__...__.__                  _._.........._NQA-11994 Subpart 2.15.
accordance with methods and procedures specified to minimize      the various parameters for the maximum load to be handled.                    information of N45.2.2, damage and preserve the quality of the item and container.        Measures shall be established and implemented to perform                      subsection 7.2.
handling activities for nuclear power plant items (see Subpart 2.2, para. 2.2) and to perform the inspections, examinations, testing, and documentation to verify conformance to specified requirements. These measures are applicable to items that require special handling because of weight, size, susceptibility to shock damage, high nil-ductility transition temperatures, or any other conditions that warrant special instructions to preserve the quality of items and container. Where this Subpart references the use of consensus standards, these measures shall include the applicable requirements of the ASME/ANSI B30 series, Safety Standards for Cableways, Cranes, Derricks, Hoists, Hooks, Jacks, and Slings, and of ANSI/ASME A 10.5, Safety Requirements for Material Hoists. Subpart 2.15 applies from the time these items are ready for delivery.
Use of permanent plant handling equipment during the construction phase is prohibited unless specifically authorized by the plant owner and conducted in accordance with the plant owner's Quality Assurance Program. If such equipment is to be used during the construction phase, it shall be reviewed to assure that such use conforms to paras. 4.1, 4.2, and 4.3; paras.
5.1, 5.2, and 5.3; paras. 6.1, 6.2, and 6.3, and Section 7, as applicable, in addition to the other requirements of Subpart 2.15.
After construction use and prior to release to the owner, the permanent plant handling equipment shall be restored to its design configuration, and it shall be inspected and tested as specified in a procedure furnished by the owner or his designee.
During subsequent use, the testing, inspection, and maintenance shall be performed as specified by applicable standards.
The requirements of Subpart 2.15 may also be extended to other appropriate parts of nuclear power plants when specified in contract documents, or to modifications involving operating plants. For other requirements, see applicable sections of Subpart 2.2.
7.2 Methods and Procedures                                        2.1 Planning and Procedures 10/28/2010                                                      Hoisting, Rigging, and Transporting Items                                                        Page 3 of 21
 
ANSI N45.21.2-1972, Section 7.. Handlinig              Quality Assurance Requirements for Hoisting, Rigging, and        :      COMME0fNTS Transporting Items for Nuclear Power Plants NQA-1 199 Subpart 2.15.
Detailed handling instructions and procedures shall be prepared    Planning and procedure preparation shall be in accordance with    Similar requirements, for all items that require special handling instructions because  the requirements of the introduction to this Part (Part II).      includes requirement to of weight, size, susceptibility to shock damage, high nil          Procedures and instructions shall contain sufficient detail such  comply with applicable ductility transition temperatures, or any other conditions that    as weights, sling locations, balance points, methods of          regulations.
warrant special instructions. Such instructions or procedures      attachment, maximum hoist line speeds, and other pertinent shall be made available prior to the time the item is to be        features to be considered as necessary for safe handling to handled and shall give weights, sling locations, balance points,  govern handling operations, inspection thereof, and methods of attachment, maximum hoist line speeds and other        documentation in accordance with this Part. Planning shall pertinent features to be considered as necessary for safe          provide for compliance with applicable federal, state, and local handling,                                                          regulations.
Items not specifically covered above shall be handled in accordance with sound material handling practices.
2.2 Classification of Items Handled The requirements for activities covered by Subpart 2.15 are      New requirement in NQA-based on classifying the items into three categories according to 1. Classification not their important physical characteristics. It is recognized that  addressed in N45.2.2. They within the scope of each category there may be a range of        were addressed in N45.2.15.
controls, and that the need for, and extent of detailed handling requirements for an item, is dependent on the importance of the item to safe, reliable operation of the plant and the complexity of the operation. Pertinent manufacturer's requirements shall be considered when classifying the items. Items for which handling activities are covered by Subpart 2.15 shall be classified into one of the three categories below. An item shall not be reclassified to a lower status without approval by the responsible organization which assigned the original category.
2.2.1 Category A.
Items classified in Category A are those that require specially selected equipment and detailed procedures for handling operations because of large size and weight. Examples of items that may be assigned to this category are:
(a) reactor vessels (b) steam generators (c) major components of reactor vessel internals (d) primary system pressurizers (e) spent fuel casks (f ) subassemblies requiring specially selected equipment Page 4 of2l 10/28/201010                                                              Rigging, and Transporting Items Hoisting, Rigging, 10/28/20                                                        Hoisting,          and Transporting Items                                          Page 4 of 21
 
ANSI N45.2.2-1972, Section 7. Handling                          Quality Assurance Requirements for Hoisting, Rigging, an.d                          COMMENTS Transporting Items for Nuclear Power, PlIants N64-    1994 Subpart 2.15                    ...
because of size or weight, such as prestressed concrete reactor vessel liners
____________________________________________2.2.2                  Category B_____________
Items classified in Category B are those that may be handled with conventional handling equipment but which require detailed procedures because of the susceptibility to damage.
Examples of items that may be assigned to this category are:
(a) reactor vessel head (b) primary and intermediate coolant pumps and their internals (c) designated instrument cabinets and control boards (d) control rod drive mechanisms (e) helium circulators (f) fuel handling equipment (g) purification equipment (h) fuel (i) core components (small) 2.2.3 Category C.
10/28/2010*                      : i:,:          i *...: : .:*.*.<                  Rigging, and
                                                                                * , classified
                                                                    ".** Hoisting:.'
                                                                          *Items                  Tra spoin                          .. *,'.*
those that may be* handled C are Item                              ...                    Page, 5. of'.,*-
in Category with conventional equipment using sound rigging practice.
Included in this category are both construction and permanent
_________________________________________plant items not included in Categories A and B.
3 TYPES OF HANDLING EQUIPMENT Equipment used for handling of items, as covered by this Part,            New requirement in NQA-can be divided into four general types. Paragraphs 3.1, 3.2, 3.3,          1. Types of Handling and 3.4 define these four types of handling equipment and list            Equipment not addressed in some examples.                                                            N45.2.2. They were
_________________________________________addressed                                                                          in N45.2.15.
________________________________________3.1                      Standard Manufactured Component Handling equipment classed as a standard manufactured component is equipment which is available for several sources.
This equipment is normally a catalog item, generally kept in stock, and normally used as a component of a handling system.
Examples of standard manufactured components are:
(a) chains and chain accessories such as hooks, shackles, and links; (b) fiber ropes and accessories;
________________________________________________(c) hooks such as link or eye type, single, sister, and                                _____________
10/28/2010                                                              Hoisting, Rigging, and Transporting Items                                                        Page 5 of 21
 
ANSI N45.2.2-1972, Section 7. Handling              Assurance Requirements QualityTransporting      Items for NuclearPower      Rigging, and for Hoisting, Plants            COM E  S
                                                                    * :
* NQA-1*i4.*S*. bpart 2.15..          ...    ...
miscellaneous; (d) transporting devices such as casters, rollers, shoes, and wheels; (e) wire rope and wire rope accessories such as blocks, clamps, sockets, thimbles, and turnbuckles; (f) miscellaneous items such as cribbing, eyebolts, pads, swivel devices, links, shackles, and sheaves.
3.2 Commercial Standard Design Equipment Commercial standard design equipment for handling is equipment which is available as an item of standard design and manufacture. Examples of commercial standard design equipment are:
(a) gantry, mobile, overhead, and jib cranes; (b) guys and stiffleg derricks; (c) hoists, winches, and trolleys; (d) jacks and jacking systems; (e) transporting devices such as forklift trucks, railcars, tractors, trailers, and transporters; (f) elements of commercial standard design equipment such as booms, masts, and struts; (g) other optional standard accessories and adaptations available from the equipment manufacturer,                            4
                                                    -4 3.3 Special Designed Equipment                                        4 Special designed equipment for handling is equipment which is not available from a commercial source as a catalog or standard designed item, or equipment for which no generally accepted consensus standard exists. This type of equipment may be designated and fabricated by using standard manufactured components and commercial standard designed equipment or by using a combination of nonstandard and standard equipment.
Examples of special designed equipment are:
(a) special gin poles, derricks, and jacking towers; (b) special crane supports such as runways, columns, and frames; (c) rigging devices such as spreader beams, strongbacks, upend and downend devices, bolsters, and yokes; (d) transporting systems such as dollies, special rail cars, and Page 6 of 21 10/28/20 10/2      10 8/2 010                                        Hoisting, Rigging, and Transporting Items Hoisting, Rigging, and Transporting Items                                      Page 6 of 21
 
ANSI N45.2.211972, Section 7. Handing:' . ..... Quality Assurance Requirements for Hoisting, Rigging, and......COMMENTS Transporting Items for Nuclear Power Plants NQA-1199M Subpart 2.15                ~      .
transporters.
3.4 Permanent Plant Handling Equipment Permanent plant handling equipment employed for handling nuclear plant items is equipment which is intended primarily for maintenance and operation of the nuclear power plant but which may also be used for construction. It may consist of standard manufactured components as defined in para. 3.1, commercial standard design equipment as defined in para. 3.2, or special designed equipment as defined in para. 3.3. Examples of permanent plant handling equipment are:
(a) fuel handling equipment; (b) overhead and gantry cranes for reactor and auxiliary (spent fuel) buildings.
4 DESIGN REQUIREMENTS Due to the wide range of equipment normally used in the              New requirement in NQA-handling of items for nuclear plants, it is appropriate that          1. Design Requirements not different criteria be used for designing different types of          addressed in N45.2.2. They handling equipment. This Section describes specific design            were addressed in N45.2.15.
criteria which are appropriate for most applications and which are recommended for general use. If it can be shown that these criteria are not appropriate for specific application, the engineer responsible shall select compatible criteria and document the justification. It is recognized that some items are also covered by other standards, which may be more stringent than Subpart 2.15, and items must meet requirements of both. Hoisting, rigging, and transporting equipment which is to be used exclusively during the construction phase shall be designed in accordance with paras. 4.1, 4.2, and 4.3. Permanent plant handling equipment is designed and selected in accordance with other standards.
The organization responsible for the design shall establish a program for assuring that the handling equipment conforms to the design requirements of the applicable potions of Subpart 2.15.
4.1 Standard Manufactured Components Standard manufactured components shall be selected to safely perform the intended operations structurally, mechanically, and 10/2 8/2 010                                              Hoisting, Rigging, and Transporting Items                                              Page 7 of 21
 
ANSI N45.2.2-1972, Section 7. Handling  QualitYAssurance Requirements for Hoisting, Rigging, and                      COMAENTS Transporting Items for Nuclear Power Plants NQA4 199,4 Subpart.215                          ......................
electrically. They shall have been designed to conform to accepted industry standards.
4.2 Commercial Standard Design Commercial standard design equipment shall be selected to safely perform the intended operations structurally, mechanically, and electrically. They shall have been designed to conform to consensus standards, or when a consensus standard is not totally adequate, to accepted standards.
4.3 Special Designed Equipment Special designed equipment shall be designed to safely perform the intended operations structurally, mechanically, and electrically. Standard manufactured components or commercial standard design equipment, or elements thereof, incorporated into the total system, shall meet the requirements of paras. 4.1 and 4.2, respectively, with safety factors as recommended by the manufacturer of the components and equipment.
4.3.1 Structural.
Structural design of the equipment, except as noted in (a) through (j), shall be in accordance, as applicable, with the latest accepted edition of Manual of Steel Construction of the American Institute of Steel Construction, Timber Construction Manual of the American Institute of Timber Construction, and Building Code Requirements for Reinforced Concrete (AC 1 318) of the American Concrete Institute.
(a) Equipment components shall be designed for the appropriate combination of vertical and horizontal loads.
(b) The effects of seismic activity need not be included in combination with lifting or transporting operations during construction.
(c) Winds in excess of 50 mph (80.5 km/h) normally need not be considered in combination with lifting or transporting operations as these operations are normally suspended before winds exceed 50 mph (80.5 km/h). If available historical wind data indicate the likelihood of operations occurring during winds greater than 50 mph (80.5 km/h), such data shall be utilized as the basis of design. ANSI A58.1, Minimum Design Loads for Buildings and Other Structures, shall be used to Hoisting, Rigging, and Transporting Items                                                    Page 8 of2l 10/28/2010 10/28/2010                                      Hoisting, Rigging, and Transporting Items                                                    Page 8 of 21
 
ANSI N.45.2.2-1472, Section 7. Handll.          . ........ Qualit Assurance RequirementsforHoisting, Rigging, and                COMMENTS Transporting Items for Nuclear PoweirPlants
,___.._...........  ... ...      __. ___.____..__._______.__.NQA        .                              1 1994 Subpart 2.15 determine the appropriate wind loads. If these forces have not been considered in design, the lifting and transporting activities shall be suspended before winds reach 50 mph (80.5 km/h).
(d) Special designed equipment normally is designed for a limited number of operations. Fatigue factors shall be included where applicable.
(e) Vertical impact shall be considered in the design, and selection of impact loads shall be supported by analysis. In no case shall vertical impact load be less than 10% of maximum handled load, excluding test load.
(f) Longitudinal and transverse horizontal forces shall be determined by the maximum acceleration or deceleration which can be delivered by the complete hoisting or transporting system, the maximum grades or slide slopes encountered, maximum out-of-plumb lift, wind, and similar loads. In no case shall longitudinal or transverse horizontal forces be less than 2% of maximum handled load.
(g) For the entire system considered as a whole, the ratio of failure stress to calculated stress shall be no less than 1.67. This minimum ratio shall exist after considering such factors as unequal load distribution, stability, slenderness ratios, and joint efficiencies.
(h) Calculated stresses developed by handling the combination of dynamic test load and vertical impact, plus longitudinal or transverse horizontal loads, if applicable, shall not exceed 133% of allowable stresses.
(i) Nondestructive examinations to be performed during manufacture and the acceptance criteria for these examinations shall be specified by the responsible design organization.
Particular attention shall be given to lamellar tearing, highly restrained connections, and welds joining load carrying members.
(j) Guys and guyed systems, such as column supported girders with traveling hoists, gallows, frames, guyed derricks, and similar equipment, shall be designed to provide system stability and restraint by:
(1) maintenance columns, poles, or masts in the desired Page 9 of 21 Hoisting, Rigging, and Transporting Items 10/28/2010 10/28/2010                                                                Hoisting, Rigging, and Transporting Items                                  Page 9 of 21
 
ANSI.N45.2.2-1972, Section 7. Handling    Quality Assurance Req.irements for Hoisting, Rigging, and        ..... COMMENTS Transporting Wites for Nuclear Pow&#xfd;er Plants NQAr 1994 Subpart 2.15                        __________
position and within desired tolerances; (2) providing capability to resist forces caused by handling Operations, impact, wind, opposing guys, eccentricity, and other similar causes.
The design shall consider the following as a minimum:
(a) handled load (b) height of column and column capability (c) slope of the guys (d) load sharing of multiple guyed systems (e) pretension requirements (f )physical characteristics or wire rope, such as area, modulus of elasticity, and spring constant (g) footing and anchorage adequacy (h) secondary loads caused by stretch of guys (i) safety factors (j) end connections (k) Nil-ductility transition temperatures shall be considered in the design. Design criteria shall be selected by the organization responsible for the design.
4.3.2 Mechanical.
The following special conditions apply to the mechanical design.
(a) Special designed equipment normally is designed for a single operation, or for a limited number of operations. Life, durability, and fatigue factors shall be included where applicable.
(b) Gearing shall be designed by use of American Gear Manufacturers Association formulas, or equivalent formulas, for strength only.
(c) Each independent wire rope or chain and sprocket hoisting unit shall have at least one holding brake. At the place where the brake is applied, the minimum static torque rating shall be 150% of the torque required to hold the maximum load to be handled, excluding the test load.
(d) Engines, gear boxes, torque converters, couplings, hydraulic jacks, pumps, valves, fittings, lines, and similar components used for hoisting operations shall be designed in conformance Page 10 of2l 10/28/20 10 10/28/2010                                        Hoisting, Rigging, and Transporting Items                                        Page 10 of 21 Hoisting, Rigging, and Transporting Items
 
ANSI N45.2.21972, Section 7. Handling                  Qu.tAssuranceRequirements for Hoisting, Rigg" 1', an...MME.
Transporting Items for Nuclear Power Plants NQA-i1994Subpart 2.15                        __________
with the consensus standard and shall be sized to:
(1) handle load, excluding test load, within the manufacturer's rated capacity; (2) operate continuously during the specified duty cycle; (3) safely resist maximum loads imposed by emergency braking.
(e) Hydraulic circuit design shall take into consideration the need for design features which minimize possibilities of unexpected lowering of loads.
(f) Engines, electric motors, brakes, gear boxes, cylinders, bearing housings, and similar components which support any part of the load shall be secured to the main structure in such a way that the entire system, including components, meets structural requirements to adequately support the load.
(g) Rigidity of machinery base, shafts, and similar components shall be adequate to permit proper functioning of the equipment under operating conditions.
4.3.3 Electrical.
The following special conditions apply to the electrical design.
(a) Electrical components and wiring used for hoisting operations shall be designed in conformance with consensus standards and shall be sized to:
(1) lift the handled load, excluding test load, within the manufacturer's rated capacity; (2) operate continuously during the specified duty cycle; (3) be compatible with mechanical requirements for brakes in accordance with para. 4.3.2(c).
(b) Electrical circuits shall contain provisions for proper grounding and shall incorporate design features to minimize possibilities of unexpected lowering of load.
5 ACCEPTANCE CRITERIA FOR MANUFACTURED HANDLING EQUIPMENT 7.3 Hoisting Equipment                                            This Section contains the requirements for manufacture and        There is no one-for-one All equipment for handling items shall be used and maintained      acceptance of manufactured equipment, structures, and            correlation of these N45.2.2 in accordance with the following:                                  accessories used in the handling of nuclear power plant items. requirements to the NQA-1, 7.3.1 Hoisting equipment used for handling shall be certified by                                                                    Subpart 2.15 requirements.
the manufacturer. The certification shall indicate the various                                                                      However, the requirements 10/28/2010                                                      Hoisting, Rigging, and Transporting Items                                          Page I11 of 21
 
ANSI N45.2.2-1972,S                                      Quality Assuran.ce.oequ.ieentsforHoisting, Rigging, and              COMMENTS Tranisporting Item's for Nuclear Power Plants>
                                                                  ...... ........................ Sbart
                                                          -----------..                                      2.15 parameters for the maximum load to be handled.                                                                                      from N45.2.2 are all 7.3.2 Hoisting equipment shall not be loaded beyond its rated                                                                      addressed, and/or load, as certified by the manufacturer, except for test purposes.                                                                  expounded upon, 7.3.3 The requirements of ANSI B30.20, Safety Standard for                                                                          throughout Sections 5, 6, Overhead and Gantry Cranes, ANSI B30.5, Safety Standard for                                                                        and 7 of the NQA-l Subpart Crawler, Locomotive and Truck Cranes, ANSI B30.6, Safety                                                                            2.15.
Standard for Derricks, and ANSI A10.5, Safety Requirements for Material Hoists shall be followed.
5.1 Standard Manufactured Components Standard manufactured components shall be manufactured and accepted in accordance with accepted industry standards.
5.2 Commercial Standard Design Commercial standard design equipment shall be manufactured and accepted in accordance with applicable consensus standards.
5.3 Special Design Equipment Special design equipment shall be based upon one of the following criteria.
5.3.1 Acceptance of existing equipment shall be based upon one of the following criteria.
(a) Historical data which show satisfactory performance in handling loads within the design capability, which are equal to or greater than the intended loads. This history would include records of tests, inspections, and maintenance performed on the equipment, along with the record of actual handling operations.
(b) A load test in accordance with Section 6.
(c) Recognition of capability by an engineer or other qualified materials handling individual when the equipment is handling Category C items only.
5.3.2 Acceptance criteria for new equipment and modifications to existing equipment shall conform with the following requirements.
(a) The design shall have been performed in accordance with Section 4.
(b) Standard manufactured components or commercial standard design equipment incorporated in the total system shall meet the requirements of para.5.1 or 5.2.
10/28/2010                                                        Hoisting, Rigging, and Transporting Items                                      Page 12 of 21
 
            "ANSIN45.221.9t, Secton 7. Handling          Quality Assurance.Req.iurements for Hoisting, Rigging, and                  COMMENTS Transporting"tesf*. :or Nucler Power Plants
_._..._.._._._.,_..,.,_                        N QA-1, I994 Subpart 2.15      .. .....
(c) Structural steel elements shall be fabricated and erected in accordance with the latest edition of AISC S302, Code of Standard Practices for Buildings and Bridges. The following additional items shall be required.
(1) Principal load carrying members shall be designated by the design organization responsible for either or both the design and application of the equipment. Materials of principal load carrying members shall meet any one of the following three qualifications:
(a) record of meeting the minimum mechanical properties as documented by certified material test reports; (b) mechanical test report of a sample of the material showing adequate mechanical properties (this may be made by the manufacturer or a testing laboratory);
(c) conservatism of design, documented by engineer's calculations [this option is acceptable only in emergency situations, where last minute changes have proved necessary by field conditions, and where options (a) and (b) above are not available].
(2) Structural welds shall be made by qualified welders using qualified procedures in accordance with the applicable requirements of the AWS Dl .1,Structural Welding Code -
Steel.
(3) Welds joining principal load carrying members shall be inspected as described in Section 6.
(4) Structural elements of material other than steel shall be constructed in accordance with applicable consensus or accepted industry standards.
(d) Operational tests of the entire system shall be conducted in accordance with Section 6.
(e) Recognition of capability by an engineer or other qualified materials handling individual will suffice in lieu of (a), (c)(l),
and (d) above when the equipment is handling Category C items only.
6 TESTING, INSPECTION, AND MAINTENANCE This Section defines requirements for testing, inspection, and        New requirement in NQA-maintenance to assure that the equipment will perform as              1. Testing, Inspection, and 10/28/2010                                              Hoisting, Rigging, and Transporting Items                                              Page 13 of 21
 
ANSI N45.2.2-1972, Section 7. Handling    Quality Assurance Requirements for Hoisting,.Rigging, an.d                  COMMNTS            .
Transporting Itenms for Nuclear Power Plants NQA-1.1994 Subpart 2.15 required for the safe handling of items at nuclear facilities.      Maintenance not addressed in N45.2.2. They were addressed in N45.2.15.
6.1 Testing A test program shall be established to demonstrate that the handling component or equipment will perform satisfactorily in service. Testing may involve either operational or load type tests, or a combination of the two. Operational type tests cover checks of control functions and capabilities. Load type tests ensure structural and mechanical capability. Test loads shall normally be handled at the same speeds and rates of acceleration (deceleration) as planned for the intended item, except that when dynamic test loads greater than 100% are designated, the rates of acceleration (deceleration) may be adjusted downward. in addition, the following shall apply as applicable.
1-                                                                  -t 6.1.1 Standard Manufacturing Components.
One of the following will satisfy the requirements for testing of these components:
(a) tests as required by applicable accepted industry standards (b) actual proof load tests by the manufacturer (c) dynamic load tests as part of the system being tested to 110% of the maximum load to be handled
: 4.                                                                  4 4-6.1.2 Commercial Standard Design Equipment.                      4 One of the following will satisfy the requirements for testing of this equipment:
(a) tests as required by applicable consensus standard (b) a dynamic load test equal to 110% of the maximum load to be handled
                                                  +                                                                    4 4-6.1.3 Special Designed Equipment.                                -t Requirements for testing of this equipment shall be as follows.
(a) An operational test shall be performed. This test shall be over the portion of the motions applicable to the handling system tested.
(b) A dynamic load test equal to 110% of the maximum load to be handled by the complete system shall be performed, except that documented proof of equivalent handling ability as Hoisting, Rigging, and Transporting Items                                              Page 14of21 10/28/2010 10/28/2010                                        Hoisting, Rigging, and Transporting Items                                              Page 14 of 21
 
ANSI... N 5.2........
          .ANSIN45..2-1972,                7 ..Handling SectionQ.7.
Sec io        ... dln Ha                    uality Assurance  .. Requirements
                                                                                              ....        "*...."    for Hoist  ...      .T' and Rigging,    I          COMMENTS            :
Transporting          Itelns    for  Nuclear Power    Plan ts.
NQA-1 1994 Subpart          2.15                      ___________
described in para. 5.3.1 (a) may be substituted. Transport equipment tests shall demonstrate adequacy of braking, drawbar pull, stability, and other similar factors. Testing shall take place with equipment in the location where it will be used for actual handling of the item, except that in cases where the test would interfere with, or needlessly endanger an existing item or the item to be lifted, testing may be conducted at another location, on or near the construction site. Where practical and useful, load tests shall be applied over the entire range of motions required for the actual handling of the item, with the following exceptions.
(1) Spreader bars, jacks, slings, or similar items whose loading is independent of travel may be tested in test fixtures at locations other than the construction site.
(2) Transporting vehicles need not be tested over the entire length of travel.
During subsequent use, the testing, inspection, and maintenance shall be performed as specified by other standards.
4 6.1.4 Rerated EauiDment.                                                      +
7.3.4 For special lifts, hoisting equipment may be re-rated, or    For special lifts, hoisting equipment may be rerated, or                        Similar requirement. NRC modified and re-rated, upon approval by the manufacturer or if      modified and rerated, upon approval by the manufacturer or, if                  Regulatory Position in the manufacturer's specifications are not available, the            the manufacturer's specifications are not available, the                        Regulatory Guide 1.38, limitations assigned to the equipment shall be based on the        limitations assigned to the equipment shall be based on the                    C. 1.b is incorporated into determinations of a qualified engineer competent in this field      determinations of a qualified engineer competent in this field                  the NQA-l requirements.
and such determination shall be documented and recorded            and such determination shall be documented and recorded appropriately. Re-rated equipment shall be given a dynamic          appropriately.
load test over the full range of the lift using a test weight at    Rerated equipment shall be given a dynamic load test over the least equal to the lift weight. A dynamic test includes raising,    full range of the lift using a test weight at least equal to 110%
lowering and traversing the load in contrast to a static test      of the lift weight. A dynamic test includes raising, lowering, where the test weight may be increased incrementally with no        and traversing the load, in contrast to a static test, in which the movement.                                                          test weight may be increased incrementally with no movement.
NRC Regulatory Guide 1.38, Regulatory Position C.1.b:
: b. Subdivision 7.3.4 of ANSI N45.2.2-1972 delineates requirements for re-rating hoisting equipment for special lifts.
This subdivision requires that re-rated equipment be given a dynamic load test over the full range of the lift, using a test weight at least equal to the lift weight. In lieu of this Page 15 of2l Items 10/28/2010                                                      Hoisting,  Rigging, and Hoisting, Rigging,        and Transporting Transporting Items                                                  Page 15 of 21
 
ANSI N45.2.*21972, Section 77.Handling                  Quality Assurance Requirements for Hoisting, Rigging, and              COMMENTS.
Transporting Items for Nuclear Power Plants SNQA-1 1994 Subpart 2.15.~1 requirement, the test weight used in temporarily re-rating hoisting equipment for special lifts in accordance with the provisions of subdivision 7.3.4 should be at least equal to 110%
of the lift weight.
7.4 Inspection of Equipment and Rigging                              6.2 Inspection An inspection program shall be established for equipment and        Handling equipment in use shall be subjected to inspection. There is no one-for-one rigging. A system shall be established that will indicate            Inspections as detailed herein include three types: frequent,  correlation between the acceptability of all equipment and rigging after each inspection,    periodic, and major. Evidence of inspections and the results of subsections of N45.2.2 to This system shall specify control of nonconforming lifting          periodic and major inspections shall be documented.            the Inspection requirements equipment. Periodic inspections shall be supplemented with                                                                          of NQA-1. However, the special visual and non-destructive examinations and dynamic                                                                          intent of the required load tests prior to handling of items described in Subsection 7.2                                                                    inspections is met through of this standard.                                                                                                                    the requirements of this 7.4.1 Rigging that is frayed, worn or otherwise deteriorated                                                                        subsection to NQA-1, shall not be used.                                                                                                                  Subpart 2.15.
7.4.2 Hoisting equipment that does not meet manufacturer's specifications shall not be used.
7.4.3 Equipment and rigging shall be kept clean and free of contaminants that are detrimental to the material being handled.
7.4.4 Rigging items such as hooks, shackles and turnbuckles that appear to have yielded or are distorted shall not be used.
                                                                  . 6.2.1 Frequent Inspections.
Frequent inspections are those performed on a day-to-day or similarly frequent basis. The inspections shall conform to the consensus standards and federal, state, and local health and safety regulations. The inspection coverage shall include parts essential to safe operation plus those parts recommended by the manufacturer. A checklist shall be used to perform the inspections. These inspections shall be performed by the individual responsible for the operation of the particular equipment or by another competent individual.
6.2.2 Periodic Inspections.
Periodic inspections are those performed on a preset interval.
The inspections shall conform to the consensus standards and federal, state, and local safety regulations. The inspection coverage shall include parts essential to safe operation plus those parts recommended by the manufacturer. If a system or Rigging, and Transporting Items                                        Page 16 of 21 10/28/2010 10/28/2010                                                        Hoisting, Hoisting, Rigging, and Transporting Items                                          Page 16 of 21
 
ANSI N45.212-1972, Section7 Handling7,                    [ Quality Assurance.Req.u.rem.n.s fo.Hohstmg.. Rigging, and            COMMENTS Transporting Items for Nuclear Power Plants
_______________________________________NQA-1_199.                                      Subpart 2.15 component is not included in established codes or standards, it shall be included in a planned, scheduled inspection program developed by the organization responsible for its use and operation. Personnel qualified by experience or special training, as determined by the organization responsible for the inspection, shall perform such inspections. Results of periodic inspections shall be documented.
6.2.3 Major Inspections.
Major inspections are those performed on an as-specified basis and shall conform to a procedure prepared by the responsible organization. The procedure shall also state when the inspections are to be performed. Inspection coverage shall include recommendations of the manufacturer or designer.
Visual examinations or nondestructive examinations shall be used for these inspections as deemed necessary by the designer of the component or system and by the organization responsible for its use and operation. Particular attention shall be paid to the following as applicable:
(a) welds at joints between highly stressed members; (b) welds at joints in principal load carrying members and highly restrained members; (c) excessive deformation in principal load carrying members or parts; (d) adequacy of brakes under both static and dynamic loadings; (e) response and positiveness of controls; (f) accuracy and response of load indicators; (g) overheating of power supply.
Welds to be inspected shall be inspected in accordance with the applicable requirements of AWS D 1.1, Structural Welding Code
                                                                        - Steel. Nondestructive examinations performed during these inspections shall be performed by an individual certified to Recommended Practice SNT-TC- 1A.
Other parts of these inspections shall be performed by personnel qualified by experience or special training, as determined by the organization responsible for the inspections.
Results of major inspections shall be documented.
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ANSI N45.2.2-1972, Section 7. Handling  Quality Assurance Requirements for Hoisting, Rigging, and                COMMENTS Transporting Items for Nuclear_ Power Plants NA1FA  1990A.uhupart Z$
6.3 Maintenance A maintenance program shall be established to ensure that the handling equipment is maintained in good operating condition.
The program shall provide for adequate protection of equipment which is used in an environment other than the environment for which it is designed. Those responsible for operation of equipment shall be responsible for maintenance.
6.3.1 Prerequisites.
Equipment shall be serviced at specified intervals in accordance with the manufacturer's recommendations, severity of service, and environment. Items damaged or worn sufficiently to affect operation of equipment shall be repaired or replaced before continuing operations. Replacement parts shall meet or exceed the specifications of the part being replaced.
6.3.2 Records.
Maintenance shall be documented and the records kept current.
These records shall show lubrication, servicing, adjustments, repairs, and replacement of the equipment.
7 CONTROL OF THE USE OF HANDLING EQUIPMENT This Section contains requirements to be fulfilled by the        New requirement in NQA-organizations that will have operational control of the handling  1. Control of the use of equipment in use at a nuclear power plant. These organizations    Handling Equipment not shall appoint a person-in-charge (PIC). The PIC shall assure      addressed in N45.2.2. They that procedures are provided as required; and he shall provide    were addressed in N45.2.15.
surveillance over the activities of personnel associated with the handling operations to ensure that the procedures are being followed, that specified quality assurance requirements are being met, and that good handling practices are being followed.
7.1 Handling Category A Items 7.1.1 Prerequisites.
Prior to the handling of a specified item and initial use of equipment, it shall have been verified that:
(a) design and manufacture of the equipment are in accordance with Sections 4 and 5; (b) the load carrying capability has been established in 10/28/2010                                        Hoisting, Rigging, and Transporting Items                                          Page 18 of 21
 
Handling  Quality Assurance Requirements foruHoisting, Riggmg, and        COMMENTS TransportingItems for Nuclear Power Plants
_..__.....__._.________._NQA-1.1994* Subpart 2.15 .
accordance with Section 6, and it equals or exceeds the load to be handled; (c) the equipment has been maintained in accordance with Section 6; (d) handling and moving clearances have been investigated and are satisfactory; (e) set down and installation areas have been cleared and prepared as required and are ready to receive the item.
7.1.2 Procedures.
The handling of Category A items shall be in accordance with written approved procedures, and associated instructions or drawings, as applicable. The procedures shall include the following as a minimum.
(a) Responsibilities shall be defined for organizations and key responsible individuals. Their qualifications shall be in accordance with Section 8.
(b) Handling equipment to be used shall be identified, and its selection shall be on the basis of its capability to handle the load. Loads handled shall not exceed the loads used in the design of the equipment.
(c) Manufacturer's instructions and conditions of operation shall be followed for the handling equipment and items to be handled.
(d) Work instructions shall be issued for tasks which, because of their relationship to each other, must be accomplished in a certain sequence.
(e) Where applicable, acceptance criteria shall be specified for determining when a task has been satisfactorily completed.
(f) Inspection checkpoints shall be included when documentation by specific individuals is required as proof of satisfactory completion. Final documentation review and sign-off shall be made to verify that the operations have been performed in accordance with the procedures.
(g) Procedures shall identify maximum safe loads which are permissible and shall describe specific methods of ensuring that these safe loads are not exceeded. Load indicating devices, properlv calibrated, shall be used in systems where the primarv Page 19 of2l 10/28/2010          Hoisting, Rigging, and Transporting Items Hoisting, Rigging, and Transporting Items                              Page 19 of 21
 
N451.2-1972, Section 7. Handling ASI                                        Quality Assurance Requirements for Hoisting, Rigging, and        COMMENTS Transporting Items for Nuclear Power P~lan~ts
_.._...._*_____ANS      __45,2.-1  __2, __ct ___an  _ing *NQA-1
__                              1994 Subpart 2.15 source of power has the capability of imposing excessive loads on the equipment, component, or item being handled.
(h) The need for soils tests shall be considered. (See Section 3 of Appendix 2.15, Subpart 3.2, Part IIH.)
7.1.3 Variations.
Variations from the procedures shall be approved and documented. Some situations may require emergency variations from the procedure. The individual with authority to act in emergencies shall have been previously identified (see para.
7.1.2). Such variations shall be documented after the fact.
7.2 Handling Category B Items 7.2.1 Prerequisites.
Prior to the actual handling of a specified item, it shall have been determined that the prerequisites of paras. 6.1 through 6.4 have been implemented. Handling and moving clearances shall have been investigated 7.2.2 Procedures.
The handling of Category B items shall be in accordance with written procedures as set forth under paras. 7.1.2(b), (c), and (d).
7.2.3 Variations.
Variations from the procedure shall be in accordance with para.
7.1.3.
7.3 Handling Category C Items 7.3.1 Prerequisites.
Evidence of maintenance in accordance with para. 6.3 shall be verified.
7.3.2 Procedures.
Written detailed procedures are not required. Category C items shall be handled by experienced personnel in accordance with good rigging and handling practices as described in safety handbooks, consensus standards, and corporate or contractor standards designated for the job, and in compliance with regulations. Manufacturer's load charts and general safe rigging manuals shall be available to personnel 7.5 Personnel                                                  8 QUALIFICATIONS OF PERSONNEL 10/2 8/2 010                                                Hoisting, Rigging, and Transporting Items                              Page 20 of 21
 
ANSI N45.2.24972, Section 7. Handling                    Quality Assurance Requirements for Hoisting, Rigging, and                COMME..S Transporting Items for Nuclear Power Plants
                                                                    . .. *NQA-11994S                      ...........................
2                          ** ........          .
The responsible organization shall determine that the personnel    This Section contains minimum qualifications for certain key        Similar requirement.
engaged in operating material handling, equipment are              personnel involved in assuring safe handling of nuclear power      Additionally addressed in competent and have demonstrated satisfactory ability in            plant items. Qualifications of these personnel shall be verified    N45.2.15.
operating similar lifting equipment.                                by objective evidence and documented.
8.1 Person-In-Charge (PIC)
The PIC of handling operations shall be designated by his          New requirement in NQA-management. He shall have demonstrated supervisory                  1. Person-In-Charge not experience in the hoisting, rigging, and transporting activities    addressed in N45.2.2. It was for which he is responsible, to the satisfaction of the cognizant  addressed in N45.2.15.
management.
8.2 Engineer The engineer responsible for the design, selection, or              New requirement in NQA-application of special equipment, or a combination of these,        1. Engineer not addressed in shall have demonstrated capability in the technical aspects of      N45.2.2. It was addressed in similar work. This capability shall be achieved through            N45.2.15.
education and experience. He shall be an engineering graduate of an accredited college or university, or a Professional Engineer registered to practice in an applicable discipline.
8.3 Inspector The inspector of hoisting, rigging, and transporting equipment      New requirement in NQA-shall have demonstrated experience in the activity for which he    1. Inspector not addressed is responsible. Nondestructive examiners shall meet the            in N45.2.2. It was addressed qualifications of Recommended Practice SNT-TC-1A                    in N45.2.15.
: 8. RECORDS                                                          9 RECORDS Record copies of completed procedures: reports; personnel          Record copies of procedures, reports, personnel qualification      Similar requirements.
qualification records; test equipment calibration records; test    records, test equipment calibration records, test deviation or deviation or exception records; and inspection and examination      exception records, and inspection and examination records shall records shall be prepared as required by this standard. These      be prepared. These records shall be retained with other project records shall be placed with other project records as required by  records as required by code, standard, specification, or project code, standard, specification or project procedures.                procedures.
10/28/2010                                                        Hoisting, Rigging, and Transporting Items                                              Page 21 of 21
 
M&TEwaspreviously        addressed in a number of.ANSI                Quality: Assurance Reqrements for Calbrationn and                    CoMMEN*.TS standards. These are addressed below with notation of the            Control of Measuring and Test EquipmentUsed in Nuclear applicable standard.                                                  .. Facilities
                                                ... ... ......                ...      NQA-1 1994.Subpart 2.16 Subpart 2.16 consists of ANSI/IEEE Std. 498-1985 Subpart 2.16 consists of ANSI/IEEE Std. 498-1985, IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities.
The following text is from the above referenced standard.
IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities ANSI N18.7 &sect; 5.2.16 Measuring and Test Equipment.                    NQA-l-1994, Part II Applicability. Applicability for all of        Requirements from ANSI
&#xb6; 4 American National Standard N45.2.4-1972 shall be applied        the Subparts (i.e., 2.x) is addressed in a general sense in the    N45.2.4 have been to those activities occurring during the operational phase that      Introduction to Part II.                                            incorporated into NQA-1, are comparable in nature and extent to related activities                                                                                Basic Requirement 12, occurring during construction.                                                                                                          Supplement 12S-1, and Subpart 2.16.
: 1. Introduction 1.1 Scope.
This standard sets forth the requirements for a calibration        NQA-1 adds introductory program to control and verify the accuracy of measuring and        statement that is similar to test equipment used to ensure that important parts of a nuclear    the overall introduction to facility are in conformance with prescribed technical              the various standards that requirements and that data provided by testing, inspection, or      contained M&TE as a maintenance are valid. These requirements also cover                subsection of the modifications and those activities occurring during the            requirements. This standard operating phase that are comparable in nature and extent to        is designed to capture the related activities occurring during the initial construction of the information from all the facility,                                                          previous standards into one location to avoid repetition.
During the construction phase and when modifications are            NQA-l-1994, QAPD, and being performed, this standard shall be used in conjunction with Standards contain within the applicable portions of ANSIIASME NQA- 1-1983 [1 ] and          provide controls for the ANSI! ASME NQA-2-1983 [2]. During the operations phase              operations phase.
this standard shall be used with the applicable portions of ANSI/ANS 3.2-1982 10/28/2010                                                      Calibration and Control of Measuring and Test Equipment                                  Page I of 11
 
M&T E was preVibusly, addreisii in a number of AN          NS I          Quality Assurance Requireements for Calibration and                  COM*MNTS standards. Theseare addressed below with notationotthe                  Control of Measuring and Test Equip menttUsed in Nuclear applicable standard.                                                              Facilities NQA-I 1994 Subpart.2.16                o_._  _
1.2 Applicability.
ANSI N18.7 &sect; 5.2.16 Measuring and Test Equipment. The                  The requirements of this standard apply to the measuring and        The maintenance and method and interval of calibration for each installed instrument        test equipment used during the installation, inspection, test, or  testing activities addressed and control device shall be defined and shall be based on the          maintenance activities performed at a nuclear facility,            by NQA-1 would be type of equipment, stability and reliability characteristics,          Measuring and test equipment does not include test equipment        comparable to the statement required accuracies and other conditions affecting calibration,        used for preliminary checks where data obtained will not be        in N18.7 regarding used to determine acceptability or be the basis for design or      calibration of each installed engineering evaluation,                                            instrument and control device. Addressed in Part II, Section 12.0 of the QAPD.
The extent to which the individual requirements of this standard    Similar words to the N45 apply will depend upon the nature and scope of the work to be      daughter standards that performed and the importance of the item or service involved,      became the basis of this standard.
The requirements of this standard are intended to be applied to    NQA- 1-1994 defines measuring and test equipment used in safety systems                applicability, not a specific equipment. 2 However; they may also be applied to measuring        requirement.
and test equipment used on non-safety related systems equipment.
Footnote 2 Safety systems equipment is defined in IEEE Std 603-1980.
1.3 Responsibility.
It is the responsibility of the organization invoking this standard New requirement for to provide for the establishment and execution of a calibration    M&TE.
program for the plant consistent with the provisions of this standard. The work of establishing practices and procedures and providing the resources in terms of personnel, equipment, and services to implement the requirements of this standard may be delegated to other organizations, and such delegation shall be documented. In any case, the organization invoking this standard shall retain responsibility for overall program effectiveness.
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T Quali Assurance Requirements for Calibration and-                        OMMENTS standards. These are addressed below with notation of the    Control of Measuring and Test Equipment Used in uciear applicable standard.                                                    iacilities
                                                                                          -F&#xb6;~              .
_______________________________________NQA44M99                              Subpart 2.16
: 2. Definitions.
The following definitions are provided to assure a uniform      These definitions are not understanding of selected terms as they are used in this        contained in the current standard.                                                        standards.
accuracy. A measure of the degree by which the actual output    New definition of a device approximates the output of an ideal device nominally performing the same function.
calibration. Comparison of items of measuring and test          Clarification, the word equipment with reference standards or with items of measuring    quantity should be replaced and test equipment of equal or closer tolerance to detect and    with quantify.
quantity [quantify in context and 1990 edition] inaccuracies and to report or eliminate those inaccuracies.
measuring and test equipment. Devices or systems used to        New definition calibrate, measure, gage, test, inspect or control to acquire research, development, test or operational data or to determine compliance with design, specifications or other technical requirements.
reference standards. Standards (that is, primary, secondary      New definition and working standards, where appropriate) used in a calibration program. These standards establish the basic accuracy limits for that program.
tolerance. The allowable deviation from a specified or true      New definition value.
: 3. References When the following standards referred to in this standard are    The VCSNS QAPD superseded by a revision approved by the American National      establishes the standards to Standards Institute, the revision is not mandatory until it has  be used with any approved been incorporated as part of this standard.                      alternatives.
[1] ANSI/ASME NQA-1-1983, Quality Assurance Program Requirements for Nuclear Facilities.
[2] ANSI/ASME NQA-2-1983, Quality Assurance Requirements for Nuclear Power Plants.
[3] ANSI/ANS 3.2-1982, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.
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M&TE was previously addressed in a number of ANSI                    Quality Assurance Requirements for Calibration and                  COMMENTS standards. These are addressed below with notation of the            Control of Measuring and.Test Equipment Used in Nuclear applicable standard.                                                        Facilities NQA-1194 Subpart 2.16
[4] IEEE Std 603-1980, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.
: 4. General Requirements N45.2 &#xb6; 1 Measures shall be established and documented to            A documented program shall be established, implemented and      NQA-1 adds detail.
assure that tools, gages, instruments, and other inspection,        maintained for the calibration and control of measuring and test measuring, and testing equipment and devices used in activities      equipment and reference standards. It shall be designed to affecting quality are of the proper range, type, and accuracy to    determine and assure the accuracy of measuring and test verify conformance to established requirements.                      equipment and reference standards and shall provide for the prompt detection of inaccuracies and for timely and effective corrective action. This documented program shall include as a minimum the following general requirements.
4.1 Equipment Identification.
A list of measuring and test equipment, and reference standards  NQA-1 adds a requirement and their assigned locations shall be prepared to specifically  to have a list of equipment identify those items within the calibration program.            and standards.
4.2 Calibration Procedures.
N45.2.4 &sect; 2.5 Measuring and Test Equipment                          Documented procedures for calibrating measuring and test        NQA-1 adds detail on 2.5.1 Selection. Use shall be made of approved industry              equipment and reference standards shall be used. Procedures      procedure content.
standards relating to measuring procedures.                          such as published standard practices, written instructions that accompany purchased equipment, or other acceptable instructions may be used.
Calibration procedures shall include the following minimum basic information:
(1) Identity of the item to be calibrated (2) Calibration equipment and reference standards to be used (3) Checks, tests, measurements, and acceptable tolerances (4) Sequence of operations (5) Special instructions when necessary 4.3 Records.
ANSI N45.2 &sect; 13. Control of Measuring and Test                      Records shall be maintained for each individual piece of        NQA-1 adds detail on Equipment                                                            equipment to show that established schedules and procedures      information to be included N45.2 &#xb6; 3 Records shall be maintained and equipment suitably        for the calibration of measuring and test equipment and          in the records.
marked to indicate calibration status.                              reference standards have been followed. The records shall contain a history of calibration and other means of control 10/28/2010                                                      Calibration and Control of Measuring and Test Equipment                                Page 4 of 11
 
M&TEwas previously addressedin a number of ANSI*:            Quality Assurance Requirements for    fCalibration and              CoS                ,
Sstandards. Theseare addressed below wth notation of the    Control of Measuring and Test Equipment Used in Nuclear applicable standard.                                                  Facilities.
NQA-11994 Subpart 2. 16 showing calibration interval, date of last calibration, when next calibration is due, conformance or nonconformance to required tolerances prior to and following adjustments, and any limitations on use.
Each record shall identify the equipment to which it applies, the NQA- I adds detail on procedure or instruction followed in performing the calibration,  information to be included the calibration data, the identity of the standard used, the      in the records.
identity of the person performing the calibration, and the calibration date.
: 5. Elements of Control The documented program shall include as a minimum the            NQA-1 adds details in elements of control described in the following subsections:      Section 5 on the elements of control.
5.1 Adequacy of Reference Standards.
Reference standards used for calibrating measuring and test      New requirement.
equipment shall have calibration ranges, precisions and accuracies so that the measuring and test equipment and plant equipment can be calibrated and maintained within the required tolerances. In general, the inaccuracy of the reference standards shall contribute no more than one fourth of the allowable measuring and test equipment tolerance. However, when the actual inaccuracy of the measuring and test equipment is less than one fourth of the plant equipment tolerance, or if reference standards less than one fourth of the tolerance of the measuring and test equipment are not available, the requirement for one fourth may not be necessary. The rationale for deviating from these requirements shall be justified and documented.
5.2 Environmental Controls.
Measuring and test equipment and reference standards shall be    New requirement.
transported, stored and calibrated in environments that will not adversely affect their accuracy. Environmental factors that shall be considered include, but shall not be limited to, temperature, humidity, vibration, radio-frequency interference, 10/28/2010                                              Calibration and Control of Measuring and Test Equipment                                Page 5 of I11
 
M&TE-was previously addressed in a number of ANSI                      Quality Assurance Requirements forCalibration and                    COMM* *S standards. These are addressed below with notation of the            Control of Measuring and Test Equipment Used in Nuclear
                      .aplicable standard.    .....                                              Facilities NQA-1 1994 Subpart.2.16. ....
electromagnetic interference, background radiation, dust, cleanliness, and fumes. When inaccuracy of measuring and test equipment or reference standards, because of environmental effects, cannot be avoided, compensating corrections shall be determined and applied.
5.3 Intervals of Calibration.
ANSI N45.2 &sect; 13. Control of Measuring and Test                        The program shall require that measuring and test equipment      Similar requirement, more Equipment                                                            and reference standards be recalled for recalibration at          detail added in NQA-1 N45.2 &#xb6; 2 The method and interval of calibration for each item        prescribed intervals to verify the required accuracy. Such shall be defined and shall be based on the type of equipment,        intervals may be in calendar time or relate to usage. Interval stability characteristics, required accuracy, and other conditions    selection should consider experience, inherent stability, purpose affecting measurement control.                                        of use, and accuracy required. Historical records which contain sufficient experience data for evaluating and adjusting calibration intervals shall be maintained.
5.4 Traceability.
N45.2 &#xb6; 1 To assure accuracy, inspection, measuring, and test        Measuring and test equipment shall be calibrated utilizing        Similar requirements in the equipment shall be controlled, calibrated, adjusted, and              reference standards whose calibration has a known valid          context of Section 5 of maintained at prescribed intervals or prior to use against            relationship to nationally recognized standards or accepted      NQA-1, Subpart 2.16.
certified equipment having known valid relationships to              values of natural physical constants.
nationally recognized standards.
N18.7 &#xb6; 2 Tools, instruments, testing equipment and measuring devices used for measurements, tests and calibration shall be of the proper range and type and shall be controlled, calibrated and adjusted and maintained at specified intervals or prior to use to assure the necessary accuracy of calibrated devices.
ANSI N45.2.1 &sect; 2.5 Test Equipment 2.5.2 Calibration and Control. Test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally known standards.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. As appropriate, measuring and test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid 10/28/2010                                                      Calibration and Control of Measuring and Test Equipment                                Page 6 of I11
 
  .M&TE was previously iaddressed in a number of ANS                    QuAlityAssurance Requirements foriCalibration and                        COMMENTS standards. These are addressed below wiith notation of the          Control4f.Measuring and Test Equipment Used in Nuclear
                      ...  .1.ap9 standard.      ...........                                      a      b.cable ties  i..                      ...
relationships to nationally recognized standards.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. Measuring and test equipment used to determine compliance with specifications, shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards. If no national standards exists, the basis for calibration shall be documented. Records of the calibrations shall be maintained and equipment suitably marked to indicate date of next required calibration. When inspection and testing equipment are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested. Test equipment found to be out of calibration shall be clearly identified as such.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. The equipment shall be adjusted or calibrated or both at prescribed intervals against certified standards having known valid relationships to national standards, where such exists.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 Calibration and Control. Measuring and test equipment used to determine compliance with Specifications, shall be adjusted and calibrated at predetermined intervals, based on equipment stability and use, against certified equipment having known valid relationships to nationally recognized standards.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. As appropriate, measuring and test equipment shall be adjusted and calibrated at prescribed intervals against certified equipment having known valid relationships to nationally recognized standards.
N45.2 &#xb6; 1 If no national standards exist, the basis for              If no national standard exists, the basis for calibration shall be    Similar requirement.
calibration shall be documented.                                      documented.
N45.2.1 &sect; 2.5 Test Equipment 10/28/2010                                                      Calibration and Control of Measuring and Test Equipment                                    Page 7 of I11
 
M&TE was previously addressed in a number of ANS                      " Qualio Assurance Requirements for CaUbration'and.                      C*MMENTS standards. These are addresse        lovwtntainfth                    Control of, Measuring and. Test Equipmnent Used in Nuclear applicables.      rd..........      ........      ...........        NQA- 14ubpart Facilities      2.16 2.5.2 Calibration and Control. If no national standards exist, the basis of calibration shall be documented.
N45.2.2 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. If no national standards exists, the basis for calibration shall be documented.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. If no national standards exists, the basis for calibration shall be documented.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. If no national standards exists, the basis for the adjustment or calibration shall be documented.
Records shall be maintained and equipment suitably marked to indicate calibration status. Measures shall be taken to assure proper handling, storage and care of installation of inspection and testing equipment after calibration in order to maintain the required accuracy of such equipment.
N45.2.8 &sect; 2.8 Measuring and Test Equipment 2.8.2 If no national standards exist, the basis for calibration shall be documented.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. If no standards exist, the basis for calibration shall be documented.
Reference standards used in the calibration program shall be      NQA- 1 adds detail on identified on calibration data records and supported by            record information related certificates, reports, or data sheets attesting to the calibration to reference standards used date, calibration facility, environmental conditions, and data    in calibration.
that shows conformance to accuracy requirements.
10/28/2010                                                          Calibration and Control of Measuring and Test Equipment                                Page 8 of I11
 
M&TE w~as previously addressed in 'anu er: of -ANSI                  Quality Assurance Requirements for Calibration and                    COMMENTS standards. These are addressed below with notationof the            Control of Measuring and Test Equipment Used in Nuclear applicable standard.                                      IFacilities NQA-1 1994: Subpart 2.16 5.5 Labeling.
Measuring and test equipment shall be labeled to indicate their    New requirement.
control status. The label shall indicate when the next calibration is due. When size or functional characteristics of measuring and test equipment or reference standards prevent the application of a label, an identifying code shall be applied to reflect status.
When neither labeling nor coding is practical, the procedures shall provide for monitoring of records to ensure control.
Measuring and test equipment whose use shall be limited shall be identified and controlled; for example, a multi-scaled instrument which may be acceptable on one or more scales but limited on a specific scale or an instrument that is intended to be used for making preliminary checks.
5.6 Precalibration Checks.
Measuring and test equipment and reference standards                New requirement.
submitted for calibration shall be checked and the results recorded, before adjustments or repairs are made.
5.7 Nonconformance.
ANSI N18.7 &sect; 5.2.16 Measuring and Test Equipment.                  Measuring and test equipment and reference standards found to      Similar requirement, but
&#xb6; 2 When calibration, testing, or other measuring devices are      be out of calibration or which have not been properly              detail added in NQA-1.
found to be out of calibration, an evaluation shall be made and    maintained or calibrated, or which have been subjected to documented concerning the validity of previous test and the        possible damage, shall be identified as nonconforming and acceptability of devices previously tested from the time of the    removed from service until such time as corrective measures previous calibration,                                                have been taken. All equipment tested or calibrated by the item ANSI N45.2 &sect; 13. Control of Measuring and Test                      since the last calibration shall be identified and sufficient Equipment                                                            investigations performed to either re-establish the acceptability N45.2 &#xb6; 2 When inspection, measuring, and test equipment are        of the equipment or to confirm a nonconformance. The results found to be out of calibration, an evaluation shall be made and      of such investigations shall be documented.
documented of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested.
N45.2.4 &sect; 2.5 Measuring and Test Equipment 2.5.2 Calibration and Control. When inspection and testing equipment are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results and 10/28/2010                                                    Calibration and Control of Measuring and Test Equipment                                Page 9 of I11
 
M&TE was previously addressed in a number of ANSI standards. These are addressed below with notation of the
                                                                                          ... ualty~sgrgceieqmrmens Quality Assurance    Requirements fr:Caibrt.o for Calibration and Control of Measuring and Test Equipment Used in Nuclear an    I        COMMENTS
                                                                                                                                                    .    *          .:[:i pplicable standard.                                                    Facities
_.. _...._  ... ...... . . . ...                      .N QA- 1 19. 94 Subpart 2.16 .              _. . ..        . . .. . .
of the acceptability of items previously inspected or tested. Test equipment found to be out of calibration shall be clearly identified as such.
N45.2.5 &sect; 2.5 Measuring and Test Equipment.
2.5.2 Calibration and Control. Test equipment found to be out of calibration shall be clearly identified as such. When discrepancies, malfunctions, or inaccuracies in inspection and testing equipment are found during calibration, all items inspected with that equipment since the last previous calibration shall be considered unacceptable until an evaluation has been made by the responsible authority and appropriate action taken.
N45.2.13 &sect; 7.4 Measuring and Test Equipment 7.4.2 Calibration and Control. When inspection, measuring and test equipment are found to be out of calibration, an evaluation shall be made and documented of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested.
5.8 Control of Measuring and Test Equipment and Reference Standards.
Measuring and test equipment and reference standards shall be    New requirement.
controlled to assure consistent results of acceptable accuracy.
The following controls shall be considered.
(1) Environmental and handling controls (2) Training and qualification of personnel (3) Checking calibration status before use (4) Interim checks between calibrations (5) Documenting and recalibrating possible damaged measuring and test equipment and reference standards (6) Limiting use to authorized personnel 10/28/2010                                                          Calibration and Control of Measuring and Test Equipment                          Page 10 of I11
 
Mt&TE was pIkviouily addressed in a number ofNS1                  VQaht&y Assursanee Requirwemetsfor        Calibration and~                  OI'VIENT.4 standards.;hese are addressed beowwith notaton of the .          Co    otrolf    aring and Test Equ~p etntUsed in Nucer          a applicable standard.                                                        Faclities
_________________________________________                        NA-11994 gubpairt,2.I                          _____________
: 6. Audits The calibrating program, in its entirety, is subject to audit in  NQA-1 states a requirement accordance with the requirements of the Quality Assurance          from 10 CFR 50, Appendix Program.                                                          B regarding audits.
: 7. Document Control Equipment identification lists, procedures, calibration records,  NQA-I adds detail to what personnel qualification reports, and nonconformance reports        is contained in ANSI shall be retained with other project records as required by        N45.2.9 regarding records.
codes, standards, specifications, or project procedures.
Collection, storage and maintenance of these records shall be in accordance with the Quality Assurance Program.
10/28/2010                                                  Calibration and Control of Measuring and Test Equipment                                  Page 11 ofll1
 
N18.7-1976/ANS-3.2.Quality.Assurance          uANSI            Requirements'for Maintenance of                COMMENT'S
              .Maintenance and Modification                                              Nuclear  Facilities
                              &sect;5.2.7                                                  NQA-1 1994 Subpart 2.18 1 GENERAL 5.2.7.1 &#xb6;1 Maintenance Programs A maintenance program            Subpart 2.18 provides amplified requirements for the            Similar requirement shall be developed to maintain safety-related structures, systems maintenance of nuclear facility components and systems.
and components at the quality required for them to perform        Maintenance consists of actions necessary to maintain or their intended functions.                                        restore an item to acceptable conditions. This Subpart supplements the requirements of Part I and shall be used in conjunction with applicable Basic and Supplementary Sections of Part I when and to the extent specified by the organization invoking Subpart 2.18. Subpart 2.18 does not apply to controlling modifications which may be determined to be needed during the performance of maintenance.
2 GENERAL REQUIREMENTS 5.2.7 &#xb6;2 Maintenance and modification of equipment shall be      Design or modification information shall be available to the    NQA-1, Part II, preplanned and performed in accordance with written              operating organization so that it can review the adequacy of    Introduction, subsection 4.1 procedures, documented instructions or drawings appropriate to    provisions for the maintenance program in accordance with the  contains similar the circumstances which conform to applicable codes,              requirements of Subpart 2.18.                                  requirements regarding standards, specifications, and criteria.                                                                                          planning for maintenance activities.
2.1 Responsibilities
&sect;3.2 Assignment of Authority & Responsibility                    Responsibilities shall be assigned for establishing and        Similar requirement The owner organization shall specify in writing the authority    implementing the maintenance program. These responsibilities and responsibility assigned individuals and organizations        shall include:
involved in establishing, executing and measuring the overall    (a) the review of the maintenance program to ensure it effectiveness of the administrative controls and quality          considers changes to plant design or modifications; assurance program required by this Standard.                      (b) the development and updating of appropriate maintenance plans, procedures, and schedules; (c) the review of planned maintenance activities to ensure that radiation exposures to personnel will be as low as reasonably achievable; (d) the conduct of the program of maintenance activities and other inspections and tests as necessary to verify satisfactory performance; (e) the assurance that activities are performed by qualified personnel, using approved processes and calibrated test equipment and tools; (f) the assurance that properly controlled and identified materials are utilized; 10/28/2010                                                                    Maintenance                                                        Page I of 15
 
ANSI N18.7-19761ANS-3.2            .    .          Quai.ty Assurance Requirementsf*or Maintenance of                        COMMENTS Maintenance and Modification              .                                Nuclear Facilities
                              &sect;5..1                                                    NQA-I 1994 Subpart 2.18..                      ___*_______________,
(g) the assurance that environmental or seismic qualification requirements of equipment are not compromised; (h) the development of provisions for installation and removal of temporary conditions (e.g., jumpers, transferring of control switch position, etc.) and returning equipment and systems to service; (i) the recording of all maintenance examination and test results including corrective actions required and actions taken; (j) the assessment and evaluation of the results of maintenance, examinations, post-maintenance tests, and equipment history; (k) the development and trending of performance indicators; (1)the retention of records.
4                                                                  1 2.2 Procedures ANSI N18.7 &sect;2.2 Glossary of Terms                                  (a) Procedures and/or written instructions shall be established      The QAPD presents this maintenance and modification procedures. Written procedures        for performance of maintenance activities. Requirements for          ANSI N 18.7 information in defining the policies and practices by which structures;          procedure format and content shall be established. Additional        Part IH,Section 5 and 6 and mechanical, electrical and instrumentation and control systems;    guidance regarding procedural requirements are contained in          Part V, Section 3.
and components thereof of a nuclear power plant are kept in a      ANS 3.2.
condition of good repair or efficiency so that they are capable    (b) Checks shall be made to verify that:
of performing their intended functions. As used in this            (1) procedures and/or written instructions with an appropriate Standard, these procedures apply to those activities performed    level of detail have been provided; and by maintenance or contractor personnel to maintain, repair or      (2) procedures include applicable format and content elements.
modify safety-related equipment. Related activities are those      (c) All changes, including temporary changes, shall be actions taken by operating personnel to determine that a          controlled.
planned maintenance activity can be safely performed under the    (d) Provisions shall be made for documenting data to assist in existing plant operating conditions, to authorize the release of  ensuring satisfactory completion of the work. Such data shall equipment to be maintained in accordance with equipment            include, as applicable:
control procedures, and to assure that the equipment has been      (1) parts used (e.g., serial no., part no., lot no.)
returned to normal operating status at the completion of the      (2) identification number of measuring and test maintenance work including verification of functional              (3) "as found" condition acceptability. Procedures for these related activities by          (4) "as left" condition operating personnel are considered to be operating procedures,    (5) adjustments, repairs, replacements made equipment used but may be included in maintenance procedures.                    (6) post-maintenance clean-up and final inspection ANSI N18.7 &sect;5.2.7 &#xb6;2 Maintenance and Modifications                (7) post-maintenance testing and acceptance results.
Maintenance or modifications of equipment shall be preplanned and performed in accordance with written procedures, documented instructions or drawings appropriate to the Page 2 of 15 Maintenance Maintenance 10/28/2010 10/28/2010                                                                                                                                                  Page 2 of 15
 
ANSI N18.7-1976/ANS-3.2                        Quality Assurance Requirements for Maintenance of COMMENTS Maintenance and Modification                                      Nuclear Facilities
                              &sect;5.2.7                                          NQA-1 1994 Subpart 2.18,____________
circumstances which conform to applicable codes, standards, specifications, and criteria. Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineations in a written procedure.
ANSI N18.7 &sect;5.2.7.1 &#xb6;3 Maintenance Programs General rules for the development of procedures under a maintenance program which is consistent with the provisions of 5.2.7 shall be written before start-up. These general rules shall form the basis for developing the repair or replacement procedures at the time of failure. Procedures required for maintenance of equipment expected to require recurring maintenance should be written prior to plant operation. As experience is gained in operation of the plants routine maintenance should be altered to improve equipment performance, and procedures for repair of equipment shall be improved as appropriate. Approved procedures shall be available for repair of safety-related equipment prior to the performance of such repairs (see also Sections 5.2.2 and 5.2.7).
ANSI N18.7 &sect;5.2.7.1 &#xb6;5 Maintenance Programs A preventive maintenance program including procedures as appropriate for safety-related structures, systems and components shall be established and maintained which prescribes the frequency and type of maintenance to be performed. A preliminary program based on service conditions and experience with comparable equipment should be developed prior to fuel loading. The program should be revised and updated as experience is gained with the equipment.
ANSI N18.7 &sect;5.2.13.3 &#xb6;1 Identification and Control of Materials, Parts and Components. Measures shall be provided for the identification and control of materials, parts, and components including partially fabricated subassemblies.
These procedures shall be implemented to provide insurance that only correct and accepted items are used and installed, and relating an item of production (batch, lot, component, part) at any stage, from initial receipt through fabrication, installation, repair or modification, to an applicable drawing, specification, or other pertinent technical document. Physical identification                                                            Pae 3 f 1 10/2/2010                            Mintnanc 10/28/2010                                                                Maintenance                                    Page 3 of 15
 
ANSI N18.7'1976/ANS-3.2                      Quality Assurance Requirements for Maintenance of COMMENTS Maintenance and Modification                                      Nuclear Facilities
                              &sect;5.2.7                    ,1994                NQA...1        bpart.2..,0 shall be used to the maximum extent possible. Where physical identification is either impractical or insufficient, physical separation, procedural control or other appropriate means shall be employed. Identification may be either on the item or on records traceable to the item, as appropriate.
ANSI N18.7 &sect;5.2.15 &#xb6;1 Review, Approval and Control of Procedures. The administrative controls and quality assurance program shall provide measures to control and coordinate the approval and issuance of documents, including changes thereto, which prescribe all activities affecting quality. Such documents include those which describe organizational interfaces, or which prescribe activities affecting safety-related structures, systems, or components. These documents also include operating and special orders, operating procedures, test procedures, equipment control procedures, maintenance or modification procedures, refueling, and material control procedures.
ANSI N18.7 &sect;5.3.5 Maintenance Procedures. Maintenance procedures shall contain applicable items listed under 5.3.2 and, in addition, measures to cover the features of maintenance described below.
(1) Preparation for Maintenance. Maintenance procedures shall reflect considerations listed under 5.2.6.
Adherence to applicable radiation protection measures shall be prescribed. These measures shall specify protective clothing and radiation monitoring needed to assure safety.
(2) Performance of Maintenance. The procedures shall contain enough detail to permit the maintenance work to be performed correctly and safely, and shall include provisions for conducting and recording results of required tests and inspections. References should be made to vendor manuals, plant procedures, drawings and other sources as applicable.
(3) Post Maintenance Check Out and Return to Service.
Instructions shall be included, or referenced, for returning the equipment to its normal operating status.
(4) Supporting Maintenance Documents. Where appropriate sections of related documents, such as vendor 10/28/2010                                                              Maintenance                                    Page 4 of 15
 
ANSI NIS.7-1976/ANS-3.2                      Quality Assurance Requirements for Main~eance of COMLM*NTS Maintenance and Modiflcation                                      Nuclear Fa~cilities
                              &sect;5.2.7                      .QA-I                      1994 Subpart.18 .....        _._."_"___'_'        _"__
manuals, equipment operating and maintenance instructions, or approved drawings with acceptance criteria provide adequate instructions to assure the required quality of work, the applicable sections of the related documents shall be referenced in the procedure, or may, in some cases, constitute adequate procedures in themselves. Such procedures shall receive the same level of review and approval as operating procedures.
ANSI N18.7 &sect;5.3.10 Test and Inspection Procedures. Test and inspection procedures shall contain a description of objectives; acceptance criteria that will be used to evaluate the results; prerequisites for performing the tests or inspections including any special conditions to be used to simulate normal or abnormal operating conditions; limiting conditions; and the test or inspection procedure. These procedures shall also specify any special equipment or calibrations required to conduct the test or inspection. Test and inspection results shall be documented and evaluated by responsible authority to assure that test and inspection requirements have been satisfied.
Where tests and inspections are to be witnessed, the procedure shall identify hold points in the testing sequence to permit witnessing. The procedure shall require appropriate approval for the work to continue beyond the designated hold point. The test and inspection procedures shall require recording the date, identification of those performing the test or inspection, as-found condition, corrective actions performed, if any, and as-left condition.
ANSI N18.7 &sect;5.2.6 &#xb6;6 Equipment Control When equipment is ready to be returned to service, operating personnel shall place the equipment in operation and verify and document its functional acceptability. Attention shall be given to restoration of normal conditions, such as removal ofjumpers or signals used in maintenance or testing or such as returning valves, breakers or switches to proper start-up or operating positions from "test" or "manual" positions. When placed into service, the equipment should receive additional surveillance during the run-in period.
ANSI N18.7 .5.2.10 &#xb6;2 Housekeeping &Cleanliness Control Page 5 of 15 Maintenance 10/28/2010 10/28/2010                                                              Maintenance                                            Page 5 of 15
 
SI N18.71976/AuS-3,y"As.su**,QuatyAsrance AN"""".                                                  Requirements for Maintenance of          COMMENTS Maintenance and Modification                              Nuclear Facilities.
15.2.7                                  'NQA-1  1994 Subpart.2.18            ___________
Where necessary, procedures and work instructions needed to assure compliance with specific requirements shall be available; e.g., inspection and cleaning of electrical bus and control centers, cleaning of control consoles, radioactive decontamination. Particular attention should be given to housekeeping in work and storage areas where important items are handled and stored to preclude damage or contamination.
American National Standard Housekeeping During the Construction Phase of Nuclear Power Plants, N-45.2.3-1973
[ 12] shall be applied to those activities occurring during the operational phase that are comparable in nature and extent to related activities occurring during construction.
ANSI N18.7 &sect;5.2.10 &#xb6;3 Housekeeping &Cleanliness Control During maintenance or modification activities, certain portions of safety-related systems may be subject to potential contamination with foreign materials. To prevent such contamination, control measures, including measures for access control, shall be established. Immediately prior to closure an inspection shall be conducted to assure cleanness and the result of such inspection shall be documented. American National Standard Cleaning of Fluid Systems and Associated Components during Construction Phase of Nuclear Power Plant N45.2.1-1973 [13] shall be applied to activities occurring during the operational phase that are comparable in nature and extent to related activities occurring during construction.
Measures for minimizing the introduction of foreign materials during maintenance or modification, or cleaning following maintenance or modification of radioactively contaminated systems or of equipment of high radiation fields require special consideration.
ANSI N18.7 &sect;5.2.19 &#xb6; Test Control A test program shall be established to assure that testing required to demonstrate that the item will perform satisfactorily in service is identified and documented, and that the testing is performed in accordance with written test procedures which incorporate or reference the requirements and acceptance limits contained in applicable design documents. The test program shall cover all required Page 6 of 15 Maintenance 10/28/2010 10/28/2010                                                        Maintenance                                              Page 6 of 15
 
teANSe andModificatiNS&#xfd;                          Qulty As~surance Requirements for Maintenance ofCMMENTS-
            * . .. * .. Maintenance
                        ,*&sect;5.*.    .Q... . 7          **: .,.,::.,..... ..                        ...AN- 1. 1nd9uclea 1..&#xfd;9. $q-p  r    18 **it arodification 2.18..
tests including:
(4) Tests during design, fabrication and construction activities associated with plant maintenance and modifications during the operational phase and the demonstration of satisfactory performance following plant maintenance and modifications or procedural changes (see Section 5.2.7).
ANSI N18.7 &sect;5.2.19.3 &#xb6; Test Control Tests Associated with Plant Maintenance, Modifications or Procedure Changes. Tests shall be performed following plant modifications or significant change in operating procedures to confirm that the modifications or changes reasonably produce expected results and that the change does not reduce safety of operation.
* 4.
ANSI N18.7 &sect;5.2.17 &#xb6; 4 Inspections                                            Recorded data shall be reviewed for completeness and            Similar requirement Inspections of safety-related activities shall be performed in                acceptability. The review shall be conducted by personnel who accordance with approved written procedures, which set forth                  are familiar with the design and operation of the equipment, the requirements and acceptance limits and specify the                        including acceptance criteria for its design features and inspection responsibilities.                                                  operating characteristics. Administrative procedures shall ANSI N18.7 &sect;5.2.17 &#xb6; 6 Inspections                                          require documentation of the acceptance of results The owner organization shall evaluate inspection results along with test results (see Section 5.2.19) to determine whether the individual inspection and test programs demonstrate that the plant can be operated safely and as designed. Records shall be kept in sufficient detail to permit adequate confirmation of the inspection program. The person recording the data as well as the person approving the inspection results shall be identified.
Deviations, their cause, and any corrective action completed or planned as a result of the deviations shall be documented.
Inspection records shall be identified as such and shall be retrievable (see also Section 5.2.12).
ANSI N18.7 &sect;5.2.19 &#xb6; 1 Test Control A test program shall be established to assure that testing required to demonstrate that the item will perform satisfactorily in service is identified and documented, and that the testing is performed in accordance with written test procedures which incorporate or reference the requirements and acceptance limits contained in applicable design documents.
Page 7 of 15 Maintenance 10/28/2010 10/28/2010                                                                                Maintenance                                                        Page 7 of 15
 
                    ,ANSI N18.7-1976/ANS-3.2                              Quality Assurance Requirements for Maintenance of                            COMMENTS
                                          *  ~~~...
Miaintenance and Modification      ..................................................
Nuclear Facilities.,... ................. =..      ... . ***,.*..=...    *.  *.
                              &sect;5.2.7                                                      NQA-11994 Subpart 2.180____________
ANSI N18.7 &sect;5.3.10 &#xb6; 1 Test & Inspection Procedures Test and inspection procedures shall contain a description of objectives; acceptance criteria that will be used to evaluate the results; prerequisites for performing the tests or inspections including any special conditions to be used to simulate normal or abnormal operating conditions; limiting conditions; and the test or inspection procedure. These procedures shall also specify any special equipment or calibrations required to conduct the test or inspection. Test and inspection results shall be documented and evaluated by responsible authority to assure that test and inspection requirements have been satisfied.
ANSI N18.7 &sect;5.3.10 &#xb6; 2 Test & Inspection Procedures The test and inspection procedures shall require recording the date, identification of those performing the test or inspection, as-found condition, corrective actions performed, if any, and as-left condition.
ANSI N18.7 &sect;5.3.5 &#xb6; 2 Maintenance Procedures (2) Performance of Maintenance. The procedures shall contain enough detail to permit the maintenance work to be performed correctly and safely, and shall include provisions for conducting and recording results of reauired tests and insnections.            4                                                                        +
4 2.3 Cleanness Control                                                  +
ANSI N18.7 &sect;5.2.10 &#xb6;3 Housekeeping & Cleanliness Control              (a) Controls to minimize the introduction of foreign materials            Similar requirement During maintenance or modification activities, certain portions        and to maintain cleanness during maintenance shall be in of safety-related systems may be subject to potential                  accordance with Subpart 2.1 of this Part (Part Il). Verification contamination with foreign materials. To prevent such                  methods shall be established to ensure these requirements are contamination, control measures, including measures for access        met.
control, shall be established. Immediately prior to closure an        (b) Immediately prior to closure of equipment, the absence of inspection shall be conducted to assure cleanness and the result      foreign materials shall be verified. The results of the of such inspection shall be documented. American National              verification shall be documented.
Standard Cleaning of Fluid Systems and Associated Components during Construction Phase of Nuclear Power Plant N45.2.1-1973 [13] shall be applied to activities occurring during the operational phase that are comparable in nature and extent to related activities occurring during construction.
Measures for minimizing the introduction of foreign materials during maintenance or modification, or cleaning following                                                                                    .5.                  Page 8 of 15 10/28/2010                                                                        Maintenance                                                                      Page 8 of 15
 
ANSI N1S.7-1976/ANS-3.2                            Quality Assurance Requirements for Maintenance of                  CO1.I.OTS Maintenance and Modification                                              Nucea failities
                              &sect;5.2.7                                                  NQA-1 1994 Subpari'2.18 maintenance or modification of radioactively contaminated systems or of equipment of high radiation fields require special consideration.
ANSI N18.7 &sect;5.3.5 &#xb6; 2 Maintenance Procedures (2) Performance of Maintenance. The procedures shall contain enough detail to permit the maintenance work to be performed correctly and safely, and shall include provisions for conducting and recording results of required tests and inspections.
2.4 Environmental and Seismic Qualifications Procedures shall be established to ensure that environmental      New requirement.
and/or seismic qualification of equipment is not voided in        Also, addressed in Part V, performing maintenance. Such procedures shall include            Section 3 of the QAPD.
identification of the qualified items, methods for reestablishing qualifications, and verification of qualification status.
2.5 Work Authorization ANSI N18.7 &sect;5.2.6 &#xb6;1 Equipment Control                            (a) Procedures shall be established for the authorization of      Similar requirement.
Permission to release equipment or systems for maintenance        maintenance work. The work authorization shall be documented      Also, addressed in Part V, shall be granted by designated operating personnel. Prior to      and serve as the identification of authorized work for the        Section 3 of the QAPD.
granting permission, such operating personnel shall verify that  purposes of work planning, scheduling, and control.
the equipment or system can be released, and determine how        (b) The work authorization shall contain the following long it may be out of service. Granting of such permission shall information as a minimum:
be documented.                                                    (1) unique work authorization identifier or number ANSI N18.7 &sect;5.2.6 &#xb6;3 Equipment Control                            (2) description of work, including identification and quality Conditions to be considered in preparing equipment for            designation of the specific equipment on which the work is to maintenance include, for example: shutdown margin; method of be performed emergency core cooling; establishment of a path for decay heat    (3) identification of performing organizations and their specific removal; temperature and pressure of the system; valves          roles between work and hazardous material; venting, draining and        (4) approval by authorized personnel flushing; entry into closed vessels; hazardous atmospheres;      (c) Interface concerns such as plant operations, health handling hazardous materials; and electrical hazards.            physics/ALARA, security, industrial safety, effluent control, ANSI N18.7 &sect;5.3.5 &#xb6; 2 Maintenance Procedures                      fire protection and quality control requirements shall be (2) Performance of Maintenance. The procedures shall contain      considered for applicability by authorized individuals prior to enough detail to permit the maintenance work to be performed      approval of the work authorization document.
correctly and safely, and shall include provisions for conducting (d) The description of work shall reference the applicable and recording results of required tests and inspections,          maintenance procedure(s). If a separate procedure is not References should be made to vendor manuals, plant                required, the work authorization shall contain or reference procedures, drawings and other sources as applicable.            necessary and sufficient information (design drawings, 10/28/2010                                                                    Maintenance                                                          Page 9 of 15
 
ANSI N18.7-1976/ANS-3.2                          Quality Assuranlce Requirements for Maintenanceof                    COM*ENTS
                . Maintenance and Modification                                            Nuclear Facilities
                              &sect;5.2.7                                                NQA-1l 1994 Subpart 2.18 equipment manuals, etc.) to perform the work.
(e) Provision shall be made for verifying the completeness of work authorization documents prior to starting the maintenance work.
(f) The work authorization approval process shall provide for approving substantive changes in the work requirements commensurate with the original scope of work.
2.6 Equipment History A system shall be established to identify equipment for which      Similar requirement equipment history files shall be maintained. Files shall be established as early in the life of equipment as possible to maintain the history of maintenance activities on each specific item. Information to be entered in the files shall be specifically identified and mechanisms established for their incorporation into the files, The files shall be organized to facilitate information retrieval.
2.7 Verification of Maintenance Work ANSI N18.7 &sect;5.2.19 &#xb6; 5Test Control                              Verification shall be performed, as appropriate, to ensure that    ANSI N18.7 includes The test program shall cover all required tests including:      equipment on which maintenance has been performed conforms        procedural changes; which (4) Tests during design, fabrication and construction activities to specified requirements. This verification shall include        are addressed in associated with plant maintenance and modifications during the  inspection, testing, or document review as necessary.              implementing procedures.
operational phase and the demonstration of satisfactory          Documentation of verification activities shall be in accordance performance following plant maintenance and modifications or    with Section 2.2 of Subpart 2.1 8.
procedural changes (see Section 5.2.7).
ANSI N18.7 &sect;5.2.19.3 Tests Associated with Plant                When maintenance involves installation, inspection shall be Maintenance, Modifications or Procedure Changes                  conducted in accordance with the applicable elements defined Tests shall be performed following plant modifications or        in Subparts 2.4, 2.5, and 2.8 of this Part (Part II).
significant change in operating procedures to confirm that the modifications or changes reasonably produce expected results and that the change does not reduce safety of operation.
2.8 Updating of Maintenance Procedures from Vendor Technical Manuals and Industry Bulletins Controls shall ensure that updated information, (vendor technical manuals, industry bulletins, etc.) is received, reviewed, and incorporated where appropriate into maintenance procedures.
10/2 8/2 010                                                                  Maintenance                                                          Page 10 of 15
 
NS.F.,                          .              Quality Assurance Requirements for Maintenance of.....              COMMENS
            . Maintenance and Modification                                            Nuclear Facilities
                                            &sect;5.                                  4Q.A-i1994 ubpart 2:18 3 PREVENTIVE MAINTENANCE 3.1 General ANSI N18.7 &sect;5.2.7.1 &#xb6; 4 Maintenance Programs                  Preventive maintenance includes all those activities performed    ANSI N18.7 provides A preventive maintenance program including procedures as      on designated equipment needed to maintain it within specified    additional guidance for appropriate for safety-related structures, systems and        design limits.                                                    transitioning from components shall be established and maintained which                                                                            construction / pre-prescribes the frequency and type of maintenance to be                                                                          operations to the performed. A preliminary program based on service conditions                                                                    operational phase.
and experience with comparable equipment should be                                                                              Also addressed in Part V, developed prior to fuel loading. The program should be revised                                                                  Section V of the QAPD.
and updated as experience is gained with the equipment.
3.2 Plans and Procedures ANSI N18.7 &sect;5.2.7.1 &#xb6; 4 Maintenance Programs                  Plans and procedures shall be developed to identify the          Similar requirement A preventive maintenance program including procedures as      equipment which requires preventive maintenance, to establish appropriate for safety-related structures, systems and        the frequency and kind of preventive maintenance to be components shall be established and maintained which          performed on the equipment, and to document those actions.
prescribes the frequency and type of maintenance to be performed.
3.2.1 Equipment.
Equipment shall be evaluated to determine its preventive          This Subpart 2.18 maintenance requirements. That evaluation shall include the      requirement is similar for vendor recommendations as delineated in their Technical          ANSI N18.7 &sect;5.2.7.1 Manual and Bulletins, applicable industry standards and operational experience, and maintenance experience and equipment history files.
Equipment shall be monitored and evaluated for degradation of performance because of age, as appropriate. Equipment which is purchased for future installation or spares shall be evaluated to determine the preventive maintenance requirements associated with its storage.
3.2.2 Frequency.
A preventive maintenance schedule shall be established to        This Subpart 2.18 uniquely identify the equipment, frequency, and preventive        requirement is similar for maintenance to be performed.                                      ANSI N 18.7 &sect;5.2.7.1 10/28/2010                                                                Maintenance                                                          Page I I of 15
 
ANSI N18.7-1976.AN.-3.2                          Quality Assurance Requirements for Maintenance of                    COMMENTS Maintenance and Modification                                            Nuclear Facilities
                                &sect;5..2.7                                              N, A-I 19"4 Subpart 2.18
_________________________________________3.2.3      Evaluation.
ANSI N18.7 &sect;5.2.7.11&#xb6;5 Maintenance Programs                      The effectiveness of preventive maintenance actions on            ANSI N 18.7 &sect;5.2.7.1 &#xb6;5 The causes of malfunctions shall be promptly determined,        equipment shall be evaluated. The evaluation results shall be    similar to Subpart 2.18 evaluated and recorded (see also Sections 4.3 and 4.4).          documented and be the basis for future preventive maintenance    Sections 3.2.3 and 3.2.4.
Experience with the malfunctioning equipment and similar        practices.
components shall be reviewed and evaluated to determine whether a replacement component of the same type can be expected to perform its function reliably. If evidence indicates that common components in safety-related systems have performed unsatisfactorily, corrective measures shall be planned prior to replacement or repair of all such components 3.2.4 Corrective Action.
When discrepancies or failures are identified as part of          ANSI N18.7 &sect;5.2.7.1 &#xb6; 5 preventive maintenance activities, they shall be corrected in    similar to Subpart 2.18 accordance with Section 4.0 of Subpart 2.18.                      Sections 3.2.3 and 3.2.4.
ANSI N18.7 &sect;5.2.7.1    &#xb6; 5 Maintenance Programs                4 CORRECTIVE MAINTENANCE                                          The attributes of NQA-I If evidence indicates that common components in safety-related  4.1 General                                                      Subpart 2.18 Section 4 are systems have performed unsatisfactorily, corrective measures    The following requirements apply to maintenance performed to      similar to ANSI NI18.7 shall be planned prior to replacement or repair of all such      restore an item to an intended condition following failure of the requirements for components.                                                      item. The term "failure," as used herein, applies to any          Maintenance Programs.
condition where an item is determined to be unable to perform within its specified limits.
4.2 Identification, Reporting, and Documenting of Equipment or Systems Requiring Corrective Maintenance ANSI N18.7 &sect;5.2.14    &#xb6; 5 Nonconforming Items                  Procedures shall be established for:                              Similar requirement Measures shall be provided to control items, services or        (a) promptly identifying (e.g., tagging or other physical activities which do not conform to requirements (see also        marking) the failed item and controlling it to preclude its Section 5.2.6). These procedures shall include as appropriate,  inadvertent use; instructions for identification, documentation, segregation,    (b) documenting and reporting of failures, in accordance with disposition and notification to affected organizations.          pre-established criteria, to:
Nonconforming items shall be reviewed and accepted, rejected,    (1) designated levels of management responsible for failure repaired or reworked in accordance with documented              analyses, authorization of corrective action, and performance of procedures. The responsibility and authority for the disposition corrective action; of nonconforming items shall be defined. Repaired and            (2) supplier and/or regulatory authority, as required.
reworked items shall be reinspected in accordance with          (c) entering the failure and the attributed cause in equipment applicable procedures.                                          history records 10/28/2010                                                                  Maintenance                                                          Page 12 of 15
 
ANSI N18.7-1976/ANS32                  .        Quality Assurance Requirements for Maintenance of            . COMMENTS Maintenance and..Modification                                            Nucear Facilities
                              &sect;5.2.7                                                NQA-141994 Subpirt 2.18:
Measures which control further processing, delivery or        (d) verifying that failures are appropriately identified and installation of a nonconforming or defective item pending a      reported as prescribed above to the extent necessary to assure decision on its disposition shall be established and maintained, appropriate attention.
Nonconforming items may be disposed of by acceptance "as is,"
by scrapping or repairing the defective item, or by rework to complete or correct to a drawing or specification. Such measures shall provide assurance that the item is identified as nonconforming and controlled. The measures shall require documentation verifying the acceptability of nonconforming items which have the disposition of "repair" or "use as is." A description of the change, waiver or deviation that has been accepted shall be documented to record the change and denote the as-built condition.
As a guideline, control of nonconforming items by tagging, marking or other means of identification is acceptable where physical segregation is not practical, although physical segregation and marking are preferred.
4.3 Assessments and Evaluations 4.3.1 Assessment.
ANSI N18.7 &sect;5.2.7.1 &#xb6; 5 Maintenance Programs                    An assessment of failure cause and required maintenance shall  Similar requirement The causes of malfunctions shall be promptly determined,        be made consistent with the type of item failure and the evaluated and recorded (see also Sections 4.3 and 4.4).          importance of the item. The assessment shall also include, as Experience with the malfunctioning equipment and similar        appropriate, the possibility of similar failure in other items.
components shall be reviewed and evaluated to determine          Assessments shall be performed in accordance with whether a replacement component of the same type can be          documented procedures and shall be appropriately reviewed.
expected to perform its function reliably. If evidence indicates that common components in safety-related systems have performed unsatisfactorily, corrective measures shall be planned prior to replacement or repair of all such components.
Replacement components should have received adequate testing or should be of a design for which experience indicates a high probability of satisfactory performance. Consideration shall be given to phased replacement to permit inservice performance of the new component to be evaluated and thereby minimize the possibility of a hidden deficiency producing a systematic failure. An augmented testing and inspection program should be 10/28/2010                                                                  Maintenance                                                        Page 13 of 15
 
ANSI NI8.7-1976/ANS-3.2                            Quality Assurance Requirements for Maintenance of                    COMME.NTS Maintenance and M-odification                                      ..... Nuclear: Facilities
                                                                  &sect;5.2.7..
                                                                  .... ,........ ......        1994 Subpart 2.18 implemented following a large scale component replacement (or repair) until such time as a suitable level of performance has been demonstrated.
4.3.2 Engineering Evaluation.
ANSI N18.7 &sect;5.2.11 &#xb6; 1 Corrective Action                          For failures identified that could have serious effect on safety or Similar requirement The program shall provide measures to ensure that conditions      operability, an engineering evaluation shall be performed and adverse to plant safety, such as failure, malfunctions,            documented to substantiate or revise the failure assessment and deficiencies, deviations, defective material and equipment,        corrective action planning.
abnormal occurrences, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to safety, the measures shall assure that the cause of the condition is determined and corrective action taken shall be documented and reported to appropriate levels of management and for independent review in accordance with Section 4.3.
4.4 Implementing Corrective Maintenance ANSI N18.7 &sect;2.2 Definitions                                        4.4.1 Corrective maintenance shall be performed utilizing work      Similar requirement maintenance and modification procedures. Written procedures        procedures developed in accordance with para. 2.2 of Subpart defining the policies and practices by which structures;          2.18.
mechanical, electrical and instrumentation and control systems; and components thereof of a nuclear power plant are kept in a condition of good repair or efficiency so that they are capable of performing their intended functions. As used in this Standard, these procedures apply to those activities performed by maintenance or contractor personnel to maintain, repair or modify safety-related equipment.
4.4.2 Provisions shall be made for emergency maintenance            New requirement work, e.g., work that must be performed immediately to eliminate a threat to the safety of personnel or facilities. These provisions shall be documented to identify:
(1) the minimum controls applicable to the authorization, planning, and performance of the work; and (2) requirements to assure effective accomplishment of the work. Emergency work shall be reviewed and evaluated immediately after work accomplishment for adequacy.
5  RECORDS ANSI N18.7 &sect;5.2.12. Plants Records Management.                    (a) Maintenance records shall be maintained to establish an        NQA-1 Subpart 2.18 Provisions shall be made for preparation and retention of plant    equipment history (reference paras. 2.2 and 2.6) and assist in      provides additional 10/28/2010                                                                      Maintenance                                                          Page 14 of 15
 
ANSI NlS.7-1976/ANS-3.2                          Quality Assurance Requirements for Maintenance of                  COMMENTS M"aintenance and.Modification...                                        Nuclear.ciities
                              &sect;5.2.7                                                NQA-I 1994 S~ubpart 2.18___________
records as appropriate. The responsibility for maintaining      performance evaluation and trend analysis. Maintenance          requirements above records and storing them at a specified location or locations    records shall include work authorization documents and shall    retention and storage.
shall be assigned. Retention periods of sufficient duration to  identify the equipment, type of maintenance performed, tools, assure the ability to reconstruct significant events and satisfy measuring and test equipment, parts and material, date of any statutory requirements which apply shall be specified.      performance, observation, failure cause, post maintenance American National Standard Requirements for Collection,          testing results, and who performed the maintenance.
Storage and Maintenance of Quality Assurance Records for        (b) Records shall be maintained in accordance with Part 1, Basic Nuclear Power Plants, N45.2.9-1974, shall be used for            Requirement 17 and Supplement 17s-1.
management of plant records during the operational phase [ 14].
10/28/2010                                                                    Maintenance                                                        Page 15 of 15
 
Document Control Desk Attachment VI CR-1 0-03108 RC-1 1-0006 Page 1 of 33 ATTACHMENT VI PROPOSED REVISIONS TO THE FSAR
 
ASME NQA-1 -1994 CONVERSION PROCESS FSAR CHAPTER 3, APPENDIX 3A RevIsions Insert #11 1.28          QUALITY ASSURANCE PROGRAM REQUIREMENTS (DESIGN AND CONSTRUCTION) (REVISION 3: 8/85)
The Virgil C. Summer Nuclear Station commits to Regulatory Position C.2 and Table 1:
only, along with NQA-1-1994 Basic Requirement 17 and Supplementary Requirement 17S,1 for quality assurance record types and retention requirements.
Insert #2 1.30          QUALITY ASSURANCE REQUIREMENTS FOR THE INSTALLATION.
INSPECTION, AND TESTING OF INSTRUMENTS AND ELECTRICAL.:
EQUIPMENT (REVISION 0: 8/72)
Delete commitment. The Virgil C. Summer Nuclear Station commitment to RG 1.30 is no longer needed with the adoption of NQA-1-1994 Subpart 2.4. NQA-1-1994 Subpart 2.4 is equivalent to the requirements of ANSI N45.2.4-1972.
Insert #3T,.
1.33'.        QUALITY ASSURANCE PROGRAM REQUIREMENTS (OPERATION)::
(REVISION 2: 2/78)
Delete commitment. The Virgil: C. Summer Nuclear Station commitment to RG 1.33 is no longer required .with the adoption of NQA-1 -1994 and the QAPD developed under.
the guidance. of NEI 06-1.4A Rev. 7, August 2010. NQA-1 -1994 and QAPD are.
equivalent to the requirements of ANSI N1 8.7-1976 and RG 1.33 Rev. 2, .2/78:.
Insert #4 1.38          QUALITY ASSURANCE REQUIREMENTS FOR PACKAGING-.
SHIPPING. RECEIVING, STORAGE, AND HANDLING OF ITEMS: FOR.:
WATER-COOLED NUCLEAR POWER PLANTS (REVISION 0: 3/73)
Delete commitment. The Virgil C. Summer Nuclear Station commitment to RG 1.38. is.:"
no longer needed with the adoption of NQA-1-1994 Subpart 2.2. NQA-1-1994 Subpart.
2.2 is. equivalent to the requirements of ANSI N45.2.2-1 973...
Insert #5 1.39          HOUSEKEEPING REQUIREMENTS FOR WATER-COOLED NUCLEAR POWER PLANTS (REVISION 2, 9/77)
Delete commitment. The Virgil C. Summer Nuclear.Station commitment to RG 1.39 is no longer required with the adoption of NQA-1 -1994ZSubpart 2.3. NQA-1 -1994 Subpart:
2.3 is equivalent to the requirements of ANSI N45.2.3-1973.
 
Insert #6 1.58:          QUALIFICATION: OF NUCLEAR POWER PLANT INSPECTION..
EXAMINATION. AND TESTING PERSONNEL (REVISION. 1: 9/80)
Delete commitment. RG. 1.58 has been withdrawn. The requirements. of NQA-1-1994......
Basic Requirement 2, Supplementary Requirement 2S.1, Supplementary Requirement%..
2S-2, and Appendix 2A-1, are equivalent to.the requirements: of ANSI N45.2.6-1.978.
Insert.#7..
1.64          QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF:
NUCLEAR POWER PLANTS (REVISION 2: 6/76).
Delete commitment. RG 1.64 has been withdrawn. The requirements of NQA-1 -1994 Basic Requirement 3, Supplementary Requirement 3S.1, are equivalent to the requirements of ANSI N45.2.11-1974 and R.G. 1.64.
Insert #8.
1.74          QUALITY ASSURANCE TERMS AND.DEFINITIONS (REVISION 0: 2/74).
Delete commitment.-. RG 1.74 has been withdrawn. With the adoption of NQA-1 -1994.:
Part I "Introduction" defining terms and, definitions ANSI.. N45.2.10-1973 is no !onger needed...-
Insert #9:
1.88.          COLLECTION, STORAGE,. AND MAINTENANCE OF NUCLEAR POWER PLANT QUALITY ASSURANCE RECORDS (REVISION 2:10/76)
Delete commitment. RG 1.88 has been withdrawn. The, adoption of NQA-1 -1994 Basic Requirement 17, Supplementary Requirement: 17S-1, and: commitment to &#xfd;R.G. 1.28.....
Rev. 3, Regulatory Position C.2 contain the. requirements for quality assurance: records.
and replaces ANSI N45.2.9-1974 and RG .1.88 Insert #10 1.94            QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION.
INSPECTION, AND TESTING OF STRUCTURAL CONCRETE AND STRUCTURAL STEEL DURING THE CONSTRUCTION PHASE OF
:NUCLEAR POWER PLANTS (REVISION 1: 4/76)
Delete: commitment. The Virgil C. Summer Nuclear Station: commitment to RG 1.94 is:
no longer required with the adoption of NQA-1 -1994 Subpart 2.5.. NQA-1 -1994 Subpart...
2.5 is equivalent to the requirements of ANSI N45.2.5 - 1974.
 
Insert #11.
1.116          QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION.,:
INSPECTION, AND TESTING OF MECHANICAL EQUIPMENT AND.
SYSTEMS (REVISION O-R: 6/76)
Delete commitment. The Virgil C. Summer Nuclear Station commitment-to RG 1:.116 is no longer required with the adoption of NQA-1-1994 Subpart 2.8.; NQA-1 -1994 Subpart 2.8 is equivalent to the requirements of ANSI N45.2.8 -, 1975.:
Insert. #12 1.123          QUALITY ASSURANCE REQUIREMENTS FOR CONTROL OF PROCUREMENT OF ITEMS AND SERVICES FOR: NUCLEAR POWER PLANTS (REVISION 1: 7/771 Delete: commitment. RG 1.123 has been withdrawn. NQA-1-1994 Basic Requirement 7 and SupplementaryRequirement 7S-1 replaces the commitment to RG 1.123 and ANSI N45.2.13..
Insert #13 1.144          AUDITING OF QUALITY ASSURANCE PROGRAMS FOR NUCLEAR POWER PLANTS (REVISION 0:' 1/79)
Delete commitment. RG 1.144 has been withdrawn.: The requirements of NQA-1-1994.
Basic Requirements 7 and 18: and Supplementary Requirements 7S-1 and 18S-1 are..
adequate alternatives to the requirements of ANSI N45.2.12-1979 and R.G. 1.144.
Insert #14:
1.146          QUALIFICATION OF QUALITY ASSURANCE PROGRAM AUDIT PERSONNEL FOR NUCLEAR POWER PLANTS (REVISION 0: 8/80)
Delete commitment. RG 1.146 has been withdrawn. The requirements of NQA-1-1994 Basic Requirement 2: and Supplementary Requirement 2S-3 are adequate alternatives to the requirements of ANSI N45.2.23-1978 and R.G. 1.1464%..
Insert #15.
1.37.          QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF FLUID SYSTEMS AND ASSOCIATED COMPONENTS OF WATER-COOLED::
NUCLEAR POWER PLANTS (REVISION 1.03/2007)
Site procedures for the operational phase meet the requirements of ASME NQA  1994, Part II, Subpart 2.1 and this guide.
 
1.26          QUALITY GROUP CLASSIFICATION AND STANDARDS FOR WATER.,
STEAM. AND RADIOACTIVE-WASTE-CONTAINING COMPONENTS 0F NUCLEAR POWER PLANTS (REVISION 3: 2/76)
Quality groups classification of fluid system: equipment for the Virgil C. Summer Nuclear Station is described in Section 3.2.2.
Nuclear Steam Supply System fluid system components important to safety are:...
classified in accordance with the August 1970 Draft of ANSI N18.2. "Nuclear Safety:
Criteria for the Design of Stationary Pressurized Water Reactor Plants" except that components of the accumulator subsystem are classified in accordance with the: 1973 version of N18.2, as finally accepted by ANSI, and components of the :Liquid and::
Gaseous Waste Processing Systems and the Boron Recycle System are classified in accordance with Regulatory Guide 1.143.
Classification by this means is an alternative acceptable method of meeting the intent of Regulatory Guide 1.26.
1.27          ULTIMATE HEAT SINK FOR NUCLEAR POWER PLANTS..
(REVISION 2: 1/76).
The Virgil C. Summer Nuclear Station complies with the recommendations of Regulatory Guide, 1.27. The transient and thermal-hydraulic.model analyses:of the service water pond satisfy the changes noted in this: guide.
The details of our analyses and design bases can be found in Sections 2.4.8 and 9.2.5:
and V..C. Summer Technical Report, TR 02230-014, "Service Water Pond Thermal Study," dated June, 2000.::                                                                    0%0 1.28          QUALITY ASSURANCE PROGRAM REQUIREMENTS (DESIGN AND CONSTRUCTION) (REVISION G'/53    9.        .3;        '.
The.Virgil C. Summer Nuclear Station complies with the recommendations of this guide as described in Section:17.1 and as discussed below.
D*  7r rV&#xfd;V          noted that the commitments concern safety related equipment; the:
    .me
  #1 Nulea Staio take mportance of Malfunction or aiem ete  inecoA~relailt of= the Virgil
                                                                          .bu rqien C.
on or Failure of the Item to Plant Reliability.*
3A-13                          Reformatted Per Amendmentr  -,.O-
 
1.29            12 SEISMIC* DESIGN CLASSIFICATION (REVISION 2: FOR Seismic classification of structures, systems, and components for the Virgil C. Summer:
Nuclear Station is as described In Sections 3.21 and 3.8.
The classification of components by safety dcass provides the means of establishing:.
applicable a, seismic design requirements of both components and systems. At.the time the Virgil C. Summer Nuclear Station was: desgned, duplication by special seismic ....
classification was unnecessary since American National Standard (ANSI) NI 8.2 was considered to establish seismic design requirements of: systems having components classified as Safety Class 1, Safety Class 2, or Safety Class 3. The structures%.
described in Section 3.8 are classified as Seismic Category I.:
Classification by this means Is an alternate acceptable method.of meeting.the intent of Regulatory Guide 1.29, since the design construction and quality assurance provided fulfill the recommendations of Regulatory Guide 1.29...
1.30            QUALITY ASSURANCE REQUIREMENTS FOR THE INSTALLATION.
INSPECTION. AND TESITNG OF INSTRUMENTS AND ELECTRICAL EQUIPMENT (REVISION 0: 8f72)
OEA1F7z-.: 'VWjOC. Summer Nuclear Station complies with the recommendations of Regule                  jr-&#xfd; A04f      Guide:                Ity assurance programs are described: In Chapter 17.
For clarification of the as                scope In regard to..      tory Guide 1.30 the..%......
following is provided.....
For time Westinghouse activid                      after            1 1972, Westinghouse..
follows the guidance o&f                Guide 130. For those es                activities        I:
performed                      ber 1, 1972, the Westinghouse Quality Assu                  uret emp                design of the Virgil C. Summer Nuclear Station may vary in d shich of R                                *111s POWN 1.31            CONTROL OF STAINLESS STEEL WELDING (REVISION 1: 6/73) 1*. Welding Under Daniel's Scope, Reulatorv" Position          Compliance.
l.a.        Procedures are qualified with filler metal containing 5-12% delta ferrite.
Procedure qualification tests, are examined by magnetic instruments to, ensure a minimum delta ferrite of 3% at the surface. The. above procedures ensure that weld deposits contain between 5: and 12% delta ferrite for wrought structures and between 5 and 15% for duplex cast structures.
3A-14.....                    RafimadtedPer.
 
1(c). Battery Performance Discharge Tests - Comply. with the exception of battery service test, intervals not to exceed 18 months.. Our service tests are perforaed during refueling outages with a nominal Interval of 18 months. However, due to scheduling requirements within outage windows, the Interval between tests can                0041 slightly exceed 18 months. In addition, per Tech Specs, service tests are not, performed during refue!ing outages that require "performance discharge tests."
Refer to Section 8.3.2.2.2.
1(d). Independence of Redundant Standby Sources - Refer to positions on Regulatory Guides 1.6 and 1.75 In Appendix 3A.
1(e). Connection of Non-Class lE Equipment to Class 1E Systems -. Refer to position on Regulatory Guide 1.75 in Appendix 3A.
I (f). Selection of Diesel Generator Set Capacity for Standby Power Supplies - Refer to position on Regulatory Guide 1.9 In Appendix 3A.
2(a).: Shared, Electric Systems for Multi-Unit Nuclear Power Plants - Refer to positon on Regulatory Guide 1.81 In Appendix 3A.
2(b).: Availability of Electric Power Sources - Refer to position on Regulatory Guide 1.93 In Appendix 3A.
1.33            QUALITY ASSURANCE PROGRAM REQUIREMENTS (OPERATION)
(REVISION 2:2/781 p"ET7 *kVirgJ qfC.Guide.Summer Nuclear Station complies with the recommendations              of VefRegu                1.33 as discussed In Section. 17.2 and Section. 6.0 of the              Icala Specificatio            the following exceptionis and clarifications:
: 1.      The plant has prog          atic control requirements In            that make the biennial    RN.
review process redundant.          se programma            trots were affected lonant effort 01-415 to ensure that plant Instructions                      are reviewed for possible revision:
when pertinent source material is              ,erefore    maintaining. the procedures biennial Quality Assuran          it of the proceduralvj~mn program utilizing a approach::---- the            of hebinnalevewprce
                                                                          "-ree........ andlo0g.:'i' s,
a  effective in                        3A-18 .....                      ... afermV.er..
 
      *,,neplant takes exception to.paragrap-h C.4 regarding the Increased              uOnm~a r    red for the performance of the Nonconformance, Surveillance T                    nd Unit          Its. The specified frequencies in C.4 are six months,                months, and twelve        ths respectively. The plant will audit these are          a minimum            RN:
frequency of            in a period of (2) two.years." using i...                                      guidance of the.              01-11 Standard Review Plan-          . This change allows .          exbility in the scheduling.
      .of audits and allocation              Also, since peagous audits have not Identified any signficant deficince in the S                      ,h    frequency change will: not decrease the effectiveness of the            .      plant will audit these areas every two years. Audits shall be pe              at the In      designated for each audit area. Schedules shall be            on the month In              audit starts. Two year audits may -be exte          ntto exceed 25 percent of itas            The maximum              R time          na        wil not exceed 30 months. When an aud                  al extension        o.0.
great~er th        month: is used. the next audit for that particula .ra            wilb sch        from the original anniversary month rather from the montlhi ofth I
1.34          CONTROL OF ELECTROSLAG WELD PROPERTIES (REVISION 0: 12172)
Electroslag welding Is not used for safety-related components at Virgil C. Summer:
Nuclear Station.
1.35            INSERVICE INSPECTION OF UNGROUTED TENDONS IN PRE-STRESSED CONCRETE CONTAINMENT STRUCTURES..
(REVIS;ION 3: 4i79 The surveillance program for the Virgil C. Summer Nuclear Station containment: %.
prestressing system Is in compliance with the recommendations of Regulatory Guide 1.35 with the following exceptions and danfications:
In place of the Lower Limit and 90% Lower Limit defined in this Guide, the 95% Base..:
Value and 90% Base Value, respectively, are used.- The Base Value is the force predicted for a tendon at the time of the surveillance. The Base Value is equal to the original stressing force minus the losses described in Proposed Regulatory Guide 1.35.1, "Determining Prestressing Forces for Inspection of Prestressed Concrete.
Containments," April 1979.
In the calculation of the Base Value, zero tolerance has been applied to the losses. The losses are combined by considering the interaction of the tendon stress relaxation and concrete creep using the procedure described in *AMethod for Predicting Prestress Losses In a Prestressed Concrete Structure" which appeared Inthe Prestressed Concrete Insttute Journal, March/April 1972. The Surveillance program is discussed in Section 3.8.1 and. the Virgil C. Summer Nuclear Station Technical Specifications.                      9 3A-19                            Reformaf          ....
 
Following the third (5th year) tendon surveillance, the total losses predicted for the. 4th and subsequent suwveillances are based upon non-interaction of loss sources which is.
conservative compared to the interaction method previously used. For the: non-interaction method each contributor to loss in tendon prestress force is evaluated individually and combined by direct summation.
1.36          NON-METALLC THERMAL INSULATION FOR AUSTENITIC STAINLESS STEEL (REVISION 0: 2/731 Regulatory Guide 1.36 is not applicable for components within*the ReactorBuiding since only stainless steel mirror insulationmor a mass type encapsulated in stainless:
steel is used on austenitic stainless steel piping and equipmenLt For austenitIc stainless steel piping and components outside the Reactor Building, Regulatory Guide: 136 is followed.
1.37            QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF FLUID SYSTEMS AND ASSOCIATED COMPONENTS OF WATER-COOLED NUCLEAR POWER PLANTS MREVISION.                                    ,..
The Virgil C. Summer Nuclear Station compiles with the recommendations of pflF,57-            Regulatory Guide:1.37. Procurement orders apply cleaning requirements dudng 109/01-0    -  fabrication and padcaging of safety-relata* components so that equipment Is delivered Sto thw site in a proper* cleaned cond                                uree for the construction and .1 operation-phswmeet the                                  ANSI                  an this guide exceptI 1.38::          QUALITY ASSURANCE REQUIREMENITS FOR PACKAGING, SHIPPING. RECEIVING. STORAGE; AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS (REVISION 0:&3W73)....
D1r,94W rOA/54-construction and operation itdesiccant used in conjunction with austenitic stainless steel and at the site meet the recommendations of the guide.
            .*  .. .      . .3..                . ~3A-20
                                                            . .    .  -  .0.....~ --
                                                                                              ...    -  A't.-Reormaded
                                                                                                                ]
fdml a l n-d?  Per_~-
r...
XiTii*-0  ...
 
1.39            1.39 HOUSEKEEPING REQUIREMENTS FOR WATER          -COOLED      NUCLEAR POWER PLANTS (REVISION 2. 9/77)
                  -"vAA~g~r~mer Nuclear Station c.omplies with the recomm
,*Af,*(    Regulatory Guide 1.                                      are in agreement with ANSI 1.40            QUALIFICATION TESTS OF CONTINUOUS-DUTY MOTORS INSTALLED INSIDE THE CONTAINMENT OF WATER-COOLED NUCLEAR POWER PLANTS (REVISION 0: 3Y73)
The specifications for continuous-duty Class I motors installed within the containment stipulate the recommendations of IEEE-334-71. The vendor's qualification tests are in.:
compliance with the recommendations of Regulatory Guide 1.40.
1.41              PREOPERATIONAL TESTING OF REDUNDANT ON-SITE ELECTRIC POWER SYSTEMS TO VERIFY PROPER LOAD GROUP ASSIGNMENTS (REVISION 0: 3173)
The Virgil C. Summer Nuclear Station preoperational testing program compiles with the recommendations of Regulatory Guide1.41.
1.42              INTERIM LICENSING POLICY ON AS LOW AS PRACTICABLE FOR GASEOUS RADIOIODINE RELEASES FROM LIGHT-WATER-COOLED NUCLEAR POWER REACTORS (REVISION 1:3/74)
The NRC staff has withdrawn this Regulatory Guide.;
1.43:            CONTROL OF STAINLESS STEEL-WELD CLADDING OF LOW-ALLOY STEEL COMPONENTS (REVISION 0: 573)
The Virgil C. Summer Nuclear Station complies with the recommendations of:
Regulatory Guide 1.43 as discussed herein. To ensure guide compliance, Welding processes that induce underclad cracidng by generating excessive heating and promoting grain coarsening in the base metal are not used. Known affected..
components are restricted to the reactor vessel, the steam generator, and the pressurizer.
The reactor vessel heads and shell courses were constructed of SA-533 Grade B Class 1 plate material made to a fine grain practice. The closure head and vessel flanges and the primary nozzles were constructed of SA-508 Class 2 forging materal.
This plate and forging material was clad utilizing the shielded metal arc and the two-wire submerged arc processes which are considered low heat input processes. Since the plate material and the low heat input clad processes used on forging material are not subject to restrictions by the guide, the vessel is in compliance with Regulatory Position C.1. Regulatory Position C.2 is not applicable in this case. The reactor vessel:
3A-21                        Reformatted Per.
        ...................      ..................                            Aen*m-e            .
 
      -1.58                QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION.
LW.FTh                      EXAMINATION. AND TESTING PERSONNEL IREVISION 1: 9180)                                /
x~f~f1 Sortionthe QAperiodprogram prior to issuance of an operating license, the Virgil C. Summer has and is continuing to use an alternate approach to Regula              ry Gui      1.58. This program is described below:
D              SCE&G or GAl personnel review the inspection, examination. a                    testing procedure of vendors and contractors who supply nuclear safety-relatbed                              for the Virgil C. ummer Nuclear Station. SCE&G or GAI also reviews ap                        e    vendor and cont ctrocedures which establish the qualification of                                examination, and testing pers nel. These procedures are reviewed prior to thel ication to:
SCE&G material equipment and proposed documentation of                                nel qualification.
to the extent requi          by the nature and scope of the work is v              prior to acceptance of the material or equi ent when performed by the vendor o contractor. SCE&G and GAl personnel responsi            for reviewing procedures,                log surveillance for procedure implementation,Tnd verifying inspection, exa                  ation, and testing records:..
are knowledgeable andIqu              ed in their particular area f inspection, exanflnation, or testing.-
SCE&G or GAI does not impose a ee-level qu                        dion of inspection, examination, and testing personnel on vendors a                            excepti in those cases where non-destructive examination (NDE) Is ure. Within the scope of the NDE services.
specifications, qualifications of person                    Ing non-destructive examination are In accordance with: SNT-TC-1A and ap                    codes....
The quality assurance programs of v              ors or      tractors which have been reviewed.-
and approved by SCE&G or GAl h e provisions                    the indoctrination and training of:
personnel as required 10 CFR 5 . Appendix B, Cdio II. Vendors and contractors.
were surveyed by SCE&G or ... and were required have indoctrination, training, and certification programs desig            to meet the needs of        inspection, examination, or Atest required. These progr s vary in scope and comple ycommensurate with the::
nature of the work perfo ed by these suppliers andthem rtance of the item or service involved.:.
Vendors and co            ctos that have done or are now doing work o              for the projects safety-related it        s and services comply with many elements of N              .2.&6 The SCE&              C Program that has been: used and is continuing to be u              during the const=ucti phase was established in accordance with 10CFR 50 Appe                            B. The elerren      of the QC program are similar to. those Imposed: on vendors and                  tractors.&#xfd;%
Su          uent to issuance of an operating license, the Virgil C. Summer Nuclear Slfion program will utilize ANSI 18.1-1971 for onsite operations organization personn ruiung qualification to this standard as defined in Chapter, 13'.
N 6L 3A-36                  ......      Reformatted
                                                                                          . ArTff nItE&#xb6; O0-0&#xb6; Per .... " ..
 
                                          -r    -.
E7Tr      I."      .an net whos qualicans          P=.
are not" requiredn to meet those specified cop."ast..al pla*n,or fthesGreat                        I e              p no        .2.817            t wthe...
              ".                                                                      pe                            4:.,43o NUCLEAR POWER PLANTS:UCLEAR manxae'reservoirs 1.60:*:/              DESIGN for BASIS  cooels ng  sytesFOR FLOODS            SCEG                  p towmever    verformed      petheanalyses (RERVISION                    1:
FOR COMMEN                14/76) the consistent wilithrtthguidelinesmpresened                ApenS    In A1fte euaor                  ude.lo Regulatory Guide 1.59 appliesto plants            s        byce                    b streamside;    n estuaries, onbso coastalwplain, or atted                  an aped          tdoes at not presently apply to plants withp:s uzman-made reservoirs for.cooling systems. SCE&G, however performed                              .the analysein, consistent with the guidelines presented                    In  Apporyi      Aof  the Regulatory    Guide. Floodgie
    .. ": design considerations are. discussed in Sections 2.4.2, 2.4.3. and,2.4A.4....                                      .........              .
1.61                  DAPIGN VAESPONSESPEIM IFOCSSMI                                      O N F UCLEAR.WER DESIGN POWER PLANTS                    1REVISION 1: 121731 The construction permit for the Virgil C. Summer Nuclear Station was issued: based on, the seismic data. given: in the PSAR. Considerable Investigation was performed by the:
on, AEC/DOL and the ACRS prior to issuance. Designs have been accomplished based data which was submitted and approved at that time. The same data is presently utilized for equipment procurement andtesting.: Refer to Sections 2.5.2 and 3.7. Since, the data given in the PSAR had AECDOL.and ACRS approval, this constitutes an,.
acceptable alternateto this regulatory guide.&#xfd;, ..
i}i:::
4.
161%    .            DAMPING VALUES FOR, SEISMIC DESIGN OF NUCLEAR pOWEM 1.62                  PLANTS (REVISION 0O PRTC3TIO M...:                                                    ACTON      (RVS.            .
The construction permit        f          the Virgil C. Summer, Nuclear Station was issued based, ont.
was performedbased      by theman AEC/DOL and the ACRSpriorPSARy the    seismmcdata        given    in  the  to issuance.        Designsinvestigaton Considerable          have been accomplished.                        on, ..
data which was submitted. and approved at that time. The same data is presently.*
the: data.for utlized            equipment given            procurement in the. PSAR.                and testing.
had AEC/DOL.        and ACRS,      to Sections Refer approval,    2.5.2 this. and37.anSince7ad ,: ..
constitutes acceptable:altenate to this regulatory guide.
1.62.            " MANUAL INITIATION OF PROTECTIONzACTIONSd(REVISION 0: 10/73)1 Manual initiation of protective actions: at the systems level: may be accomplished from:.                                              .*:'
the control room of -theVirgil C. Summer Nuclear Stalrtio In compliance with the.'.z                                                  .
,*      recommendations of Regulatory Guide.1.62. Drawings and descriptions of the manual*::*;
,::    - ~initiation circuits:are found In: Chapter& 7 and 8:*...-                                                                ..
3A3*  ..                              e...mat.e.....
 
Category 4        The majority of AC control circuits (i.e.. thos circuits which are not identified as Category 1 and 2) are protected with primary and backup overcurrent protective devices in series Both devices are sized to dear:
a fault before the I2t capability of their associated penetration conductors is reached.
1.64,            QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS (REVISION 2: 61761 esign of dhe Virgil C. Summer Nuclear Station began pdor to the issu Regul          Guide 1.64 or its referenced document-ANSI N45.2.11-1974.                  &G did impose, h              the requirements of Criterion3:.Design Control,*              CFR 50 Appendix B, on or            tons having design control responsibi          r this project From the outset of the project,      anizations having design res          blity have been: closely rN%~ItT  audited for Implementation .            eaningful and e          design control programs which meet, Criterion 3 of 10 CFR 50 Ap            -. An          nt conditions in the audited..:
        .design; control programs were Identified a            eycorrective action taken to resolve these deficiendes on the design e                the    . Summer Nuclear Station.
Upon "11 issuance of ANSI                the requirements of thewe..
SCE&G and compa                the Implemented design control progra            this project. The guidelines set. t        mRegulatory Guide.1.64, and its subsequent leis              in 1975 and 1976 are          tve &#xfd;bnd meaningfuil guidelines for the establishmen of a des'            ntrol pr1 1n            udear power plants,.and SCE&G complies with the recommnato guide....._                                                                      __  _  __  _
1.65            MATERIALS'AND: INSPECTIONS FOR REACTOR VESSEL CLOSURE..
STUDS fREVISION 0: 101731.
Regulatory Guide 1.65 was issued after the Virgil C. Summer Nuclear Station reactor vessel boiling material was procured. However, this material directly meets the major:
portions of the guide. The only exceptions are that a maximum tensile strength of 170,000 psi was not actually specified although achieved, and the calibration for the radial ultrasonic testing was established on each stud. Each point of compliance and the exceptions are discussed in detailas follows:
: 1. Boltingi Materials.
The Virgil C. Summer Nuclear Station reactor vessel closure head studs were RN:
manufactured from SA-540 Grade B24 material and the closure head HydraNuts                    084.03 and washers were manufactured from SA-540 Grade B23 material. These materials directly comply with Regulatory Position C.l.a of the guide.
3A-40                            Reformatted Per Amendment 00t; .....
 
1.72                SPRAY POND PLASTIC PIPING (REVISION 0:12/731 Regulatory Guide 1.72 does not apply to the Virgil C. Summer Nuclear Station since the design does not incorporate plastic piping.
1.73                QUALIFICATION TESTS OF ELECTRIC VALVE OPERATORS INSTALLED INSIDE THE CONTAINMENT OF NUCLEAR POWER..
PLANTS (REVISION 0. 1/74)
The Virgil C. Summer Nuclear Station complies with the recommendations Regulatory Guide 1.73 with the following clarifications:
For safety-related motor operated valves located inside containment, the%.
recommendations of Regulatory Guide 1.73 with the exception that stem mounted limit switches are tested separately to the provisions of IEEE STD. 382-1972 are followed.
1.74                QUALITY ASSURANCI TERMS AND DEFINITIONS (REVISION 0:2/74)
Ghas developed a glossary of termns which are listed Inthe SCE&G, Assura                      company's quality assurance program for Iotion                      of the
#lr requirements for 1                              Ix B. Terms requriq:            o&#xfd;r definition have been so defined in specifications a                                        as needed.
It is the -position -of SCE&G                  trsand.definitl                  Ithas used in the.:
implementation of                  tyassurance program of this project a                            with the deft. ~fv~tained In ANSI N.45.2.10-1.973, and. the: definition of *Prod]c                        m&u mlt1ient" as noted in Section C of Regulatory Guide 1.74..
1.75                PHYSICAL INDEPENDENCE OF ELECTRICAL SYSTEMS.
(REVISION 1: 1f/75)
The Virgil C. Summer Nuclear Station design complies with the recommendations of Regulatory Guide. 1.75 with the following clarifications:
: 1. The basis for physical separation is described in Section 8.3.1.4. Since issuance of the guide followed significant design completion of affected areas, Virgil C. Summer Nuclear Station will comply with Section 4.6.2 of IEEE 384-1974 by analysis as in alternative :
: a.      A case-by-case analysis Is described in Appendix 8C to demonstrate that circuits in a non-safety related tray that runs adjacent to a safety related tray will not degrade the separation levels between the circuits in the safety related tray and any redundant safety related circuits. Cases in which the adequacy of separation between a non-safety related tray and safety related tray(s) of a single channel cannot be demonstrated, will be separated by:
barriers as described in Appendix 88.
3A-45.
                                                      .............    ..  .............. AA Reformatted renrnl00 Per..
(0T "- ........
 
    '1.85          1.85 CODE CASE ACCEPTABIUTY ASME SECTION III MATERIALS (REVISION 28: 4/92)
(Withdrawn O6/2003) Materials Code Case Acceptability - ASME Section III, Division I (Guidance incorporated into Revision 32 of Regulatory Guide 1.84, published 06/03).
1.86            TERMINATION OF OPERATING LICENSES FOR NUCLEAR                                            RN REACTORS (REVISION 0: 6/741                                                              04-011 The termination of the operating license and subsequent decommissioning of the Virgil C. Summer Nuclear Station will be in accordance with regulations in effect at that time.
1.87            CONSTRUCTION OF CLASS 1 COMPONENTS IN ELEVATED TEMPERATURE REACTORS (SUPPLEMENT TO ASME SEQQTION II1Ii CODE CASES 1592. 1593, 1594. 1595. 1596WREVISION 1: 6/75)
Regulatory Guide 1.87 does not apply to the Virgil C. Summer Nuclear Statlon.
1.88            COLLECTION. STORAGE. AND MAINTENANCE OF NUCLEAR-POWER PLANT QUALITY ASSURANCP RFrCORnS IR=VISION 2- 1017R%
Doe eVirgil C. Summer Nuclear Station quality assurance.records program complies the,        mendations of this Regulatory Guide with the following exceptions a calaritica ANSI-N"5.2.9-74.
S Sctin:. Exce                lrfctos 5.3Duinng the intert                          Ich the SCE&G's Quality Systems (QS) rid:Mateialsement (M&P) organizations maintain, records puior        nsmttai to      Permanent Records Storage Facility        ),the records wilg b      tIn approved temporary
                          .r        strgefacilities without the n          astorage procedure etining the elements required by Paragraph      .SCE&G        justifies this position based on. the fact that Prgah2.2.2              Si...
N45.2.9 recognizes that these records are of no value'i demonstrating plant acceptability but only establishes that acti were nerlbrmad.
3A-53 :..                          Reformatted Per Ad. ! n            t.. :... .....--
 
t SI-N45.2.9-74 Exceptions and Clarifications A
Note: This position is applicable to these nop-permanent record being bacltted within:the period from commercial operations December 1982.
5.6          The: Nuclear Operations Building records vault.is                and located to protect contents from possible destruction      causes:.
uch as fire, tornado, flooding, insects, rodents,          possible tenoration by a combination of extreme variatlo in temperature an    umidity conditions.
The N          Operations Building records v      is designed to meet a4 hour        rating,
* 3.2.7      For SCE&G          ality Systems (QS) a    Materials and Procurement (M&P) organiza          s' generated        required by Appendix A.
the following-docu oft ill be          ignated for tumover to the PRSF with retelntion .es c            as "non-permanent records" as required by Paragraph .2.7:
: 1. Quality Records:
: a. QS R            Include.
GAP          ures APAs Surveillance Reports:::
Audit Reports:
M & P Records are:.-.
Vendor Procedures Vendor Inspection Reports Vendor Audit Reports Vendor Survey Reports Vendor Surveillance Reports.
3A-54                        Reformatted Per
 
lI-N452.9-74
~~~~Excepnaon                    and Cladfctos*
2.i    After commercial operation, the records referenced in: I abo*
will be placed In the PRSF within 6 months of time all associated with closeout and/or acoroval are comolete stored electronically as described in FSAIR Section 17.                7.12..
: 3.      Non-permanent records generated prior to operations will only be placed within the PRSF if y were..:
generated within 3 years prior to commercial                  tion.,::    ,
SCE&G justifies this position based on the                that Paragraph 2.2.2of ANSI N45.2.9 recogni                that these rds are of no value in demonstrting            nt acceptability...
only establish that activities were:              ed; and based::
on e fact that SCE&G utilizes th                      s for 3 years withi*                t control progra Note: Im          entation of              non-permanent records.
generated *thIn 3 years pio o commercial operation into the SCE&(G            nent facility expected to be completed by December, 1 3.2.7 App. A    Applicable codes and s            a:    will either be maintained at the%
plant. site or will be read                ble from other sources.
Vendor QA Manu              Man . will not be sent to PRSe; however.
objective eviden          audit and s        reports, review sheets, etc.)
that manuals            reviewed will      senL.
Vendor R            .- SCE&Gs suppl              safety related hardware have bee equired by procurement d                  ments to have records:
control stems which meet the requir                      of 10 CFR 50, Appe          B and ANSI N45.2.9 Including.            term retention.-
                -caplity. The suppliers have been audited assure that:..
cient records were generated and that su            It tention ilites, procedures, etc.. were In place and satIl Implemented. In-process surveillance of plant s                    equipment has confirmed design control and verification progra                to be functional at the supplier's facilities. Since all design r uirements                  .
(including design basis.event) have thus been demons                        and documented in SCE&G s permanentrecords. supplier itemIesign calculations are not required and have not been obtained. S tem.
design calculations performed by the NSSS supplier and the have been retained by these agencies which have programs wh.
have been verified to contorm to ANSI N45.2.9. For these rea 3A-55 Reformatted Per
                                                                                  ,.,..,  ,.  --Q1 .
 
some of the record types listed in Appendix A of ANSI N4529 (e.g.,.design calculations and purchase orders) were not obta from the suppliers. All necessary records which demonstra inherent capability of the equipment to meet the requirem                    of the; design specification such as material test reports, we procedures, seismic, and environmental qualification:                  be:
retained in the Permanent Records Storage Facility. CE&G'will: .
continue to procure equipment in this manner.
In addition:,
: 1. Records are str            In metal cabinets. No records are                  on the floor.
Adequate access              aisle ways are maintained.
: 22. Work not directly assocd            with records storage retrieval is prohibited within..
the Nuclear Office Buildi            ecords vault              aes of such prohibited activites include but are not limited t. records reprod                    ,film developing, and fabrication of microfiche cards.
: 3. Smoking, eating, and drinking are                I        throughout the permanentlrecords vaults.:
: 4. Ventilation, temperature, and hu                        trot equipment is protected insidewith ventilation firedampers or bla              ts whe        they penetrate fire barriers bounding..%...
the storage facility.
5      The Nuclear Office Buildi Permanent Records.                      orage: Facility meets the intent of Regulatory Guide 1. as follows: %
Painted sheetrock          s added to the concrete block: ma            ry waltswhich provides an additional on our to the fire rating and serves as a                    isture barrier. Tile floor was installed dmeets the intent of the standard since tile an acceptable...:.
alternative t      rce sealant on concrete (actually better).-.
A 4 inch      C conduit in the floor caries :refrlgerant lines and has                  sealed with silico . This is acceptable since the terminal end of,the concrete e cased PVC:
Pip      buried in the yard and there could be no fire propagation throu i. The re            concrete roof is inside and slope is not a consideration as It                  Idbe in exterior application.
3A-56.                                Reformatted Per
    .  ..  ..    .  .. . . . ...    ,...    .  ..  ... .. ..                    ..  .      lr1p~t 00
 
                                                                                                                  ~1 netratons which required sealingwere as follows: 1) Halon pipe, 2) ou          xes,  electrical brawee        eaedreceptacles,  3) penetrations it Kowoland/or              for toggle RTV-732          bolts for H siliconiL":.**.... ank
: 6. Some records                  ted by Nuclear:Operations during the                tions phase are needed for varying                  s of time at the. place of odigi -aM for ready reference. ...
Ts        rel        wi rebe s          lmpol dly as      des In one        re-retardant c          1binet by 7the o.ginators In                  r Brealdng  vaultw    Tempo nlecords Storage Facilities until they              permit to the                          issuan*ce oeFaculities. The e .89of timereoe thategcrudsmane of              i                will be defined for each type record in'.
fo    the Remors Accumulairon a                        tion CprrThe rmquireas of ANSuI:
poit2o9 regarding  seiectedy            a      retirneabil                records will be mete elec the, recoqm      frs p            Temporary Records                          s foritlesh; ieisth qualcA.              El        ic reordst will be stored as describedn inCeldinge4 F ,6on:9            to 17.2.17.2.(5 BOPscopewas                          the reuit Bse idinton                    used onlyas a TemporEEy 3R be of                                    17        and acilary d    n accordance with plant procedures.
1.89:              QAiFIC7R                                  EQIPMN          FO    NjCER OE PLANTS: (RE-VISION 0: 11/7f4l Engineering design of the Virgil C. Summer Numenr Station (VCSNS)was cof mencedtra and  construction permit was granted prior to the issuance of Regulatory Guide 1.89to Therefore, the -guidance of IEEE-323-1971 was used: as the principal. document in:...
fIEEEl323-197          or original environmental qualification programs for Class Eequipment the used Int the Virgi C. Summer Nudeaw Station.
NUREG-0588, *Interim: Staff Position on Environmentas. Nualficatnon :of Safety-Relatedc Electrical Equipment! was Issued in November of 1979 to provide~the NRC staff:
positions regardinag selected areas of environmental qualification of safety-related electrical equipment for plants committed to satisfy the requirements set forth in either the:1971 or. 1974 version of the IEEE 323 standard.
Environmental qualification of safety-related electrical equipment purchased under the...
NSSS scope was based on the requirements of IEEE 323-1971 and the supplemental qualification program described in NS-CE-692 (7/101075) frornC. Eicheldinger tW:
D. B. Vassailo, of the Nuclear Regulatory Commission.
Environmental qualification of safetyreated electrical equipment.purchased under the BOP scope was based on the requirements of IEEE 323-1971 or !EEE 323-1974 and ancillary daughter standards (e.g., IEEE Stds. 317. 3341 382, 383) in accordance with the guidance provided by NUREG-0588. Environmental qualification of BOP electrical.
equipment was performned :in accordance with NUREG-0588. CaL 11. which relates to IEEE 323-1971l for the orginalt plant design, However, some equipment was qualified to:
IEEE 323-1974 (NUREG 0588, CaL 1)requirements,. NOW and replacement electrical..
3M-57. %.                            Reformatted Per
 
1 .94        QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION.
The Virgil C. Summer Nuclear Station complies with Regulatory Guide 1.95.
Compliance with Section C.2 Is currently ensured through the onsite storage of chlorine in amounts less than. 150 lbs. per tank. Should per tank storage in amounts in excess of 150 lbs. become necessary, the pertinent regulatory guide recommendations will be re-evaluated. Accidental chlorine release is discussed further inSections 2.2 and 6.4.
1.96          DESIGN OF MAIN STEAM: ISOLATION VALVE LEAKAGE CONTROL SYSTEMS FOR BOILING WATER REACTORS NUCLEAR POWER':
PLANTS: (REVISION 1: 6/76.
Regulatory Guide 1,.96 is not applicable to the Virgil C. Summer Nuclear Station since: it uses a PWR.
3A-59...                      Reformatted Per Amendme.*t-00* -.
 
1.114 .                GUIDANCE ON BEING OPERATORAT THE CONTROLS OF A NUCLEAR POWER PLANT (REVISION 0: 2/76)
The Virgil C. Summer:Nuclear Station operators will follow the guidance presented In:
Regulatory Guide 1.114.
11156-.                  PROTECTION AGAINST: LOW TRAJECTORY TURBINE MISSILES..
(REVISION 0: FOR COMMENT: 3/761).:
A turbine missile analysis has been prepared for the Virgil C. Summer Nuclear Station by General Electric letter GE/SCE&GIJO.2010. This analysis demonstrates: that the hazard presented to an essential system or target from low trajectory turbine missiles is                              02.01 less than 10F7/year. and that based on the single piece monoblock rotor there is no longer any wheel disc integrity concern.
1.116                  QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION.
INSPECTION. AND TESTING OF MECHANICAL-EQUIPMENT AND.
SYSTEMS (REVISION 0-R: 6/76) 1.117:                  TORNADO DESIGN CLASSIFICATION (REVISION 0: FOR COMMENT:
6/76).
This: guide isrnot applicable due to its implementation date. However, structures, systems, and. components are constructed and/or protected against the design basis.
tornado (Regulatory Guide 1.76) and the resulting postulated missiles to ensure that (1) the plant can be safely shutdown and. maintained in a safe condition (2) doses from the postulated related failures will be within acceptable Emits. Tomado missile protection Is presently being included for ESF equipment For other equipment, where it is impractical due to present building design and layout, probability analysis is utilizedto indicate conservatism. The Reactor Building has been designed to withstand the..
design basis: tornado and the control room vents are provided with a tornado missile..
shield.
Design features utilized include redundancy, separation, barriers, or probability considerations (see Regulatory Guides 1.76.and: 1.12).
1.118                    PERIODIC TESTING OF ELECTRIC POWER AND PROTECTION.
SYSTEMS (REVISION 0: 6/76)...
Section 7.1.2.11 outlines the provisions for dealing with periodic testing of electric power and protection systems in conformance with IEEE 338-1971. Chapter 14.0 outlines preoperational testing. Regulatory: Guide 1.118 supplements IEEE 338-1975.
Therefore, Regulatory Guide 1.118 is considered not applicable to the Virgil C. Summer Nuclear Station..
3A-66.                    .          Reformatted Per
... ... .. .. . ... .. . .. ..  ....  .. .... .. * . ... . .....  . --. -... ..... ... . . . *.:...- nendr  enet.00 , -, . .  .  ...
 
1.121          BASES FOR PLUGGING DEGRADED PWR STEAM GENERATOR.
TUBES (REVISION 0; 8/76)
Section XI, Subsection IWB-3521 1: of the ASME Code requires steam generator tube:
plugging or repair when a defect has penetrated 40% through the tube wail for tubes:
with a r/t ratio of > 8.70. and does not address specific degradation modes.
RG 1.121 (draft) has been used as the basis for establishing tubing operability Omits for specific degradation modesi. While the Alloy 690 tubing in the Delta-75 steam.
generators are not expected to experience service related degradation, RG 1.121 can:
be used to assess the operability of specific non-destructive examination indications.
The U. S. NRC has claimed that RG 1.121 forms the basis for the current Standard Technical Specifications steam generator tube plugging limit. however, detailed analyses performed by Westinghouse have routinely established acceptable defect depths in excess of 40% throughwall (with eddy current uncertainty applied). The U. S.
NRC has never accepted these alternate depth based analyses, with the exception of a:
few case by case submittals (such as pitting degradation at Indian Point Unit 2) applied to a limited number of tubes.
1.123:::        QUALITY ASSURANCE REQUIREMENTS FOR CONTROL OF PROCUREMENT OF ITEMS AND: SERVI[CES FOR NUCLEAR POWER
,1A4=                PLANTS (REVISION 1: 7/77)
(REVISION 1: 10/79)I TheVirgifl C. Summer Nuclear Station complies with the recommendations of.....
Regulatory Guide 1.137 as discussed below.:
Reaulatorv %
Position:..:      Compliance C.l.aA      Responses to separate regulatory guides are found in Appendix 3A.
Commission regulations are addressed individually, as required by the:..
regulation.
C.1 .b      The Diesel Generator Fuel Oil System quality assurance meets the recommendations of Regulatory Guide 1.28i as discussed in Appendix 3A..
3A-67                        Reformatted Per
                                                                            .Awendment00=0 .    .
: 9. Regulatory Guide 1.143 specifies 30 minute hold time for leak testing of piping systems in addition to the: required codes and standards. An exception to the Regulatory Guide 1.143 30 minute hold time Is the 10 minute specified in ASME and ANSI codes without an additional 30 minutes. The basis for this exception is,i all. systems installed, maintained, and modified are tested in accordance with ASME Section III, Section Xl and ANSI 6-31-1 Codes.. This exception will eliminate any confusion regarding test time and ANSI code requirements.
1.144            AUDITING OF QUALITY ASSURANCE PROGRAMS FOR NUCLEAR:
POWER PLANTS (REVISION 0: 1/79f rgll C. Summer Nuclear Station complies with the recommendations of Regu'"
1.144 except as stated herein.,
.7'. The,ltinial      period as specified in the Reg. Guide is defined by SCE&G a                    ree (3) years pI .r minus three (3) months from the date of the previous aud                            .effect of 3.
three montxtension will: not be cumulative, and. the long term avere wil be maintained as:as            possible to a three year interval. The annuperiod as spefie in the Reg. Gu          defined by.SCE&G as one (1) yearplusor                    usone (1) month from the date of th revious audit or annual evaluation. The                          of a one month extension will not be          ulative and the long term average I: be maintained as close as possible to a one yea nterval. Annual evaluations wiot be performed during the:
years that triennial audits a performed, provided the                  it is performed within the three years plus or minus thr months Interval. Au                and evaluations may be performed earlier and/or more            n even though      periodicity definition for triennialV and annual have minus tolerances plied Applicability (Paragraph 1.2)
SCE&G imposes on its suppliers by y of p                  rement documents, the QA system audit requirements necessary for              item or se ice being supplied. Requirements for:
the audit elements of executing                ures, chec      ,auditor        qualifications, documented reporting of res.,            follow-up, and corr            action verification and evaluation are imposed.
Reporting. (Paragraph .4)
SCE&G meets th              uirement to Issue audit reports within thirty                after the post-audit conf            for adl internal audits and for extemal audits                there are identified d        encles (findings) requiring response and corrective a                  from the audited o nization. In the case of external audits where no deficien                          equidng respon are identified, normal practice is to issue audit                        wiin        y      after the        t-audit conference. Relaxation of strict adherence to the thirty day req                        t in      case of external audits with no identified findings is seen as an aid in the oritization of quality resources to those. areas where problems or issues exist.
3A-71                                  Reformatted Per:
                                                                                          .Aiiifi&t-mehU-I..
 
1.14&sect;.%        QUALIFICATION OF QUALITY ASSURANCE PROGRAM AUDIT PERSONNEL FOR NUCLEAR POWER PLANTS (REVISION 0:!8/801:
RN Ib th Carolina Electic and Gas Company meets the requirements of this regulat 4*-str    gu          the following darifIcatdon. RG 1,146 recognizes the use of ANSI                .2.23-1978              tion of Quality.Assurance Program Audit Personnel for                  Power Plants as the $        ard for qualifying auditors. SCE&G complies            this9stdard with one exception. S*            .3.4 specifiesr"The prospective            itor sha have....
participated in a minimum              quality assurance aud        In a period of time not to exceed three          prior to the      of qualification  e audit of which shalld be a nuclear quality assurance audit within            eato      his qualification.fi SCE&G, alternative is *Prospective Lead Auditors                monstrate: their ability to effectively        05403 implement the audit process and e              ely le      udit team., This process is described in written procedure                provide for            and documentation of the" results of this demonstra        .A  prospective Lead Auditor s          eparticipated hnat least one nucear q            assurance audit within the year preced              individuals:        ..
effective dante lualification. Upon successful demonstration of the; a                to effectively imnple&#xfd;menp      audit process and effectively lead audits, and having. met the provia $ of section 2.3; of ANSI/ASME N45.2.23-1978, the individual may. be c~e
_;&#xfd;ing qualified to lead audits.'.
          !147            INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SECTION XI DIVISION 1. (REVISION 13: 6/03)..:.                                          I03-044..
South Carolina lectric & Gas Company-meets the requirements of the implemented code cases: of this regulatory guide.
3A-72                            Reformatted Per Afl1ndrntmfn 00-Or
 
FSAR Chapter 13.1.2,13.4, 13.5, & 13.6 Revislons/Inserts 13.1.2.2.4.8 At FSAR Page 13.1-21 Modify to.read: "Further detail can be found in the VCSNS Unit I's QAPD.-
13.&1.7 At FSAR Page 13.5-4.
Modify by deleting "(See Appendix 3A)-
Insert A At FSAR Page 13.4-1 NOTE 13A..1..
Section 13.4.1 is being retained for historical purposes only.
Insert B At Pages 13.4-2 and 13.4-3 Part V, Section 2 of the Virgil C. Summer Nuclear Station Unit I's Quality Assurance...
Program Description.
Insert C At Pages 13.4-3 and 13.6-1 Part II, Section 18 of the Virgil C. Summer Nuclear Station Unit l's Quality Assurance Program Description Insert D At Page 13.5-3 The Virgil C. Summer Nuclear Station Unit I conforms to NQA-1-1994 through VCSNS:
Unit I's Quality Assurance Program Description. Operating procedures were prepared:
using ANSI N18.7, Revision 1, February 19, 1976 as a guide.
Insert E At: Page 13.6-1:
Basic Requirement 17 and Supplement 17S-.1 of ASME NQA-141994 and Regulatory Guide 1.28 Rev. 3 (See Appendix 3A).
Insert F At Page 13.6-1 Part II, Section 17.2 of the Virgil C. Summer Nuclear Station Unit I's Quality Assurance Program Description.
 
The Supervisor, Access Control and Fitness for Duty, responsibilities are to supervise, direct and manage the personnel screening. access authorization, fitness for duty, and investigative activities of the nuclear station security              03-024 organization in accordance with regulatory requirements..
: 8. Quality Systems Department                                                                  07.023 The Manager, Quality Systems, is responsible for audit, surveillance, anid.
inspection of Nuclear Operations activities to ensure that all safety-related activities are performed in accordance with a quality assurance program which meets the                    1 criteria of 10 CFR 50, Appendix B. Quality Assurance and Quality Control services..
may be subcontracted as needed. Further detail can be found in Seetie.            .4A.
13.1.2.2.5        Manager, Business and Financial Services%-                                      :
The Manager, Business and Financial Services, is responsible for supervising Business.
Management and Payroll. Additionally, Station Accounting reports to him for.
administrative purposes& He is responsible for project prioritization, business:.                RN development Including budget and business plan development and tracldng, payroll, site          o"24 vehicles, coordination with external industry groups, and coordination with the Station's Accounting support personnel.
13.1.2.2.6        Others Reporting Directly to the Vice President Nuclear Operations
: 1. Deleted:
: 2. Deleted.
: 3. NSBU Projects Coordinator                                                                  RN.
03-024 development, The NSBU Projects Coordinator is responsible for the planning, implementation, and completion of selected nuclear operations projects, including management development, long term planning, and succession planning. The incumbent heads a committee. for development of a Management Development Program and a board for addressing division training needs. The incumbent also serves on an SCE&G committee for considering application opportunities with::
transferring technologies. As NSBU Project Coordinator, the incumbent prepares            RN reports for, or communicates directly for, the Senior Vice President, Nuclear              .03-024 Operations, as directed.
13.1.2.3        Shift Crew Composition The:Virgil C. Summer Nuclear Station is operated from one central control room. The:
Shift Supervisor is directly responsible for the safe and efficient operation of the planLt%
For the operation of one unit, each shift is normally manned by one Shift Supervisor (Senior Reactor Operators Ucense), one Control Room Supervisor (Senior Reactor 13.1-21:                          Reformatted Per ATn.ndment.00*1*1  .
 
13.4.          REVIEW ANDAUDIT A program of inplant and independent reviews and audits has been developed by South Carolina Electric and Gas Company (SCE&G) to provide a system to ensure that plant:
startup and operation are consistent with company policies, approved procedures, and license provisions. The. review and audit program also assures that abnormal:
occurrences are promptly investigated and corrected in a manner which: reduces the:
probability of recurrence of such events, and detects trends which may not be apparent to a day to day observer. Guidance provided by ANSI N18.7, OAdministrative Controls and Quality Assurance for the Operating Phase of Nuclear Power Plants," I has been.
used in establishing the SCE&G review and audit program for the Virgil C. Summer%::
M'NE*T" Nuclear Station:::
6 '.=.
    .,,,.*b*..
13.4.1        REVIEW AND:AUDIT - CONSTRUCTION Review and audit during the design and construction phase of the Virgil C. Summer Nuclear Station are a part of the SCE&G quality, assurance program. The review function is performed primarily by the exchange of information between SCE&G, the principal contractors, and other contractors and suppliers. Audits are conducted internally and externally in accordance with the approved quality assurance plan to:
ensure that design and construction are in accordance with the requirements of:
10CFR5O, Appendix B (see Chapter 17).:
13.4;2        REVIEW AND AUDIT - OPERATIONS 13.412.1      Onisite Review:
The onsite review system at the Virgil C. Summer Nuclear Station is basically a part of the individual job responsibilities of the plant supervisors. It is their responsibility to conduct a continuous review and audit of the plant activities under their direction. For::
example, plant supervisor responsibilities include a verification that safety-related:..
activities are performed in accordance with approved procedures and a review of documentation and records to verify that technical and quality requirements are maintained.
To ensure that items which do not fall under the direct supervision of any one supervisor are reviewed in a thorough and prompt manner, a more systematic approach is used.
The General Manager, Nuclear Plant Operations has the responsibility and the authority for the coordination and completion of special reviews and audits. Reviews and audits of this nature include review of procedures, changes, tests, and experiments. The General Manager, Nuclear Plant Operations will also verify that abnormal occurrences and:unusual events are promptly investigated and corrected in a manner which reduces.
the probability of recurrence of such events. Administrative procedures to standardize..
these reviews and audits are included in the plant operating procedures. For example,.
the: development of safety-related procedures is covered by procedures which describe the system by which safety-related procedures are written, reviewed, and approved for implementation..
13.4-1                            Reformatted Per 4WF.nn        99f 01 -
 
The requirements for preparation; formatl and content of safety-related procedures,:
status of development incorporation of comments, and the approval in preliminary or In final form, are covered by procedures,.
Subjects to be covered by an onsite systematic review include:
: 1. Review of safety-related procedures.
: 2. Review of proposed tests and experiments to be: conducted after initial fuel loading that affect nuclear safety.&#xfd;
: 3. Review of proposed changes, to Technical Specifications, emergency plan, security plan, and licenses.
: 4. Review of proposed design changes, field changes, and modifications to plant safety-related systems, structures, or components.
: 5. Review investigations of violations of Technical Specifications, license requirements, applicable codes, and regulations.,
: 6. Review of abnormal occurrences, unusual events, and emergency plan activations..
7.:  Preparation of reports covering evaluation and recommendations to prevent recurrence.
: 8. Review of significant operating abnormalities or deviations from the normal or expected performance of plant equipment
: 9. Review of any indications of a deficiency in design, operation, or testing of safety-related systems, structures, or components.
: 10. Performance of special reviews and rendering of reports thereon as requested by the General Manager, Nuclear Plant Operations.                                          J99.o1
: 11. Review the acceptance of safety-related material that has been identified in nonconformance reports and that has been accepted "as is."
In addition to the Review cycle as stated above, the Plant Safety Review Committee will function and have Review Responsibilities as described in S          16'aldi"e            r4Z 7-"
Aft-l G.SUmnFrO        luelear, Station roohnwea Spocil-fic-insAr                                -
13.4-2                    Reformatted Per
                                        ..........                            Amend ent9..-...        ..  .
 
For each review:.
: 1. Determine whether or not the item reviewed may require a license amendment as defined in 10CFR50.59. In such a case, these items will be referred to the Plant          0241 Safety Review Committee.. This 50.59 evaluation may be subject to review and approval by the Nuclear Safety Review Committee. (Applicable to items 2,3,4, and 5 above.)
The records of the Nuclear Safety Review Committee ar maintained at the plant site.:
2..&#xfd;: Recommend approval or disapproval of the matter reviewed if,it is determined that::.
no possible license amendment, violation, or license requirement is involved.              02-o1 (Applicable to items 2. 3, and 4 above.)
: 3. Ensure that the adequacy of investigative and corrective action is such that the probability of recurrence is significantly reduced. (Applicable to items 5 and 6 above.)
13.4.2.2      Independent Review An independent review of the activities of the Virgil C. Summer Nuclear Station will be D"lr        1j4 conducted by an independent review body. This review body will be in the form of a            ,    a committee called the Nuclear Safety Review Committee (NSRC) which will function and have Review Responsibilities as described in Seete- 6 of the  ,,  rgil G. Summezr N, s-                .
Gtatien T-*o*hkel Spesfio-i.*n.-    No more than a minority of the members of the NSRC:
shall have line responsibility for the operation of the plant:
13.4.2.3:      Indeoendent Audit Proaram.
DE-O
* Independentaudits of activities involving the safe operation of the Virgil C. Summer.. ofj.f TE
    ,AJ.5E4(r Nuclear Station will be conducted by the SCE&G Quality Systems Department as. A ,,
.3-AJ.S'X"    described in GSepteF-4. Audits will also be conducted under the auspices of the.        XA/s,      r 7
Nuclear Safety Review Committee (NSRC) as further defined in ChOpt:r"17 -dthe              6 Pbnt Techioo~l Spez.'fisalions in Chept"r S.
13.
 
==4.3        REFERENCES==
: 1. ANSI N18.7, "Administrative Controls and Quality Assurance for the Operating Phase of Nuclear Power Plants," February, 1976.
13.4-3..                      Reformatted Per A..e.dm-nt 9"!        .
: 11. Automatic Actions The automatic actions that occur as a result of an emergency should be identified.
: 12. Immediate Operator Actions For emergencies, steps should be specified for operation of controls or.
confirmation of automatic actions that are required to stop the degradation of conditions and to mitigate their consequences.
: 13. Probable Cause The probable cause for alarms should be specified.
: 14. Acceptance Criter4a The qualitative or quantitative criteria against which an evaluation of acceptability may be made.
: 15. Attachments Additional information that may be attached to a procedure for clarification or ease of understanding...
The.Mirgil . Summzre ttzkideer i~etz ~ub          R lguleler; e~t        Guide 4.3a (eac:
* Op*m.n "Appe* -,- k)....                      - are*Fr.... u.. ANSI N48.7, Re;t,-n 4 ,iJS Be,-
-Fztr.ar 10,107 .... a gudo. The General Manager, Nuclear Plant Operations or his:
designated alternate has final approval before procedures are implemented.                    J>
13.5.1        ADMINISTRATIVE PROCEDURES The administrative procedures as described in the administrative manual, provide a dear understanding of operating philosophy and management policies to ensure safe..
operation of the plant within the limits:set by the operating license and Technical.
Specifications. They provide that plant activities are conducted. in a manner that will...
protect the general public; plant personnel, and equipment. A list of administrative..
procedure categories is provided in Tabled13.5-1. A description of these procedure categories is as follows:
13.5.1.1      Plant Orcanization and Responsibility Procedures.:
These procedures describe the plant organization and give the responsibility of the individuals by position and authority to operate the plant in a safe and efficient manner.
13.5-3                          Reformatted Per.
                                                        .    ......      Amendment00-O1
 
13.5.1.4      Control of Plant Documents Procedures.
These procedures describe the preparation and retention of plant records. Retentiomn periods are established to assure theability to reconstruct significant events and satisfy statutory requirements.
13.5.1.5      Corrective Action RePortino Procedures These procedures assure that conditions adverse to plant safety such as equipment,..
and material malfunction, abnormal occurrences, and nonconformances are promptly identified and corrected. They ensure that the cause of the conditions is determined:
and reported to the appropriate level of management for corrective action.
13.5.1.6:      Eauioment Control Procedures.
These procedures describe the control measures and actions such as locking, tagging.-
notification, removal of tags, and identification of equipment They provide for control of.
equipment to maintain reactor and personnel safety and to avoid unauthorized..
operation of equipment. As required by NUREG 0737, items I.C.8 and I1.1.1 (sub.-
items 5 and 10), administrative procedures provide: instructions for verifying correct performance of operating activities;, This item has been specifically addressed under separate cover letter to the NRC dated December 11, 1980.
13.5.1.7::      Desion ModifIcation Control Procedures, These procedures ensure that plant modifications satisfy, at a minimum, the same design requirements as the original equipment. Regulatory Guide 1.64 was used as a:
guide for the preparation&#xfd; of these. procedures, (e A;ppen*  i. 3x..
13.5.1.8        Procurement and Materials Control Procedures These procedures provide for the control of purchased material, equipment and services, They provide for proper identification, quality level requirements, control, handling, storage, and shipping of materials, parts, and components. These procedures also provide for the proper documentation to ensure quality of safety-related systems, equipment, and structures after maintenance or repair.
13.5.1.9        Control and Calibration of Test Eouioment and Instrumentation Proicedures These procedures ensure that testing and measuring devices are of the proper range and type and are controlled, calibrated, adjusted, and maintained at specified intervals or prior to use to assure the necessary accuracy of calibrated devices. Records are made and equipment suitably marked to indicate calibration status.
13.5-6::                      Reformatted Per.
                                                .Amendment                            00-01
 
13.6          PLANT ECORDS, MxrxE7      Records documenting the quality of the design, constructiorn testing, operation, zg56de      maintenance, and modification of the Virgil C. Summer Nuclear Station will be maintained to meet the requirements of N4.9.9. The records maintained comply with                                                  102-01 the requirements of Criterion XVII of Appendix B of IOCFRSO and ANSI MsO.? f9fe,:
              "AMMIlmostrem        %,. .u .. ,Ie    a,..        j**s*  r~c.JIin,  LW fl.fl U L  ~9e~* SSM. ~flS a  , ase.a  , ,~
DLA5Lr  I-7 Pe*W    P6Mt&.--
:LFE7      Records are normally stored and maintained in the permanent records storage facility which provides facilities to preserve the records in a manner to preclude deterioration.
Records that are not maintained In the permanent record storage facility will be.                                                  102-01 duplicated and stored in a separate remote: location. Electronic records will be maintained as described in FA,, S.ize,,, 47.2.17.2.
W 0" Records will not normally be removed from the permanent records storage facility as                                              J 9        :
specified in implementing procedures. However, under unusual circumstances, the:
Document Control and Records Supervisor, designee or the General: Manager,                                                        I RM.
Organization Effectiveness may authorize temporary removal                                    of records      from  the            03.02A permanent records storage facility;. The SCE&G Quality Assurance organization is responsible for auditing these quality records as described in See.don 17.2:7. pFE1--                                                */A!:21 13.6.1        PLANT HISTORY Upon completion of the plant design, construction, and construction testing, the: :
engineering and construction departments transferred or disclosed the location of all quality documentation to the plant staff and operations quality services: group., The engineering and:construction departments will state that the: record types necessary to document quality have been identified and that ft list is complete and accurate.
Records not maintained at the plant site are kept at the material supplier's due to code and standard requirements or at Parsons Power, LTD. (formerly Gilbert Associates, Inc.)                                              .03-024 I RNs..":
offices, the architect-engineer for the Virgil C. Summer Nuclear Station.
This documentation, together with the: records generated durng the testing program,:
operation, maintenance, inspection, modification, and events of the Virgil C. Summer Nuclear Station, as described in Sections 1.3.6.2 and 13.6.3, serve as a: recorded history of plant activities.
13.6.2        OPERATING RECORDS:
Preoperational and startup test records generated during the testing program are kept at the plant site along with: appropriate operating records.. These operating records include chemistry records; manuals and procedures; operating, maintenance, and testing records; special nuclear materials records; records and reports required by regulatory agencies; and administrative records.
                                  ... . ...                            .. . . ..13.6-1
                                                                                  .'  . .. ".... . . .. ..    . ... .A mnReformatted e ndme n t-0 2Per A W .. . . . .....-
 
The following replaces FSAR Section 17.2 in its entirety:
17.2 QUAUTY ASSURANCE DURING THEWOPERATIONS PHASE The description of the Quality Assurance Program atV.C. Summer Unit I Is found in the V.C. Summer Nuclear Station Unit 1 Quality Assurance Program Description (QAPD). The QAPD is governed by 10 CFR 50.54(a).
 
Document Control Desk Attachment VII CR-10-03108 RC-1 1-0006 Page 1 of 5 ATTACHMENT VII Comparison of Unit I QAPD to Units 2 & 3 QAPD
 
Document Control Desk Attachment VII CR-1 0-03108 RC-1 1-0006 Page 2 of 5 South Carolina Electric & Gas Co. (SCE&G) submitted V. C. Summer Nuclear Station (VCSNS) Units 2&3's Quality Assurance Program Description (QAPD) as Part 13 to VCSNS Unit 2&3's combined operating licensing application (COLA). The submitted QAPD has been subsequently revised in response to NRC request for additional information (RAI) and meets NEI Template 06-14 Revision 7, July 2009 "Quality Assurance Program Description" requirements. VCSNS Unit l's submitted QAPD was developed using NEI Template 06-14A Revision 7, August 2010. The following items identify the differences between the two NEI Template 06-14 revisions and Unit specific positions.
: 1. The title of Chief Nuclear Officer has changed from the position of Executive Vice President, Generation (EVPG) as depicted in VCSNS Unit 2&3's QAPD, Step 1.1.3 to the position of Senior Vice President, Nuclear Operations (SVPNO) as depicted in VCSNS Unit l's QAPD, Step 1.1.3. VCSNS Unit 2&3's QAPD will be revised.
: 2. Because of the organizational change described above, VCSNS Unit l's QAPD, Step 1.1.4 depicts the SVPNO as the CNO. VCSNS Unit 2&3's QAPD will be revised.
: 3. VCSNS Unit l's QAPD, Step 1.1.6 describes the position of Director, Nuclear Training. This position is responsible for both Unit 1 and Unit 2&3 training programs. This is a new position and VCSNS Unit 2&3's QAPD will be revised.
: 4. VCSNS Unit 2&3's QAPD depicts both a construction and operations organizational structure. VCSNS Unit l's QAPD depicts the current operations organizational structure.
: 5. The independent review requirements were relocated from NEI 06-14 Part II, Section 2 of Revision 7, July 2009 to NEI 06-14A Part V, Section 2 of Revision 7, August 2010. The independent review requirements are the same between the NEI template revisions. Both option 1 (independent review body) and option 2 (independent review committee) were adopted in both QAPDs.
 
Document Control Desk Attachment VII CR-10-03108 RC-1 1-0006 Page 3 of 5
: 6. The following are the selection of options when provided in the two NEI template revisions:
: a. As noted in Item 5 above both independent review options were taken in both VCSNS Unit 1 and Unit 2&3's QAPDs.
: b. Both QAPDs took option 1 in meeting NQA-1 -1994, Supplement 2S-1 to include the use of the guidance provided in NQA-1 -1994 non-mandatory Appendix 2A-1 the same as if it were part of the Supplement 2S-1. Both Regulatory Guides (RG) 1.8 Revision 3 and RG 1.28 Revision 3 require using NQA-1 -1994, non-mandatory Appendix 2A-1 for inspection and test personnel qualification.
: c. Both QAPDs took the optional alternative to NQA-1 -1994, Supplement 1OS-1, of the third bullet of NEI Template(s) Section 10.3.
: d. Part II, Section 13 of NEI Template 06-14A Revision 7, August 2010 added three optional clarifications / alternatives to QA requirements of NQA-1 -1994, Subparts 2.1, 2.2 & 2.3 which are}}

Latest revision as of 07:34, 13 January 2025

License Amendment Request - LAR-10-03108, Proposed Change to Relocate Administrative Control Requirements Related to Quality Assurance and Submittal of Quality Assurance Program Description (QAPD)
ML110810688
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/18/2011
From: Gatlin T
South Carolina Electric & Gas Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-11-0006
Download: ML110810688 (531)
v • d • e


Text

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