ML20126E677
| ML20126E677 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/03/1992 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20126E661 | List: |
| References | |
| NUDOCS 9212290263 | |
| Download: ML20126E677 (83) | |
Text
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V(D RANCHO SECO QUALl~Y MANUAL l
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NUMBER: RSQH - POLICY (O RANCHO SECO QUALITY MANUAL REVISION: 5
(/ PAGE 1 QF 2 LEAD DEPARTHENT: Qf]TgEDATE HELEAR_0VALIIY_ASSURAEE REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Clarified Policy Statements II and III to be consistent with statements made in Section II of RSQH regarding the applicability of and responsibility for the Quality
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Assurance Program.
- 3. Added " Revision Summary" page to this and all other sections of this Manual.
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NUMBER: RSQH - POLICY RANCHO SECO QUALITY MANUAL REVISION: S
( PAGE 2 0F 2 _
QUALITY ASSURANCE POLICY 5-~ The Sacram' ento Municipal Utility District's (SMUD) policy regarding Nuclear Quality Assurance is as follows:
I. Organizations involved in safety related activities shall be structured, managed, and operated to provide compliance with this manual.
Procedures and instructions shall be prepared to implement the activities required to provide direct support of the operation of Rancho Seco Nuclear Generating Station to achieve the following objectives:
- a. To comply with government regulations and established SMUD management policies and procedures, applying a systematic, disciplined and uniform approach to Quality Assurance.
- b. To perform assigner fork correctly the first time,
- c. To provide facilities which are designed, modified, constructed, tested and operated in accordance with specified requirements, with assurance against failure or malfunctions, and without undue, risks
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to the health and safety of the public.
- d. To ensure prompt identification and resolution cf actual and potential problem areas in design, procurement, corstruction, O testing, operations, maintenance and modification of safety related systems, structures and components.
5- II. The Rancho Seco Quality Assurance Program applies to activities, plans and programs affecting the operation and the quality of structures, systems, components, and services. This Program will be implemented by organizations responsible for achieving and verifying quality.
III. The Deputy Assistant General Manager, Nuclear has delegated the responsibility and authority for development and execution of the Rancho Seco Quality Assurance Program to Hanager, Quality Assurance. Any conflicts or questions involving interpretation of the requirements or resulting from the implementation of the Quality Assurance Program must be referred to the Manager, Nuclear Quality Assurance for resolution.
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Paul BenTer RiiiShetier Manager, (feputy
- Nuclear Quality Assurance Assistant General Manager, Nuclear
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- NUMBER: . RSQM -; TOC:
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-RANCHO SECO QUALITY MANUAL ; REVISION:c::6
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PAGE. 1-OF12-- 1 LEAD DEPARTMENT:'- .
= NUCLEAR- OUALITY~ ASSURANCE
-ggTgE'DATE 9
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REVISION.
SUMMARY
- 1. Deleted columns for " Latest Revision":and "Date of:-
Revision." This. control.is provided'through Nuclear:
Operating Records Management System via the-Procedures Control . group in Administrativ.e Services who maintain-litis-- '
status information. 1 i
- 2. ' Added " Revision Summary" page to-this and all othir sections of this Manual..
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NUMBER: RSQM - TOC r RANCHO SECO QUALITY MANUAL REVISION: 6
'( PAGE 2 0F 2
+ RANCHO SECO QUALITY MANUAL TABLE OF CONTENTS SECTION NO. TITLE 6+ Quality Assurance Policy
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I Organization II Quality Assurance Program III Design Control IV Procurement Document Control V Instructions, Procedures and Drawings VI Document Control -
VII Control of Purchased Material, Equipment and Services VIII Identification and Control of Haterials, Parts and Components IX Control of Special Processes X Inspection XI Test Control XII Control of Heasuring and Test Equipment XIII Handling, Storage and Shipping XIV Inspection, Test and Operating Status XV Nonconforming Haterials, Parts or Components XVI Corrective Action WII Quality Assurance Records XVIII Audits O
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I NUMBER: R5QM - SEC110N 1 RANCHO SECO QUALITY HANUAL REVISION: 7 PAGL_LOL 5 LEAD DEPARTMENT: EFFECTIVE DATE:
08-03-92 HUCLEAILOUALLILM5ufBNCE REVISION
SUMMARY
The following revisions were made to make the RSOM-Section I consistent with the Defueled Technical Specifications (License Amendment No. 119).
- 1. Added General Manager responsibility statement. (Para 4.1) --
- 3. Revised MSRC and PRC reporting chain. (Paras 4.5 and 4.6)
- 4. Revised MSRC review and audit .ictivities. (Para 4.6) .
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NUMBER: RSQM-SECTION 1 O RANCHO SECO QUALITY MANUAL REVISION:
EAGE 2 0F_5 7
- 1. ORGANIZATION 1.0 EURE0SE This section describes the Sacramento Municipal Utility District (SMUD) organizations and personnel responsible for establishing, implementing, and verifying the Quality Assurance Program at Rancho Seco Nuclear Generating Station.
2.0 REEIRENCLDOCUMENIS 2.1 10Cfr(50, Appendix B, Criterion I, Organtzat1on 2.2 ANSI N45.2-1971, Section 2, Organization 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants ,
2.4 Rancho Seco Technical Specifications. Section 6.0 0 3.0 E0LICI 3.1 The establishment and implementation of the Rancho Seco Quality Assurance Program shall be the responsibility of SMUD. Portions of the Quality Assurance Program functions may be delegated to other SMUD approved external organizations, but overall responsibility for the piogram is retained and exercised by SMUD.
3.2 Definitive lines of authority, responsibility and communication shall be established for those organizations involved in the Rancho Seco Quality Assurance Progthm.
3.3 Quality Assurance personnel assigned to Rancho Seco have defined responsibilities and organizational freedom to identify problems that affect quality; to initiate, recommend, or provide solutions; and to verify implementation of solutions. They have the authority to initiate action to stop unsatisfactory work pending implementation of necessary corrective action to bring the unsatisfactory conditions into conformance.
3.4 The organizational structure and functional responsibility assignments shall be such that attainment of program objectives is accomplished by individuals or groups who inspect, examine, audit or otherwise verify conformance to established requirements, and who are independent of the individuals or groups who performed the original activity.
- - - = . - _ - . _ - - . _ _ . ~ _ _ . - _ _ _ _ _ _ _ _ _ _ - _ - _ _
(N NUMBER: RSQM-SECTION I
( RANCHO SECO QUALITY HANUAL REVISION:
fAGL_ LDF 5 7
4.0 ORGANIZATION AND RESPONSIBILITIES 7+ 4.1 The General Manager (GM) through the Assistant General Manager (AGM) and Chief Operations Officer shall have corporate responsibility for overall safe operation of the facility and shall take any measures needed to ensure acceptable performance of the staff in coerating, maintaining, and providing technical
+ support to the facility to ensure NUCLEAR SAFETY.
4.2 The Deputy Assistant General Manager, Nuclear reports directly to the Assistant General Hanager (AGM) and Chief Operations Officer of the Sacramento Municipal Utility District. The Deputy AGH, Nuclear assures that Rancho Seco is properly staffed and adequately budgeted to safely carry out its responsib111ttes. Ho assures the staff responds to the recommendations of the Management Safety Review Committee (HSRC) and coordinates concerns relating to nuclear safety with the Manager, Nuclear Quality Assurance. -
The Deputy Assistant General Manager, Nuclear is responstb e for the safe and reliable decommissioning of Rancho Seco and reports to the AGM and Chief Operations Officer. The Deputy AGH has the
[ responsibility and authority for development and execution of the Rancho Seco Quality Assurance Program and ensures optimurr quality performance of Rancho Seco. In fulfilling this commitment, the Deputy AGM shall conduct a final review of Rancho Seco Quality Manual revisions and shall provide signature approval upon concurrence. The Deputy AGH has delegated cuthority and responsibility for development and execution of the Quality Assurance Program to the Manager, Nuclear Quality Assurance.
The Deputy AGH, Nuclear is responsible for the administrative actions necessary to assure that the Ran:ho Seco Quality Assurance Program is implemented by the organizations under his direction. To this extent, the Deputy AGM shall maintain a continuing involvement in quality matters and shall assess the scope, status, implementation and effectiveness of the Quality Assurance Program through Quality Status' Reports, Trend Analyses, Quality Audits or Surveillances and Management Safety Review Committee (HSRC) meeting minutes, f3 V
l NUMBER: RSQM-SECTION I
{q j RANCHO SECO QUALITY HANUAL REVISION:
PAGLJLOF S 7
4.3 The Manager, Nuclear Quality Assurance reports directly to the Deputy AGH, Nuclear, is independent from the pressures of other lines of authority, and ensures that an active Quality Assurance Program is Implemented at Rancho Seco in accordance with regulatory requirements.
The Hanager, Nuclear Quality Assurance shall have sufficient authority and organizational freedom to identify problems that affect quality, recommend solutions, and verify implementation of solutions as appropriate. Commensurate with this responsibility is the authority to initiate action to stop unsatisfactory work and control further processing, delivery, installation, construction or modification or nonconforming items, or continuation of nonconforming services / operations, pending correction of the unsatisfactory condition.
4.4 Corporate and on-site organizational responsibilities are described in greater detail in Rancho Seco Administrative -
Pro:edures. Specific duties and responsibilities for .
organizations whose activities affect quality are described in Sections 11 through XVIII of this manual.
~T 7++ 4.5 The Plant Review Committee (PRC) advises the Deputy AGH, Nuclear (V and the Management Safety Review Committee (HSRC) on all matters related to nuclear safety. The Committee composition, responsibility and authority, subjects to be reviewed, and reporting requirements are addressed in Section 6.0 of the Rancho Seco Technical Specifications and the PRC Procedure.
7+ 4.6 The Management Safety Review Committee (HSRC) advises the AGH and
+ Chief Operations Officer on facility operations. Composition, responsibility and authority of the HSRC as well as the subjects to be reviewed, administrative controls,.and reporting requirements are addressed in Section 6 of the Rancho Seco Technical Specifications and the HSRC Procedure.
The HSRC also functions to provide for an independent review and audit of designated activities in areas of:
7+ a. Facility Operation
- b. Engineering and Nuclear Engineering
- c. Chemistry and'Radiochemtstry
- d. Radiological Safety
+ e. Quality Assurance Practices
7 NUMBER: RSQM-SECil0N I
!. ) RANCHO SECO QUALITY MANUAL REVISION: 7
-_fAGE_LQL5 4.7 The Commitment Management Review Group (CHRG) is the senior management group responsible for reviewing all Potential Deviations from Quality (PDQ) to determine if a condition requires determination of the cause, extent, remedial corrective action and action to prevent recurrence. The CHRG reviews'and approves Deviation from Quality (DQ) dispositions and assigns action for implementation. The CHRG also determines whether a PDQ 15 potentially reportable under 10 CFR 21.
5.0 GENEIMLilLSP.0MSIDILIIIES Each organization involved In the design, o)eration, maintenance and modification of Rancho Seco is responst)le for describing and clearly defining the duties and authority of Individuals whose work affects quality. Each organization has the responsibility to ensure that their procedures implement the Rancho Seco Quality _
Assurance Program requirements. .
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RANCHO SECO QUALITY HANUAL fSfbH:
--- PAGE 1 OF 15
- LEAD DEPARTHENT: EFFECTIVE DATE*'
NUCLIAILOVAllILASSURANCE _
08-03-92 REVISION
SUMMARY
- 1. Updated References cited on Attachment 11-1 to agree with Defueled Technical Specifications. (License Amendment No. 119) i 1
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NUMBER: RSQM-SECTION 11 O RANCHO SECO QUALITY HANUAL REVISION: 6
.JAGE_2 RE_.15
- 11. QUALITY ASSURANCE PROGRAM 1.0 EUREQSE The purpose of this section is to describe the Quality Assurance Program which shall be implemented at Rancho Seco Nuclear Generating Station.
2.0 REEERENCES 2.1 10 CFR 50, Appendix B, Criterion II, Quality Assurance Program 2.2 ANSI N45.2-1971, Section 3 Quality Assurance Program 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants .
2.4 10 CFR 71, Subpart H, Quality Assurance Requireme0ts for i Packaging and Transportation of Radioactive Haterial 3.0 EQLICY 1he Quality Program described herein is designed to assure compliance with the requirements of 10 CFR 50, Appendix B.
" Quality Assurance Criteria for Nuclear Power Plants and fuel Reprocessing Plants," including the requirements of appitcable NRC Regulatory Guides, and ANSI Standards.
4.0 GENER&LJ1EQUIRBWIS 4.1 This Quality Manual is organized to present the Rancho Seco Quality Assurance Program in the order of the 18 criteria of 10 CFR 50 Appendix B. The nono 1 atates tne Rancho Seco policy for each of the criteria and describes how the controls pertinent to each are to be carried out. Any changes made to this manual that do not reduce the commitments previously accepted by the Nuclear Regulatory Commission (NRC) shall be submitted to the NRC at least annually. Any changes made to this manual that reduce the commitments previously accepted by the NRC will be submitted to the NRC and shall receive NRC approval prior to implementation. The submittal of the changes described above will be made in accordance with the requirements of 10 CFR 50.54(a).
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NUMBER: RSQH-SECTION !!
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RANCHO SECO QUALITY HANUAL REVISION:- 6 PAGL_1.0L15 4.2 The Rancho Seco Quality Assurance Program is implemented by organizations responsible for achieving quality and by organizations responsible for verifying quality.
The Hanager, Nuclear Technical Services is responsible to develop a Master Equipment List (MEL). The HEL is a list of equipment, that have been assigned an equipment 10. The HEL provides a ready reference for design and procurement information for each listed equipment. Q-List is a subset of the HEL, that includes I all equipment that have been assigned QA Class I or identified as '
requiring Environmental Qualification. The HEL 1s revised as a result of design changes.
1 4.3 The Quality Assurance Program applies to activities affecting the l operation and the quality of safety related structures, systems, l components, and services during plant operation, maintenance ;
testing and modifications, i Appropriate elements of this manual apply to emergency plans, radiation protection procedures, radioactive waste shipment I programs, fire protection, effluent control and environmental monitoring as indicated in Attachment 11-1, V 4.3.1 Attachment II-I illustrates minimal regulatory and licensing requirements; implementing procedures shall meet or exceed these requirements.
4.4 The programmatic Regulatory Guides and ANSI Standar's, d and the applicable revisions,.to which SHUD commits with regard to quality assurance _ matters and an appropriate explanation of-interpretations and exceptions are tabulated in Attachment Il-2' and 11-3 of this section.
4.5 The extent to which the Quality Assurance Program and its controls are applied are established as follows:
- a. SHUD uses the criteria specified in Technical Services Procedures for identifying structures, systems and components to which the Quality Assurance Program applies:--
- b. This identification process results in a HEL which identifies safety-related items. The HEL-is a controlled document. Safety-related items are determined by engineering analysis of the function (s) of plant structures, systems and components in relation to safe operation and shutdown; (7
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- c. The controls saecified in the Quality Assurance Program described in tils marual are applied to safety-related Items -
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O HUMBER: RSQH-SECTION 11
( RANCHO SEC0 QUAL.!TY HANUAL REVISION: 6
. _ _ PAGL_4_DE_15 4.6 Safety-related activities are accomplished under controlled conditions. Preparations for such activities include confirmation that prerequisites have been met.
4.7 Development, control, and use of computer programs affecting nuclear power plant safety-related design and operation are subject to appropriate controls.
4.8 Training and indoctrination programs shall be established to assure that personnel responsible for performing and verifying activities that affect quality have the required proficiency and qualifications to perform the assigned tasks.
4.9 Quality Assurance Program: Policy / Procedures / Instructions
- a. The Quality Assurance Program is documented by written Rancho Seco policies, procedures, and instructions. The overall policies and general requirements are outilned in the Rancho Seco Quality Manual (RSQH). Specific details related to implementation of the established quality policies are contained in the Rancho Seco Administrative Procedures (RSAP). Additional implementing procedures shall be prepared as required by the organizations responsible for
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performing the function. The quality organization reviews such procedures to assure that quality-related functions are accomplished in a controlled manner, with specified equipment, under suitable environmental conditions, and that prerequisites have been satisfied prior to inspection or testing.
- b. The Manager, Nuclear Quality Assurance is responsible for the preparation, issuance, and control _of the Rancho Seco Quality Manual.
- c. Proposed changes to the Quality Hanual shall be reviewed and approved by the Manager, Nuclear Quality Assurance and the-AGH, Nuclear. Requests to revise any portion of this manual shall be submitted in writing to the Manager, Nuclear Quality Assurance,
- d. The Rancho Seco Quality Manual, including any changes, supplements, or attachments, is issued and maintained as a controlled document.
- e. Rancho Seco Quality Manuals are assigned by'the Manager, Nuclear _ Quality Assurante to managers of departments. All changes will be distributed to the assignees and they will be responsible for inserting the revisions in their manuals.
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HUMBER: RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION: 6 PAGE _5_Or 15 4.10 Resolution of Differences The provisions delineated in the Rancho Seco Quality Manual shall take precedence over differing quality requirements specified in other departmental procedures until the Manager, Nuclear Quality Assurance has evaluated the issue and determined which requirement (s) are to be modified.
Questions on disputes involving interpretation of the requirements or implementation of this manual must be referred to the Manager, Nuclear Quality Assurance for resolution and/or initiating changes to commitments or procedures as necessary to resolve the differences.
4.11 Packaging and Transportation of Radioactive Material This Quality Assurance Program shall be applied to packaging and transportation of radioactive material as specified in Ref. 254.
S.0 ftESPONSIDILUIES General organizational responsibilities are described in O Section I, ORGANIZATION.
6.0 AUACllHENIS II-1, Application of Rancho Seco Quality Program Criteria 11-2, Regulatory Commitments 11-3, Exceptions O
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NUMBER: RSQH-SECTION II (T RANCHO SECO QUALITY HANUAL REVISION:
PAGE 6 Of 15 6.
ATTACHMENT 11-1 6+ - - -- - - - - --
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l r NUMBER: RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION: 6 PAGL LQP 15
. ATTACHMENT II-2 REGULATORY COHHITHENTS SMUD commits to the requirements of the regulations and industry standards listed below with any exceptions identified in Attachment 11-3.
DQCUMINI _Rfl151QHLDATE TITLE ,
- 1. Reg. Guide 1.8 Personnel Selection and Training
- As referenced in the Tech. Spec, i 2. Safety Guide 28 6/7/72 Quality Assurance Requirements ANSI N45.2 71 for Nuclear Power Plants
- 3. Reg. Guide 1.28 8/85 Supplementary Requirements for ANSI /ASME NQA-1 83 Quality Assurance Reco'rds (See -
Supplement 17!;-1 exceptionNo.1inAttachmentII-3);
- 4. Safety Guide 30 8/11/72 Quality Assurance Requirements ,
ANSI N45.2.4 72 for the Installation, Inspection, and l
l O Testing of Instrumentation and Electrical Equipment (See exception No. 2 in +
l Attachment 11-3)
S. Safety Guide 33 Administrative Controls for Nuclear Power Plants
- As referenced in the Tech. Spec.
- 6. Reg. Guide 1.37 3/16/73 Quality Assurance Requirements.for-ANSI N45.2.1 73 Cleaning Fluid Systems and Associated Components of Hater-Cooled Nuclear Power Plants (See exception No. 3 in Attachment-II-3) l 7. Reg. Guide.1.38 3/16/73 Quality. Assurance Requirements for ,
l ANSI N45.2.2 72 Packaging.. Shipping, Receiving, Storage l and Handling of-Items-for Hater-Cooled L Nuclear Power Plants (See exception No. 8 L in Attachment II-3)
'8. Reg. Guide 1.39 3/16/73 Housekeeping Requirements for Hater-ANSI N45.2.3 73 Cooled Nuclear Power Plants (See exception No. 4 in Attachment 11-3)
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NUMBER: RSQM-SECTION Il O RANCHO SECO QUALITY MANUAL REVISION:
IMGL_B_QF 15 6
ATTACHMENT 11-2 (Continued)
REGULATORY COMMITMENTS DQCUliEtil REVISlQlilDAR TIILE
- 9. Reg. Guide 1.54 6/73 Quality Assurance Requirements for ANSI N101.4 72 Protective Coatings Applied to Nuclear factitties
- 10. Reg. Guide 1.58 9/80 Qualification of Nuclear Power Plant ANSI N45.2.6 78 Inspection, Examination, and Testing Personnel (See exception No. 5 in Attachment 11-3) li. Reg. Guide 1.64 10/73 Quality Assurance Requirements for the ANSI N45.2.11 74 Casign of Nuclear Power Plants (See exception No. 6 in Attachment 11-3) -
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- 12. Reg. Guide 1.74 2/74 Quality Assurance Terms and Definitions ANSI N45.2.10 73 (See exception No. 7 in Attachment 11-3)
- 13. Reg. Guide 1.94 2 Quality Assurance Requirements for ANSI N45.2.5 78 Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
- 14. Reg. Guide 1.116 6/76 Quality Assurance Requirements for ANSI N45.2.8 75 Installation, Inspection, and Testing of Mechanical Equipment and Systems
- 15. Reg. Guide 1.120 11/77 fire Protection Guidelines for Nuclear Power Plants
- 16. Reg. Guide 1.123 7/77 Quality Assurance Requirements for ANSI ll45.2.13 76 Control of Procurement Items and Services for Nuclear Power Plants
- 17. Reg. Guide 1.144 1/79 Auditing of Quality Assurance Programs ANSI N45.2.12 77 for Nuclear Power Plants
- 18. Reg. Guide 1.146 8/80 Qualification of Quality Assurance Program ANSI N45.2.23 78 Audit Personnel for Nuclear Power Plants'
- 19. Reg. Guide 4.15 2/79 Quality Assurance for Radiological Monitoring Programs
.br') RANCHO SECO QUALITY MANU/,
NUMBER:
REVISION: 6 RSOM-SECTION II PAGE_ 9 0F_.15
. ATTACHMENT II-3 EXCEPTIONS EXCEPTION NO. 1: Reg. Guide 1.28/NQA-1. Supplement 175-1 j SHUD compiles with the recontnendations of this regulatory guide with the following clarifications:
Hith regard to Section 2.4 of Supplement 175-1 titled JAdu: The phrase "an index" is clarified to mean a collection of documents or indices which, when taken together, supply the information attributed to "an l
Index" in the standard. ,
1 The specific location of a record "within a storage area" may not be '
delineated (e.g. The specific location within a computer record file may l not be constant. Further, SMUD may utilize a computer assisted random l access filing system where such location could not be readily _i
" documented," or would such a location be " relevant.") The storatje location will be delineated, but where flie locations change with time, the specific location of a record wtthin that file may not always be documented.
With regard to Section 4.3, Supplement 17S-1 titled Safekeening:
Routino general office and nuclear site security systems and access controls are provided: No special security systems are required to be established for record storage areas.
With regard to Section 4.4, Supplement 175-1, titled Eacility: This Section provides no distinction between temporary and permanent facilities. To cover temporary-storage, the following clarification is added: " Records completed but not yet transferred for permanent storage may be temporarily stored in one-hour fire rated file cabinets. In general, records shall not be maintained in such temporary storage for more than four months after completion without being microfilmed or placed in permanent storage. Open-ended documents _ revised or updated on a more-or-less continuing basis over an extended period of time (e.g.
- personnel qualification and training documents, equipment history cards)
L which are cumulative in nature (e.g. nonconforming item logs and control
, room log books) shall become QA records when they are issued as a specific revision (e.g. the master audit schedule); when they are filled-up or discontinued (e.g log books or equipment history cards); on-a predefined periodic basis when the completed portion of the on-going document shall be transferred to records control as a " record" (e.g.
training and qualification records).
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NUMBER: RSOH-SECTION II RANCHO SECO QUALITY HANUAL REVISION: 6 PAGE 10 0F 15
. ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 2: REG. GUIDE 1.30/ ANSI N45.2.4-72 Spocific clarifications for ANSI N45.2,4 - 1972 are indicated below by sections.
Section 1.4 Definitions in this standard which are not included in ANSI N45.2.10 shall be used; all definitions which are included in ANSI N45.2.10 shall be used as clarified in SMUD commitment to Regulatory Guide 1.74.
Section 2.1 Planning requirements, as determined by engineering, shall be incorporated into modification procedures.
Section 2.3 Pro.cedures and Instruction; shall be implemented av set forth in Sections-II, III, V, X and XI of this program and by compliance with the Rancho Seco Plant Technical Specifications and Regulatory Guide 1.33 (ANSI.N18.7).
V Section 2.4 Result 1 will be implemented as set forth in Sections X, XI, and XVII of this program and by compliance with l ANSI N18.7 in lieu of the requirements set forth here.
Section 2.S.2 CAMbration and control-covers three classes of instrumentation used by SHUD: -(1) M&TE (portable measuring instruments, test equipment, tcols, gages, and non-destructive test equipment used la measuring and inspecting safety-related structures, systems, and components); (2) reference standards (primary, secondary, I transfer, and working); and (3) permanently installed
- process 1nstrumentation (PI).
With respect to the first sentence, H&TE and reference standards shall be included in calibration program and shall either be calibrated at,prescrib'sd Intervals or shall be calibrated prior to use. With respect to the last sentence, personnel shall be trained and procedures shall require that the calibration sticker shall be reviewed to determine callbration status. prior.to use:
This label shall be considered to clearly _ identify equipment which is out:of calibration. Lack of a sticker shall require record review and affixing a new sticker based on calibration data, H&TE and reference standards shall comply with sentences 2, 3 and 4.
NUMBER: RSQH-SECTION II RANCHO SEC0 QUALITY MANUAL REVISION: 6 PAGLlLOL15 ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 2: REG. GUIDE 1.30/ ANSI N45.2.4-73 (Continued)
Hith respect to the third sentence, SHUD uniquely identifies each safety-related component of permanently installed process instrumentation. This identification provides traceab111ty to calibration data. These actions are SMUD's alternative to the tagging or labeling of items to indicate the calibration date and the identity of the person who performed the calibration. Permanently installed process instrumentation shall comply with sentences 1, 2, and 5.
Section 3 Pntoni.truction Verification will be implemented as -
follows: -(1) is required only for m.3difications .{2) no special checks are required to be made by the person withdrawing a replacement part from the warehouse -
equivalent controls are assured by compItance with s
Regulatory Guide 1,38 (ANSI N45.2.2) as set forth in this s table, and, (3) shall be compiled with as determined by engineering, by individual technicians as part of the '
modification process.
Section 5.1 Inine.CtjDni, including subsections 5.1.1, 5.1.2, and 5.1.3, will be implemented as set forth in Section X of this program. The inspection program will incorporate, as determined by engineering and Quality those items Ilsted in these subsections.
Section 5.2 12111, including subsections 5.2.1 through 5.2.3. will be i implemented as set forth in Sections III and XI of this program. In some cases-Surveillance testing may be used to meet the appropriate requirements of this section.
Section 6 Post-Constructicn VRIlf1CAllRD is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval between installation and operation. Where considered necessary by engineering and Quality, the elements described in this Section will be used in the development ,
and implementation of inspection and testing programs as describe in Sections III, X, and XI of this program. -
- fm Section 7 Data Analysis and EvaluatlpD will be implemented as-Q stated herein after adding the clarifying phrase "Where used" at the beginning of that paragraph,
NUMBER: RSQM-SECTION II ~
O RANCHO SECO QUAL.ITY HANUAl. REVISION: 6 fAGL12_0Lli ATTACHMENT !!-3 (Continued)
EXCEPTIONS EXCEPTION NO. 3: REG. GUIDE 1.37/ ANSI N45.2.1-73 Specific clarifications for this Regulatory Guide and ANSI Na5.2.1 -
1973 are indicated below:
With regard to Paragraph C.3 of Regulatory Guide 1.37: The water quality for final flushing of fluid systems and associated components shall be at least equivalent to the quality of the operating system water, except for the oxygen and nitrogen content; but this does not infer that chromates or other additives, normally in the system water, will be added to the flush water.
With regard to Paragraph C.4 of Regulatory Guide 1.37: Expendable -
materials, such as inks and related products; temperature ind'cating sticks; tapes; gummed labels; wrapping materials (other than polyethylene); water soluble dam materit.ls; lubricants: NOT penetrant materials and couplants, desiccants, which contact stainless steel or O nickel alloy surfaces shall not contain lead, zinc, copper, mercury, cadmium and other low melting points metals, their alloys or compounds as basic and essential chemical constituents, no more than 0.1 percent (1,000 ppm) halogens will be allowed where such elements are leachable or where they could be released by breakdown of the compounds under expected environmental conditions.
With regard to Section 5 of ANSI N45.2.1 - 1973 titled InitallAtlon Clfta0109: The recommendation that loral rusting on corrosion resistant alloys be removed by mechanical methods is interpreted to mean that local rusting may be removed mechanically, but the use of other removal means is not precluded, as determined by engineering or Chemistry.
EXCEPTION NO. 4: REG. GUIDE 1.39/ ANSI N45.2.3-73 Specific classifications for ANSI N45.2.3 - 73 are indicated for specific sections below:
Section 1.4 N Linitions: Definitions in this Standard which are not included in Regulatory Guide 1.74 (ANSI H45.2.10) will be used: all definitions which are 'nciuded in ANSI N45.2.10 will be used as clartfled in SHUD's commitment to Regulatory Guide 1.74.
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NUMBER: RSQM-SECTION 11 O RANCHO SECO QUALITY HANUAL REVISION:
PAGL110L1L 6
ATTACHMENT 11-3 (Continued)
EXCEPTIONS EXCEPTION NO. 4: REG. GUIDE 1.39/ ANSI N45.2.3-73 (Continued)
Section 2.1 PjannlDg: SHUD may choose not to utilize the five-level zone designation system, but will uttitre standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety; and fire protection.
Cleanliness will be maintained, consistent with the work being performed, so as to prevent the entry of foreign r,,aterial into safety-related systems. This will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary (e.g. the opening is larger than the tools being uied) _
control of personnel, tools, equipment, and supplies will be established when the reactor system is opened for inspection, maintenance, modification or repair.
Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
Section 2.2 P.toceduteLand_ Ins _itucitons: Appropriate procedures will be written and implemented.
Section 3.2 ConttoLDLlactllties: SMUD may choose not to uttlize the five-level zone designation system, but will uttitze standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant and parsonnel safety, and fire protection.
Cleanliness will be maintained, consistent wtth the work being performed, so as to prevent the entry of foreign material into safety-related systems. This will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary, (e.g. the opening is larger than the tools being used) control of persc,imel, tools, equipment, and supplies will be established when the reactor system is opened for inspection, maintenance, modification or repair.
Additional housekeeping requirements will be implemented O as required for control of radioactive contamination.
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NUMBER: RSQM-SECTION II RANCHO SEC0 QUALITY HANUAL REVISION: 6 PAGL1LQF 15
. ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 5: REG. GUIDE 1.58/ ANSI N45.2.6 SHUD compiles with the recommendation of the regulatory guide with the following clarification.
With regard to Paragraph C.5: The Level III function of inspection planning.. reviewing and concurring with inspection, examination and testing procedures is performed by designated individuals from the Quality f, Industrial Safety Department.
EXCEPTION NO. 6: REG. GUIDE 1.64/ ANSI N45.2.11 i SMUD compiles with the recommendation of the regulatory guide with the following clarification: 6,,
Hith regard to Paragraph C.2: In exceptional circumstances, the designer's immediate supervisor can perform design verification, provided:
The supervisor is the only technically qualified individuci 1.
available.
- 2. The need is individually documented and approved in advance by the supervisor's management,
- 3. QA audits cover frequency and effectiveness of use of supervisors as design verifiers to guard against abuse.
EXCEPTION NO. 7: REG. GUIDE 1.74/ ANSI N45.2.10-73 SHUD complies with the recommendations of this regulatory guide with the following clarifications.
SHUD reserves the right to defbte additional words or phrases which are ,
not included in this Standard. -Such additional definitions will be documented in appropriate procedures.
In addition to the Standard's definition of " Inspection,"'SMUD will use the following: " Inspection-(when used to refer to activities.that are NOT performed by QC personnel) - Examining, viewing closely, scrutinizing, looking over or otherwise checking activities. Personnel performing these functions are not necessarily certified to Regulatory Guide 1.58 (ANSI N45.2.6)."
l c NUMBER: RSQM-SECTION 11 RANCHO SECO QUALITY MANUAL REVISION: 6 PAGE 15 0F 15 ATTACHMENT 11-3 (Continued)
EXCEPTIONS EXCEPTION NO. 7 (Continued)
When SMUD intends for Inspection to be performed in accordance with the QA Program by personnel certified as required by that program and for activities defined by " inspection" in ANSI N45.2.10, appropriate references to the plant QC organization or the procedures to be used for perfor?ln; the activity will be made. If such references are NOT made, inspections are to be considered under the additional definition given above.
"Independens .erification": - Verification by an individual other than the person who performed the operation or activity being verifled that required actions have been completed. Such verification may not .
necessarily require confirmation of the action at the physical location if adequate remote indication of completion of action is available, in determining the acceptability of remote verification, the consequences of the action not being 1007. completed and the validity of the remote indication for confirming the completion of the desired action will be O considered. Examples include, but are not limited to: Verification of a breaker opening by observed remote breaker indication lights; verification of a set point (made with a voltmeter or ammeter for example) by observing the actuation of status or indicating lights at the required panel-meter indicated value; verification that a valve has been positioned by observing the starting or stopping of flow on meter indications or by remote valve positions indicating lights.
" Hill" - (Not defined in any ANSI Standard) - Means the same as "shall" except when used to denote simple futurity. When used to denote futurity, "will" is normally followed by "be".
EXCEPTION NO 8: REG. GUIDE 1.38/ ANSI N45.2.2 Section 2.7 CIA 55Hicat10tLQfliCE$ - SMUD may choose not to utilize the four level classification of items, but will address packaging and storage requirements for items based on the needs of individual items and manufacturers recommendation.
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(] RANCHO SECO QUALITY HANUAL 1.EAD DEPARTHENT:
A Or 5 QIjg[gEDATE l
liUCLDULOUALLILAMURAliCE i
)
REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, i responsibilities and requirements. !
- 2. Added " Revision Summary" page to this and all other sections of this Manual. !
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NUMBER: RSQM-SECTION III REVISION: S O RANCHO SECO QUALITY HANUAL PAGL_2_.0F 5
!!!. DESIGN CONTROL 1.0 PUREQSE This section describes the Quality Program measures established for control of design activities affecting structures, systems and components at the Rancho Seco Nuclear Generating Station.
In addition, this section also defines the requirements for the development and implementation of control measures to assure that design functions affecting performance of operational, construction and modification activities are carried out in a planned, controlled, and orderly manner and are in compliance with applicable regulatory commitments.
2.0 REELRfJiCES 2.1 10CFR50, Appendix B Section III, " Design Control',' .
2.2 10CFR50.49, " Environmental Qualification of Electrical Equipment" 2.3 10CFR50.59, " Changes Tests and Experiments" 2.4 Reg Guide 1.64/ ANSI N45.2.11, 1974, " Quality Assurance Requirements for the Design of Nuclear Power Plants", with exceptions noted in Section II of this manual.
2.5 ANSI N45.2, Section 4, " Design Control" 3.0 20LICY The requirements specified in this section apply to all organizations performing design functim s for modifications, changes, replacement or additior cr strsctures, systems or components at Rancho Seco, p
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NUMBER: RSQM-SECTION III
/T RANCHO SECO QUALITY tMNVAL REVISION: 5 V PAGE 3 0F 5 4.0 GENERAL REQUIREMENTS Procedures shall be established and executed to control design activities. Procedures covering design control activities shall include the following requirements:
4.1 Applicable design inputs such as design bases, regulatory requirements, codes and standards, methodology and all assumptions with appropriate justifications are identified, documented and correctly translated into design output documents such as specifications, drawings, procedures or instructions.
4.2 Exceptions, waivers to or deviations from engineering requirements are documented and controlled.
4.3 Hethods are specified for the selection and classification of suitable materials, parts, equipment, and processes used in meeting applicable requirements for structures, systems and components. .
Materials, parts,com)onentsandequipmentwhicharestandkrd, commercial (off-the-sielf) or which require environmental qualification, or which have been previously approved for other
(_l V
similar applications are reviewed for suitability and appropriately classified.
4.4 Systematic methods are established for communicating and controlling the flow of related design information across the external and internal design interfaces, including any changes to the design information as the work progressss.
4.5 Interfaces between the Nuclear Technical Services Department and other participating design organizations (either internal or external to SHUD) are identified and documented. This identification include: those organizations providing design inputs, design analyses, design specifications, and design verification for operational, construction and modification design activities.
4.6 Participating design organizations establish and describe the controlled methods for preparation, review, approval, release, distribution, and revision of documents (such as design analyses, specifications, drawings, reports) involving design interfaces.
4.7 Verifying or checking the adequacy of design for modifications or changes performed. Acceptable verification methods include, but are not-limited to design reviews, alternate calculations or qualification testing. If a test program is used to verify the 7m adequacy of a design, it must include qualification testing of a Q prototype unit under the most adverse design conditions.
NUMBER: RSQH-SECTION III
/7 RANCHO SECO QUAT.ITY MANUAL. REVISION: 5
() PAGE. 4 0F 5 4.8 ' Computer program codes used for design calculations are certified for use and their use is specified.
4.9 Design verification is performed by competent individuals or groups other than those who performed the original design but who may be from the same organization. This verification may be performed by the originator's supervisor provided the supervisor is the only technically qualified individual available and meets the appropriate clarification provisions of Ref. 2.4. The results of the design verification efforts must be documented with the identification of the verifier c1carly provided.
4.10 Provisions are specified for the control of design analyses such as reactor physics, stress, thermal, hydraulic, and accident; compatability of materials; accessibility for inservice inspection, maintenance, and repair; and delineation of acceptance criteria for inspections and tests.
4.11 Design problems which are identified during field installation or testinj activities shall be documented and forwarded to the Nuclear Technical Services Department for evaluation and resolution.
4.12 Design and specification changes, including field changes, O's receive the same degree of control and ap)roval as the original design unless another qualified, responsi)1e organization is specifically designated.
4.13 Errors and deficiencies in the design process, including computer programs, that could adversely affect structures, systems or components are documented and corrective action is taken to preclude repetition.
4.14 Proposed modifications or design changes which involve an unreviewed safety question or a change to the Rancho Seco Technical Specifications are handled in accordance with the requirements of 10CFR50.59.
4.15 Modifications are reviewed by plant personnel for effect on plant operation prior to making the modification operational.
4.16 Design documents are reviewed for accessibility of equipment and components for inservice inspection, tests, maintenance or modifications.
4.17 Design and/or test documentation must be obtained from all suppliers on procurements of ASME code components used for replacement or modification to Rancho Seco.
C's V
n RSQM-SECTION III ~
RANCHO SECO OVALITY HANUAL ,
PAGE 5 0F 5 5.0 ,
RES20llSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 Manager, Nuclear Technical Services is responsible for implementing a design control process per this section and to:
- a. Provide and control design change packages.
- b. Optimize nuclear fuel value and reactor safety by managing.-
fuels management and core analysis,
- c. Ensure integrity and regulatory conformance of configuration control,
- d. Provide plant configuration control including establishing and maintaining baseline documents.
- e. Provide coy uter engineering support for plant computers, IDADs. training simulator, etc. r
- f. Perform probabilistic analysis in support of plant design,
- g. Provide engineering cupport to Nuclear. Power Productt n.
h h. Provide and maintain engineering procedures, standards and
- specifications and drawings.
- i. Provide technical support.to maintain the training simulator operable and within plant configuration.
- j. Prepare and maintain.the Master Equipment List described in-Section II.
5- - 5.2 The Manager,: Nuclear Quality Assurance is responsible for:
- a. Review and concurrence ofl design control procedures.
- b. Monitoring implementation of the Design Control Program,
- c. Auditing'the Design Control Program per Section XVIII of this manual.
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NUMBER: RSQH - SECTION IV REVISION: 5 O RANCHO SECO QUALITY MANUAL LEAD DEPARTHENT:
PAGE 1 0F 5 grgTgEDATE RUCLEAR_00ALITY ASSURMCE REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Sumary" page to this and all other sections of this Manual.
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I NUMBER: RSQH-SECTION IV RANCHO SECO QUALITY MANUAL REVISION: 5 O' PAGE 2 0F 5 IV. , PROCUREMENT DOCUMENf CONTROL 1.0 WR201E This section describes the Quality Program measures established to control procurement documents for material, equipment and services at the Rancho Seco Nuclear Generating Station.
2.0 REEEELMCE_00CUMERIS 2.1 10CFR50 Appendix B, Criterion IV, Procurement Document Control 2.2 ANSI N45.2-1971, Section 5. Procurement Document Control 2.3 Reg Guide 1.123/ ANSI N45.2.13-1976, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants .
3.0 00LICY O Procurement documents for Rancho Seco materials, equipment, components / spares or services shall include applicable technicr.1 requirements, quality requirements, regulatory requirements and other provisions necessary to assure that purchased items and services are adequately described to the supplier.
4.0 GENERAL __REQQIREMENTS 4.1 Procedures shall be established and implemented to control the preparation, review, approval and issuance of procurement documents.
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NUMBER: RSQH-SECTION IV RANCHO SECO QUALITY MANUAL REVISION: 5
.i PAGE 3 0F 5 4.2 Procurement documents shall include provisions for ihe following, as applicable:
- a. Description of item or service.
- b. Identification of design specifications and technical requirements by reference to specific drawings, codes, regulations, industry standards or other documentation, including the applicable revision thereto, that describe the items or services to be furnished.
- c. Identification of test, inspection and acceptance requirements, and any special instructions and requirements for activities such as design, fabrication, identification, cleaning, erecting, packaging, handling, shipping and extended storage.
- d. Identification of applicable QA Program criteria.
- e. Applicability of 10 CFR 21. .
- f. Identification of the documentation, such as drawings, specifications, procedures, fabrication and inspection plans, inspection and test records, personnel and procedure O' qualifications, and chemical and physical test reports to be prepared and maintained by the supplier or contractor, and requirements for submittal to SHUD for review anti approval,
- g. Identification of those records to be retained, controlled and maintained by the supplier or contractor and those to be delivered to SHUD at the time of shipment of the procured item.
- h. SHUD's right of access to the supplier's facilities and records for inspection and audits.
- 1. Extension of applicable requirements to lower tier subcontractors and suppliers, including SHUD's right of access to facilities and records.
- j. Supplier submittal of nonconforming items and SHUD approval for " Accept-as-is" or " Repair" dispositions of nonconformances.
- k. SHUD's right to hold shipment if procurement document requirements, including those for documentation, have not -
been fulfilled.
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NUMBER: RSQM-SECTION IV RANCHO SECO QUALITY MANUAL REVISION: 5
)n) PAGE 4 0F 5 4.3 ' Technical and quality review by qualified personnel and approval l by designated individuals shall be performed prior to issuance of the procurement document. The review and approval shall be-documented and available for verification.
4.4 Review and concurrence by Quality shall be performed to assure adequacy of quality requirements and to verify that the requirements are correctly stated, inspectable and controllable; that there are adequate acceptance and rejection criteria; that the procurement documents have been prepared, reviewed and approved in accordance with the requirements of the established procedures.
4.5 Materials Group shall verify that the supplier is on the Approved -
Suppliers List (ASL).
4.6 Revisions to procurement documents shall receive an equivalent $
review and approval as the original documents. Exceptions to this include changes in quantity, estimated price, cost codes, taxes, format or editorial changes that do not affect the quality of the item or service. r 4.7 Procurement documents for spare or replacement parts for safety-related structures or systems shall specify procurement controls
(' at least equivalent to those required.for purchase of the
(
original equipment.
4.8 Methods shall be established to assure that the items received-are trLo: J'le to procurement documents..
5.0 BESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 Manager, General Services is responsible to:
- a. Purchase items in conformance to procurement documents.
- b. Purchase safety-related items from approved suppliers.
- c. Arrange for suppliers to be placed on the Approved Suppliers List.
- d. Arrange for source inspection when specified on the procurement documents.
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, . NUMBER:- RSQM-SECTION.IV--
J/~N =
RANCHO _SECO QUALITY: MANUAL REVISION: 5:
PAGE '5 0F 5 -j 5.2 ,
The Manager, Te hnical: Services;is:responsibleifor: _ j 5- '
- a. Maint(0- a' staff-of qualified Engineers: wh'o provide.
technis r, and quality requirements = for purchasing <
~ safety-related items.-
' 5-~ 5.3 ' The Manager, Nuclear Quality Assurance-is._ responsible _for:; )
- a. - Review and concurrence of. material management ~ procedures.
.i
- b. Review and concurrence of. procurement documents for.
safety .related- items.:
Auditing the procurement program per Section XVIII'of this
. c.
manual,
- d. Developing and maintaining an Approved Suppliers' List.
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RANCHO SECO QUALITY HANUAL fgfh.RSW-SECTIONV
)
PAGE 1 OF 3 _i LEAD DEPARTHENT:
INhlhyEDATE fiUCLEAR 00ALITY ASSURANCE .
REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. d "R v s n Summary" page to this and all other sections l app
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v N F01V A" O N O N _Y u, ,
NUMBER: RSQM-SECTION V
- \ RANCHO SECO QUALITY MANUAL REVISION
- 'S
(,1 PAGE 2 0F 3 V. , ' INSTRUCTIONS, PROCEDURES AND DRAWINGS 1.0 13JREQS1 This section describes the Quality Program measures established to assure that all the activities affecting the quality or safety of the Rancho Seco Nuclear Generating Station are described and accomplished in accordance with documented instructions, procedures, drawings or other documents appropriate to the circumstances.
Ii 2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion V Instructions, Procedures and Drawings 2.2 ANSI N45.2-1971, Section 6. Instructions, Procedures and Drawings 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants
~
k 3.0 POLICY Activities affecting the operational safety or quality performance at Rancho Seco shall be described by and implemented in accordance with documented instructions, procedures, and drawings.
4.0 GENERA.L REOUIREMENTS 4.1 Hritten instructions, procedures, drawings, or other documents appropriate to the circumstances shall be prepared to provide measures for complying with the provisions of the Rancho Seco Quality Program.
4.2 Instructions, procedures, or drawings shall include applicable quantitative and/or. qualitative acceptance criteria for verifying that the activities have been satisfactorily accomplished.
4.3 The responsible organizations shall establish procedures which define responsibilities and delineate the sequence of actions to be accomplished in the preparation, review, approval and control-of instructions, procedures, or drawings, and changes thereto.
p 4.4 Activities affecting quality shall be accomplished in accordance
.g with approved instructions, procedures, and drawings.
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'f.-.Y. .R N'A CHO-SECO QUALITY MANUAL - REVISIONi -. 5~-
b);
'PAGE 3 ' 0F_]
f 5.0; ,
RESPONSIBILITIES- ,
4- c Genera 11 organizational.-responsibilities, are" described in: I
^
. Section_I,> ORGANIZATION.- .'s
. : <. . . 4 5-~- 5.1 :
The manager'of each department is responsible!to. assure--that
- activities .affecting quality performed by their departments::are +-
described in instructions,-p'rocedures-and drawings." ,,
- 5.2 'The Manager,' Nuclear Quality Assurance is-responsibleitolperform . I audits' toiverify that any nctivitiesiaffecting quality are' ' .
- described.in instructions procedures and' drawings. Audits shallf .
be conducted in accordance with Section XVIII of this: manual.-
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RANCHO SECO QUALITY MANUAL REVISION: S O.- PAGE - 10F ?
LEAD DEPARTHENT: ggTgEDATE
!!UCLEAR 00ALITY A[SURAMCE REVISION
SUMMARY
- 1. Upaated to reflect current organizational titles, responsibilities and requirements.
- 2. Clarified wording to correlate the requirements with those described in the referenced ANSI Standards and to be consistent with Section II of this Hanual.
- 3. Added " Revision Sumary" page to this and all other sections of this Manual.
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- m. NUMBER:l -RSQM-SECTION VI f~Y RANCHO-SECO QUALITY MANUA(. , - REVISION:' 5 ,
?j PAGE- 2 0F 3-
- _ +
L VI. ,- 00C1 MENT CONTROL -
l' 0 15hTQSE <
This_section describes the Quality Program measures established '
for the issuance and control of documents.that control' activities' affecting quality.at_ the Rancho Seco Nuclear Generating Station. 1 2.0 REEDlENCE DOCUMEMIS 2.1 10CFR50, Appendix B, Criterion VI, Document Control 2.2 ~ ANSI N45.2-1971, Section 7. Document Control 5-~ 2.3 ANSI N45.2.ll-1974, Section 7 Document Control
- 3.0 POLICY i r
Applicable documents, including. changes thereto,-.that prescribe:
activities affecting-the quality operation at Rancho Seco shall-(~T be issued'and controlled in a manner that precludes 1the use of
\_f inappropriate or outdated documents.
4.0 GENERAL _ REQUIREMENTS 5- 4.1 Procedures shall be established for'the-review, approval, issuance, change-and.use of documents that specify quality requirements such as instructions, procedures, drawings ~and other ,
documents-which implement the quality assurance program.
4.2 Procedures which establish document control measures-shall
-include:
- a. Identification of documents-to be controlled;
- b. Identification of- individuals or organizations responsible for the review, approval, issuance and revision-of_ documents;
- c. Criteria to ensure that' adequate technical and quality
-- requirements are-incorporated prior-to implementation;.
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RANCHO SECO QUALITY HANUAL hfh5N:
) PAGE 3 0F 3 5- , d. Review of changes to documents by the same organizations
- that performed the initial review and approval or by the organizations designated in accordance with the applicable procedures.
4,3 Controlled documents, including changes, shall-be issued and distributed to organizations noted on distribution lists so that proper and current documents are available as required, and obsolete or superseded documents are identified and not used for prescribed activities.
4.4 Master lists or equivalent means shall be used to identify the current revision of controlled documents, and shnll be made
- available at work locations as appropriate.
5.0 RESPONSIllILITIES General organizational responsibilities are described in -
Section I, ORG/,NIZATION. , g 5- 5.1 The Supervisor, Document Control is responsible for developing and implementing a document control program in accordance with f~') this section.
v 5.2 The Manager of each department is responsible for:
- a. Defining document review, approval and revision authority in department procedures,
- b. Providing for a review of documents for concurrence with quality assurance-related aspects by the Nuclear Quality Assurance Department as appropriate.
5.3 The Manager, Nuclear Quality Assurance is responsible for:
- a. Review and concurrence of document control procedures,
- b. Review and concur with procedures, instructions or documents-that implement the Quality Program to assure compliance with the applicable provisions of this manual.
- c. Auditing the document control program per Section XVIII of this manual.
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NUMBER: RSQH - SECTION VII-RANCHO SECO QUALITY MANUAL REVISION: -S O LEAD DEPARTHENT:
PAGE 1 0F 4 EFFECTIVE DATE NUCLEAR OVALITY ASSURANCE 10-23-91 REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Sunanary" page to this and all other sections of this Manual, 1
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NUMBER:. RSQM-SECTION VII
- REVISION: 5 RANCHO SECO QJALITY MANUAL
-(h PAGE 2 0F 4
- VII.- , ' CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 4
1.0 filR00SE This section describes the Quality Program measures established to assure that material, equipment and services purchased for-the Rancho Seco Nuclear Generating Station conforms to the procurement documents.
2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion VII.. Control of Purchased Haterial, Equipment, and Services 2.2 ANSI N45.2-1971, Section 8. Control of Purchased Haterial, Equipment, and Services 2.3 Reg. Guide 1.123/ ANSI N45.2.13-76.-Quality Assurance Requirements for Control of Procurement of Items and Services for Nucleir Power Plants 3.0 EOL12 Heasures shall be established to assure that material, equipment and services conform to the specified requirements of the related procurement documents.
4.0 GENERAL REOUIREMENTS 4.1 Control of purchased material, equipment and services shall include the following, as appropriate:
- a. Source evaluation.and selection of suppliers.
- b. Objective evidence of quality furnished by the supplier.
- c. Source inspection, audit, and/or surveillance activities,
- d. Examination of items or services upon delivery or completion.
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NUMBER: RSQH-SECTION VII REVISION:
,% RANCHO SECO QUALITY HANUAL S PAGE 3 0F 4 Q _
4.2 , Source evaluation and selection of suppliers shall be based on
-one or more of the following criteria:
- a. An evaluation of the Supplier's QA Program /Hanual/ Procedures,
- b. Review and evaluation of historical quality performance data,
- c. Supplier audits by SHUD or by utility groups to which SMUD belongs.
- d. Utilities holding Nuclear Plant Operating Licenses
- e. ASME Hanufacturer/Haterial Supplier Certificate of Authorization.
Results of source evaluation shall be documented and retained on file. Acceptable suppliers shall be listed on SHUD's Approved Supplier List which is controlled by the Nuclear Quality 5-- Assurance. _
4.3 Procedures for control of materials, equipment and services shall address the following:
- a. Responsibilities of departments performing supplier technical and quality evaluations, and the method of -
evaluation.
- b. Inspection activities that specify the characteristics or processes to be witnessed, inspected or verified; the method of verification and the extent of documentation required; and the organization responsible for implementing the inspection,
- c. Auditing to verify conformance and implementation to requirements of this policy. Source inspection and audits-may not be necessary when conformance of an-item to procurement requirements can be verified by receipt inspection, review of test reports, certified reports or other means specified by the Manager, Nuclear Quality 5-~ Assurance.
- d. Receipt inspection of supplier furnished items to assure:
(1) the proper identification of items on the receiving .
documentation, (2) that the items are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use (3) that inspection records or certificates of conformance are available at the plant site prior to installation or use of the items, and (4) that items accepted and released are identified as to their inspection status prior to storage or use.
RANCHO SECO QUALITY HANUAL hN: 5
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- e. Review, acceptance, and maintenance of records to assure ,
adequacy of documentation that-identifies the purchased item, and that specific procurement requirements (e.g.,
codes, standards, specifications) have been met or satisfied.
- f. Review and approval of documentation required to be submitted by the procurement documents (CHTR's, C of C, Procedures, Specifications, etc.).
- g. Procurement control of spare or replacement parts for safety-related systems to assure compliance with requirements that are equivalent to the original item, or those'specified by a properly reviewed and approved revision to the original requirements.
5.0 RESP 0tGIBILITIES -
T General organizational responsibilities are described in Section I, ORGANIZATION.
(~}
tj 5.1 Hanager, Nuclear Technical Services is responsible to:
- a. Ensure quality and qualifications of parts and materials by
- managing definition of quality specifications, and storage in accordance with regulatory requirements, in close cooperation with maintenance and operations.
- b. Ensure regulatory compliance of materials and parts by managing documentation, and review (and implementation as appropriate) of NRC and related parts / materials bulletins.
- c. Examination of items or services upon delivery or completion, as deemed necessary to. supplement-or replace formal inspection activities.
5- 5.2 The Manager, Nuclear Quality Assurance is responsible'for:
- a. Developing and maintaining an Approved Suppliers List.
- b. Performance of required inspections, evaluations, and-audits,
- c. Review and concurrence with material management procedures.
- d. Auditing the Materials Management Program in accordance with Section XVIII of this manual.
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RANCHO SECO QUALITY HANUAL N
A ASSURANCE REVISION
SUMMARY
1.
Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Add "R v Sumary" page to this and all other sections
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t PAGE 2 0F 4 VIII. . ' IDENTIFICATION AND CONTROL OF MATERIALS, PARTS & COMPONENTS 1.0 PURPOSE This section describes the Quality Program measures established to provide for the identification and control of material, parts and components for the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMEXIS 2.1 10 CFR 50, Appendix B, Criterion VIII, Identification and Control of Materials, Parts and Components 2.2 ANSI N45.2-1971 Section 9. Identification and Control of Materials, Parts and Components 3.0 NLLCY ) l Procedures shall be established and implemented to assure that j materials, parts or components are properly identified and
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controlled to preclude the use of incorrect or nonconforming v items.
4.0 GENERAL REOUIRENENTS 4.1 Materials, parts or components, including partially fabricated subassemblies and consumables, shall be identified such that they can be related to their applicable drawing, specification, purchase document and inspection records at any stage from initial receipt through fabrication / construction, installation, repair, modification or use.
4.2 Identification, controls, implementation procedures and documentation shall be used to ensure that only correct and accepted items are used during all stages of construction, installation and operation, q
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NUMBER: RSQH-SECTION VIII nl_. RANCHO SECO QUALITY MANUAL REVISION: 5
! PAGE 3 0F 4
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4.3 Unique identification of items is required, e.g., by part number,
' ' serial number, heat number, drawing _ identification number or other traceable coding methods.
4.4 Identification is required to be maintained either on the item or on records traceable to the item. Physical identification, such as by marking or tagging, shall be used to the maximum extent practical.
4.5 Hhen specified by codes, standards, procurement documents, or other requirements, trentification.is required such that items are traceable to appropriato documentation (e.g., specifications, drawings, purchase orders, manufacturing and inspection documents, nonconfoimance reports, physical or chemical mill test reports).
4.6 Where identification marking is employed, the marking is required to be clear, unambiguous and indelible, and shall be applied such' as not to affect the fit, function or quality of the item. . :.
4.7 Markings shall be transferred to each part of an ittm, if subdivided. The markings shall not be obliterated or hidden'by.
surface treatment or coatings unless other means of G identification are substituted.
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4.8 Procedures are required to provide for the verification and documentation of correct identification of items. prior'to release for use. Items may be conditionally released under adequate procedural controls.
4.9 Bulk consumables (such as weld rod, chemicals, reagents, gases, resins, lub"cating oil and grease, fuel oil, cleaning solvents, etc.) are required to be identified and controlled in accordance with approved procedures that specify the applicable requirements for identification and use of the consumables.
4.10 in the event the identification or traceability of an item is lost, it shal'1 be handled ~ in accordance with Section XV of this -
manual.
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RSQM-SECTION VIII-RANCHO SECO QUALITY MANUAL [ fsf h PAGE 4 0F 4 -
5.0 ,
RESPONSIBILITIESE
- General ~ organizational responsibilities are described-in Section I, ORGANIZATION.
5.1 The Manager, General Services is_ responsible for identification
- and' control of items from procurement through withdrawalifrom the warehouse. ,
5.2 The Manager, Nuclear Maintenanc'e is'. responsible for maintaining
- identification and control of items- from withdrawal from the warehouse.through installation.
5-* 5.3 The Manager, Nuclear Quality Assurance is responsible for:
- a. Review and concurrence of procedures.for controlling; material, parts and components from procurement through:
storage, issuance and installation,
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- b. Auditing the process for identification and control of materials, parts and components in accordance with- Section-XVIII of this manual.
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NUMBER: RSQM - SECTION IX REVISION: 6 O RANCHO SECO QUALITY MANUAL LEAD DEPARTMENT:
PAGE 1 0F 3 ggTgEDATE tiUCLEAR 00ALITY ASSURANCE REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Summary" page to this and all other sections of this Manual. ___
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NUMBER:= RSQH-SECTION IX
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RANCHO SECO QUALITY HANUAL REVISION:
PAGE 2 0F 3 6
IX. CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE This section describes the Quality Program measures established to govern special processes used at the Rancho Seco Nuclear Generating Station.
2.0 REEEREEE. 00CUMENTS 2.1 10CFR50, Appendix B, Criterion IX, Control of Special Processes 2.2 ANSI N45.2-1977, Section 10. Control of Special Pra cesses 2.3 ASME Section V and IX s
3.0 POLICY , {
Procedures shall be established and implemented to assure that special processes, and equipment are controlled and that ttie activities are accomplished by qualified personnel and procedures.
4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be prepared to provide for proper control of special processes, which include welding, heat treating, chemical cleaning, application of protective coatings and nondestructive examination (NDE).
4.2 Controls shall be established to assure'that only approved materials and equipment are used to perform special processes.
4.3 Personnel who perform special processes shall be qualified in accordance with industry standards.
4.4 Special process requirements shall be prescribed in the controlling specifications, drawings, procurement documents or procedures.
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i NUMBER:- lRSQM-SECTION IX; V 's RANCHO SECO QUALITY MANUAL.; . REVISION:: 6 (j - PAGE -3 0F 3 5 .'O RESPONSIBILITIES-
- General organizational;tesponsibilitiesiare-describedLin-
- Section I,: ORGANIZATION..
5.1 - Manager. Nuclear Technical Services-is responsibleifor:'
- a. Specifying the special processes lon design documents:
governing-maintenance / modifications activities. ,
- b. Developing _ qualifying, and: maintaining special process .
procedures identified in Para =4.1 of this section. ,
- c. Qualifying personnel to perform special processesi identified-.
in Para 4.1 of this section.
- d. Performing NDE other than those-listed in 5.2.b.
6-~ 5.2 , ~ The Manager, Nuclear. Quality Assurance is responsible'fori; :
L.
- a. Review and concurrence of special process procedures.r--
- b. . Performing NDE on Maintenance /Modificationf Activity,
- c. Auditing the special, process:-program in-accordance with
-Section-XVIII of this: manual. ,
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NUMBER: RSQM - SECTION X O RANCHO SECO QUALITY MANUAL REVISION:
PASL_J OF 4 6
LEAD DEPARTHENT: EFFECTIVE DATE:
WCLEAR 00ALITY ASSURANCE 12-01-92 REVISION
SUMMARY
- 1. Remove ASME Code Section XI requirements.
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, NUMBER:- RSQM-SECTION.X REVISION: 6 s
'~ )- RANCHO SECO QUALITY HANUAL
-PAGE 2 0F 4 X. ,
INSPECTION 1.0 EURE01E This section describes the Quality Program measures established to provide for the inspection of material, parts and components for the Rancho Seco Nuclear Generating Station.
2.0 REEERENCE DOCUMERIS 2.1 10CFR50, Appendix 8, Criterion X, Inspection 2.2 ANSI N45.2-1971, Section 11, Inspection 2.3 Reg Guide 1.58/ ANSI N45.2.6-78, Qualification of Nuclear Power Plant Inspection, Examination and. Testing Personnel with .
exceptions noted in Section II of this manual, g 2.4 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants
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- 3.0 EOLLCI L
l Procedures shall be establ.ished and implemented to assure that inspections are performed to verify compliance with specified requirements at Rancho Seco.
4.0 GENERAL REOUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and-6+ modification activities to verify that items and activities
+ conform to_specified requirements _.
4.2 Inspection planning documents shall be prepared or reviewed by the Nuclear Quality Assurance in accordance with established j procedures. Inspection-planning documents shall' identify the following as applicable:
- a. Characteristics and activities to be inspected;
- b. Inspection organization;
- c. Accept / reject criteria; p),
- d. Hold points and/or witness points; (f
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- NUMBER: R50M-SECTION X
'/ RANCHO SECO QUALITY MANUAL REVISION: 6 b PAGE 3OL4
,' e. Inspection Methods;
- f. Provisions for recording objective evidence of inspection results;
- g. Measuring and test equipment of the necessary accuracy for performing inspection.
4.3 Process monitoring may be used where direct inspection alone is impractical or inadequate. Both inspection and process monttoring are performed when control is inadequate without both.
4.4 Training and qualification of personnel who perform inspections, including NDE, shall be performed in accordance with approved procedures.
4.5 Hold points are designated as mandatory inspection points when confirmation is needed that the work at the point is acceptaille before additional work can proceed. Hold point inspections are performed, and work is released for further processing or'ljse, by authorized personnel.
4.6 Inspections are performed and documented in accordance with O written procedures. The results are documented and evaluated by qualified personnel in order to verify the acceptability of the item or work.
6+ 4.7 Inspections of receiving, maintenance and modification activities
+ are performed by Nuclear Quality Assurance personnel.
4.8 Inspection records shall contain the following where applicable:
- a. Item inspected;
- b. The date of the inspection;
- c. Inspector or data recorder identification;
- d. Identification of M&TE used to perform inspections;
- e. Type of observation;
- f. Results or acceptability;
- g. Reference to information on action taken on nonconformances to resolve any discrepancies noted.
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? RANCHO SECO. QUALITY MANUAL- REVISION! 6- i 9h- ]1 PAGE? -4 0F'41 q
5.0 f RESPONSIBILII1ES General organizational responsibilities are described in Section I, ORGANIZATION._.
5.1 The Manager, Nuclear Quality Assurance is responsible for* _.,
- a. Qualifying Quality Control ~. Inspect' ors,
- b. Developing inspection planning for modification / maintenance-activities.
- c. Performing inspections per inspection plans..
5.2 The Manager, Nuclear Maintenance Department is. responsible-for assuring:
- a. Inspections are performed as required by inspection p1anning'.; ,.
r
- b. Work.doesnotproceedbeyondinspectorsignoffs-forN1d .
-points. .
5.3 The managers of each department are responsible for;
- a. Supporting inspection activities.-
- b. Providing prompt corrective action _to any deficiencies found. J
.during the inspection.- .
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NUMBER: RSQM - SECTION XI A RANCHO SECO QUALITY HANUAL REVISION: 5 PAGE 1 0F 4 tttttilyt UAit LEAD DEPARTMENT:
10-23-91 RUCLEAR OJACITY ASSURANCE 4
REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Sumary" page to this and all other sections of this Manual.
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'( ) PAGE 2 0F 4 XI. ,' TEST CONTROL 1.0 PURPOSE This section describes the Quality Program measures established :
to provide for acceptance and surveillance testing at the Rancho Seco Nuclear Generating Station.
2.0 REFEREEE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion XI, Test Control 2.2 ANSI N45.2-1971, Section 12, Test Control 2.3 Safety Guide 33/ ANSI N18.7. Administrative Controls for Nuclear Power Plants 3.0 F 20LIG Procedures shall be established and implemented to assure ~that
(] required testing to demonstrate that structures, systems and V components will perform satisfactorily in service is identified, performed and documented.
4.0 GENERAL REOUIRLAENTS 4.1 Tests shall be performed in accordance with procedures and-criteria-that designate when tests are required and how they are to be performed. Such to: ting includes the following:
- a. Qualification tests, as applicable, to verify design adequacy,
- b. Tests of equipment and components to assure their proper operation prior to delivery or_ pre-operational tests;
- c. Pre-operational tests to assure proper and safe operation of systems and equipment prior to start-up tests or operations; (3
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NUMBER: RSQH-SECTION XI RANCHO SECO QUALITY MANUAL REVISION: 5 h(' PAGE 3 0F 4 4.1 , (Continued)
- d. Start-up tests, including precritical, criticality, low-power and power ascension tests performed after fuel loading to assure proper and safe operation of systems and equipment.
- e. Surveillance tests to assure continuing proper and safe operation of systems and equipment.
- f. Maintenance tests after preventive or corrective maintenance.
4.2 Test procedures and instructions shall include provisions for the following, as applicable:
- a. The requirements and acceptance limits contained in the applicable design and procurement documents;
- b. Test prerequisites such as calibrated instrumentation, ,
required test eg'Jipment, degree of completeness of the item to be tested, suitable and controlled environmental r conditions and provisions for data collection and storage;
- c. Verifying that test prerequisites have.been met;
- d. Instructions for performing the test; -
- e. Any inspection points;
- f. Acceptance criteria;
- g. Documenting or recording test data and results; and
- h. Verification of completion.
4.3 Test procedures and instructions shall be reviewed by the applicable organizations for technical content.
4.4 Test results shall be documented and evaluated by responsible authorities to assure that test requirements have been satisfied.
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NUMBER: RSQH-SECTION XI RANCHO SECO QUALITY MANUAL REVISION: 5 PAGE 4-OF 4 4.5 Test records shall contain the following information where
.' applicable:
- a. . Item tested and type of observation;
- b. The date and results of the test;
- c. Information related to deviations or nonconformances;
- d. Identification of person recording the data;
- e. Evidence as to the acceptability of the results; and
- f. Action taken to resolve any deviations and nonconformances noted.
5.0 RESPONSIBILITIES General orgsnizational respons!bilities are described in '
Section I, ORGANIZATION.
5- 5.1 The Manager, Nuclear Quality Assurance is responsible for:
- a. Performance of audits to assure conformance to testing.
requirements applicable to safety-related items per Section XVIII of this manual.
5.2 The Manager, Nuclear Technical Services is responsible for:
- a. Establishing the procedure for acceptance and surveillance testing,
- b. Providing personnel to perform the testing and acceptance evaluations.
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NUMBER: RSQM - SECTION XII RANCHO SECO QUALITY MANUAL REVISION: 5 PAGE 10F 4 O. LEAD DEPARTHENT: EFFECTIVE DATE NUCLEAR OUALITY ASSURANCE 10-23-91 REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Summary" page to this and all other sections of this Manual.
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l NUMBER: RSQM-SECTION XII RANCHO SECO QUALITY HANUAL REVISION: 5 Os PAGE 2 0F 4 XII. . '00NTROL 0/ hEASURING AND TEST EQJIPMENT 1.0 EUR20SE This section describes the Quality Program measures established _
to provide for the control of measuring and test equipment at the Rancho Seco Nuclear Generating Station.
2.0 REEERBCE_DQCLHIMIS 2.1 10 LFR 50, Appendix B, Criterion XII, Control of Heasuring and Test Equipment 2.2 ANSI N45.2-1971, Section 13 Control of Heasuring and Test Equipment 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants, j_
2.4 Reg. Guide 1.30/ ANSI N45.2.4-72, Quality Assurance Requirements for the installation, inspection and Testing of Instrumentation and Electric Equipment with exception noted in Section II of this manual.
3.0 EQLICY Procedures shall be established and implemented to assure that measuring and testing devices used in final acceptance of activities affecting quality are properly controlled, calibrated and adjusted at specified intervals to maintain the desired accuracy.
4.0 G GERAL RE001REMENTS 4.1 Procedures shall be established for calibration, maintenance and control of measuring and test equipment utilized in the operation, measurement, inspection or monitoring of items.
4.2 Heasuring and test equipment shall be uniquely identified and shall be traceable to its calibration test data.
i NUMBER: RSQM-SECTION XII
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/' ) RANCHO SECO QUALITY HANUAL PAGE 3 0F 4 5
,/ l 4.3 , l.abels shall be attached to measuring and test equipment to
, display the next calibration due date. Where labels cannot be j attached, a control system shall be used that identifies to ;
potential users any equipment which may be beyond the calibration !
due date. l 4.4 Heasuring and test equipment shall be calibrated at specified intervals. These intervals are based on the amount of use, stability, characteristics and other conditions that could adversely affect the required measurement accuracy. Reference and secondary calibration standards shall be traceable to nationally recognized standards where they exist. Where national standards do not exist, provisions shall be established to document the basis for calibration.
4.5 H&TE shall be calibrated from reference standards with an accuracy ratio of at least four-to-one (reference standard to M&TE). Calibration accuracy ratios of less than four but equal to or better than one (Reference standard to H&TE) shall be :
acceptable when equipment required to mee' specified requitements is not commercially available. The basis of acceptance intthese cares shall be documented.
O 4.6 H&TE used for calibrating plant process instrumentation (PI)
O shall have calibration rangas, precisions,.and accuracies such that the PI can be calibrated from M&TE with an accuracy ratio of at least two-to-one (H&TE to PI). Calibration accuracy ratios of less than two but equal to or better than one shall be acceptable when equipment to meet specified requirements is not commercially' available. The basis of acceptance in-these cases shall be documented.
4.7 When measuring and testing equipment used for final inspection and test is found to be out of calibration, evaluations shall be conducted to determine the validity of the results obt41ned since the most recent calibration. The results of evaluatio.', shall be documented. Retests or reinspections shall be performed on suspect items as necessary.
4.8 Identification of measuring and test equipment used shall be documented and traceable to work performed to allow for corrective measures to be taken when a device is found to be out of calibration.
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i NUMBER! RSQN-SECTION XII i' RANCHO SECO QUALITY HANUAL REVISION: 5 PAGE 4 0F 4 5.0 , RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 The Manager, Nuclear Maintenance is responsible for:
- a. Establishing methods for control of measuring and-test ,
equipment. !
- b. Determining the need for calibrated instruments and measuring devices in Rancho Seco activities.
- c. Providing administrative procedures that address the j requirements for calibration, !
- d. Control of measurement devices to ensure their use'and accuracy.
5- 5.2 TheManager,NuclearQualityAssuranceisresponsitle'for:j:
- a. Performlag audits.in-accordance with Section XVIII-of:this ;
manual to assure conformance to the program for control of-measuring and test equipment, y h
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I RANCHO SECO QUALITY HANUAL fg ; lSQH-SECTIONXII LEAD DEPARTHENT: ffkCTIV DATE HUCLEAR OUALITY ASSURANCE 10-23-91 REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. d "R v n Summary" page to this and all other sections
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I NUMBER: RSQM-SECTION XIII T.EVISION: 5 f RANCHO SECO QUALITY HANUAL PAGE 2 0F 3 XIII. . HANDLING, STORAGE AND SHIPPING 1.0 LNH20SI This section describes the Quality Program measures established to provide for the handling, storage, cleaning and preservation of material and equipment at the Rancho Seco Nuclear Generating Station.
2.0 REfRBCLDOCUMBIS 2.1 10CFR50 Appendix B, Criterion XIII, Handling, Storage and Shipping 2.2 ANSI N45.2-1971, Section 14. Handling, Storage and Shipping 2.3 Reg Guido 1.38/ ANSI N45.2.2-1972 Packaging, Shippli;g, Receivi..g, Storage and Handling of Items for Nuclear Power Plants
- with exceptions noted in Section II of this manual. i 3.0 20LICf Procedures shall be established and implemented to assure that materials and equipment are properly handled, stored, shipped, cleaned and preserved to prevent damage or deterioration.
4.0 GBERALREQUIRWEMIS 4.1 Procedures shall be established for assuring that proper handling, storage, shipping and preservation instructions are included in applicable drawings and/or specifications.
4.2 When required for specific items, special protective environments, such as inert gas atmosphere, specific moisture content levels, and temperature levels, shall be specified.
4.3 A shelf-life program shall be in effect and monitored to prevent usage after the expiration date without recertification for extension of shelf-life.
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4.4 'Special material handling and preservation instructions shall be
,' developed when required by appilcable drawings and/or specifications.
4.6 Materials for packaging, shipment, and storage with the potential for causing contamination or radiation exposure require marking and labeling to indicate the need for special radiological controls.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 The Hanager, Nuclear Technical Services is responsible for:
- a. Establishing methods and procedures to ensure that applicable drawings and/or specifications include handling, storage, shipping, and preservation requirements.
5.2 The Manager, Nuclear Halntenance is responsible for:
Q V
- a. Establishing methods for special handling, storage, and.
preservation during maintenance activities.
- b. Providing administrative procedures which specify the required controls.
5-~ 5.3 The Manager, Nuclear Quality Assurance is responsible for:
- a. Performing audits in accordance with Section XVIII of this manual to assure conformance to ths program for handling, storage, and shipping.
5.4 The Manager, General Services is responsible for:
- a. Maintaining material control / warehousing control of items and equipment which require special handling ar.d. storage, f3
I NUMBER: RSQH-SECTION XIV REVISION: 5 O RANCHO SECO QUALITY HANUAL LEAD DEPARTHENT:
MGE_0E- 3 Eff ECT ,VE DATE HUCLEAR OUAllIY_ASSURAt[CE_.___ 10-23-91 REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added " Revision Sumary" page to this and all other sections of this Manual.
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NUMBER: RSQM-SECTION XIV p, RANCHO SECO QUALITY MANUAL. REVISION:. 5 t / PAGE 2 0F 3 XIV. , INSPECTION, TEST AND OPERATING STATUS 1.0 ISR20SE :
This section describes the Quality Program measures established to provide for a system to identify the inspection.-test and 4 operating status of individual items at the Rancho Seco Nuclear-Generating Station.
2.0 REFERENCE _DQCUMERIS 2.1 10CFR50 Appendix B Criterion XIV, Inspection. Test and Operating Status ;
2.2 ANSI N45.2-1971, Section 15. Inspection Test and Operating Status 1 5
3.0 20GCY i F
Procedures shall be established and implemented to assure that measures are provided to indicate the status of inspections,.
tests and operations.
! 4.0 GENERAL REOUIREMERIS .
4.1 Procedures-shall be written to control nonconforming material, parts and components to prevent their. inadvertent.use in plant operations. '
4.2 . Procedures shall specify the degree of control required for the. ,
indication of inspection and test status of items required for ,
modification activities..
4.3 The sequence of inspections. tests, and other operations.-and -
changes thereto shall be controlled by. procedures..
4.4 Procedures shall provide. methods- for. identifying the- _
nonconforming items, inoperable systems-and components by tags, markings, labels, etc. to. prevent inadvertent use.
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NUMBER: RSQH-SECTION XIV RANCHO SECO QUALITY MANUAL REVISION: 5 O PAGE 3 0F 3 5.0 , RESEDMSIlllLIIIIS General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 The Nuclear Operations Manager is responsible for:
- a. Clearance procedures to ensure safety of personnel and equipment during maintenance and testing activities.
- b. Installation and removal of test and operating status indicators.
5-- 5.2 The Manager, Nuclear Quality Assurance is responsible for:
- a. Identifying the quality status of material, parts, and components.
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NUMBER: RSQM-SECTION XV
^ RANCHO SECO QUALITY HANUAL REVISION: 5
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I PAGE 10F 4 LEAD DEPARTHENT: EFFECTIVE DATE NUCLEAR DUALITY. ASSURANCE 10-23-91 REVISION SUHHARY:
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. The Commitment Management Review Group (CHRG) has replaced the Engineering Review Board (ERB) and has expanded management representation to review identified conditions which are adverse to quality and the cort-ective action for those same identified conditions.
- 3. Added " Revision Summary" page to this and all other sections of this Manual.
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1 NUMBER: RSQH.SECTION XV RANCHO SECO QUALITY MANUAL REVISION: 5 O' PAGE 2 0F 4 XV. NONCONFORHING MATERIALS, PARTS OR COMPONENTS 1.0 LTREDSE This section describes the Quality Program measures established for controlling material, components, parts, or systems that are not in conformance to specified requirements at the Rancho Seco Nuclear Generating Station.
2.0 RELEllEEED.JXDMERIS 2.1 10 CFR 50, Appendix B, Criterion XV, Nonconforming Haterials, Parts or Components 2.2 ANSI N45.2-1971, Section 16, Nonconforming Items 3.0 EQLLC1 {
Procedures shall be established and implemented to assure that materials, parts or components which do not conform to specified requirements are controlled to prevent their inadvertent use or O installation.
4.0 GENERAL RE001REMENTS 4.1 Procedures shall be developed for controlling, documenting, and resolving items, services or activities identified as nonconforming.
4.2 Nonconforming items shall be identified by marking, tagging, segregating, or other means.
4.3 Nonconformances shall be documented, processed, controlled and retained to provide records of the action which was taken to resolve the nonconforming condition.
4.4 Appropriate levels of management will approve the disposition and technical justification of all dispositions.
4.5 The nonconformance program shall receive the attention of management personnel to assure prompt closure of nonconformances in their area of responsibility.
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NUM8ER: RSQM-SECTION XV RANCHO SECO QUALITY MANUAL REVISION: 5 fl \j PAGE 3 0F 4 5-~ 4.6 . Trending may be used as a mechanism for providing management
, information on programmatic or other significant deficiencies, t
4.7 Nonconformances shall be reviewed to determine if they are potentially reportable per 10 CFR 21.
5.0 RESPONSIBI_LITIES S* General organizational ' responsibilities are described in Section I, ORGANIZATION.
5.1 The Manager Nuclear Quality Assurance is responsible for:
- a. Providing management representation and expertise on the
-Commitment Management Review Group (CMRG); reviewing i identified conditions which are adverse to cuality and the corrective action associated with those concitions.
b.
Establishing methods for controlling and. documenting [ #
nonconformances, r
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- c. Ensuring expertise is available to' disposition nonconformances.
- i. . x d. Developing-safety analyses that address the nonconforming l condition, if required.
5.2 _ The Manager, Nuclear . Technical Services is responsible for:-
- a. Ensuring expertise is available.to disposition <
, nonconformances,
- b. Developing _ safety analyses that address the nonconforming conoitton, if required.
- c. Providing management representation and expertise on the-Commitment Management Review Group (CNRG); reviewing identified conditions which are adverse to quality and the corrective action associated with those conditions.- f
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RANCHO SECO QUALITY HANUAL lSQH-SECTIONXV
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PAGE 4 0F 4 5- 5.3 ,
The Manager, Nuclear Operations is responsible for:
- a. Taking appropriate action to ensure operation of the plant in conformance to license requirements when a nonconformance identifies a condition prohibiting components, structures, or systems from returning to an acceptable condition,
- b. Determining the safety significance of the nonconforming condition on the status of the plant.
- c. Providing management representation and expertise on the Commitment Management Review Group (CHRG); reviewing identified conditions which are advense to quality and the corrective action associated with those conditions.
- d. Ensuring expertise is available to disposition nonconformances.
- e. Developing safety analyses that adcress the nonconforming .
condition, if required. 4 F
5.4 The Manager, Nuclear Radiation Protection and Chemistry is:
responsible for: ,
( a. Ensuring expertise is available to disposition nonconformances. .
- b. Developing safety analyses that address the nonconforming condition, if required.
- c. Providing management representation and exportise on the Commitment Management Review Group (CHRG); reviewing _
identified conditions which are adverse to quality and the corrective action associated wiik those conditions.
5.5 The Manager, Nuclear Haintenance is responsible for:
- a. Ensuring expertise is available to disposition nonconformances.
- b. Developing safety analyses that address the nonconforming condition, if required.
- c. Providing management representation and expertise on the Commitment Management Review Group (CHRG); reviewing identified conditions which are adverse to quality and the
- corrective action associated with those conditions, p
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NUMBER: RSQH-SECTION XVI RANCHO SECO QUALITY MANUAL REVISION: 5 O LEAD DEPARTHENT:
PAGE 10F 3 QF g E DATE W CLEAR OUALITY ASSURANCE REVISION
SUMMARY
- 1. Updated to reflect current organizational titles, responsibilities and requirements.
- 2. Added that the Commitment Management Review Group (CHRG) is responsible to review identified conditions which are adverse to quality and approve the corrective action fer these same identified conditions.
- 3. Clarified that the Manager, Nuclear Quality Assurance is responsible to establish the corrective action program and to perform audits of the program as implemented throughout the plant.
- 4. Added"RevisionSummary"pagetothisandallothersections
- T of this Manual.
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NUMBER: I RSQM-SECTION XVI RANCHO SECO QUALITY HANUAL REVISION: 5 h'^'T PAGE 2 0F 3 XVI. .
CORRECTIVE ACTION 1.0 PURPOSE l This section describes the Quality Program measures established' J to provide for a corrective action program to assure that conditions adverse to quality are promptly identified and ,
corrected at the Rancho Seco Nuclear Generating Station, j i
2.0 REFERENCE DOCUMENTS 2.1 10CFR50 Appendix B, Criterion XVI Corrective Action .
2.2 ANSI N45.2-1971, Section 17 Corrective Action 3.0 20LICY ,
Procedures shall be established and implemented to assure.that i significant conditions adverse to quality are identified and that c
corrective action is taken to preclude repetition.
4.0 GENERAL. REQUIREMENTS 4.1 Controls shall assure conditions adverse to quality such as malfunctions, errors, deficiencies or nonconformances are identified, documented and approsriate corrective action.taken.
The controls shall assure that t1e corrective action is implemented in a timely manner.
4.2 for significant conditions: adverse to quality, corrective action:
includes determining the cause and extentLof the condition, taking corrective _ action to remedy the condition and taking '
action to prevent recurrence. These actions shall be reported to management personnel for review and-assessment.
4.3 Conditions adverse to quality are evaluated to determine if they are potentially reportable per 10CFR21 or 10CFR50.73.
54 ._ 4 . 4 Identified conditions adverse to quality shall be reviewed by the:
Commitment Management Review Group (CHRG) for severity.
Corrective' action for identifled conditions shall be reviewed' and '
- approved by the CHRG.
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NUMBER: RSQH-SECTION XVI
<w RANCHO SECO QUALITY MANUAL REVISION: 5 L ) PAGE 3 0F 3 v
5.0 , RESPONSIBILLIllS General organizational responsibilities are described in Section I, ORGANIZATION.
54 5.1 The Hanagers, of all departments, are responsible for:
- a. Formulating appropriate corrective actions as they apply to their departments.
- b. Implementing proposed corrective action,
- c. Assuring that proposed corrective action is effective.
5.2 The Manager, Nuclear Quality Assurance is responsible for:
- a. Establishing the corrective action program. j
- b. Performing audits of the Corrective Action Program, as "
- implemented-throughout Section the plant, in accordance with ,f XVI!! of this manual.
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NUM8ER: RSQM.SECTION XVII 1 I RANCHO SECO QUALITY MANUAL REVISION!- 5 PAGE 1 0F 3 LEAD DEPARTMENT:
- NUCLEAR _ QUALITY ASSUMMCE
{Qjl@ MTE ,
e i REVISION
SUMMARY
- 1. Updated to reflect current organizatit.ial titles, responsibilities and requirements.
- 2. Revised requirements for interim storage of records to be consistent with those stated in Section !!. Quality Assurance Program, of this Manual. !
- 3. Added " Revision Summary" page to this and all other sections _
of this Manual.
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I NUMBER: RSQH-SECTION XVII RANCHO SECO QUV TY HANUAL REVISION: 5 PAGE 2 0F 3 XVII. QUALITY ASSURANCE RECORDS 1.0 EUR20SE This section describes the Quality Program measures established for the storage and maintenance of Quality Assurance Records which provide the documentary evidence of activities affecting quality performed at Rancho Seco Nuclear Generating Station.
2.0 REEIRBCE DOCUMENTS 2.1 10 CFR 50, Appendix 8. Criterion XVII, Quality Assurance Records 2.2 ANSI N45.2-1971, Section 18. Quality Assurance Records 2.3 Safety Guide 33/ ANSI NIB.7, Administrative Control for Nuclear Power Plants, para 5.2 .,
2.4 RGl.28/ ANSI /ASHE,NQA-1-1983, Supplement 175-1. Supplement $ry Requirements for Quality Assurance Records with exceptions noted in Section II of this manual.
2.5 Technical Specifications Section 6.0 3.0 POLICY Procedures shall be established and implemented to assure storage 5- and maintenance of records which represent evidence of activities
- described in Section II, Paragraph 4.2 of this manual.
4.0 GMEEALREOUIREMENTS 5-~ 4.1 Quality Assurance records shall be permanently stored in a facility that meets the requirements of Ref. 2.4.
5- 4.2 Quality Assurance records shall be protected during interim
- storage in accordance with Ref. 2.4.
4.3 Documents that furnish evidence of the quality of items and services are generated and controlled in accordance with the procedures that govern those activities. Such documents are considered Quality Assurance Records upon completion. Quality Assurance Records are considered completed when they have been stamped, initialed or signed and dated by authorized personnel or otherwise authenticated.
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, i NUMBER: RSQM-SECTION XVII l Q RANCHO SECO QUALITY MANUAL REVISION: 5 l
h PAGE 3 0F 3 1
4.4 , The record system shall provide for identification and ;
. istrievability of the records to the extent that information can '
be obtained in a reasonable amount of time.
4.5 The records program shall address records classification 5-~ (retention period), storage location and responsibility for retention and retrievability.
l 54~ 4.6 A records retention schedule shall be established which addresses the requirements of Ref. 2.4 and 2.5.
l 5.0 RES20KSIBillI1ES General organizational responsibilities are described in Section I, ORGANIZATION. )
54~ 5.1 The Supervisor, Records Control is responsible for:
- a. Establishing methods for control of records.,
e
- b. Providing administrative procedures which define the records storage program and provide for ready retrievability.
5-~ 5.2 The Manager of each department'is responsible for 4
- a. ' Transmitting completed records to Records Management Department.
- b. Providing inte' rim storage in accordance with Section 4.2, prior to transmittal to Records Management.-
5-* 5.3 The Manager, Nuclear Quality Assurance-is responsible for:
- a. Conducting audits in accordance with Section XVIII of this manual of the. records management system to assure conformance to specified requirements.
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NUMBER: RSON-SECTION XVIII -
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RANCHO SECO QUALITY MANUAL REVISION:
PAGE 1 OF 3-5 l
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LEAD DEPARTMENT: EFFECTIVE DATE NUCLEAlt OUALITY ASSURANCE 10-23-91 REVISION SUMKARY:
- 1. Updated to reflect current organizational titles.
responsibilities and requirements.
- 2. Conditions adverse to quality identified during audits are processed using the Rancho Seco Corrective Action Program. ,
The severity of those conditions is reviewed and approval of i corrective action is given by the Commitment Management i Review Group (CNRG).
- 3. Added " Revision Summary" page to this and ail other sections of this Manual. - ,
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Bh lSQM-SECTION XV
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RANCHO SECO QUALITY MANUAL
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PAGE 2 0F 3 XVIII. ,' AUDITS 1.0 EURNSE This section describes the Quality Program measures established for a comprehensive system of planned and periodic audits to determine the effectiveness of the Quality Program at the Rancho Seco Nuclear Generating Station.
2.0 REEEREliCLDQCUMENTS 2.1 10CFR50, Appendix B, Criterion XVI!!, Audits 2.2 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.3 Reg. Guide 1.144/ ANSI N45.2.12-1977 Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants g 2.4 Reg Guide 1.146/ ANSI N45.2.23-1978, Qualification of Quality Assurahcc Program Audit Personnel for Nuclear Power Plants 2.S Technical Specifications, Section 6.0 3.0 EQLICY Procedures shall be established and implemented to assure that planned and periodic audits are conducted to verify compliance with all aspects of the Rancho Seco Quality Program and Technical Specifications.
4.0 GENERAL REOUIREMENTS 5-- 4.1 The Manager, Nuclear Quality Assurance shall establish a schedule for auditing the activities affecting quality. The audit
~ ... schedule shall be consistent with the Technical Specification requirements at Rancho Seco.
4.2 The audit program shall be described in procedures which implement the requirements of this section, q
NUMBER: RSQH-SECTION XVIII ,
(] RANCli0 SECO QUALITY HANUAL REVISION:
PAGE 3 0F 3 5
V 4.3 'Auditsshallbeconductedtodeterminetheadequacyand '
? effectiveness of programs implemented for the ustign, procurement, modification, maintenance and operational activities I at Rancho Seco.
4.4 Audit plans shall be develooed which identify the audit scope, the requirements, activities to be audited, organizations to be ,
notified, the applicable documents and the audit schedule.
5-4.5 Audits shall be performed using approval audit checklists.
4.6 Audit reports shall be issued which identify the activity which was audited, personnel contacted during the audit, and any conditions adverse to quality noted during the audit.
4.7 Identified conditions adverse to quality will be processed using the Rancho Seco Corrective Action Program.
4.8 Personnel conducting audits shall be trained and qualified in.
acco* dance with Refererce 2.4.
4.9 Regularly scheduled audits shall be supplemented by special Audits when conditions which warrant special audits exist or when f--)
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- requested by Management.
5.0 RESP 0liSIBILUIES General organizational responsibilities are described in Section I, ORGANIZATION.
5*~ 5.1 The Manager, Nuclear Quality Assurance is responsible for:
- a. Establishing a schedule for performance of required audits,
- b. Reviewing audit results to evaluate the effectiveness of the Quality Program,
- c. Implementation of the established audit program,
- d. Training and qualification of audit personnel.
5-~
- e. Preparation of trend analysis data.
5.2 The manager of each department is responsible for.-
a- Supporting the audit activities.
5-~ b. Providing prompt response to any deviations from quality (o) identified in the audit.