ML20246L731
| ML20246L731 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/31/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89583, NUDOCS 8909070033 | |
| Download: ML20246L731 (276) | |
Text
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""ll Log # TXX-89583.
~~. ..~" File # 10010 r C 917.2 7t#ELECTR/C Ref. # 10CFR50.34(b)-
August 31, 1989 7 Executive hw besWent
, .U. S.' Nuclear Regulatory Commission-
. j Attn: Document Control Desk-Washington, D. C. 20555-I
SUBJECT:
COMANCHE: PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 ADVANCED FSAR SUBMITTAL OPERATIONS QUALITY ASSURANCE PROGRAM
\
REF: " Request for Additional Information Pertaining to the Comanche Peak Steam Electric Operations Quality Assurance Program," from
. C. C. Grimes, to W. J. Cahill, Jr. , dated July 7,1989.
Gentlemen: -!
..- This letter provides an advance copy of changes to be included in a future FSAR~ amendment regarding the CPSES operations quality assurance program. 1 These changes are.provided in. response to the referenced Request for 'i Additional Information (RAI). Based on discussion with'the NRC in the meeting- ;l held among the NRC, CASE, and TU Electric on August 1,1989, and the' l conference call held between the NRC and TU Electric on August 17, 1989, i TV Electric understands that the preliminary NRC review indicated that these l changestare acceptable. Unless the final NRC review identifies a concern, no ;
further correspondence regarding these changes will be required. The responses to these questions and comments, with epplicable justification to support conclusions, are delineated in either the attachment or the i enclosure to this submittal. The attachment format provides the original NRC question and comment, and TU Electric's response.to close the issue. In order to facilitate NRC staff review of these changes, the enclosure is organized as follows: l
- 1. Draft revised FSAR pages, with changed portions indicated by a bar/ DRAFT in the margin, as they are to appear in a future amendment l (additional pages immediately preceding and/or following the revised i pages are provided if needed to understand the change).
I i
'8909070033'690854
,. PDR- ADOCK 05000445 f A PDC I ( l 400 North Olive Street LB81 Dallas, Texas 75201
TXX-89583. E August 31, 1989 Page 2 of 2
- 2. A copy cf related SER/SSER. sections.
[L
- !? 3. .Line-by-line description / justification of each item revised.
I- 4. An indexlpage containing the title of "ou11ets" which consolidate and catzgorize similar individual changes by subject and related g l-SER/SSER section. '
- 5. The bold / overstrike version of the revised.FSAR pages. referenced by the description / justification for each item identified above. The old/ overstrike version facilitates review of the new text.in bold.
~
I type font and overstriking with a slash (/) the portion of- the. text -
- j. that is deleted.
TV Electric requests-that the NRC' perform an expedited review of the'above FSAR changes and inform us as to their acceptability. Sincerely, fff T William J. Cahill, Jr. By: Mb - Rtfge'r D( Walker. Manager, Nuclear Licensing-L l DAR/dar. Attachment Enclosure c - Mr.. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l r
~
Atta'chrdnt 1 to TXX-89583 August 31, 1989 Page 1 of 29 REQUEST FOR ADDITIONAL'INFORMATION COMANCHE PEAK OPERATIONS QUALITY ASSURANCE PP.0 GRAM - FSAR AMENDMENT 76 NRC Question 1:, FSAR ' Amendment 76 added the following exception to' the ' Regulatory Guide 1.38 commitment: For handling of items during operations phase, the following codes and' standards shall apply. ANSI B30.9-1971 ANSI B30.2-1976 (1967 for Design and-Fabrication) ANSI B30.5-1968 Specify the guidance in Regulatory Guide 1.38 which will. not ' be followed and the ~ provisions in the listed ANSI standards which will provide an equivalent level of quality and quality assurance. TU Electric Response: It- was not our intent to take exception to Reg.- Guide 1.38. It'is our intent to clarify the versions of these standards which would be employed at CPSES. These standards.are employed in the following documents: a) Procurement specs for cranes b) . Project response to NUREG-0612 (accepted by NRC staff in 1984) c) DBD-NE-06. Control of Heavy Loads at Nuclear Plants Our clarification of the 1967 version of ANSI B30.2 for design and fabrication is a clarification' of our commitment to Reg. Guide .1.38. This-clarification is necessary because the crane purchase orders were either issued or in the process of procurement prior to August 1976. The use of this version of B30.2 was reviewed and accepted by the NRC staff during their review of CPSES response to NUREG-0612. FSAR Appendix 1A(B) will be revised to change " exception" to
" clarification."
Attachment i to TXX-89583 August 31, 1989 Page 2.of 29 l NRC Question 2: i 'The justification for deleting "nonroutinely" from page 17.2-7 indicates ~ that the 0A Department reviews procurement documents only when these. documents impose OA requirements. How does the QA Departrent ensure that GA requirements'are not omitted from other procurement documents? TU Electric Response: The deletion of "non-routinely" was intended to ' clarify the QA' review responsibilities for - procurement documents and eliminate the misleading . corollary that " routinely" procured items and services. do not receive a OA - review. The QA Department reviews all procurement documents which are classified by Engineering as'having quality assurance' requirements. The QA Department ensures .that other procurement' documents are being correctly classified ~ by Engineering through the OA audit program. Also, . the guidelines used by Engineering for classification of procurement documents are addressed in procedures _ which require OA Department review and concurrence. I m__.-m_-_m-. _
'Attachm:nt'.1.to TXX-89583 August 31', 1989
, Page 3 of 29 NRC-Question 3: FSAR Section 17'2.1.3
. states that the Quality Assurance Section is responsible for an effective audit and surveillance program at CPSES.
Clarify whether this responsibility extends to- suppliers . and contractors during the operations phase.. TU Electric Response: The intent of this change was to identify the 0A section~ responsibility for-the audit and surveillance programs, which was previously not stated in the. organization section. Requirements for imposing the responsibility for suppliers and contractors.
' to have an audit program during the operations. phase are described in FSAR -
Sections 17.2.4, 17.2.7 and 17.2.18. Requirements for performing audits and surveillance on suppliers- and contractors during the- operations phase are described in FSAR Sections
~17.2.1, 17.2.7 and 17.2.18.
. In order to clarify the 0A Section responsibilities this sentence will be changed to read. "... responsible for the administration and implementation-of an effective quality assurance audit and . surveillance program for CPSES." _-______-____-________Q
-Attachurnt l' to TXX-89583' August- 31, 1989 Page 4 of 29 j; NRC Ouestion 4:
l- FSAR Section 17.2.1.4 addresses the Quality Control Section. but it does not address the Brown .& Root -Site 0A Manager' which Figure 17.2-1 shows reporting to '.the Manager, Quality Control. Discuss the authority and responsibility of-this position (organization) during the operations phase. Also, Section 17.2.1.4 . states that the. Quality Control Section. is-responsible for- an effective inspection program, but it also states that personne1' performing inspections may be from' the same department that performed the work. Clarify to' whom personnel that ' perform inspections report. If these personnel report outside the Quality Control Section.- - clarify how the Quality Control Section fulfills its responsibility for an effective inspection program. TU Electric Response: .l The B&R Site 0A Manager will be deleted from Figure 17.2-1. .This position was . inadvertently - shown when the same NEO organization chart was used for both Sections 17.1 and 17.2. FSAR Section 17.1 addresses this position *s authority and responsibilities for the construction phase (as the ASME III NA Certificate Holder). These responsibilities do not apply to this position during the operations phase. FSAR'~ Section 17.2.10 (page 17.2-26) states that. the Manager, QC is responsible for administering and implementing the CPSES. quality control inspection program and that quality control inspectors, which may be selected from among any of the NE0 departments, will report directly to the Manager, QC when scting in the capacity of quality. control inspectors. 4 I
sAttachm nt 1 to TXX-89583 August 31, 1989 Page 5 of 29
'NRC Ouestion 5:
'FSAR Amendment 71 (at the middle of page 17.2-11) included a commitment to perform independent management audits of quality assurance 1 activities as necessary to assess the scope, status, implementation, and effectiveness of the OA program. FSAR Amendment 76 (same location) changed this commitment
'to a commitment to perform an annual independent assessment of the audit program with periodic meetings of the Vice Presidents to assess and report on .tne status, adequacy, and overall effectiveness of the 0A program.
' Clarify the difference between the' independent management audits of quality assurance activities and the independent assessments of the audit program.
Provide justification for what appears to be a decrease in commitment in. this regard. Meetings do not generally satisfy the NRC perceived need for independent assessment of the scope, status, implementation, and effectiveness of the operations phase QA program by licensee management above or outside the QA organization. TU Electric Response: This change was intended as a clarification to more accurately describe the two elements which comprise the assessment of the status and adequacy of the QA Program - i.e., the annual independent assessment of the TV Electric QA audit program and the Senior Management GA Overview program (0A0P). TV Electric currently participates in the Joint Utility Management Audit (JUHA) program to provide an annual independent assessment of the implementation and adequacy of the TU Electric QA audit program, and any other aspect of the QA Program as requested by the Executive VP, NEO. The OA0P provides a mechanism to keep NE0 senior management advised of the overall adequacy and effectiveness of the OA Program through review ' of pertinent data; and provides a mechanism to . perform, report, track and follow-up elements of program assessment. The OAOP also requires an annual written assessment, prepared by the Vice Presidents, of the overall effectiveness of the QA Program be provided to the Executive VP, NEO. This written assessment incorporates the results of the independent assessment of the QA audit program along with information derived from the OA Overview Committee meetings, the audit program, Corrective Action Reports, Quality trending, NRC Notices of Violations and Deviations, and other sources of program evaluation to provide a qualitative and quantitative assessment of the effectiveness of the 0A Program.
Attach =.nt I to TXX-89583' August 31, 1989 Page 6 of 29 -l NRC-Question 6:
- FSAR Amendment 76 revised the two-sentence paragraph towards ..the top of page 17.2-13. This paragraph addresses:
(a) the QA Manager's review of procedures and (b) QA review of procedure implementation. Regarding (a), clarify the purpose of the OA Manager's review of procedures that require SORC review, clarify that this purpose is documented, and clarify .how ' TU Electric ensures that other procedures (not submitted for SORC review) should not have the same level of review. Regarding (b), the change in Amendment 76 appears to place more responsibility on line management to ensure that procedures having no " quality assurance requirements" are . properly implemented. Clarify whether this is the intent. If,not, clarify the intent. If so,' describe how line management is made aware of this increased responsibility.
.TU Electric Response:
1' The intent, of the change in the first sentence was to clarify that not all procedures involving operation, maintenance, modification, inspection and testing during the operations phase are reviewed by SORC. The Manager, GA, as a 50RC member, provides the OA Department review for those procedures which require 50RC review. The purpose of this review, as stated in this sentence, is "for quality assurance requirements" and is intended to provide the quality assurance expertise to the SORC review function. Operations procedures which do not require SORC review but which address systems, structures, components or activities identified as having quality assurance requirements still require QA Department review. This requirement is imposed through the administrative procedure controlling procedure preparation and review (STA-202), which itself requires SORC review and approval. This change did not realign any responsibilities for ensuring that procedures are properly implemented. FSAR Section 17.2.5 still states that cognizant supervision is responsible for ensuring that activities are performed in accordance with the procedures and instructions governing the activities. In addition, the word " assurance" in the last sentence of the second paragraph will be deleted to clarify that procedural implementation of quality requirements is periodically reviewed through audit and surveillance, and not just requirements related to the OA function. l
Attach 2snt 1 to TXX-89583 K . August 31, 1989 L Page 7 of 29 i NRC Ouestion 7: FSAR Amendment 76 deleted the commitment. at the top of- page 17 ~.2-14 ' of AmenCment 71 that procedures used to implement the QA program are prepared . I before the controlled activities begin. Justify this deletion. TU Electric Response: The justification submitted to .the NRC f ailed to address the -deletion of the first sentence. The first sentence- was deleted because this requirement is already, and more appropriately . stated in FSAR Section 17.2.5 (" Administrative procedures and instructions are reviewed and approved prior to performance of the activity") and 17.2.6 (" Documents, and changes thereto, are promptly distributed to ensure availability prior to commencement of work").
L l( Attach =nt I to TXX-69583 L. August 31,~1989 h Page-8 of 29
'NRC' Question 8:
FSAR~ Amendment 76 changed page 17.2-21 regarding document review. ' Describe measures which ensure the independence of: document reviewers from document-preparers when reviews for QA-related aspects are made by an individual not in the NEO QA Department. TU Electric Response: The measures to ensure.the independence of the reviewer are included in the administrative.. procedures which govern preparation and review of.-' the, applicable documents. The term " independent" is taken in this context to-refer simply to ;an individual other than the preparer. These procedures are reviewed by the . 0A Department to ensure the necessary controis are-tincluded. l l 1 l l 1. l . _ _ _ _ _ - . . . ..
Attachasnt 1 to TXX-89583 August 31,:1989 4
-.Page 9 of.29
'NRC Question 9:
The description of the first FSAR Amendment --76 change on page 17.2 - states that it is to clarify responsibilities / requirements for identifying inspection . hold points. Neither the earlier version - nor the ' new. version mention inspection hold points. Clarify the description of this change. TU Electric Response: The justification submitted to the NRC for this change was incorrect. The-justification of the change is (1). to clarify that the OA Department-performs reviews of special process procedures versus just the Manager, QC, and (2) to delete- the reference to 50RC as certain special . process procedures do not - require SORC review (e.g., NDE procedures generated by the OA Department). - ____ _ _ _ _ . _ . _ _____._-__m.__ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
1: Attacht:nt'1!to TXX-89583 August 31, 1989 Page 10 of 29 L NRC Question 10:
.In FSAR Amendment 76, the last paragraph on page 17.2-27 indicates that inspection hold points are the only controls required in administrative control procedures and instructions. - Discuss .the pros . and cons of adding "and" to the revision such that it reads: "In. addition, administrative and-instructions are reviewed by the QA Section to assure that required-controls are included and to provide for the necessary reviews for the assignment of inspection on hold points."
TU Electric Response: The "and" will be added to this sentence as proposed. The intent of the change as submitted was to clarify the review requirements within the context. of FSAR Section 17.2.10, which deals with inspection. However, since the QA review does include. asturing that required controls are: included ' (i .e., quality assurance requirements are incorporated), the proposed change is acceptable.
- AttachCent~1 to TXX-89583 I August 31,11989 e Page'11 of.29
- } '
NRC Ouestion 11: The -last sentence on: page .17.2-30' of FSAR Amendment 76 states- that measuring and' test equipment (M&TE) and reference standards are labeled or
~
tagged to indicate the next calibration due date or otherwise controlled in-accordance with approved procedures. Describe the method of "otherwise controlling" calibration schedules.
~ TU Electric Response:
Application of labels / tags which indicate Calibration Due Date is the ~
-normal practice; however, there are exceptions.
In some instances, Calibration Due Date does not apply and would not appear
-on the label / tag. For example:
a) The Calibrate Prior to Use status requires that the device' be calibrated prior to each use, and the calibration expires when the device is returned after use. Post usage calibration may be requested at the discretion of the user, b) The Inactive status provides that the device is temporarily removed from the M&TE program and has to be calibrated prior to entry back into the program. In other instances, size or functional characteristics of M&TE or reference standards make labeling / tagging impractical. In these cases, the CPSES - program. meets the intent of IEEE 498-1985 which states in part (section 5.5): "When size or functional characteristics of measuring and test equipment or reference standards prevent the application of a label, an identifying code shall be applied to reflect status. When neither labeling nor coding is practical, the procedures shall provide for monitoring of records to ensure control." In order to clarify the purpose of "otherwise controlled," this sentence will be changed to read, "... or otherwise controlled in accordance with approved procedures which ensure only M&TE and reference standards with current calibration are utilized."
t AttachmQnt'I to TXX-89583 4 August 31, 1989 i Page 12 of 29 i
- NRC Ouestion'12:
Identify (by position title) TU Electric's management authorized to accept calibration accuracy ratios of less than 4 to 1 for reference standards to M&TE and not better than " greater than" for other calibrations. Also, identify who accepts the bases for calibration where no nationally recognized standard or natural physical. constant exists. TU Electric Response: When reference - standard to M&TE accuracy ratios of less than 4 to 1 are used, the basis for calibration is documented and approved by.-the responsible' discipline Engineering Manager. In no case will the accuracy of a calibrating standard be less than the accuracy of the reference standard being calibrated. When calibrating. standards with the same accuracy are used, the basis for calibration is documented and approved by the manager of the organization which is responsible for.the calibration. When no nationally recognized standard or natural physical constant exists, the' basis for calibration is documented and approved by the manager of the organization which is responsible for the calibration. Section ' 17.2.12 of the FSAR will be changed to identify the management ~ responsible for approving the conditions cited above and, to clarify the accuracy requirements for calibrating standard to reference standard.
'f.( ; ,,
I ( ' 1 'httachh;nt'I to TXX 89583 s'- LAugust 31, 1989.: O Page.33 of 29 i E.~ , NRC-Question 13: Consider substituting "and".for "of" in the middle of the paragraph on page i ;17.2-31 of FSAR Amendment '76 which states "... determine the - validity' of -
'all inspection. tests .of measurement'results ..."-
3., TU Electric Response: This '.is: a typo error - the change submitted read "or" and not "of". This
, sentence will be corrected to read "and/or". .
o 4
. (_. -. - Attachment'~1 to TXX-89583 August 31, 1989 Page 14 of 29 NRC Ouestion 14:
.FSAR -Amendment 76, at the bottom of page 17.2-33, has changed "nonconformance r^ ports" to "nonconformance documents." Clarify whether non:onformance trending and analyses takes into account all nonconformance regardless of-where they are documented.
TU Electric Response: Yes
,t
[ E LAttachzentItoTXX-89583
. August 31. 1989 Page'15 of 29 'NRC Question 15:.
The justification given for - deleting responsibility for definition of activities related to nonconformance control from the cognizant manager, is because .this responsibility is " assigned to the executive Vice President, Nuclear Enc heering and Operations ..." Identify where this responsibility is shown in T.... FSAR. TU Electric Response: The intent of this change was to clarify that cognizant managers are only responsible for ' implementation of activities related to nonconformance control. Definition of the nonconformance' control program occurs at the E n cutive VP. NEO level through the NE0 procedure hierarchy. The: Executive VP, NEO has approval authority for NEO level' procedures / programs. This responsibility is generically addressed in the FSAR in paragraph 17.2.1.1.1
~and is also described in the response to NRC Ouestion 421.72.
A typographical' correction on page 17.2-34 of the FSAR will identify Question.421.72 in the margin next to the applicable paragraph.
. Attach 22nt I to TXX-89583 August- 31, 1989 P_ age _16 of 29 NRC Ouestion 16:
The: controls associated with nonconforming' item conditional release in the last paragraph of Section 17.2.15 -(pages 17.2-34. and _35) eliminate-
-Engineering Department evaluation and approval. These responsibilities and responsibility for reinstallation, operation, and use of~ nonconforming items _ are now shown as Nuclear _ Operations. Describe quality assurance p controls of these actions which assure safe operation. Also, "in violation of Technical Specification requirements" has- been added to the . commitment that_ nonconforming materials are not relied upon- for -safety-related service. ' Justify this limitation. .TU Electric Response:
C'PSES procedures specify that the Shift Supervisor shall review Conditional v e precautions or limitations for the installation, Releases.. and prescri' - operation or use of nonconforming items which are conditionally released. These reviews will . be performed - by the Shift Supervisor or 'an SRO to determine the impact on the safe operation of plant equipment. The ad'dition of the. phrase' "in violation of Technical Specification. E requirements" was intended to clarify the phrase " relied on for safety related service." It was not intended to be a limitation. The Shift Supervisor or SRO will review the Conditional Release to determine if the nonconformance effects the Technical Specification operability of equipment. Section 17.2.15 of the FSAR will be changed to clarify the controls which are provided in administrative procedures for' conditional releases, and use of_ nonconforming items, l l l
Attachcnnt I to TXX-89583 August 31, 1989 Page 17 of 29 NRC Question 17: FSAR Amendment 76 added Regulatory Guides 1.68 and 1.68.2 (among others) to Table 17.2-2. To be consistent with the Standard Review Plan (NUREG-0800), delete these two Regulatory Guides and add Regulatory Guides 1.26 and 1.29. TU Electric Response: Table 17.2-2. will be changed to delete Regulatory Guides 1.68 and 1.68.2 and add Regulatory Guides 1.26 and 1.29, with reference to FSAR Appendix 1A(B) for the CPSES position on compliance. l l l l l
Attach:3nt I to TXX-89583 August 31, 1989 ' Page 18 of 29 NRC Question 18(a): p The fo110 wing' items refer to changes made in Table 17A-1 by FSAR Amendment L. 76.
- ( A )' Boron Recycle System (sheets 9-: & 10): Justify changing - components-fron( Safety Class 3 to llNS: from ASME III to ASME VIII Mfrs. Stds.,
Or>' ANSI B31.1; ' f rom Code Class -3 to no Code Class; and from an-Appendix B OA program during the operations phase to .no 0A' program l; during. the operations ~ phase. -Clarify whether TU Electric's i
"specifica11y' structured non-Appendix B quality assurance program," as discussed in the last paragraph of- FSAR 17A-1, will be applied 'to these components during the operations phase.
1 TU Electric Response: The Boron Recycle System was reclassified so that it is no longer ASME. III, Code Class 3, and Safety Class 3. . System reclassification was performed in accordance with -Table A-1 of ANSI /ANS-51.1-1983. As a result- of . system reclassification, those portions of the Boron Recovery System that were originally ASME III, are now shown on the flow diagram as being within the Radioactive Waste Management System. The . Operations Quality -Assurance Program for Non-Safety Related Systems / Programs will be applied to these components during the operations phase. Table 17A-1 will be changed to add Note C to clarify this requirement for all RWMS items. In addition, Table 17A-1 and Table 17A-2 have been reviewed for consistent. application of operations OA notes and clarific~ations/ corrections have been made to ensure consistency. 1' l. _ _ . _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ __mm._.-.___________________..._______mm-______.-__-_-m._-___ _ _ _ _ ___-----
4 = Attach:2nt I to TXX-80583'
$@7' . August 31,-1989 Page~19 of 29:
.NRC Ouestion 18(b): @
The following items ; refer to changes made :in Table:17A-1 by FSAR Amendment 76. (b) .The description of the change 'to sheet 15 indicates that the Turbine Driven . Pump Control Panel ."is now seismic and non-1E." and the panel has -' been deleted. from the table. Clarify QA commitments for this panel'during the operation phase.
.TU Electric Response:
'The Turbine Driven Pump . Test Panel is non-seismic and'non-1E. No special i
quality ' assurance requirements during the operations phase ~are required..
.The change described for in Amendment 76 was inaccurate (typographical error) in stating that the " panel,is .now seismic" and should have stated that the " panel'is not seismic.'
l l u-1 i i
g Attacharnt I to TXX-89583-
, ' August 31 1989-Page:20 ef.29 NRC Ouestion 18(c):
The fc!10 wing items refer to changes made in Table 17A-1 by FSAR Amendment 7G. (c). Clarify why - the quality - assurance requirements of Branch ' Technical' Position ETSB 11-1 are not. required for the chemical drain tank: pump of/the liquid waste processing. system (sheet 22) and for the handling 11 equipment of the solid waste processing system (shect 25). l 1 'TU. Electric Response: h The requirements of Branch Technical ' Position ETSB 11-1 (Rev. 1).are not' required for the chemical drain tank pump since this Lis considered to be
'part of. the collection system (similar to. sump pumps). Thef handling.
equipment for the' solid waste processing system has been excluded because there' are no ' specific quality assurance . requirements in Branch Technical Position ETSB 11-1 for this equipment and the guideline does not' appear to
'be applicable. Note C was erroneous for these~ items and has been deleted.
Note 28 is the applicable note. l o l: '
4'
. 1 ? Attach: nt 1-to TXX-89583 !
August 31,.2989-l, Page.21 of 29 NRC Ouestion 18(d): The following items refer to changes made in Table 17A-1 by FSAR Amendment 76. E '(d) For tne following items. FSAR Amendment 76 shows no quality' assurance during the operations phase. Clarify what 0A program will be applied to' these items during the operations phase.
- Spent fuel handling tool Sheet 34 l . Burnable poison rod assemblies Sheet 37 H Primary source rods Sheet 37.
l Plant vent stack monitors Sheet 42 l~ High range area monitors Sheet 42 Low range area monitors Sheet 42 Steam generator blowdown monitor Sheet 43 Condenser off-gas monitor Sheet 43-Ventilation duct monitors Sheet 43 Turbine' building drain monitors Sheet 43 l Failed fuel monitors Sheet 43 . L Service water monitors Sheet'43 Boron recycle mcnitor Sheet-43
. Auxiliary steam condensate monitor Sheet 43 Spent fuel pool cooling and sample monitors Sheet 43 Steam generator blowdown sample monitors Sheet 43 Rod control equipment Sheet 46 Rod position indication containment cabinets Sheet 46 Control board demultiplexes Sheet 46 TV Electric Response:
. The notes for the individual items listed will be updated to reflect the Quality Assurance Program during the operations phase. The following items
!' will require the Operations Quality Assurance Program for Non-Safety Related Systems / Programs (Note C) during the operations phase: Plant vent stack monitors High range area monitors Low range area monitors Steam generator blowdown monitor Condenser off-gas monitor Ventilation duct monitor Turbine building drain monitors Failed fuel monitors Service water monitors Boron recycle monitor Auxiliary steam condensate monitor Spent fuel pool cooling and sample monitors Steam generator blowdown sample monitors For these items Note 28 will be deleted.
l Attach 2:nt 1 to TXX-89583 . August 31, 1989 Page 22 of 29 ,
'i l
.TV Electric Response to Question 18(d) (Cont'd): 1 1
The following items have been evaluated and determined to require QA during operations-. The. safety class will be changed to 3 and._ Note A will be E added. For these items Note 28 will be deleted. Burnable poison. rod assemblies Primary source rods The following items add or retain Note 28:
- Spent fuel handling tool Rod control equipment' Rod position indication containment cabinets Control board demultiplexes These items are not Nuclear Safety Related and had procurement GA applied during original procurement for economic reasons (by Westinghouse). These items do not require any special provisions during construction or operations. Note 28 was added in Amendment 76 -for clarification. Table 17A-1 .has 'been reviewed for consistent application of Note 28 and clarifications / corrections have been made to ensure consistency.
----.--_--------------a-._----a--_---
i Attachm:nt'I to TXX-89583 August 31, 1989 Page 23 of~29
.NRC Question 18(f):
The following items refer to changes made in Table 17A-1 by FSAR Amendment 76. (f) Justify the portion of Note 65 on sheet 56 which states: " Tubing systems previously pressure tested as being satisfactory, which were later repaired Or replaced, shall not require an additional pressure test prior to initial plant startup ..." v TU Electric Response: The tubing sizes used for safety class.2 and 3. installations at CPSES are 3/8 inch and 1/2 inch outside diameter. The engineering basis for exempting. repaired and replaced tubing from a repressure test is based on ASME XI Articles IWA-4400, IWA-7000, IWB-7324, and IWC-7000, 1983 Edition Summer' Addenda. These sections of the ASME XI code exempt component connections, piping, 'and associated valves 1 inch nominal pipe size and smaller from requiring a system hydrostatic test after repairs. While the installations at CPSES are not code stamped (NA 8000) and not third party inspected (NA 5000), all safety related tubing, valves, and fittings are purchased to ASME III Class 2 requirements. See Note 41, Table 17A-1. The assembly and . installation of fittings is in accordance with the manufacturers recommendations. The replaced and repaired sections are evaluated under a functional leak test.
AttachmGnt I to TXX-89583 August 31, 1989 Page 24 of 29-NRC Question 18(g): The following items refer to changes made in Table 17A-1 by FSAR Amendment 76. (g) Note 69 on sheet 57 does not appear to be referenced in Table 17A-1. i Specify where this note is referenced in the table Or consider its l- deletion. TV Electric Response: Sheet 47 references note 69. _____________________._________J
c Attach ent'l to TXX-89583' August 31, 1989 Page 25'of 29-NRC Question 19(a): The~ following . items - refer to changes make in responses to earlier QA
.related questions:
(a) 'The response to 0421.4 has been - changed in FSAR Amendment 76 to address only the OA Manual. Clarify the involvement of the OA
. organization in other manuals that include QA requirements. See also 0&R421.28.
TV Electric Response: The term " manuals" addressed by 0421.4 refers to the four. previous OA manuals which have - been consolidated into the CPSES QA Manual. These previous manuals were the Corporate OA Program, . the CPSES OA Plan, the Start-up QA ~ Plan, and the Operations Administr!t he Control and- Quality Assurance Plan. The question originally addressed review responsibilities for. these manuals in relation to the separate QA organizations at the Corporate office and onsite. These ' separate QA organizations were subsequently : consolidated into one QA Department. The changes in the response were intended to reflect the current organization and the consolidated QA Manual. The reference to Q&R 421.28 is unclear. For QA involvement in the review of procedure manuals, refer to the discussion on question number 6.
-Attacha;nt 1 to TXX-89583 August 31, 1989 Page 26 of 29.
l NRC Ouestion 19(b): l The following' items ' refer to changes made in . responses to' earlier l0A related questions:
-(b) Question 421.12. addresses an - . annual management assessment.-of the scope -~ status, implementation,_ and effectiveness of ' the CPSES QA
- l. program. The response should be incorporated into Section 17.0 of the-L FSAR. We note that the activities of_the Operations: Review Committee and the QA organization do not. normally satisfy the NRC guidance for an: independent assessment. See also question 5,'above, and 0&R421.50.
TU Electric Response: The response to 0421.12- was not changed in Amendment 76 to reflect ' the annual assessment ' described in FSAR Section 17.2.2 because 0421.50 addressed the. question and this'. response refers to FSAR Section 17.2.2. 1
. _ _ _ _ .__ -___--__ _ _ a
Attachm;nt 1 to TXX-89583
. August 31, 1989 Page 27 of 29 NRC Ouestion 19(c):
R421.54 refers to Figure 13.1-4 which is now an affidavit. Identify the approximate number of technical onsite 0A pe- mnnel reporting to the Manager 0A.
' TU Electric Response:
The approximate number of technical onsite OA personnel reportin0 to the Manager. 0A is 35. l
' Attach snt~1 to TXX-89583 August 31. 1989 Page 28 of 29 NRC. Question 19(d):
R421.79 indicates that "off the shelf" commercial items are " subject to the same. procedural control as all ' safety-related structures, systems, and components." Clarify the response and the-FSAR text.to address procurement and subsequent'. inspections / tests of commercial items from suppliers without a 10 CFR 50 Appendix B OA program. TV Electric Response: During the procurement- phase of commercial grade (off the shelf) items, characteristics critical to the. safety function of the item are identified by procurement engineering. These critical characteristics are subsequently verified by one or more of the following methods:
- 1) suppliers quality assurance program approved by TV Electric
- 2) inspection / test by TU Electric- at the supplier, upon receipt, or
.during post installation testing.
The response to- 0421.79 will be changed to reflect the above, and FSAR. Section 17.2.4 will be changed to address the identification and verification of critical characteristics as a method of assuring the quality of procured items. b - _ .___________ _ __
- _ - - _ = _ - - _ _ _ - _ _ _ _ - _ _ _ _
F w Attach 2:nt'I to TXX-89583-
>s '
, y August 31..1989'
& Page 29 oft 29 l1 l-l
'NRC Ouestion'19(e):
Five' FSAR references are given on page 387.of the Attachment'.to TXX-89201 - regarding the removal'of chlorine detectors from sheet 45. Clarify.whether there will not be chlorine detect s or whether the' chlorine detectors- have been~ determined to be not important ? safety. TU Electric Response:
' The chlorine detectors previously listed in- Table.17A-1. have been removed from the design and are no. longer required. The chlorination systems have
- been redesigned as described in FSAR Section 2.2.3.2.2.
I
L-Enclosure to TXX-89583 Page l'of 244 Enclosure to TXX-89583 August 31, 1981 Advance FSAR Change Regarding the CPSES Operations Quality Assurance Program - Amendment 76. Item 1 Draft Revised FSAR Pages pg. 2 thru 109 Item 2 Related SER/SSER Pages pg. 110 thru 119 Item 3 Description / Justifications for pg. 120 thru 135 all FSAR Changes Item 4 Index Page Containing the pg. 135a Title of " Bullets" Item 5 Bold /0/d/df H Kd version of pg. 137 thru 244 Revised FSAR pages l I l ; l l 1 l' \ __ ___
l. b ' Enclosure' to'TXX-89583 - CPSES/FSAR
' Pag 2 2 of 244 1
,o utilized in the: area of. packaging,-shipping, receiving,' storage and 76
-handling:of items during the operations phase,-as described'in Section~17.2, will comply with the applicable guidance contained in-i Revision 1 (10/76) of this regulatory guide. -The application of the provisions of ANSI N45.2.2 -11972, as endorsed by this regulatory
' guide, will reflect the guidance provided in ANSI N18.7 - 1976.
4 Although ANSI N45.2.2'- 1972 isentitled." Packaging,[ Shipping, . DRAFT-Receiving, Storage, and Handling of Items for Nuclear Power Plants-During the Construction Phase," CPSES meets the requirements of this standard.during the operation phase with the clarification noted below: I For handling of items during operation phase. the following~ codes and 76= standards shall apply. ANSI B30.9 - 1971 76, ANS1 B30.2 - 1976 (1967 for Design and Fabrication) 76 ANSI B30.5 - 1968 76 Regulatory Guide 1.38, Revision 2 (5/77) is not addressed. 76 Also refer to Appendix 1A(N) and Section 17.2. 8 Reaulatory Guide 1.39 Housekeeping Requirements for Water-Cooled Nuclear Power Plants-Discussion 0421.19
- The administrative methods utilized to control station housekeeping 70 practices will comply with ANSI N45.2.3 - 1973, as endorsed by Revision 2 (9/77) of this regulatory guide and as applied to the operations' phase by the provisions of ANSI N18.7 - 1976.
1A(B)-17 Draft Version
l' c,li Enclosure to TXX-89583 CPSES/FSAR
- Pag 2 31of 244 17.2 OUALITY ASSURANCE DURING THE OPERATIONS PHASE
~17.2.1 ORGANIZATION 17.2.1.1 Organizational Structure Texas Utilities Electric Company. (TV Electric),- as the licensee, has. 53' overall responsibility for the operation of the Comanche Peak Steam ::
El.ectric Station (CPSES). Nuclear Engineering and Operations- (NEO) has been designated by TU Electric to coordinate the design, construction and operation of CPSES. The organizational structure of TV Electric and NEO are described in Section 13.1. The following paragraphs amplify upon Section 13.1 with regard to 53 establishment and execution of the quality assurance program for the operation of CPSES. Figure 17.2-1 shows the structure and relationships of those elements of NEO which function under the control of the QA program. Figure 17.2-2 shows the CPSES Nuclear 62 Operations organizational structure. TU Electric may, from time to time, assign responsibility for 53 executing certain portions of the program to qualified consultants and contractors. However. TU Electric, retains ultimate responsibility for the CPSES operations quality assurance program. 17.2.1.1.1 Executive Vice-President, Nuclear Engineering and 56 Operations 56 The Executive Vice-President, Nuclear Engineering and Operations is 56 responsible for the overall management of company operations, including operation of CPSES, and for the establishment of company policies. He has the overall responsibility for the establishment and execution of the quality assurance program for.the operation of
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CPSES. 17.2-1 Draft Version
-____________a
h 9 Enclosuro'to TXX-89583 Page'4 of 244- CPSES/FSAR DRAFT The Executive-Vice-President, Nuclear Engineering and Operations has assigned to the Vice-President, Nuclear Operations through the Senior Vice-President the overall responsibility for operation.of CPSES and for implementation of the quality assurance program for the Nuclear Operations function at CPSES. DRAFT The Executive Vice-President, Nuclear Engineering and Operations has assigned to the Senior Vice-President the overall responsibility for engineering and construction of CPSES, and for implementation of the quality assurance program for the Engineering and Construction function at CPSES.
-76 The Executive Vice-President, Nuclear Engineering and Operations has assigned to the Vice-President.. Nuclear Engineering the overall responsibility for licensing, fuel management, reactor engineering, safety and risk analysis, and quality assurance / quality control; and for_ implementation of.the quality assurance program for the Nuclear Engineering function at CPSES.
15 17.2.1.1.2 Vice President, Nuclear Operations DRAFT The Vice President, Nuclear Operations is responsible to the Executive Vice President. Nuclear Engineering and Operations through the Senior Vice-President for operating activities at CPSES. 71 53 Specific duties and responsibilities of the Vice President, Nuclear Operations include the following: DRAFT. 1. Technical and administrative direction of the Plant Manager. 56 DRAFT 2. Technical and administrative direction of the Manager, Startup. Draft Version 17.2-2
4
- ' Enclosure to TXX-89583 - CPSES/FSAR
'Page:S of 244: .
3. Technical and administrative direction of-the Manager.. Nuclear DRAFT Operations Support. j 4. Technical and administrative direction of the Manager. DRAFT-Projects.
' DRAFT
- 5. : Technical and administrative direction of the Plant Evaluation 62 manager.,
- 6. Technical and administrative direction of the Manager. Nuclear DRAFT-Training.
- 7. Operational and technical support of all Nuclear Plants operated- 62 by TV Electric.
- 8. Technical ani administrative direction for the implementation of 62
!. quality assurance requirements and controls at nuclear plants operated by TV Electric. I 62
- 9. Overall responsibility for the Initial Startup Test Program at 71
'CPSES.
17.2.1.2.3 Plant Manager DRAFT The Plant Manager is responsible to the Vice President, Nuclear DRAFT Operations for Plant operations activities at CPSES. He is the individual who is directly responsible for the safe. reliable, and efficient operation of CPSES. 37 Specific duties and responsibilities of the Plant Manager include the DRAFT following: 1 l 17.2-3 Draft Version 1
~
L Enclosure to TXX-89583 Pag 2 6 of.244 CPSES/FSAR. 15 1. Management of all operations-activities at CPSES. l 15 2. ' Technical and administrative direction of: DRAFT a. Manager, Operations DRAFT b. Manager, Maintenance ) 62- . c. Instrumentatic.i and Control Manager l..
- 3. Chairmanship of the Station Operations. Review Committee.
15 4. Membership on the Operations Review Committee. 71 62 17.2.1.1.4 Director, Quality Assurance 71- The. Director,. Quality Assurance, reports directly to the Vice-President, Nuclear Engineering and is responsible to him for assuring effective implementation of the Quality Assurance Program. This-55 reporting relationship assurer that the Director, Quality Assurance has sufficient authority, organizational freedom, and independence
~
from undue influence from, or responsibility for, costs and schedules such that he can effectively assure implementation of and compliance with the CPSES operations quality assurance requirements and controls. 71 The Director Quality Assurance is responsible for submitting the Quality Assurance Manual for concurrence and approval to the Executive Vice President, Nuclear Engineering and Operations. He is
- 62 responsible for the performance of quality assurance activities in support of CPSES operation.
I Draft Version 17.2-4 1 1 l
Enclosure to TXX-89583 PagG 7.ef 244 CPSES/FSAR The Director. Quality Assurance communicates directly with NEO 55 l
-supervisory and management personnel and with appropriate management levels in consultant and contractor quality assurance organizations to identify quality problems; initiate, recommend or provide solutions;_
and to verify implementation of solutions to quality problems. He alto has authority to "stop work" during the operatiens phase. 14 1: Specific duties and responsibilities of the Director. Quality 55 Assurance include the following:
- 1. Direction of Quality Assurance Department personnel.
l62
- 2. Technical and, administrative-direction of: 62
- a. Deputy Director 0A- 74
- b. Manager, QC 62
- c. Manager, OA 62
- 3. Verification through audit and surveillance that procedures for 62 the control of quality-related activities comply with quality
. assurance requirements.
- 4. Verification through audit and surveillance of the 62 implementation of the quality assurance program within NEO and evaluation of its effectiveness.
62
- 5. Assurance through audit, surveillance and inspection that consultants, contractors _and suppliers providing quality-related items or services have established and implemented an adequate quality assurance program.
- 6. Membership on, or supervision of a member of the Operations 55 Review Committee. -
17.2-5 Draft Version
l e L Enclosuri to TXX-89583'
, ' Pag 3 8 of;244 CPSES/FSAR.
~
DRAFT l17.2.1.1.5 Chief Engineer
- c DRAFT ~ The Chief Engineer is responsible for providing engineering related technical services in support of CPSES operations.
DRAFT. Specific duties and responsibilities'of the Chief Engineer includes the.following: 53 1. Technical support to Nuclear operations. RF 5 2.. Technical direction ~and administrative guidance to h?s staff. R S 3. Assistance, as required, in the procurement of equipment, materials, and services for.the operation, maintenance or modification of CPSES. 62 17.2.1.2 Ouality Assurance Department 62 The-'Ouality Assurance Department, under the direction of the Director. Quality Assurance functions to assure effective implementation of the 74 quality assurance program. The Deputy-Director, Quality Assurance reports to the Director, Quality Assurance and is responsible for the day-to-day management and operations of the OA Department as assigned by the Director. 0A. 62- ' Specific functions performed by the Quality Assurance Department include: 62 1. Quality assurance auditing of NE0 quality-related activities, both offsite and onsite.
- 2. Evaluation of consultants *, contractors', and suppliers' quality assurance programs and implementing procedures. -
- 3. Quality assurance auditing of consultants, contractors, and suppliers.
Draft Version 17.2-6
'Enclosuro to TXX-89583.
Page'9 of 244 CPSES/FSAR
- 4. Surveillance-and inspection conducted at equipment and material suppl.iers' facilities.
- 5. Review of procurement documents to assure incorporation of 76 adequate quality assurance requirements for procured items and services.
- 6. Surveillance and inspection of site quality related activities 76 to assure compliance with the applicable quality requirements.
17.2.1.3 Quality Assurance Section 74' I. 0421.48 The Quality Assurance Section, is supervised by the Manager, QA who reports directly.to the Director, OA, and to the Deputy Director. 0A for those responsibilities' assigned to that position. The Quality DRAFT Assurance Section is responsible for the administration and implementation of an effective quality assurance audit and surveillance program for CPSES. 71 l 0421.48 The Manager, OA has sufficient authority and organizational freedor at' 74 CPSES to. identify quality problems, recommend solutions, verify implementation of solutions, to stop unsatisfactory work and control further. processing, delivery or installation of non-conforming material until proper disposition has occurred. l 0421.48 In addition, the Manager, OA advises the Director. 0A, and the Deputy 74 Director. 0A, of the status of the quality assurance program at CPSES and of any significant conditions which are adverse to quality. 17.2-7 Draft Version
Encl osura ' to' TXX-89583 :
.Paga 10 of 244 CPSES/FSAR ;
1 74 17.2.1.4 Ouality Control Section 0421.11 74 The'0uality Control Section is supervised by the Manager. 0C who reports;directly'to the-Director. 0A and the Deputy Director. 0A for those responsibilities assigned to that position. The Quality Control?SectIon is responsible for the administration.and.
- implementation'of an effective quality control inspection program at CPSES.
76 The Manager, QC has sufficient authority and organizational freedom at CPSES to identify quality problems, recommend solutions, verify implementation of solutions, to stop unsatisfactory work and control i further processing, delivery or installation of non-conforming material until proper disposition has occurred.
- l. .74 Inspections shall be performed by qualified individuals other than those who performed or directly supervised the activity being inspected. Personnel performing these inspections may be from the same department but are not from the same group that performed the work.
0421.11 74 In addition, qualification criteria for inspection personnel are reviewed for concurrence by the Manager, Quality Control. 65 74 17.2.1.5 Doerations Review Committee Independent reviews of activities affecting plant safety during the operations phase are performed by the Operations Review Committee. The structure and responsibilities of this committee are described in Section 13.4. 74 Delecation of Ouality Assurance Functions l17.2.1.6 w - 53 -NEO periodically retains qualified consultants and contractors to provide safety-related services. All consultants and contractors providing safety-related services and suppliers providing safety-Draft Version 17.2-8
~ Enclosuro to TXX-89583 -
Pag 2'11 of 244: CPSES/FSAP..
'related equipment or materials for CPSES are required to establish and implement quality assurance. programs appropriate for their scope of supply. NEO includes specific. requirements in procurement documents 53 with which consultants *, contractors *, or suppliers' quality assu'rance programs must comply.
17.2.1.7 Personnel Qualifications 74 0421.6 17.2.1.7.1 Director, OA and Deputy Director. 0A l74 The Following qualification requirements have been established for the 74 Director. 0A and Deputy Director. 0A.
- 1. Minimum of ten-years related experience in design, construction, 59 and/or operation of power plants. A maximum of four years of this ten years experience may be fulfilled by related technical or academic training.
- 2. A bachelors degree from an accredited college, university or 59 other institution.
0421.47 l 3. Demonstrated ability to manage people and projects. 9 0421.47 l 4. Knowledge of quality assurance requirements for nuclear plants 59 including a minimum of one year related experience in the implementation of a nuclear quality assurance program, 74 17.2-9 Draft Version
Enclosure to TXX-89583' l Page 12 of 244 CPSES/FSAR L 0421.11
.71 17.2.2 OUALITY ASSURANCE PROGRAM 71 The Quality Assurance Program requires a Quality Assurance manual be developed for each nuclear power plant, which prescribe specific
- measures'to assure the quality of safety-related activities, structures, systems and components of that facility. The quality assurance requirements and controls implemented-during operations of CPSES are established by the portion of the CPSES Quality Assurance Program in this section (17.2) of the FSAR. The quality assurance requirements and' controls implemented during design and construction l
of the CPSES are established by the CPSES Quality Assurance Program (Design and Construction), which is described in Section 17.1. 0421.15 l~ Quality assurance requirements and controls are established and implemented throughout the testing and operation' phases at CPSES. 9 This program shall be implemented at least 90 days prior to fuel 71 loading. Responsibilities and authority, and measures for the cortrol and accomplishment of activities affecting the quality and operation of safety-related structures, systems, and components of CPSES are defined. The structures, systems, and components covered 71 by the quality assurance program are listed in Table 17A-1. These provisions apply to all activities, such as operating, maintaining, repairing, modifying, and refueling which affect the safety-related functions of those structures, systems, and components. Draft Version 17.2-10
, . Enclosura.to TXX-89583 :
Paga 13Lof 244 - CPSES/FSAR i- '
^62!
-A Quality Assurance' Program shall be developed and-implemented:to: 62-attain high: levels of quality; assurance during the. operation ofz CPSES.1This program 'shall comply with the requirements of Title-10, Code of Federal Regulations, Part 50 Appendix B. " Quality ;
-Assurance Criteria for Nuclear Power Plants and Fuel Processing
-Plants," and certain NRC Regulatory Guides and ANSI standards as.
identified in the. Final Safety Analysis Repcrt (SAR). t; Overall responsibility for the Quality Assurance (QA) Prograu lies '62 with the Executive Vice President, Nuclear Engineering.and. Operations. Specific responsibility for development and' administration of the program rests with the Director.-Quality Assurance. 0421.50-The Executive Vice President -Nuclear Engineering'and Operations will' 76 assure that an annuai'indeper. dent asst.ssment of the audit program is-performed. These independe.at assessments will be conducted in DRAFT-accordance'with predetermined schedules, with results documented, and-a follow-up syste:a utilized to assure that corrective action is' taken and audited when it is.ronsidered neesssary to verify implementation. The Vice-Presidents shall meet periodically to assess the 76 status and adequacy of the quality assurance program, and at least annually previde a written assessment of the overall effectiveness of the OA program to the Executive Vice-President. Nuclear Engineering and Operations, which includes the results of the independent
' assessment of the audit program.
.The quality &ssurance requirements and controls applicable t', the 71 operations phase, comply with the requircunti of 10 CFR Part 50, Appendix 0. Table 17.2-1 provides a matrix showing those sections of the QA Manual which satisfy the requirements of each criterion of 10 CFR Part 50, Appendix B. The quality assurance requi mments and -
controls'shall be consistent with the applicable guidance of those ! Regulatory Guides and industry standards listed in Table 17.2-2'and discussed.in Appendix 1A(B). 17.2-11 Draft Version
' N l Enclosure t'o;TXX-89583'-
;Page 14 offTi4 CPSES/FSAR
_ gf0421'51 711 The Director. 0A is responsible for> controlling the distribution of L the Quality Assurance Manual and revisions thereto.
- 71) .The quality assurance requirements and controls are. designed to assure that activities affecting-the quality and operation of safety-related items are accomplished in a planned and controlled manner.
' Activities'affecting quality are accomplished in accordance with written, approved procedures and instructions under. suitably controlled conditions. Controlled conditions include,_as applicable, appropriate equipment, suitable environmental conditions, and 71_ completion of prerequisites. All procedures prescribing activities affecting quality are controlled and distributed in accordance with the measures described in Section 17.2.6.
'71 .The Director. Quality. Assurance, is responsible for assuring, through audits and surveillance, implementation of the Quality Assurance Program.. He is responsible fer regularly assessing the status and adequacy of the Program, within NEO,'and as implemented by consultants, contractors, and suppliers. .The Director. Quality 62 Assurance, reports the results of these evaluations to the Vice-President, Nuclear Engineering. Unresolved issues between the Director. Quality Assurance and others concerning quality are brought to' the Executive Vice-President, Nuclear Engineering and Operations for resolution.
0421.54 71 The Director. 0A has overall responsibility for the identification, scheduling, assignment, conduct and reporting of station activities 76 assigned to the QA Department. Station activities affecting quality tare subject to quality surveillance and audit by quality assurance site personnel. Draft Version 17.2-12 r
O ' Enclosure to TXX-89583
; Page 15 of 244 CPSES/FSAR.
In' addition, the Manager, OC.has' responsibility for administration'and J74-implementation of the CPSES quality control program. 0421.54
- The Manager, QA reviews procedures involving operation, maintenance, 76
? modification, inspection and testing. during the. operations phase for quality assurance" requirements as a normal function'of the Station-Operations Review Committee. Procedural implementation of quality DRAFT requirements is periodically reviewed by the OA organization through audits and surveillance activities. An indoctrination and training program is established for those -71 personnel performing activities affecting quality. The scope, objectives, and methods for implementing the indoctrination and - training program are prescribed by written, approved procedures. These procedures also prescribe methods for documenting the accomplishment of training. The indoctrination and training program includes provisions that personnel performing activities affecting quality are:
- 1. Instructed as to the purpose, scope, and implementation of the 71 Quality Assurance Program and related procedures and instructions as appropriate to their activities.
- 2. Qualified in the principles and techniques of activities for which they are responsible.
- 3. Retrained, re-examined or decertified, when appropriate, to maintain necessary proficiency in those activities for which they are responsible.
17.2-13 Draft Version
i l Enclosure'to TXX-89583 CPSES/FSAR L . Paga 16 cf 244 ( 76 0421.55 17,2.3 DESIGN CONTROL 0421'.57 l 17 1 Requirements for the control of design activities associated with modifications of safety-related structures, systems, and components are consistent with the provisions of Regulatory Guide 1.28, and Regulatory Guide 1.64 as discussed in Appendix 1A(N) and in Appendix 1A(B). 0421.55 DRAFT The CPSES Plant Manager shall have the responsibility for approving and controlling the implementation of station design modifications. The Senior Vice President has the overall responsibility for developing procedures to msintain and control the design control process, l 0421.57 71 Final approval of all station modifications is the responsibility of the 50RC. The SORC will submit all proposed station design 44 modifications which involve a change in CPSES Technical Specifications or an unreviewed safety question to the ORC for review and approval DRAFT before proceeding with implementation. Safety evaluations on station design modifications which do not involve unreviewed safety questions or a change in CPSES Technical Specifications will be reviewed by ORC, however, this will not be a prerequisite for implementation. Upon recommendation from SORC, the CPSES Plant Manager approves each station design modification for implementation. Draft Version 17.2-14
~ Enclosure to TXX-89583- - Page 17 of 244 CPSES/FSAR h
0421.55- l All des'ign modification requests made by station personnel, shall be DRAFT submitted to the Manager, Nuclear Operations Support for coordination i of the station level engineering review. The actual change of design. for those design modification r quests approved by the CPSES Plant ! Manager may be done by NE0 engineering personnel or approved ng ee i fo ht R a tor n n r Dep me 11 be responsible. The above organizations will have approved oesign ! procedures and/or instructions before-any design modifications are. 53 l performed by the respective organization. These procedures and/or instructions will assure proper design review and verification. , These procedures and instructions will also assure that design control is commensurate with the original design. The Senior Vice President DRAFT-will assure that the designer is provided with the latest revisions to i l all drawings, specifications, and other design documents which are j applicable. l l I Design changes, including those originating on site, are subject to l the same controls which were applicable to the original design. NEO may designate an organization to make design changes other than the' l 1 one which prepared the original design. In these cases, NEO will assure that that organization has access to pertinent background information, including an adequate understanding of the requirements i 1 and intent of the or~:ginal design, and has demonstrated competence in l applicable design areas. 0421.56 The Senior Vice President shall coordinate necessary revisions to DRAFT drawings and other design documents. The Plant Manager shall I coordinate necessary revisions to plant procedures and instructions as DRAFT l a res( of design changes. Changes are promptly distributed to ensure availability to responsible plant personnel prior to 44 ; commencement of work. ' l 1
)
17.2-15 Draft Version
-x TEnc1csure to TXX-89583 LPage-18 of.24%, CPSES/FSAR m
.71-
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Design changes made'to the facility are accomplished in a planned and controlled manner in accordance with written, approved procedures.. These procedureslinclude provisions, as necessary, to ensure'that:
- 1. Design documents, Specifications, drawings, and' procedures and-instructions reflect applicable regulatory requirements and design bsses.
- 2. Design documents specify quality requirements or reference
. quality' standards as necessary.
62 3.- There.is adequate review of the suitability of materials, parts,- components.~ and processes which are essentia? to the safety-related functions of structures systems, cnd components. 62 4. Materials,; parts,'and components which are standard commercial
,(off the shelf) or which have been previously approved for a different application are evaluated for suitability prior to selection.
4- 5. Design documents are revised to reflect design modifications.
- 6. Internal and external design interfaces between organizations participating in design modifications are adequately controlled, includingLthe review, approval, release, and distribution of design documents and revisions.
62 The above controls are applied as n.ecessary to such aspects of design as reactor physics; seismic, stress, thermal, hydraulic, radiation, and-accident analyses; compatibility of materials: and accessability for inservice inspection, maintenance, repair and replacement. Draft Version 17.2-16 - _=__________--
t
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lL E ' Enclosur65toTXX-89583-JPag2 19 off244' ;CPSES/FSARL p The adequacyL of. design changas shall- be verified by the performance of:
. design reviews.' alternate calculations, or qualificationctesting.
-The control; measures'specified inithe plan for control of: design.
verification activities are as follows:
- 1. Personne1' responsible for design verification do not include the original designer or the designer's immediate supervisor.
- 2. Written procedures ;dcccify the positions- or organizations = <
responsible for design verification and define their authority and responsibility.
- 3. Qualification tests.to verify the adequacy of the design are performed using the most adverse specified design conditions.
4.. Design changes are reviewed to assure that design parameters are defined and that inspection and-test criteria are identified. Any errors or deficiencies found in the . design process or the design - itself are documented and corrective action taken, as described in Section 17.2.16. Design documents and revisions thereto are controlled and distributed as described in Section 17.2.6. Records of design activities and design changes are collected, stored, and maintained, as described in Section 17.2.17. 17.2.4 PROCUREMENT DOCUMENT CONTROL Requirements are established for the control of procurement documents 71 prepared by NE0, or their designated agents for safety-related components, materials, and services. These requirements are consistent with the provisions of Regulatory Guide 1.33 and Regulatory - Guide 1.123 as discussed in Appendix 1A(B) and apply to procurement documents prepared by NEO, or their designated agents. 17.2-17 Draft Version ___a
y
.Enclosuro.to TXX-89583 Pag 2120'of'P44' CPSES/FSAR
'71' Procurement documents, such as purchase specifications, contain or
; reference the following:
'0421.35-
.76 l'. The design basis technica1' requirements, including the applicable regulatory requirements, material and compcnent' identification requirements,. drawings, specifications, codes and industrial standards, and test and inspection requirements, including inspection hold points.
DRAFT 2. The applicable requirements of-10.CFR Part 50, Appendix B and of
-the QA Program, which must be complied with and described in'the ,
supplier's OA program: or, identification and verification of characteristics critical to the safety function of the procured l ' item to provide reasonable assurance that the item will perform its intended safety related function. 53 3. Identification of the documentation to be prepared, maintained, or submitted (as apolicable) to NE0 for review and approval. These documents may include, as necessary, inspection..and test records, qualification records, or code required documentation.
- 4. Identification of those records to be retained, controlled, and maintained by the supplier, and those delivered to the purchaser prior to use or installation of the hardware.
9 5. NE0's right of access to supplier's facilities and records for source inspection and audit.
- 6. Requirements for supplier reporting and dispositioning of nonconformances from procurement requirements.
- 7. Provisions for extending applicable requirements of the procurement documents to lower-tier suppliers. ~
Draft Version 17.2-18
l
- L " Enclosure to TXX-89583-Page'21 of=2441 ~CPSiS/FSAR~
15 0421.58 V NE0 procurement documents'are prepared, reviewed. approved.-and controlled in accordance with written procedures which clearly delineate' the, sequence of actions to be accomplished and which- 'F i
' identify the individuals or groups responsible for accomplishing those actions. These procedures include provisions for review of procurement documents. This review is perfo'?med to insure that necessary quality- 9
- requirements are incorporated and correct, and that procurement requirements for spare or replacement parts are equivalent to or better than those used for the original equipment. Documentary evidence of that review and approval is retained-and'available for verification.
. NEO evaluates ' supplier quality assurance programs. prior to award of '
contracts or issuance of purchase orders, as discussed in Section 17.2.7. 17.2.5 INSTRUCTIONS, PROCEDURES. AND DRAWINGS 0421.59-Activities affecting the quality of. safety-related structures, 71. systems, and components be prescribed by and accomplished in accordance with documented instructions, procedures, and drawings. The manager or supervisor. who has cognizance over a specific safety- 62 related activity is responsible for the development and approval of procedures and instructions for prescribing the accomplishment of that activity. Administrative procedures and instructions are reviewed and approved prior to performance of the activity. The cognizant 55 supervisor is responsible for ensuring that the activity is performed 53 in accordance with the procedures and instructions. The development. 76 review, and use of procedures, instructions, and drawings is reviewed on a periodic basis by the Manager. Quality Assurance as part of the station quality surveillance and audit program. These requirements are consistent with the provisions of Regulatory Guides 1.33, 1.30 15 - and 1.116 as discussed in Appendix 1A(B). 0421.59 17.2-19 Draft Version
- Encl osuro ' to .TXX-89583 LPage 22 of,244 CPSES/FSAR:
d"b * ' 71 Requirements regarding the content of various / types of instructions and procedures are-established which provide for thet inclusion, as-necessary, of items such as prerequisites, precautions, qualitative or h .quantitativeLacceptance criteria, inspection' points, and checklists,
~ depending upon the nature of the instruction or procedure.
Administrative procedures clearly delineate.the sequence of actions' to
.be accomplished in the preparation, review, approval, and control of those instructions and. procedures, and they identify the individuals responsible for those actions.
L 71 Confirmation that'these instructions and procedures meet requirements of.the OA Program and are properly implemented is accomplished through audit or surveillance' activities by the QA Department. 17.?. 6 DOCUMENT CONTROL
'71 ' Requirements are established for the control of documents-that prescribe activities affecting quality. The. documents which are to be controlled include:
.1. Design Specifications
- 2. Design, manufacturing, construction, and installation drawings
- 3. Procurement documents 71 4. The OA Manual and all station procedures and instructions which implement requirements of the QA Program.
53 E. Maintenance, modification, and operating procedures and instructions ll t Draft Version 17.2-20 1.
Enclosure to TXX-89583 ; Page 23 of 244 CPSES/FSAR
- 6. Final. Safety Analysis Report l53 7 Inspection and test procedures and instructions l53 i
These requirements are consistent with the provisions of Regulatory 71 Guide 1.33 as discussed in Appendix 1A(B) and include the following measures: 0421.60
- 1. Documents, and changes thereto, are reviewed for adequacy and approved for release by authorized personnel in accordance with written procedures. These procedures identify those individuals or groups responsible for reviewing, approving, and issuing documents and revisions thereto. These reviews include as 76 appropriate a review for QA-related aspects by the NEO OA Department or an individual other than the person who generated the documents but qualified in quality assurance.
- 2. Documents, and changes thereto, are promptly distributed to ensure availability prior to commencement of work.
- 3. Changes to documents are reviewed and approved by the same organization that performed the original review and approval unless another qualified organization is designated.
- 4. Haster status lists identifying the current revision of documents are periodically updated and utilized to preclude the use of superseded documents.
- 5. Obsolete or superseded documents are destroyed or identified to prevent their it. advertent use.
Documents generated by NE0 are controlled in accordance with written, 53 approved procedures and instructions. Maintenance, modification and - inspection procedures and instructions affecting safety related 17.2-21 Draft Version
LEnclosure to TXX-89583 Pag 2 24'of 244 CPSES/FSAR-
- 53- equipment are reviewed by a person knowledgeable.in 0A disciplines to determine:
0421.6 - 9 .A. The need for inspection, identification of inspection personnel. and documentation of inspection results. 0421.6
.9- B. That the necessary inspection requirements, methods, and
~
acceptance criteria have been identified.
' 74' The Manager, OA and the Manager. OC are responsible for providing the necessary reviewstof these procedures and instructions. ,
17.2.7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 71- Requirements are established for the control of purchased safety-related material, equipment and services including spare or 76 replacement parts. These requirements are consistent with the provisions of Regulatory Guides 1.33, 1.38, and 1.123 as discussed in Appendix 1A(B). 59 Measures have been established in procedures which determine the level of quality assurance required for the procurement of an item or
-service. As-required, contractor and suppliers are evaluated by -
quality assurance personnel prior to award of a purchase order or contract to assure the contractor's or supplier's capability to comply with procurement document requirements. This evaluation is based on one or more of the following:
- 1. A review of the supplier's quality assurance program description provided with the proposal / bid.
l~ 1 L 2. A review of historical evidence of the supplier's performance in providing similar items or services. - l l. 1 i Draft Version 17.2-22 l _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
H it Enclosure to TXX-89583 (, PageL25 of 244' CPSES/FSAR. [ . 3' ~. .A preaward survey:of the supplier's facilities and-0A program. 0421.62 [ Technical requirements for items and materials to be procured are 9
; developed byLthe design,or engineering organization responsible for 7 the modification or maintenance activity. Procurement documents for 62 Esafety related items and materials,are' reviewed for inclusion'of
. technical;and quality' assurance requirements by.the Quality Assurance.
L
~ Department prior to initiation of the procurement action by;the g; purchasing organization. The results:of the" quality assuranoe review are documented and. retained for future reference. 9 Surve111ance', inspection and audit of suppliers and contractors, are 76.
conducted where appropriate, to assure compliance with quality requirements. The Quality Assurance Department is responsible for surveillance, inspection und audit of offsite suppliers and contractors. The CPSES Quality Assurance Section is responsible for surveillance of contractors providing services onsite. Surveillance 62 of suppliers'and contractors is performed by~ qualified personnel in 53.- accordance'with written procedures, instructions and checklists. Surveillance, inspection and audit of suppliers are performed to an 76 extent consistent with the importance, complexity, and quantity of the item (s) being purchasec! and include measures to periodically confirm the' validi.ty of suppliers' certificates' of conformance. Quality verification-records are reviewed by quality assurance personnel to assure their completeness and their compliance with procurement document requirements. Receipt inspections at CPSES are performed by qualified quality 53 control inspectors in accordance with written procedures and instructions to assure that:
- 1. Materials, equipment, or components are properly identified and -
correspond with associated documentation. 17.2-23 Draft Version
EnclosurG to TXX-89583 PagQ 26 of 244 CPSES/FSAR
- 2. Inspection records or certificates of conformance attesting to the acceptance of materials, equirment, and components are completed and are available at CPSES prior to installation or use,
- 3. Materials, equipment, and components are inspected and judged acceptable in accordance with predetermined inspection instructions prior to installation or use.
- 4. Items accepted or released are identified as to their inspection status prior to forwarding them to a controlled storage area or releasing them for installation or further work.
- 5. Nonconforming items are clearly identified, controlled, and segregated where practical, until proper disposition is made.
17.2.8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS 71 Requirements are established for the identification and control of safety-related materials, parts, and components, including spare or replacement items. These requirements are consistent with the provisions of Regulatory Guides 1.33, and 1.38 as discussed it Appendix 1A(B). 71 Materials, parts, and components are identified and controlled to prevent the use of incorrect or defective items. Identification of items is maintained either on the item in a manner that does not affect the function or quality of the item, or on records traceable to l the item. Suppliers of safety-related materials, parts, or components are required by procurement documents to establish a system of - identification and control which is consistent with the above requirements. Draft Version 17.2-24
JEncl$sure to!TXX-89583: I Page'27;of 244 CPSES/FSAR q
. Procedures and instructions implementing these requirements provide _ 53 !
~
x .for the-following: i 1.- m ,
' Verification that items. received onsite are properly identified -l ;
and can be traced to the' appropriate documentation. such as ' -! It drawings, specifications, purchase orders, manufacturing and inspection documents, nonconformance reports or mill test reports.- 2.- . Verification of item identifi;ation consistent with the inventory control system and traceable to documentation which l identifies the proper uses or applications of the item. ] I 17.2.9- CONTROL OF SPECIAL PROCESSES 0421'.J3 Requirements'are established for the contrcl of special processes. 76' , s which are those processes where direct inspection is impossible or i disadvantageous such as welding, heat treating, nondestructive testing, and cleaning, which are consistent-with the provisions of ] Regulatory Guides 1.30, 1.33, 1.37, 1.58, and 1.94 as discussed in ~i Appendix 1A(B). j i
- j. Special processes are performed by qualified personnel using proper 71 j equipment and in accordance with written qualified procedures and -{
instructions. These personnel, procedures and instructions are to be qualified in accordance with applicable codes, standards, and 53 L specifications. Qualification records of special process procedures and instructions, and personnel performing special processes are filed, maintained, and available for verification, j 0421.64 1 Qualification of special processes, equipment, and personnel is the 62 responsibility of the cognizant Managers or 17.2-25 Draft Version l u .
Enclosure to TXX-89583 Page 28 of 244. CPSES/FSAR 62- Section Supervisors. Qualified test laboratories and consultants may 9 be used in qualification of special processes. Procedures shall be developed which delineate the requirements for special process. 76 These procedures shall be reviewed by the Quality Assurance. Department. 17.2.10 INSPECTION 71 Requirements are established for an inspection program to verify conformance of activities affecting quality with requirements 76 specified for those activities. These requirements are consistent with the provisions of Regulatory Guides 1.30, 1.33, 1.39, 1.58, 1.94, and 1.116 as discussed in Appendix 1A(B). 0421.48 0421.11 74 The Manager, QC is responsible for administering and implementing the 76 CPSES quality control inspection program. Inspections are performed by quality control inspectors who are qualified and certified in accordance with ANSI N45.2,6-1978 and who are independent of the individuals performing or directly supervising the activity being inspected. The quality control inspectors may be selected from among 74 any of the NEO departments, including contract personnel, and will report directly to the Hanager. OC when acting in the capacity of quality control inspectors. All quality control inspection personnel 13 have authority to stop unsatisfactory work and control further processing, delivery, or installation of nonconforming material, parts 71 or components. The quality control inspector's qualifications and certifications are maintained current through the NEO training program. 0421.83 14 Inspections at CPSES are performed in accordance with written procedures, instructions, or checklists, appropriate to the Draft Version 17.2-26
y, -; i ) Enclosure to'TXX-89583-e ~ PLg2 29 of:244- CPSES/FSAR-4 circumstances which provide for the following: ,14 ; 0421.35
.h- Identification of characteristics and activities to be- 76' -j
) -inspected. including inspection hold points.
- 2. ' Acceptance and rejection criteria.-
- 3. Method of-inspection.
- 4. Recording the results of the inspection and identification of ~
the quality control inspector. T 5. Indirect control by monitoring of processing methods, equipment, j and personnel when direct inspection is not possible. 0421.66.
- 6. Identification of any required procedures, drawings, or 11
+ specifications.
r 0421.67 L Station administrative procedures controlling the Measuring and Test 11- [F Equipment program contain criteria for determining the accuracy of M&TE to be used in performing inspections depending upon the accuracy requirements of the parameters being measured. 0421.35 Maintenance, repair, and modification procedures and' instructions 53 containing inspection criteria shall be reviewed by a level III inspector qualified in accordance with ANSI N45.2.6-1978 to ensure that adequate inspection hold points are included and that the inspection methods are adequate. Criteria contained in appropriate station administrative procedures and in applicable codes and 11 standards shall be used in determining when inspections and tests are required. In addition, administrative control procedures and instructions are DRAFT reviewed by the OA Section to assure that required controls are included and to provide for the necessary reviews for the assignment of inspection hold points. j 17.2-27 Draft Version
. Enclosure to TXX-89583 Paga 30:of 244' CPSES/FSAR .
~0421.58 9 Inspection results are documented-in accordance with procedures.and-
,9 instructions developed and approved for that activity. Inspection.
results-are. evaluated and then acceptability determined by individuals
-qualified to perform that function in accordance with the station training program. Records of the evaluations are documented and retained in the station quality records.
4 . Contractors performing work at CPSES and equipment and material suppliers are required to work under inspection programs consistent with applicable codes and standards. These contractors and suppliers are required to provide work' plans or ' inspection and fabrication. procedures or outlines, which are reviewed for adequacy by NEO personnel. y 17.2.11 TEST CONTROL 71 Requirements are established for the control of testing of safety-1 76 related systems,. equipment, and structures. These requirements are consistent with the provisions of Regulatory. Guides 1.30.-1.33, 1.58, 1.68, 1,68.2, 1.94, and.1.116 as discussed in Appendix 1A(B). 17.2.11.1 Test Prooram 71 Preoperational and initial startup testing is performed in accordance with Section 14.2 of the FSAR. I' i Surveillance testing is performed during the operational phase to verify continuing operational readiness and adequacy for those systems and components which are normally in a standby condition and to evaluate whether there has been any degradation of performance, or any departure from the prescribed operating conditions for the systems or components normally in service. - Draft Version 17.2-28
- l. . . . . . . . . ..
i IEnclosurG to TXX-89583 h' Page 31 of 244 CPSES/FSAR l h ' Tests are performed following station modifications or repairs to demonstrate satisfactory performance prior to placing affected. items: in service.. When' pressure boundaries are breached functional tests 71 shall. be conducted to the extent required-to demonstrate acceptability of the repair or maintenance. 17.2.11.2 Test Procedures Testing is identified documented, and controlled in accordance with written administrative procedures. Each test is accomplished in accordance with written test procedures by qualified personnel. The. administrative procedures controlling the test program identify the necessary test procedures,'the provisions to be included in those procedures, the method of reviewing and approving those procedures, and the methods for documenting and evaluating the results. Test procedures include the following provisions as appropriate:
- 1. Prerequisites - those items of work which.must be completed prior to establishing initial conditions for'the test, including:
- a. Calibrated instrumentation;
- b. Adequate and appropriate equipment;
- c. Initial conditions and completeness of the item to be tested; and
- d. Suitable environmental conditions, if applicable 76
- 2. Special precautions - items needed for safety of personnel or equipment. Special situations where caution or extraordinary attentiveness to operational circumstances is required.
- 3. Instructions for performing the test - steps required to conduct ~
the test, observations to be made, data to be recorded. 17.2-29 Draft Version
m , l ! Enclosure to TXX-89583 :CPSES/FSAR" Page:32tof 244
' 4. Acceptance criteria l- criteria against which'the success or-
~
~
~
o s failure of the test can>be determined.
- 76' SE " Phovisi'on's for collecting. documen' ting, or recording test data o and results.
L17.2.11.3' Test Results Records of test results are reviewed by qualified personnel to assure acceptability. These records are retained as quality. verification records in accordance.with the controls described in Section 17.2.17.- 17.2.12 CONTROL OF MEASURING AND TEST EQUIPMENT
-76 The TV Electric Quality Assurance Program provides measures for the-control of measuring and test equipment (M&TE) used as the basis for -
acceptance in. inspection, testing, and measurement activities which affect quality. 76~ The Nuclear Engineering and Operations organization is responsible for the development of procedures for the M&TE control program. These-procedures delineate responsibilities for the implementation of this program and methods for the procurement, handling, storage, control, scheduling, and calibration of M&TE and reference standards. For the operations phase these methods are consistent with the provisions of Regulatory Guide 1.33 as discussed in Appendix 1A(B).
'76 TU Electric Quality Assurance performs pre-awared evaluations / surveys as well as periodic audits and surveillance to assure adequacy and effective implementation of the M&TE program.
76 M&TE and reference standards are traceable to their calibration
' DRAFT records. These devices are labeled or tagged to indi ate the next calibration due date or otherwise controlled in accordance with approved proce'dures which ensure only M&TE and reference standards with current calibration are utilized.
Draft Version 17.2-30
Enclesure to TXX-89583 Page 33 cf 244 CPSES/FSAR Periodic calibration and adjustment of M&TE is performed and 76 controlled to assure accuracy is maintained within limits necessary to I verify that design and operating condition requirements have been met. M&TE is normally calibrated against reference standards
'which have an uncertainty of no more than one fourth (1/4) of the r equired uncertainty of the M&TE being . calibrated. If this 4:1 DRAFT accuracy requirement is not reasonably 'ochievable, a documented evaluation of the adequacy of the calibration is performed and approved by the responsible discipline Engineering Manager.
Calibrating standards have accuracy greater than or equal to reference DRAFT standards being calibrated. If equal accuracy is used, the basis for calibration is documented and approved by the manager of the organization which is responsible for the calibration. M&TE and reference standards are traceable to nationally recognized 76 standards or natural physical constants. Where no nationally DRAFT recognized standard or natural physical constant exists, the basis for calibration is documented and approved by the manager of the organization which is responsible for the calibration. When M&TE or reference standards are lost or found to be out of DRAFT calibration, a documented review is conducted to determine the validity of all inspection, test and/or ineasurement results gained through the use of the affected device since its last acceptable calibration. Corrective action is taken for items determined to be suspect. 76 Contractor and supplier organizations which provide 76 engineering / calibration services to TV Electric are responsible for implementing measures to ensure that M&TE accuracy is maintained within required limits. The M&TE programs of these organizations shall satisfy the TU Electric M&TE program requirements. - 17.2-31 Draft Version
M;5EnclosuretoTXX-89583
~Page'34.-of,244 CPSES/FSAR-17.2.13' HANDLING, STORAGE,'AND SHIPPING 71~
Requirements are established for the control, handling, storage, shipping. cleaning, and preservation of material and equipment in i
-accordance with established instructions, procedures, or drawings.
76 'These requirements are consistent with the provisions of Regulatory Guides 1.33..'1.38. and 1.39 as discussed:in Appendix 1A(B) and include the following provisions, as necessary: 0421.70 53 1.. For critical, sensitive', perishable, or high value items, specific written procedures and instructions for handling, storing, packing, shipping, and preserving are used. These 9 procedures and instructions reflect design and specification requirements such as inert gas' atmosphere, specific moisture content levels, and temperature levels, and reflect manufacturers recommendations in regards to special handling and storage requirements such as shelf life and environmental controls.
- 2. Personnel responsible for handling these special items are qualifie'd to the extent required by these special handling
. instructions.
- 3. Special handling tools and equipment are inspected and tested in accordance with written procedures to verify that they are adequately maintained.
17.2.14 INSPECTION, TEST, AND OPERATION STATUS 71 Requirements are established for identification and control of the inspection, test, and operating status of safety-related structures, systems, and components. These requirements are consistent with the provisions of Regulatory Guide 1.33 as discussed in Appendix 1A(B). ~ Draft Version 17.2-32
- Enclosure' to TXX 89583 Pag 2 35.of 244 CPSES/FSAR Written' procedures and instructions prescribe-the use of tags, labels, 53
- -and logs to indicate the inspection, test, and' operating status of systems <and equipment at CPSES. These procedures and instructions also provide for tagging of nonconforming, inoperative, or ll malfunctioning equipment to prevent inadvertent use. In addition.
L -these procedures and instructions identify those individuals who are
-authorized to apply or remove those tags and labels and provide for.
the use of logs to maintain the status of tags and labels ~in use at CPSES. CPSES personnel and contractor personnel working onsite are instructed regarding the purpose of, and precautions associated with, the various tags and labels used at CPSES. Proper use of tags and labels to DRAFT indicate inspection, test, and operating status is . verified through surveillance and audit by onsite Quality Assurance personnel. 17.2.15 NONCONFORMING MATERIALS, PARTS, OR COMPONENTS Requirements are established for the control of nonconforming 71 materials,. parts or components. These requirements are consistent
.with the provisions of Regulatory Guides 1.33, 1.38, and 1.123 as discussed in Appendix 1A(B).
Material, parts, or components found nonconforming through review. DRAFT inspection, or testing are controlled by administrative procedures. These procedures provide for the following: 71
- 1. Identification of nonconforming items, prior to installation. 76 by use of nonconformance tags, and segregation of those items, if practical, to prevent inadvertent use pending proper disposition and reinspection.
- 2. Identification of those individuals or organizations responsible -
for disposition of nonconforming items. 17.2-33 Draft Version
I r Enclosure to TXX-89583 .CPSES/FSAR-Page 36 of 244
. 7'6 3'-
. Preparationiof nonconformance documents which identify-nonconforming items and describe the nonconformance, the- _
Disposition:of the nonconformance. and the reinspection or testing; performed.to determine the. acceptability of the item after'the disposition has been completed.
-76 4. Review of nonconformance documents written on installed plant DRAFT equipment to determine impact on operability. The
, administrative controls assure that nonconforming materials do.
not affect the operability of safety related equipment in violation of Technical Specification requirements, u DRAFT 5. Conditional releases allow issuance of nonconforming items from
- the warehouse for initial installation and testing.
Conditional releases also allow operation of the item pending disposition of.the nonconformance provided credit is not taken for Techncial-Specifiestion operability of the item. Each conditional . release also describes any limitations or special' precautions required. Conditional releases are periodically evaluated as to their status and the resu'Its forwarded to management for their review.
- 6. . Verification of the acceptability of rework / repair of items by
- t' reinspection or testing of the item as originally perfo'rmed or by a method which is equivalent to the original inspection and testing method.
- 7. Nonconformance reports which are dispositioned "use as is" or
" repair" are made part of the quality verification records associated with the items.
- 8. Periodic analysis of these reports to be performed and forwarded to management to show quality trends.
~
0421.72 DRAFT -Responsibility for the implementation of activities related to nonconformance control is assigned to the cognizant manager of the area of concern. Nonconformances which are resolved by repair or use-as-is dispositions are reviewed and approved by Engineering. Draft Version 17.2-34
[Enclesurhto'TXX-89583-
~PagQ 37 of 244~ .
CPSES/FSAR-t
~
0421.71'
;Independentireview offnonconformances, including disposition and 65 closeout. is performed by appropriate Quality. Assurance personnel.
0421.73. Markin'g and segregation of nonconforming items, when required,-are DRAFT addressed in. station procedures. Compliance with these-administrative requirements is . verified through the station 53'
-surveillance and audit program.
17.2.16' CORRECTIVE ACTION' Requirements are established for the identification and correction of' 71 conditions adverse'to quality. These requirements are consistent with the provisions of Regulatory Guide'1.33 as discussed in Appendix 37. IA(B). Conditions adverse to quality, such as failures, malfunctions,- 71 deficiencies and deviations, identified through review of documents, surveillance,: audits. or experience during operation, are documented and dispositioned. Significant conditions adverse to quality are.
.evalua'ed t to determine the cause of the condition and the corrective-action to be taken to preclude recurrence.
Reports of significant conditions adverse to quality are reviewed by the Operation Review Committee and that committee's decisions and/or recommendations regarding corrective action are forwarded to appropriate management pe'rsonnel . Follow-up reviews to verify proper implementation of corrective action are conducted by quality assurance ~ personnel. 17.2.17 OUALITY ASSURANCE RECORDS Requirements are established for the identification. collection, and 71 ~ storage of quality assurance records. These requirements are 17.2-35 Draft Version
Enclosure to TXX-89583 Page 38 of 244 CPSES/FSAR consistent with the provisions of Regulatory Guides 2.33 and 1.88 as discussed in Appendix IA(B). 71 Sufficient records are maintained to provide documentary evidence of the quality of items and of the accomplishment of activities affecting quality. Records to be maintained include such items as drawings, specifications, procurement documents, nonconformance reports, corrective action reports, operating logs, personnel and procedure qualifications, results of inspections and test, material certifications and test results, and audit reports. 53 Quality assurance records are maintained in accordance with procedures and instructions which assign responsibilities for the collection, maintenance, and protection of records. These procedures and instructions provide a system of record identification to assure retrievability and prescribe retention periods for various types of records. 0421.74 DRAFT The Senior Vice President is responsible for development of procedures and instructions to implement the management requirements related to 0A records. The OA Department reviewt and approves the 76 administrative control procedures and instructions and the retention periods assigned for quality assurance records. 74 Ouality assurance records are stored in specially constructed storage facilities at CPSES to prevent their destruction, deterioration, or theft. Records are stored in the Engineering Records Center, the Operations Records Center, and the Project Records Center. These storage facilities, and others which may be designated in the future, are designed, constructed, and maintained in accordance with the applicable requirements of the regulatory guides referenced above. Access to the records facilities is controlled so that only authorized Draft Version 17.2-36 l _ ________-__-
Enc 1csure to TXX-89583 CPSES/FSAR Page 39 of 244 personnel have access to the records areas. As allowed by ANSI 76 N45.2.9-1974, maintenance of duplicate records stored in a remote location may be used as an alternative to the utilization of these storage facilities, and the appropriate administrative controls for the maintenance of duplicate records are prescribed by procedures ano instructions. 17.2.18 AUDITS Requirements are established for an audit program. The audit program 76 is consistent with the applicable portions of Regulatory Guides 1.33,. 1.144, and 1.146 as discussed in Appendix 1A(B), Planned and periodic audits are performed in accordance with written 71 procedures to verify compliance with all aspects of the quality assurance program. Responsibility for the audit program has been assigned to the Director Quality Assurance. Audits are conducted by 62 personnel of the Quality Assurance Department and include examination of quality-related activities such as:
- 1. Operation, maintenance, and modification of CPSES.
- 2. Receiving and work inspection.
1 i
- 3. Preparation, review, approval and control of instructions, procedures, drawings, specifications, and other quality-related l documents.
l
- 4. Indoctrination and training.
- 5. Control of measuring and test equipment.
l 17.2-37 Draft Version \. .__. _ - _ - _ _ _ _ _ _ - _ _ - _ _ - - _ -
ic 4 l I L Enclosura to"TXX-89583 L 'Page 40iof 244 CPSES/FSAR: L
- ' Organizations performing: activities affecting quality that are subject to audit' include the following:
1' f m s L55% -1 Thel engineering and construction, startup. operations, maintenance, engineering, quality assurance, and support. organizations for CPSES. l
~ 2. Contracto.rs,. consultants, and suppliers of. quality related items !
.or service. !
.0421.75 -l 33 As part.of the Quality Assurance program NEO OA:. ;
l l l
.9 1. Utilizes an audit planning document which defines the
organizations and activities to be audited and the frequency of the audits. 9 2. Requires auditors to be familiar with the type of activities to.
-be audited and have no direct responsibilities in the area being ,
I audited.
'l i
I 9 3.- Provide auditing checklists or other. objective-guidelines to ; identify those activities which affect quality. -! I l
.9 '4. Requires examination of the' essential characteristics of the l quality activity examined. !
'l 1 9 5. Requires an audit report be prepared and that it notes the l extent of examination and deficiencies found.
i 1 9 .6. Requires the audit report be sent to management responsible for , 1 the area audited for review and corrective action for j deficiencies. I i l. Draft Version 17.2-38 I
._.___________-__-___-___D
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~ : EnclosurG 7toiTXpB9583jt)b<p;;
P< Yb,l $n
, ?PaggL41"ofD244f, ' *
?CPSES/FSAR
.p.
11:., , ,
. 7. . l 1 Requires ' corrective "cction taken as result of the audit be 9
. reportddi '
- 8. . . Requires reauditing ofL deficient areas when.it isFconsidered: '9- 1 %
necessary to verify -implementation of- required corrective i W"#M
~
i: ;
' acti ons',i 4
s 3
' 9.: Requirds vendors / subcontractors to comply with items 1-8'above? E 37f , I tc th'e-' extent necessary.
.l' 1
, ...y' .
'Documentationiof audits performed bf I participating contractors is mades 53" .l available:to.-NE0 for evaluation. ~
;0421.75^ -)
In svamdr'yONE0 verifies conformance of the regulatory audit 1 19. requireteents- UN three methods: ~ l i
\
- 1. Review of contractor's/ vendors' quality assurance methods for 1 71( ,
auditing. :i 1 l 3
- 2. Review of documentation of the audit report performed by these- '71 contractors / vendors. )
l
- 3. Internal and external audits performed by members of the Quality 9 Assurance staff. ;
i.
)
i
. .i i
1-l l l i i i l . i 1 17.2-39 Draft Version o
L Enclosure to TXX-89583 Page 42 of 244' CPSES/FSAR TABLE 17.2-2 (Sheet 1.of 3) a REGULATORY GUIDES AND INDUSTRY STANDARDS s
-ThelCPSES quality assurance program is consistent with the applicable 71-guidance of the NRC Regulatory Guides and industry standards listed below. TV Electric will commit to comply-with the respective
. regulatory positions as discussed in Appendix 1A(B).
Regulatory Guide Titig 7
~
- 1. 8 ' Personne1 Selection _an'd. Training 76 (endorses ANSI N18.1-1971) 71 1.26 Quality Group Classifications and DRAFT-Standards for Water . Steam . and i
Radioactive- Waste-Containing Components of Nuclear Power Plants (see Appendix 1A(B) for CPSES position and compliance) , t 1.28 Quality Assurance t'rogram Requirements. I'76 (Design and Construction) (Endorses ANSI N45.2-1971) 1.29 Seismic Design Classification DRAFT 1.30 Quality Assurance Requirements for 3 u , Installation. Inspection, and Testing of Instrumentation and Electric Equipment L (endorses ANSI N45.2.4-1972) 1.33 Quality Assurance Program Requirements L (Operations) (endorses ANSI N18.7-1976)
- CPSES/FSAR' l Enclosureito!TXX-89583 ? TABLE 17.2-2 lPaga 43 of 244 :
(Sheet 2) REGULATORY GUIDES AND INDUSTRY' STANDARDS Regulatory. __sgide- Titig " 1.37 ' Quality Assurance Requirements for, Cleaning'of Fluid Systems and Associated' a Components of Water-Co'oled Nuclear Power-Plants-(endorses ANSI N45.2.1-1973)'
-1.38 Quality Assurance Rsquirsments for Packaging, Shipping ~, Receiving, Storage,:
and Handling of, Items for Water-Cooled:
-Nuclear Power.-Plants (endorses ANSI N45.2.2-1972) 1.39~ Housekeeping Requirements' for Watercooled -
Nuclear Power Plants (endorses ANSI N45.2.3-1973) 1.58 Qualification of Nuclear Power Plant Inspection. Examination, and Testing Personnel (endorses ANSI N45.2.6 1978) 1.64 Quality Assurance Requirements for Design of Nuclear Power Plants (endorses ANSI N45.2.11-1974) 40 DRAFT 1.74 Quality Assurance Terms and Definitions (endorses ANSI N45.2.10-1973) b 1.88 Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records (endorses ANSI N45.2.9-1974)
'Encicsure to TXX-89583 CPSES/FSAR Pag] 44 of 244 TABLE 17.2-2 (Sheet 3)
REGULATORY GUIDES AND INDUSTRY STANDARDS Regulatory Guide Title 1.94 Quality Assurance Requirements for 76 Installation. Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (endorses ANSI N45.2.5-1974) 1.116 Quality Assurance Requirements for Installation. Inspection, and Testing of Mechanical Equipment and Systems (endorses ANSI N45.2.8-1975) 1.123 Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants (endorses ANSI N45.2.13-1976) 1.144 Auditing of Quality Assurance krograms 76 for Nuclear Power Plants (endorses ANSI N45.2.12 - see Appendix 1A(B) for CPSES position and compliance) 1.146 Qualification of Quality issurance 76 Program Audit Personnel for Nuclear Power Plants (endorses ANSI N45.2.23-1978) 76
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