ML20199B994
| ML20199B994 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/27/1998 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20199B990 | List: |
| References | |
| NUDOCS 9801290076 | |
| Download: ML20199B994 (513) | |
Text
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l ATTACHMENT I TO W3F1-98-0013 l -~ ._ QAPM Table of Contents Revision 12 Changes affecting CAPM Chapters 1,16, and Appendix A to Revisions 11,6, and 5, respectively l
9001290076 980127 PDR ADOCK 05000382 P PDR_
g WAT'ERFORD 3 TABLE OF CONTENTS REV. 12.0
- Entergy QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 1OF1 TITLE q REVISION DATE Forward and Policy Statemn " 1,0 04/22/92 Chapter 1 Organizati n MI & Pr3g'rarn' / h 11.0 10/16/96 l Chapter 2 QualityMdbroned 9.6 03/20/96 Chapter 3 Design Control 3.0 06/14/95 CMpter 4 Procurement Document Control 4.0 01/16/95 Chapter 5 Instructions, Procedures, and 4.0 03/20/96
, Drawings 1
Chapter 3 Document Control 5.0 01/16/95 Chapter 7 Control of Purchased Materials, 5.0 01/16/95 Equipment, and Services Chapter 8 Identification and Control of Materials, 4.0 01/16/95 Parts, and Components Chapter 9 Control of Special Processes 5.0 10/25/95 Chapter 10 Inspection 6.0 03/20/96 Chapter 11 Test Control 2.0 03/20/96
- Chapter 12 Control of Measuring and Test Equipment 2.0 06/11/93 Chapter 13 Handling, Storage, Packaging and Shipping 4.0 01/16/95 06/11/93 Chapter 14 Inspection, Test, and Operating Status 1.0 Chapter 15 Nonconforming Materials, Parts or 5.0 07/01/94 Components Chapter 16 Corrective Action 6.0 10/16/S6 l
-Chapter 17 Quality Assurance Records 4.0 01/16/95 Chapter 18 Audits 5.0 03/20/96 Appendix A Regulatory Guidance Document 5.0 10/16/96 l Appendix B 10CFR50, Appendix B Compliance 0.0 04/01/91 Appendix C Terms and Definitions 5.0 10/07/94
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE:
Revise the Quality Assurance Program Manual (QAPM), Chapter 1, Rev.10.0, to address the composition of PORC.
10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment O Yes *
- No to the QA Program description previously accepted by the NRC?
Explain:
Tha Waterford 3 Quality Assurance Program Manual, Chapter 1, Revision 10, Paragraph 4.9.2 will be revised to state:
'Tha PORC shall be composed of site management members as assigned, in wnting, by the GMPO. The GMPO will also indicate, in wnting, the PORC Chairman."
This change provides the GMPO the flexibility to meet PORC membership needs and still allow for organizational ch!nges. QAPM, Chapter 1, Revision 10, Paragraph 4.9.3 currently assigns responsibility to the GMPO to assign PORC alternates and a temporary PORC chairman. This change is consistent with these responsibilities, addresses tha Waterford 3 desire to upgrade the composition of PORC, ensures PORC effectiveness, and does not result in a IIssening of commitment.
- 2. If item 1 above is YES, does the proposed change include the basis to conclude that the revised program incorporating the O Yes O No ** N/A change continues to meet the criteria of 10CFR50 Appendix B and other previously accepted PSAR commitments?
Explain:
lf L YO D Reviewed By:' ' QA ReqTr'esentative Date RECOMMENDATION:
Does not represent a lessening of commitment and it can be implemented immediately.
Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation.
Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the chan e should not be processed.
Ab '
Recommended By: QA Supervisor Date DISPOSITION:
Approved for implementation Disapproved O Approved for submittal to the NRC for acceptance Approved By:
=0wiQs
'QA Mandger [
%ht' date QAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11
______J
CHANGE
- Address the composition of PORC. Para. 4.9.2 - Change will read: "The PORC shall be
{
composed of site management members as assigned, in writing, by the GMPO. The GMPO will also indicate, in writing, the PORC Chairman."
BASIS FOR NO REDUCTION OF COMMITMENT This change provides the GMPO the flexibility to meet PORC membership needs and still allow for organizational changes. Chapter 1 Rev.10, Para. 4.9.3 (now 4.10.3 deleted) currently cssigns responsibility to the GMPO to assign PORC alternates and a temporary PORC Chairman. This change is consistent with these responsibilities, addresses the Waterford 3 desire to upgrade the composition of PORC, ensuras PORC effectiveness, and does not result in a lessening of commitment.
OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Rev.10 4.9.2 i
m '
,q WATERFORD 3 CHAPTER 1 REV.10.0
( / Entergy QUALITY ASSURANCE R TYPE: C1.31
~ Operations PROGRAM MANUAL PAGE 10 OF 15 4.8.10 Records of SRC &ctivities shall be prepared, approved, and distributed as indicated below-
- a. Minutes of each SRC meeting shall be prepared, approved, and forwarded to t'le Vice President, Operations within 14 days following each meeting;
- b. Reports of reviews encompassed !n paragraph 4.8.8 above shall be prepared, approved, and forwarded to the Vice Preslosnt, Operations withir) 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of t hapter 18 shall be forwarded to the Vice President. Operations and to the mar assment positions responsible for the areas audited within 30 dayr after completion of the audit by the auditing organization; 4.9 Plant Operations Review Cor.1mittce (PORC) 4.9.1 The PORC sha'l function to advise the General Manager, Plant Operadons on all matters to nuclear safety.
4.9.2 The PORC shall be composed of the following members with either the Man 0ger Technical Services or the Manager Operations and Maintenance s the Chalm'an:
Manager Technical Services Manager Operations and Maintenance l Management Knowledgeable in Engineering' l
l Maintenance Superintendent Operetions Superintendent Radiation Protection Superintendent Management Knowledgeable in Quality Assurance / Control
- Management knowledgeable in engineering is one of the following: STA Supervisor, Systems Engineering Electric /HVAC Supervisor, Systems Engineering Mechanical Superviser or Reactor Engineering and Performance Supervisor.
4.9.3 in the absence of the PORC Cnalrman, the General Manager, Plant Operations will appoint a temporary Chairman. All other attemnte members shall be appointed in wnting by the PORC Chairman to serve on a temporary basis; however, no more than two attemates shall participate as voting members in PORC activities at any one time.
4.9.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated attemate.
4.9.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions shall consist of the Chairman or his designated attemate and three members, including attemales.
l
/ WATERFORD 3 CHAPTER 1 REV.11.0 L Ent UALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 14 OF 21
- b. Reports of reviews encompassed in paragraph 4.8.8 above shall
, be prepared, approved, and fonvarded to the Vice President, Operations within 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of Chapter 18 shall be forwarded to the Vice President, Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization; 4.9 Plant Operations Review Committee (PORC) 4.9.1 The PORC shall function to advise the General Manager, Plant Operations on all matters related to nuclear safety.
4.9.2 The PORC shall be composed of site management members as .
assigned, in writing, by the GMPO. The GMPO will also indicate, in M writing, the PORC Chairman.
4.9.3 In the absence of the PORC Chairman, the General Manager, Plant Operations will appoint a temporary Chairman. All other alternate I
members shall be appointed in writing by the PORC Chairrnan to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
4.9.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.
4.9.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions shall consist of the Chairman or his designated alternate and three members, including alternates.
4.9.6 The PORC shall be responsible for;
- a. Review of (1) all plant administrative procedures required by Technical Specification 6.8 and changes thereto, (2) all programs required by Technical Specification 6.8 and changes thereto, (3) changes to the Waterford 3 Emergency Operating Procedures required to implement the requirements of NUREG 0737 and NUREG 0737, Supplement 1, as stated in Generic Letter 82-33, and (4) any other proposed procedures or changes thereto as determined by the General Manager, Plant Operations; e
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QUALITY ASSURANCE PROGRAM J 2 CHANGE REVIEW FORM PROPOSED CHANGE:
Rsvise the Quality Assurance Program Manual (QAPM), Chapter 1, Rev.10.0. to address the composition of the SRC, <
10CFR50.64 REVIEW:
- 1. Does the proposed change represent a reduction of commitment to the QA Program description previously accepted by the NRC?
C Yes @ No Explain:
The Waterford 3 Quality Assurance Program Manual will be revised to change the following:
I ' Chapter 1, Revision 10,0, Paragraph 4.2.2 which currently shows the Vice President, Operations as the SRC Chairman will be revised to read: "The Vice President, Operations is responsible for appointing the Chairman of the Safety Review Committee (SRC). The Vice President, Operations is also responsible for oversight of the SRC,"
This change does not represent a lessening of commitment as currently justified in the following paragraphs of Chapter 1, Revision 10.0 of the QAPM:
- Paragraph 4.8.1 requires the SRC to provide an independent review. The guidance in ANSI N18.7, Paragtsph 4.3.3 is "An organizational unit assigned primary responsibility for review of operational phase activities shall re'i ort to a dssignated management representative who is assigned authonty and responsibility for effective functioning of the unit and who is not immediately responsible for the performance of the activities to be reviewed."
' Paragraph 4.8.9 currently requires the SRC to report to and advise the Vice President, Operations on areas of rssponsibility.
By implementing this change Waterford 3 is providing a more conservative approach towards compliance to Regulatory Guide 1.33,
- 2. If item 1 above is YES, does the proposed change include the basis to conclude that the revised program incorporating the Yes C No E N/A change continues to meet the criteria of 10CFR50 Appendix 0 and other previous? accepted FSAR commitments?
Explain:
Reviewed By:
x%fe[$sU QA Re(dresentative
%M'l Date 4
QAP-018 R6.0 Attachment 7.1 R-TYPE. J311 o
s M 1_ MN* 1 RECOMMENDATION: 0 Does not represent a lessening of commitment and it can be implemented immediately.
Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation.
Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the ch,ange should not be processad.
/
6\lL 1
ch<lw%
9 Recommended By: QA Supervisor Date DISPOSITION:
Approved for implementation Disapproved Approved for sub I to the NRC for acceptance 0#
UL% ctb $!\1 9 (,
Approved By: QA Mariager / Date l
QAP-018 R6.0 Attachment 7,1 R-TYPE: J311
~
' CHANGE Address the composition of the SRC. Para. 4.2.2 which currently shows the Vice President, Operations as the SRC Chairman will be changcd to read: "The Vice President, Operations is rssponsible for appointing the Chairman of the Safety Review Committee (SRC). The Vice President, Operations is also responsible for oversight of the SRC."
BASIS FOR NO REDUCTION OF COMMITMENT This change does not represent a lessening of commitment as currently justified in the following paragraphs of Chapter 1, Rev.10.
Paragraph 4.8.1 requires the SRC to provide an independent review. The guidance in ANSI N18.7, Paragraph 4.3.3 is "An organizational unit assigned primary responsibility for review of operational phase activities shall report to a designated management representative who is ,
assigned authority and responsibility for effective functioning of the unit and who is not immediately responsible for the performance of the activities to be reviewed."
Peragraph 4.8.9 currently requires the SRC to report to and advise the Vice President, Operations on areas of responsibility.
By implementing this change Waterford 3 is providing a more conse:vative approach towards l compliance to Regulatory Guide 1.33.
QAPM SEC 'lONS AFFECTED BY THIS CHANGE Chapter 1 Rev.10 4.2.2
WATERFORD 3 CHAPTER 1 REV.10.0 p)Entsigy
( QUALITY ASSURANCE R TYPE: C1.31
~ Operations PROGRAM MANUA'. PAGE 2 OF 15 4.1.3 Entergy Operations Management is responsible for ensuring that implementing procedures within their department adequately implement Waterford 3 commitments 1Q and obligations.
4.2 VICE PRESIDENT, OPERATIONS 4.2.1 The Vice President, Opert lons is responsibio for assuring the develor'ient and approval of Waterford 3 quality policies. Reporting to him are the:
- a. General Manager, Plant Operations;
- b. Director, Plant Modification and Construction;
- c. Director, Site Support; $
- d. Director, Nuclear Safety;
- e. Training Manager; and
- f. Safety Review Committee.
4.2.2 The Vice President, Operations is responsible for acting as the chairman of the Safety Review Committee (SRC) and appointing the vice chairman and other members of the SRO. He also appoints SRC attemetes and subcommittee chairmen and members.
4.2.3 The Vice President, Operations reviews trend reports, status summaries, and the results of management assessments to evaluate the effectiveness of the Waterford 3 Qeality Assurr. ice program. In addition, the Vice President, Operations or his designee, endorses the Waterford 3 Management Manual, and revisions thereto, whics) contain policies and directives applicable to Waterford 3.
4.3 GENERAL MANAGER, PLANT OPERATIONS 4.3.1 The Waterford 3 plant operations organization (hereinafter referred to as the Plant Operations Staff) is headed by the General Manager, Plant Operations. The primary qua!ity related responsibilities of the General Manager, Plant Operatioris include:
- a. Providing and maintaining a trained and qualified staff to safely oporte and maintain the plant;
- b. Assuring the development and proper implementation of quality related procedures and instructions for activities such as plant operations, maintenance, repair, test, radiation protection, fits protection, and safety to e'isure plant and personnel safety;
- c. Addressing matters brought to his/her attention by the Plant Operations Review Committee (PORC), which is established to ensure on-site review and evaluation of plant operations, maintenance, and test programs. The PORC reports to the General Manager, Plant Operations and advises him/her on matters related to nuclear safety, including referral of topics requiring review and potential action by the SRC. PORC membership and responsibilities are in accordance with this manual. The PORC is also responC!e for the review of design changes and site nonconformance documents whiu1 have been dispositioned as 'use-as-is" or " repair.";
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S- Ent N WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.11.0 PROGRAM MANUAL PAGE: 2 OF 21 4.0 RESPONSIBILITIES 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsibility for the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations to ensure that an effective Quality Assurance program is maintained. ,
4.1.2 Entergy Operations management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality '
! Assurance program.
4.1.3 Entergy Operationr, Management is responsible for ensuring that implementing procedures within their department adequately implement Waterford 3 comrnitments and obligations.
4.2 VICE PRESIDENT, OPERAT!ONS 4.2.1 The Vice President, Operations is rr.sponsible for assuring the -
development and approval of Waterford 3 quality policies. Reporting to him are the:
a.- General Manager, Plant Operations; b.- Director, Plant Modification and Construction;
- c. Director, Site Support;
- d. Director, Nuclear Safetyy
- e. Trainina Manager; and f' Safety Review Committee.
4.2.2 The Vice President, Operations is responsible for appointing the 3 ,
Chairman of the Safety Review Committee (SRC). The Vice M President, Operations is also responsible for oversight of the SRC.
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE:
Revise the Quality Assurance Program Manual (QAPM), Chapter 1, Rev.10.0, to address the orgainizational changes regarding the transfer of responsibility for the secruity department from the GMPO to the Director, Site Support 10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment to the QA Program description previously accepted by the NRC?
O Yes @ No Explain:
The Waterford 3 Quality Assurance Program Manual, will be revised to address the change above by relocating rIsponsibilities (Secunty Department related) assigned to the GMPO (Chapter 1, Section 4.3.z,aa, and bb) to the Director, Site Support (Chapter 1, Section 4.5.1).
- All commitments are transferred intact from the GMPO to the Director, Site Support, thus, this change does not )
r:present a lessening of commitment.
- 2. If item 1 above is YES, does the proposed char,se include the basis to conclude that the revised progran, incorporating the C Yes No ** N/A change continues to meet the criteria of 10CFR50 Appendix B and other previously accepted FSAR commitments?
Explain:
Reviewed By:
t$ W l. -
&hb QA Re%sentative Date l RECOMMENDATION:
l Does not represent a lessening of commitment and it can be implemented immediately, Represents a lessening of commitment, however, the change has sufficient basis to demonstrate centinued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation.
Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the change should not be processed, f
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9 k h *1 L Recommended By: QA Supervisor Date DISPOSITION:
@ Approved for implementat!on Disapproved Approved for submittal to the NRC for acceptance Approved By:
cxfe a mh QA Manker f 9/< '
7/74 Date QAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11
_A
CHANGE
~ Shift responsibility for the Security Department from the General Manager Plant Operations to the Director, Site Support.
BASIS FOR NO REDUCTION OF COMMITMENT The Quality Assurance Program Manual was r6 vised to address the change by relocating responsibilities (Security Department related) from the General Manager Plant Operations (Sections 4.3.1.z, aa, & bb) to the Director, Site Support (Section 4.5.1). All commitments were transferred intact, thus, this change does not represent a lessening of commitment.
QAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Rev.10 4.3.1. z 4.3.1.aa 4.3.1 hb l
Q
(~/ Enters';
WATERFORD 3 QUALITV ASSURANCE CHAPTER 1 REV.10.0 R TYPE: 01.31 Operations PROGRAM MANUAL PAGE 4 OF 15
- x. Performing a quality review of all maintenance initiated work authorizations not containing a hold point, not involving special pro esses, or not classified as safety related, to e 1sure the inclusion of quality requirements;
- y. Tracking controlled maintenance activities related to installed plant hardware to closure;
- z. Implementing the Security Plan and Safeguards Contingency Plan; aa. Contrelling plant area access; bb. Implementing the Fitness For Duty program, including;
- 1. Reviewing and interpreting presumptive positive test results obtained through the Fitness For Duty program.
cc. Directing the management of the Hazardous Waste / Hazardous Mutottal programs; dd. Acting as a liaison with regulatory agencies on technical issues involving the environr'1ent; I
ee. Developing and implementing Radiological and Non-Radiological l Environmental Monitoring programs; and I ff. Implemerf.ing the Entergy Ooeraticns, Inc. welding pmgram.
4.4 DIRECTOR, PLAHY MODIFICATION AND CONSTRUCTION 4.4.1 The primary quality related responsibilities of the Director, Plant Mcdification and Construction include:
e
- a. Coordinating plant design changes;
- b. Managing the plant modification process through the phases of design, implementation, testing, and acceptance;
- c. Coordinating the development and review of departmental procedures;
- d. Reviewing and processing assigned work authorizations and managing services for plant repair, modification, and construction which is under his jurisdiction;
- e. Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction work prior to acceptance; and
- g. Coordinating construction tasks involved with outages a'id retrofitting.
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WATERFORD 3 CHAPTER 1 REV.11.0
&{fN e QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 5 OF 21
- v. , Reviewing design changes and plant modifications from a radiological standpoint;
- w. Assembling Work Authorization Packages including support documentation such as procedures, drawings, etc.;
- x. Performing a quality review of all maintenance initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- y. Tracking controlled maintenance activities related to installed plant hardware to closure; 111
- z. Directing the management of the Hazardous Waste / Hazardous Material programs; aa. Acting as a liaison with regulatory agencies on technicalissues involving the environment; bb. Developing and implementing Radiological and Non-Radiological Environmental Monitoring programs; and cc. Implementing the Entergy Operations, Inc. welding program.
4.4 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION 4.4.1 The primary quality related responsibilities of the Director, Plant Modification and Construction include:
- a. Coordinating plant design changes;
- b. Managing the plant modification process through the phases of design, implementation, testing, and acceptance
- c. Coordinating the development and review of depa-tme*al
- procedures;
- d. Reviewing and processing assigned work authorizations and managing services for plant repair, modification, and construction which is under his jurisdiction;
g WATERFORD 3 CHAPTER 1 REV 11.0
- Entenu
~ ' c/ -
QUALITY ASSURANCE PROGRAM MANU AL R-TYPE: C1.31 PAGE: 6 OF 21
- e. ,
Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Erisuring proper completion of modification and construction work prior to acceptance; and
- g. Coordinating construction tasks involved with outages and ,
retrofitting.
l 4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- e. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and performance of practice drills; and
- c. Providing support for records management, including execution of ~
document control and records storage programs;
- d. Coordinating the development, preparation, and maintenance of Waterford 3 policies and directives.
- e. Implementing the Security Plan and Safeguards Contingency Plan;
- f. Controlling plant area access; 1_1
- g. Implementing the Fitness For Duty program, including;
- 1. Reviewing and interpreting presumptive positive test results obtained through the Fitness For Duty program.
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QUALITY ASSURANCE FROGRAM CHANCaE REVIEW FORM PROPOSED CHANGE: QAPM Chapter i Rev.10.0
- 1. para 4 3.1.d . changed to read ' Designating the Chairman of the Condition Review Board',
- 8. para 4 6.1 m . transfer responsibility from the Director, Nuclear Safety to the Director, Site Support (para 4 51.d)
- 3. para 4 6 2 d.14 transfer responsibdity from the OA Manager to the Director, Nuclear Safety (para 4 61.f) 1 4
- 4. para. 4 6 2.d 15 transfer responsibility from the QA Manager to the Director, Nuclear Safety and reword to read ' Oversight of the administration of the Condition Report process, root cause analysis and trend programs. (para 4 61 r)
Q para 4 6.1.1. change
- Quality Team (0 Team) to 'F,mployee Concerns Program * (para. 4 6.1.n)
- 6. para 413. change "Entergy Operations' to "Waterford 3' 10CFR60.54 REVIEW: '
- 1. Does the proposed change represent a reduction of commitment Yes '" No-to the QA Program description previously accepted by the NRC?
Explain: \
- 1. The General Manager. Plant Operations designates the chairman of the Condition Revew Board providing a high management level of attention to identified adverse conditions. This role was not desenbod in the previously accepted QA Program (Chapter 16) description.
3.
All commitments are transferred intact from the Director, Nuclear Safety to the Director, Site Support, thus, this chan e dogs not represe a lessening of commitment (Ccs%[dQ (b4.1=pJ $g1.wAm , ( Jw .hr+-n f A 3 [MA.4 j e <
314. The administration of the Condition Report prbcess, root cause analysis prbcess and trend program have been transferred from QA to the In-House Events Analysis group still reporting to the Nuclear Safety Director. There is no reduction of analysis efforts or level of Independence because of this organizational change.
- 9. This is a program name change only. All commitments still remain with the Director. Nuclear Safety, ttis, there is no lessening of commitment.
- 6. Changed to allow all Waterford 3 personnel to identify adverse conditions. This is not a lessening of commitment.
- 2. If item 1 abovs is YES, does the proposed change include the basis to conclude that the revised program incorporating the O Yes No ** NIA change continues to meet the criteria of 10CFR50 Appendix B and other previously accepted FSAR commitments?
Explain:
/
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Reviewed By: QA Replosentative Date RECOMMENDATION:
l k8 l Does not represent a lessening of commitinent and it can be ifrplemented immediately.
Represents a lessening of commitment, however, the change has cufficient basis to O demonstra*e continued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation.
Represwnts a lessening of commitment with insufficient basis to determine continued
- g _ compilance. There .
, the change should not be processed.
, .W Recommended By[ QA Supervisor Date DISPOSITION:
- - Approved forimplementation Dicapproved Approvad for sub ittal to the NRC for acceptance
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/ zt/7t Approved By: QA Martager Date OAP-01C R6.0 Attachment 7.1 R-TYPE: J311 i
QUALITY ASSURANCE PROGRAM 1 CHANGE REVIEW FORM PROPOSED CHANGE: OAPM Chapter 16 Rev,5.0 (Revision 1)
< 1, para. A 1.1 a . add "Designatirg the Chairman of the Condition Review Board".
- 2. delete para 4 41.b. c & d and add para 4 5. *The In-House Events Analysis Supervisor is responsible for -
a, Administenng the Condition Report Process; e
- b. A1ministenng a root cause investgation and trend ana ysis program for correctrve acten documents and for pubhshing a wntten or electronic trend report.
- 3. add para 4 2.1.c ' Oversight of the administration of the Condition Report process, toot cause analysis and trend programs.
4 para. 4.2.1 a . change ' Performing' to Assunng the performance of ..'
' 9 delete para. 5 2 in its entroty.
p 6 para 4 8 - change "Entergy Operations
- to "Waterford 3' 10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes ** No to the QA Program description previously accepted by the NRC?
Explain:
1.
The Gere:a; tAanager, Plant Operations designates the chairman of the Condition Review Board providing a high management level of attsntion to identifiad adverse conditions. This role was not desenbod in the provously accepted QA Procram (Chapter 16) desenption.
813. The administration of the Conditon Report process, root cause analysis process and trend program have tmr transferred from QA to the in House Events Analysis group still reporting to the Nuclear Safety Director. See added 4.2.1.c and 4 5. ~1here will be no reduction of analysis efforts oc level of independence.
4.
This change clanfies the roirt of the Director, Nuclear Safety to indicate the responsibility for performance of res,ortabiltty reviews.
G.
The deleted section (5.2) is redundtnt to information provided in secten 5.1. The oversight of the correctrve action program is maintained by the Condition Review Board, the Safety Review Committee and Quality Assurance.
- 6. Changed to allow all Waterford 3 personnel to identify adverse conditions. This is not a lessening of commetment
- 2. If item 1 above is YES, does the proposed change include the basis to conclude that the revised program incotporating the Q Yes .No ** N/A change continues to meet the criteria of 1(,CFR50 Appendix B and other previously accepted FSAR commitments? .. .
I Explain:{fffr 7)sg .7fVpra unibt?y1 CN WW&f f ygd>lkn'eiTQ r AJ ~ Awf]IYLh.Y3 tWl'CU*A YUO 'Y N E
- Reviewed By:
/lL4N QA Repfosentative b 9lf7b b Date RECOMMENDATION:
El Does not represent a lessening of commitment and it can be implemented immediately.
- Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix P and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance p.h ' to implementation.
g Represents a lessening of commitment with Insufficient basis to determino continued compliance. Therefore, the change should not be processed. 1 ? 9L Recor mended By: QA Suhrvisor # II # Date DISPOSITION:
** Approved for implementation Disapproved Approved for s bmittal to the NRC for acceptance
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I WM Ch Y2Cf9 d Approved By: QA Mhagerf l ate D OAP-018 RS.O - Attachment 7,1 R-TYPE: J3.11
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE: OAPM Chapter 16 Rev. 5.0
- 1. para 4.1.1 a add "Chainng the Cundrtion Revow Board *.
- 3. delete para 4 41 b, c & d and add para 4 5 "The in-House Events Analysis Supervisor is responsible for. ]
- s. Administenng the Condition Report Process; I
- b. Administenng a root cause investigation and trend analyus program for corrective action documents and for pubimhing a written 1 or electronic trend report.
l 3 Odd para 4 2.1 c ' Oversight of the administration of the Condition Report process., root cause analysis and trend programs. l 4 para. 4 2.1.a change " Performing
- to Assunng the performance of..,*
- 5. delete para 5 2 in its entirety.
10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes W No
, to the QA Program description previously accepted by the NRC? i Explain:
- i. The General Manager, Plant Operations is chainng the Condition Revow Board providing a high management level of attention to identified adverse conditions. This role was not desenbod in the previously accepted QA Program (Chapter 16) descnption.
' 313. The administration of the Condition Report process, root cause analysis process and trend program have been transferred from QA to the in House Events Anstysis grnup still reporting to the Nuchar Safety Director. See added 4 2.1.c and 4 5. There will be no reduction of anaiysis j efforts or level of independence. ! 4. This change clanfies the role of the Director, N,citar Safety to indicate the responsibihty for performance of reportabihty revows.
- 5. The deleted s6ction (5 2) is redundant to information provided in section 5.1. The oversight of the corrective action program is maintained by 3^
the Condition Review Board, the Safety Revow Committee and Quality Assurance.
- 2. If item 1 above is YES, does the proposed change include the basis to conclude that the revised program incorporating the Yes No E N/A
! change continues to meet the criteria of 10CFR50 Appendix B 1 and other previously accepted FSAR commitments? Explain:
.t Y% h(,
, Reviewed By: QA Rogesentative Date . RECOMMENDATION: Does not represent a lessening of comrt'itment and it can be implemented immediately. Represents a lessening of commitmont, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, e it should be submitted to the NRC for acceptance prior to implementation. g Represents a lessening of commitment with insufficient basis to determine continued compilance. Therefore, the change should not be processed. l Recommended By: QA Supervisor
' Ev6 # '
Tc/u Date l-DISPOSITION:
** Approved for implementation Disapproved 1
- Approve orsub al to the NRC for acceptance L.
4 W 6 v-(~u a 6b/74 6 I Approved By: Date QA Manqger j OAP-018 R6.0 Attachment 7.1 R TYPE: J3.11 i k
$Viairperson o f thMVevisedry Chaptor 16 add B
ASIS edethisCondition s Reviesponsibility of FOR NO ection. GeneralMa ar na T REDU ewBo d(CRB)gerPlantO his provide was CTIONOF o s cr COM to design a ting thperations,in fr not des ibedin tha high m n trepres anagem c om MITMENT e hairma nfacting as OAPM enta lessening ofepreviou e entlev lof attenti s lyacc o the CRB. SECTIONS comm itmen t.eptedon toiden Rev.ptC_ ha !!L1 AFFECTED QA Program (tifiedadv 10 BY erse 4.3.1.d C_ha THIS CH Chapter conditio 16)de Rev.ptgL16 5 ANGE scription. TFns.role This 4.1.1.a 4does
/'
CHANGE Chapter 1 revised responsib!!ity of General Manager Plant Operations, in, from acting as Chairperson of the Condition Review Board (CRB) to designating the chairman of the CRB. Chapter 16 added this section. BASIS FOR NO REDUCTION OF COMMITMENT This provides a high management level of a" ..ition to identified adverse conditions. This role was not described in the previously accepted QA Program (Chapter 16) description. This does not represent a lessening of commitment. CAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 16 Rev.10 Rev.5 4.3.1.d 4.1.1.a
WATERFORD 3 CHAPTER 1 REV.10.0 p/Entergy t QUALITY ASSURANCE R TYPE: C1.31 Operations PROGRAM MANUAL PAGE 3 OF 15
- d. Acting as Chairperson of the Condition Review Board (CRB);
- e. Analyzing conditions, for trends regarding equipment failure, and publishing a quarterly trend report;
- f. Approving design changes prior to implementation;
- g. Developing and maintaining quality related operations and maintenance procedures;
- h. Implementing Tect.nical Specification controls and surveillances;
- i. !dentifying and performing required corrective and preventive maintonance;
)
J. Implementing a measuring and test equipment calibration program; i Providing engineering 4echnical support for primary / secondary chemistry,
~
k. l environmental monitoring, radiation prtt.ection, water treatment, and process 5 controls;
- l. Initiating, prioritizing, and performing acceptance testing of plant modification activities;
- m. Reactor engineering and special nudear material control and accountability controls;
- n. Coordinating the Fire Protection program;
- o. Housekeeping inside the Radiation Controlled Areas;
- p. On site handling, storage, packaging, and shipping of radioactive wastes;
- q. Providing technical expertise to assist in the on-site handing, storage, packaging, desning, and release for shipping to a transit carrier of radioactive material;
- r. Developing and controlling the ALARA program;
- s. Developing and controlling the Radiation Protection program, induding Radiological Effluent Monitoring program;
- t. Managing or implementing the in-service Testing, Local Leak Rate Testing, and the Hydrostatic Testing programs;
- u. Acting as a liaison with regulatory agencies on technical issues involving plant chemistry;
- v. Reviewing design changes and plant modifications frorr a radiological standpoint;
- w. Assembling Work Authorization Packages induding support documentation such as procedures, drawings, etc.;
I o _________i
t-i O WATERFORD 3 UAL;TY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.11.0
- ENt N PROGRAM MANUAL PAGE: 3 OF 21 I 4.2.3 The Vice President, Operations reviews trend reports, status summaries,
, and the results of management assessments to evaluate the
, effectiveness of the Waterford 3 Quality Assurance program. In addition,
- . the Vice President, Operations or his designee, endorses the Waterford 3 l Msnagement Manual, and revisions thereto, which contain policies and
- directives applicable to Waterford 3.
4.3 GENEPAL MANAGER, PLANT OPERATIONS , 4.3.1 Ns Waterford 3 plant operations organization (hereinafter referred to as
'he
. Plant Operations Staff) is headed by the General Manager, Plant Operatior.J. The primary quality related responsibilities of the General Manager, Plant Operations include:
- a. Pioviding and maintaining a trained and qualified staff to safely !
operate'and maintain the plant;
- b. Assuring the development and proper implementation of quality related procedures and instructions for activities such as plant operations, maintenance, repair, test, radiation protection, fire ,
protection, and safety to ensure plant and personnel safety;
- c. Addressing matters brought to his/her attention by the Plant Operations Review Committee (PORC), which is established to ensure on site review and evaluation of plant operations, maintenanc6, and test programs. ?he FORC reports to the General Manager, Plant Operationu and advises him/her on matters related to nuclear safet/, including ,cferral of topics requiring review and potential action by the SRC. PORC membership and responsibilities are in accordance with this manual. The PORC is also responsible for the review of design changes and site nonconformance documents which have been dispositioned as use-as is" or " repair,":
- d. Designating the Chairman of the Condition Review 11 ,
Board (CRB);
- e. Analyzing conditions for trtuds - arding equipment failure, and ,
publishing a quarterly trend rer
- f. Approving design changes pr r tg implementation;
. - - - . . . - ,- ,.w . ~ . , . - ,,,w -. v..-, , ,- .~ ..,--,-m.,n , . . . ,n . .-
/
WATERFORD 3 gEntergy QUALITY ASSURANCE CHAPTER 16 REV 50 _ Operations R-TYPE: C1.31
. PROGRAM MANUAL p39, 3 of 3 TITLE: C9ftRECTIVE_ ACTION EFFECTIVE DATE: 01/16/95 1
PREPARED B l hi DIRECTOR, NUCLEAR SAFETY: M QA MANAGER: N VICEPRESIDENT, OPERATIONS.keh bh o, 1.0 PURPOSE The Corrective Action Program assures that adverse conditions are promptly identified and corrected.
2.0 REFERENCES
2.1 10CFR50, Appendix B, Criterion XVI, ' Corrective Action' 2.2 _ USNRC Regulatory ;ulde 1.33 Revision 2, February 1978 (wnich endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants.") 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, ."LANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible for:
- a. Analyzing conditions for trends regarding equipment failure, and publishing a quarterly trend report i
- b. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
g- Ent WATERFORD 3 CHAPTER 16 REV. 6.0 QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 1 OF 5 TITLE: C.QBRECTIVE ACTION EFFECTIVE DATE: 10/16/96 1 PREPARED B /; w E DIRECTOR, NUCLEAR SAFETY: bh OA MANAGER: d+dt ' VICE PRESIDENT, OPERATIONS [ , : 1.0 PURPOSE The Coirective Action Program assures that adverse conditions are prore ptly identified and corrected. 2.0 rtEFERENCES 2.1 10CFR50, Appendix B, Criterion XVI," Corrective Action" 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants.") 3,0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible for:
- a. Designating the chairman of the Condition Review Board Ql
- b. Analyzing conditions for trends regarding equipment failure, and -
publishing a quarterly trend report; 9
CHANGE Transferred responsibility for coordinating the development, preparation, and maintenance of Waterford 3 policies and directives from the Director, Nuclear Safety (deleted sect. 4.6.1.m) to the Director, Site Support (added sect. 4.5.1.d). BASIS FOR NO REDUCTION OF COMMITMENT All commitments were transferred intact from the Director, Nuclear Safety to the Director, Site Support, thus, this change does not represent a lessening of commitment. QAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Rev.10 4.6.1.m 4.5.1.d i
WATERFORD 3 CHAPTER 1 REV.10.0 eEntergy QUALITY ASSURANCE R TYPE: C1.31
~ Operatioris PROGRAM MANUAL PAGE 6 OF 15
- j. Malntaining SRC charters;
- k. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification requirements;
- l. , Overseeing the activiiles of the Quality Team (Q Team); end
~
- m. Coordinating the development, preparation, and maintenance of Waterford 3 ,
policies and directives. 4.6.2 The Director, Nuclear Safety is also responsible for the direction and administratior' of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance program. The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, reco nmend or provide solutions through designated channels; and
- 3. Vertfy implementation of solutions.
- b. This organizational freedom includes sufficient independence
,from cost and schedula when opposed to safety considerations;
- c. The Quality Assurance Manager has the authortty to stop unsatisfactory work and/or control further processing, delivery, or installation of nonconforming material through designated channels;
- d. The primary quality related responsibilities of the Quality Assurance Manager include:
- 1. Planning, organizing, and administering the Quality Assurance program;
- 2. Developing, reviewing, and concurring with the content of the Waterford 3 Quality Assurance Program Manual and changes thereto; 1Q
- 3. Developing and maintaining Quality Assurance Procedures (QAPs);
- 4. Assisting in establishing that portion of the Training program that addresses quality assurance;
- 5. Advising, reviewing, and concurring on the scope and content of quality assurance training and indoctrination programs for personnel performing quality related activities;
- g. , ~. - w
- I ffp WATERFORD 3 CHAP"ER1 REV.10.0
- ) \{MD,atergy QUALITY ASSLRANCE R TYPE: C1.31 Operations PAGE 5 OF 15 l ! PROGRAM MANUAL 4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and
, implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and performar.ce of practice dtills; and
- c. Providing support for records management, including execution of document control and records storage programs; 4.6 DIRECTOR, NUCLEAR SAFETY 4.6.1 The primary quality related responsibilities of the Director, Nuclear Safety include:
- a. Coordinating and reviewlag responses to Nuclear Regulatory Commission
- matters, as assigned; b, Managing the preparation of updates / revisions to the Final Safety Analysis 2 Report and the Technical Specifications;
- c. Managing the Waterford 3 Commitments Management System;
- d. Managing the preparation of responses to IE bulletins, NRC orders, inspection reports, generic letters, Information noticos, and Notices of Violation; ;
C.b ' '
- e. Reviewing corrective adlon documents for determination of reportability;
- f. Interfacing with on-site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors to ensure quality is maintained;
- g. Reviewing plant system problems and performance coccoms;
- h. Reviewing operating abnormalities and Licensee Event Reports;
- i. Examining plant operating characteristics, NRC lasuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as part of the independent Technical Review function. The independent Technical Review functions include responsibility for:
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance adivities, operations activities, or other means of improving plant safety;
- 2. Maintaining surveillance of plant activities to provide itependent verification that these adivities are performed correctly and that human errors are reduced as much as practical; .
g WATERFORD 3 CHAPTER 1 REV.11.0
= Ente 6 QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 8 OF 21
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical;
- l. Maintaining SRC charters;
- m. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification requirements;
- n. Overseeing the activities of the Employee Concerns Program 1-1 4.6.2 The Director, Nuclear Safety is also responsible for the direction and administration of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance progran:,
The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, recommend or provide solutions through designated channels; and
- 3. Verify implementation of solutions.
- b. This organizational freedom includes sufficient independence ,
from cost and schedule when opposed to safety considerations; e
S -E N WATERFORD 3 QUALITY AhSURANCE CHAPTER 1 R TYPE: C1,31 REV,11,0 PROGRAM MANUAL PAGE: 6 OF 21
- e. , ,
Performing a quality review of all construction :.1itiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction wark prior to acceptance; and
- g. Coordinating construction tasks involved with outages and retrofitting.
4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and performance of practice drills; and
- c. Providing support for records management, including execution of document control and records storage programs;
- d. Coordinating the development, preparation, and maintenance of Waterford 3 policies and directives.
- e. Implementing the Security Plan and Safeguards Contingency Plan;
- f. Controlling plant area access; 11
- g. Implementing the Fitness For Duty program, including;
- 1. Reviewing and interpreting presumptive positive test results obtained through the Fitness For Duty program.
em
+
9 A
CHANGE Chapter 1 transferred responsibility for #1.( 4.6.2.d.14) analyzing conditions for human performance trends and publishing quarterly trend reports and #2 (4.6.2.d.15) administering a root cause investigation and trend analysis program for identified adverse conditions from the Quality Assurance (QA) Manager to the Director, Nuclear Safety. Also reworded #2 to read:
" Oversight of the administration of the Condition Report Process, root cause analysis and trend programs."
Chapter 16 added (reworded) #2 (4.2.1.c). BASIS FOR NO REDUCTION OF COMMITMENT The oversight of the Condition Report process, root cause analysis prucess and trend program has been transferred from QA to the Director, Nuclear Safety. There is no reduction of analysis cfforts or level of independence because of this organizational change. i QAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 16 Rev.10 Rev.5 4.6.2.d.14 4.2.1.c 4.6.2.d.15 l
1 (qJEntergy WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 REV.10.0 R. TYPE: C1.31
" Operations PROGRAM MANUAL PAGE 7 0F 15
- 6. Providing requested inspection training to personnel performing quality related activities;
- 7. Certifying Lead Auditors and inspectors;
- 8. Assuririg effective implementation of the Quality Assurance program l through a comprehensive system of reviews, assessments, and the l performance or monitoring of nondestructive examinations and other special processes;
- g. Ensuring that quality reviews are conducted for quality related implementing procedures and design changes, including drawings and specifications, to ensure ti:s inclusion of quality requirements;
- 10. Reviewing all safety related work authorizations (WAs), WAs contain!ng hold points, or WAs involving special processes, to ensure the inclusion of quality requirements, and ensuring that quality reviews are conducted for all other initiated work authonzations;
- 11. Reviewing nonconformance work authorization packages:
- 12. Assuring that the corrective adion processes under his/her jurisdiction are implemented according to approved procedures;
- 13. Conduding reviews, assessments and monitoring of the vrarious corrective action processes to ensure that the required pr0 gram aspects are adequately addressed;
*14. Analyzing conditions for human performance trends ard publishing quarter 1y trend reports;
.. v,15. Administering a root cause investigation and trend analysis program for identified adverse conditions;
- 16. Conduding an ongoing assessment of the radiation protection and radwaste programs;
- 17. Establishing and maintaining documentation of Quality Assurance activities; and
- 18. Providing status information regarding the Quality Assurance program to the Director, Nuclear Safety ar,d the Vice President, Operations;
- e. The qualifications of the Quality Assurance Mr. nager include as a minimum:
1, Graduate of a college or university with a Bachelor's degree in an engineering, science or related field, or equivalent capabliities;
- 2. A minimum of four years experience in quellty assurance or a quality assurance related activity with at least two of those years in the nuclear power industry as a manager or supervisor,
- 3. Experience in development and implementation of quality assurance programs, plans, and procedures;
WATERFORD 3 CHAPTER 1 REV.11.0 gfN QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1,31 PAGE: 10 OF 21 1
- 10. Reviewing all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensure the inclusion of quality requirements, and ensuring that quality reviews are conducted for all other initiated work authorizations:
- 11. Reviewing nonconformance work authorization packages;
- 12. Assuring that the corrective action processes (results of audits, assessments) under his/her jurisdiction are implemented according to approved procedures;
- 13. Conducting reviews, assessments and monitoring of the various corrective action processes to ensure that the required program aspects are adequately addressed;
- 14. Conducting an ongoing assessment of the radiation ul protection and radwaste programs;
- 15. Establishing and maintaining documentation of Quality Assurance activities; and
- 16. Providing status information regarding the Quality Assurance program to the Director, Nuclear Safety and the Vice President, Operations;
- e. The qualifications of the Quality Assurance Manager include as a minimum:
i
- 1. Graduate of a college or university with a Bachelor's degree
; in an engineering, science or related field, or equivalent capabilities;
't
< 2. A minimum of four years experience in quality assurance or a quality assurance related activity with at least two of those years in the nuclear power industry as a manager or supervisor;
, 3. Experience in development and implementation of quality assurance programs, plans, and procedures;
-e . - - - - - . - .- . . _ - ,,._,n - - - -
WATERFORD 3 CHAPTER 1 REV.11,0 j g=Ent QUALITY AShuRANCE R. TYPE: C1,31 PROGRAM MANUAL PAGE: 7 OF 21 4.6 DIRECTOR, NUCLEAR SAFETY 4.0.1 The primary quality related responsibilites of the Director, Nuclear Safety include:
- a. Coordinating and reviewing responses to Nuclear Regulatory Commission matters, as assigned;
- b. Managing the preparation of updates / revisions tt, the Final Safety Analysis Report and the Technical Specifications;
- c. Managing the Waterford 3 Commitments Management System; i
d, Managing the preparation of responses to IE bulletins, NRC orders, inspection reports, generic letters, information notices, and Notices of Violation;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs; M
f, Analyzing conditions for human performance trends and publishing quarterly trend repc;ts;
- g. Reviewing corrective action documents for determination of reportability;
- h. Interfacing with on site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors to ensure quality is maintained;
- i. Reviewing plant system problems and performance concerns; J. Reviewing operating abnormalities and Licensee Event Reports;
- k. Examining plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety
- as part of the Independent Technical Review function. The
- Independent Technical Review functions include responsibility for:
9 WATERFORD 3 OEntergy QUALITY ASSURANCE CHAPTER 16 REY. 5.0 1 Operations R-TYPE: C1.31 PROGRAM MANUAL Page 2 of 5 i
- c. Perfoming reportability doterminations and making ,.
appropriate notifications in accordance with 40CFR for identified environmentel adverse conditions. 4.2 DIRECTOR, NUCLEAR SAFETY i 4.2.1 The Director, Nuclear Safety is responsible for:
/ a. Performing reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and I /b. Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adeountely implemented.
4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible for: j a. Assuring _that procedures are developed and maintained to implement the Corrective Action Program;
/ b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; j J c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for:
/ a. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation;
/ b. Administering the Condition Report process;
g WATERFORD 3 CHAPTER 16 REV. 6.0 Ent QUALITY ASSURANCE R-TYPE: C1.31 l PROGRAM MANUAL PAGE: 2 0F 5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
~, 4.2 DIRECTOR, NUCLEAR SAFETY I 4.2.1 The Director, Nuclear Safety is responsible for: ) a. Assuring the performance of reportability reviews of Condition gl Reports (CRs) in accordance with 10CFR50.73 and 10CFR21;
- b. Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented; and
! c, Oversight of the administration of the Condition Report process, g root cause analysis and trend programs. 4.3 DIRECTORS AND MANAGERS i 4.3.1 Directors and Managers are responsible for,
- a. Assuring that procedures are developed and maintained to implement the Corrective Act% Program; j b. Assuring that personnel are infaillar with the requirements of the Corrective Action Program;
- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for: , ~ a: Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; e 9 - - - - - - -
, - . - , - - , , - , , , - ,- ,, , - , - y- --, , ,,, . , , ,- -----,,----,--w - , , - - - , ,
- 4 .-
i '- C"HANGE 1
- Changed
- Quality Team (Q Team)" to ' Employee Concerns Program"
. BASIS FOR NO REDUCTION OF COMMITMENT
, This is a program name change only. All commitments still remain with the Director, Nuclear Safety, thus, there is no lessening of commitment. I j QAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 ~ } Rev.10 l 4.6.i .1 h ! i a 1 i h 1 i i ! i 5= ; i 4' I l f s I i i i i I i. i l:
._r., , - - - , , ,--w--n-- w m--m ~m v- v" W-
WATERPORD 3 cHAPTami Entergy QUALITV ASSWIANCg R Type: c1.Si 6 v.1o.D PAGE 6 QF 15 Opera h s PROWIAM MANUAL I J. Mairdaining SRC charters; l
- k. Performing independent twiews, safety examinations, and other twiew l
edivnies in support of the SRC and Technical Specifloation requirements: i
- l. Overseeing the activniss of the Quality Team (Q Team); and i l-
- m. Coonlinating the development, preparation, and maintenance of Waterford 3 y 1 policies and directives.
4 l 4.6.2 The Director, Nuclear Safety is sino responsilde for the direction and administration of i the Quality Assurance Mana0er and staff, who have the following responsibilities and ! authortt6es: 4
- a. The Quality Assurance Mana0er has the authority and responeitWilty for ,
j developing, coonlinating, and vertfying implementation of the Waterford 3 ) Quality Assurance proprem. The Quality Aneurance Manager mairtains an i overv6ew of Waterfoni 3 quality reisted activnies through reviews, audits, survoinerus, and inspections. Quauty Aneurance personnel have sufficient authortty and .rp M freedom to offectivdy:
- 1. Identify quaNty pmblems; ,
i
- 2. Inlitete, recommend or provide so;utions through desi0nated channois;
,' and. ,
- 3. Vertfy implementation of solutions.
, b. This organizational freedom includes sufflaient independence l /mm cost and schedule when opposed to safety considerations; l
- c. The Quality Assurance Manager has the authortty to stop unsatisfadory work j and/or contml further processing, delivery, or installation of nonconforming
- material thmugh designated channels; i d. The primary quality related responsibilities of the Quality Assurance Manager include
- 1. Planning, organizin0, and administerin0 the Quality Assurance program; i
- 2. Developing, reviewing, and concurdne with the content of the Waterford 3 Quality Assurance Program Manuel and chan0es thereto; 10 l
l 3. Developing and maintaining Quality Assurance Procedures (QAPs);
- 4. Assisting in estatdishing that portion of the Training program that 5 addresses quality assurance;
- 5. Advising, reviewing, and concurring on the scope and content of quality assurance training and Indoctrination programs for personnel performing quality related activMies; l
-. __ .___ _ _ _ - - . .- ._- . - - _ . - - - - - . - .- - - ~
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R. TYPE: C1.31 REV.11,0 i PROGRAM MANUAL PAGE: 8 OF 21
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety; 2, Maintaining survelflance of plant activities to provide independent verification that these activities are performed correctly and that hurnan errors are reduced as much as practical;
- l. Maintaining SRC charters;
- m. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification requirements;
- n. Overseeing the activities of the Employee Concerns Program.
11 4.6.2 The Director, Nuclear Safety is also responsible for the direction and administration of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying irnplementation of the Waterford 3 Quality Assurance program.
The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, recommend or provide solutions through designated channels; and
- 3. Verify implementation of solutions.
- b. This organizational freedom includes sufficient independence ,
from cost and schedule when opposed to safety considerations; s
CHANGE 1 Changed *Entergy Operations" personnel to "Waterford 3" personnel. l BASIS FOR NO REDUCTION OF COMMITMENT This change allows all Waterford 3 personnel to identify adverse conditions. This is not a j lessening of commitment. ' OAPM SECTIONS AFFECTED BY THIS CHANGE ! Chapter 1 Chapter 16 , Rev.10 Rev. 5.0 ) 4.13 4.7 ' l
? , - , ..4-~,- -.,...~y v.y.m---,,.-.,_.. ._.y< m. , , , . , , . y..,_,,,,.,_. __m-yy,_,.,r,,,, . , _ . ~ . . . , , , , , . , 4 m, ,, . - - . ,_4 , , . . . , _,,---w,,~r .-
4
)/Entergy WATERFORD 3 QUAUTY ASSURANCE CHAPTER 1 REV.10.0 R TYPE: C1.31
" Operations PROGRAM MANUAL PAGE 15 OF 15 4.13 ENTERGY OPERAT6ONS PERSONNEL Entergy Operations personnel are responsible for adherence to the requirements delineated !n this OA Program Manual and its implementing procedures. Entergy Operations personnel are also responsible for identifying sn:l reporting conditions adverse to quality and for identifying program or procedural enhancements.
4.14 SUPPLIERS / CONTRACTORS Suppliers / contractors of quality related material, equipment, spare parts, and/or services shall be required, as appropriate, by procurement documents to have a quality program. In such cases, a line of communication shall exist between the supplier / contractor and the Waterford 3 or Headquarters Quality Assurance organization. The overall responsibility for quality at Waterford 3 remains with Entergy Operations at all times. 8.0 DETAILS 5.1 ORGANIZATIONS PERFORMING QUALITY ASSURANCE FUNCTIONS Attachment I shows the lines of authority for the major Entergy Operations organizations that perform Quality Assurance functions at Waterford 3. 6.0 ATTACHMENTS Attachment i . Waterford 3 Orgentzstion Chart, a \ W
[' g WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.11.0
. . EntN l
PROGRAM MANUAL PAGE: 20 OF 21 l . 6. Purchasing and receipt of equipment, parts, materials, and
, supplies in support of Waterford 3 operations and station :
modifications;
- 7. Administering a receipt inspection program to assure acceptability of quelity related materials, parts, and t
components;
- 8. Coordinating the processing and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, including maintenance and design changes; 9 Establishing quality assurance and technical requirements in quality related procurement documents:
- 10. Maintaining storage conditions necessary to sustain material
- quality; and
- 11. Processing and securing material traceability data to support historical reference.
4,13 WATERFORD 3 PERSONNEL Waterford 3 personnel are responsibla for adherence to the requirements 11 delineated in this OA Program Manual and its implementing procedures. Waterford 3 personnel are also responsible for identifying and reporting ' conditions adverse to quality and for identifying program or procedural , enhancuments. 4.14 SUPPLIERS / CONTRACTORS Suppliers / contractors of quality related material, equipment, spare parts, and/or services shall be required, as appropriate, by procurement documents to have a quality program, in such cases, a line of communication shall exist botween the supplier / contractor and the Waterford 3 or Headquarters Quality Assurance organization. The overall responsibility for quality at Waterford 3 remains with Entergy Operations at all times. , e
o g WATERPORD 3 m/Entoeg Operat e QUAUTY ASSURANCE g[p[ I' 3'33 RW , 5.0 ( PROGRAM MANUAL Page 3 of 5
/c. Reviewing Cofidition Reports to determine if the identified condition (s) represent a significant adverse condition;..and
[d. Administering a root cause investigatun and trend analysis program for corrective action documents, i and for issuing a periodic human performance trend report') u t.
- e. Issuing Stop Work Orders when conditions warrant.
/4.5 SAFETY REVIEW COMITTEE The Safety Review Cosmiittee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Action l
Program at Waterford 3. The SRC assessment shall include, at a minimum, the review of the trend reports and significant adverse conditions.
, 4.6 CONDITION REVIEW BOARD The CR8 is responsible for reviewing Controlled Maintenance Condition Identifications and Condition Reports to ensure adverse conditions receive the proper significance classification, priority, and dedication of resources.
/4.7 ENTERGY OPERATIONS PERSONNEt.
Entergy Operations personnel are responsible for promptly identifying and documenting adverse conditions on corrective action documents. Entergy Operations personnel are also responsible for recommending that an activity be stopped if the specific work is not being done in accordance with approved procedures, drawings, specifications, or regulatory requirements.. 5.0 DETAILS 5.1 PROCEDURAL REQUIREMENTS 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for: - p
- a. Deficiency identification and immediate action; ;
i
g WATERFORD 3 CHAPTER 16 REV. 6.0
- Entergy QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 3 OF 5
- b. Issuing Stop Work Orders when conditions warrant.
4.5 The In House Events Analysis Supervisor is responsible for 1
- a. Administering the Condition Report Process; and E
- b. Administering a root cause investigation and trend analysis program for corrective action documents and for publishing a written or electronic trend report, 4.6 SAFET( REVIEW COMMITTEE The Safety Review Committee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Acticn Program at Waterford
- 3. The SRC assessment shallinclude, at a minimum, the review of the trend reports and significant adverse conditions.
4,7 . CONDITION REVIEW BOARD The CRB is responsible for reviewing Controlled Maintenance Condition Identifications and Condition Reports to ensure adverse conditions receive the proper significance classification, priority, and dedication of resources. 4.8 WATERFORD 3 PERSONNEL i Waterford 3 personnel are responsible for promptly identifying and g documenting adverse conditions on corrective action documents. Waterford 3 personnel are also responsible for recommending that an activity be stopped if the specific work is not being done in accordance with approved procedures, drawings, specifications, or regulatory requirements. 5.0 DETAILS 5.1 PROCEDURAL REQUIREMENTS 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for: ,
- a. Deficiency loentification and immediate action;
- b. Review for impact and assignment;
* -, ,.s--- - - - - - - - - , , - - . .-.
CHANGE Added Para. 4.5 'In House Events Analysis Supervisor", transferred responsibility for #1 (4.4.1.b) Administering the Condition Report Procest, and #2 (4.4.1.d) administering a root cause investigation and trend analysis program for corrective action documents and for issuing a periodic human performance trend report from the Quality Assurance (QA) Manager to the In-House Events Analysis Supervisor still reporting to the Director, Nuclear Safety. Also reworded
#2 to read: " Administering a root cause investigation and trend analysis program for corrective cction documents and for publishing a written or electronic trend report.
Deleted para. 4.4.1.c. BASIS FOR NO REDUCTION OF COMMITMENT The administration of the Condition Repor1 process, root cause analysis process and trend program has been transferred from OA to the in House Events Analysis Supervisor still reporting to the Director, Nuclear Safety. There will be no reduction of analysis efforts or level of independence. CAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 16
,Rev.5 4.4.1.b -4.4.1.c--
4.4.1.d p I
- _ - . . - _ - - . _ - - -= . ._ .
WATERFORD 3 e_Entergy QUALITY ASSURAM CHAPTER 16 REV. 5.0 Operations R-TYPE: C1.31 PROGRAM MANUAL page 2 of 5 l
- c. Performing reportability determinationa and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAf5T) 4.2.1 The Director, Nuclear Safety is responsible for:
/ a. Performing reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and
/b. Requesting or ensuring periodic indeper. dent assessments of the corrective action program to ensure that the pro:ess elements are adequately implemented.
4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible for: J a. Assuring that procedures are developed ...a maintained to implement the Corrective Action Program; s b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; J c. Assuring departmental responsiveness to the Corrective Action Program, through problem identificat. ion and resolution. 4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for:
/ a. Auditing and reviewing the Corrective Action Program to ensi4re acceptable implementation;
/ b. Administering the Condition Report process;
WATERFORD 3
/Entergy QUALITY ASSURANCE CHAPTER 16 REY. 5.0 Operations R-TYPE: C1.31 l, PROGRAM MANUAL Page 3 of 5
/c. Reviewing Condition Reports to determine if the identified condition (s) represent a significant adverse conditioni..and
!d. Administering a root cause investigation and trend analysis program for corrective action documents, 1 and for issuing a periodic human performance trend report'; u t
- e. Issuing Stop Work Orders when conditions warrant.
/4.5 SAFETY REVIEW COMMITTEE The Safety Review Committee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Action Program at Waterford 3. The SRC assessment shall include, at a minimum, the review of the trend reports and significant adverse conditions. , 4.6 CONDITION REVIEW BOARD The CRB is responsible for reviewing Controlled Maintenance Condition Identifications and Condition Reports to ensure adverse conditions receive the proper significance classification, priority, and l dedication of resources.
l
/4.7 ENTERGY OPERATIONS PERSONNEL Entergy Operations personnel are responsible for promptly identifying and documenting adverse conditions on correctiva action documents.
Entergy Operations' personnel are also responsible for recommending that an activity be stopped if ~.he specific work is not being done in accordance with approved procedures, drawings, specifications, or regulatory requirements. 5.0 DETAILS 5.1 PROCEDURAL REQUIREMENTS 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for: -
- a. Deficiency identification and immediate action;
, _ i
j - f l i g- Ent WATERFORD 3 QUAUTY ASSURANCE CHAPTER 18 R TYPE: C1.31 REV. 8.0 PROGRAM MANUAL PAGE: 2 OF 5 l l c. Performing immediate notification determinations and making 1 appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and i : 4
- d. - Performing reportability determinations and making appropriate i !
notifications in accordance with 40CFR for identified environmental l adverse conditions. , 1 L 4.2 DIRECTOR, NUCLEAR SAFETY
- 1 l 4.2.1 The Director, Nuclear Safety is responsible for:
- a. Assuring the performance of reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21;
[l 4 i
- b. Requesting er ensuring pc. dic independent assessments of the corrective action program to ensure that the process elements are ;
j _ adequately implemented; and l ) c. Ovsrsight of the administration of the Condition Report process, g root cause analysis and trend programs. l l 4.3 DIRECTORS AND MANAGERS l 4.3.1 Directors and Managers are responsible for: I
- a. Assuring that procedures are developed and maintained to
- implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the j Corrective Action Program; *
- c. Assuring departmental responsiveness to the Corrective Action i Program, through problem identification and resolution.
- i 4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for:
i a: Auditing and reviewing the Corrective Action Program to ensure
- . acceptable implementation; j gl L .
..,_,.m______ . , , . , , , _ _ _ . _ _ . _ _ ...,.._.,_,.__,_,,.._.,_,,,._.,._,.....,,-..,.._..,..,,_m,%, ,,,,,,,,,-w., ...m.,.
g WATERFORD 3 CHAPTER 16 REV. 6.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 3OF5
- b. Issuing Stop Work Orders when conditions warrant.
4.5 The In House Events Analysis Supervisor is responsible for:
- a. Administering the Condition Report Process; and
- b. Administering a root cause investigation and trend analysis program for corrective action documents and for publishing a written or electronic trend report.
4.6 SAFETY REVIEW COMMITTEE The Safety Review Committee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Action Program at Waterford
- 3. The SRC assessment hallinclude, at a minimum, the review of the trend ,
reports and significant adverse conditions. 4.7 CONDITION REVIEW BOARD The CRB is responsible for reviewing Controlled Maintenance Condition Identifications and Condition Reports to ensure adverse conditions receive the proper significance classification, priority, and dedication of resources 4.8 WATERFORD 3 PERSONNEL Waterford 3 personnel are responsible for promptly identifying and g documenting adverse conditions on corrective action documents. Waterford 3 personnel are also responsible for recommending that an activity be stopped if the specific work is not being done in accordance with approved proceduren, drawings, specifications, or regulatory requirer.1ents. 5.0 DETAILS 5.1 PROCEDURAL REQ'JlREMENTS 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for; ,
- a. Deficiency identification and immediate action;
- b. Review for impact and assignment;
, - ~ - - - g---- ~, -, - - - - - - -
CHANGE I Changed para. 4.2.1.a from
- Performing" to " Assuring the performance of..." and deleted para.
5.2 in it's entirety. BASIS FOR NO REDUCTION OF COMMITMENT l ~ The change to para. 4.2.1.a clarifles the role of th- Director, Nuclear Safety to indicate the responsibility for performance of reportability reviews. The deleted section (5.2)is redundant to 1 information provided in section 5.1. The oversight of the corrective action program is 2 maintained by the Condition Review Board, the Safety Review Committee and Quality. l Assurance. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter _16 Rev.5 1 4.2.1.a 5.2 ' 2 i I i
q WATERFORD 3 _ Entergy CHAPTER 16 REY. 5.0 l QUAUTY ASSURANCE ' Operat!ons R-TYPE: C1.31 l PROGRAM MANUAL Page 2 of 5 ' 1
- c. l'erforming reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR,- NUCLEAR SAFETY 4.2.1 The Director, Nuclear Safety is responsible for:
/ a. Performing reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and
/b. Requesting or ensuring periodic independent assessments of the corrc:tive action program to ensure that the process elements are adequately implemented.
4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible for: J a. Assuring that procedures are developed and maintained to implcment the Corrective Action Program; s b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; J c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution. 4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for:
/ a. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation;
/ b. Administering the Condition Report process;
. a q
Q Entergy WATERFORD 3 CHAPTER 16 REV. 5.0 QUALITY ASSURANCE Operations R-TYPE: C1.31 PROGRAM MANUAL page 4 of 5 '
- b. Review for impact and assignment;
- c. Investigate and analyze;
- d. Corrective action planning and implementation; i
- e. Prioritization of corrective action;
/ f. Verification of completion; and
/g. Verification of effectiveness.
5.1.2 Implementing procedures shall assign responsibility to each individual employed by Entergy Operations to promptly identify adverse conditions. 5.1.3 Implementing procedures shall be developed to ensure that each individual has the appropriate corrective action documents and guidance necessary to properly document adverse conditions. 5.1.4 Procedures shall also address corrective actions identified external to Entergy Operations and throajh internal programs such as trend analysis. 5.2 CONFIRMATION OF CORRECTIVE ACTIONS 5.2.1 The various corrective action processes shall be monitored to ensure acceptable completion of:
/ a. Cause determinations as appropriate;
" b. Corrective actions which address identified causes; s c. Assignment of priority and level of management attention; and
> d. Tracking and closure.
I Y
) g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 16 R-TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 2OF5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY 4.2.1 The Director, Nuclear Safety is responsible for:
- a. Assuring the performance of reportability reviews of Condition Ql Reports (CRs) in accordance with 10CFR50.73 and 10CFR21;
- b. Requesting or ensuring periodic indeoendent assessments of the corrective action program to ensure that the process elements are adequately implemented; and
- c. Oversight of the administration of the Condition Report process, g root cause analysis and trend programs.
4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible for;
- a. Assuring that procedures are developed and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program;
- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for: ,
- a. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; aI 4
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 16 R-TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 4 OF 5
- c. Investigate and analyze;
- d. Corrective action planning and implementation;
- e. Prioritization of corrective action;
- f. Verification of completion; and
- g. Verification of effectiveness.
5.1.2 Implementing procedures shall assign responsibility to each individual employed by Entergy Operations to promptly identify adverse conditions. 5.1.3 Implementing procedures shall be developed to ensure that each individual has the appropriate corrective action documents and guidance necessary to properly document adverse conditions. 5.1.4 Procedures shall also address corrective actions identified external to Entergy Operations and through intemal programs such as trend analysis. 21 5.2 STOP WORK ORDER (SWO) 5.2.1 When an individual determines that specific work is not being performed in occordance with approved drawings, specifications, procedures, or regulatory requirements, the individual should recommcnd to the appropriate supervisor, that the activity be stopped until adequate corrective action is taken. The Quality Assurance Manager shall be notified if the activity does not cease. 5.2.2 The Quality Assurance Manager or his designee should verbally request that the adverse activity be stopped at the next safe stopping point. 5.2.3 If work is not stopped as requested, a Stop Work Order shall be issued by the Quality Assurance Manager or his designee, to the organization responsible for not terminating the work that is adverse to quality. Work shall not proceed until the Stop Work Order is released by the Quality Assurance Manager. m e
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE: Revise the Quakty Assurance Program Manual (QAPM) Appendix A Rev. 4.0, to clarify the provisions of Regulatory Guide 1.38 (ANSI N45.2.2) regarding motors in storage. Corrected para. 2 B. Comment 3 to read "NUREG-0737"-(editorial change only) 10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment to the QA Program description previously accepted by the NRC?
O Yes *
- No Explain:
Ths Waterford 3 Quality Assurance Program Manual, Appendix A. Rev. 4.0, Paragraph 6, will be revised to add a second paragraph that states the following:
" ANSI N45.2.2 states that motors in storage should have the insulation resistance checked on a scheduled basis.
W:terford 3 conducts complete insulation tests upon receipt of the motor and again before the motor is installed in the plint. An extensive motor run-in is also performed before installation to venfy operability." Th3 change only clanfies the commitment to have the insulation resistance checked on a scheduled basis. The scheduled basis is now specified. This change does not represent a lessening of commitment.
- 2. If item 1 above is YES, does the proposed change include the basis to conclude that the revised program incorporating the Yu Q No @ N/A change continues to meet the criteria of 10CFR50 Appendix B and other previously accepted FSAR commitments?
Explain: J k W&Mb Reviewed By: QA Replisentative Date RECOMMENDATION: Does not represent a lessening of commitment and it can be implemented immediately. Represents a lessening of commitment, however, the change has sufficient basis to O demonstrate continued comPilant.e with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. O Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the change should not be processed. f a,tiQv - -
%\s Recommended By: QA Superv or Y Date DISPOSITION:
** Approved for implementation Disapproved Approved for submittal to the NRC for acceptance LW CL Approved By: dA Man $ger L Date OAP-018 R6 0 Attachment 7.1 R-TYPE: J3.11
_ _ _ _ _ _ _ _ -l
l .. CHANGE l Revised manual to clarify the provisions of Regulatory Guide 1.38 (ANSI N45.2.2) regarding motors in storage and made a typographical correction on para. 2. B Comment 3 to read NUREG-0737 instead of NUREG-0731. BASIS FOR NO REDUCTION OF COMMITMENT The Waterford 3 Quality Assurance Program Manual Appendix A was revised to add a second paragraph that states the following: " ANSI N45.2.2 states that motors in storage should have the insulation resistance checked on a scheduled basis." Waterford 3 conducts complete insulation tests upon receipt of the motor and again before the motor is installed in the plant. An extensive motor run-in is also performed before installation to verify operability." The change only clarifies the commitment to have the insulation resistance checked on a scheduled basis. The scheduled basis is now specified. This change does not represent a lessening of commitment. OAPM SECTIONS AFFECTED BY THIS CHANGE Appendix A Rev. 4 Para. 2 B. (#3) Para. 6
WATERFORD 3
-(]>
( Entergy QUALITY ASSLRANCE APPENDIX: A REY. 4.0 Operations PROGRAM MANUAL R-TYPE: C1.31 Page 2 of 8 m Document *
.C.gged B. ANSI /ANS 3.1-1978, 2. The qualification of personnel
" Standards for Selection other than those in the Health and Training of Physics, Radwaste, and Chemistry Personnel for Nuclear Departments are in accordance with Power Plants' ANSI /ANS 3.1-1978. Specific cosuiitments are shown in FSAR Chapter 13,
- 3. Personnel performing Independent Technical Review functions meet -
the qualification requirements of NUREG-0731-1980 instead of Section 4.7.2 of ANSI /ANS 3.1-1978.
- 3. Regulatory Guide 1.30, August 1. Waterford 3 applies the provisions 1972, ' Quality Assurance of this Regulatory Guide and its Requirements for the endorsed standard to Class IE Installation, Inspection and equipment only.
Testing of Instrumentation and S Electrical Equipment" 2. Each safety related item of (Endorses ANSI N45.2.4-1972) process instrumentation is identified with a unique number. This number is used in instrument maintenance records so that current calibration status, including data such as the date of the calibration and identity of the person that performed the calibration, can be readily determined. Such information may also be contained on tags or labels that may be attached to installed instrumentation. 4 Regulatory Guide 1.33, Rev. 2, 1. ANSI N18.7 references certain February 1978, " Quality other standards to which Entergy Assurance Program Requirements Operations takes exception. (Operational)" Waterford 3 exceptions and (Endorses ANSI N18.7-1976) alternatives are listed in this table. m
APPENDIX: A REV. 4.0 v/Entergy QUAUTY AN R-TYPE: Cl.31 Operations PROGRAM mal (JAL f ., Page 5 of 8 Document Conment
- 4. Regulatory Guide 1.33 7. ANSI N18.7, Section 5.2.15 states, (Continued) " Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years."
Waterford 3 has programmatic control requirements in place that initiate procedure reviews upon identification of new or revised source material that has a potential to affect the intent of the procedure. A biennial audit is performed by the Quality Assurance Department to verify compliance with existing programmatic controls used to maintain procedures current.
- 5. Regulatory Guide 1.37, March No exceptions.
1973, " Quality Assurance Requirements for Cleaning Fluid Systems and Associated Components of Water Cooled Nuclear Plants" (indorses ANSI N45.2.1-1973)
- 6. Regulatory Guide 1.38, Rev. 2, For the storage of new fuel assemblies May 1977, " Quality Assurance and neutron sources, Waterford 3 commits Requirements for Packaging, to the storage requirements of Level B Shipping and Receiving, of ANSI N45.2.2-1972 less the flooding Storage and Handling of Items prevention requirements and will for Water Cooled Nuclear Power minimize dust and other particles Plants" (Endorses ANSI contacting these items by placing a fire N45.2.2-1972) retardant polyethylene cover over these items or the cell locations in which the items are stored.
J
g- Ent .
- WATERFORD 3 QUALITY ASSURANCE APPENDIX A R-TYPE: C1.31 REV.5.0 PROGRAM MANUAL PAGE: 2OF8 Document Comment B. ANSI /ANS 3.1-1978, 2. The qualification of personnel other
" Standards for Selection than those in the Health Physics, and Training of Personnel Radwaste, and Chemistry for Nuclear Power Plants" Departments are in accordance with ANSI /ANS 3.1-1978. Specific commitments are shown in FSAR Chapter 13.
- 3. Personnel performing Independent Technical Review functions meet the qualification requirements of NUREG-t 0737-1980 instead of Section {l-4.7.2 of ANSl/ANS 3.1-1978.
l
- 3. Regulatory Guide 1.30, August 1, Waterford 3 applies the provisions of 1972," Quality Assurance this Regulatory Guide and its Requirements for the installation, endorsed standard to Class 1E Inspection and Testing of _ equipment ontf.
Instrumentation and Electrical Equipment" (Endorses ANSI 2. Each cafety related item of process N45.2.4-1972)- instrumentation is identified with a unique number. This number is used in instrument maintenance records so that current calibration status, including data such as the date of the calibration and identity of the person that performed the calibration, can be readily determined. Such information may also be contained on tags or - labels that may be attached to installed instrumentation. em O
,, .. O g WATERFORD 3 APPENDIX A REV.5.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 5 OF 8 Document Comment
- 4. hegulatory Guide 1.33 Waterfo'rd 3 has programmatic control (Continued) requirements in place that initiate procedure reviews upon identification of new or revised source material that has a potential to affect the intent of the procedure.
A biennial audit is performed by the Quality Assurance Department to verify compliance with existing programmatic controls used to maintain procedures current.
- 5. Regulatory Guide 1.37, March No exceptions.
1973," Quality Assurance Requirements for Cleaning Fluid Systems and Associated Components of Water Cooled Nuclear Plants" (Endorses ANSI N45.2.1 1973)
- 6. Regulatory Guide 1.38, Rev. 2, For the storage of new fuel assemblies and May 1977, " Quality Assurance neutron sources, Waterford 3 commits to the Requirements for Packaging, storage requirements of Level B of ANSI Shipping and Receiving, Storage N45.2.2-1972 less the flooding prevention and Handling of items for Water requirements and w;!I minimize dust and Coo!ed Nuclear Power Plants" other particles contacting these items by (Endorses ANSI N45.2.2-1972) placing a fire retardant polyethylene cover over these items or the cell locations in which the items are stored, i ANSI N45.2.2 states that motors in storage should have the insulation resistance checked on a scheduled basis. Waterford 3 conducts complete insulation tests upon g receipt of the motor and again before the motor is installed in the plant. An extensive -
motor run-in is also performed before installation to verify operability.
t l L ATTACHMENT lli TO W3F1-98-0013 ' QAPM Table of Contents Revision 14 Changes affecting QAPM Chapters 1,2,4,7,15,.16, and 18 to l Revisions 13,11, 5, 7, 7,' 8, and 7, respectively
g WATERFORD 3 TABLE OF CONTENTS
- Ent QUALITY ASSURANCE PROGRAM MANUAL REV. 14.0 R-TYPE: C1.31
_.. .lM 3E: 1OF1 TITLE EVISION DATE Forward,and Policy Statement g 1.0 04/22/92 Chapter 1 Organization mvdni i%p I *- 13.0 03/11/97 Chapter 2 Quality Assurance Program 11.0 03/11/97 Chapter 3 Design Control 3.0 06/14/95 Chapter 4 Procurement Document Control 5.0 03/11/97 l Chapter 5 Instructions, Procedures, and 4.0 03/20/96 Drawings Chapter 6 Document Control 6.0 01/17/97 Chapter 7 Control of Purchased Materials, 7.0 03/11/97 Equipment, and Services l Chapter 8 Identification and Control of Materials, 5.0 01/17/97 Parts, and Components Chapter 9 Control of Special Processes 5.0 10/25/95 Chapter 10 Inspection 6.0 03/20/96 Chapter 11 Test Control 2.0 03/20/96 Chapter 12 Control of Measuring and Test Equipment 2.0 06/11/93 Chapter 13 Handling, Storage, Packaging and Shipping 4.0 01/16/95 Chapter 14 Inspection, Test, and Operating Status 1.0 06/11/93 Chapter 15 Nonconforming Materials, Parts or 7.0 03/11/97 Components l Chapter 16 Corrective Action 8.0 03/11/97 Chapter 17 Quality Assurance Records 5.0 01/17/97 Chapter 18 Audits 7.0 03/11/97 l Appendix A Regulatory Guidance Document 5.0 10/16/96 Appendix B 10CFR50, Appendix B Compliance 0.0 04/01/91 Appendix C Terms and Definitions 5.0 10/07/94 l
QUALITY ASSURANCE PROGRAM } CHANGE REVIEW FORM PROPOSED CHANGE: 4 SEE ATTACHED
- 10CFR60.54 REVIEW
- ,
- 1. Does the proposed change represent a reduction of commitment Yes ** No I
to the QA Program description previously accepted by the NRC? Explain: ! l l SEE ATTACHED ' i l 2. If item 1 above is YES, does the proposed chants include the Yes No ' E N/A . basis to conclude that the revised program incorporating the , change continues to meet the criteria of 10CFR60 Appendix B , and other previously accepted FSAR commitments? ! Explain: a l
,f t/fr ///$$7 Reviewed By: QA R4resentative Date l
RECOIMIENDATION:
** Does not represent a lessening of commitment and it can be implemsated immediately.
4
. Represents a lessening of commitment, however, the change has sufficient basis to I demonstrate continued compilance with Appendix B and other FSAR commitraents. Therefore,
. It should be submitted to the NRC for acceptance prior to implementation. Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the change should not be processed, bw fil6%vv M 20YV 7 Recommended By: QA Supervisor Date l' DISPOSITION:
** Approved forimplementation Disapproved j Approved for subm o the NRC for acceptance D 7 Approved By: Q/Manafor j Date
} . l QAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11 i
PROPOSED CHANGE This change will revise Chapters 1,2,4,7, and 18 to clearty identify that services shared between EOl sites are controlled under the Waterford 3 Quality Assurance Program and Chapters 1, 2,15,16 to reassign organizational responsibilities between the Director, Site Support (responsible for Security, Emergency Planning, Quality Assurance and Employee Concems Program) and the Director, Nuclear Safety and Regulatory Affairs (responsible for Licensing, Operational Experience Engineering ar.d in-House Events Analysis).and to clarify the responsibility of the Vice President, Operations Support for administering security implementation (Access Authorization and Fitness For Duty).
- 1. Does the proposed change mpresent a reduction of commitment to the QA Program description previously accepted by the NRC? NO Chapter 1, Rev.12.0 paragraph 4.13.1.a; j Added " implementation (Access Authorization and Fitness for Duty)" behind security Chapter 1, Rev.12.0 paragraph 4.13.1.b.1; Evaluating quality assurance prograrns and activities of Waterford 3 suppliers and contractors... is revised to read; ...Waterford 3 suppliers, contractors, and EOl shared servbes"...
Chapter 1, Rev.12.0 paragraph 4.15; Sentence is added which reads, " Services obtained from other EOl sites are initiated through documented agreenwnts between the various EOl sites." . Chapter 1, Rev.12.0 parsgraph 4.5.1.e,f & I and 4.6.1.e,f & j; Paragraph 4 5.1 c,f & i(Director, Site Support) was movsv' to 4.6.1.e,f & J (Director, Nuclear Safety and Regulatory Affairs) respectively. Chapter i, Rev.12.0 paragraph 4.6.1.f Paragraph 4.6.1.f was moved to 4.6.1.h and the word " initiating" was added to be consistent with Chapter 15 (para. 4.4) responsibilities for the Daroctor, Nuclear Safety and Regulatory Affairs. 4
Ch:pter 2, R;v.10.0 paragr:ph 4.10;
...Informations Systems, Supplier QA and Materials... is revised to read; ...Informations Systems, Supplier QA, EOl shared services, and Materiais...
Chapter 2, Rev.10.0 paragraphs 4.4 and 4.5; Revised to move Operational Experience Engineering and in-House Events Analysis from the Director, Site Support to the Director, Nuclear safety and Regulatory Affairs. Chapter 4, Rev. 4.0 paragraph 1.2; Paragraph added which reads, " Services performed by other EOl sites (shared services) are obtained from those sites in accordance with documented agreements between the sites." Chapter 7. Rev. 6.0 paragraph 1.4; Same as Chapter 4. Chapter 15, Rev. 6.0 paragraphs 4.3.1,4.3.2,4.3.3,4.4.2 & 4.4.3; Paragraph 4.3.1 was editorially changed to be consistent with format of previous paragraphs and the last sentence (which was left in error from the last revision) was removed. Paragraph 4.4.1 was added for format consistency and paragraphs 4.3.2 & 4.3.3 were moved to 4.4.2 & 4.4.3 respectively. Chapter 16, Rev. 7.0 paragraphs 4.3.b,4.3.1 & 4.2.1.b; Paragraph 4.3.b was moved to 4.2.1.b and 4.3.1 was added for format consistency. l Chapter 18, Rev. 6.0 paragraph 4.1; f ... suppliers and contractors... is changed to read; "... suppliers, contractors, and EOl shared services"... Entergy Operations sites (Arkansas Nuclear One, Grand Gulf Nuclear Station, Riverbend Station, and Waterford 3) share various services between the sites (e.g., TLD processing, calibration facility for various Measuring and Test Equipment). Each EOl site works to an NRC cpproved Quality Assurance Program, as well as oversight from the corporate headquarters. Services shared between the sites have been, and continue to be, subject to the site's QA programs. This revision does not add requirements nor delete any requirements, it simply clearly identifies that the shared services are recognized under the Waterford 3 Quality Assurance Program.
Ch:ng:s to Chrpt:r 1, p r:grcph & 4.13.1.b.1, Chrpt:r 2, p;rcgrcph 4.10, and Ch pt:r 18, paragraph 4.1 clearly identifies that the Vice President, Operations Support provides for the cvaluation of shared services. Changes to Chapter 1, paragraph 4.13.1.a clarifies that the Vice President, Operations Support is respransible for administering security implementation for Access Authorization and Fitness For Dut/. Changes to Chapter 1, pa'ragraph 4.15, Chapter 4, para raph 1.2 and Chapter 7, paragraph 1.4 adds a paragraph to clearly state that shared services between EOl sites are in accordance with documented agreements but do not rely on site procurement documents. Changes to Chapter 1 paragraphs 4.5.1.e,f & i and 4.6.1.e,f & J, Chapte' ' caragraphs 4.4 and 4.5, Chapter 15 paragraphs 4.3.1,4.4.1,4.3.2,4.3.3,4.4.2 & 4.4.3 and , : apter 16 paragraphs 4.3.b,4.2.1.b and 4.3.1 were made to transfer organizational responsibilities from the Director, Site Support to the Director, Nuclear Safety and Regulatory Affairs. All commitments were transferred intact. The revision does not represent a reduction of commitment to the Waterford 3 Quality Assurance Program previously accepted by the NRC. l l
CHANGE QAPM revised to clearly identify that services shared between EOl sites are controlled under the Waterford 3 Quality Assurance Program and to reassign organizational responsibilities between the Director, Site Support (responsible for Security, Emergency Planning, Quality Assurance and Employee Concerns Program) and the Director, Nuclear Safety and Regulatory Affairs (responsible for Licensitig, Operations Experience Engineering and in House Events Analysis), and to clarify the responsibility of the Vice President, Operations Support for cdministering security implementation (Access Authorization and Fitness For Duty). BASIS FOR NO REDUCTION OF COMMITMENT EOl sites (Arkansas Nuclear One, Grand Gulf Nuclear Station, Riverbend Station and Waterford
- 3) share various services between the sites (e.g., TLD processing, calibration 6,cility for various M&TE). Each EOl site works to an NRC aporoved QA Program, as well as aversight from the corporate headquarters. Services shared between the sites have been, and continue to be, subject to the site's QA programs. This revision does not add requirements nor delete any requirements, it simply clearly identifies that the shared services are recognized under the Waterford 3 QA Program.
Chapter 1 (4.13.1.a) added " implementation (Access Authc.;zation and Fitness for Duty)" behind security. (4.13.1.b.1) Evaluating quality assurance programs and activities of Waterford 3 suppliers and contractors...is revised to read;...Waterford 3 suppliers, contractors, and EOI shared services"...(4.15) Sentence is added which reads, " Services obtained from othei EOI sites are initiated through documented agreements between the various EOl sites."(4.5.1.e, f & i) Director Site Support moved to (4.6.1.e, f & j) Director, Nuclear Safety and Regulatory Affairs respectively (4.6.1.f) moved to 4.6.1.h and the word " initiating" was added to be consistent with Chapter 15 para. 4.4 Chapter 2 (4.4 and 4.5) revised to move Operational Experience Engineering and in-House Events Analysis from Director, Site Support to Director, Nuclear Safety and Regulatory Affairs. Chapter 2 (4.10) ...Information Systems,- Supplier QA and Materials...is revised to read;...Informations Systems, Supplier QA, EOl shared services, and Materials... Chapter 4 (1.0) added paragraph 1.2 which reads, " Services performed by other EOl Sites (shared services) are obtained from those sites in accordance with documented agreements between the sites." Chapter 7 (1.0) same as Chapter 4. Chapter 15 (4.3.1,4.3.2,4.3.3,4.4) Paragraph 4.3.1 was editorially changed to be consistent with format of previous paragraphs and the last sentence (which was left in error from the last revision was removed. Paragraph 4.4.1 was added for format consistency and paragraphs 4.3.2 & 4.3.3 were moved to 4_4.2 & 4.4.3 respectively. Chapter 16 (4.3 & 4.3.b) Paragraph 4.3.b was moved to 4.2.1.b and 4.3.1 was added for format consistency. Chapter 18 (4.1) ... suppliers and contractors...is changed to read; " .. suppliers, contractors, and EOl shared services"... The revisions above do not represent a reduction of commitment to the Waterford 3 Quality Assurance Program previously accepted by the NRC. 1
OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 2 Chapter 4 Chapter 7 i Rev.12 Rev.10 Rev. 4 Rev. 6 4.13.1.a 4.4 1.0 1.0 4.13.1.b.1 4.5 4.15 4.10 4.5.1.e 4.5.1.f 4.5.1.1 4.0.1.f Chapter 15 Chapter 16 Chapter 18 Rev. 6 ,Rev. 7 Rev. 6 4.3.1 4.3 4.1 4.3.2 4.3.b 4.3.3 4.4
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S- Ent WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.12.0 PROGRAM MANUAL PAGE: 19 OF 21
- c. Thermal hydraulic analysis;
- d. Nondestructive analysis;
- e. Metallurgical evaluations;
- t. Fuel fabrication and related services;
- g. Reactor engineering and special nuclear material control and accountability; and
- h. Entergy Operations. Sc. weiding program.
4.13 VICE PRESIDENT, OPERATIONS SUPPORT 4.13.1 The Vice President, Operations Support reports directly to the Executive
. Vice President & Chief Operating Officer, and is responsible for.
I -
- a. Administering corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technology transfer, and centrallicensing; providing oversight of site Health Physics-and Chemistry activities; and managing the Plant Support and Assessment, Information Systems, Supplier QA, and Materials, Purchasing and Contracts groups, it is the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program; and
- b. Providing the direction and administration necessary relative to the following liste d primary quality related responsibilities as they relate to the Waterford 3 Quality Assurance Program:
- 1. Evaluating quality assurance programs and activities of Waterford 3 suppliers and contractors of quality related items, spare parts, and services through reviews, surveillances, and audits;
- 2. Conducting pre-award evaluations for quality requirements of vendors, suppliers, and contractors where applicable;
4- Ent WATERFORD 3 WALITY ASSURANCE CHAPTER 1 l 4 TYPE: C1.31 REV.13.0 PROGRAM MANUAL PAGE: 19 OF 21
- c. ' Thermal hydrtculic analysis;
- d. Nondestructive analysis;
- e. Metallurgical evaluaticos;
- f. Fuel fabrication and related services;
- g. Reactor engineering and special nuclear material control and accountability; and
- h. Entergy Operations, Inc. welding program.
4.13 VICE PRESIDENT, OPERATIONS SUPPORT 4.13.1 The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for: i
- a. Administering corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security implementation (Access Authorization and Fitnsas For Duty), emergency planning, technology transfer, 3
and centrallicensing; providing oversight of site Health Physics and Chemistry activities; and managing the Plant Support and Assessment, Information Systeme, Supplier QA, and Materials, l Purchasing and Contracts groups, it is the responsibility of the } Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the reouirements of the Waterford 3 Quality Assurance program; and
- b. Providing the direction and administration necessary relative to the fClowing listed primary quality related responsibilities as they relate to the Waterford 3 Quality Assurance Program:
- 1. Evaluating quality assurance programs and activities of Waterford 3 suppliers, contractors, and EOl shared services of quality related items, spare parts, and services 3
through reviews, surveillances, and audits;
- 2. Conducting pre-award evaluations for quality requirements of vendors, suppliers, and contractors where applicable;
-l
g WATERFORD 3 CHAPTER 1 REV.12.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 21 OF 21 4.15 SUPPLIERS / CONTRACTORS Suppliers / contractors of quality related material, equipment, spare parts, and/or services shall be required, as appropriate, by procurement documents to have a quality program, in such cases, a line of communication shall exist between the supplier / contractor and the Waterford 3 or Headquarters Quality Assurance organization. The overall responsibility for quality at Waterford 3 remains with Entergy Operations at all times.
5.0 DETAILS 5.1 ORGANIZATIONS PERFORMING QUALITY ASSURANCE FUNCTIONS Attachment I shows the lines of authority for the major Entergy Operations organizations that perform Quality Assurance functions at Waterford 3. 6.0 ATTACHMENTS Attachment 1 - Waterford 3 Organization Chart. .
./
WATERFORD 3 CHAPTER 1 REV.13.0 eE UALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 21 OF 21
'4.14 WATERFORD 3 PERSONNEL Waterford 3 personnel are responsible for adherence to the requirements delineated in this QA Program Manual and its implementing procedures.
Waterford 3 personnel are also responsible for identifying and reporting conditions ariverse to quality and for identifying program or procedural enhancemcats. 4.15 SUPPLIERS / CONTRACTORS Suppliers / contractors of quality related material, equipment, spare parts, and/or services shall be required, as appropriate, by procurement documents to have a quality program, in such cases, a line of communication shall exist between the supplier / contractor and the Waterford 3 or Headquarters Quality Assurance l organization. The overall responsibility for quality at Waterford 3 remains with j Entergy Operations at all times. Services obtained from other EOl sites are initiated through documented 13 agreements between the various EOl sites. 5.0 DETAILS 5.1 ORGANIZATIONS PERFORMING QUALITY ASSURANCE FUNCTIONS Attachment I shows the lines of authority for the major Entergy Operations organizations that perform Quality Assurance functions at Waterford 3. 6.0 ATTACHMENTS Attachment I - Waterford 3 Organization Chart. J
g- Ent WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.12.0 PROGRAM MANUAL PAGE: 6 OF 21
- d. Reviewing and processing assigned work authorizations and managing services for plant repair, modification, and construction which is under his jurisdiction:
- e. Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction work prior to acceptance; and
- g. Coordinating construction tasks involved with outages and retrofitting.
4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and performance of practice drills; and
- c. Implementing the Security Plan and Safeguards Contingency Plan; al
- d. Controlling plant area access;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs;
- f. Analyzing conditions for human performance trends and publishing quarterly trend reports;
- g. Interfacing with on-site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors to ensure quality is maintained;
- h. Reviewing plant system problems and performance concerns;
4 g WATERFORD 3 CHAPTER 1 REV.12.0
- Ent UALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 7 OF 21
- 1. Examining plant operating characteristics, NRC issuances (includes information Notices), industry advisories, Licensee Event
, Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as part of the Independent Technical Review function. The Independent Technical Review functions include responsibility for:
3
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are perfoimed correctly and that human errors are reduced as much as practical; J. Overseeing the activities of the Employee Concerns Program; and
- k. Implementing the Fitness For Duty Program 4.5.2 The Director, Site Support is also responsible for the direction and j administration of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance program. M The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, recommend or provide solutions through designated channels; and
- 3. Verify implementation of solutions.
j
e- Ent WATERFORD 3 WAlm AMRANCE CHAPTER 1 R-TYPE: C1,31 REV.13.0 PROGRAM MANUAL PAGE: 6 OF 21
- c. Coordinating the development and review of departmental procedures;
- d. Reviewing and processing assigned work authonzations and I
managing services foc plant repair, modification, and construction which k under hisjurisdlction;
- e. Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper con @@n of modification and construction work prior to acceptance; and g.
Coordinating construction tasks involved with outages and retrofitting. 4.5 blRECTOR, SITE SUPPORT 4.5.1 The piimary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drih scenarios and performance of practice drills; and c.
Implementing the Security Plan and Safeguards Contingency Plan;
- d. Controlling plant area access:
- e. Interfacing with on-site and outside organizations such as the M!
NRC, INPO, Quality Assurance, and equipment vendors to ensure qualityis maintained; and f. Overseeing the activities of the Employee Concems Program. Ml
O - Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.13.0 PROGRAM MANUAL PAGE: 10 OF 21 c.
' Managing the Waterford 3 Commitments Managament System;
- d. Managing the preparation of responses to NRC bulletins, orders, inspection reports, generic letters, and Notices of Violstion;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs;
- f. M Analyzing conditions for human performance trends and publishing quarterly trend reports;
- g. Reviewing corrective action documents for determindion of
, reportability; h. ' Reviewing operating abnormalities and initiating Licensee Event M Reports;
- i. Coordinating Nuclear Regulatory Commission interface;
- j. Reviewing plant system problems and performance concems;
- k. Examining plant operating characteristics, NRC issuances (includes Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as pa:t of the independent Technical Review function. The Independent Technical Review functions include responsibility for:
1. M Making recomrnendations for improving plant safety including procedure revisior,s, equipment modifications, maintenance activities, operations activities, or other means ofimproving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly ano that human errors are reduced as much as practical;
- l. Maintaining SRC charters; and
g- Ent WATERFORD 3 QUAL.lTY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.12.0 PROGRAM MANUAL PAGE: 10 OF 21
- 4. Expertise in interpretation and application of Appendix B to
.- 10CFR50 and related codes, standards, and regulatory guides;
- 5. Knowledge of inspection and nondestructive testing g requirements;
~
- 6. Ability to plan, organize, and administer a Quality Assurance program; and
- 7. Ability to maintain an effective working relationship with employees, contractors, suppliers, govemment agencies, and the public.
4.6 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.6.1 The primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs include:
- a. Coordinating and reviewing responses to Nuclear Regulatory Commission matters, as assigned;
- b. Managing the preparation of updates / revisions to the Final Safety Analysis Report and the Technical Specifications;
- c. Managing the Waterford 3 Ccmmitments Management System;
- d. Mansging the preparation of responses to NRC bulletins, orders, inspection reports, generic le"9rs, and Notices of Violation;
- e. Reviewing corrective action documents for determination of reportability;
- f. Reviewing operating abnormalitias and Licensee Event Reports;
- g. Coordinating Nuclear Regulatory Commission interface; 31
- h. Ma;ntaining SRC charters; and
- i. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification requirements.
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t e- Ent WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.13.0 PROGRAM MANUAL PAGE: 10 OF 21 I c.
' Managing the Waterford 3 Commitments Management System;
- d. Managing the preparation of responses to NRC bulletins, orders, inspection reports, generic letters, and Notices of Violation;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs;
- f. M Analyzing conditions for human performance trends and publishing quarterly trend reports;
- g. Reviewing corrective action documents for determination of reportabilky; h.
Reviewing operating abnonnalities and initiating Licensee Event M Reports;
- i. Coordinating Nuclear Regulatory Commission interface;
- j. Reviewing plant system problems and performance concems;
- k. Examining plant operating characteristics, NRC issuances (includes Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving uni +s of similar design, which may indicate areas for improving plant safety as part of the Independent Technical Review function. The Independent Technical Review functions include responsibility for:
1. M Making recomrendations for improving plant safety including procedu,e revisions, equipment modifications, maintenance activi%s, operations activities, or other means ofimproving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical;
- i. Maintaining SRC charters; and
t g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 R. TYPE: C1.31 REV.10.0 PROGRAM MANUAL PAGE: 3 OF 11 A 4.2.1 Plant Operations Review Committee (PORC) The PORC is responsible for functioning as the on site independent review committee, and is responsible for reviewing plant operations items and procedures which are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with applicable procedures. Additional responsibilitlec ma listed in Chapter 1 and the j Waterford 3 Technical Specifications. 4.3 D! RECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Modification l Control, Construction, and Project Management. The primary quality related responsibilities of the Director, Plant Modification and Construction are listed in Chapter 1. 4.4 DIRECTOR. SITE SUPPORT The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency Planning; Quality M Assurance; Operational Experience Engineering; In H,ouse Everns Analysis; and Employee Concems Program. The primary quality related responsibilities of the Director, Site Support are listed in Chapter 1. 4 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS M The director, Nuclear Safety and Regulatuy Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the Licensing unit. The primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are lisied in Chapter t $l 4.6 TRAINING MANAGER The Training Manager is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Operations Training; Simulator Training ' Maintenance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Training Manager are listed b Chapter 1.
- y. --
g WATERFORD 3 CHAPTER 2 REV.11.0
- Ent QUAUTY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 3 OF 12 4.2.1 Plant Operations Review Committee (PORC)
The PORC is responsible for functioning as the on site independent review committee, and is responsible for reviewing plant operations items and procedures which are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with applicable
- procedures. Additional responsibilities are listed in Chapter 1 and the 1
Waterford 3 Technical Specifications. 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for ensuring the development and mair.tenance of procedures or instructions for the implementation of the following programs and organizational units: Modification Control, Construction, and Project Managemer.t. The primary quality related responsibilities of the Director, Plant Modification and Construction are listed in Chapter 1. 4.4 DIRECTOR, SITE SUPPORT The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency Planning; Quality Assurance; and Employee Concems Program. The primary quality related Ml responsibilities of the Director, Site Support are listed in Chapter 1. 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nuclear Saf6ty and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Licensing; Operational Experience Engineering; and in-House Events Analysis. The Ml primary quality related responsibliities of the Director, Nuclear Safety and Regulatory Affairs are listed in Chapter 1.
)
1
g WATERFORD 3 CHAPTER 2 REV.10.0
- Ente . QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 4 OF 11 4.7 MANAGER, SITE BUSINESS SERVICES The Manager, Site Business Services is responsible for ensuring the 10 development and maintenance of procedures or instructions for the implementation of Records, Document Control, and Policies and Directives activities.
4.8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The prirnary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 VICE PRESIDENT, ENGINEERING The Vice President, Engineering reports directly to the Executive Vice President
& Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1.
4.10 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support reports directly to the Executive Vice Presider,t & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, cheralstry, environmental services, operations, mairrtenance, outage management, security, emergency planning, technology transfer, and centrallicensing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Information Systems, Supplier QA and Materials, Purchasing and Centracts groups. It is the responsibility of thy Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 R TYPE: C1.31 REV.11.0 i PROGRAM MANUAL PAGE: 5 OF 12 4.10 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technology transfer, and centrallicencing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Information Systems, Supplier QA, EOl shared services, and Materials, Purchasing and ,gl Contracts groups, it is the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program. 5.0 DETAILS 5.1 DOCUMENT HIERARCHY 5.1.1 Attachment I depicts the hierarchy of documents comprising the Waterford 3 Quality Assurance program. This attachment identifies various program documentation that controls quality related activities at Waterford 3. Quality Assurance program implementing documents define the responsibilities of individuals and organizations participating in quality related activities.- 5.1.2 The highest level of the Waterford 3 Quality Assurance program includes:
- a. Federal and state regulations; b.. Industry codes and standards;
- c. Licensing agreements and specifications; and
- d. The Final Safety Analysis Report.
5.1.3 The next level of the document hierarchy includes: _
- a. ' Nuclear Management Manual;
- b. Waterford 3 Management Manual; and
4 3 WATERFORD 3 CHAPTER 4 REY. 4.0 Entergy (%,) Operations QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 Page 1 of 6 TITLE: PROCUREMENT DOCUMENT CONJRQL EFFECTIVE DATE: 01/16/95 PREPARED BYh k b f' ' DIRECTOR, NUCLEAR SAFETY: . ud' QA MANAGE . b. VICE PRESIDENT, OPERATIONS: r- u;b. U 1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterford 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the original it.em.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants.") 2.2 USNRC Regulatory Guide 1.89, " Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants." 3.0 DEFINITIONS 3.1 See Appendix C
g WATERFORD 3 CHAPTER 4 REV. 5.0
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PREPARED BY Cha ds DIRECTOR, SITE SUPPORT: M mm Q NAGER b sr/.dp VICE PRESIDENT, OPERATIONS: (y-ic0 PURPOSE 1.1 Proct rement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and , replacement parts, components, and services required to modify, maintain, i repair, test, inspect or operate Waterford 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the originalitem. 1.2 Services performed by other EOl sites (shared services) are obtained from 2 those sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1 July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants.") 2.2 USNRC Regulatory Guide 1.89, " Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Piants." 3c0 DEFINITIONS 3.1 See Appendix C
- - - _ . - u
g- EntC WATERFORD 3 QUALITY ASSURANCE CHAPTER 7 R TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 1OF7 TITLE: C_QHIROL OF PURCHASED EFFECTIVE DATE: 01/17/97 MATEb;iLS, EQUIPMENT AND
' SERVICES PREPARED BY: u//h/ DIRECTOR, SITE SUPPORT: f/ ~_
QA MANAGER: a N VICE PRESIDENT, OPERATIONS: / *b
<-(
1.0 PURPOSE 1,1 Safety related material, equipment, and services, whether purchased directly or through others, conforms to procurement document specifications as described in Chapter 4. Provisions are made, as appropriate, for source evaluation and selection, review for objective evidence of quality, inspection at source, and inspection upon delivery, in addition, products may be accepted by pre / post installation testing or qualification testing by Entergy Operations or an approved test laboratory. 1.2 Vendors' Quality Assurance Programs are reviewed at periodic intervals commensurate with the importance, quantity, and complexity of the product or services being purchased. These reviews may employ audits, surveillances, source verifications, independent inspections, or tests to verify that documentation, such as inspection records and certifications, are reliable and valid. . 1.3 Proposals (bids or quotations) by vendors are reviewed to ensure that no exceptions are taken which would violate safety, technical, or quality requirements. The program requirements for control of purchased material, equipment, and services are contained in approved written procedures.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976," Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants.")
g WATERFORD 3 CHAPTER 7 REV. 7,0
= Ent QUAllW ASSURANCE R TYPE: C1,31 PROGRAM MANUAL PAGE: 1OF7 TITLE: CONTROL OF PURCHASEQ EFFECTIVE DATE: 03/11/97 MATERlALSmEQUleMENT AND SERVICES PREPARED B bytt.hM DIRECTOR, SITE SUPPORT: f/// e ,,,,y .
A ANAGER f
// Mitt //2 VICE PRESIDENT, OPERATIONS: N W 1.0 PURPOSE 1.1 Safety related material, equipment, and services, whether purchased directly or through others, conforms to procurement document specifications as described in Chapter 4. Provisions are made, as appropriate, for source evaluation and selection, review for objective evidence of quality, inspection at source, and inspection upon delivery, in addition, products may be accepted by pre / post installation testing or qualification testing by Entergy Operations or en approved test laboratory.
1.2 Vendors' Quality Assurance Programs are reviewed at periodic intervals commcnsurate with the importance, quantity, and complexity of the product or services being purchased. These reviews may employ audits, surveillances, source verifications, independent inspections, or tests to verify that documentation, such as inspection records and certifications, are reliable and valid. 1.3 Proposals (bids or quotations) by vendors are reviewed to ensure that no exceptions are taken which would violate safety, technical, or quality rec,uirements. The program requirements for control of purchased material, equipment, and services are contained in approved written procedures. 1.4 Services performed by other EOl sites (shared services) are obtained from Z those sites in accordance with documented agreements between the sites
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirements for Centrol of Procurement of items and Services for Nuclear Power Plants.") ~ ,
___ . _._ _.. _ _ . _ _ _ _ . _ _ . _ . _ .. . .~. _ -
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g- Ent WATERFO!!D 3 QUALITY ASSURANCE CHAPTER 15 R TYPE: C1.31 REV.8.0 j
! PROGRAM MANUAL PAGE: 2 OF 5
- 4.0 RESPONSIBILITIES l 4.'1 GENERAL MANAGER, PLANT OPERATIONS l The General Manager, Plant Operations is responsible for the nonconformance
{ control system at Waterford 3 for material, parts, and components under plant ! . jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use-as-is". i f 4.1.1 PLANT OPERATIONS REVIEW COMMITTEE j . The PORC is responsible for reviewing safety related nonconformances j dispositioned " repair" and "use as-is" and recommending approval to the General Manager, Plant Operations, j 4.2 DIRECTOR, DESIGN ENGINEERING 1 The Director, Design Engineering is responsible for reviewing nonconformances ! with recommended dispositions of " repair" or "use-as-is", and for evaluating and , processing changes to resulting design drawings. The Director, Design Engineering is also responsible for dispositioning other nonconformances I assigned to his organization. Y 4.3 DIRECTOR, SITE SUPPORT Tne Director, Site Support is responsible for: . 4.3.1 The review and audit of the Corrective Action Program. ! initiating Licensee Event Reports under 10CFR50.73: 4.3.2 The on site Independent Technical Review function which includes
- providing a random independent review of nonconformance dispositions l and closures during the operations phase; and g l 4.3.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC as required by 10CFR21.
- 4.4 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nucioar Safety and Regulatory Affairs is responsible for initiating ,
Licensee Event Paports under 10CFR50.73.
I g WATERFORD 3 CHAPTER is REV.7 0 ' - Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 2 OF 6 l 4.0 RESPONSIBILITIES i 4.1 GENERAL MANAGER, PLANT OPERATIONS i j The General Manager, Plant Operations is responsible for the nonconformance ! control system at Waterford 3 for material, parts, and components under plant i jurisdiction. Additionally, the General Manager, Plarit Operations is responsible
- for approving nonconformances dispositioned " repair" or "use-as-is".
4.1.1 PLANT OPERATIONS REVIEW COMMITTEE ! The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending approval to the { General Manager, Plant Operations. l 4.2 DIRECTOR, DESIGN ENGINEERING
- The Director, Design Engineering is responsible for reviewing nonconformances i
with recommended dispositions of " repair" or "use-as-is", and for evaluating and _ processing changes to resulting design drawings. The Director, Des!gn Engineering is also responsible for dispositioning other nonconformances assigned to his organization. l .. ! 4.3 DIRECTOR, SITE SUPPORT ! The Director, Site Support is responsible for the review and audit of the ! Corrective Action Program. Zl 4.4 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS [
- The Director, Nuclear Safety and Regulatory Affairs is responsible for
i 4.4.1 Initiating Licensee Event Repoits under 10CFR50.73. ! { 4.4.2 The on site Independent Technical Review function which includes
- providing a random independent review of nonconformance dispositions and closures during the operations phase; and Z >
. 4.4.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC as required by 10CFR21.
i' . 1 1 g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 18 R TYPE: C1.31 REV. 7.0 PROGRAM MANUAL PAGE: 2 OF 5
- c. Performing immediate notification determinations and making
- appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
{
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is responsible for:
- a. Assuring the performance of reportability reviews of Condition !
Reports (CRs) in accordance with 10CFR50.73 and 10CFR21. I 4.3 DIRECTOR, SITE SUPPORT
- a. Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented; and I
- b. Oversight of the administration of the Condition Report process, root cause analysis and trend programs.
l 4.4 DIRECTORS AND MANAGERS 4.4.1 Directors and Managers are responsible for: E
- a. Assuring that procedures are developed and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; and
!- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution. 4.5' QUALITY ASSURANCE MANAGER 4.5.1 The Quality Assurance Manager is responsible for: c c
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l 1 2 g Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER is R. TYPE: C1.31 REV. 8.0 i-PROGRAM MANUAL PAGE: 2 OF 5
] c. ' Performing immediate notification determinations and making appropriate notifications in ac;ordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental
! adverse conditions.
- 4.2 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is resoonsible for
- a. Assuring the performance of reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and j b. Oversight of the administration of the Condition Report process. A
- root cause analysis and trend programs.
4.3 DIRECTOR, SITE SUPPORT ] 4.3.1 The Director Site Support is responsible for: @l a .- Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented. El DIRECTORS AND MANAGERS
- 4.4 -
l- - 4.4.1 Directors and Managers are responsible for. l - a. Assuring that procedures are developed and maintained to L implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; and -
t
- c. Assuring departmental responsiveness to the Corrective Action J
Program, through problem identification and resolution. , 1 l l
g WATERFORD 3 CHAPTER 18 REV. 6.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 1OF8 TITLE: AUDITS EFFECTIVE DATE: 01/17/97 I #I7[N DIRECTOR, SITE SUPPORT: f//[
PREPARED BYf _ _ UM bh VICE PRESIDENT, OPERATIONS:
~
QA MANAGER: y (- 1.0- PURPOSE 1.1 Audits are perforrned to verify compliance with the Quality Assurance Flogram requirements and to determine the program effectiveness. This chapter defines the requirements of the Waterford 3 Quality Assurance Audit Program.
2.0 REFERENCES
2.1 Waterford 3 Quality Assurance Program Manual, Chapter 18," Corrective Action" 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4,1 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support is responsible for planning, scheduling and conducting audits and surveillances of suppliers and contractors which provide meterials, componenta, parts and services to be used in safety related applications. 4.2 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for planning, scheduling, and conducting audits of the Waterford 3 Quality Assurance Program, and its implementing procedures. l
______ .~.__ _._ _ __ ___ _ ___ _ __ _ _. _ ___ _ . _ _ _ _ _
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g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 18 R TYPE: C1.31 REV. 7.0 PROGRAM MANUAL PAGE: 1OF8 TITLE: AUDITS EFFECTIVE DATE: 03/11/97 4 PREPARED BY h4 w h do DIRECTOR, SITE SUPPORT: //// m,_ bNAGE gMf/// VICE PRESIDENT, OPERATIONS: [ /d j 1.0 PURPOSE 1.1 Audits are performed to verify compliance with the Quality Assurance Program requirements and to determine the program effectiveness. This chapter defines the requirements of the Waterford 3 Quality Assurance Audit Program.
2.0 REFERENCES
2.1 Waterford 3 Quality Assurance Program Manual, Chapter 16," Corrective Action" 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 VICE PRESIDENT, OPERATIONS SUPPORT l The Vice President, Operations Support is responsible for planning, scheduling , I and conducting audits and surveillances of suppliers, contractors, and EOI Z shared services which provide materials, components, parts and services to be used in safety related applications. l 4.2 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for planning, scheduling, and conducting audits of the Waterford 3 Quality Assurance Program, and its implementing procedures. l 1
t 1 h 4 i i i I i i t ll 4 i 1 . 4 ATTACHMENT IV TO W3F198-0013 l ,1 - j QAPM Table of Contents Revision 15 . l Changes affecting QAPM Chapters 1 and 5 to Revisions 14 and 5, respectively 1 i 1 i i 3 i i 5 I
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I g- Ent WATERFORD 3 QUALITY ASSURANCE TABLE OF CONTENTS REV. 15.0 PROGRAM MANUAL R TYP5i C1.31 PAGE: 1OF1 ; TITLE q a r , ,,, REVISION DATE Forward and Policy Statement bd i V L.b 1.0 04/22/92 Chapter 1 Organization 14.0 04/30/97 l Chapter 2 Quality Assurance an No. _ 04 7 33 o 03f 3 3fg7 Chapter 3 Design Control 3.0 06/14/95 Chapter 4 Procurement Document Control 5.0 03/11/97 Chapter 5 Instructions, Procedures, and 5.0 04/30/97 l Drawings Chapter 6 Document Control 6.0 01/17/97 Chapter 7 Control of Purchased Materials, 7.0 03/11/97 Equipment, and Services Chapter 8 Identification and Control of Materials, 5.0 01/17/97 Parts, and Components Chapter 9 Control of Special Processes 5.0 10/25/95 Chapter 10 Inspection 6.0 03/20/96 Chapter 11 Test Control 2.0 03/20/96 Chapter 12 Control of Measuring and Test Equipment 2.0 06/11/93 , Chapter 13 Handling, Storage, Packaging and Shipping 4.0 01/16/95 Chapter 14 Inspection, Test, and Operating Status 1.0 06/11/93 Chapter 15 Nonconforming Materials, Parts or 7.0 03/11/97 Components Chapter 16 Corrective Action 8.0 03/11/97 Chapter 17 Quality Assurance Records 5.0 01/17/97 Chapter 18 Audits 7.0 03/11/97 Appendix A Regulatory Guidance Document 5.0 10/16/96 Appendix B 10CFR50, Appendix B Compliance 0.0 04/01/91 Appendix C Terms and Definitions 5.0 10/07/94
1 4 QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM , PROPOSED CHANGE: Ch:pter i Rev.13 0, paragraphs 4.9.7,4 9.10.b 4.10.7.a & 4.10.7.b j Chapter 5 Rev. 4.0, paragraphs $ 5.1.c and 5.5.1.d The changes correct typographical errors in the above paragraphs (ref. CR 97 0453) 10CFRSO 64 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes " No to the QA Program description previously accepted by the NRC7 Explain:
Chapter 1 Rev.13.0, paragraph 4 9.7 refers the reader to paragraph 4.8.3, this change corrects that to read paragraph 4 9.3 Paragraph 4 9.10.b refers the reader to paragraph 4.8 8, this change corrects that to read paragraph 4.9.8. Paragraph 4.10.7.a refers the reader to paragraphs 4.9.6 a through d & l. this change corrects that to read 4.10.6 a through d & l. Paragraph 4.10.7.b refers the reader to 4 9.6.a through e, this change corrects that to read paragraph 4.10.6.a through e. Chapter 5 Rev. 4.0, paragraphs 5.5.1.c & d refer the reader to paragraph 4.9.6 of Chapter 1, this change corrects that to read paragraph 4.10.6 of Chapter 1. No content cbnnge is associated with these revisions, only typographical changes to reflect correct paragraph numbers. This revision does not lessen any commitments in the previously accepted QAPM.
- 2. If item 1 above is YES, does the proposed change include the Yes No E N/A basis to conclude that the revloed program incorporating the change continues to meet the criteria of 10CFRSO Appendix B and other previously accepted FSAR commitments?
Explain: M 0- Y'Ab # 9? Reviewed By: ' QA'1tepresentative Date RECOMMENDATION:
" Doof sot represent a loosening of commitment and it can be implemented immediately.
Represents a loosening of commitment, however, the change has sufficient basis to demonstrate continued compilence with Appendix 5 and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. O "o'm"p'ilance.
**"'"'*"'"****"**"'*'*h'"*""'"'"***d'*'"'"""""*d Therefore, the chance should not be processed.
c
% 7 Recommended By: QA SupervM Date DEPOSITION:
O Approved forimplementation C Disapproved O Approved for su ittal to the NRC for acceptance
*Y '/ E 7 Approved By: QA Madager Date OAP-018 R6.0 Attachment 7.1 R TYPE: J3.11
CHANGE Changes to correct typographical errors referenced in CR97 0453 BASIS FOR NO REDUCTION OF COMMITMENT Chapter 1 (4.9.7) referred the reader to para. 4.8.3, this change corrected that to read para. 4.9.3 Paragraph 4.9.10.b referred the reader to para. 4.8.8, this change corrected that to read para. 4.9.8. Paragraph 4.10.7 a referred the reader to para. 4.9.6.a through d & I, this change ! corrects that to read 4.10.6.a through d & l. Paragraph 4.10.7.b refers the reader to 4.9.6.a through e, this change corrects that to read para. 4.10.6.a through e. Chapter 6 (6.6.1.c & d) referred the reader to paragraph 4.9.6 of Chapter 1, this change corrects that to read para. 4.10.6 of Chapter 1. No content change was associated with these revisions, only typographical changes to reflect correct paragraph numbers. This revision does not lessen any commitments in the previously accepted QAPM. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 5 Rey.13 Rev. 4 4.9.7 5.5.1.c 4.9.10.b 5.5.1.d-4.10.7 a 4.10.7.b l
+0er g WATERFORD 3 UALITY AS50RANCE CHAPTER 1 REV.13.0 R TYPE: C1.31
= EntomE
'" O PROGRAM MANUAL PAGE: 13 OF 21 4.9.4 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two attornates shall participate as voting members in SRC activities at any one time.
4.9.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advise to the SRC, 4.9.6 The SRC shall meet at leest once per calendar quarter during the initial year of unit operation following fuelloading and at least once per 6 months thereafter. 4.9.7 The quorum of the SRC necessary for the performance of the review and audit function shall consist of a minimum of five members or of not lese than a majority of the composition of members in paragraph 4.8.3 above, whichever is greater. No more than a minority of the members shall have line responsibility for operation of the plant. 4.9.8 The SRC shall be responsible for the review of:
- a. The safety evaluations for (1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actior,a did not constitute an unreviewed safety question;
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59;
- d. Proposed changes to Technical Specifications or the Operating License;
- e. Violations of codas, regulations, orders, Technical Spocifications, license requirements, or of intemal procedures or instructions having nuclear safety significance;
- f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear ssfety;
- g. All REPORTABLE EVENTS;
g WATERFORD 3
*^" ^SSURANC E CHAPTER 1 REV.14.0 R TYPE: C1.31
= Ente'mI o PROGRAM MANUAL PAGE: 13 OF 21 4.9.4 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at aqy one time.
4.9.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advise to the SRC. 4.9.6 The SRC shall meet at least once per calendar quartcr during the initial year of unit operation following funi loading and at least once per 6 months thereafter. 4.9.7 The quorum of the SRC necessary for the performance of the review and audit function shall consist of a minimum of five members or of not less than a majority of the composition of members in paragraph 4.9.3 jf l above, whichever is greater. No mcre than a minority of the members shall have line responsibility for opuration of the plant. 4.9.8 The SRC shall be responsible for the review of:
- a. The safety evaluations for (1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;
, c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59;
- d. Proposed changes to Technical Specifications or the Operating License;
- e. Violations of codes, regulations, orders, Technical Specifications, licence requirements, or of internal procedures or instructions having nuclear safety significance;
- f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nucleLr safety;
- g. All REPORTABLE EVENTS;
g{fN WATERFORD 3 QUALITY ASSilRANCE PROGRAM MANUAL CHAPTER 1 R-TYPE: C1.31 PAGE: 14 OF 21 REV.13.0 t:. All recognized Indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and I. Reports and meeting minutes of the PORC. 4.9.9 The SRC shall report to and advise the Vice President, Operations on areas of responsibility. 4.9.10 Records of SRC activities shall be prepared, approved, and distributed as indicated below;
- a. Minutes of each SRC meeting shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following each meeting;
- b. Reports of reviews encompassed in paragraph 4.8.8 above shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of Chapter 18 shall be forwarded to the Vice President, Operations and to the management positions responsible for the areas audited within 30 days after completion of the audi'. by the auditing organization; 4.10 Plant Operations Review Committee (PORC) 4.10.1 The PORC shall function to advise the General Manager. Plant Operations on all matters related to nuclear safety.
4.10.2 The PORC shall be composed of site management members as assigned, in writing, by the GMPO. The GMPO will also indicate, in writing, the PORC Chahnan. 4.10.31n the absence of the PORC Chairman, the General Manager, Plant Operations will appoint a temporary Chairman. All other alternate members shall be appointed in writing by the PORC Chairmaa to serve on a tomporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
o g WATERFORD 3
"^" ASSURANCE CHAPTER 1 REV.14.0
- Ent N PROGRAM MANUAL R TYPE: C1.31 PAGE: 14 OF 21 1
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and I. Reports and meeting minutes of the PORC.
4.9.9 The SRC shall report to and advise the Vice President, Operations on areas of responsibility. 4.g.10 Records of SRC activities shall be prepared, approved, and distributed as indicated below;
- a. Minutes of each SRC meeting shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following each meeting;
- b. Reports of reviews encompassed in paragraph 4.9.8 above Ml shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of Chapter 18 shall be forwarded to the Vice President, Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization; 4.10 Plant Operations Review Committee (PORC) 4.10.1 The PORC shall function to advise the General Manager, Plant Operations on all matters related to nuclear safety.
4.10.2 The PORC shall be composed of site management members as assigned, in writing, by the GMPO. The GMPO will also indicate, in writing, the PORC Chairman. 4.10.3 In the absence of the PORC Chairman, the General Manager, Plant Operations will appoint a temporary Chairman. All other altemate members shall be appointed in writing by the PORC Chairman to *~ve on a temporary basis; however, no more than two alte,',stes
. sh&
participate as voting members in PORC activities at any one time.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.13.0 PROGRAM MANUAL PAGE: 16 OF 21
- 1. Review of the Security Plan and submittal of recommended changes to the Safety Review Committee; J. Review of the Emergency Plan and submittal of recommende:
changes to the Safety Review Committee;
- k. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PORC meeting;
- l. Review of proposed modifications to the CPC addressable constants based on information obtained through the Plant Computer-CPC data link;
- m. Review of any accidental, unplanned or uncontrolled radioactive release including reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President, Operations l and to the Safety Review Committee;
- n. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL, and major changes to radwaste treatment systems;
- o. Review of the Fire Protection Program and submittal of recommended changes to the Safety Review Committee; and
- p. Review of proposed procedures and changes to procedures which involve an unreviewed safety question as defined in 10CFR50.59; 4.10.7 The PORC shall:
- a. Recommend in writing to the General Manager, Plant Operations, prior to implementation except for temporary changes to procedures as provided in Technical Specification 6.8.3, approval or disapproval of items considered under paragraph 4.9.6 a.
through d. and I;
g WATERFORD 3 CHAPTER 1 REV.14.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 16 OF 21
- 1. Review of the Security Plan and submittal of recommended changes to the Safety Review Committee; J. Review of the Emergency Plan and sutmittal of recommended changes to the Safety Review Committee;
- k. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PORC meeting;
- l. Review of proposed modifications to the CPC addressable constants based on information obtained through the Plant Computer-CPC data link;
- m. Review of any accidental, unplanned or uncontrolled radioactive release including reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President, Operations and to the Safety Review Committee;
- n. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL, and major changes to radwaste treatment systems;
- o. Review of the Fire Protection Program and submittal of recommended changes to the Safety Review Committee; and
- p. Review of proposed procedures and changes to procedures which involve an unreviewed safety question as defined in 10CFR50.59; 4.10.7 The PORC shall:
- a. Recommend in writing to the General Manager, Plant Operations, prior to implementation except for temporary changes to procedures as provided in Technical Specification 6.8.3, approval or disapproval of items considered under paragraph 4.10.6 a 14 l through d and I;
~
g WATERFORD 3 CHAPTER 1 REV.13.0
=Er IW QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 17 OF 21
- b. Pender determinations in writing, prior to implementation except for temporary changes to procedures as provided in Specification 6.8.3, with regard to whether or not each item considered under paragraph 4.9.6 a. through e. constitutes an unreviewed safety question; and
- c. Provide written notification within 24 hours to the Vice President, Operations and the Safety Review Committee of disagreements between the PORC and the General Manager, Plant Operations; however, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
4.10.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Vice President, Operations and the Safety Review Gomrnittee. 4.11 DIRECTOR, DESIGN ENGINEERING 4.11.1 The primary quality related responsibilities of the Director, Design Engineering, (who reports to the Vice President, Engineering, domiciled in Jackson and not part of the Waterford 3 site organization) include:
- a. Being tha design authority for changes to the design basis except for nuclear fuel and core design;
- b. Performing design evaluations to address plant problems;
- c. Maintaining the design configuration documentation in an as-built condition;
- d. Assessing the impact of changes to plant design and operation on the design basis accident analysis;
- e. Supporting plant activities for environmental qualification (EQ);
- f. Reviewing new or changed technical and quality requirements for spare and replacement part requisitions classified as EQ;
- g. Maintaining the Waterford 3 EQ List;
e- Ent Y WATERFORD 3 UALITY ASSURANCE PROGRAM MANUAL CHAPTER 1 R TYPE: C1.31 REV.14.0 PAGE: 17 OF 21
- b. Render determinations in writing, prior to implementation except for temporary changes to procedures as provided in Specification 6.8.3, with regard to whether or not each item considered under paragraph 4.10.6 a through e constitutes an unreviewed safety Ml question; and
- c. Provide written notification withiri 24 hours to the Vice President, Operations and the Safety Review Committee of disagreements between the PORC and the General Manager, Plant Operations; however, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to Technical Specificatloa 6.1.1.
4.10.8 The PORC shail maltdain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities parformed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Vice President, Operations and the Safety Review Committee. 4.11 DIRECTOR, DESIGN ENGINEERING 4.11.1 The primary quality related responsibilities of the Director, Design Engineering, (who reports to the Vice President, Engineering, domiciled in Jackson and not part of the Waterford 3 site organization) include:
- a. Being the design authority for changes to the design basis except for nuclear fuel and core design;
- b. Performing design evaluations to address plant problems;
- c. Maintaining the design configuration documentation in an as-built ,
condition; I
- d. Assessing the impact of changes to plant design and operation on the design basis accident analysis;
- e. Supporting plant activities for environmental qualification (EQ);
- f. Reviewing new or changed technical and quality requirements for spare and replacement part requisitions classified as EQ: 1 1
- g. Maintaining the Waterford 3 EQ List;
\.
1' ; WATERPORD 3 CHAPTER 5 REv. 4.o ; Entergy R.wpE: C1.31 l
- _ QUAUTY ASSLMANCE Page 4 of 5 ;
l Operations PROGRAM MANUAL i i
- b. Chan0es the procedures as described in the PSAR; r
I
- c. Conducts tests or experiments not described in the FSAR: or i d. Creates a condition or conducts an operation which exceeds, or could result in
. exceeding, the limits identified in the Technical Speelfications.
^
5.5 TECHNICAL REVIEW AND CONTROL PROCESS ' 5.5.1 Procedures required by Techn6 cal Speelflestion 6.8.1 and other procedures which affect nuclear safety, as determined by the General Manager Plant Operations, and changes thetelo, shall be reviewed as follows: ;
- a. Each procedure or chan0e shall be independently re', lowed by a quellflod Individual luc; dgble in the area a3ected other than the individual who l i
- prepared the procedure or procedure char,0s. This review shall include a determination of whether or not additional oroes disciplinary reviews are
! necessary, if deemed necessary, the reviews shall be performed by the review personnel of the appropriate discipline (s).
- b. Individuals performing these reviews shall meet the applicable quellfloations of AN81/AN8 3.1 1978, Section 4.0, excluding subsections 4.5.2 and 4.5.3, and be approved to perforin these reviews in a given area by the General Mana0er Plant Operations.
- c. Those procedures and pmgrams spoolflod by pere 0raph 4.9.6 of Chapter 1, and changes in intent therste, shall be reviewed by PORC and approved by the General Manager, Plant Operations prior to implementation.
- d. Those procedures and programs spoolflod by Technical Specification 8.8.1, and
' changes in intent thereto, with the awe of those specified in paragraph ! 4.9.4 of Chapter 1, chall be approved by the appropriate Group Head as specified in station administrative procedures. Review of the procedure or procedure change will include a determination of f i e. whether or not an unreviewed safety question is involved. This determination will be based on the review of a written safety evaluation prepared by a qualified individual, or documentation that a safety evaluation is not required. PORC review, SRC review, and NRC approval of items involving unreviewed safety - questions shall be obtained prior to station approval for implementation.
- f. Wrtiten records of rev6ews shall be prepared and maintained in accordance with this manual.
5.6 PROCEDURE COMPLIANCE 5.6.1 All personnel should be cognizant of their responsibility to adhere to procedures and instruct 6ons. Prior to performing any quellty related activity, all personnel are responsible to ensure that: l
- a. Procedures or instructions have been developed to control the adivity; a .-
w.-= . i. i, , , < .,. m L _ ..,_.-,,.,_--_,_.m ,._m._,.._....-m, ----..--,,--.-A,---,_.,.mw~
4 m' g!- En WATERFORD 3 QUALITY ASSURANCE PROGRAM MANUAL CHAPTER 5 R TYPE: C1.31 pan 8 OF 7 REV. 6.0
- b. Individuals performing these reviews shall meet the applicable qualifications of ANSI /ANS 3.1-1978, Section 4.0, excluding subsections 4.5.2 and 4.5.3, and be approved to perfomt these :
reviews in a given area by the General Manager Plant Operations.
- c. Those procedures and programs specified by paragraph 4.10.6 gl of Chapter 1, and chcnges in intent thereto, shall be reviewed by PORC and approved by the General Manager, Plant Operations ;
prior to implementation. '
- d. Those procedures and g Mirams specified by Technical Specification 6.8.1, am aanges in intent thereto, with the exception of thow specified in paragraph 4.10.6 of Chapter 1, shall be approved by the appropriate Group Head as specified in
}l station administrative procedures,
- e. Review of the procedure or procedure change will include a determination of whether or not an unreviewed safety question is involved. This determination will be based on the review of a written safety evaluation ;,repared by a qualified individual or documentation that a safety evaluation is not required. PORC .
review, SRC review, and NRC approval of items involving unreviewed safe'y questions shall be obtained prior to station approval for impeentation.
- f. Written records of reviews shall be prepared and maintained in accordance with this manual.
5.6 PROCEDURE COMPLIANCE 5.6.1 All personnel should be cognizant of their responsibility to adhere to procedures and instructions. Prior to performing any quality related activity, all personnel are responsible to ensure that:
- a. Procedures or instructions have been developed to control the activity;
- b. They understand the content of the procedure or instruction and are capable of following it without deviation; i
,.,,....,.,,-,,-.m_, . . , . - . , ,.,n,.n_,..,._,- ,,_~.,...n.,,, ,-,.....nn..nn_-.n,
_ {f___ _ _ '. = Y k b i ATTACHMENT ll TO W3F1-98-0013 QAPM Table of Contents Revision 13 Changes affecting QAPM Chapters 1,2,6,7,8, and 15 through 18 to Revisions 12,10, 6, 6, 5, 6, 7, 5, and 6, respectively b E M
g WATERFORD 3 TABi E CF CONTENTS
- Ent QUALITY ASSURANCE PROGRAM MANUAL RIN. 13,0 R-NPE: C1.31 PAGn: 1OF1 TITLE REVISION DATE n n s gni 1 r n Forward and Policy StatergeJ' : d i ULLCy 1. 04/22/92 Chapter 1 Organizatio 12.0 01/17/97 6(//
Chapter 2 Quality A ufus4 Ace Prcd Mi' 10.0 01/17/97 Chapter 3 Design Control 3.0 06/14/95 Chapter 4 Procurement Document Control 4.0 01/16/95 Chapter 5 Instructions, Procedures, and . 4.0 03/20/96 Drawings Chapter 6 Document Control 6.0 01/17/97 Chapter 7 Control of Purchased Materials, 6.0 01/17/97 Equipment, and Services Charatt- 0 Identification and Control of Materials, 5,0 01/17/97 Parts, and Components Chytr 3 Controi of Special Processes 5.0 10/25/95 Chapter 10 Inspection 6.0 03/20/96 Chapter 11 Test Control 2.0 03/20/96 Chapter 12 Control of Measuring and Test Equipment 2.0 06/11/93 Chapter 13 Handling, Storage, Packaging and Shipping 4.0 01/16/95 Chapter 14 Inspection, Test, and Operating Status 1.0 06/1:!93 Chapter 15 Nonconforming Materials, Parts or 6.0 01/17/97 Components Chapter 16 Corrective Action 7.0 01/17/97 Chapter 17 Quality Assurance Records 5.0 01/17/97 i Chapter 18 Audits 6.0 01/17/97 Appendix A Regulatory Guidance Document 5.0 10/16/96 Appendix B 10CFR50, Appendix B Compliance 0.0 04/01/91 Appendix C Terms and Definitions 5.0 10/07/94
1 QUALITY ASSURANCE PROGRAM '
; ,, CHANGE REVIEW FORM _. ;
PROPOSED CHANGE: Chapter 2 Rev. 9.0
- 1) f*evise to address organizational changes regarding transfer of responsibilities for Secunty Department from the General Manager Plant Operations (GMPO), and Pohey 4' Directives from the Director. Nuclear Safety to the Director, Site Support.
v 2) Add in-House Events Analysis (new group responsible for Administration of the Condition Report p,ocess, root e.ause analysis process and trend program which was formerty under the QA Manager) as an organization reporting to the Director. Nuclear Safety.
- 3) Change group name trom Technical Services to Plant Engineenng.
, 4) Elmnate the Safety Revow group from Nuclear Safety organization and change the Quakty Team title to Employee Concems Program The above chariges are being incorporated at this time due to inadvertently faihng to make them when Chapter 1 Rev.11.0 and Chapter 16 Rev. 6 0 were processed 10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitneont Yes *
- No to the QA Program description previously accepted by the NRC?
Explain: , 1) Th3 QAPM was revised to change the responsibihty for Secunty De partment from the GMPO (Section 4 2) and Pohey & Directives from the j Dir:ctor, Nuclear Safety (Section 4.5) to the Director, Site Support (Section 4 4). All commitments were transferred intact for both programs, th)8 change 00es not constitute a lessening of commitment. 2)In-House Events Analysis was formed to administer the Condition Report Process, Root Ca'ise analysis process and trend program (formerty under the QA Manager who reports to the Director, Nuclear Safety). Since this group still rero ts to the Director, Nuclear Safety (Section 4 5), 2 th;re is no reduction of analysis efforts or level of independence and does not constitute a lessening of commitment.
- 3) The name change of Tachnical Services to Plant Engineering (Section 4 2) does not constitute a lessening of commi* ment since all commitments still remain with the GMPO.
- 4) Eliminating the Safety Review group does not constitute a lessening of commrtment because the review / support functions are performed by the
! GRC Review subcommittee. Functions performed by the Quakty Team (Employee Concems) remain (Section 4 5), only the title was changed to reflect more accurately the actrvity that was addressed by the Quakty Team. ! 2. If item 1 above is YES, does the proposed change include the Yes No [ G N/A basis to conclude that the revised program bcorporating the I change continues to meet she criteria of 10CFR50 Appendix B and other previously accepted FSAR commitments? 2- Explain:
\ e- ,
l06m.-- /t WW3 N ,.2l~ Q Reviewed By:- QA Representative Date , RECOMMENDATION: Pa Does not represent a lessening of commitment and it can be implemented immediately. Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. , Represents a lessening of commitment with insufficient basis to determine continued compliance. Therefore, the change should not be processed.
/
/ f.
Recommended By: QA Sud II Date DISPOSITION:
Approved for implementation O Disapproved Approved for subm to the NRC for acceptance o
Q ' r mi j cu~u // O/f/ i
- Approved By: QA Managfr Date OAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11 a
CHANGE Revised to address #1 organizational changes regarding transfer of responsibilities for Security Department from the General Manager Plant Operations (GMPO) (4.2) #2 Policy & Directives from the Director, Nuclear Safety (4.5) to the Director, Site Support (4.4), #3 Added In-House Events Analysis (new group responsible for Administration of the Condition Report process, root cause analysis process and trend program which was formerly under the OA Manager) as an organization reporting to the Director, Nuclear Safety, #4 Changed group name from Technical l' Services to Plant Engineering, #5 Eliminated the Safety Review group from Nuclear Safety organization and changed the Quality Team title to Employee Concerns Program #6 Changed title from Director, Nuclear Safety to Director, Nuclear Safety and Regulatory Affairs. BASIS FOR NO REDUCTION OF COMMITMENT , #1 Transferred responsibility for Security from the General Manager Plant Operations (GMPO) (4.2) to the Director, Site Support (4.4) all commitments were transferred intact, thus this does not constitute a lessening of commitment.
#2 Transferred responsibility for Policy & Directives from the Director, Nuclear Safety (4.5) to the Director, Site Support then to the Manager Site Business Services (4.7 added). There is no lossening of commitment, all commitments were transfected intact.
i
#3 Added in-House Events Analysis under the Director, Nuclear Safety then transferred to Director, Site Support (4.4). All commitments were transferred intact. There is no lessening of commitment.
#4 Changed name of Technical Services under GMPO to Plant Engineering (4.2). This was a name change only all commitments remain with the GMPO.
#5 Eliminated the Safety Review group from the Director, Nuclear Safety (4.5), maintained the functions of the Quality Team and changed the title to Employee Concerns Program, then transferred to the Director, Site Support (4.4). This does not constitute a lessening of commitment because the review / support functions are performed by the SRC Review Subcommittee.
#6 Changed title from Director, Nuclear Safety to Director, Nuclear Safety and Regulatory
; Affairs (5.4.3.g & Attachment 1 #10)
OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 2 Rev.9 4.2 4.4 4.5 5.4.3.g Attachment 1 #10
WATERPORD 3 CHAPTER 2 REV. 9.0
- y Ent9 Fey QUAUTY ASSLRANCE R TYPE
- C1.31 Operations Page 2 of 8
- PROGRAM MANUAL
, 4.o- RESPONSIBluTIES ! 4,1 VICE PRESIDENT, OPERATIONS The Vice President, Operations is responsible for providing overall approval and direction for the
- Waterford 3 Quality Assurance Program.
4 i 4.1.1 Safety Review Committee (SRC) The Safety Review Committee is responsible for functioning as the off site independent review committee. The SRC is responsible for: providing independent review and audit of Waterford 3 operations, reviewing changes or modifications which involve an j unreviewed safety question, and reviewing safety evaluations of changes made to the
- plant and plant procedures under the provisions of 10CFRSO.5g. Additional j responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications.
l 4.2 GENERAL MANAGER, PLANT OPERATIONS [ The General Manager, Plant Operations is responsible for ensuring the development of pmcodures or instructions for the implementation of the following functional units: Plant
- Operations Review Committee (PORC); Operations and Maintenance
- Technical Services; Planning and Scheduling; and Security and General Support. The primary quality related -
responsibilities of the General Manager, Plant Operations are listed in Chapter 1. j 4.2.1 Plant Operations Review Committee (PORC) The PORC is responsible for functioning as the on-site independent review committee, and is responsible for reviewing plant operations items and procedures which are
- submitted to it; and for recommending approval by the General Managier, Plant
~ Operations in accordance with applicable procedures. Additional responsibilities are i listed in Chapter 1 and the Waterford 3 Technical Specifications.
- 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION i
The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs p~ and organizational units: Modification Control, Construction, and Project Management. The primary quality related responsibilities of the Director, Plant Modification and Construction are listed in Chapter 1. L 4.4M' DIRECTOR, SITE SUPPORT i l The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational l units: Site Business Services; Emesgency Planning and Administration; and Management
- Programs and Excellence. The primary quality related responsibilities of the Director, Site 2 Support are listed in Chapter 1.
5 4.5 ' DIRECTOR, NUCLEAR SAFETY 4
- The Director, Nuclear Safety is responsible for ensuring the development and maintenance of l procedures or instructions for the implementation of the following programs and organizational p units: Licensing; Safety Review; Policy and Directivec: Quality Assurance; and Operational Experience Engineenng. The primary quality related responsibilities of the Director, Nuclear j Safety are listed in Chapter 1.
1 a
, - - - ~ - - - . , . . , , - - . .- -
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 R-TYPE: C1.31 REV.10.0 PROGRAM MANUAL PAGE: 2 OF 11 2.3 10CFR50, Appendix B," Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" 3.0 DEFINITIONS 3.1 See Appendix C. 4.0 RESPONSIBILITIES 4.1 VICE PRESIDENT, OPERATIONS l The Vice President, Operations is responsible for providing overall approval and l direction for the Waterford 3 Quality Assurance Program. 4.1.1 Safety Review Committee (SRC) The Safety Review Committee is responsible for functioning as the off-site independent review committee. The SRC is responsible for: providing independent review and audit of Waterford 3 operations, reviewing changes or modifications which involve an unreviewed safety question, and reviewing safety evaluations of changes made to the plant and plant procedures under the provisions of 10CFR50.59. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 4.2 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for ensuring the development of procedures or instructions for the implementation of the following functional units: Plant Operations Review Committee (PORC); Operations; Maintenance; Plant Engineering; Chemistry; Radiation Protection / Safety; 1Q l and Planning and Scheduling. The primary quality related responsibilities of the quality related responsibilities of the General Manager, Plant Operations are listed in Chapter 1.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 R-TYPE: C1.31 REY.10.0 PROGRAM MANUAL PAGE: 3 OF 11 4.2.1 Plant Operations Review Committee (PORC) The DORC is responsible for functioning as the on-site independent review committee, and is responsible for reviewing plant operations items and procedures which are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with applicable procedures. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and orcanizational units: Modification Control, Construction, and Project Management. The primary quality related responsibilities of the Director, Plant Modification and Construction are listed in Chapter 1. 4.4 DIRECTOR, SITE SUPPORT The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency Planning; Quality 3 Assurance; Operational Experience Engineering; in-H.ouse Events Analysis; and Employee Concems Program. The primary quality related responsibilities of the Director, Site Support are listed in Chapter 1. 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS M The Director, Nuclear Safety and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the Licensing unit. The primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are listed in Chapter 1. 3 4.6 TRAINING MANAGER l The Training Manager is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Operations Training; Simulator Training; Maintenance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Training Manager are listed in Chapter 1.
g- Ent WATERFORD 3 QUAUTY ASSURANCE CHAPTER 2 R-TYPE: C1.31 REV.10.0 PROGRAM MANUAL PAGE: 4 OF 11 4.7 MANAGER, SITE BUSINESS SERVICES The Manager, Site Business Services is responsible for ensuring the g development and maintenance of procedures or insurtions for the implementation of Records, Document Control, and Policies and Directives activities. 4.8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The primary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 VICE PRESIDENT, ENGINEERING The Vice President, Engineering reports directly to the Executive Vice President
& Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1.
4.10 VICE PRESIDENT, OPERATIONS SUPPORT t The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technology transfer, and centrallicensing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Information Systems, Supplier QA and Materials, Purchasing and Contracts groups. It is the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program.
4 WATERFORD 3 CHAPTER 2 REV 9.0 O yE ntergy QUAUTY ASSURANCE R WPE: C1.31 Page 5 of 8 Operations PROGRAM MANUAL
- g. Computer Software;
- h. ALARA Program;
- 1. Radiation Protection; 1- ,
J. ATWS; and
- k. Station Blackout.
5.4 PROCEDURES AND INSTRUCTIONS 5.4.1 The individual Entergy Operations organizations assigned responsibilities by the Nuclear Management Manual, Waterford 3 Management Manual, and the QAPM shall be responsible for the development, maintenance, and implementation of procedures and instructions to detail the respective elements of program performance. 5.4.2 The procedure types listed in 5.4.3 have been developed at Waterford 3 to address required aspects of plant management and operations. These procedures will: 4
- s. Implement the policy and direction of the Nuclear Management Manual, Waterford 3 Management Manual, and the QAPM to provide control over quality
- related operations and activities to a degree consistent with their importance to safety;
- b. Provide a clear understanding of the operating philosophy at Waterford 3; and 1
- c. Delineate the responsibilities and authorttles of the Waterford 3 staff.
q
- 5.4.3 The Waterford 3 procedures and instructions contained in this level are the:
- a. Plant Operating Manual;
- b. Quality Assurance procedures;
- c. Site Support procedures;
- d. Design Engineering procedures;
- e. Design Engineering Administrative Manual (DEAM);
l f. Plant Moditication and Construction procedures; 4
- g. Nuclear Safety procedures; and
- h. Nuclear Training procedures. Rl
. 5.5 IDENTIFICATION OF SAFETY RELATED STRUCTURES, SYSTEMS, AND COMPONENTS 5.5.1 The Quality Assurance Program applies to all activities associated with quality related stmetures, systems, and components to an extent commensurate with their importance a to safety. FSAR Table 3.21, Appendix A to this manual, and the Waterford 3 Q-List provide safety related classifications of plant structures, systems, and components and identifies those items sut8ect to 10CFR50 Appendix B requirements.
.~
g WATERFORD 3 CHAPTER 2 REV.10.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 8 OF 11
- e. Design Engineering Administrative Manual (DEAM);
- f. Plant Modification and Construction procedures;
- g. Nuclear Safety and Regulatory Affairs procedures; and 's
- h. Nuclear Training procedures.
5.5 IDENTIFICATION OF SAFETY RELATED STRUCTURES, SYSTEMS, AND COMPONENTS 5.5.1 The Quality Assurance Program applies to all activities associated with quality related structures, systems, and components to an extent commensurate with their importance to safety. FSAR Table 3.2-1, Appendix A to this manual, and the Waterford 3 Q-List provide safety related classifications of plant structures, systems, and components; and identifiy those items subject to 10CFR50 Appendix B requirements. 5.5.2 Procedures provide further guidance for the identification of s6fety and quality related structures, systems, components and related activities to assure that the appropriate level of Quality Assurance program requirements are applied. 5.5.3 Procedures for the preparation and control of procurement documents , provide guidance for spare and replacement part classification determination. These procedures invoke applicable codes, standards, l regulations, FSAR requirements, and the Q-List classifications for determining the classification of spare or replacement parts or materials. 5.6 RESOLUTION OF DISPUTES 5.6.1 Disputes involving quality, arising from a difference of opinion between Entergy Operations departments, are normally resolved via direct interaction between the managers involved. If a satisfactory resolution cannot be reached, the disputes are resolved through higher levels of management. The Quality Assurance Manager should be consulted for disputes involving the Waterford 3 Quality Assurance program interpretation and implementation.
, m -
*d ll Om
- 1, 3 QUALITY ASSURANCE PROGRAM DOCUMENTATION
'.=e
!! s identaitcaten Descnotegn Acorevel and Cc.itrol r
3 et 9 Plant Modification and Construchon A set of pocedures which prescnbe adtvites Prepared by ungnaisnt p A ;* withen Plant Q and resportsabshises within the Plant Modificahon ass Construction. Quality related Procedures Moddication and Construction organization. p Cs shah receive a quahty related review TC
.Neroved by the Diredor, Plant Moddicasson and construchon. Issued and controIIed by Sete O Qr >I Support -
EU E mm><38 d
- 10. Nuclear Safety Procedures A set of procedures which presc'Le adivities Prepared *>y cognizant personnel within Nuclear EWO and responsstmhties witNn tha Nudear Safety Safety QuaWy related procedures shaE receive h organization. a quakty reassed review Approved by the C> W Diredor Nudear Safety or Departrnent Manager >
I issued and contro#e1 by Site Stapport
- 11. Nuc* Jar Training Procedures A sr. of procedures which presenbe adivities Prepared by cxydzant personnel within Nudear and responsibehties within the Nuclear Training Training. Quakty related procedures shes Ortianization receive a quakty related review, Approved by 2 the Manager Nudear Training. Issued and controged by Site Support >2O o
"I .
C
- b. IT D c m9u
*i
_9 u 9
- 2. O w
I
. t OUALITY ASSURANCE PROGRAM DOCUMENTATION ~i Identification Descriotion Anoroval and Control 9
N. 1 D
- 10. Nuclear Safety and A set of procedures which Prepared by cognizant personnel Regulatory Aftairs presenbe activities and within Nuclear Safety and Regulatory Procedures recponsibilities.within the Nuclear Affairs. Quality related procedures Safety and Regulatory Affairs. shall receive a quality related 3 organization. review. Approved by the Director, !
Nuclear Safety and Regulatory Affairs or Department Manager. O issued and controlled by Site 5 c-Business Services. "o f :E o >
- 11. NuclearTraining A set of procedures which Prepared by cognizant personnel within Nuclear Training. Quality
$,N E ,, (
Procedures prescribe activities and l responsibilities within the Nuclear Training Organization related procedures shall receive a quality related review. Approved JE$ zga by the Manager, NuclearTraining. 5 z ** Issued and controlled by Site FS ; Business Services..
- 12. Site Business Services A set of procedures which Prepared by cognizant personnel Procedures prescribe activities and responsibilities within the Site within Site Business Services.
Quality related procedures shall J>2Q Business Services organization. receive a quality related review. of]M>
"' o 4 This includes the Corporate Site based Materials, Purchasing and Approved by the Manager, Site M Business Services with the
*Eh5 og.a w
Contracts department. exception of those pertaining to the ,-4 a ! Materials, Purchasing and Contracts a g group. These exceptions will be < approved by the Manager, Materials, g Purchasing and Contracts with - o concurrence by the Manager, Site Business Services. i i
QUALITY ASSURANCE PROGRAM l CHANGE REVIEW FORM PROPOSED CHANGE:
- 1. R; vise the QAPM to reassign organizational responsibilities of he Director, Nuclear Safety and the Director Site Support.
Responsibilities and functions of the Director, Nuclear Safety to be reassigned to the Director, Site Support are as follows: QA, OEE, lHEA, and Employee concems Program. Responsibilities and functions of the Director, Site Support to be reassigned to th) Manager, Site Business Services are as follows: Administrative Services (changed from Emergency Planning and Administration) and Process and Project Support Programs (previous'y titled Management Programs and Excellerice). The M: nager, Site Business Services reports directly to the Vice President, Operations.
- 2. The Manager of Licensing will be responsible for fulfilling the remaining duties of the Director, Nuclear Safety and reports directly to the Vice President, Operations, until a permanent Director, Nuclear Safety and Regulatory Affairs is named.
- 3. The revision also reflects the title change from
- Nuclear Safety" to " Nuclear Safety and Regulatory Affairs
- 10CFR50,54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes -
No to the QA Program description previously accepted by the NRC? Explain: Chapter 1 Revision 11, paragraphs 4.5.1.c,4.5.1.d 4.5.1 g,4.6.1.e,4 6.1.f. 4.6.1.h,4.6.1.1,4.6.1.k. 4.6.1.n, and 4.6.2 were revised to r;flect the change in functions and responsibilities of the Director, Nuclear Safety and the Director, Site Support. Paragraph 4.8 w:s added to reflect the reassignrnent of responsibilities of the Manager, Site Business Services. The Nuclear Safety title change to Nuclear Safety and Regulatory Affairs was also reflected in paragraphs 4.2.1.d 4.6. and 4.6.1 There is no lessening of commitment associated with the reorganization because site senior management (Vice President, Operations) provides direct ov rsight of the Manager, Site Business Services, Also, the Licensing Manager now reports directly to the Vice President, Op; rations ensunng that those tonctions, responsibilities, and commitments assigned to the Director, Nuclear Safety continue to rec:ive senior managemeni oversight. Nuclear Safety responsibilities assigned to the Director, Site Support were transferred intact and all commitments associated with those functions are maintained. Attachment 1 was also revised to reflect the current org:nization, as d:scussed above the Ucensing Manager is maintaining functions that continue to be assigned to the Director, Nuclear Safety, until a new Director is named. Attachment 1 continues to show the Director, Nuclear Safety and Regulatory Affairs position. Ch:pter 2 Revision 9, paragraphs 4.4 and 4.5 were revised to show the reassigned functions and responsibilities of the virector, Nuclear Safety and the Director, Site Support. Paragraph 4.7 was added to reflect the assigned responsibilities of the Manager, Sita Business Services.faragraph 5.4.3.g and Attachment 1, item 10 were revised to reflect the Nuclear Safety title change to Nuclear Safety and Regulatory Affairs. Chapter 6 Revision 5, paragraph 4.2 was revised to indicate that the Manager, Site Business Services is now responsible for document control activities. Chapter 7 Revision 5, paragraph 5.2.1 was revised to indicate that procurement planning is a shared responsibility between Site Business Services and Operations Support organizations. Chapter 15 Revision 5, paragraph 4.3 was revised to show responsibilities of the Director, Site Support instead of the Director, Nuclear Safety. A new paragraph 4.4 was added to indicate the new Director, Nuclear Safety and Regulatory Affairs title and indicates that the position retains responsibility for initiating Licensee Event Reports. Paragraphs 4.4 and 4.5 were renumbered 4.5 and 4.6 respectively, Chapter 16 Revision 6, paragraph 4.2 was revised in incluca the title change for the Director, Nuclear Safety, Paragraphs 4.2.1.b and 4.2.1.c were also revised (new paragraph 4.3) to reflect the reassignment of responsibilities to the Director, S!?e Support. Subsequent paragraphs were renumbered for consistency. Ch:pter 17 Revision 4, paragraph 4.1 was revised to reflect new responsibility of the Manager, Site Business Services. Chapter 18 Revision 5, paragraph 5.8 was revised to reflect reporting audit data to the Director, Site Support and not the Director, Nuclear Safety. Nona of the above changes are considered to be a lessening of commitment because all commrtments were transferred and or maintained intact with the reassignment of function and responsibilities . Prior to the reorganization the Licen:ing Manager riported to the Director, Nuclear Safety; the Licer. sing Manager now reports (in the interim, until a new Director, Nuclear Safety and R:gulatory Affairs is named.) directly to the Vice President, Operations. The Manager, Site Business Services now reports directly to tha Vice President, Operations.. 2, if item 1 above is YES, does the proposed change include the O Yes No r* NIA basis to conclude that the revised program incorporating tha . change continues to meet the criteria of 10CFR50 Appendix B and other previously accepted FSAR commitments? Explain; f gn /2lY Reviewed By: QA R4resentative Date OAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11
.-________o
RECOMMENDATION: Does not represent a lessening of commitment and it can be implemented immediately. Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, l It should be submitted to the NRC for acceptance prior to implemer tation. Represents a lessening of commitment with insufficient basis to determine continued l compilance. Therefore, the change should not be processed. N '3 / f 94 Recommended By: QA Supe Date DISPOSITION: ia Approved for impleme tion Disapproved Approved for alto the NRC for acceptance IT c5lcy ( l j <J ' Approved By: QA Manager l Date i i J QAP-018 R6.0 Attachment 7.1 R-TYPE: J3.11 Q
l
SUMMARY
As a result of the vacancy of the Director, Nuclear Safety position several organl7ctional changes were enacted by the V;ce President, Operations. As a result of these organizational changes several functions and responsibilities of the Director, Nuclear Safety were transferred to the Director, Site Support. Some responsibilitien and functions of the Director, Site Support were transferred to the Manager, Site Business Services. Additionally during the interim period that the Director, Nuclear Safety position will be vacant the Licensing Manager will report directly to the Vice President, Operations and will be responsible for the functions and responsibilities assigned to the Director, Nuclear Safety. The Manager, Site Business Services, originally reporting to the Director, Site Support, is riow reporting directly to the Vice President, Operations. Because of the above organizational changes the Quality Assurance Program Manual (QAPM) required several changes. Quality Assurance worked with Human Resources representatives to identify the required changes. A 50.54 evaluation was completed to ensure that the changes did not lessen Waterford 3 commitments accepted by the NRC. The majority of the changes were in Chapters 1 (Organization) and 2 (Quality Assurance Program). Changes were also made in Chapters 8,7,15,16,17, and 18. It was determined that the changes t'o the OAPM retained all responsibilities and functions, no commitments were deleted or lessened, The reporting chain for the positions involved remained at the same or higher lever (e.g., Licensing Manager reports directly to the Vice President, Operations vs. reporting to the Director, Nuclear Safety), thus ensuring that the responsibilities associated with those positions retain the same level of senior management oversight. The attached 50.54 evaluation and changed QAPM pages present the required changes in detail.
CHANGE Revise the OAPM to reassign organizational responsibilities of the Director, Nuclear Safety and the Director, Site Support. Responsibilities and functions of the Director, Nuclear Safety to be reassigned to the Director, Site Support are as follows: QA, OEE, lHEA, and Employee concerns Program. Responsibilities and functions of the Director, Site Support to be reassigned to the Manager, Site Business Services are as follows: Administrative Services (changed from Emergency Planning and Administration) and Process and Project Support Programs (previously titled Management Programs and Excellence). The Manager, Site Business Services reports
- directly to the Vice President, Operations.
- The Manager of Licensing will be responsible for fulfilling the remaining duties of the Director, Nuclear Safety and reports directly to the Vice President, Operations, until a permanent Director, Nuclear Safety and Regulatory Affairs is named.
- The revision also reflects a title change only from " Nuclear Safety" to " Nuclear Safety and Regulatory Affairs."
BASIS FOR NO REDUCTION OF COMMITMENT it was determined that the changes to the OAPM retained all responsibilities and functions, no commitments were deleted or lessened. The reporting chain for the positions involved remained , at the same or higher level thus ensuring that the responsibilities auociated with those positions retain the same level of senior management oversight. Chapter 1 Rev.11, paragraphs 4.6.1.e (moved to 4.5.1.e),4.6.1.f (moved to 4.5.1.f),4.6.1.h (moved to 4.5.1.g),4.6.1.1 (moved to 4.5.1.h),4.6.1.k (moved to 4.5.1.i),4.6.1.n (moved to 4.5.1.j) and 4.6.2 (mnved to 4.5.2) were revised to reflect the change in functions and responsibilities from the Director, Nuclear Safety and the Director, Site Support. Paragraph 4.8 was added to reflect the reassignment of responsibilities of the Manager, Site Business Services. Paragraph j 4.5.1,c was moved to 4.8.1.a, paragraph 4.5.1.d was movad to 4.8.1.b and 4.5.1.g.1 was moved to 4.8.1.c and reworded. The Nuclear Safety title change to Nuclear Safety and Regulatory Affairs was also reflected in para. 4.2.1.d,4.6 and 4.6.1. There is no lessening of commitment associated with the reorganization because site senior management (Vice President, Operations) , provides direct oversight of the Manager, Site Business Services (4.8 & 4.2.1.f added). Also, The Licensing Manager now reports directly to the Vice President, Operations ensuring that those functions, responsibilities, and commitments assigned to the Director, Nuclear Safety continue to receive senior management oversight. Chapter 2 Rev. 9, paragraphs 4.4 and 4.5 were revised to show the reassigned functions and responsibilities of the Director, Nuclear Safety and the Director, Site Support. Paragraph 4.7 was added to reflect the assigned responsibilities of the Manager, Site Business Services. Paragraph 5.4.3.g and Attachment 1, item 10 were revised to reflect the Nuclear Safety title change to Nuclear Safety and Regulatory Affairs. Chapter 6 Rev. 5, paragraph 4.2 (moved to 4.3) was revised to indicate that the Manager, Site Business Services is now responsible for document control activities. Chapter 7 Rev. 5, paragraph 5.2.1 was revised to indicate that procurement planning is a shared responsibility between Site Business Services and Operations Support organizations. E_._. __ -__ _ . - _ _ _
Chapter 15 Rev. 5, parcgrcph 4.3 was revis:d to show responsibilities of the Director, Sits Support instsed of the Director, Nucisar Safsty. A n:w paragraph 4.4 was added to indicate tho new Director, Nuclear Safety and Regulatory Affairs title and indicates that the position retains responsibility for initiating Licensee Event Reports. Paragraphs 4.4 and 4.5 were renumbered 4.5 and 4.6 respectively. Chapter 16 Rev. 6, paragraph 4.2 was revised to include the title change for the Director, Nuclear Safety. Paragraphs 4.2.1.b and 4.2.1.c (moved to paragraph 4.3) to reflect the reassignment of responsibilities to the Director, Site Support. Subsequent paragraphs were renumbered for consistency. Chapter 17 Rev. 4, paragraph 4.1 was revised to reflect new responsibility of the Manager, Site Business Services. Chapter 18 Rev. 5, paragraph 5.8 was revised to reflect reporting audit data to the Director, Site Support and not the Director, Nuclear Safety. QAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 2 Chapter 6 Chapter 7 Rev.11 Rev.9 Rev.5 Rev.5 4.2.1.d 4.4 4.2 5.2.1 4.5.1.c 4.5 4.5.1.d 5.4.3.g 4.5.1.g.1 Attachment 1 #10 4.6 4.6.1 4.6.1.e 4.6.1.f 4.6.1.h
- 4.6.1.i 4.6.1.k 4.6.1,n 4.6.2 i Chapter 15 Chapter 16 Chapter 17 Chapter 18 Rev.5 Rev.6 Rev. 4 Rev.5 4.3 4.2 4.1 58 i 4.4 4.2.1.b
, 4.5 4.2.1.c
WATERFORD 3 CHAPTER 1 REV.11.0 UALITY ASSURANCE
-E N PROGRAM MANUAL R-TYPE: C1.31 PAGE: 7 OF 21 4.6 DIRECTOR,, NUCLEAR SAFETY 4.6.1 The primary quality related responsibilities of the Director, Nuclear Safety
- include:
- a. Coordinating and reviewing responses to Nuclear Regulatory Commission matters, as assigned;
- b. Managing the preparation of updates / revisions to the Final Safety Analysis Report and the Technical Specifications;
- c. Managing the Waterford 3 Commitments Management System;
- d. Managing the preparation of responses to IE bulletins, NRC orders, inspection reports, generic letters, information notices, and Notices of Violation;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs; 11
- f. Analyzing conditions for human performance trends and publishing quarterly trend reports;
- g. Reviewing corrective action documents for determination of reportability; .
- h. Interfacing with on-site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors to ensure quality is maintained;
- i. Reviewing plant system problems and performance concerns; J. Reviewing operating abnormalities and Licensee Event Reports; 2 k. Examining plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety ,
as part of the Independent Technical Review function. The
-Independent Technical Review functions include responsibility for:
i g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.11.0 PROGRAM MANUAL PAGE: 8 OF 21
- 1. Making recommendations for improving plant safety
, including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as
, practical;
- l. Maintaining SRC charters;
- m. Performing independent reviews, safety examinations, and other
- review activities in support of the SRC and Technical Specification
- requirements;
- n. Overseeing the activities of the Employee Concerns Program 11 4.6.2 The Director, Nuclear Safety is also responsible for the direction and administration of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance program.
The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively: 2
- 1. Identify quality problems;
- 2. Initiate, recommend or provide solutions through d9signated I channels; and i
- 3. Verify implementation of solutions.
- b. This organizational freedom includes sufficient independence ,
i from cost and schedule when opposed to safety considerations;
g- Ent WATERFORD 3 UALlW ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.12.0
- PROGRAM MANUAL PAGE: 6 OF 21 l l l
- d. Reviewing and processing assigned work authorizations and
! managing services for plant repair, modification, and construction j which is under his jurisdiction; l l e. Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the
- inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction work j prior to acceptance; and i
l g. Coordinating construction tasks involved with outages and ! retrofitting. \ 4.5 DIRECTOR, SITE SUPPORT { 4.5.1 The primary quality related responsibilities of the Director, Site Support 1 include:
- a. Managing the preparation and approval of the Waterford 3 l Emergency Plan and implementing procedures; -
- b. Coordinating the preparation of emergency drill scenarios and
- performance of practice drills; and i
- c. Implementing the Security Plan and Safeguards Contingency Plan; ul
- d. Controlling plant area access;
{ e. Oversight of the administration of the Condition Report process, i root cause analysis and trend programs; M i f. Analyzing conditions for human performance trends and publishing l quarterly trend reports; ] g. Interfacing with on-site and outside organizations such as the i NRC, INPO, Quality Assurance, and equipment vendors to ensure
; quality is maintained;
- h. Reviewing plant system problems and performance concems; i
J 1
. . . . _ .. . . . _ . - . - ~ . __. - _.
g- Ent , WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.12 r PROGRAM MANUAL PAGE 7 OF 21
- i. Examining plant operating characteristics, NRC issuances (includes information Notices), industry advisories, Licensee Event
, Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as part of the Independent Technical Review function. The Independent Technical Review functions include responsibility for:
M
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical;
- j. Overseeing the activities of the Employee Concerns Program; and
- k. Implementing the Fitness For Duty Program 4.5.2 The Director, Site Support is also responsible for the direction and administration of the Quality Assurance Manager and staff, who have the following responsibilities and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance program. 3 The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, recommend or provide solutions through designated channels; and
- 3. Verify implementation of solutions.
t g- Ent WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.11.0 PAGE: 6 OF 21 PROGRAM MANUAL
- e. ',
Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction work prior to acceptance; and
- g. Coordinating construction tasks involved with outages and retrofitting.
4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and performance of practice drills; and
- c. Providing support for records management, including execution of document control and records storage programs;
- d. Coordinating the development, preparation, and maintenance of Waterford 3 pohcies and directives.
- e. Implementing the Security Plan and Safeguards Contingency Plan;
- f. Controlling plant area access; 11
- g. Implementing the Fitness For Duty program, including;
- 1. Reviewing and interpreting presumptive positive test results obtained through the Fitness For Duty program.
m o
f g WATERFORD 3 CHAPTER 1 REV.12.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 11 OF 21 4.7 TRA!NING MANAGER ,
4.7.1 The primary quality re'ated responsibilities of the Training Manager include:
- a. Providing training for Waterford 3 personnel, including training required by regulations, General Employee Training, and training for the Engineering Support Personnel;
- b. Maintaining training records; and
- c. Providing an instructor certification program.
4.8 MANAGER, SITE BUSINESS SERVICES 4.8.1 The primary quality related responsibilities of the Manager, Site Business Services include:
- a. Providing support for records management, including execution of document control and records storage programs;
- b. Coordinating the development, preparation, and maintenance of Waterford 3 policies and directives; g
- c. Providing Medical Review Officer services (reviewing and j interpreting presumptive positive test results) for the Fitness for Duty Program; and
- d. Providing direction to on-site Materials, Purchasing and Contracts group.
I
0. WATERFORD 3 CHAPTER 1 REV.11.0 O" Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1,31 PAGE: 2 OF 21 4.0 RESPONSIBILITIES 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsibility for the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations to ensure that an effective Quality Assurance program is maintained. l 4.1.2 Entergy Operations management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality Assurance program. 4.1.3 Entergy Operations Management is responsible for ensuring that implementing procedures within their department adequately implement Waterford 3 commitments and obligations. 4.2 VICE PRESIDENT, OPERATIONS 4.2.1 The Vice President, Operations is responsible for assuring the development and approval of Waterford 3 quality policies. Reporting to him are the:
- a. General Manager, Plant Operations;
- b. Director, Plant Modification and Construction; ,
I
- c. Director, Site Support;
- d. Director, Nuclear Safety
- e. Trainir.g Manager; and f- Safety' Review Committee.
4.2.2 The Vice President, Operations is responsible for appointing the 3 , Chairman of the Safety Review Committee (SRC). The Vice 11 President, Operations is also responsible for oversight of the SRC. e
e WATERFORD 3 CHAPTER 1 REV.12.0 i e_ g N QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 2 OF 21 4.0 RESPONSIBILITIES 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsibility for
- the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations te ensure that an effective Quality Assurance program is maintained.
4.1.2 Entergy Operations management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality Assurance program. 4.1.3 Entergy Operations Management is responsible for ensuring that i implementing procedures within their department adequetely implement Waterford 3 commitments and obligations. 4.2 VICE PRESIDENT, OPERATIONS l 4.2.1 The Vice President, Operations is responsible for assuring the development and approval of Waterford 3 quality policies. Reporting to him are the:
- a. General Manager, Plant Operations;
- b. Director, Plant Modification and Construction;
- c. Director, Site Support;
- d. Director, Nuclear Safety and Regulatory Affairs; gl
- e. Training Manager;
- f. Manager, Site Business Services; and Ml
- g. Safety Review Committee.
(] WATERFORD 3 E/ Entergy CHAPTER 6 REV. 5.0 QUALITY ASSURANCE Operations R-TYPE- C1.31 PROGRAM MANUAL page 2 of 6 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS 1l 4.1.1 The General Manager, Plant Operations is responsible for ensuring that as-built drawings are utilized for plant operation and maintenance upon completion of a related modification. 4.2 DIRECTOR, SITE SUPPORT 4.2.1 The Director, Site Support is responsible for the development of a document control system which includes procedures and instructions for the processing and distribution of:
- a. The Safety Analysis Report;
- b. The Plant Operating Manual; }l
- c. Design documents, including drawings and specifications;
- d. The Waterford 3 Management Manual;
- e. Fabrication, construction, installation, inspection, test, maintenance, modification, and operation procedures;
- f. Vendor technical manuals and service bulletins;
- g. Safeguards information;
- h. Safety related departmental procedures; and
- i. Other documents as assigned.
i g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 6 R-TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 2OF6 l 4.0 RESPONSIBILITIES 4.1 vENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible for ensuring that as-built drawings are utilized for plant operation and maintenance upon completion of a related modification, el 4.2 D! RECTOR, DESIGN ENGINEERING 4.2.1 The Director, Design Engineering is responsible for the revision and update of controlled drawings and configuration documents to reflect l design changes. 4.3 MANAGER, SITE BUSINESS SERVICES 4.3.1 The Manager, Site Business Services is responsible for the development of a document control system which includes procedures and instructions for the processing and distribution of;
- a. The Safety Analysis Report;
- b. The Plant Operating Manual;
- c. Design documents, including drawings and specifications;
- d. The Waterford 3 Management Manual;
- e. Fabrication, construction, installation, inspection, test, maintenance, modification, and operation procedures;
- f. Vendor technical manuals and service bulletins;
- g. Safeguerris information;
- h. Safety related departmental procedures; and
- i. Other documents as assigned.
WATEME 3 h w eEnt ergy QUALITY ASSURANCE CHAPTER 7 R-TYPE: C1.31 REV. 5.0 Operations PROGRAM MANUAL { Page 4 of 8
- b. A review of the records and performance of vendors who have previously provided items and services similar to the type being procured; or
- c. A survey of the vendor's facilities and/or quality assurance program to determine the vendor's capability to provide a specified service or product which meets design, manufacturing and quality requirements.
5.1.3 Re-evaluation and requalification of vendors on the QSL shall be made on a periodic basis, as specified in applicable procedures. 5.1.4 Suppliers of safety related structures, systems, components, and, services for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21, when applicable, for reporting defects and noncompliances that could create a substantial safety hazard. 5.2 PROCUREMENT PLANNING 5.2.1 Procurement planning is a shared responsibility between the Site Support and Operations Support organizations. 5.2.2 Based on the relative importance, complexity, or quantity of the item or service, planning activities .chall establish the following in accordance with approved prsedures:
- a. The need to perform surveillance (s) of the vendors /subtier vendors activities and/or products during the manufacturing process;
- b. The need to participate in the inspection hold poirit program established by the vendor or to establish Entergy Operations mandatory hold points.;
- c. The identification of documents. such as, qualifications of personnel or procedures to be generated and submitted to Entergy Operations for approval prior to start of work;
~
o. g WATERFORD 3 CHAPTER 7 REV. 6.0
- Ent QUAUTY ASLURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 4OF7 5.1.3 Re evaluation and requalification of vendors on the QSL shall be made on a periodic basis, as specif ed in applicable procedures.
5.1.4 Suppliers of safety related structures, systems, components, and, servicos for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21, when applicable, for reporting defects and noncompliances that could create a substantial safety hazard. 5.2 PROCUREMENT PLANNING 5.2.1 Procurement planning is a shared responsibility between the Site Q Business Services and Operations Support organizations. , 5.2.2 Based on the relative impcrtance, complexity, or quantity of the item or l service, planning activities shall establish the following in accordance with approved procedures:
- a. The need to perform survelliance(s) of the vendors / subtler vendors activities and/or products during the manufacturing process;
- b. The need to participate in the insi+ction hold point program established by the vendor or to establish Entergy Operations mandatory hold points.;
- c. The identification of documents, such as, qualifications of personnel or procedures to be generated and submitted to Entergy Operations for approval prior to start of work;
- d. The identification of schedules, plans, drawings, design documents, test / inspection results, etc., tv be submitted to Entergy Operations for approval or information;
- e. The method for acceptance of items or services by Entergy Operations;
- f. The scope and frequency of audits /surveillances required to monitor performance and/or maintain vendor qualifications;--
I WATERFORD 3 CHAPTER 15 REV. 5.0
, eEntergy QUALITY ASSURANCE R-TYPE: C1.31
~ Operations PROGRAM MANUAL Page 2 of 5 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS I The General Manager, Plant Operations is respcnsible for the nonconformance control system at Waterfo. 4 for material, parts, and components under plant jurisdiction. Mditionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use as is".
4.1.1 PLANT OPERATIONS REVIEW COMMITTEE The PORC is responsible for reviewing safety related nonconformances dispositioned "use-as-is" and " repair" and , recommending approval to the General Manager, Plant Operations. 4.2 DIRECTOR, DESIGN ENGINEERIN7 . The Director, Design Engineering is responsible for reviewing nonconformances with recommended dispositions of "use-as-is" or
" repair", and for evaluating and processing changes to resulting design drawings. The Dir+ctor, Design Engineering is also responsible for dispositioning other nonconformances assigned to -
his organization. 4.3 DIRECTOR, NUCLEAR SAFETY The Director, Nuclear Safety is responsible for: 4.3.1 The review and audit of the nonconformance control system, and for initiating Licensee Event Reports under 10CFR50.73; 4.3.2 The on-site Independent Technical Review function which , includes providing a random independent review of nonconformance dispositions and closures during the operations phase; and 4.3.3 The screening, evaluation, tracking, and reoorting of ' nonconformances to the NRC as required by 10CFR21.
4 g WATERFORD 3 CHAPTER 15 REV. 6.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1,31 PAGE: 2 OF 5 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for the nonconformance centrol system at Waterford 3 for material, parts, and components under plant jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use as-is".
4.1.1 PLANT OPERATIONS REVIEW COMMITTEE The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending approval to the General Manager, Plant Operations. 4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for reviewing nonconformances with recommended dispositions of " repair" or "use-as is", and for evaluating and processing changes to resu! ting design drawings. The D! rector, Design Engineering is also responsible for dispoc:tioning other nonconformances assigned to his organization. 4.3 DIRECTOR, SITE SUPPORT The Director, Site Support is responsible for: 4.3.1 The review and audit of the Corrective Action Program, initiating Licensee Event Reports under 10CFR50.73; 4.3.2 The on site Independent Technical Review function which locludes providing a random independent review of nonconformance dispositions and closures during the operations phase; and Q 4.3.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC as required by 10CFR21. 4.4 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nuclear Safety and Regulatory Affairs is responsible for initiating Licensee Event Reports under 10CFR50.73.
g WATERFORD 3 CHAPTER 16 REV. 6.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 2 OF 5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY 4.2.1 The Director, Nuclear Safety is responsible for:
- a. Assuring the performance of reportability reviews of Condition Ql Reports (CRs) in accordance with 10CFR50.73 and 10CFR21;
- o. Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process el aments are adequately implemented; and
- c. Oversight of the administration of the Condition Report process, g root causo analysis and trend programs.
4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible for:
- a. Assuring that procedures are developed and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program;
- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
4.4 QUALITY ASSURANCE MANAGER 4.4.1 The Quality Assurance Manager is responsible for:
- a. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; Ql
E I g WATERFORD 3 CHAPTER 16 REV 7.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 2 OF 5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS l I 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is responsible for:
- a. Assuring the performance of reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21, 4.3 DIRECTOR, SITE SUPPORT
- a. Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented; and Z
- b. OversipSt of the administration of the Condition Rep::rt process, root cuse analysis and trend programs.
4.4 DIRECTORS AND MANAGEPS 4.4.1 Directors and Managers are responsible for: I
- a. Assuring that procedures are developed and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; and
- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
4.5 QUALITY ASSURANCE MANAGER 4.5.1 The Quality Assurance Manager is responsible for: I
e' WATERFORD 3 OEntergy QUALITY ASSURANCE CHAPTER 17 REY. 4.0 Operatione R-TYPE: C1.31 P110 GRAM MANUAL Page 1 of 5 TITLE: QUALITY ASSURANCE RECORDS EFFECTIVE DATE: 01/16/95 PREPARED B ldt2 DIRECTOR, NUCLEAR SAFETY: . l' QA MANAGE
,r - -
VICE PRESIDENT, OPERATIONS: 1 h 1.0 PURPOSE 1.1 Quality assurance records ne those completed records that furnish documented evidence of the quality of items or of activities affecting quality and those records required by the Technical Specifications. This chapter defines requirements for the control of quality assurance records.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.88, Revision 2, October 1976 (which endorses ANSI N45.2.9-1974, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants." 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants.") 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES iI 4.1 DIRECTOR, SITE SUPPORT The Director, Site Support is responsible for: 4.1. l _ Assuring the preparation of procedures for the execution of f a document control and records storage program; and i
c' g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 17 R TYPE: C1.31 REV.5.0 PROGRAM MANUAL PAGE: 1OF5 TITLE: QUALITY ASSURANCE RECORDS EFFECTIVE DATE: 01/17/97 PREPARED BY: dI ///7[k DIRECTOR, SITE SUPPORT: / ~, QA MANAGER: )(4 VICE PRESIDENT, OPERATIONS: M- - - V I 1.0 PURPOSE 1.1 Quality assurance records are those completed records that furnish documented evidence of the quality of items or of activities affecting quality and those records required by the Technical Specifications. This chapter defines requirements for the control of quality assurance records. 20 REFERENCES 2.1 USNRC Regulatory Guide 1.88, Revision 2, October 1976 (which endorses ANSI N45.2.9-1974, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants" 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINiil0NS 3.1 See Appendix C. 4.0 RESPONSIBILITIES 4.1 MANArER, SITE BUSINESS SERVICES The Manager, Site Business Services is responsible for: g 4.1,1 Assuring the preparation of procedures for the execution of a document control and records storage program; and
WATERPORD 3 CHAPTER 18 REV. 5.0 y Entergy QUAUTY ASSURANCE R TYPE: C1.31 Page 6 of 6 Operations PROGRAM MANUAL 5.7.3 At any time when required response dates or proposed implementation dates cannot be ; reasonably met, the audited organization shall develop a response, advising the QA i Manager or appropriate supervisor of the new response date. I 5.8 ANALYSIS OF AUDIT DATA Audit data shall be analyzed by the Quality Assurance Manager or appropriate supervisor, who shall report any significant quality problems, including the need for re audit of deficient areas, to the Director Nuclear Safety and the Vlos President, Operations. 5.9 PROCESS SURVEYS (SURVEILLANCES) 5.9.1 Entergy Operations Quality Assurance may conduct process surveys (surveillances) to verify that an hem or activity comorms to specified requirements. These process surveys (surveillanoes) shall supplement regular audits, They are usually limited in scope, and usually involve:
- a. A specific activity being performed;
- b. A procedure or portion of a procedure; or
- c. A specific area within a program.
5.9.2 Distribution of process survey (surveillance) reports include the appropriate Quality Assurance manager and the affeded organization. 5.10 RECORDS < Audit records shall include audit plans, reports, written replies, and documentation of completion of corrective action. Other dot e mtation, such as checklists, may be retained as quality records as necessary to suppe . .udit results. 6.0 ATTACHMENTS None
,my.-- - . - . -r.-. - , . -a ---w,-. p. , , . - - -,w-,. n..c.w ,.,-. .c x--- % ,._m .- -
,s -w.
g WATERFORD 3 QUALITY ASSURANCE CHAPTER 18 R TYPE: C1.31 REV, 6.0
== EnteW, PROGRAM MANUAL PAGE: 8 OF 8 i
5.7.3 At any time when required response dates or proposed implementation dates cannot be reasonably met, the audited organization shall develop a response, advising the QA Manager or appropriate supervisor of the new response date. 5.8 ANALYSIS OF AUDIT DATA Audit data shall be analyzed by the Quality Assurance Manager or appropriate supervisor, who shall report any significant quality problems, including the need for re-audit of deficient areas, to the Director, Site Support and the Vice gl President, Operat:ons. 5.9 PROCESS SURVEYS (SURVEILLANCES) 5.9.1 Entergy Operations Quality Assurance may conduct process surveys (surveillances) to verify that an item or activity conforms to specified requirements. These process surveys (surveillances) shall supplement regular audits. They are usually limited in scope, and usually involve:
- a. A specific activity being performed;
- b. A procedure or portion of a procedure; or
- c. A specific area within a program.
5.9.2 Distribution of process survey (surveillance) reports include the appropriate Quality Assurance manager and the affected organization. 5.10 RECORDS Audit records shall include audit plans, reports, written replies, and documentation of completion of corrective action. Other documentation, such as checklists, may be retained as quality records as necessary to support audit results. 6.0 ATTACHMENTS None
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE: Chapter 8 Rev. 4.0 Add references 2.1,2.2 & 2.3 also add para. 5.2.2. 5.3.3. 5.3 3.1,5.3.3 2 & 5.3.4 to clanfy matenal traceability requirements. 10CFR60.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes ** No to the QA Program description previously accepted by the NRC?
Explain: The cdded refereness and paragraphs were included to provide guidance in the area of material traceability l requirements based on regulations, ASME Codes and ASTM standards committed to by Waterford 3. Thme additions are not considered a lessening of commitment. l
- 2. If item 1 above is YES, does the proposed change include the '
basis to conclude that the revised program incorporating the Yes O No N/A change continues to meet the criteria of 10CFR60 Appendix B and other previously accepted FSAR commitments? Explain: Reviewed By: 862<ML QA Repfosentative 9ho/s c Date RECOMMENDATION: Does not represent a lessening of commitment and it can be implemented immediately. Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compilance with Appendix B and other FSAR commitment:. Therefore, it should be submitted to the NRC for acceptance prior to implementation. Rs presents a lessening of commitment with Insufficient basis to determine continued compliance. Therefore, the change should not be processed. AL A Am-. ////3/% Recommended By: QA Supervisor Date DISPOSITION:
** Approved for implementation Disapproved Approved for sub I to the NRC for acceptance MM O ///o /f(
Approved By: QA MaEagerl Date QAP 018 R6.0 Attachment 7.1 R. TYPE: J3.11
-CHANGE Added references and paragraphs to clarify material traceability requirements.
BASIS FOR NO REDUCTION 0F COMMITMENT The added references and paragraphs were included to provide guidance in the area of material traceability requirements based on regulations, ASME Codes, and ASTM standards committed to by Waterford 3. These additions are not considered a lessening of commitment. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 8 Rev. 4 2.1
- 2.2 2.3 5.2.2 5.3.3 5.3.3.1 5.3.3.2 5.3.4 i
t N e
WATERFORD 3 v/ Entergy CHAPTER 8 REV. 4.0 QUALITY ASSURANCE Operations R-TYPE: 01.31 PROGRAM MANUAL p,g,3 of 4 TITLE: IDENTIFICATION AND CONTROL OF EFFECTIVE DATE: 01/16/95 MATERIALS. PARTS AND COMPONENTS PREPARED BY <
. DIRECTOR, NUCLEAR SAFETY: be.(I '
QA MANAGER Oo__.ff VICE PRESIDENT, OPERATIONS: db_ l.0 PL'RPOSE Idtntification and control of safety related materials, parts, and comptnents are acccmplished in accordance with approved procedures and apply to materials, parts, or components in all stages of fabrication, storage, installation, use, or removal from use. This chapter defines requirements for the identification and control of materials, parts, and components.
2.0 REFERENCES
None 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES AI 4.1 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for verifying adherence to applicable procedures for the identification and control of materiais, parts, and components through the performance of periodic audits, surveillan:es, and inspections.
t g WATERFORD 3 CHAPTER 8 REV. 5.0
- Entergy QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 1OF5 TITLE: IDENTIFICATION AND CONTROL EFFECTIVE DATE: 01/17/97 ,
OF MATERIALS PARTS AND COMPONENTS PREPARED BY: (c /MMt DIRECTOR, SITE SUPPORT: m-QA MANAGER: m d4 VICE PRESIDENT, OPERATIONS: n I i 1.0 PURPOSE , identification and control of safety related materials, parts, and components are accomplished in accordance with approved procedures and apply to materiale, parts, or components in all stages of fabrication, storage, installation, use, or removal from use, i This chapter defines requirements for the identification and control of materials, parts, and components.
2.0 REFERENCES
2.1 10CFR50.55a 2.2 ASME Boller and Pressure Vessel Code Section lll 2 4 2.3 10CFR50 Appendix B 4 30 DEFINITIONS 4 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 QUAllTY ASSURANCE MANAGER The Quality Assurance Manager is responsible for verifying adherence to applicable procedures for the identification and control of materials, parts, and components through the performance of periodic audits, surveillances, and inspections.
WATERFORD 3 p()Entergy QUALITY ASSURANCE CHAPTER 8 REV. 4.0 Operations R-TYPE: C1.31 PROGRAM MANUAL Page 3 of 4 3 5.1.2 When identification markings are employed, they shall be clear, unambiguous, indelible, and not detrimental to the service life of the item. 5.1.3 The inclusion of identification requirements in desigr . documents shall be checked during design verification by , the design organization. 5.1.4 Items of production (batch, lot, component, part, etc.) shall be identified from the initial receipt or fabrication of the item up to and including installation and use. This identification shall relate the item to applicable design or other specifying documents. 5.1.5 Procedures shall include provisions to prevent the use of incorrect or defective items by requiring that identification be maintained either on the ite.n or on records traceable to the item. The identification of materials, parts, and components shall be verified and documented prior to release from storage areas to ensure that only correct and accepted items are used and installed. 5.2 TRACEABILITY 5.2.1 Inventory and issuance controls shall be established to ensure material traceability to storage and plant locations. < 5.3 MAINTAINING IDENTIFICATION AND TRACEABILITY 5.3.1 Procedures shall be established and maintained to pre ride continued cross-referencing between the various identifications that have been used for traceability during an item's life (i.e , between the Architect Engineer's system, the NSSS supplier's system, manufacturer's systems, and the Waterford 3 Station Information Management System)
..rder to en:ure continued retrievability of pertinent re. ds.
g WATERFORD 3 QtJALITY ASSURANCE CHAPTER 8 R TYPE: C1.31 REV.5.0
= EntebiE PROGRAM MANUAL PAGE: 3 OF 5 5.1.2 When identification markings are employed, they shall be clear, unambiguous, indelible, and not detrimental to the service life of the item.
5.1.3 The inclusion of identification requirements in design documents shall be i checked during design verification by the design organization. 5.1.4 Items of production (batch, lot, component, part, etc.) shall be identified from the initial receipt or fabrication of the item up to and including installation and use. This identification shall relate the item to applicable design or other specifying documents. 5.1.5 Procedures shallinclude provisions to prevent the use of incorrect or defective items by requiring that identification be maintained either on the item or on records traceable to the item. The identification of materials, parts, and components shall be verified and documented prior to release from storage areas to ensure that only correct and accepted items are used and installed. 5.2 TRACEABILITY 5.2.1 Inventory and issuance controls shall be established to ensure material traceability to storage and plant locations. 5.2.2 Procedures shall be established and maintained to ensure that material identification is specified on procurement documents. Since marking requirements vary between specifications for different materials and 2 construction codes, procedures must be established to ensure material to be used has been purchased in accordance with the requirements of the proper specification and construction code for the application. 5.3 MAINTAINING IDENTIFICATION AND TRACEABILITY 5.3.1 Procedures shall be established and maintained to provide continued cross-raferencing between the various identifications that have been used for traceability during an item's life (i.e., between the Architect Engineer's system, the NSSS supplier's system, manufacturer's systems, and the Waterford 3 St6ilon Information Management System) in order to ensure continued retrievability of pertinent records. 5.3.2 Procedures shall be established and maintained for the control of item identification consistent with the planned duration and conditions of storage, such as:
A WATERFORD 3 ()Entergy QUALITY ASSURANCE CHAPTER 8 R-TYPE: C1'31 REV. 4.0 Operations PROGRAM MANUAL p g, 4 or 4 5.3.2 Procedures shall be established and maintained for the control of item identification consistent with the planned duration and conditions of storage, such as:
- a. Provisions for the maintenance or replacement of markings due to damage during handling or aging;
- b. Protection of markings on items subject to excessive deterioration due to environmental exposure; and
- c. Provisions for updating existing plant records.
5.4 LIMITED LIFE ITEMS 5.4.1 Items having limited shelf or operating life shall be identified and controlled to preclude the use of items whose shelf or operating life has expired. Use of such items beyond the specified limits shall be evaluated and documented justification provided. 6.0 ATTACHMENTS None i
/ g WATERFORD 3 CHAPTER 8 REV.5.0
- EntemV v'
QUALITY ASSURANCE R TYPE: C1.31 ; PROGRAM MANUAL PAGE: 4 OF 5 {
- a. Provisions for the maintenance or replacemmt of markings due to damage during handling or aging;
- b. Protection of markings on items subject to excessive deterioration due to environmenta! exposure; and
- c. Provisions for updating existing plant records.
5.3.3 Identification of the item shall be maintained by heat number, part number, serial number, or other appropriate means, either on the item or on records traceable to the item, throughout fabrication, erection, installation, and use of the item, All means of treceability of material shall be maintained to the maximum extent possible. Where identification or markings must be destroyed, hidden or removed from an item, traceability must be maintained to documents and records associated with the material. 5.3.3.1 Class 1. 2 or 3 Code material: Where bulk material will be cut, each piece of material shall be marked to include all means of traceability to the maximum extent possible. The marking shall include the material specification and grado, the heat number or heat code. For class 1,2 or 3 Code material with less than 1 inch in any direction available for marking, the item must be packaged in a container that is marked with the material specification and grade and the heat number or heat code. 5 5.3.3.2 Non-Code material: Where bulk material will be cut, each piece of material should be marked for traceability to the stockcode, purchase order and Material Receiving Inspection Report. 5.3.4 Stamping is allowed on 1/4" or thicker material, if Idantification of material by metal stamping is performed, low stress stamps (sometimes referred to as blunt nosed or round faced stamps) with minimum radius of 1/32" shall be used. QA (not other department employees acting as inspectors) is the only group allowed to use interrupted dot die stamps. When vibrating marking tools are used, they shall be fitted with carbide marking tip or equivalent and shall be designed to provide a rounded impression not to exceed 0.010 inches in depth. Etching shall not be performed on nickel alloys or on weld areas or sensitized areas of stainless steel. Electric are markers shall not be used.
t
! J 4
i t i 1- [ A E
?
4 r 4 i 1-1 l 4 ATTACHMENT V TO W3F198-0013 4 > . QAPM Table of Contents Revision 16
- Changes affecting QAPM Chapters 1 through 18 along with Appendices A, B,& C to ,
i Revisions 15,12,4,6,6,7,8,6,6,7,3,3,5,2,8,9,6,8,6,1, and C, respectively 4 a v 4 i 0 l- .i Y
- i i
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7 . , - - . , , . . - . .,-,..-...,,..,,.m___,_____.,. . , _ , ,, _ . , , .._, _._,.r.,.-~.. ..r_.,--_...,
g WATERFORD 3 TABLE OF CONTENTS
- Entergy QUAUTY ASSURANCE q rPPEC$AH WHJAL REV. 16.0 R TYPE: C1.31
, 1 \ TI l
) PAGE: 1OF1 TITLE REVISION DATE Forward,and Policy StatOfibRh' No. 1.0 04/22/92 Chapter 1 Organization 15.0 06/04/97 Chapter 2 Quality Assurance Program 12.0 06/04/97 Chapter 3 Design Control 4.0 06/04/97 Chapter 4 Procurement Document Control 6.0 06/04/97 Chapter 5 Instructions, Procedures, and 6.0 06/04/97 Drawings Chapter 6 Document Control 7.0 06/04/97 Chapter 7 Control of Purchased Materials, 8.0 06/04'97 Equipment, and Services Chapter 8 Identification and Control of Materials, 6,0 06/04/97 Parts, and Components Chapter 9 Control of Special Processes 6.0 06/04/97 Chapter 10 Inspection 7.0 06/04/97 Chapter 11 Test Control 3,0 06/04/97 Chapter 12 Control of Measuring and Test Equipment 3.0 06/04/97 Chapter 13 Handling, Storage, Packaging and Shipping 5.0 06/04/97 Chapter 14 Inspection. Test, and Ope.ating Status 2.0 06/04/97 Chapter 16 Nonconforming Materials, Parts or 8.0 06/04/97 Components Chapter 16 Corrective Action 9.0 06/04/97 Chapter 17 Quality Assurance Records 6.0 06/04/97 Chapter 18 Audits 8.0 06/04/97 Appendix A Regulatory Guidance Document 6.0 06/04/97 Appendix B 10CFR50, Appendix B Compliance 1.0 06/04/97
. sppendix C Terms and Definitions 6.0 06/04/97
. f
. 4 Page 1 of 3 l 1 QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PREPOSED CHANGE:
- 1. Revise the QAPM to renect organization changes assoc.ated with the appointment of the Director Quality.
Re assign functions fro,m the Menager, Site Business Services to the Director, Site Support. Denne 'periodicily' as related to management assessments of the QA Program as 'not to exceed 24 months?
- 2. The Director Quality is a new position, responsible for the Quality Assurance organization and reports directly to the Vice President, Operations. ,The Manager, Site Business Services will again report to the Director, Site Support instsad of the Vice President, Operations.
- 3. The title of the Training Manager has been changed to Director, Training; the reporting chain remains the same, direct to the Vice President, Operations.
10CFR60.64 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes ** No to the QA Program description previously accepted by the NRC?
Explain: See Attached
- 2. If item 1 above is YES, does the proposed change include the O Yes No ** NIA basis to conclude that the revised program incorporating the change continues to meet the criteria of 10CFR60 Appendix B and other previously accepted FSAR commitments?
Explain: Reviewed By: W ou - G. . % L QA Representative 5/9 / q , Date RECOMMENDATION:
** Does not represent a lessening of commitment and it can be implemented immediately.
Represents a lessening of commitment, however,the change has sufficient basis to O demonstrate coa $ued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. Represents a lessening of commitment with Insumclent basis to determine continued O compilance. Therefore, the change should not be processed. L - 9 '? Recommended By: QA SupMoNr # ' 'Date DISPOSITION:
** Approved for implementation O Disapproved O Approved for submittal to the NRC for acceptance' Approved By:
YtWNb~ QA M6 nager - W5Y97 Date Attachment 7.1 R TYPE: J3.11 QAP-018 R6.0
Page 2 of 3 Chapter 1. Rev.14.0 p. . igraph 4.2.1,4.5.1,4.7. 4.8, & Attachment 1 Added the Director, Quality and changed Training Manager title to Director, Training. The Manager, Site Business Services was removed because all quality related functions associated with this position have been reassigned to the Director, Site Support. No reduction of commitment results from this revision because all functions and responsibilities affected by the revision continue to be fulfilled at the same or higher management level, i.e., Quality Assurance now reports directly to the Vice President, Operations whereas before the QA organization reported to the Director, Site Support. Chapter 2, Rev.11.0 paragraph 4.4,4.6, 4.7, 5.6.1, 5.6.2, 5.7.2, 5.9.1, Attachment 1; Quality Assurance functions were removed from section 4.4, Director, Site Support and relocated to section 4.6, Director, Quality. Also, section 4.4 was revised to show that Site Business Services again reports to the Director, Site Support. Section 4.7 is now titled Director, Training. Section 5.6.1,5.6.2, and 5.7.2 were revised to reflect the title of the Director, Quality and not QA Manager. Section 5.9.1 was revised to define periodically as "not to exceed 24 months." Attachment 1, Item 5 was revised to reflect the title of the QA Manager to Director, Quality. Chapter 3, Rev. 3.0 paragraph 4.4; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 5, Rev. 5.0 paragraph 4.2; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 6, Rev. 6.0 paragraph 4.3; Section was revised to show that the Director, Site Support is again responsible for the functions previously assigned to the Manager, Site Business Services. This realigns the organization to the same that existed after the late December,1996 organization change that resulted from the resignation of the Director, Nuclear Safety and was reflected in Revision 5 of this chapter. Chapter 7. Rev. 7.0 paragraphs 4.4; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 8, Rev. 5.0 paragraph 4.1; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 9 Rev. 5.0 paragraphs 4.3,5.4.1; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality.
Page 3 of 3 Chapter 10 Rev. 6.0 paragraphs 4.3,5.1.2.c. 5.3.3, & 5.4; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 12, Rev. 2.0 paragraphs 4.3; (Editorial) Title was changed froni Quality Assurance Manager to Director, Quality. Chapter 13, Rev. 4.0 paragraph 4.3; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 14, Rev.1.0 paragraph 4.2; (Editorial) Title was changed from Quality Assurance Manager to Director, Quality. Chapter 15, Rev. 7.0 paragraph 4.3 & 4.4; Section 4.3 was deleted, the responsibility assigned to the Director, Site Support is now l reflected in section 4.4 and is assigned to the Director, Quality.. Chapter 16, Rev. 8.0 paragraph 4.3,4.5, & 5.2; Section 4.3 and 4.5 were revised to indicate that the Director, Quality now has the responsibility formerly assigned to the Director, Site Support. Section 5.2 was revised to show the title change from Quality Assurance Manager to Director, Quality. J Chapter 17, Rev. 5.0 paragraph 4.1; Revised to show that the Director, Site Support now has the responsibilities formerly assigned to the Manager, Site Business Services. Chapter 18, Rev. 7.0 paragraph 4.2, 5.3.1, 5.6.3.a, 5.6.5, 5.7.3, 5.8, & 5.9.2; 'Editoriel) Title was changed from Quality Assurance Manacor to Director, Quality. All 18 Chapters and Appendix A, B, & C; (Editorial) Signature blocks for each chapter were revised to reflect the organization change from QA Manager to Director, Quality. None of the above revisions are considered to be a lessening of commitment because all commitments were transferred and or maintained intact with the reassignment of functions and responsibilities. Functions and esponsibilities continue to be assigned at the same or higher level of management.
4 Amendment 18 50.54 Pago 3a based on comments received Chapter 1. Rev.14.0 para. 4.5.h (Editorial) Changed the word Directives to Procedures, the Management Manual no longer contains Directives. Chapter 2, Rev.11.0 Attachment 1 #3,10, & 12
#3 removed the word Directives from the Description section (Management Manual no longer contains Directives); (Editorial) #10 - removed "...or Department Manager" from under the Approval and Control section (removal of QA Manager from under Nuclear Safety & Regulatory Affairs) #12 - deleted entire section and moved reference to MP& C under #8 Site Support Procedures (Site Business Services again reports to the Director, Site Support under recent organization change) .
None of the above changes are considered a lessening of commitment, all functions and/or responsibilities continue to be implemented. Reviewed By: Oh b- ac 5' 2 ~7['7 7
~
QA Representative ' Dats Recommended By: ( 27 /9 ) QA Supervisor i ~ Date Approved By:
.i 1 f/
Dir6ctor, Qi,iality /Date'
. - - _ - - = _ . -.-_-_- _ - _ - -- ____ - - _-
CHANGE Revised OAPM to reflect organization changes associated with the appointment of the Director , Quality. All chapters were revised in signature block area to reflect this change. Re assigned functions from the Manager, Site Business Services to the Director, Site Support. Defined
" periodically" as related to management assessments of the OA Program as "not to exceed 24 months." The Director, Quality is a new position, responsible for the Quality Assurance organization and reports directly to the Vice President, Operations. The Manager, Site Business Services will again report to the Director, Site Support instead of the Vice President, 1
Operations. The title of the Training Manager has been changed to Director, Training, the reporting chain remains the same, direct to the Vice President, Operations. BASIS FOR NO REDUCTION OF COMMITMENT Chapter 1 Rev.14 (4.2.1) and (Attachment 1) added Director, Quality (4.2.1.e) and moved responsibilities back from Director Site Support (4.5.2) to (4.7), changed Training Manager (4.2.1.e) i (moved to 4.2.1.f) and (4.7) to Director, Training (4.8). Deleted Manager, Site Business Services (4.8) l and moved all quality related functions associated with the position to the Director Site Support (4.5.1. g, h,1). (4.8.1.b) (moved to 4.5.1.h) Changed the word Directives to Procedures, the Management , Manual no longer contains Directives. Chapter 2 Rev.11 QA functions moved from Director, Site Support (4.4) to Director, Quality (4.6) Section 4.4 was also revised to show that Site Business Services (4.7) again reports to Director, Site Support @.4). Changed title from Manager, Training (4.6)(moved to 4.7) to Director, Training. (5.6.1, 5.6.2 & 5.7.2 & Attachment 1 Item 5) revised to reflect title change from QA Manager to Director, Quality. (5.9.1) revised to define periodically as "not to exceed 24 months." , (Attachment i ltem 3) removed word Directives from description, Management Manual no longer contains Directives) (ltem
- 10) removed "...or Department Manager" from under the Approval and Control Section (removal of OA Manager from under Nuclear Safety & Regulatory Affairs (Item 12) deleted entire section and moved references to MP&C under #6 Site Support Procedures (Site Business Services again reports to the Director, Site Support).
Chapter 3 Rev. 3 (4.4) changed QA Manager to Director, Quality. Chapter 5 Rev. 5 (4.2) changed QA Manager to Director, Quality. Chapter 6 Rev. 6 (4.3) Section revised to show that the Director, Site Support is again responsible for
- the functions previously assigned to the Manager. Site Business Services.
Chapter 7 Rev. 7 (4.4) changed QA Manager to Director, Quality. Chapter 8 Rev 5 (4.1) changed QA Manager to Director, Quality. Chapter 9 Rev. 5 (4.3 & 5.4.1) changed QA Manager to Director, Quality. Chapter 10 Rev. 6 (4.3,5.1.2.c,5.3.3 & 5.4) changed QA Manager to Director, Quality. Chapter 12 Rev. 2 (4.3) changed QA Manager to Director, Quality. Chapter 13 Rev. 4 (4.3) changed QA Manager to Director, Quality. Chapter 14 Rev.1 ( 4.2) changed QA Manager to Director, Quality. Chapter 15 Rev. 7 (4.3) deleted, responsibilities assigned to the Director. Site Support is now reflecte in section 4.4 and is assigned to the Director. Quality. Chapter 16 Rev. 8 (4.3 & 4.5) revised to indicate that the Director, Quality now has the responsibility formerly assigned to the Director, Site Support. (5.2) changed QA Manager to Director, Quality. Chapter 17 Rev. 5 ( 4.1) revised to show that the Director,-Site Support now has the responsibilities formerly assigned to the Manager, Site Business Services. Chapter 18 Rev. 7 (4.2, 5.3.1, 5.6.3.a 5.6.5, 5.7.3, 5.8 & 5.9.2) changed QA Manager to Director, Quality. Chapters 1 - 18 and Appendix A, B & C Signature blocks revised to refL~t change from OA Manage to Director, Quality.
None of tha abova rcvisions ara consid: red to be a 1:ss ning of commitm:nt b:c: usa cll commitm:nt w:ro trcnsf:rred cnd or maint:In:d intact with tha rcassignm:nt of functions end responsibiliti:s. Functions and responsibilities continue to be assigned at the same or higher level of management. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 2 Chapter 3 Chapter 5 Chapter 6 Rev.14 Rev.11 Rev.3 Rev.5 _Rev.6 4.2.1 4.4 4.4 4.2 4.3 4.2.1.e 4.6 4.5.2 4.7 4.7 5.6.1 4.8 5.6.2 4.8.1.b 5.72 Attachment 1 5.9.1 Attachment 1 (#3,5,10, & 12) Chapter 7 Chapter 8 Chapter 9 Chapter 10 Rev.7 Rev.5 Rev.5 Rev.6 4.4 4.1 4.3 4.3 5.4.1 5.1.2.c 5.3.3 5.4 Chapter 12 Chapter 13 Chapter 14 Chapter 15 Chapter 16
.Rev. 2 Rev. 4 Rev.1 - Rev. 7 Rev.8 4.3 4.3 4.2 4.3 4.3 4.5 5.2 Chapter 17 Chapter 18
_Rev.5 Rev. 7 4.1 4.2 5.3.1 5.6.3.a 5.6.5 5.7.3 5.8 5.9.2
.s e- Ent N WATERFORD 3 UALITY ASSURANCE PROGRAM MANIJAL CHAPTER 1 R TYPE: C1.31 REV.14.0 PAGE: 2 OF 21 4.0 RESPONSIBILITIES 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsibility for the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations to ensure that an effective Quality Assurance program is maintained.
4.1.2 Entergy Operations management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality Assurance program. 4.1.3 Entergy Operations Management is responsible for ensuring that implementing pur.edures within their department adequately implement Waterford 3 comnisments and obligations. 4.2 VICE PRESIDENT, OPERATIONS 4.2.1 The Vice President, Operations is responsible for assuring the development and approval of Waterford 3 quality policies. Reporting to him are the:
- a. General Manager, Plant Operations;
- b. Director, Plant Modification and Construction;
- c. Director, Site Support; i d. Director, Niiclear Safety and Regulatory Affairs;
- e. Training Manager;
- f. Manager, Site Business Services; and
- g. Safety Review Committee.
l
l 4- Ent WATERFORD 3 UALlW ASSURANCE CHAPTER 1 RM: C1.31 REV.15.0 PROGRAM MANUAL PAGE: 2 OF 21 4.0 . RESPONSIBILITIES l 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsibility for the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations to ensure that an effective Quality Assurance program is maintained. i 4.1.2 Entergy Operations management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality Assurance program. 4.1.3 Entergy Operations Management is responsible for ensuring that implementing procedures within their department adequately implement Waterford 3 commitments and obligations. 4.2 VICE PRESIDENT, OPERATIONS 4.2.1 The Vice President, Operations is responsible for assuring the development and approval of Waterford 3 quality policies. Reporting to him are the:
- a. General Manager, Plant Operations;
- b. Director, Plant Modification and Construction;
- c. Director, Site Support;
- d. Director, Nuclear Safety and Regulatory Affairs;
- e. Director, Quality gl
- f. Director, Trainir.g 15
~
- g. Safety Review Committee.
- i. -
i G - Ent WATERFORD 3 UALIW ASSURANCE CHAPTER 1 R M :C141 REV.14.0 4 1 PROGRAM MANUAL PAGE: 11 OF 21
- m. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification
, requirements, j
! 4.7 TRAINING MANAGER ' 4.7.1 The primary quality related responsibilities of the Training Manager include: h a. Providing training for Waterford 3 personnel, Inc.luding training l required by regulations, General Employee Training, and training l l for the Engineering Support Personnel;
- b. Maintaining training records; and
- c. Providing an instructor certification program.
- ..s -
i 4.8 MANAGER, SITE BUSINESS SERVICES i !' 4.8.1 The primary quality related responsibilities of the Manager, Site Business Services include: l a. Providing support for records management, including execution of j document control and records storage programs; ! b. Coordinating the development, preparation, and maintenance of l Waterford 3 policies and directives; i l c. Providing Medical Review Omcor services (reviewing and interpreting presumptive positive test results) for the Fitness for
~
Duty Program; and
- d, Providing direction to on-site Materials, Purchasing and Contracts group.
1 i 1
.- . _ . . _ . . . . . , _ . . _ _ , . _ _ _,_ . _ - , . . _ . . . . . _ . - . _ . ~ . . . _ _ . . . _ _ _ . _ . _ _ _ . _ - . , _ _ . , , . . . . . .- .,
- WATERFORD 3 CHAPTER 1 REV.15,0 $
L g~ Ent
- UALITY ASSURANCE R-TYPE: C1,31 PROGRAM MANUAL PAGE: 11 OF 21 h 17. Intsrfacing with on-site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors > , to ensure quality is maintained; and
- c. Qual;ty Assurance personnel have sufficient authority and organizational freedom to effectively:
- 1. Identify quality problems;
- 2. Initiate, recommsnd or provide solutions through 1_5 designated channels; and
- 3. Verify implemantation of solutions.
\
- d. This organizational freedom includea sufficient independence from cost and schedule when opposed to safety considerations;
- e. The Director, Quality has the authority to stop unsatisfactory work and/or control further processing, delivery, or installation of nonconforming material through designated channels; 4.8 DIRECTOR, TRAINING 4.8.1 The primary quality related responsibilities of the Director, Training include:
- a. Providing training for Waterford 3 personnel, including training required by regulations, General Employee Training, and training for the Engineering Support Personnel;
- b. Maintaining training records; and
- c. Providing an instructor cietification program.
b
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- c. Coordinating the development and review of dt.gtmentd procedures;
- d. Reviewing and processing assigned work authorizations and managing services for plant repair, modification, and ccnstruction which is under his jurisdiction;
- e. Performing a quality review of all construction initiated work authorizations not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements;
- f. Ensuring proper completion of modification and construction work prior to acceptance; and
- g. Coordinating construction tasks involved with outages and retrofitting. '
4.5 DIRECTOR, SITE SUPPORT 4.5.1 The primary quality related responsibilities of the Director, Site Support include:
- a. Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures;
- b. Coordinating the preparation of emergency drill scenarios and pt:formance of practim dril!s; and
- c. Implementing the Security Plan and Safeguards Contingency Plan;
- d. Controlling plant area access;
- e. Overseeing the activities of the Employee Concems Program.
- f. Providing d:rection to on-site Materials, Purchasing and Contracts group.
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- g. Providing support for records management, including execution of document control and records storage programs;
- h. Coordinating the development, preparation, and maintenance of Waterford 3 policies and procedures; and
_15
- 1. Providing Medical Review Officer services (reviewing and interpreting presumptive positive test results) for the Fitness for Duty Program.
4.6 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS ' 4.6.1 The primary quality related responsi'oilities of the Director, Nuclear Safety and Regulatory Affairs include:
- a. Coordinating and reviewing responses to Nuclear Regulatory Commission matters, as assigned;
- b. Managing the preparation of updates / revisions to the Final Safety Analysis Report and the Technical Specifications;
- c. Managing the Waterford 3 Commitments Management System;
- d. Managing the preparation of responses to NRC bulletins, orders, inspection reports, generic letters, and Notices of Violation;
- e. Oversight of the administration of the Condition Report process, root cause analysis and trend programs
- f. Analyzing conditions for human performance trends and publishing quarterly trend reports
- g. Reviewing corrective action documents for determination of reportability;
- h. Reviewing operating abnormalities and initiating Licensee Event Reports;
- i. Coordinating Nuclear Regulatory Commission interface;
^ O WATERFORD 3 CHAPTER 1 iREV.14.0
- Ent N UALITY ASSURANCE PROGRAM MANUAL R. TYPE: C1.31 PACE: 7 OF 21 4.5.2 The Director, Site Support is also responsible for the direction and administration of the Quality Assurance Manager and staff, who have the following responsibilit'es and authorities:
- a. The Quality Assurance Manager has the authority and responsibility for developing, coordinating, and verifying implementation of the Waterford 3 Quality Assurance program.
The Quality Assurance Manager maintains an overview of Waterford 3 quality related activities through reviews, audits, surveillances, and inspections. Quality Assurance personnel have sufficient authority end oiganizational freedom to effectiveh:
- 1. Identify quality problems;
- 2. Initiate, recomtnend or provide solutions through designated channels; and 3, Verifyimplementation of solutions.
- b. This organizational freedom includes sufficient independence from cost and schedule when opposed to safety considerations;
- c. The Quality Assurance Manager has the authority to stop unsatisfactory work and/or control further processing, delivery, or installation of ncaconforming material through designated channels; d.
The primary quality related responsibilities of the Quality Assurance Managerinclude: 1. Planning, organizing, and administering the Quality Assurance program;
- 2. Developing, reviewing, and concurring with the content of the Waterford 3 Quality Assurance Program Manual and changes thereto;
- 3. Developing Quality Assurance Procedures (QAPs);
4. Assisting in establishinc that portion of the Training program that addresses quality assurance; m _ _
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- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.14.0 PROGRAM MANUAL PAGE: 8 OF 21
- 5. Advising, reviewing, and concurring on the scope and content of quality assurance training and indoctrination programs for personnel performing quality related activities;
- 8. Providing requested inspection training to personnel performing quality related activities;
- 7. Certifying Lead Auditors and Inspectors;
- 8. Assuring effective implementation of the Quality Assurance program through a comprehensive system of reviews, assessments, and the performance or monitoring of nondestructrve examinations and other special processes;
- 9. Ensuring that quarity reviews are conducted for quality l
related implementing procedures and design changes, including drawings and specifications, to ensure the inclusion of quafrty requirements; m
- 10. Reviewing all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensura the inclusion of quality requirements, and ensuring that quality reviews arc conducted for all other initiated work authorizations; 11.
Reviewing nonconformance work authorization packages;
- 12. Assuring that the corrective action processes (results of audits, a/,sessments) under his/herjurisdiction are impiemented according to approved procedures; 13.
Conducting re.iews, assessments and monitoring of the various corrective action processes to ensure that the required program aspects are adequately addressed;
- 14. Rducting an ongoing assessment of the radiation protection and radwaste programs; 15.
Establishing and maintaining documentation of Quality Assu ance act!vities; and m n ___----
^ e- Ent WATERFORD 3 UALITY ASSURANCE PROGRAM MANUAL CHAPTER 1 R-TYPE: C1.31 REV,14.0 PAGE: 9 OF 21
- 16. Providing status informat;on regarding the Quality Assurance program to the Director, Site Support and the Vice President, Operations;
- e. The qualifications of the Quality Assurance Manager include as a minimum:
- 1. Graduate of a college or university with a Bachelor's degree in an engheering, science or related field, or equivalent capabilities;
- 2. A minimum of four years expenence in quality assurance or a quality assurarce related activity with at least two of those years in the nuclear power industry as a manager or supervisor,
- 3. Expe'ience in development and implementation of quality assurance programs, plans, and procedures;
- 4. Expertise in interpretation and application of Appendix B to 10CFR50 and related codes, standards, and regulatory guides;
- 5. Knowledge of inspection and nondestructive testing requirements;
- 6. Ability to plan, organize, and administer a Quality Assurance program; and
- 7. Ability to maintain an effective working relationship with employees, contractors, suppliers, govemment agencies, and the public.
4.6 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.6.1 The primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs include: a. Coordinating and reviewing responses to Nuclear Regulatory y Commission matters, as assigned; b. Managing the preparation of updates / revisions to the Final Safety 1 Analysis Report and the Technical Specifications;
g WATERFORD 3 CHAPTER 1 REV.15.0
- Ent UALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 8 OF 21 J. Reviewing plant system problems and performance concerns;
- k. Examining plant operating characteristics, NRC issuances (includes Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as part of the Independent Technical Review function. The Independent Technical Review functions include responsibility for:
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety:
- 2. Maintai.*g surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical;
- l. Maintaining SRC charters; and
- m. Performing independent reviews, safety examinations, and other review activities in support of the SRC and Technical Specification requirements.
M 4.7 DIRECTOR, QUALITY 4.7.1 The Director, Quality is responsible for the direction and administration of the Quality Assurance organization.
- a. The quaiifications of the Director, Quality Mclude as a minimum:
- 1. Graduate of a college or university with a Bachelor's 15
~
degree in an engineering, science or related field, or equivalent capabilities;
- 2. A ri.a.imum of four years erperience in quality assurance or a quality assurance related activity with at least two of those years in the nuclear power industry as a manager or supervisor;
- 3. Experience in development and implementation of quality
< , - a
8- Ent - WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.15.0 m PROGRAM MANUAL PAGE: 9 OF 21 assurance programs, plans, and procedures;
- 4. Expertise in interpretation and application of Appendix B to 10CFR50 and related codes, standards, and regulatory guides;
- 5. Knowledge of inspection and nondestructive testing requirements;
- 6. Ability to plan, organize, and administer a Quality Assurance program; and
- 7. Ability to maintain an effective working relationship with employees, contractors, suppliers, government agencies, and the public,
- b. The primary quality related responsibilities of the Director, Quality include: '
- 1. Planning, organizing, and administeri ig the Quality Assurance program;
- 2. Developing, reviewing, and concurring with the content of the Waterford 3 Qu7lity Assurance Program Manual and changes thereto;
- 3. Developing Quality Assurance Procedurec (QAPs);
- 4. Assisting in establishing that portion of the Training program that addresses quality assurance;
- 5. Advising, reviewing, and concurring on the scope and content of quality assurance training and indoctrination programs for personnel performing quality related activities;
- 6. Providing requested inspection training to personnel performing quality related activities; I
e- Entanu
~ ' OI WATERFORD 3 UALITY ASSURANCE PROGRAM MANUAL CHAPTER 1 R-TYPE: C1.31 REV.15.0 PAGE: 10 OF 21
- 7. Certifying i.ead Auditors and inspectors;
- 8. Assuring effective implementation of the Quality Assurance program through a comprehensive system of reviews, assessments, and the performance or monitoring of nondestructive examinations and other special processes;
- 9. Ensuring that quality reviews are conducted for quality related implementing procedures and design changes, including drewings and specifications, to ensure the inclusion of quality requirements;
- 10. Reviewing all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensure the inclusion of quality requirements, and ensuring that quality reviews are conducted for all other initiated work authorizations;
- 11. Reviewing nonconformance work authorization packages;
- 12. Assuring that the corrective action processes (results of audits, assessments) under his/her jurisdiction are implemented according to approved procedures; 3
- 13. Conducting reviews, assessments and monitoring of the
' various corrective action processes to ensure that the required program aspects are adequately addressed;
- 14. Conducting an ongoing assessment of the radiation protection and radwaste programs;
- 15. Establishing and maintaining documentation of Quality Assurance activities; and
- 16. Providing status information regarding the Quality Assurance program to the Vice President, Operations; i
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a g WATERFORD 3 CHAPTER 2 REV.11.0 4
- Ent . QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 3 OF 12 4.2.1 Plant Operations Review Committes (PORC)
The PORC is responsible for functioning as the on-site independent review committee, and is responsible for reviewing plant operatione items and procedures which are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with applicable procedures. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Modification Control, Construction, and Project Management. The primary quality related
- responsibilities of the Director, Plant Modification and Construction are listed in l Chapter 1.
l I 4.4 ' DIRECTOR, SITE SUPPORT l The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency Planning; Quality l Assurance; and L:.nployee Concerns Program. The primary quality related Ml responsibilities of the Director, Site Support are listed in Chapter 1. 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nuclear Safety and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the t implementation of the following programs and organizational units: Licensing; Operational Experience Engineering; and in-House Events Analysis. The M] primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are listed in Chapter 1. I __--_ o
f g WATERFORD 3 CHAPTER 2 REV.12.0 , ! - Entergy QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 3 OF 11 L p 4.2.1 - Plant Operations Review Committee (PORC) [ The PORC is responsible for functioning as the on-site independent review ccmmittee, and is responsible for reviewing plant operations items E and procedures which are submitted to it; and for recommending approval i . by the General Manager, Plant Operations in accordance with applicable j procedures. Additional responsibilities are listed in Chapter 1 and the
- Wsterford 3 Technical Specifications.
- 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION i
l The Director, Plant Modification and Construction is responsible for ensuring the i development and maintenance of procedures or instructions for the ! implementation of the following programs and organizational units: Modification i Control, Construction, and Project Managemant. The primary quality related i responsibilities of the Director, Plant Modification and Construction are listed in i Chapter 1. ! :4.41 DIRECTOR, SITE SUPPORT p , The Director, Site Support a responsible for ensuring the development and
- i. maintenance of procedureo or instructions for the implementation of the following
- i. programs and organizational units: Security; Emergency Planning; Site 121 l Business Services; and Employse Concems Program.'The primary quality 7
! related responsibilities of the Director, Site Support are listed in Chapter 1. , e l - 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS l The Director, Nuclear Safety and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the j implementation of the following programs and organizational units:. Licensing;
- Operational Experience Engineering; and in-House Events Analysis. The
' primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are listed ir. Chapter 1.
F 54.6j' DIRECTOR, QUALITY The Director, Quality is responsible for ensuring the development and 12
- j. maintenance of procedures or instructions for the implementation of the Quality Assurance organization. The primary quaiity related responsibilities of the Director, Quality are listed in Chapter 1.
l s - ,,e ~
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 ;REV.11.0 R. TYPE: C1.31 PROGRAM MANUAL PAGE: 4 OF 12 4.6 TRAINING MANAGER The Training Manager is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Operations Training; Simulator Training; Mainteriance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Traiaing Manager are listed in Chapter 1. 4.7 f MANAGER, SITE BUSINESS SERVICES The Manager, Site Business Services is responsible for ensuring the development and maintenance of procedures or instructions for the l implementation of Records, Document Control, and Policies and Directives activities. 4.8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The primary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 VICE PRESIDENT, ENGINEERING The Vice President, Engineering reports directly to the Executive Vice President
& Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1.
4
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g - WATERFORD 3 CHAPTER 2 REV.12.0 x
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 4 OF 11 4.7 DIRECTOR, TRAINING 12
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The Director, Training is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Opcrations Training; Simulator Training; Maintenance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Director, Training are listed in Chapter 1. 3 4.'8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The primary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 VICE PRESIDENT, LGINEERING The Vice President, Engineering reports directly to the Executive Vice President ! & Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1. 4.10 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technology tiansfer, and centrallicensing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Ir formation Systems, Supplier QA, EOl shared serv!ces, and Materials, Purchasing and Contracts groups. It is the responsibihty of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 REV.12.0 ) R TYPE: C1.31 PROGRAM MANUAL PAGE: 3 OF 11 4.2.1 Plant Operations Review Committee (PORC) The PORC is responsible for functioning as the on site independent review committee, and is responsible for reviewing plant operations items and procedures which are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with applicable procedures. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Modification l Control, Construction, and Project Management. The primary quality related l responsibilities of the Director, Plant Modification and Construction are listed in Chapter 1. 14.4j DIRECTOR, SITE SUPPORT - The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency Planning; Site 3 Business Services; and Employee Concems Program. The primary quality _ related responsibilities of the Director, Site Support are listed in Chapter 1. 4.5 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nuclear Safety and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units:. Licensing; Operational Experience Engineering; and In-Knyse Events Analysis. The primary quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are listed in Chapter 1. 4.8 f DIRECTOR, QUALITY The Director, Quality is responsible 'or ensuring the development and maintenance of procedures or instructions for the implementation of the Quality 3 Assurance organization. The primary quality related responsibilities of the Director, Quality are listed in Chapter 1.
g WATERFORD 3 CHAPTER 2 REV.11.0
- Ent QUAUTY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 9 OF 12 s
5.6 RESOLUTION OF DISPUTES 5.6.1 j Disputes involving quality, arising from a difference of opinion between Entergy OperatW departments, are normally resolved via direct interaction between the managers involved if a satisfactory resolution cannot be reached, the disputes are resolved through higher levels of management. The Quality Assurance Manager should be consulted for disputes involving the Waterford 3 Quality Assurance program interpretation and implementation. 5.6.2 Disputes involving quality, arising from a difference of opinion between Entergy entities, contractors, or suppliers, are normally resolved through the appropriate manager. If a satisfactory resolution cannot be reached, the disputes should be elevated to the Vice President, Operations, if necessary. The Quality Assurance Manager should be consulted for disputes involving other Entergy entities. The Vice President, Operations Support and/or the Quality Assurance Manager should be consulted for disputes conceming contractors or suppliers. 5.6.3 Written notification shall oe provided to the Vice President, Operations, and the Safety Review Committee regarding disputes or disagreements arising from a difference of opinion between the Plant Operations Review Committee and the General Manager, Plant Operations. The General ! Manger, Plant Operations has responsibility for resolution of such disputes in accordance with the technical specifications. 5.7 INDOCTRINATION, TRAINING, AND QUALIFICATION PROGRAMS 5.7.1 Indoctrination, training, and qualification programs shall be established for Entergy Operations personnel performing quality related activities. These programs shall be designed to ensure that personnel involved are knowledgeable in quality procedures and requirements, and have the necessary proficiency to perform the tasks. The scope, objective, and method of implementing the indoctrination and training program shall be documented in approved procedures.
g- Ent WATERFORD 3 QUALITY AS$URANCE CHAPTER 2 R-TYPE: C1.31 REV.11.0 }
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PROGRAM MANUAL PAGE: 10 OF 12
!6l.7.2[ Entergy Operations management is responsible for assuring that personnei are properly trained to perform activities in a safe and effective manrier. The Training Manager is responsible for providing professional, technical, and educational programs to support the indoctrination and training of Waterford 3 employees, contractors, and visitors to assure their safety and proficiency during the performance of their activities at Waterford 3, The Quality Assurance Manager reviews the content of quality related Indoctrination and training programs to assure adequacy.
5.7.3 Indoctrination, training, and qualification programs require: :
- a. Personnel responsible for performing activities that affect quality are instructed on the purpose, scope, ar,d implementation of quality related manuals, instructions, and procedures;
- b. Personnel performing activities that affe::t quality are trained and qualified in the princip!es, techniques, and requirements of_the _ __
activity being performed;
- c. Proficiency and qualification of personnel performing or verifying activities are maintained by retraining, re-examining, and/or recertifying on a periodic basis, as applicable;
- d. Proficiency testing is utilized to determine qualifications when education, experience, and training cannot be verified by other means; and
- e. Training and qualification documentation is maintained which describes the objectives, content, attendance, tests, acceptance criteria, and the functions personnel are qualified to perform.
5.7.4 The training program for Waterford 3 personnel is further described in Chapter 13 of the FSAR and in implementing procedures. 5.7.5 Waterford 3 Quality Assurance or tha Entergy Operations Supplier QA organization conducts audits of other organizational units, such as suppliers and contractors engaged in quality related activities at or for Waterford 3 to verify that personnel are adequately indoctrinated, trained, and qualified. c
g- Ent WATERFORD 3 QUAUTY ASSURANCE CHAPTER 2 REV.12.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 8 OF 11 Design Engineering Administrative Manual (DEAM);
- f. Plant Modification and Construction procedures;
- g. Nuclear Safety and Regulatory Affairs procedures; and
- h. Nuclear Training procedures.
5.5 IDENTIFICATION OF SAFETY " ELATED STRUCTURES, SYSTEMS, AND COMPONENTS 5.5.1 The Quality Assurance Program applies to all activities associated with quality related structures, systems, and components to an extent commensurate with their importance to safety. FSAR Table 3.2-1, Appendix A to this manual, and the Waterford 3 Q-List provide safety related classifications of plant structures, systems, and components; and identify those items subject to 10CFR50 Appendix B requirements. 5.5.2 Procedures provide further guidance for the identification of safety and quality related structures, systems, components and related activities to assure that the appropriate level of Quality Assurance program requirements are applied, 5.5.3 Procedures for the preparation and control of procurement documents provide guidance for spare and replacement part classification determination. These procedures invoke applicable codes, stardards, regulations, FSAR requirements, and the Q-List classifications for determining the classification of spare or replacement parts or materials. 5.6 RESOLUTION OF DISPUTES 5.6.1 L Disputes involving quality, arising from a difference of opinion between Entergy Operations departments, are normally resolved via direct interaction between the managers involved. If a satisfactory resolution cannot be reached, the disputes are resolved through higher levels of management. The Director, Quality should be consulted for disputes 1_2l involving the Waterford 3 Quality Assurance program interpretation and implementation. < J
l l g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 REV '12.0 i R-TYPE: C1.31 ! PROGRAM MANUAL , PAGE: 9 OF 11 i
- 5.8.2 Disputes involving quality, arising from a differer*ce of opinion between Entergy entities, contractors, or suppliers, are r.ormally resolved through the appropriate manager, if a satisfactory resolution cannot be reached, the disputes should be elevated to the Vice President, Operations, if l
necessary. The Director, Quality should be consulted for disputes involving other Entergy entities. The Vice President, Operations 3l ! Support and/or the Director, Quality should be consulted for disputes 3l !- conceming contractors or suppliers. 5.6.3 Written notification shall be provided to the Vice President, Operations, and the Safety Review Committee regarding disputes or disagreements arising from a difference of opinion between the Plant Operations Review Committee and the General Manager, Plant Operations. The General Manger, Plant Operations has responsibility for resolution of such disputes in accordance with the technical specifications. 5.7 INDOCTRINATION, TRAINING, AND QUALIFICATION PROGRAMS 5.7.1 Indoctrination, training, and qualification programs shall be established for Entergy Operations personnel performing quality related activities. These programs shall be designed to ensure that personnel involved are - knowledgeable in quality procedures and requirements, and have the necessary proficiency to perform the tasks. The scope, objective, and method of implementing the indoctrination and training program shall be documented in approved procedures. 15.7.21 Entergy Operations management is responsible for assuring that personnel are properly trained to perform activities in a safe and effective manner. The Director, Training is responsible for providing
-12l professional, technical, and educational programs to support the indoctrination and training of Waterford 3 employees, contractors, and visitors to assure their safety and proficiency during the performance of their activities at Waterford 3. The Director, Quality reviews the content of quality related indoctrination arm training programs to 3l assure adequacy.
5.7.3 Indoctrination, training, and qualification programs require:
- a. Personnel responsible for performing activities that affect quality are instructed on the purpose, scope, and implementation of quality related manuals, instructions, and procedures;
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 R-TYPE: C1.31 REV.11.0 PROGRAM MANUAL PAGE: 11 OF 12 5.8 CONTROLLED CONDITIONS FOR PERFORMING ACTIVITIES Quality related activities shall be accomplished under controlled conditions by personnel with the necessary skills to attain the required quality. Activities shall be performed using appropriate equipment, under suitable environmental conditions and with the assurance that prerequisites for the given activity have been satisfied. 5.9 MANAGEMENT REVIEW OF THE QUALITY ASSURANCE PROGRAM 5.9.1 >The Vice President, Operations ensures that a management assessment of the Quality Assurance program is conducted periodically by a qualified independent organization. 5.9.2 The information from these management assessments, the trend report, and summaries of the Quality Assurance program status are used by the Vice President, Operations to evaluate the effectiveness of the Quality-Assurance program and to take action, as necessary, to assure that the program complies with applicable regulatory requirements. 5.10 MAINTENANCE OF THE QUALITY ASSURANCE PROGRAM 5.10.1 Revisions to the Quality Assurance Program Manual are issued as necessary to support effective implementation of the Quality Assurance Program. The NRC shall be notified annually, or 6 months after each refueling outage provided the interval between successive updates does not exceed 24 rnonths, of any changes to the Quality Assurance Program description that do not reduce the commitinents previously accepted. The revisions must reflect all changes up to a maximum of 6 months prior to the date of filing. If a change is contemplated which would reduce the commitments in the approved Quality Assurance Program description, the proposed change shall be submitted to the NRC for approval prior to implementing the change. 5.10.2 Revisions to the Quality Assurance Program Manual (Special Scope) are issued as necessary to support effective implementation of the Quality Assurance Program. NRC notification regarding changes to the Quality Assurance Program Manual (Special Scope) is not required.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 2REV.?12.07 R TYPE: C1.31 PROGRAM MANUAL PAGE: 10 OF 11
- b. Personnel performing activities a,at affect quality are trained and qualified in the principles, techniques, and requirements of the
, activity being performed;
- c. Proficiency and qualification of personnel performing or verifying activities are maintained by retraining, re-examining, and/or recertifying on a periodic basis, as applicable;
- d. Proficiency testing is utilized to determine qualifications when education, experience, and training cannot be verifed by other means; and
- e. Training and qualification documentation is maintained which-i describes the objectives, content, attendance, tests, acceptance criteria, and the functions personnel are qualifed to perform.
l L' 5.7.4 The tra!ning program for Waterford 3 personnel is further described in Chapter 13 of the FSAR and in implementing procedures. 5.7.5 Waterford 3 Quality Assurance or the Entergy Operations Supplier QA organizat!cn conducts audits of other organizational units, such as suppliers and contractors engaged in quality related activities at or for Waterford 3 to verify that personnel are adequately Indoctrinated, trained, and qualified. 5.8 CONTROLLED CONDITIONS FOR PERFORMING / ".TIVITIES Quality related activities shall be accomplished under controlled conditions by personnel with the necessary skills to attain the required quality. Activities shall be performed using appropriate equipment, under suitable environmental-
- conditions and with the assurance that prerequisites for the given activity have been satisfied.
5.9 MANAGEMENT REVIEW OF THE QUALITY ASSURANCE PROGRAM i 5.91hThe Vice President, Operations ensures that a management assessment of the Quality Assurance program is conducted periodically (not to 12 exceed 24 months) by a qualified independent organization.
s QUALITY ASSURANCE PROGRAM DOCUMENTATION identificatiQD Descriotion Acoroval and Control g@ 2 m
- 1. Quality Assurance Defines the Quality Assurance Prepared by Quality Assurance, Program Manual Program, assigns responsibilities to concurred with by the affected various organizations, and defines organizations and approved by the i safety-related activities. Vice President Operations, Water'c-d 3. Issued and controlled by Site Business Services. .
- 2. Nuclear Management A set of Policies and Procedures Prepared by cognizant personnel. u Manual which prescribe activities and issued and controlled by 2@ >
responsibilities. Headquarters, Entergy Operations oC and approved by Entergy Operations $m Management. E$% j ego
'3. Waterford 3 Management A set of Policies, Directives and Prepared by cognizant personnel, $g$
Manual Procedures which prescribe and approved by Waterford 3 Vice jz ca activities and responsibilities at President, Operations. Issued r- Q Waterford 3. and controlled by Site Business Services. A manual consisting of a set of Prepared by cognizant plant staff T>2o
- 4. Waterford 3 Plant Operating Manual procedures which prescribe organizational units. Quality related $dk%
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required aspects of plant procedures shall receive a quality 3 management and operation. This related review. Approved by the ajfg manual provides the mechanism General Manager, Plant Operations. Oma through which the administrative issued and controlled by Site '$N" controls and quality assurance Business Services. m z requirements are implemented Q during the operation of Waterford 3. k. The POM applas to all personnel $ when they are within the Waterford 3 protected area. L______
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QUALITY ASSURANCE PROGRAM DOCUMENTATION Identification Description Approval and Control 9
- 3
- 1. Quality Assurance Defines the Quality Assurance Prepared by Quality Assurance, N Program Manual Program, assigns responsibilities to concurred with by the affected various organizations, and defines organizations and approved by the safety-related activities. Vice President, Operations, Waterford 3. Issued and controlled by Site Business Services. -
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- 2. Nuclear Management A set of Policies and Procedures Prepared by cognizant personnel. o Manual which prescribe activities and issued and controlled by $p@g respcnsibilities. Headquarters, Entergy Operations ojg>
and approved by Entergy Operations Management.
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- 3. 'Waterford 3 Management A set of Policies and Procedures Prepared by cognizant personnel,12
!$0 z g t3 Manual which prescribe activities and and approved by Waterford 3 Vice"l sz" responsibilities at Waterford 3. President Operations. Issued F$
and controlled by Site Business Services.
- 4. Waterford 3 Plant A manual consisting of a set of Prepared by cognizant plant staff j>?Q Operating Manual procedures which prescribe organizational units. Quality related procedures shall receive a quality g3 g required aspects of plant -
o mH management and operation. This related review. Approved by the "g3$ manual provides the mechanism General Manager, Plant Operations. Oggg through which the administrative issued and controlled by Site ,wa controls and quality assurance Business Services. a g requirements are implemented g during the operation of Waterford 3. g The POM applies to all personnel o when they are within the Waterford , 3 protected area. t
IdentificatiOD QUALITY ASSURANCE PROGRAM DOCUMENTATION Descriotion Anoroval and Control ge -
- 5. Quality Assurance A set of procedures prepared and Prepared by Quality Assurance and k I Procedures Manual issued to specify and control the coordinated with other organizat ons activities of the Quality Assurance as applicable. Approved by the !
organization. Quality Assurance Manager. Issued and controlled by Site Business Services. ,
- 6. Site Support Procedures /. set of procedures which Prepared by cognizant personnel ,O
- prescribe activities and within the Site Support Group. 2>
responsibilities within the Site Quality related procedures shall Support Group. receive a quality related review. g5f O
<M Approved by the Director Site E$$
Support. Issued and controlled ego by Site Business Services. $y$ C u
- 7. Design Engineering A set of procedures which Prepared by cognizant personnel E ,P o
prescribe activities and within Design Engineering, Quality Procedures responsibilities within the Design related procedures shall receive a Engineering organization. quality related review. Approved by the Director, Design Engineering i>2o or Department Manager. Issued and controlled by Site Business
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QUALITY ASSURANCE PROGRAM DOCUMENTATION e r , Identification Description Approval and Control ' lgll3
- 5. Quality Assurance A set of procedures prepared and Prepared by duakty Assurance and -
Procedures Manual issued to specify and controlthe coordinated with other organizabons ! activrbes of the Quakty Assurance as appbcable. Apprnved by the j organizabon. Dwector, Quakty. Issued and 12 l controlled by Site Bussness Services i
- 6. Site Support Procedures A set of procedures which Prepared by cognizant personnel ., O pie. wit,6 actwshes and vnthin the Site Support Group. '
is-:-#~;-e w?hin the Site Quakty related procedures shal. N>h 8C Support Group, which intenta= ine receive a quakty related review AN jNl5 Corporate site based Materials, procedures shall be approved by the E$$ Purchasing and Contracts Dwector, Site Support, with the ggg ; departrnent. excephon of those pertaining to the Materials, Ptadias; q and zga jz se ! Contracts group. These 12
- r- Q excephons will be approved by l the Menager, Matenais, Purchasing :
and Contracts with concurrence by j the Drector, Site Support. Issued J>2Q i and controlled by Site Business Services. "fk> o
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- 7. Design Engineering A set of procedures which Prepared I./ cognizant personnel o m o.
Procedures presenbe at,Jvitics and within Design Engineenng, Quakty * $ 'f " responsibihbes within the Design related procedures shall receive a "_, a ' Engineering organization. quahty related review. Approved $ by the Drector, Design Engineenng . or Department Manager. Issued 5 and controlled by Site Business Services. , I
._ _ - _ _ _ _ . . _ - - _ _ - . _ _ _ . _ . . . . - _ . _ - . ~ . . _ _ _ _ _ _ . _ . . . . - . _ .
QUALITY ASSURANCE PROGRAM DOCUMENTATION identification Descriotion Anoroval and Control gO 2
' 30. Nuclear Safety and A set of procedures which Prepared by cognizant personnel Regulatory Affairs prescribe activities and within Nuclear Safety and Regulatory Procedures responsibilities within the Nuclear Affairs. Quality related procedures Safety and Regulatory Affairs shall receive a quality related review.
e ganization. Approved by the Director, Nuclear
- Safety and R<.egulatory Affairs or l Department Manager. Issued and l controlled by Site Business Services. 1h 3
0 > r- lE l 11. NuclearTraining A set of procedures which Prepared by cognizant personnel o > Procedures prescribe activities and responsibilities within the Nuclear within NuclearTraining. Quality related procedures shall receive a
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Training Organization quality related review. Approved by the Manager, Nuclear Training. lEQ z g *o issued and controlled by Site 5z* Business Services.. r-Q
- 12. Site Business Services A set of procedures which Prepared by cognizant personnel Procedures prescribe activities and within Site Business Services.
responsibilities within the Site Quality related procedures shall J 3Q Business Services organization. receive a quality related review. Oy > This includes the Corporate Site Approved by the Manager, Site -o mH based Materials, Purchasing and Business Services with the *Eh5 Contracts department. Ogg,
- exception of those pertaining to the Materials, Purchasing and Contracts , H -a . >
group. These exceptions will be 2 approved by the Manager, Materials, L,E Purchasing and Contracts with g concurrence by the Manager, Site .o Business Services. .
QUALITY ASSURANCE PROGRAM DOCUMENTATION ! identification Desenption Approval and Control yO 2
.10. NuclearSafety and A set of procedures which Prepared by cognizant personnel Regulatory Affairs presenbe activities and within Nuclear Safety and Regulatory i Procedures responsibilities within the Nuclear Affairs. Quality related procedures i Safety and Regulatory Affairs shall receive a quality related review. !
organization. Approved by the Director, Nuc ear Safety and Regulatory Affairs. ' --12l lasued and controlled by Site ! Business Services. 2
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- 11. NuclearTraining A set of procedures which Prepared by cognizant personnel bC Procedures presenbe activihes and within NuclearTraining. Quality $m responsixidios within the Nuclear related procedures shall receive a E$$
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- 10. Nuclear Safety and A set of procedures which Prepared by cognizant personnel %
Regulatory Affairs prescribe activites and within Nuclear Safet
- and Regulatory Procedures responsibilities rAthin the Nr Affairs. Quality related pivcedures Safety and Regulatory Affairs shall recerve a quality related review.
organization. Approved by the Drector, Nuclear Safety and Regulatory Affairs or Department Manager. ksued and controlled by Site Business Services. *O
- 11. NuclearTraining A set of procedures which Prepared by cognizant personnel 3>4 0 r-o->
Procedures presenbe activities and within Nuclear Training. Quality $$ responsibi5 ties within the Nuclear related procedures shall rec 3ive a E$$ Training Organization quality related review. Approved JEQ by the Manager, Nuclear Training. zgo issued and conLv"ed by Site E z '* Business Services.. FS 12.' Site Busineso Services A set of procedures which Prepared by cognizant personnel Procedures presenbe actrvities and wi:hin Site Business Sennces. responsibilities withhi the Site Quality re'ated procedures shall j>3Q Business Services organization. receive a qualty related review. This includes the Corporate Site
*c9 sed Materials, Purchasing and Approved trf the Manager, Site Business Service., vAth the Oh]M>
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** E Contracts department. exce> of those pertaining 'o the ogh5 =
Materials, Purchasing and C0ubadi, , M -= group. These exceyGens will be - E approved by the Manager Materia's, < Purchasing and Contracts with ; concurrence by the Manager, Site
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WATERFORD 3 p/Entergy t o QUALITY ASSURANCE CHAPTER 3 REV. 3.0 Operations R-TYPE: C1.31 PROGRAM MANUAL PAGE 2 of 8 4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for design activities, including the review of safety related changes in design to ensure the inclusion of quality assurance requirements, and for approval
~ 1 of final design documents and design changes at Waterford 3.
4.3 PLANT OPERATIONS REVIEW C0mlTTEE The PORC is responsible for review and re*ommendations ,oncerning selected design changes and their affect ie safety. Specific PORC responsibilities are delineated in this manual 4.4 IQUALITY ASSURANCE MANAGER The Quslity Assurance Manager is responsible for ensuring that quality reviews of safety related changes in design are conducted. 1 5.0 DETAILS 5.1 DESIGN PROCESS 5.1.1 The design control program involves the p;eparation, review and approval of design documents, including the translation of applicable regulatory requirements and design bases into design, procurement, and procedural documents. The design control program assiires and controls such activities as field design engineering; physics, seismic, stress, thermal, hydraulic, radiation, and FSAR accident analyses; associated computer programs; compatibility of materials; accessibility for in-service inspection; maintenance and rephir; quality standard. -d safety significance. When a new design or design change is prepared, appropriate quality standards shall be specified in the design documents.
g - WATERFORD 3 CHAPTER 3 REV, 4.0
- Ent QUAUTYASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF8 f
4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for design activities, including the review of safety related changes in design to ensure the inclusion of quality assurance requirements, and for approval of final design documents and design changes at Waterford 3. 4.3 PLANT OPERATIONS REVIEW COMMITTEE The PORC is responsible for review and recommendatics concerning selected design changes and their affect on safety. Specific PORc uspo Abilities are delineated in this manual 4.4 DIRECTOR, QUALITY 4 The Director, Quality is responsible for ensuring that quality reviews of safety related changes in design are conductsd. 5.0 DETAILS 5.1 DESIGN PROCESS 5.1.1 The design control program involves the preparation, review and approval of design documents, including the translation of applicable regulatory requirements and design bases into derign, precurement, and procedural documents. The design control program assures and controls such activities as field design engineering; physics, seismic, stress, thermal, hydraulic, radiation, and FSAR accident analyses; associated computer programs; compatibility of materials; accessibility for in-service inspection; maintenance and repair; quality standards; and safety significance. When a new design or design change is prepared, appropriate quality standards shall be specified in the design documents. 5.1.2 Procedural control shall be established for design documents that reflect commitments of the FSAR. Design documents subject to procedural control include specifications, calculations, computer programs, the FSAR when used as a design document, drawings including flow diagrams, piping and instrument drawings, control logic diagrams, electrical single line diagrams, structural drawings for major facilities, site anangements, and equipment locations.
\ i
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g WATERFORD 3 CHAPTER 4 REV. 6.0 ;
- Ent
- QUALITY ASSURANCE R TYPE: C1.31 l
- PROGRAM MANUAL PAGE: 1OF6 '
TITLE: PROCUREMENT DOCUMENT EFFECTIVE DATE: 03/11/97 CDNIRQL PREPARED BY Cho vIs DIRECTOR, SITE SUPPORT: M , , , , QA MANAGER AMb r/.dp VICE PRESIDENT, OPERATIONS: /' b-
/
1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterford 3. Safety related vendors /contrautors and subtler vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the originalitem. 1.2 Services performed by other EOl sites (shared services) are obtained from Q those sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.131976, " Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants.") 2.2 USNRC Regulatory Guide 1.89, " Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants." 3.0 DEFINITIONS 3.1 See Appendix C
i g WATERFORD 3 CHAPTER 4 REV.6.0
- Eni QUALITY ASSURANCE R TYPE: C1.31
- PROGRAM MANUAL PAGE: 1OF6 TITLE: PROCURF. MENT DOCUMENT EFFECTIVE DATE: OG/04/97 CONTROL PREPARED BY: Mow. C. Qd DIRECTOR, QUALITY:
m 1 $ REVIEWED BY-GM ,s 4 * - VICE PRESIDENT, OPERATIONS:($' p, 1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterforti 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the originalitem. 1.2 Services performed by other EOl sites (shared services) are obtained from those sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirement 3 ior control of Procurement of items and Services for Nuclear Pcwer Plants.") 2.2 USNRC Regulatory Guide 1.80, " Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Plants." 3.0 DEFINITIONS 3.1 See Appendix C 1 i l
e a g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 5 R TYPE: C1.31 REV.5.0 ,~, PROGRAM MANUAL PAGE: 2 OF 7 4.2 ; QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible far assuring that a quality review 4 of safety re!ated Waterford 3 procedures, instructions, drawings, and specifications, to ensure the inclusion of applicable Quality Assurance Program requirements, is accomplished. 4.3 PLANT OPERATIONS REVIEW COMMITTEE (PORC) The PORC is responsible for reviewing and making recommendations concerning procedures required by Section 6.8 of the Technical Specifications and others which are used to assure the proper operation and maintenance of safety related equipment as determined by the General Manager, Plant Operations. 5.0 DETAILS 5.1 PREPARATION OF INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.1.1 Procedures shall be written and implemented in accordance with applicable codes, standards, and regulations to provide a controlled method for preparing, reviewing, changing, and approving instructions, procedures, and drawings, Each department shall have a governing procedure which describes the appropriate method for procedure development to assure consistency in preparation. The goveming procedure shallincorporate the requirements of the Quality Assurance Program. 5.2 CONTENTS OF INSTRUCTIONS AND PROCEDURES 5.2.1 Instructions and procedures prescribing safety related activities shall identify any special equipment and conddions required to perform the activity, responsibilities, applicable quantitative and qualitative acceptance criteria, and promions for documenting that activities were accomplished in accordance with the instructions and procedures, b l
o WATERFORD 3 CHAPTER 5 REV.6.0
- Ent . QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF7
. 4.2 DIRECTOR, QUALIT'.
6 The Director, Quality is responsible for assuring that a quality review of safety " related Waterford 3 procedures, instructions, drawings, and specifications, to ensure the inclusion of applicable Quality Assurance Program requirements, is i accomp!!shed. 4.3 PLANT OPERATIONS REVIEW COMMITTEE (PORC) The PORC is responsible for reviewing and making recommendations concerning procedures required by Section 6.8 of the Technical Specifications and others which are used to assure the proper operation and maintenance of safety related equipment as determined by the General Manager, Plant Operations. 4 5.0 DETAILS l 5.1 PREPARATION OF INSTRUCTIONS, PROCEDURES, AND DRAWINGS , 5.1.1 Procedures shall be written and implemented in accordance with applicable codes, standards, and regulations to provide a controlled method for preparing, reviewing, changing, and approving instructions, procedures, and drawings. Each department shall have a governing procedure which describes the appropriate method for procedure development to assure consistency in preparation. The goveming procedure shallincorporate the requirements of the Quality Assurance Program. 5.2 CONTENTS OF INSTRUCTIONS AND PROCEDURES 5.2.1 Instructions and procedures prescribing safety related activities shall identify any special equipment and conditions required to perform the activity, responsibilities, applicable quantitative and qualitative acceptance criteria, and provisions for documenting that activities were accomplished in accordance with the instructions and procedures.
g WATERFORD 3 CHAPTER 6 REV.8.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 2 OF 6 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible for ensuring that as built drawings are utilized for plant operation and maintenance upon completion of a related modification, aI 4.2 DIRECTOR, DESIGN ENGINEERING 4.2.1 The Director, Design Engineering is responsible for the revision and update of controlled drawings and configuration documents to r6flect design changes.
i MANAGER, SITE BUSINESS SERVICES 4.3 4.3.1 The Manager, Site Business Services is responsible for the development of a document control system which includes procedures and instructions for the processing and distribution of:
- a. The Sa'ety Analysis Report;
- b. The Plant Operating Manual;
- c. Design documents, including drawings and specifications; a
- d. The Waterford 3 Management Manual;
- e. Fabrication, construction, installation, inspection, test, maintenance, modification, and operation procedures;
- f. Vendor technical manuals and service bulletins;
- g. Safeguards information;
- h. Safety related departmental procedures; and
- i. Other documents as assigned.
g- Ent , WATERFORD 3 QUALITY ASSURANCE CHAPTER 6 R TYPE: C1.31 REV. 7.0 1 PROGRAM MANUAL PAGE: 2OF6 4;0 RESPONSIBILITIES i 4.1 GENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible for ensuring that ) as built drawings are utilized for plant operation and maintenance upon l completion of a related modification. 4.2 DIRECTOR, DESIGN ENGINEERING 4.2.1 The Director, Design Engineering is responsible for the revision and update of controlled drawings and configuration documents to reflect design changes. 4.3 - DIRECTOR, SITE SUPPORT 7 4.3.1 The Director, Site Support is responsible for the development of a document control system which includes procedures and instructions for the processing and distribution of;
- a. The Safety Analysis Report;
- b. The Plant Operating Manual;
- c. Design documents, including drawings and specifications;
- d. The Waterford 3 Management Manual;
- e. Fabrication, construction, installation, inspection, test, maintenance, modification, and operation procedures;
- f. Vendor technical manuals and service bulletins;
- g. Safeguards information;
- h. Safety related departmental procedures; and I. Other documents as assigned.
l
1 g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 7 REV. 7.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 3OF7 4.3 DIRECTORS / MANAGERS Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in support of their i departmental activities. 4.4 - QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for assuring that appropriate quality standards are maintained throughout the procurement process. 5.0 DETAILS 5.1 QUAllFICATION OF VENDORS 5.1.1 Safety related equipment, materials, and services shall be obtained from vendors, contractors, and consultants contained on a qualified suppliers list (QSL), when required, to assure compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and consultants shall be qualified for inclusion on the QSL through an evaluation of their technical and quality assurance capabilities for providing safety related items and servic )s. Quality Assurance evaluations shall be conducted by appropriately certified personnel and the results docJmented and maintained in accordance with quality records management procedures. 5.1.2 The evaluation of vendors shall be based on one or more of the following criteria:
- a. The vendors ability to comply with the requirements of the Quality Assurance Program as applicab!e to the type of material, equipment or service being procured;
- b. A review of the records and performance of vendors who have previously provided items and services similar to the type being procured; or
- c. A survey of the vendors facilities and/or quality assurance program to determine the vendors capability to provide a specified service or product which meets design, manufacturing and quality requirements.
l
b g WATERFORD 3 CHAPTER 7 REV.8.0 +
- Ent QUALITY ASSUPANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 3OF7 4.3 DIRECTORS / MANAGERS Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in support of their departmental activities.
4A DIRECTOR, QUALIT(
~
8 The Director, Quality is responsible for assuring that appropriate quality standards are maintained throughout the procurement process. 5.0 DETAILS 5.1 QUALIFICATION OF VENDORS 5.1.1 Safety related equipment, materials, and services shall be obtained from vendors, contractors, and consultants contained on a qualified suppliers list (OSL), when required, to assure compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and consultants shall be qualified for inclusion on the QSL through an evaluation of their technical and quality assurance capabilities for providing safety related items and services. Quality Assurance evaluations shall be conducted by appropriately certified personnel and the results documented and maintained in accordance with quality records management procedures. 5.1.2 The evaluation of vendors shall be based on ene or more of the following criteria:
- a. The vendors ability to comply with the requirements of the Quality Assunnce Program as applicable to the type of material, equipment or service being procured;
- b. A review of the records and performance of vendors who have previously provided items and services similar to the type being procured; or
- c. A survey of the vendors facilities and/or quality assurance program to determine the vendors capability to provide a specified service or product which meets design, manufacturing and quality requirements.
4
. I g- Ente WATERFORD 3 QUALITY ASSURANCE CHAPTER 8 R TYPE: C1.31 REV. 5.0 PROGRAM MANUAL PAGE: 1OF5 l TITLE: IDENTIFICATION AND cQRTHQL EFFECTIVE DATE: 01/17/97 l OF MATERIALS. PARTS AND l COMPONENTE i i
PREPARED BY: # ///N DIRECTOR, SITE #PPORT: m, QA MANAGER: % d4 VICE PRESIDENT, OPERATIONS: m I I 1.0 PURPOSE Identification and control of safety related materials, parts, and components are accomplished in accordance with approved procedures and apply to materials, parts, or components in all stages of fabrication, storage, installation, use, or removal from use. This chapter defines requirements for the identification and control of materials, parts, and components.
2.0 REFERENCES
2.1 10CFR50.55a 2.2 ASME Boller and Pressure Vessel Code Section ill 2 2.3 10CFR50 Appendix B 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 i QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for verifying adherence to applicable procedures for the identification and control of materials, parts, and components through the performance of periodic audits, surveillances, and inspections. , i i
o g- Ent WATERFORD 3 QUAllTV ASSURANCE CHAPTER 8 R TYPE: C1.31 REV. 6.0 PROGRAM MANU AL PAGE: 1OF5 TITLE: IDENTIFICATION AND CONTROL EFFECTIVE DATE: 06/04/97 OF MATERIALS, PARTS AND COMPONENTS PREPARED BY:y a hs O. M DIRECTOR, QUALITY: ,'
) 6 REVIEWED BY: * -
VICE PRESIDENT, OPERATIONS ///bo , -
~' \ V 1.0 PURPOSE Identification and control of safety related materials, parts, and components are accomplished in accordance with approved procedures and apply to materials, parts, or components in all stages of fabrication, storage, installation, use, or removal from use.
This chapter defines requirements for the identification and control of materials, parts, and components.
2.0 REFERENCES
2.1 10CFR50.55a 2.2 ASME Boller and Pressure Vessel Code Section lll 2.3 10CFR50 Appendix B 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 DIRECTOR, QUALITY 6 The Director, Quality is responsible for verifying adherence to applicable procedures for the identification and control of materials, parts, and components through the performance of periodic audits, surveillances, and inspections.
WATERFORD 3 (O)Entergy CHAPTER 9 REV. 5.0 , QUALITY ASSURANCE R-TYPE: C1.31 E Operations PROGRAku1ANUAL Page 3 of 6 4.3 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for assuring the establishment of the control of special processes program and for l verifying the effectiveness of its implementation through reviews, l inspection's, audits and surveillances. Additionally, the Quality Assurance Manager is responsible for approving NDE and inspection personnel certifications, and for the development and implementation of nondestructive examination and inspection procedures. 4.4 VICE PRESIDENT, ENGINEERING The Vice President, Engineering is responsible for the administrative, programatic, and operational control of the Entergy Operations, Inc. welding program. 5.0 DETAILS 5.1 SPECIAL PROCESSES SUBJECT TO CONTROLS 5.1.1 Special processes are those safety related special processes or operations that require special in-process controls and verification of essential characteristics. Acceptance may not be determined solely by inspection, test, or examination. Assurance that all steps of the process were properly carried out depends in part on the skill of the operator, use of specific equipment, and adherence to the qualified process procedures and controls, 5.1.2 Special processes include, but may not be limited to, the following as they are applied to safety related items:
- a. Welding;
- b. Heat treating;
- c. NDE;
- d. Chemical cleaning;
- e. Concrete and grout placement (seismic applications);
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 9 REV.6.0 R TYPE: C1.31 l PROGRAM MANUAL PAGE: 3OF6 4.3 ' DIRECTOR, QUALITY 6 The Director, Quality is responsible for assuring the establishment of the ' control of special processes program and for verifying the effectiveness of its implementation through reviews, inspections, audits and surveillances. Additionally, the Director, Quality is responsible for approving NDE and 6l Inspection personnel certifications, and for the development and implementation of nondestructive examination and inspection procedures. 4.4 VICE PRESIDENT, ENGINEERING The Vice President, Engineering is responsible for the administrative, programmatic, and operational control of the Entergy Operations, Inc. welding program. 5.0 DETAILS 5.1 SPECIAL PROCESSES SUBJECT TO CONTROLS 5.1.1 Special processes are those safety related special processes or operations that require special in-process controls and verification of essential characteristics. Acceptance may not be determined solely by inspection, test, or examination. Assurance that all steps of the process were properly carried out depends in part on the skill of the operator, use of specific equipment, and adherence to the qualified process procedures and controls. 5.1.2 Special processes include, but may not be limited to, the following as they are applied to safety related items: l a. Welding; l l b. Heat treating;
- c. NDE;
- d. Chemical cleaning;
(p)Entergy WATERFORD 3 QUALITY ASSURANCE CHAPTER 9 R-TYPE: CI.31 REV.'5.0-Operations PROGRAM MANUAL Page 5 of 6 ,
- h. The activity and process acceptance criteria; and
- i. The methods and sequences, when necessary, for the performance of the special process.
~
5.3 QUALIFICAT10N OF PERSONNEL, PROCEDURES, AND/0R EQUIPMENT 5.3.1 Qualification and certification may be provided by authorized agencies or by designated individuals, in writing, within Entergy Operations. Certification shall include necessary training followed by an examination of each individual. The period of validity for certification of personnel shall be in accordance with criteria described in applicable codes, standards, and specifications. 5.3.2 Personnel ftiling retest shall not be allowed to perform the special process until they have been recertified. 5.3.3 A Level 111 shall review and concur with procedures to assure they are in accordance with applicable requirements l of governing codes, standards, and specifications. A Level
!!! shall provide and/or assure training, examination, and qualification and recommend certification of Level I, II, and 111 personnel.
5.3.4 For special processes not covered by existing codes or standards, or when the quality requirements exceed the requir6ments of established codes or standards, the necessary qualifications of personnel, procedures, and/or equipment shall be defined. 54 DOCUMENTATION / RECORDS
) 5.'4. I ' A certified Level 11 or higher in the applicable discipline, shall evaluate and approve test / inspection results. Documentation of this evaluation and approval shall be maintained and controlled as a quality assurance record. Documents prepared by contractor personnel shall be independently reviewed and approved by an Entergy Operations Level 11 or III certified in the applicable discipline. The Entergy Operations review of contractor I
reports may be waived but only as approved in writing by the Waterford 3 QA Manager. n
- g WATERFORD 3 CHAPTER 9 REV. 8.0
- Entergy QUAUTY ASSURANCE PROGRAM MANUAL R TYPE: C1.31
, PAGE: 5 OF 6
- h. The activity and process acceptance criteria; and I. The methods and sequences, when necessary, for the performance of the special process.
5.3 QUALIFICATION OF PERSONNEL, PROCEDURES, AND/OR EQUIPMENT 5.3.1 Qualification and certification may be provided by authorized agencies or by designated individuals, in writing, within Entergy Operations. Certification shall include necessary training followed by an examination of each individual. T5 period of validity for certification of personnel shall be in accordance with criteria described in applicable codes, standards, and specifications. 5.3.2 Personnel falling retest shall not be allowed to perform the special process until they have been recertified. 5.3.3 A Level lli shall review and concur with procedures to assure they are in accordance with applicable requirements of governing codes, standards, and specifications. A Level ill shall provMe and/or assure training, examination, and qualification and recommend certification of Level I, ll, and lli personnel. 5.3.4 For special processes not covered by existing codes or standards, or when the quality requhements exceed the requirements of established codes or standards, the necessary qualifications of personnel, procedures, and/or equipment shall be defined. F.4 DOCUMENTATION / RECORDS 5.4.1 ' A certified Level ll or higher in the applicable discipline, shall evaluate and approve test / inspection results. Documentation of this evaluation and approval shall be maintained and controlled as a quality assurance record. Documents prepared by contractor personnel shall be independently reviewed and approved by an Entergy Operations Level ll or ill certified in the applicable discipline. The Entergy Operations review of contractor reports may be waived but only as approved in writing by the Director, Quality. . 6,l
= , _ _ , . . - -,
1 WATERFORD 3 CHAPTER 10 : REV.8.0 s Entergy QUAUTY ASSURANCE R. TYPE: C1.31 Page 2 00 Operations PROGRAM MANUAL 4.o REspoNSIBluTIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for. 4.1.1 The control and maintenance of ANil interfaces involving inspedions related to modifications, repairs, and replacements under the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, Section 111, Division I Class 1,2,3, and MC components and their supports; 4.1.2 Support of the Nor inspedien program by recommending and providing personnel to be , certified and to perform peer inspedions; and 4.1.3 Preparing maintenance and modification work instructions which contain the required inspection holdpoints and criteria. 4.2 DIRECTOR, DESIGN ENGINEERING 4.2.1 The Diredor, Design E,$r.::-;r.g is responsible for the control and maintenance cf the Waterford 3 ASME Ten Year Irweervre inspedion Program. The Diredor, Design Engineering is also responsible for all 6 : .11 interfaces in matters reisted to the Irkservice inspection Program. 4.3 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for. 4.3.1 The development and administration of the plant inspection program at Waterford 3; 4.3.2 Certifying inspedion personnel; 4.3.3 Rev6ew6tyj all safety related work authortzstions (WAs),WAs containing hold points, or WAs involving spedal processes, to ensure the indusion of quellty requirements, 6 and ensurifs that quality reviews are conducted for all other initiated work autnortzstions; and 4.3.4 Conducting or coor66nating inspections of modifications and maintenance activities; 4.4 VICE PRESIDENT, OPERATIONS SUPPORT 4.4.1 The Vice President Operations Support is responsibie for the performance of receipt and storage inspections. 8.0 DETAILS 5.1 INSPECTION PROGRAM 5.1.1 Entergy Operations has three sources of inspection personnel for safety related activities at Waterford 3: e, Quality Assurance personnel;
WATERFORD 3 CHAPTER 10 REV. 7.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF9 3.2 PEER / MAINTENANCE INSPECTOR - An ANSI N45.2.6 certified individual normally assigned to the line organization, but who reports to the QA Inspections unit during the inspection activity. This individualis not directly responsible for, or supervisor of, the activity being inspected.
4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for: 4.1.1 The control and maintenance of ANil interfaces involving inspections related to modifications, repairs, and replacements under the American Society of Mechanical Engineers (ASME), Boller and Pressure Vessel Code (Code), Section XI, Section Ill, Division I Claa 1,2, 3, and MC components and their supports; , 4.1.2 Support of the Peer Inspection program by recommending and providing personnel to be certified and to perform peer inspections; and 4.1.3 Preparing maintenance and modification work instructions which contain the required inspection holdpoints and enteria. 4.2 DIRECTOR, DESIGN ENGINEERING 4.2.1 The Director, Design Engineering is responsible for the control and maintenance of the Waterford 3 ASME Ten Year in service Incpection Program. The Director, Design Engineering is also responsible for all ANil interfaces in matters related to the in service Inspection Program.
; 4.3 blRECTOR, QUALITY 7
The Director, Quality is responsible for: 4.3.1 The developmqnt and administration of the plant inspection program at Waterford 3; 4.3.2 Ceriifying inspection pt 'onnel;
WATERFORD 3 CHAPTER 10 REV.6.0 4 p)Entergy ( QUALITY ASSURANCE R. TYPE: C1.31
" Operations PROGRAM MANUAL Page 3 of 7
- b. Line organization personnel (i.e. Peer / Maintenance inspectors); or
- c. Contract personnel.
5.1.2 Inspections shall be controlled as follows:
~
- a. Inspections are performed in accordance with rxocedures approved by Entergy Operations;
- b. Inspection results are documented, evaluated and their acceptability determined by responsible personnelin accordance with approved procedures;
+ c. Inspection procedures,inspectiot r.ersonnel qualifications and certifications are concurred with by the Quality Asst rance Manager;
- d. Inspections are performed by certified individuals other than those who performed or diredly supervised the activity being inspected;
- e. Inspection of operating activities may be conducted by second-line supervisory personnel or by other certified personnel not assigned first line supervisory responsibility for conduct of the work; and
- f. Inspeellon activities not conducted by Quality Assurance are periodically reviewed by Quality Assurance.
5.1.3 Inspections of operating activities or work functions associated with normal operation of the plant, routine maintenance, and certain technical support services routinely performed by the plant staff may be conducted by qualified and certified personnel selected by plant management. 5.1.4 Receipt and storage inspections are performed by qualified and certified personnel. For special inspections, such as nuclear fuel receiving, qualified and certified personnel reporting to the General Manager, Plant Operations may be utilized. 5.1.5 Inspections requiring expertise in a particular area, such as in service inspectior,, certain nondestructive testing, and containment vessel leak rate tests and inspections, may be conducted by off site Entergy Operations, or contractor personnel. In such instances, the inspedlon edivities shall be conduded under the Waterford 3 Quality Assurance Program or an approved contractor program. 5.1.6 Individuals performing inspections shall bt ;esponsible for verifying that the M&TE used in the inspection meets the crtleria noted in the procedure and that inspection results are within the specified acceptance enteria stated. 5.1.7 Inspedions conducted by persons during on-the-}ob training shall be under the direct observation and supervision of a person certified to Level 11 or higher in the appropriate discipline Verification of conformance is by the certified Level ll until certification is achieved.
g- Ent0 - WATERFORD 3 QUAUTY ASSURANCE CHAPTER 10 R TYPE: C1.31 REV. 7,0 PROGRAM MANUAL PAGE: 3OF9 4.3.3 Reviewing all safety related work authorizations (WAs), WAs containing , hold points, or WAs involving special processes, to ensure the inclusion of quality requirements, and ensuring that quality reviews are conducted for all other initiated work authorizations; and 4.3.4 Conducting or coordinating inspections of modifications and maintenance activities; 4.4 VICE PRESIDENT, OPERATIONS SUPPORT 4.4.1 The Vice President, Operations Support is responsible for the performance of receipt and storage inspections. 5.0 DETAILS 5.1 INSPECTION PROGRAM 5.1.1 Entergy Operations has three sources of inspection personnel for safety related activities at Waterford 3:
- a. Quality Assurance personnel;
- b. Line organization personnel (i.e. Peer / Maintenance Inspectors); or
- c. Contract personnel.
5.1.2 Inspections shall be controlled as follows:
- a. Inspections are parformed in accordance with procedures approved by Entergy Operations;
- b. Inspection results are documented, evaluated and their acceptaoility determined by responsible personnel in accordance with approved procedures;
- c. 5 Inspection procedures, inspection personnel qualifications and certifications are concurred with by the Director, Quality;
{l
WATERFORD 3 CHAPTER 10 REV,60 SEntergy QUALITY ASSURANCE R TYPE: C1.31' Page 5 of 7 ~ Operations PROGRAM MANUAL 5.3 INSPECTOR QUALIFICATIONS 5.3.1 inspectors shall be qualified through experience, education, and training programs to perform their assigned inspedion tasks. Where required, inspectors shall be formally examined and certified. A file shall be maintalned containing the credentials for each inspector, inspector qualifications and certifications shall be kept current. Procedures shall contain quellfication criteria for inspection personnel for the various types of Inspections. 5.3.2 Procedures shall be developed to define the training programs / curriculum for inspection personnel. 5.3.3 The inspector qualification program shall be reviewed and concurred with by the Quality Assurance Manager or his des 69 nee. The Quality Assurance Manager shall be responsible for approving the certification of inspectors. 1 i 5.4 INSPECTION BY SAMPLING METHODS l Sampling inspedion methods may be used when tests are destructive or when quality assurance l 1 records and inherent charaderistics of the hem indicate that a reduction in items inspected or tested can be achieved without jeopardizing the assurance of quellty, When a sampling method is used to verify acceptability, the sampilng procedures shall provide justification for the cample size and selection process and shall be concurred with by the Quality Assurance Manag:: athis designee. 5.5 INDIRECT INSPECTION 5.5.1 When it is not possible or practical to verify conformance of processed material or products by dired inspection, Indirect control may be employed by observation of processing methods, equipment, and personnel. To ensure adequate control, both direct inspection and process monitoring shall be provided when control by only one method is considered inadequate. 5.5.2 A combination of inspection and process monitoring methods, when used, shali be performed in a systematic manner to assure that the specified requirements for control of the process and quality of the item are being achieved throughout the duration of the process. 5.5.3 Controls, where required, shall be established and documented for the coordination and sequencing of these activities at established inspection points during successive stages of the process or construction. 5.6 RECEIVING INSPECTION Receiving inspection of purchased items and materials shall be performed by qualified ?nd certified personnelin accordance with written procedures / instructions /checMists. 5,7 IDENTIFICATION OF HOLD POINTS 5.7.1 Work plans, procedures, and instrudions for maintenance, modification or test of safety related structures, systems or components shall be reviewed to verify inclusion of inspection requirements, criteria, and hold points Work in process shall not proceed past the identified hold points without satisf action of inspection requirements.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 10 R TYPE: C1.31 REV. 7.0 PROGRAM MANUAL PAGE: 6OF9 l 5.2.3 Safety related inspection procedures shall be reviewed to verify the inclusion of the above requirements. 5.2.4 . The procedure originator shall be responsible for ensuring that the accuracy and precision requirements of inspection equipment are sufficient to obtain reliable date. Accuracy and precision requirements shall be based on procurement and/or plant technical specifications. Individuals performing inspections shall be responsible for assuring the equipment used meets the criteria noted in the procedure. 5.2.5 Quality Assurance shall be responsible for verifying that inspection equipment meets the criteria of the procedure and that inspection results are within the acceptance criteria. 5.3 INSPECTOR QUALIFICATIONS 5.3.1 Inspectors shall be qualified through experience, education, and training p grams to perform their assigned inspection tasks. Where required, inspectors shall be formally examined and certified. A file shall be maintained containing the credentials for each inspector. Inspector qualificationa and certificat8 ! s shall be kept current. Procedures shall , contain qualification criterit. ur inspection personnel for the various types of inspections. 5.3.2 Procedures shall be developed to define the training programs / curriculum for inspection personnel. 5.3.3 l The inspector qualification program shall be reviewed and concurred with by the Director, Quality or his designee. The Director, Quality shall be [l responsible for approving the certification of inspectors. 5.4 INSPECTION BY SAMPLING METHODS Sampling inspection methods may be used when tests are destructive or when quality assurance records and inherent characteristics of the item indicate that a reduction in items inspected or tested can be achieved without jeopardizing the assurance of quality. When a sampling method is used to verify acceptability, the sampling procedures shall provide justification for the sample size and selection process and shall be concurred with by the Director, Quality or his designee. [ ,
,r's /
WATERFORD 3 CHAPTER 11 REv. 2.0 ( )Entergy QUALITY ASSURANCE R TYPE: C1.31 Operations PROGRAM MANUAL Page 1 of 4 TITLE: TEST CONTROL EFFECTIVE DATE: /20/M PREPAREDB > f- - DIRECTOR. NUCLEAR SAFETY. QA MANAGER: VICE PRESIDENT, OPERATIONS: e t i 1.0 PURPOSt1 1.1 This Chapter defines the requirements for the control of functional, surveillance, and special tests. .'esting is pelformed in accordance with appropriate procedures to demonstrate that safety related equipment and systems will perform satisfadortly in service and malfunctions are identified and corrected in a timely manner. Records document tes' results in accordance with the Waterford 3 Quality Assurance Program requirements. 1.2 Procedures inclMe criteria for determining when a test is required and hew testing activities are to be performed. Test procedures require a review of applicable specJfications, test guidelines, and equipment technical manuals in order to determine required test equipment securacy. 2.0 RETERENCES 2.1 Waterford 3 'In Service inspectio9 (ISI) Program.' 2.2 NUREG 1117, " Technical Specifications.* 2.3 10CFR50.59, " Changes, Tests ano Egeriments.* 2.4 USNRO Regulatory Guide 1.30, August 1972 (which endorses ANSI N45.2.41972," Quality Assurance Requirements for the Installation, inspection and Testing of Instrumentation and Electrical Equipment.") 2.5 USNRC Regulatory Guide 1.94, Revision 1, April 1976 (which endorses ANSI N45.2.51974,
- Quality Assurance Requirements for installation,Intpection, and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants'.')
2.6 USNRC Regulatory Guide 1.118, Revision 0-R, May 1977 (which endorses ANSI N45.2.8-1975,
" Quality Assurance Requirements for instalWtion, inspection and Testing of Mechanical Equipmert and Systems.")
2.7 USNRC Regulatory Guide 1.8, Revision 1 R, September,1975 (which endorses ANSI /ANS 3.1-1978, "Etandard for Selection and Training of Personnel for Nuclear Power Plants.") 2.8 USNRC Regulatory Guide 1.58 Revision 1. September,1980 (which endorses ANSI N45.2.6-1978,
- Qualification of Nuclear Power Plant inspection, Examination and Testing Personnel.')
2.9 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.71978,
' Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.")
4 g WATERFORD 3 CHAPTER 11 REV. 3.0
- Ent QUALITY ASSURANCE R-TYPE: C1.31
- PROM AM MANUAL PAGE: 1OF5 TITLE: TEST CONTROL EFFECTIVE DATE: 06/04/97 l
PREPARED BY:Mo% d. % 4 DIRECTOR, QUALITY: /, __ REVIEWED 8 VICE PRESIDENT, OPERATIONb fl[ 7 1.0 PURPOSE 1.1 This Chapter defines the requirements for the control of functional, surveillance, and special tests. Testing is performed in accordance with appropriate proceriures to demonstrate that safety related equipment and systems will perfor; : satisfactorily in service and malfunctions are identified and corrected in a timely manner. Records document tast results in accordance with the Waterford 3 Quality Assurance Program requirements. 1.2 Procedures include criteria for determining when a test is required and how testing activities are to be performed. Test procedures require a review of applicable specifications, test guideilnes, and equipment technical manuals in order to detem1ine required test equipment accuracy.
2.0 REFERENCES
2.1 Waterford 3 "in-Service Inspection (ISI) Program" 2.2 NUREG-1117, " Technical Specifications" 2.3 10CFR50.59, " Changes, Tests and Experiments" 2.4 USNRC Regulatory Guide 1.30, August 1972 (which endorses ANSI N45.2.4-1972, " Quality Assurance Requirements for the Installation, Inspection and Testing of Instrumentation and Electrical Equipment") 2.5 USNRC Regulatory Guide 1.94, Revision 1, April 1976 (which endorses ANSI N45.2.51974, " Quality Assurance Requirements for Installation, inspection, and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants")
~
4 WATERFORD 3 S,Entergy QUAUTY ASSURANCE $ psi!3,33 * * " Operations PROGRAM MANUAL Page 2 of 6 300 DEFINITIONS 3.1 See Appendix C 3.2 MEASURING AND TEST EQUIPMENT (M&TE. Devices or systems used to calibrate, measure, gage, test, inspect, or control in order to acquire research, development, test or operational data, or, to datermine compliance t h h design, specifications, or other ' technical requirements. M&TE does not include pamanently installed operating equipment, nor test equipment used for preliminary checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation. 4.0 RESPONSIBILITIES 4.1 GENERAL MANGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for ensuring the establishment and implementation of procedures by the Plant Operations staff for the calibration, control, and use of M&TE in safety related activities. 4.2 DIRECTORS / MANAGERS Directors and Managers are responsit 'e for the development, maintenance, and implementation of .ocedures for activities related to calibration, control, and/or use of M&TE in safety l related activities. . 4.3 Q'UALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for the review and audit of the program for control of measuring and test equipment and for ensuring the establishment and implementation of procedures for the calibration and control of M&TE employed in safety related activities. l
g WATERFORD 3 CHAPTER 12 REV. 3,0
= Ente QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL P *GE 2 OF 5 3.0 DEFINITIONS 3.1 See Appendi$ C.
3.2 MEASURING AND TEST EQUIPMENT (M&TE)- Devices or systems used to calibrate, measure, gage, test, inspect, or control in order to acquire research, development, test or operational data; or to determine compliance with design, specifications, or other technical requirements. M&T'I does not include permanently installed operating equipment or test equipment used for preliminary checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation. 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, Pl. ANT OPERATIONS The General Manager, Plant Operations is responsible for ensuring the establishment and implementation of procedures by the Plant Operations staff for the calibrailon, control, and use of M&TE in safety related activities. 4.2 DIRECTORS / MANAGERS Directors and Managers are responsible for the development, maintenance, and implementation of procedures for activities related to calibration, control, and/or use of M&TE in safety related activities. 4.3 DIRECTOR, QUALITY 3 The Director, Quality is responsible for the review and audit of the program for control of measuring and test equipment and for ensuring the establisument and implementation of procedures for the calibration and control of M&TE employed in safety related activities. 5.0 DETAILS 5.1 CAllBRATION 5.1.1 The calibration program shall be designed to ensure the accuracy of M&TE. The calibration program shall provide for the prompt detection of inaccuracies and timely, effective corrective action.
WATERFORD 3 ew Entergy QUALITY ASSURANCE CHAPTER 13 REV.-4.0 Operations R-TYPE- C1.31 PROGRAM MANUAL Page S of 5 4.2 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Piant Modification and Construction is responsible for: 3 4.2.1 , Assuring the establishment and/or implementation of controls for handling safety related items released for construction; 4.2.2 The establishment and/or implementation of procedures required for handling and the maintenance of items withdrawn from storage and those that are installed but are not jet released to plant operations; and 4.2.3 The establishment of required cleanliness classifications (or zones) wnen opening components or systems for modification purposes which require specific internal cleanliness levels.
- 4.3 . QUALITY ASSURANCE MANAGER si The Quality Assurance Manager is responsible for performing audits, and surveillances of Waterford 3 activities associated with handling, shipping, storage, and preventive maintenance of safety related items in storage.
4.4 VICE PRESIDENT, OPERATIONS SUPPORT i The Vice President, Operations Support is responsible for: 4.4.1 Handling, cleanliness, storage, preservation and inspection of items within storage and warehouse areas in accordance with Quality Assurance Program requirements; and 4.4.2 Packing and shipping outgoing items (except radioactive waste and spent fuel) and for housekeeping within the ' receiving and warehouse areas. _ . . I
g WA1ERFORD 3 CHAPTER 13 REV.5.0
- Entt QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL P.4GE: 3OF5 4.2 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for:
4.2.1 Assuring the establishment and/orimplementation of controls for handling safety related items released for construction; 4.2.2 The establishment and/or implementation of procedures required for handling and the maintenance of items withdrawn from storage and those that are installed but are not yet released to plant operations; and 4.2.3 The estaolishment of required cleanliness classifications (or zones) when opening components or systems for modification purposes which require specific intemal cleanliness levels. f4.3 . DIRECTOR, QUALITY 5 The Oirector, Quality is responsible for performing audits, and surveillances of Waterford 3 activities associated with handling, shipping, storage, and preventive maintenance of safety related items in storage. 4.4 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Suppelis responsible for: 4.4.1 Handling, cleanliness, storage, preservation and inspection of items within l storage and warehouse areas in accordance with Quality Assurance Program requirements; and 4.4.2 Packing and shipping outgoing items (except radioactive waste and spent fuel) and for housekeeping within the receiving and warehouse areas. ( l
e WATERFORD 3 ~
&_Entergy CHAPTER 14 REV. 1.0 QUAUTY ASSURANCE R-TYPE: C1.31
~ Operations PROGRAM MANUAL Page 1 of 3 06/11/93 TITLE: INSPECTION. TEST. AE EFFECTIVE DATE: ^4,,-/;Lho u OPERAflNG STATUS PREPARED BY ) M '- DIRECTOR, NUCLEAR SAFETY- ,[2
<i /.< '
QA MANAGER: ,, MAA4 5 3 VICE PRESIDENT, OPE - v.y - 1.0 PURPOSE Inspection, test, and operating status of safety related structures, systems, and components are conspicuous 1; indicated in accordance with written procedures, to assure that required inspections anf tests are not inadvertently bypassed, or to assure that equipment under a controlled status is not inadvertently operated.
2.0 REFERENCES
None l 3.0 DEFINITIONS l l 3.1 See Appendix C l 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for the developa m snd maintenance of procedures which define the responsibhities and controls required for identifying t!.e test and operating status of installed safety related equipment, components, and systems.
~
1 4.2' QUALITY ASSURANCE M WAGER The QA Manager is responsible for the development and administration of procedures which define the responsibilities and controls required for inspections of safety related plant equipment, components, and systems. i
g- Ent WATERFORD 3 QUAUW ASSURANCE CHAPTER 14 R-TYPE: C1.31 REV. 2.0 PROGRAM MANUAL PAGE: 1OF3 TITLE:. INSPECTION, TEST, AND EFFECTIVE DATE: 06/04/97 OPERATING STATUS PREPARED BY: Mhm o On,y DIRECTOR, QUALITY: - - REVIEWED B C -- VICE PRESIDENT, OPERATIONS- ff f
<j -
~
4 1.0 PURPOSE Inspection, test, and operating status of safety related structures, systems, and components are conspicuously indicated in accordance with written procedures, to assure that required inspections and tests are not inadvertently bypassed, or to assure that equipment under a controlled status is not inadvertently operated.
2.0 REFERENCES
None 3,0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPEPATIONS The General Manager, Plant Operations is responsible for the development and maintenance of procedures which define the responsibilities and controls required for identifying the test and operating status of installed safety related equipment, components, and systems.
;4.2 ~ DIRECTOR, QUALITY 2
The Director, Qual;ty is responsible for the development and administration of procedures which define the responsibilities and controls required for inspections of safety related plant equipment, components, and systems. a
_ . _ . . _ . _ _ _. . _ _ _ _ . _ __ ~ . ~ . _ . . _ . _ _ s i I l g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 15 R-TYPE: C1.31 REV. 7.0 r , ' i PROGRAM MANUAL PAGE: 2OF5 ' 4.0 ~ RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for the nonconformance control system at Waterford 3 for material, parts, and components under plant jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use-as-is". 4.1.1 PLANT OPERATIONS REVIEW COMMITTEE The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending approval to the Geneial Manager, Plant Operations. 4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for reviewing nonconformances with recommended dispositions of " repair' or "use-as-is", and for evaluating and processing changes to resulting design drawings. The Director, Design Engineering is also responsible for dispos;tioning other nonconformances assigned to his organization. 4.3 gDIRECTOR, SITE SUPPORT The Director, Site Support is responsible for the review and audit of the Corrective Action Program. Zl 4.4 blRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS The Director, Nuclear Safety and Regulatary Affairs is responsible for: 4.4.1 Initiating Licensee Event Reports under 10CFR50.73. 4.4.2 The on-site independent Technical Review function which includes providing a random independent review of nonconformance dispositions and closures during the operations phase; and Z 4.4.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC es required by 10CFR21.
g WATERFORD 3 CHAPTER 15 REV. 8.0 '
- Ente. QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF5 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible for the nonconformance control system at Waterford 3 for material, parts, and components under plant jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use-as-is".
4.1.1 PLANT OPERATIONS REVIEW COMMITTEE The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending appreval to the General Manager, Plant Operations. 4.2 DIRECTOR, DESIGN ENGINEEF< LNG The Director, Design Engineering is responsible for reviewing nonconformances with recommended dispositions of" repair" or "use-as-is", and for evaluating and processing changes to resulting design drawings. The Director, Design Engineering is also responsible for dispositioning other nonconformances assigned to his organization. 4.3 el DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS - The Director, Nuclear Safety and Regulatory Affaim is responsible for: 4.3.1 Initiating Licensee Event Reports under 10CFR50.73. 4.3.2 The on-site Independent Technical Review function which includes providing a random independent review of nonconformance dispositions and closures during the operations phase; and 4.3.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC as required by 10CFR21. m
u g WATERFORD 3 CHAPTER 15 REV. 8.0 ,
- Ent QUAUTY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 3 OF 5 W#4A - l DIRECTOR, QUALITY 8
The Director, Quality is responsible for conducting reviews or assessments to monitor satisfactory implementation of the Corrective Action Program at Waterrord 3. 4.5 WATERFORD 3 PERSONNEL All Waterford 3 personnel are respons3.ble for ioentifying and reporting > nonconforming items on the appropriate nonconformance document (Condition Report). 5.0 DETAILS The following actions are required when safety related materials, parts, components, systems, act;vities or services do not conform to drawings, specifications, workmanship standards or other applicable documents: 5.1 IDENTIFICATION 5.1.1 Nonconformances observed in the course of inspection, testing, operations, maintenance, modifications, etc. shall be documented. in cases where required documentary evidence is not available that items have satisfactorily passed necessary inspections and tests, the associated hardware shall be considered nonconforrning. 5.1.2 Nonconformances shall be clearly and thoroughly described, documented and controlled. 5.2 NOTIFICATION 5.2.1 Organizations affected or potentially affected by a nonconforming item shall be notified upon identification of the nonconformance. 5.2.2 Until suitable documentary evidence is available to show the affected material or equipment is in conformance, affected systems shall be evaluated for operability in accordance with the Waterford 3 Technical Specifications and other license agreements (i.e., Equipment Qualification program).
~ , _ _a
4 g- Ent WATERi:ORD 3 QUALIT( ASSURANCE CHAPTER 16, REV. 8.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for
, identified adverso conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is responsible for:
- a. Assuring the performance of reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and
- b. Oversight of the administration of the Condition Report process, g root cause analysis and trend programs.
4.3~ < DIRECTOR, SITE SUPPORT 4.3.1 The Director Site Support is responsible for:
- a. Requesting or ensuring periodic independent assessments of the i corrective action program to ensure that the process elements are i
adequately implemented, 4.4 aI DIRECTORS AND MANAGERS 4.4.1 Directors and Managers are responsible for:
- a. Assuring that procedures are develeped and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; and
- c. Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution.
g WATERFORD 3 CHAPTER 16 REV. 8.0 4
- Entt '
QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 3OF5
'4.5 QUALITY ASSURANCE MANAGER 4.5.1 The Quality Assurance Manager is responsible for;
- a. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; and
- b. Issuing Stop Work Orders when conditions warrant.
4.6 IN-HOUSE EVENTS ANALYSIS SUPERVISOR 4.6.1 The in-House Events Analysis Supervisor is responsible for:
- a. Administering the Condition Report Process; and
- b. Administering a root cause investigation and trend analysis program for corrective action documents and for publishing a written or electronic trend report.
4.7 SAFETY REVIEW COMMITTEE The Safety Review Committee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Action Program at Waterford
- 3. The SRC assessment shallinclude, at a minimum, the review of the trend reports and significant adverse conditions.
4.8 CONDITION REVIEW BOARD The CRB is responsible for reviewing Controlled Maintenance Condition Identifications and Condition Reports to ensure adverse conditions receive the proper significance classification, priority, and dedication of resources. 4.9 WATERFORD 3 PERSONNEL i Waterford 3 personnel are responsible for promptly identifying and documenting adverse conditions on corrective action documents. Waterford 3 personnel are also responsible for recommending that an activity be stopped if the specific work is not being done in accordance with approved procedures, drawings, specifications, or regulatory requirements.
g WATERFORD 3 CHAPTER 16 ' REV. 9.0
- Ent QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF5
- c. Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and
- d. Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions.
4.2 DIRECTOR, NUCLEAR SAFETY AND REGULATORY AFFAIRS 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is responsible for:
- a. Assuring the performance of reportability reviews of Condition Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and
- b. Oversight of the administration of the Condition Report process, root cause analysis and trend programs.
/ 4.3 DIRECTOR, QUALITY 4.3.1 The Director, Quality is responsible for: g
- a. Requesting or er.suring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented.
- b. Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; and
- c. Issuing Stop Work Orders when conditions warrant.
4.4 DIRECTORS AND MANAGERS 4.4.1 Directors and Managers are responsible for-
- a. Assuring that procedures are developed and maintained to implement the Corrective Action Program;
- b. Assuring that personnel are familiar with the requirements of the Corrective Action Program; and l
l _____ _ j
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 16 R TYPE: C1.31 REV. 8.0 ; PROGRAM MANUAL PAGE: 4 OF 5 5.0 DETAILS 5:1 PROCEDURAL REQUIREMENTS 5.1.1 Procedures and instructicns for correcting adverse conditions shall include provisions for:
- a. Deficiency identification and immediate action;
- b. Review for impact and assignment;
- c. Investigt le and analyze;
- d. Corrective action planning and implementation;
- e. Prioritization of corrective action;
- f. Verification of compietion; and
- g. Verification of effectiveness.
5.1.2 Implementing procedures shall assign responsibility to each individual employed by Entergy Operations to promptly identify adverse conditions. 5.1.3 Impem?aGg procedures shall be developed to ensure that each individual has the appropriate corrective action doc iments and guidance necessary to properly document adverse conditions. 5.1.4 Procedures shall also address corrective actions identified extemal to Entergy Operations and through intemal programs such as trend analysia. 5.2 STOP WORK ORDER (SWO) 5.2.1 'When an individual determines that specific work is not being performed in accordance with approved drawings, specifications, procedures, or regulatory requirements, the individual should recommend to the appropriate supervisor, that the activity be stopped until adequate corrective action is taken. The Quality Assurance Manager shall be { notified if the activity does not cease. ~ I 5.2.2 The Quality Assurance Manager or his designee should verbally request that the adverse activity be stopped at the next safe stopping point.
g- Entemy WATERFORD 3 WALITY ASSURANCE CHAPTER 16 REV. 8.0
- R TYPE: C1.31 PROGRAM MANUAL PAGE: 5 OF 5 5.2.3 If work is not stopped as requested, a Stop Work Order shall be issued by the Quality Assurance Manager or his designee, to the organization responsible for not terminatin;; the work that is adverse to quality. Work I shall not proceed until the Stop Work Order is released by the Quality Assurance Manager.
5.3 CONTRACTOR RESPONSIBILIT( Contractors performing services or activities pertaining to safety r stated systems, structures, or components shallidentify adverse conditions accorCing to thk manual or their Entergy Operations approved QA Program. 5.4 RECORDS Corrective action reports and supporting documentation shall become quality assurance records. 6.0 ATTACHMENTS None
g WATERFORD 3 CHAPTER 16 REF.9.0 i
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 4 OF 5 i 5.0 DETAILS
. l 5.1 PROCEDURAL REGUIREMENTS 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for;
- a. Deficiency identification and immediate action;
- b. Review for impact and assignment;
- c. Investigate and analyze;
- d. Corrective action planning and implementation;
- e. Prioritization of corrective action;
- f. Verification of completion; and
- g. Verification of effectiveness.
5.1.2 Implementing procedures shall assign responsibility to each individual employed by Entergy Operations to promptly identify adverse conditions. 5.1.3 Implementing procedures shall be developed to ensure that each individual has the appropriate corrective action documents and guidance necessary to properly document adverse conditions. 5.1.4 Procedures shall also address corrective actions identified extemal to Entergy Operations and through intemal programs such as trend analysis. 5.2 - STOP WORK ORDER (SWO) 5.2.1 When an individual determines that specific work is not bebg performed in accordance with approved drawings, specifications, procedures, or regulatory requirements, the individual should recommend to the appropriate supervisor, that the activity be stopped until adequate corrective action is taken. The Director, Quality shall be notified if gl the activity does not cease.
g WATERFORD 3 CHAPTER 16 REV. 9.0
- Ent QUAUTY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 5OF5 5.2.2 The Director, Quality or his designee should verbally request that the adverse activity be stopped at the next safe stopping point.
-l 9
5.2.3 ;lf work is not stopped as requested, a Stop Work Order shall be issued by the Director, Quality or his designee, to the organization responsible for not terminating the work that is adverse to quality. Work shall not -l 9 proceed until the Stop Work Order is released by the Director, Quality. 9l 5.3 CONTRACTOR RESPONSIBILITY Contractors performing services or activities pertaining to safety related systems, structures, or components shall identify adverse conditions according to this manual or their Entergy Operations approved QA Program. 5.4 RECORDS Corrective action reports and supporting documentation shall become quality assurance records. 6.0 ATTACHMENTS I None
y, g WATERFORD 3 CHAPTER 17 LREV,5.0 '
- Entergy QUAUTY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 1OF5 ,
TITLE: QUALITY ASSURANCE RECORDS EFFECTIVE DATE: 01/17/97 PREPARED BY: 4 1//Mk DIRECTOR, SITE SUPPORT; // - == = -- QA MANAGER: A4 VICE PRESIDENT, OPERATIONS: OE -- - V I 1.0 PURPOSE 1.1 Quality assurance secords are those completed records that furnish documented evidence of the quality of items or of activities affecting quality and those records required by the Technical Specifications. This chapter defines requirements for the control of quality assurance records.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.88, Revision 2, October 1976 (which er.;orses ANSI N45.2.9-1974, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants" 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Appendix C. ? 4.0 RESPONSIBILITIES "4.1~ MANAGER, SITE BUSINESS SERVICES The Manager, Site Business Services is responsiole for: 2 4.1.1 Assuring the preparation of procedures for the execution of a document control and records storage program; ar:d
, u_
i 8 l l l g WATERFORD 3 CHAPTER 17 REV. 6.0 ! - Entergy QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF5 TITLE: QUALITY ASSURANCE RECORDS EFFECTIVE DATE: 06/04/M PREPARED BY:bQh b k' DIRECTOR, QUAL!"iY:
~
6 REVIEWED B v ,k' _ f VICE PRESIDENT, OPERATIONS
- /k,v j ,_ --
1.0 PURPOSE 1.1 Quality assurance records are those completed records that furnish documented evidence of the quality of items or of activities affecting quality and (nose records required by the Technical Specifications. This chapter defines requirements for the control of quality assurance records.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.88, Revision 2, October 1976 (which endorses ANSI N45.2.9-1974, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants" i 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Appendix C. 4.0 RESPONSIBILITIES
;4.1'. ! DIRECTOR, SITE SUPPORT 6 i The Director, Site Support is responsible for: -
4.1.1 Assuring the preparation of procedures for the execution of a document l control and records storage program; and
g WATERFORDs CHAPTER 18 REV. 7.0
- Ent QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF8 TITLE: AUDITA EFFECTIVE DATE: 03/11/97 PREPARED BY & ubd DIRECTOR, SITE SUPPORT: 9de, A NAGE M/f/// VICE PRESIDENT, OPERATIONS: [ /d 1.0 PURPOSE 1.1 Audits are performed to verify compliance with the Quality Assurance Program requirements and to determine the program effectiveness. This chapter defines the requaements of the Waterford 3 Quality Assurance At:dit Program.
2.0 REFERENCES
2.1 Waterford 3 Quality Assuranc.e Program Manual, Chapter 16, " Corrective Action" 3.0 DEFINITIONS 3.1 See Appendix C 4,0 RESPONSIBILITIES 4.1 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support is responsible for planning, scheduling and conducting audits and surveillances of suppliers, contractors, and EOl Z c".ared services which provide materials, components, parts and services to be used in safety related applications.
- 4.2 QUALIT( ASSURANCE MANAGER The Quality Assuranco Manager is responsible for planning, scheduling, and conducting audits of the Waterford 3 Quality Assurance Program, and its implementing procedures.
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 18 1 REV. 8.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF8 TITLE: AUDITS EFFECTIVE DATE: 06/04/97 P R E P/' 9 E D B Y: c m O .97, k DIRECTOR, QUALITY: --
/_
[ 8 REVIEWED BY W VICE PRESIDENT, OPERATIONS 1, p 1.0 PURPOSE 1.1 Audits are performed to veiify compliance with the Quality Assurance Program requirements and to determine the program effectiveness. This chapter defines the requirements of the Waterford 3 Quality Assurance Audit Program. l
2.0 REFERENCES
2.1 Waterford 3 Quality Assurance Program Manual, Chapter 16, " Corrective Action" 3.0 DEFINITIONS 3.1 See Appendix C 4.0 RESPONSIBILITIES 4.1 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support is responsible for planning, scheduling and conducting audits and surveillances of suppliers, contractors, and EOl shared services which provide materials, components, parts and services to be used in safety related applications. 4.2 ' DIRECTOR, QUALITY 8 The Director, Quality is responsible for planning, scheduling, and conducting audits of the Waterford 3 Quality Assurance Program, and its implementing procedures.
g WATERFORD 3 CHAPTER 18 REV. 7.0
~. Ent QUALITY ASSURANCE R TYPE: C1.31 PROG. TAM MANUAL PAGE: 4OF8
- g. The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee ..ce
. protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.
- h. The Primary Coolant Sources Outside Containment Program at least once per 24 months.
- i. The in-Plant Radiation Monitoring Program at least once per 24 months.
- j. The Secondary Water Chemistry Program at least once per 24 months.
- k. The Post-Accident Sampling Program at least once per 24 months.
- l. The Basemat Monitoring Program at least once per 24 months.
- m. The radiological environmental monitoring program and the results
- thereor at least once per 12 months.
- n. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
- o. The PROCESS CONTROL FROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
- p. The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.
5.3 PRE-AUDIT ACTIVITIES S.3.11 Quality Assurance shall provide an audit notification letter signed by the appropriate Quality Assurance manager or supervisor. The letter shall be submitted to the organization to be audited, and shall identify the audit dates and the areas to be audited.
l WATERFORD 3 CHAPTER 18 REV,8,0~
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 4 OF 8
- g. The fire protection equipment and program implementation at least
.once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection
' consultant. An outside independent fire protection consultant shall be used at least every third year.
4
- h. The Primasi .oolant Sources Outside Containment Program at least once pe,/ 24 months.
- 1. The in-Plant Radiation Monitoring Program at least once per 24 months.
J. The Secondary Water Chemistry Program at least once per 24 months.
- k. The Post-Accident Sampling Program at least once per 24 months,
- l. The Basemat Monitoring Program at least once per 24 months, r: The radiological environmental monitoring program and the results thereof at least once per 12 months.-
- n. The OFFSITE DOSE CALCULATION MANUAL and implementing -
procedures at least once per 24 months. L o. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at j least once per 24 months,
- p. The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision i
1, June 1974 and Regulatory Guide 4.1,- Revision 1, April 1975 at least once per 12 months, 5.3 PRE-AUDIT ACTIVITIES 5;3.1FQuality ~ Assurance shall provide an audit notification letter signed by
; the Director, Quality or appropriate supervisor. The letter shall be l
submitted to the organization to be audited, and shall identify dates and the areas to be audited. ge---
g- Ent WATERFORD 3 QUALITY t.7SURANCE CHAPTER 18 R-TYPE: C1.31 REV. 7.0 PROGRAM MANUAL PAGE: 6OF8 5.5.3 Lead Auditors sha!! participata in an auditor training program and maintain proficiency through training, review and study of codes and standards related to quality assurance, or through active participation in the audit program. 5.5.4 Lead auditors shall be certified. Audit teams may include consultants or technical specialists as auditors under the supervision of a lead auditor. 5.6 POST-AUDIT ACTIVITIES 5.6.1 Upon completion of an audit, the audit team shall determine the need for and coordinate a post-audit conference, which shall include the presence of those individuals with the authority to effect corrective action (if required) for findings identified during the audit. 5.6.2 Audit findings shall be presented in written form. Written acknowledgment should be obtained from the audited organization for each audit f:nding. 5.6.3 Formal audit reports shall be issued within 30 working days of the post-audit conference or completion of the audit. Audit reports required by the SRC Audit Program shall be issued within 30 days. Distribution includes: 4
- a. The Quality Assurance Manager;
- b. The manager of the audited organization;
- c. The SRC (receives only operations audit reports);
- d. The manager (s) responsible for corrective action; and
- e. The Vice President, Operations (for audit reports required by the SRC Audit Program).
5.6.4 It shall be the responsibility of the audited organization ta review the audit report and to take action as necessary to ensure that corrective action is accomplished in a timely manner.
g WATERFORD 3 CHAPTER 18 REV. 8.0 - Entemvw QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 6OF8 5.5.3 Lead Auditors shall participate in an auditor training program and maintain proficiency through training, review and study of codes and standards related to quality assurance, or through active participation in the audit program. 5.5.4 Lead auditors shall be certified. Audit teams may include consultants or technical specialists as auditors under the supervision of a lead auditor. 5.6 POST-AUDIT ACTIVITIES 5.6.1 Upon completion of an audit, the audit team shall determine the need for and coordinate a post-audit conference, which shall include the presence of those individuals with the authority to effect corrective action (if required) for findings identified during the audit. 5.6.2 Audit findings shall be presented in written form. Written acknowledgment should be obtained from the audited organization for each audit finding. 5.6.3 Formal audit reports shall be issued within 30 working days of the post-audit conference or completion of the audit. Audit reports required by the SRC Audit Program shall be issued within 30 days. Distribution includes:
- a. The Director, Quality; gl
- b. The manager of the audited organization;
- c. The SRC (receives only operations audit reports);
- d. The manager (s) responsible for corrective action; and
- e. The Vice President, Operations (for audit reports required by the SRC Audit Program).
5.6.4 It shall be the responsibility of the audited organization to review the audit report and to take action as necessary to ensure that corrective action is accomplished in a timely manner.
g WATERFORD 3 CHAPTER 18 REV. 7.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 7OF8 5.6.5 The Quality Assurance Manager, supervisor, or the audit team leader shall be responsible for follow-up action (including re-audits) as required to ensure that corrective action nas been taken and is effective. Audit findings shall be documented in corrective action documents and noted in the audit report. Corrective actions and re-audits shall be documented with reference to the original audit.
5.7 CORRECTIVE ACTION PLAN 5.7.1 If, after investigation or evaluation of an audit finding, it is determined that a violation of specified requirements has occurred, the required response shall provide a corrective action plan which cc.itains at a minimum the requirements of QAPM, Chapter 16 and include the following, as applicable:
- a. The methods and, when applicable, the results of investigations or evaluations used to identify all affected hardware and software
- items;
- b. The methods and, when applicable, the results of investigations or evaluations used to determine the root cause(s);
- c. The action taken, or to be taken, to correct each affected hardware and software item;
- d. The actions taken, or to be taken, to preclude the recurrence of the violation;
- e. The scheduled completion date(s) for each of the applicable items identified above; and
- f. The status of each uncompleted item at the time of response submittal.
5.7.2 in cases where the presented objective evidence does not support the conclusion that a violation of specified requirements has occurred, the response shall clearly state that fact, along with complete justification and objective evidence for the response. )__.........
l I i ' g WATERFORD 3 CHAPTER 18 REV. 8.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 7OF8 5.6.5 The Director, Quality, supervisor, or the audit team leader shall be responsible for follow up action (including re-audits) as required to ensure 8l that corrective action has been taken and is effective. Audit findings shall be documented in corrective action documents and noted in the audit report. Corrective actions and re-audits shef. ca documented with reference to the original audit.
5.7 CORRECTIVE ACTION PLAN 5.7.1 If, after investigation or evaluation of an audit finding, it is determined that a violation of specified requirements has occurred, the required response shall provide a corrective action plan which contains at a minimum the requirements of QAPM, Chapter 16 and include the following, as applicable:
- a. The methods and, when applicable, the results of investigations or evaluations used to identify all affected hardware and software items;
- b. The methods and, when applicable, the results of investigations or evaluations used to determine the root cause(s);
- c. The action taken, or to be taken, to correct each affected hardware and software item;
- d. The actions taken, or to be taken, to preclude the recurrence of the violation;
- e. The scheduled completion date(s) for each of the applicable items identified above; and
- f. The status of each uncompleted item at the time of response submittal.
5.7.2 in cases where the presented objective evidence does not support the conclusion that a violation of specified requirements has occurred, the response shall clearly state that fact, along with complete justification and objective evidence for the response. i
4 g WATERFORD 3 CliAPTER 18 REV. 7.0 ~
- Entergy QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 8OF8 l
5.7.3 At any time when required response dates or proposed implementation dates cannot be reasonably met, the audited orgatilzation shall develop a ! response, advising the QA Manager or appropriate supervisor of the new resporise date. 1 5.8 ' ANALYSIS OF AUDIT DATA Audit data shall be analyzed by the Quality Assurance Manager or appropriate supervisor, who shall report any significant quality problems, including the need for re-audit of deficient areas, to the Director, Site Support and the Vice President, Operations. 5.9 PROCESS SURVEYS (SURVEILLANCES) 5.9.1 Entergy Operations Quality Assurance may conduct process surveys (surveillances) to verify that an item or activity conforms to specified requirements. These process surveys (surveillances) shall supplement regular audits. They are usually limited in scope, and usually involve:
- a. A specific activity being performed;
- b. A procedure or portion of a procedure; or
- c. A specific area within a program.
15.9.2 ' Distribution of process survey (surveillance) reports include the appropriate Quality Assurance manager and the affected organization. 5.10 RECORDS Audit records shall include audit plans, reports, written replies, and documentation of completion of corrective action. Other documentation, such as checklists, may be retained as quality records as necessary to support audit results. 6.0 ATTACHMENTS None
g WATERFORD 3 CHAPTER 18 L REV.8.0
- Ent QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 8OF8 5.7.31At any time when required response dates or proposed !mplementation dates cannot be reasorwbly met, the audited organization shall develop a response, advising the L, rector, Quality or appropriate supervisor of the new response date. 8l
- 5.8 ANALYSIS OF AUDIT DATA Audit data shall be analyzed by the Director, Quality or appropriate supervisor, 8l who shall report any significant quality problems, including the need for re-audit-of deficient areas, to the Director, Quality and the Vice President, Operations, g l 5.9 PROCESS SURVEYS (SURVEILLANCES) 5.9.1 Entergy Operations Quality Assurance may conduct process surveys (surveillances) to verify that an item or activity conforms to specified requirements. These process surveys (surveillances) shall supplement regular audits. They are usually limited in scope, and usually involve:
- a. A specific activity being performed;
- b. A procedure or portion of a procedure; or
- c. A specific area within a program.
5.9.2 Distribution of process survey (surveillance) reports include the Director, Quality and the affected organization. g 5.10 RECORDS Audit records shall include audit plans, reports, written replies, and documentation of completion of corrective action. Other documentation, such as checklists, may be retah ed as quality records as necessary to support audit results. 6.0 ATTACHMENTS None 1 2
g WATERFORD 3 APPENDIX A REV. 5.0
- Enterey D ., QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF8 TITLE: REGULATQRY GUIDANCE DOCUMENTS EFFECTIVE DATE: 10/16/96 PREPARED BY __ h t. DIRECTOR, NUCLEAR SAFET(: /M h QA MANAGE w M VICE PRESIDENT, OPERATIONS:
d ( , This appendix contains a listing of Regulatory Guides and ANSI Standards applicable to the Quality Assurance Program for Waterford 3. Reference FSAR Section 1.8 for a complete listing of regulatory guides and standards applicable to the design and operation of Waterford 3. Document Comment l
- 1. Appendix B to 10CFR50 " Quality 1. Criterion Vil, Control of Purchased Assurance Criteria for Nuclear Materials, Equipment, and Services Power Plants and Fuel states that documentary evidence that Reprocessing Plants" material and equipment conform to the procurement requirements shall be available at the nuclear power plant or fuel reprocessing plant site prior to installation or use of such material and equipment.
The Waterford 3 Quality Assurance Program requires that required documentary evidence be available at the site prior to use, but not necessarily prior to installation. This allows installation to prcceed under specified conditions while any missing documents are being obtained, but precludes dependence on the item for safety purposes.
- 2. A. Regulatory Guide 1.8, 1. The qualifications of personnelin the Revision 1_R. September Health Physics, Radwaste, and .
1975, " Personnel Selection Chemistry Departments are in and Training" (Endorses accordance with ANSI N18.1-1971 as ANSI N18.1-1971) endorsed by this Reg. Guide and/or as shown in FSAR Chapter 13.
--.-_.h
g- Ent QUALITY ASSURANCE WATERFORD 3 APPENDIX A R-TYPE: C1.31 REV. 6.0
- PROGRAM MANUAL PAGE: 1OF8 TITLE: REGULATORY GUIDANCE EFFECTIVE DATE: 06/04/97 DOCUMENTS PREPARED BY me C- M DIRECTOR, QUALITY: s /
REVIEWED B r- _ VICE PRESIDENT, OPERATIONS . b n( This appendix contains a listing of Regulatory Guides and ANSI Standards applicable to the Quality Assurance Program for Waterford 3. Reference FSAR Section 1.8 for a complete listing of regulatory guides and standards applicable to the design and operation of Waterford 3. Document Comment
- 1. Appendix B to 10CFR50 " Quality 1. Criterion Vil, Control of Purchased Assurance Criteria for Nuclear Materials, Equipment, and Services Power P' ants and Fuel states that documentary evidence that -
Reprocessing Plants" material and equipment conform to the procurement requirements shall be available at the nuclear power plant or feel reprocessing plant site prior to installation or use of such material and equipment. The Waterford 3 Quality Assurance Program requires that required documentary evidence be available at the site prior to use, but not necessarily prior to installation. This allows installation to proceed under specified conditions while any missing documents are being obtained, but precludes dependence , on the item for safety purposes.
- 2. A. Regulatory Guide 1.8 1. The qualifications of personnel in the Revision 1, September Health Physics, Radwaste, and 1975, " Personnel Selection Chemistry Departments are in and Training" (Endorses accordance with ANSI N18.1-1971 as ANSI N18.1-1971) endorsed by this Reg. Guide and/or as shown in FSAR Chapter 13.
4 WATERFORD 3 (] (/Intergy QUALITY ASSURANCE APPENDIX: B RTYPE: cl.31 REV. 00 j Operations PROGRAM MANUAL PAGE: 1 of 4 i e TITLE: _10CFR50. APPEdDII B COMPLIANCE EFFECTIVE DATE: 04/01/91 PREPARED BY: M.b DIRECTOR NUCLEAR SAFETY- du* QA MANAGER: (AA4 VICE PRESIDENT, OPERATIC 1S kb . This appendix illustrates the relationship between 10CFR50 Appendix B and the Nuclear Safety Quality Policies. 10 CFR 50. Appendix B Criterion Euclear Safety Ouality Policy 4 1. Organization Chapter 1 - defines the organizational structure and delineates the authority and responsibilities of individuals and
~
organizations performing quality assurance activities. II. Quality Assurance Chapter 2 - defines the scope of the Quality Program Program and establishes that activities
. ecting safety related structures, systems, and components will be conducted n .
accordance with approved procedures. III. Design Control Chapter 3 - defines requirements for the control of the design of safety related structures, systems, and components including the design of plant modifications.
g WATERFORD 3 APPENDIX B REV.1.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF3 TITLE: _10CFR50, APPENDlX B EFFECTIVE DATE: 06/04/97 COMPLlANCE PREPARED BY hm 6 .QA DIRECTOR, QUALITY: /- .
REVIEWED BY ,-- D VICE PRESIDENT, OPERATION / g,-
/
This appendix illustrates the relationship between 10CFR50, Appendix B and the Nuclear Safety Quality Policies. 10CFR50, Appendix B Criterion Nuclear Safety Quality Policy
- 1. Organization Chapter 1 - defines the organizational structure and delineates the authority and responsibilities of individuals and organizations performing quality assurance activities.
II. Quality Assurance Program Chapter 2 - defines the, scope of the Quality Program and establishes that activities affecting safety related structures, systems, and components wil! .>e conducted in accordance with approved procedures. 111. Design Co.itrol Chapter 3 - defines requirements for the control of the design of safety related structures, systems, end components including the design of plant modifications. IV. Procurement Document Control Chapter 4 - defines requirements for the control of procurement of safety related structures, systems, components, materials, and services. V. Instructions, Procedures, and Chapter 5 - defines rcquirements for the Drawings development and control of instruct!cns, procedures, and drawings.
7 WATERFORD 3 p/Entergy y QUALITY ASSURANCE APPENDIX: C REY. 5.0 Operations PROGRAM MANUAL R-TYPE: C1.31 p.g.: 3 op 3g TITLE: TERMS A M DEFINITIONS EFFECTIVE DATE: 10/07/94 PREPARED BY '_ DIRECTOR,NUCLEARSAFETY:() QA MANAGEP VICE PRESIDENT, OPERATIONS:
/
This appendix provides a compilation af terms and definitions which are important to establishing the boundaries of the Waterford 3 Quality Amirance Program. They are provided as guidance to achieve standardization wit Waterford 3 documents and at an aid in the implementation of the Qualit, Assurance Program. The terms and definitions were selected from those contained within the ANSI standards listed in Appendix A on the basis of most frequent usage. 1 Those responsible for the Quality Assurance Program implementation are reminded that those terms and definitions provided by the standards but not listed herein shoulu be regarded as valid. Therefore, the user is referred to the standards listed in Appendix A for additional guidance. It is the responsibility of the user of the terms and definitions contained herein to escertain that they are appropriate for the intended application.
- Where a term is used to convey a different intent than that defined herein, clarification should be provided at the point of application.
2 The subscript following each definition provides the source of the definitier.. An index of the subscripts is contained at the end of this appendix. f
e g- Ent WATERFORD 3 QUALITY ASSURANCE APPENDIX C R TYPE: C1.31 REV. 6.0 PROGRAM MANUAL
- PAGE: 1 OF 19 TITLE: TERMS AND DEFINITIONS EFFECTIVE DATE: 06/04/97 PREPARED BY Ohm GO DIRECTOR, QUALITY:
REVIEWLO BY: 4* VICE PRESIDENT, OPERATION [ , ,v , , This appendix provides a compilation of terms and definitions which are important to cstablishing the boundaries of the Waterford 3 Quality Assurance Program. They are provided as guidance to achieve standardization within Waterford 3 documents and as an aid in the implementatbn of the Quality Assurance Program. The terms and definitions w:re selected from those contained within the ANSI standards listed in Appendix A on the basis of most frequent usage. Those responsible for the Quality Assurance Program implementation are reminded that those terms and definitions provided by the standards but not listed herein should be regarded as valid. Therefore, the user is referred to the standards listed in Appendix A for additional guidance. It is the responsibility of the user of the terms and definitions contained herein to ascertain that they are appropriate for the intended application. Where a term is used to convey a different intent than that defined herein, clari6 cation shou;d be provided at the point of cpplication. The subscript following each definition provides the source of the definition. An index of th] subscripts is contained at the end of this appendix.
ATTACHMENT VI TO W3F198-0013 QAPM Table of Contents Revision 17 Changes affecting QAPM Chapter 1 to Revision 16 I e
g WATERFORD 3 TABLE OF CONTENTS 1
- Entergy QUALITY ASSURANCE REV. 17.0 '
ppCf$HgyJAL R TYPE: C1.31
,,\ ,
PAGE: 1OF1 TITLE REVISION DATE g Forward and Policy Statem6CPY No. - 1 04/22/92 Chapter 1 Organization 16.0 07/31/97 l { Chapter 2 Quality Assurance Program 12.0 06/04/97 Chapter 3 Design Control 4.0 06/04/97 Chapter 4 Procurement Document Control 6.0 06/04/97 Chapter 5 Instructions, Procedures, and 6.0 06/04/97 Drawings Chapter 6 Document Control 7.0 06/04/97 Chapter 7 Control of Purchased Materials, 8.0 06/04/97 Equipment, and Services Chapter 8 Identification and Control of Materials, 6.0 06/04/97 Parts, and Components Chapter 9 Control of Special Processes 6.0 06/04/97 Chapter 10 Inspection 7.0 06/04/97 Chapter 11 Test Control 3.0 06/04/97 Chapter 12 Control of Measuring and Test Equipment 3.0 06/04/97 Chapter 13 Handling, Storage, Packaging and Shipping 5.0 06/04/97 Chapter 14 Inspection, Test, and Operating Status 2.0 06/04/97 Chapter 15 Nonconforming Materials, Parts or 8.0 06/04/97 Components Chapter 16 Corrective Action 9.0 06/04/97 Chapter 17 Quality Assurance Records 6.0 06/04/97 l l Chapte. 8 Audits 8.0 06/04/97 Appendix A Regulatory Guidance Document 6.0 06/04/97 Appendix B 10CFR50, Appendix B Compliance 1.0 06/04/97 Appendix C Terms and Definitions 6.0 06/04/97 _ m , -
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE: Chapter 1 Rev.15.0 To provide additional clanfication regarding the composition requirements of the Plant Operating Review Committee (PORC). 10CFR50.64 REVIEW:
- 1. Does the proposed change represent a reduction of commitment O Yes " No to the QA Program description previously secepted by the NRC7 Explain:
Chapter 1, Revision 15.0, Paragraph 4,10.3 was deleted thereby eliminating the appointment of temporary PORC ch:irmen and attemate PORC members, Peregraph 4.10.4 has been renumbered 4.10.3 and revised to delete reference to designated attemate PORC chairmen, and Paragraph 4.10.5 has been renumbered 4.10.4 and revised to delete reference to designated alternate PORC chairmen and PORC afternates. P:ragraph 4.10.2 already requires the General Manager Plant Operations (GMPO) to appoint the PORC chairman and PORC members from site management personnel. The intent is that the GMPO will name a sufficient number of site management personnel to currently existing PORC positions that the need to name temporanes and attemates is nullified. This change is not considered a lessening of commitment because the appointment of the PORC chairman continues to reside with the GMPO, while the appointment of attemates, previously accomplished by the PORC Ch ltman, will be nullified by the GMPO's appointment of permanent site management personnel to PORC memberchip. The departmental positions of PORC will not be altered by this revision.
- 2. If item 1 above le YES, does the proposed change include the Yes No E N/A beels to coelude that the revised program incorporating the change continues to meet the criteria of 10CFR50 Appendix 8 and other previously accepted FSAR commitments?
Explain: Reviewed By: O h QA Representative
- 8. M '7 h/9 7 Date RECOMMENDATION:
" Does not represent a lessening of commitment and it can be implemented immediately.
Represents a lessening of commitment however, the cliange has sufficient basis to demonstrate continued compilance with Appendix 8 and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. Represents a lesset.Ing of c mmitment with Insufficient basis to determine continued O compliance. Therefore, the chan e should not be processed, f 4 * - 7//)? 7 Recommended By: QA Superviso[ ' Date DISPOSITION:
- Approved for implementation Disapproved Approved for submittal o th N or accepttnce b 7 I Approved By: ^^ Y d.E. f p /,f y D a e m ,t, A q
. Da't e
) I . QAP 018 R6.0 Attachment 7.1 R TYPE: J3.11 _- l
1
- CHANGE To provide additional clarification regarding the composition requirements of'he Plant Operating Review Committee (PORO).
i BASIS FOR NO REDUCTION OF COMMITMENT Paragraph 4.10.3 was deleted thereby eliminating the appointment of temporary PORC chairmen and alternate PORC members, porngraph 4.10.4 has been renumbered 4.10.3 and
- revised to delete reference to designated alternate PORC chairmen, and 4.10.5 has been
]' renumbered 4.10.4 and revised to delete reference to designated alternate PORC chairmen and PORC alternates. Paragraph 4.10.2 already requires the General Manager Plant l Operations (GMPO) to appoint the PORC chairman and PORC members from site , management personnel. The intent is that the GMPO will name a sufficient number of site management personnel to currently existing PORC positions that the need to name temporaries and alternates is nullified. This change is not considered a lessening of commitment because the appointment of the PORC chairman continues to reside with the GMPO, while the appointment of alternates, previously accomplished by the PORC Chairman, will be nullified by the GMPO's appointment of permanent site management personnel to PORC membership. . The departmental positions of PORC will no be aitered by this revision. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1
. Rev.15
) 4.10.3 4.10.4 4.10.5 2 I
~
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,P e- ErII N WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.15.0 PROGRAM MANUAL PAGE: 14 OF 21
- h. All recognized indications of an unanticipated deficiency in some
. aspect of design or operation of structures, systems, or components that could affect nuclear safety; and I. Reports and meetir.g minutes of the PORC.
4.9.9 The SRC shall report to and advise the Vice President, Operations on areas of responsibility. 4.9.10 Records of SRC activities shall be prepared, approved, and distr;buted as indicated below;
- a. Minutes of each SRC meeting shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following each meeting;
- b. Reports of reviews encompassed in paragraph 4.9.8 above shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of Chapter 18 shall be forwarded to the Vice President, Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization; 4.10 F; ant Operations Review Committee (PORC) 4.10.1 The PORC shall function to advise the General Manager, Plant Operations on all matters related to nuclear safety.
4.10.2 The e JRC shall be composed of site management members as assigned, in writing, by the GMPO. The GMPO will also indicate, in l writing, the PORC Chairman. i 4.10.3 ln the absence of the PORC Chairman, the General Manager, Plant l Operations will appoint a temporary Chairman. All other alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
- - - _ = _
l/** ; ! e- Ent WATERFORD 3 QUALITY ASSURANCE PROGRAM MANUAL CHAPTER 1 R TYPE: C1,31 REV 16.0 l i PAGE: 14 OF 21 i i ! h. All recognized indications of an unanticipated deficiency in t,ome j aspect of design or operation of structures, systems, or
- , components that could affect nuclear safety; and i
- 1. Reports and meeting minutes of the PORC.
4.9.9 The SRC shall report to and advise the Vice President, Operations on areas of responsibility. 4.9.10 Records of SRC activities shall be prepared, approved, and distributed as indicated below: L l
- a. Minutes of each SRC meeting shall be prepared, approved, and
- forwarded to the Vice President, Operations within 14 days i following each meeting;
, b. Reports of reviews one.ompassed in paragraph 4.9.8 above ! shall be prepared, approved, and forwarded to the Vice President, l Operations within 14 days following completion of the review; and
- c. Audit reports encompassed by paragraph 5.2 of Chapter 18 shsil -
be forwarded to the Vice President, Operations and to the . management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization;- 4.10 Plant Operations Review Committee (PORC) 4.10.1 The PORC shall function to advise the General Manager, Plant Operations on all matters related to nuclear safety. 4.10.2 The PORC shall be composed of site management members as I assigned, in writing, by the GMPO. The GMPO will also indicate, in writing, the PORC Chairman. 18 I 4 p 4 4
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e- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R TYPE: C1.31 REV.15.0 PROGRAM MANUAL PAGE: 15 OF 21 4.10.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated attemate. 4.10.5The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions shall consist of the Chairman or his designated alternate and three members, including alternates. 4.10.6 The PORC shall be respont,ible for;
- a. Review of (1) all plant administrative procedures required by Technical Specification 6.8 and changes thereto, (2) all programs i required by Technical Specification 6.8 t:nd changes thereto, (3) changes to the Waterford 3 Emergency Operating Procedures required to implement the requirements of NUREG 0737 and NUREG 0737, Supplement 1, as stated in Generic Letter 82-33, and (4) any other proposed procedures or changes thereto as determined by the General Manager, Plant Operations;
- b. Review of all proposed tests and experiments that affect nuclear l
safety;
- c. Review of all proposed changes to Appendix "A" Technical Specifications;
- d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;
- e. Review ofinvestigations of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager, Plant Operations and to the Safety Review Committee;
- f. Review of all REPORTABLE EVENTS;
- g. Review of unit operations to detect potential hazards to nuclear safety;
- h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the General Manager, Plant Operations or the Safety Review Committee;
O WATERFORD 3 UALin' ASSURANCE CHAPTER 1 REV 4.0
- Ent N PROGRAM MANUAL R TYPE: C1.31 PAGE: 15 OF 21 4.10.3 The PORC shall meet at least once per calencar month and as convened by the PORC Chairman. gl 4.10.4 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions shall consist of the Chairman and three members.
3 4.10.5 The PORC shall be responsible for:
- a. Review of (1) all plant administrative procedures required by Technical Specification 6.8 and changes thereto, (2) all programs required by Technical Specification 6.8 and changes thereto, (3) changes to the Waterford 3 Emergency Operating Procedures required to implement the requirements of NUREG 0737 and NUREG 0737, Supplement 1, as stated in Generic Letter 82-33, and (4) any other proposed procedures or changes thereto as determined by the General Manager, Plant Operations;
- b. Review of all proposed tests and experiments that affect nuclear safety;
- c. Review of all proposed changes to Appendix "A" Technical Specifications;
- d. Review of all proposed changer, or modifications to unit systems or equipment that affect nuclear .%fety;
- e. Review of investigations of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to
- the General Manager, Plant Operations and to the Safety Review l Committee;
- f. Review of all REPORTABLE EVENTS;
- g. Review of unit operations to detect potential hazards to nuclear safety;
- h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the General Manager, Plant Operations or the Safety Review Commi'be; m /
j l i ATTACHMENT Vll TO W3F198-0013 QAPM Table of Contents Revision 18 Changes affecting QAPM Chapters 1 through 18 to-Revision 18
, . , ~ ,---.--y ,-, .c-.-, - , - , -. y e-3-vr ir - wr-v,
4 Waterford 3 Quality Assurance Program Manual Revision 18 TABLE OF CONTENTS C h a pte r 1 Org s niza tion . .. ... . . . . . ...... ... . . . .... . .. .. . . ... . . . . . . .. . ... . . . . . . . . . . . . .. .. .. . . . . . . . . . .. .. . . . . . . . . . . . . . ... Attachment 7.1 - Waterford 3 Organization................................................................ 21 C hapter 2 - Quality Ass ura nce Prog, am..................................................................... ... 22 Attachment 7.1 - Quality Assurance Program Documentation................................... 33 Attachment 7.2 - Regulatory Guidance Documents................................................... 37 Attachment 7.3 - 10CFR50, Apnendix B Compilance................................................ 45 Attachment 7.4 - Terms And Definitions...... ... .. .... ...... ... . .. ... ... ......... .... . . ... .. ..... ..... . . . . .. 4 8 C h a pte r 3 Des ig n C o ntrol.. . . .. .. .. . . .... . . . . . . .. . . .. ... . .. ... . . . . .... ... . . . . .. . .. . . . .. . . . . . . . .. .. . . . .. ... . . . . . . . . .. . . 6 7 C hapter 4 Proc urement Document Control................................................................ 75 Cnapter 5 Instructions. Procedures, and Drawings................................................... 80 t C ha pter 6 - Doc u men t Control.............................................................. ...... ................... 86 Chapter 7 - Control of Purchased Materials, Equipment, and Services..................... 91 Chapter 8 -Identification and Control of Materials, Parts, and Components............ 98 C hapter 9 - Control of Special Processes................................ ...................................103 C h a pte r 10 - In s pec tio n . ...... . . . . . . .. ... . .. .... . ..... .. .. . . . ........ ... .. .... . ..... .. .. . . .. . . ..... . . . . . ... .... . . . . . . .. . 108 C h a pter 1 1 - Tes t Co n trol. . ... . .. ..... .. ........ ..... . . . . . ........ .. . . . ..... .. . . . .... . . ..... ... .. . .. .. ... . . .. . .. .. .. . . . 1 16 Chapter 12 Control of Mes.suring and Test Equipment............................................121 Chapter 13 - Handling, Storage, Packaging and Shipping.........................................126
- Chapter 14 - Inspection, Test, and Operating Status..................................................131 Chapter 15 - Nonconforming Materials, Parts or Components..................................134 C ha pter 16 - C orrective Action..................................................................................... 13 9 Chapter 17 - Quality Assurance Records....................................................................144 C ha p ter 18 _- A ud its .. . ... . ... .... . .. ... . .. .. .. .... . . . .. .. ..... .. ................ . . . . . . . . ... .. ... . . . .... . .. . . . .. .. .. .. . . . .. . 148 -
LIST OF EFFECTIVE PAGES 1 - 155 Revision 18 1
cheek one 'NOT APPLCAntaa O PORC REEUEST/APPRSVAL PACE g ouALrtED REviaWER O DEPARTMENTAL
/ROCEDURE NO.: QAFM Chapters 118 REVISION NO.: 18 CHANGE: !
TITLE: Waterford 3 Quality Assuranco Program Manual EFFECTIVE DATE: taln ier (1f different from approval date) TYPE OF ACTION: Check One New Procerfure O Tcmporary Procedure O Expiration Date Revision @ Deletion O , Ch:noe O Ch6nge Notice (CN) O Final Approval Due Deviation O Expiration Date Edit: rial Correction (EC) O The change is editorial or typographicsl as defined in Section 3,7 of W2.109. Identify the applicable condition (s) by number:
# DESCRIPTION OF REQUEST: Revised fonnat in scardance with Waterford 3 Management Minual procedures W2.109 & W1.110. Due to format requirements, all individual Chapter revision levels were eliminated and new sut. sequent Table of Contents revision level (18) is used throughout.
CHAPTER 1, para. 4.8.1.11.b - moved section to Director, Quality (para. 4.7.1.2.6), para. 4.9.6 - deleted reference to initial year of operation, para. 4.13.1.1 - changed ' Supplier Quality Assurance
- to ' Material Requirements *, para. 4.13.1.2.e - deleted ' site specific', para. 4.13.1.2.g - aded ' quality
.ontrol' and para. 4.16 - added 'Inc.* sfter *Entergy Operations *, CHAPTER 2, para. 4.10 & 5.7.6 -
chrnged " Supplier Quality Assurance
- to
- Material Requirsments', para. 8.4.3.9 - added ' Materials.
Purchasing & Contracts Administrative Procedures *, Attachenant 7.1, identification 88 - deleted from
# REASON FOR REQUEST:
YES N/A YES N/A Technical Review Attached: E, O. 50.59 Review Attached: O S Qu:lified Review Attached: O, a 50.54 Review Attached: E O PREPARER: fde / MAwj! ATE: j0//7/c77 TECHNICAL REVIEWER: QUALIFIED REVIEWER: /) /A DATE: TE: N//f/c > SUPERVISOR: M Ent - DATE: 10/4e197
- GROUP / DEPT. HEAD (CI.cle One) REVIEW / APPROVAL: W/ % DATE: :2e. ,,n. o y GM, PLANT MANAGER (Circle One) REVIEW / APPROVAL
- z (A) /n2 _ pATE: . .
VICE PRESIDENT, OPERATIONS APPROVAL *TUM/WA/ rd.CNDATE: 1D 'L*3 [O { CN APPROVAL (Supervisor): ~4) / 'g' - DATE: l CN APPROVAL (On-Shift SS or CRS): A) / 4 DATE: ,; APPLICABLE CONDITIONS (Deviatloas & Temponwy procedures only): /.) / a . I vtnmirn fuseMQpgN necessary.
~
COPY No. -
, , . ,, w --- , , , . . , , . - , . , . , , - . . , --,--.n. , - , -.---n.--.-...c, - -,
REQUEST / APPROVAL PAGE (Continuation Page) PROCEDURE NO,: QAPM REVISION NO.: 18 CHANGE: TITLE: _ Waterford 3 Quality Assurance Program Manual , DESCRIPTION OF REQUEST: (continued) Desenption "which includes the Corporate site '
'~
based Materiah, Purchasing & Contracts Department *, deleted from Approval & Control
- With the I exception of those pertaining to the Matenals, Purchasing & Contracts group. These exceptions will be approved by the Manager. Materials, Purchasing and Contracts with concurrence by the Director, Site Support", Identification #12 added ' Materials Purchasing & Contracts Administrative Procedures". CHAPTER 4, pera.1.1,5.1.2,5.1.4.4 7 & 11 - added "Inc.* after 'Entergy Operations", ;
yara.1.2 added "Entergy Operations, Inc." before and parenthesis around 'EC para. 4.1, 5.1.1, 5.2.2 & 3 added ' assurance
- after ' quality", para. 4.2.1 & 3 - deleted " site spet. , , para. 4.2.4 -
changed 'quakty classification
- to ' procurement or safety classification *, deleted "related' and 'when applicable" and at,ded ' assurance and technical" after
- quality", para. 4.2.5 - added "QL,lity control *,
para. 4.2.7 - deleted in its entirety, para. 5.1.2 - added ' structures, systems' a'.ter *re:sted parts", para. 5.1.3 - changed ' quality classification" to ' procurement or safety classification' and added
'Prccurement and safety classificatk,,) are invoked to conform with committed to,*. para. 5.1.4.2 -
changed "quakty* to ' procurement or safety *, para. 5.1.4.9 - added 'non commercial grade item" before ' safety related', para. 5.1.4.11 - changed ' warehouse
- to ' Stores Operations *, para. 5.1.5 -
added " inspection plan or both" after ' documents' and ' safety related* after
- intended *, para. 5.2.1 -
changed ' revision
- to ' change' and para. 5.2.4 added 'and electronic" after
- electrical *. Chapter 5, Jara. 5.1.1 - changed woming from 'shall have* to 'shall use'. CHAPTER 7, para.1.1,5.2.2.3 5 & 8, .
5.3.3, 5.4.2, 5.7.2 & 3 - added *Inc." after 'Entergy Operations *, para.1.3 added *assuranco' after
'4Jakty", para. 4.2.1 & 2 - deleted ' site specific *, para. 5.1.1 & 4 added *(not commercial grade)*
aft:r " safety related*, para. 5.1.4 deleted "when applicable
- and para. 5.2.1 - changed ' Site Business, S rvices" to ' Site Support", para. 5.4.1 - added " quality control' before ' receipt" and changed ' safety' to " quality", para. 5.5.1 changed ' material parts and equipment that are essential to the safety r lated functions of structures systems and components
- to
- items", para. 5.5.2 - added " grade' between ' commercial" and ' item *, deleted
- listing", changed ' receipt inspection requiremt nts' to
'acceptr.nce methods
- and added 'or equivalent' after 'altemate", para. 5.5.4 - added *or inspection plan' after ' documents". CHAPTER 10, para. 5.1.2.1, 5.1.5 & 5.7.2 - added *Inc.' after ' Ente,gy
_ Operations", para. 5.1.2.3 - added ' NOTE
- CHAPTER 15, para 1.2 - changed " required" to
, allowed", para. 5.5.1 changed ' scrap" to " dispose". Appendix C moved to Chapter 2 as Att:chment 7.4, changed definition of " Procurement Classifications
- along with ' Quality Related Table" to conform to those changes, also changed definitions of Adverse Condition, Cause (Root Cause), .
Jondition Adverse to Quakty, Corrective Action, Nonconforming Condition (Nonconformance), and Significant Adverse Condition (Significant Condrtion Report). Appendix A - moved to Chapter 2 as Attachment 7.2. Appendix B - moved to Chapter 2 as Attachment 7.3. Forward & Policy Statement - deleted. REASON FOR REQUEST: (continued)
e l l l QUAllTV ASSURANCE PROGRAM i CHANGE REVIEW FORM P',OPOSED CHANGE:
- 1) Revise the QAPM to rehect organttetion name changes associated with the abgnment of Matenals. Purchasing and Contracts reporting to the h:ecossae's based Vice Presidsnt. Opersbons Support and the communication chain to Site Support, included is the change from *Suppher QA' to
' Mat:nals Requirements
- and ' Warehouse
- to
- Stores
- 4 2) Add the M6tenats. Purch6+ing & Contracts Admmistrattve manual as the document containing the responsibiktes and procedures used by MP&C m the performance Cady activities.
continued on page 2 l 10CFR50.54 REVIEW:
- 1. Does the proposed change represent a reduction of commitment Yes O No to the QA Program description previously accepted by the NRC?
4 Explain: See Attached, l
- 2. If item 1 above is YES, does the proposed r nange include the O Yes C No 0 N/A i
basis to conclude that the revised prograr s incorporating the change continues to meet the criterie d 10CFR50 Appendix B and other previously accepted FSAR commitments? Explain: 24t6 l /b60Adnt4 f/7/97
//
Reviewed By: / QA Repisp en$tive d Date RECOMMENDATION: m Does not represent a lessening of commitment and it can be implemented immediately. Represents a lessening of commitment, however, the change has sufficient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore, it should be submitted to the NRC for acceptance prior to implementation. Represents a lessening of commitment with Insufficient basle to determine continued compilance. Therefore, the change should not be processed. 7!? 2 Recommended By: QA Supervisor Date DISPOSITION:
" Approved for Implementation O Disapproved
- Approved for submittal to the NRC for accept nc ,
N '
/
/A T/ 7 ,2 Approved By: ^^ " r:;:
/ /~[ ' Dale i
QAP-018 R6.0 Attachment 7.1 R Type: J3.11
e 2 QUALITY ASSURANCE PROGRAM CHANGE REYlEW FORM CONTINUED PROPOSED CHANGE (COSTINUED)
- 3) Authorize the Director, Materials, Purchasing & Contracts to approve MP&C procedures. The QAPM required concurrence by the Director, Sitg Support with approval by the Manager, Materials, Punhasing & Contracts. _ _
- 4) Change the definitions of Procurement classifications to standardize the defmitions throug.hout the nuclear facilities and lleadquarters.
- 5) Administrative changes for clarification and consistency of language and terminology used throughout t! e nuclear organizations, in accordance with 10CFR50 Appendix B ,10CFR21, ANSI N45.2.2 N45.2.6 er MP&C Administrative Procedure manual, such as adding "Inc." after "Entergy Operations", or adding " Assurance" after " Quality".
- 6) Reformat all chapters in accordance with Waterford 3 Management Manual prcredure W2.110 " Procedure Format Standards". Move Appendix A,B & C into Chapter 2 as Attachment 7.2,7.3 & 7.4 respectively. Delete Forward &
Policy Statement in its entirety. 1 10CFR 50.54 REVIEW:(CONTINUED) CHAPTER I REVISION 16.0 parat,.wh 4.6.1.k.2 (4.6.1.11.hs . Moved section to Director, Quality (para. 4.7.1.2.1). Director, Nuclear Safety & Regulatory Affairs is not responsible for tu activity, paragraph 4.9.6 Deleted reference to initial year of operation. Editorial change, no longer necessary, paragraph 4.13.l.a_ (4.13.1.1) Ch.mged from " Supplier Quality Assurance" to " Material Requirements". Name change with organizational responsibilities and reporting chain the same. paragraph 4.13.1.b.5 (4.13.1.2.e) Deleted " site specific". It is the responsibility of the Vice President, Operations Support to select vendors and contractors for the entire Entergy Operations, Inc. (EOI) nuclear organization. paragraph 4.13 l.b.7 (4.13.1.2.g) Added " quality control". Chrification of the level of receipt inspection performed in language consistent with ANSI N45.2 and ANSI N45.2.6 paragraph 4.15 Added "Inc." after "Entergy Operations". Editorial change to the legal name of the corporation. DISCUSSION: None of the changes represent a lessening of commitments and clarify the organizational structure and responsibilities of the Vice President, Operations Support. CHAPTER 2 REVISION 12.0 paragraph 4.10 Changed from " Supplier Quality Assurance" to Material Requirements". Name change with organizational responsibilities and reporting chain the same, paragraph 5.4.3.1 (5.4.3.9) Added Mates als, Purchasing & Contracts Administrative Procedures, identifies the procedure manual used by Materials, Purchasing and Contracts to perform activities in support of Waterford 3.
4 3 payraph 5.7.5 Changed from " Supplier Quality Assurance" to " Material Require, ants". Name change with organiational responsibilities and reporting chain the same.
,Attaebment 7.1 Changed identification # 6:
Deleted from Description,", which includes the Corporate site based Materials, Purchasing and Contracts Department". Deleted from Approval and Control,",with the exception of those pertalning to the Materials, Purchasing and Contracts group These exceptions will be approved by ne Manager, Materials, Purchasing and Contracts with concurrence by the Director, Site Support. Added: Identification # 12: MATERIALS, PURCHASING & CONTRACTS ADMINISTRATIVE PROCEDURES Added Description,"A set of procedures which prescribe activities and responsibilities within the Materials l Purchasing & Contracts organintion." l Added Approval and Control," Prepared by cogninnt personnel within Materials, Purchasing & Contracts. Quality Related procedures shall receive a quality related review. Approved by the Director, Materials, Purchasing & Contracts, issued and controlled by Materials, Purchasing & Contracts." l DISCUSSION: None of the changes represent a lessening of commitments and clarify the organintional structure and respons'bilities of the Vice President, Operations Support and the Director, Materials, Purchasing and Contracts. The addition of the Materials, Purchasing & Contracts Administrative Manualis provided to ensure that procedures atTectmg Waterford 3 Safety Relateo structures, systems, components, services c.nd activities are included in the Quality Assurance Program Manual. 'the approval chain for procedures requires preparation at the Process Owner level and Director level approval instead of Director concurrence. MP&C Managers ensuie a commitments management system, 10CFR50.59 and quality review of procedures is performed for the nuclear sites and headquarters prior to final approval and implert.ents, tion. CHAPTER 4 REVISION 6,0 paragraph 1.1 Added "Inc." after "Entergy Operations". Editorial change to the legal name of the corporation. paragraph 1.2 Added "Entergy Operations, Inc." before and parenthesis around "EOl". Clarification of the use of the abbreviation EOl in the procedure text. paragraph 4.1 Added "Assuran:c" after " Quality". Clarification using terminology from 10CFR50 Appendix B and ANSI N45.2. paragraph 4.2.1 & 4.2.} , Deleted " site specific". It is the respor.sibility of the Vice President, Operations Support to select vendors and contractors for the entire Entergy Operations, Inc. (EOl) nuclear organiution.
0 4 paragraph 4.2.4 Changtd "quality classification" to " procurement or safety classifications", deleted "related" and "w hen applicable" and added " assurance and technical" after " quality". Terminology consistent with the responsibilities and language in the MP&C administrative procedures. paragrsph 4.2.5 Added " quality control". Clarificat on i of the level of receipt inspection performed in language consistent with ANSI N45.2 and ANSI N45.2.6 paragraph 4.22 Deleted in entirety. Redundant with 4.2.4 paragraph 5.1.1 Added " Assurance" after" Quality". Clarification using terminology from 10CFR50 Appendix B and ANSI N45.2. paragraph 5.l.2 Added "Inc." after "Entergy Operations". Editorial change to the legal name of the corporation. Added " structures. systems" after"related parts,", Language change to be consistent with 10CFR50 Appendix B and ANSI N45.2. i paragraph 5.1.3 Changed " quality classification" to " procurement or safety classification" and added " Procurement and safety classifications are invoked to conform with committed to,". Clarification of the language to be consistent with . requirements and procedures in the MP&C Admin!strative Procedures. , , paragraph 5.1.4.b ! (5.1.4.2) Changed " quality" to " procurement or safety". Clarification of language to be consistent with the requirements and procedures in the MPAC Administrative Procedures. Purchase order documents use procurement classifications and contract documents use safety related and non safety related classifications, paragraph 5.1.4 (d. e, f, n. A k) (5.l.4.4. 5,6,7 & 11) Added "Inc." after "Eatergy Operations". Editorial change to the legal name of the corporation. pernaraph 5.1.4.1 (5.l.4.9) Added "non commercial grade item" before " safety related". Safety related (not commercial grade) suppliers are j i a on the EOl Qualified Suppliers List. Dedication of Commercial Grade items is determined on an as needed basis and
- invoked at the time of procurement. 10CFR21 does not require commercial grade item suppliers be on a licensee Qualified Suppliers List.
paragraph 5.l.4.k (5.1.4.11) Changed " warehouse" to " Stores Operations". Department name change to be consistent at each nuclear facility. paragraph a 5.l.5 Added "inspectiott plan or both" after " documents" and " safety related" after "in: ended". Language is consistent with 10CFR21 for dedicating a cornercial grade item for use as a basic component. paragraph 5.2.1 Changed " revision" 'o "chtsge". Char.ges are reviewed, approved and incorporated into procurement documents. ' Changes may occur at any time, nodust at the time of procurement and the method of incorporation is dependent on the change and when the change occurred. t 9
, ~ . . _ . - -. . , , . , , . . . .-._. .- m - ., ,- - - . _ , ,. , , , - . _ , , . , . ,-
5 p ragraph 5.2.2 md 5.2.3 Added " Assurance" after " Quality" Clarification using terminology from 10CFR50 Appendix B and ANSI N45.2. paragraph 5.2.4 Added "and electronic" after " electrical". Safety related electronic equipment in a harsh environment requires qualification. DISCUSSION None of the changes represat a lessening of commitments. Administ. 've changes are for clarification such as the addition bf"Inc." after "Entergy Operations" and " Assurance" after "Q ..ity" Additionally, each site is using the same procurement classification for Safety related (Level 1), Commercial Grade (Level 2), Special Scope /.' ugmented Quality (Level 3) and Balance of Plant (Level 4). Ea.h site uses the terminology " Procurement contained either in 10CFR50 Appendix B 10CFR21, ANSI N45.2 and'or ANSI N45.2.6. The MP&C Administrative Procedures use language and terminology from 10CFR 50 Appendix B,10CFR21 and implementing ANSI standards in order to ensure consistency throughout the Nuclear organization. CHAPTER 5 REVISION 6.0 paragraph 5.1.1 Changed wording from "shall have" to "shall use" Clarification due to new Site Procedures W2.109 " Procedure Development, Review & Approval", and W2.110 " Procedure Format Standards". CHAPTER 7 REVISION 8.0 pa ra gra pb I.1, 5.2.2. (e, d, e,1-), 5.3.3, 5.4.2, 5.7.2, & 5.7.3 (5.2.2.3,4,5, & 8) Added " lac." after "Entergy Operations". Editorial change to the legal name of the corporation. paragraph 1.3-Added " Assurance" after " Quality". Clarification using terminology from 10CFR50 Appendix B and ANSI N45.2. paregraph 4.2.1 and 4.2.2 Deleted " site specific". It is the responsibility of the Vice President, Operations Support to select vendors and contractors for the entire Entergy Operations, Inc. (EOI) nuclear organization. paragraph 5.1.1 and 5.l.4 Added "(not commercial grade)" after " safety related" In accordanct with 10CFR21 suppliers of Commercial Grade items are not remired to be on a Qualified Suppliers List. The method of dedication of commercial grade items is determined on a case by case basis at the time of procurement and is accomplished and documented prior to use of the item as a basi: component. paragraph 5.1.4 Deleted "when applicable". Procurement documents to suppliers of safety related (not commercial grade) items require compliance with 10CFR21. paragraph 5.2.1 Changed " Site Business Services" to" Site Support". Identifies the communication chain for the Site Support organization and the on site Materials, Purchasing & Contracts departrnent. , paragraph 5.4.1 Added " quality control" before " receipt" and changed " safety" to "quahty". Clarification of the level of receipt inspection performed in language consistent with ANSI N45.2.6. The QAPM requires a quality control receipt inspection on quality related items, not just safety related items.
6 paragraph 5.5.1 Changed " material, parts, and equipment that are essential to the safety related functions of structures, systems and components" to " items". Terminology consistent with 10CFR21 ensures that commercial grade items att evaluated and dedicated prior to use as a basic component. I paragraph 5.5.2 ! Added " grade between " commercial" and " item", deleted " list!. , and ch nged " receipt inspection requirements" to
" acceptance methods" Added "or equivalent" after "altemats", fermino'sgy consistent with 10CFR21. Allows the use of an identical item, an approved alternate or an approved equiva:e 1.
paragraph 5.5.4 Added "or inspection plan" after " documents". Dedication activities are the responsibility of the licensee not the supplier. Clarified that dedication may occur at receipt or installation and that the acceptance method is specified in the procurement documents, in the inspection plan or in a combination of both. DISCUSSION None of the changes represent a lessening of commitments. Most are administrative, such as the addition of"Inc." after "Entergy Operations"," Assurance" after " Quality" and " Commercial Grade item" in lieu of shortened versions. Other changes are incorporated in order to comply with language and terminology contained either in 10CF R$0 Appendix B, 10CFR21 ANSI N45.2, ANSI N45.2.6 and'or the QAPM. The MP&C Administrative Procedures use language and terminology from 10CFR 50 appendix B,10CFR 21 and implementing ANSI standards to ensure consistency throughout the Nuclear Organization. CHAPTER 10 REVISION 7,0 paragraph 5.1.2.s,5.1.5,5.7.2 (5.1.2.1) Added "Inc." after "Entergy Operations" Editorial change to the legal name of the corporation. paragraph 5.1.2.c (5.1.2.3) Added " NOTE:" clarifying control of Materials, Purchasing & Contracts Administrative Procedures. DISCUSSION These changes do not represent a lessening of commitments. CHAPTER 15 REVISION 8.0 paragraph 1.2 Changed " required" to " allowed". Appears to be a typographical error. paragraph 5.5.3 Changed " scrap" to " dispose . EOl evaluates and disposes oti.ca conforming material, it may not be in the best interest of the corporation to " scrap" all nonconforming material. DISCUSSION Changes do not represent a lessening of commitments. Changes clarify the MPAC practice for disposal of nonconforming material. 1 0 _ __ . . , . , - 7.. , _ _ . - - k
_ _ _ . _ . _ _ _ _ _ ~_- - - . . - i 7 APPENDIX C REVISION 6.0 (Chapter 2 - Attachment 7.4) , i Changed the dennition of" PROCUREMENT CLASSIFICATIONS" to the following: i Procurement classincation Level I (L1) is assigned to those items that are procured as safety related under the
- responsibility of the suppliers approved 10 CFR $0 Appendix B type quality assurance program with 10 CFR part 21 -
reportability imposed on the supplier, t i Procurement classification Level 2 (L2) is assiped to those items that are safety related or items meeting the definition of commercial grade, procured under the responsibility of the site quality assurance program for which Entergy Operations, ] Inc assumes the responsibility defined in 10 CFR Part 21. ) Procurement classification Level 3 (L3) is assiped to those items which are not safety related but fall into Augmented
- Quality /special scope as described in the site design basis licensing documents.
4 Procurement classification Level 4 (L4) is assiped to those permanent plant items which are defined as non safety related ,
; (Balance of Plant) for which no quality assurance requirements are imposed.
Procurement classification Level Pending (LP) is assigned to those items pending review by Materials Purchasing & J Contracts for as.lgning the correct procurement classification. j Procurement classification Level Exempt (LE) is assiped to non permanent plant items (exempt). 1 Below is a matrix relating former and current procurement classifications (procurement quality levels), Chanpd Quality
- j. Related table to conform to Procurement Classification changes.
l 1 FORMER CURRENT
- QCl/Qi (SAFETY RELATED) Li (SAFETY RELATED)
QC2/Q2 (SPECIAL SCOPE) _ L2 (SAFETY RELATED/ COMMERCIAL ' i- ORADE/ DEDICATED) QC3/Q3 (SAFETY RELATED/ COMMERCIAL L3 (AUGMENTEDQUALITY) L GRADE / DEDICATED) i QC4/Q4 (BALANCE OF PLANT) L4 (BALANCE OF PLANT)- i; QCE/QE (EXEMPT) ; LE (EXEMPT) NONE LP (PENDING) , l
- DISCUSSION I
- ne definitions for procurement classifications are standardized throughout Entergy Operations, Inc, and represent a name i
change only, ne associated definitions are essentially the same with minor rewording to satisfy the different site's QAPM language. 1 1 _. _. __ ____- ._ . . _ . - _ .-_ _ _-.-___ _ .~ .. _ __ _ - _ - _ . _ - . _ . _ _ _ , . _ . . - . . . _ _.
CHANGE
#1 - Reformatted all chapters in accordance with Waterford 3 Management Manual procedure
/ W2.110 " Procedure Format Standards", moved Appendix A,B & C into Chapter 2 as Attachments 7.2,7.3 & 7.4 respective!y, and deleted Forward & Policy Statement in its entirety.
#2 Revised QAPM to reflect organization name changes associated with the alignment of i
Materials, Purchasing and Contracts (MP&C) reporting to the headquarters based Vice President, Operations support and the communication chain to Site Support, included is the change from " Supplier QA" to " Materials Requirements" and "Warehousc" to " Stores."
#3 - Added MP&C Administrative manual as the document containing the responsibilities and procedures used by MP&C in the performance of daily activities.
#4 - Authorized the Director, MP&C to approve MP&C procedures.
#5 - Changed the definitions of Procurement classifications to standardize the definitions throughout the nuclear facilities and Headquarters.
#6 - Administrative changes for clarification and consistency of language and terminology used throughout the nuclear organizations, in accordance with 10CFR50 Appendix B,10CFR21, ANSI N45.2.2, N45.2.6 or Mr>&C Administrative Procedure manual, such as adding "Inc." after "Entergy Operations" or adding " Assurance" after " Quality" BASIS FOR NO REDUCTION OF COMMITMENT 5
Changes clarify the organizational structure and responsibilities of the Vice President, Operations Support and Director, Materials, Purchasing and Contracts. Administrative changes such as the eddition of "Inc." after *Entergy" and " Assurance" after " Quality" are for clarification and standardizatio of language throughout Entergy Operations, Inc. Other changes are incorporated in order to comply } with language and terminology contained either in 10CFR50 Appendix B,10CFR21, ANSI N45.2.2 and/or N45.2.6 and/or the QAPM. None of these changes represents a lessening of commitment.
- Chapter 1 Rev.16 (4.6.1.k.2) mcVed to Director, Quality (4.7.1.2.1). Director, Nuclear Safety &
Regulatory Affairs i= not responsible for this activity (4.9.6) deleted reference to initial year of operation (4.13.1.a) changed from " Supplier Quality Assurance" to " Material Requirements" (4.13.1.b.5) deleted " site specific" (4.13.1.b.7) added " quality control" (4.15) added "Inc." after Entergy Operations (editorial only, no revision bars required). Chapter 2 Rev.12 (4.10) changed " Supplier Quality Assurance " to
- Material Requirements" (4.5.3.1) added Materials, Purchasing & Contracts Administrative Procedures (5.7.5) changed from " Supplier Quality Assurance" to " Material Requirements"(Attachment 7.1 #6) Deleted i
from Description "which includes the Corporate site based Materials, Purchasing and Contracts Department", deleted from Approval & Control"with exception of those pertaining to the Materials, Purchasing and Contracts group. these exceptions will be approved by the Manager, Materials, Purchasing and Contracts with concurrence by the Director, Site Support." (Attachment 7.1 #12) added Materials, Purchasing & Contracts Administrative Procedures. Chapter 4 Rev. 6 (1.1) added "Inc," after "Entergy Operations (editorial only, no revision bars required) (1.2) added "Entergy Operations, Inc." before and parenthesis around "EOl"(4.1) added "Assuranca" after " quality" (4.2.1 & 4.2.3) deleted " Site specific" (4.2.4) changed " quality classification" to " Procurement or safety classifications", deleted "related" and "when applicable" and added " assurance and technical" after " quality" (4.2.5) added " quality control" (4.2.7) deleted in entirety, redundant with 4.2.4 (5.1.1) added " Assurance" after " Quality" (5.1.2) added "Inc." after "Entergy Operations (editorial only, no revision bars required) and added " structures, 4 systems" after "related parts" (5.1.3) changed " quality classification" to " Procurement or safety classification" and added " Procurement and safety classifications are invoked to conform with committed to," f
. - , - - . . .r., , ,<-~ .-e, , . .,. -. --_ , .-. , ,-- ,, _, . -,- - . , , . - , .- .n r
___ _ _ _ _ . _ . - _ _ _ . . - _ . _ _ _ _ - - _ ~ _ _ _ - - -_ . (5.1.4.b) ch:nged "qu:lity" to "procur:m:nt or saf:ty" (5.1.4.d, o, f, g & k) add:d "Inc." cft:r "Ent:rgy Op rctions"(cditorial only, no revision bars required) (5.1.4.1) cdd:d "non commerci::l grade item" before " safety related" (5.1.4.k) changed warehouse" to " Stores Ope. tions" (5.1.5) added " inspection plan or both" after "doeurnents" and " safety related" after " intended" (5.2.1) changed " revision" to " change" (5.2.2 & 5.2.3) added " Assurance" after " Quality" (5.2.4) ; added "and electronic" after " electrical". ! Chapter 5 Rev. 6 (5.1.1) changed wording from "shall have" to "shall use". ! Chapter 7 Rev 8 (1.1, 5.2.2.c, d, e, h, 5.3.3, 5.4.2, 5.7.2 & 5.7.3) added "Inc." after "Entergy . ' Operations" (editorial only, no revisicn bars required) (1.3) added " Assurance" after " Quality" (4.2.1 & 4.2.2) deleted " site specific"(5.1.1 & 5.1.4) added "(not commercial grade)" after
" safety related" (5.1.4) deleted "when applicable" (5.2.1) changed " Site Business Services" to
" Site Support" (5.4.1) added " quality control" before " receipt" and changed " safety" to " quality" (5.5.1) changed " material, parts, and equipment t"at are essential to the safety related functions of structures, systems and components" to " items"(5.5.2) added " grade" between " commercial" and " item", deleted " listing" changed " receipt inspection requirements" to " acceptance methods", and added "or equivalent" after " alternate" (5.5.4) added "or inspection plan" after
" documents".
Chapter 10 Rev. 7 (5.1.2.a 5.1.5 & 5.7.2) added "Inc." after "Entergy Operations" (editorial only, no revision bars required) (5.1.2.c) added " NOTE". Chapter 15 Rev. 8 (1.2) chaaged " required" to " allowed" (5.5.3) changed " scrap" to " dispose". Appendix C Rev. 6 changed definition of Procurement Classifications and revised 0 Related Table to be consistent with classification changes. OAPM SECTIONS AFFECTED BY THIS CHANGE Chapter 1 Chapter 2 Chapter 4 Chapter 5 Rev.16 Rev.12 Rev. 6 Rev.6 4.6.1.k.2 4.10 1.2 5.1.1 4.9,6 5.4.3.1 4.1 ^ 4.13.1.a 5.7.5 4.2.1 4.13.1.b.5 Attachment 7.1 4.2.3 4.13.1.b.7 (#6 & 12) 4.2.4 4.2.5 4.2.7 5.1.1 5.1.2 5.1.3 5.1.4 b 5.1.4.1 5.1.4.k 5.1.5 5 2.1 5.2.2 5.2.3 5.2.4
Chrpt r 7 Chrphr 10 Chapt:r 15 App;ndix C R v.8 R:v.7 R:v.8 R:v. 6 1.3 5.1.2.c 1.2 Procurement Classifications 4.2.1 5.5.3 Q Related Table 4.2.2 5.1.1 5.1.4 5.2.1 5.4.1 5.5.1 5.5.2 5.5.4 I
A
- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.16.0 PROGRAM MANUAL PAGE: 8 OF 21
- j. Reviewing plant system problems and performance coi. terns;
- k. Examining plant operating characteristics, NRC lesuances (includes Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may Indicate areas for improving plant safety as part of the Independent Technical Review function. The Independent Technical Review functions include responsibility for:
- 1. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means ofimproving plant safety;
- 2. Maintaining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical;
- l. Maintaining SRC charters; and
- m. Performing independent reviews, safety examin?tions, and other review activities in support of the SRC and Technical Specification requirements.
4.7 DIRECTOR, QUALITY 4.7.1 The Director, Quality is responsible for the direction and administration of the Quality Assurance organization.
- a. The qualifications of the Director, Quality include as a minimum:
- 1. Graduate of a college or university with a Bachelor's degree in an engineering, science or related field, or equivalent capabilities;
- 2. A minimum of four years experience in quality assurance or a quality assuranca related activity with at least two of those years in the nuc! ear power industry as a manager or supervisor;
Waterford 3 Quality Assurance Program Manual Chapter i Organization Revision 18 4.6.1.9 Coordinating Nuclear Regulatory Commission interface; 3l 4.6.1.10 Reviewing plant system problems and performance concerns; 3 & 3l 4.6.1.11 Exaniining plant operating characteristics, NRC issuances (includes Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar design, which may indicate areas for improving plant safety as part of the Independent Technical Review function. The independent Technical Review functions include responsibility for: 3&3
- a. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety.
3,p&3 4.6.1.12 Malr.taining SRC charters; and 4.6.1.13 Performing independent reviews, safety examinations, and other review 13
~
activities in support of the SRC and Technical Specification requirements. l 4.7 g&3l Director, Quality 4.7.1 The Director, Quality is responsible for the direction and administration of the Quality Assurance organization, d.7.1.1 The qualifications of the Director, Quality include as a minimum:
- a. Graduate of a college or university with a Bachelor's degree in an engineering, science or related field, or equivalent capabilities; 12 & 15 A minimum of four years experience in quality assurance or a quality assurance related activity with at least two of those years in the nuclear power industry as a manager or supervisor;
- c. Experience in development and implementation of quality asserance prog.ams, plans, and procedures;
- d. Expertise in interpretation and application of Appendix B to 10CFR50 and related codes, standards, and regulatory guides;
- e. Knowledge of inspection and nondestructive testing requirements; 8
Wsterford 3 Ouality Assurarco Program Manual Chapter i Organization u Revision 18: 'l
- f. Ability to plan, organize, and administer a Quality Assurance program; and
- g. Ability to maintain an effecthie working relationship with employees, contractors, suppliers, government agancies, and the public, i
4.7.1.2 The primary quality related responsibilities of the Director, Quality include:
- a. Planning, organizing, and administering the Quality Assurance program;
- b. Developing, reviewing, and concurring with the content of the Waterford 3 Quality Assurance Program Manual and changes thereto; >
- c. Developing Quality Assurance Procedures (QAPs);
- d. Assisting in establishing that portion of the Training program that addresses quality assurance; 3&3
- e. Advising, reviewing, and concurring on the scope and content of quality assurance training and indoctrination programs for personnel performing quality related activities;
- f. Providing requested inspection training to personnel performing quality -
related activities;
- g. Certifying Lead Auditors and Inspectors;
- h. Assuring effective implementation of the Quality Assuiance program through a ecmprehensive system of reviews, assessments, and the performance or monitoring of nondestructive examinations and other special processer; lll l blainhining surveillance of plant activities to provide independent verification that these activities are performed correctly and that human i enw . are reduced as much as practical; 3
J. Ensuring tnat quelity reviews are conducted for quality related implementing procedures and design changes, including drawings 3 & 3 and specifications, to ensure the inclusion of quality requirements; 9 c , ,
*9 g WATERFORD 3 CHAPTER 1 REV.16.0
- Ent QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: Ci.31 PAGE: 13 OF 21 4.9.4 All alternate members shall be appointed in writing by the SRC Chairmsn to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
4.9.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advise to the SRC. g 4.9.S The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 _b__ months thereafter. 4.9.7 The quorum of the SRC necessary for the performance of the review and audit function shall consist of a minimum of five members or of not less than a majority of the composition of members in paragraph 4.9.3 above, whichever is greater. No more than a minority of the members shall have line responsibility for operation of the plant. 4.9.8 The SRC shall be responsible for the review of: 4 a. The safety evaluations for (1) changes to procedures, equipment, g~ or systems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safetv question;
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59;
- d. Proposed changes to Technical Specifications or the Operating License;
- e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance;
- f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety;
- g. Ail REPORTABLE EVENTS;
}
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 7 4.9.2.6- Radiological safety; 4.9.2.7 Mechanical and electrical engineering; and 4.9.2.8 Quality assurance practices. 4.9.3 The SRC shall be composed of at least five members, including the Chairman. Members of the SRC may be from within the Entergy Operations Inc. organization or from organizations external to EOl. The qualifications of members selected for the SRC shall be in accordance with Section 4.7 of ANSI /ANS3.1-1978. 4.9.4 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two attemates shall participate as voting members in SRC activities at any one time. ( 4.9.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advise to the SRC. W4,9'.64 The "9C shall meet at least once per 6 months. 18l 4.9.7 : The quorum of the SRC necessary for the performance of the review and audit function shall consist of a minimum of five members or of not less than a majority of the composition of members in paragraph 4.9.3 above, whichever is greater. 13 l No more than a minority of the members shall have line responsibility for , operation of the plant. 4.9.8 The SRC shall be responsible for the review of: 4.9.8.1 The safety evaluations for (1) changes to procedures, equipment, or cystems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; 4.9.8.2 Proposed changes to procedures, equipment or systams which involve an unreviewed safety question as defined in 10 CFR 50.59; ) 4.9.8.3 Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; 12
wg t ' g Ent WATERFORD 3 UAIM ASSURANCE CHAPTER 1 : REV.18,0 R TYPE: C1.31 1 PROGRAM MANUAL PAGE: 19 OF 21
- c. Thermal hydraulic analysis;
- d. Nondestructive analys!s;
- e. Metallurgical evaluations; i
i f. Fuel fabrication and related services; i , g. Reactor engineering and special nuclear material control and
- accountability; and i
'h. Entergy Operations, Inc. welding program.
4.13 VICE PRESIDENT, OPERATIONS SUPPORT l 4.13.1 The Vics President, Operations Support reports directly to the Executive ! Vice President & Chief Operating Officer, and is responsible for:
.a. ] Administering corporate support functions in the areas of
- radiological protection, radicactive waste management, chemistry,
! environmental services, operations, maintenance, outage < management, security implementation (Access Authorization ) ' and Fitness For Duty), emergency planning, technology transfer, and central licensing; providing oversight of site Health Physics -
- and Chemistry activities; and managing the Plant Support and Assessment, Information Systems, Supplier QA, and Materials, Purchasing and Contracts groups. It is the responsibility of the
- Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program; and
- b. Providing the direction and administration necessary relative to the 1 following listed primary quality related responsibilities as they relate
- to the Waterford 3 Quality ' Assurance Program
1
- 1. Evaluating quality assurance programs and activities of Waterford 3 suppliers, contractors, and EOl shared
- services of quality related items, spare parts, and services i through reviews, surveillances, cnd audits;
- 2. Conducting pre-award evaluations for quality requirements of vendors, suppliers, and contractors where applicable;
[
Jl Waterford 3 Quality Assurance Program Manual- Chapter 1 Organization
= Revision 18 Oy 4.12.1.2 Plant transient analysis; 4.12.1.3 Thermal hydraulic analysis;
-4.12.1.4 Nondestructive analysis; 4.12.1.5 Metallurgical evaluations; 4.12.1.6 Fuel fabrication and related services; 4.12.1.7 Reactor engineering and special nuclear material control and l accountability; and i
4.12.1.8 Entergy Operations, Inc. welding program. 4.13 Vice President, Operatiorm Support 4.13.1 The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer,- and is responsible for: iM;13,1;12 7 Administering corporate support functions in the areas of radiological protection, radioactive waste management,' chemistry, environmental services, operations, maintenance, outage management, security implementation (Access Authorization and Fitness For Duty), 13l emergency planning, technology transfer, and central licensing; providing-~ oversight of site Health Physics and Chemistru activities; and managing . the Plant Support and Assessment, Information Systems, Material 18 Requirements, and Materials, Purchasing and Contracts groups. It is the respons.ibility of the Vice President, Operati_ons Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program; and
- 4.13.1.2 - Providing the direction and administration necessary relative to the '
following listed primary quality related responsibilities as they relate to the Waterford 3 Quality Assurance Program:
- a. Evaluating quality assurance programs and activities of Waterford 3 suppliers, contractors, and EOl shared services of quality related _13l items, spare parts, and services through reviews, surveillances, and audits; 18
. ____ s
/
e- Ent WATERFORD 3 UALITY ASSURANCE CHAPTER 1 R-TYPE: C1.31 REV.18.0'
- PROGRAM MANUAL PAGE: 20 OF 21
- 3. Maintaining a qualified suppliers list (QSL) for use in procuring safety related items, spare parts, and services;
' 4. Performing design review and fuel fabrication audits as necessary to ensure that nuclear fuel procured for use by Entergy Operations is designed and fabricated in accordance with applicable codes, standards, and regulations;
- 5. Selecting site specific vendors and contractors based upon technical, quality and commercial evaluations;
- 8. Purchasing and receipt of equipment, parts, materials, and supplies in support of Waterford 3 operations and station modifications; 7.- Administering a receipt inspection program to assure acceptability of quality related materials, parts, and components;
- 8. Coordinating the processing and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, l
including maintenance and design changes;
- 9. Establishing quality assurance and technical requirements in quality related procurement documents;
- 10. Maintaining storage conditions necessary to sustain material quality; and
- 11. Processing and securing material traceability data to support historical reference.
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization
- Revision 18
- b. Conducting pre award evaluations for quality requirements of vendors, suppliers, and contractors where applicable;
- c. Maintaining a qualified suppliers list (OSL) for use in procuring safety related items, spare parts, and services;
- d. Perforraing design review and fuel fabrication audits as necessary to ensure that nuclear fuel procured for use by Entergy Operations, Inc. is g desigeed and fabricated in accordance with applicable codes, standards, and regulations;
- e. Selecting vendors and contractors based uoon technical, quality and commercial evaluations; 3l
- f. Purchasing and receipt of equipment, parts, materials, and supplies in support of Waterford 3 operations and station modifications;
- g. 1 Administering a quality control receipt inspection program to assure acceptability of quality related materials, parts, and components; 3l
- h. Coordinating the processing and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, including maintenance and design changes;
- i. Establishing quality assurance and technical requirements in quality related procurement documents,
- j. Maintaining storage condiuons necessary to sustain material quality; and
- k. Processing and securing material traceability data tc support historical reference.
4.14 Waterford 3 Personnel Waterford 3 personnel are responsible for adherence to the requirements 11 delineated in this QA Program Manual and its implementing procedures. Waterford' 3 personnel are also responsible for identifying and reporting conditions a.1 verse to quality and for identifying program or procedural enhancements. 19
an. g- Ent - WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 REV.12.01 ' R-TYPE: C1.31 PROGRAM MANUAL PAG;I: 4 OF 11 s 4.7 DIRECTOR, TRAINING 12 The Director, Training is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Operations Training; Simulator Training; ; Maintenance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Director, Training are listed in Chapter 1. 12 e.8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the j following programs and organizaf.onal units: Safety and Eligineering Analysis; l Procurement / Programs Engineering; and Design Engineering. The primary ! quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.g VICE PRESIDENT, ENGINEERING - The Vice Preticient, Engineering reports directly to the Executive Vice President
& Chief Operaag Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1.
- 4.10 ;VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support reports directly to the Executive Vice
-- President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, cutage management, security, emergency planning, technology transfer, and centrallicensing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Information Systems, Supplier QA, EOl shared services, and Materials, Purchasing and Contracts groups. It is the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Quality Assurance program.
. Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program - Revision 18- .
4.8 Director, Design Engineering The Director, Design Engineering is responsible for ensuring the developrrient and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The primary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 Vice President, Engineering The Vice President, Engineering reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The priniary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1. f 4.10 - - Vice President, Operations Support The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technoicgy transfer, and central licensing; oversight of site Healtn Physics and Chemistry activities; and mar,agement of the Plant Support and Assessment, Information Systems, Material Requirements, EOl shared services, and Materials, Purchasing 11 & 18 l Purchasing and Contracts groups. It is the responsibility of the Vice PresidenC Operations Suppert to assure that these functions performed for Waterford 3 are performed in .udance with the requirements of the Waterford 3 Quality Assurance ;ra m . 25 l
, u
f g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 2 :REV.12.0 R-TYPE: C1.31 PROGRAM MANUAL PAGE: 8 OF 11
- e. Design Engineering Administrative Manual (DEAM);
- f. Plant Modification and Construction procedures;
- g. Nuclear Safety and Regulatory Affairs procedures; and
- h. Nuclear Training procedures.
i 5.5 IDENTIFICATION OF SAFETY RELATED STRUCTURES, SYSTEMS, AND COMPONENTS 5.5.1 The Quality Assurance Program applies to all activities associated with quality related structures, systems, and components to an extent commensurate with their importance to safety. FSAR Table 3.2-1, Appendix A to this manual, and the Waterford 3 Q-List provide safety related classifications of plant structures, systems, and components; and identify those items subject to 10CFR50 Appendix B requirements. 5.5.2 Procedures provide further guidance for the identification of safety and quality related structures, systems, components and related activities to assure that the appropriate level of Quality Assurance program requirements are applied. 5.5.3 Procedures for the preparation and control of procurement documents provide guidance for spare and replacement part classification determination. These procedures invoke applicable codes, standards, regulations, FSAR requirements, and the Q-List classifications for determining "' classification of spare or replacement parts or materials. 5.6 RESOLUTION OF DISPUTES 5.6.1 Disputes involving quality, arising from a difference of opinion between Entergy Operations departments, are normally resolved via direct interaction between the managers involved. If a satisfactory resolution < cannot be reached, the disputes are resolved through higher levels of management. The Director, Quality should be consulted for disputes 3l involving the Waterford 3 Quality Assurance program interpretation and implementation.
9 Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 ' ; 5.4.3.7 Nuclear Safety and Regulatory Affairs procedures; ] 5.4.3.8 Nuclear Training procedures; and 5.4.3.9" 3 Materials, Purchasing & Contracts Administrative Procedures. 3l 5.5 Identification of Safety Related Structures, Systems, and Components E 5.5.1 The Quality Assurance Program applies to all activities associated with quality related structures, systems, and components to an extent commensurate with their importance to safety. FSAR Table 3.2-1, Chapter 2 Attachment 7.2, and the Waterford 3 Q-List provide safety related classifications of plant structures, ' systems, and components; and lJentify those items subject to 10CFR50 Appendix B iequirements. 5.5.2 Procedures provide further guidance for the identification of safety and quality related structures, systems, components and related activities to assure that the appropriate level of Quality Assurance program requirements are applied. 5.5.3 Procedures for the preparation and control of procurement documents provide guidance for spare and replacement part classification determination. These procedures invoke applicable codes, standards, regulations, FSAR requirements, and the Q-List classifications for determining the classificauon of spare or replacement parts or materials. 5.6 Resolution of Disputes 5.6.1 Disputes involving quality, arising from a difference of opinion between Entergy Operations, Inc. departments, are r:ormally resolved via direct interaction between the managers involved. If a satisfactory resolution cannot be reached, the disputes are resolved through higher levels of management. The Director, Quality should be consulted for disputes involving the Waterford 3 Quality 12 Assurance program interpretation and implementation. 5.6.2 Disputes involving quality, arising from a difference of opinion between EOI entities, contractors, or suppliers, are normally resolved through the appropriate manager. If a satisfactory resolution cannot be reached, the disputes should be elevated to the Vice President, Operations, if necessary. The Director, Quality 12l - should be consulted for disputes involving other EOl entities. The Vice l President, Operations Support and/or the Director, Quality should be consulted 3l for disputes concerning contractors or suppliers. 29 1
O g WATERFORD 3 CHAPT 4R 2 REV.12.0 _
- Ent QUALITY ASSURANCE PROGRAM MANUAL R-TYPE: C1.31 PAGE: 10 OF 11
- b. Personnel performing activities c,at affect quality are trained and qualified in the principles, techniques, and requirements of the activity being performed;
- c. Proficiency and qualification of personnel performing or verifying activities are maintained by retraining, reexamining, and/or
- recertifying on a periodic basis, as applicable;
- d. Proficiency testing is utilized to determine qualifications when education, experienco, and training cannot be verified by other means; and
- e. Train;ng and qualification documentation is maintained which describes the objectives, content, attendance, tests, acceptance criteria, and the functions personnel are qualified to perform.
5.7.4 The training program for Waterford 3 personnc!is further described in Chapter 13 of the FSAR and in implementing procedures. 5.7.5 - Waterford 3 Quality Assurance or the Entergy Operations Supplier QA organization conducts audits of other organizational units, such as suppliers and contractors engaged in quality related activities at or for Waterford 3 to verify that personnel are adequately indoctrinated, trained, and qualifieo. 5.8 CONTROLLED CONDITIONS FOR PERFORMING ACTIVITIES Quality related activities shall be accomplished under controlled conditions by personnel witii the necessary skills to attain the required quality. Activities shall be performed using appropriate equipment, under suitable environmental conditions and with the assurance that prerequisites for the given activity have been satisfied. 5.9 MANAGEMENT REVIEW OF THE QUALITY ASSURANCE PROGRAM 5.9.1 The Vice President, Operations ensures that a management assessment of the Quality Assurance program is conducted periodically (not to 3 exceed 24 months) by a qualified independent organization.
L '- *: i L .. Waterford 3 Quality Assurance Program Manual- Chapter 2 Quality Assurance Program . - # Revision 18? j j i
' 5.7.3.5 Training and qualification documentation is maintained which describes the objectives, content, attendance, tests, acceptance criteria, and the function's personnel are qualified to perform.
[ 5.7.4 The training program for Waterford 3 personnel is further described in Chapter 13 of the FSAR and in implementing procedures. {5.7.5l 7 Waterford 3 Quality Assurance or the Entergy Operations, Inc. Material } Requirements organization conducts audits of other organization units, 18 such as suppliers and contractors engaged in quality related activities at or for-
~
.Waterford 3 to verify that personnel au adequately indoctrinated, trained, and
- l. qualified.
1 5.0 ! - Controlled Conditions For Performing Activities i 5.8.1 Quality related activities shall be accomplished under controlled conditions by . i ._ personnel with the necessary skills to attain the required quality. Activities shall be performed using appropriate equipment, under suitable environmental
- conditions and with the assurance that prerequisites for the given activity have :
- been satisfied.
- 5.9 Management Review of the Quality Assurance Program h
!. -5.9.1 The Vice President, Operations ensures that a management assessment of the-I - Quality Assurance program is conducted periodically (not to exceed 24' months) 12 l
' by a ' qualified independent organization.
[ [ 5.9.2 . The information from these management assessments, the trend report, and l . summaries of the Quality Assurance program status are used by the Vice 1 President, Operations to evaluate the effectiveness of the Quality Assurance c proy.im and to take action, as riecessary,- to assure that the program complies with applicable regulatory requirements. y i t 1 31
,,n.--w, ,,m. . , , _ . . . . --4. m , - - ., . , . , . ,,.--,,,,,,..n, , - , ,.,.y ,
_ .o QUALITY ASSURANCE PROGRAM DOCUMENTATION T Identification Description Approval and Control g::S
- 5
- 5. Quality Assurance A set of procedures prepared and Prepared by Quality Assurance and %
Procec;ures Manual issued to specify and control the coordinated with other organizations activities of the Quality Assurance as applicable. Approved by the organization. Director, Quality. Issued and 12 l controlled by Site Business Services .
- 6. Site Support Procedures A set of procedures which Prepared by cognizant personnel ., O prescribe activities and within the Site Support Group.
responsibilities within the Site Quality related procedures shall 2>h o C Support Group, which includes the receive a quality related review. All $m N Corporate site based Materials, Purchasing and Contracts procedures shall be approved by the E$$ Director, Site Support, with the EyO department. exception of those pertaining to the $g$ Materials, Purchasing and jz c4 Contracts group. These 12 exceptions will be approved by
- r-Q the Manager, Materials, Purchasing and Contracts with concurrence by the Director, Site Support. Issued j > :P Q and controlled by Site Business, o Services. "hM>
o m z .@- m3
- 7. Design Engineering A set of procedures which Prepared by cognizant personnel Eoa '
Oma Procedures prescribe activities and responsibilities within the Design within Design Engineering, Qualit/ '$N" related procedures shall receive a , z Engineering organization. quality related review. Approved E by the Director, Design Engineering a or Departinent Manager. Issued " b
- a7d controlled by Site Business i
Services.
. Js QUAllTY ASSURANC' E PROGRAM DOCUMENTATION M Identification Description _ Approval and Control
- 5. Quality Assurance A set of procedures prepared and Prepared by Quality Assurance and Procedures Manual issued to specify and control the coordinated with other organizations i activities of the Ous;ity Asse:ance as applicable. Approved by the organization. Director Quality. Issued and -12l j
controlled by Site Business Services ,
~
10
- 6. Site Support Proceduree A set of procedures which Prepared by cognizant pe6sonnel prescribe activities and within the Site Support Group.
responsibilities within the Site Quality related precedures shall Support Group. receive a quality related review. Approved by the Director, - 12 & 18 Site Support. Issued and centrolled by Site Busine:>3 10 Services.
- 7. Design Engineering A set of procedures which Prepared by cognizant cersonnel Procedures presciibe activities and within Design Engineering, Quality responsibilities within the Design related procedures shall receive a Engineering organization. quality related review. Approved by the Director, Design Engineering or Deparfrnent Manager. Issued and controlled by Site Business 10---
Servn:es. Chapter 2 Rev.'18 L # Attachment 7.1 (Page 2 of 4) 34 ____ - n.
identification QUALITY ASSURANCE PROGRAM DOCUPAENTATION Description _ Approval and Control ge 2
- 10. NuclearSafety and A set of procedures which Prepared by cognizant personnel Regulatory Affairs presenbe activities and within Nuclear Safety and Regulatory responsibilities within the Nuclear Affairs. Quality related procedures ;
Procedures Safety and Regulatory Affairs shall receive a quality related review. l organization. Approved by the Director, Nuclear Safety and Regulatory Affairs. ' pl - Issued and controlled by Site Business Services T0 3 > lE
- 11. Nuclear Training A set of procedures which Prepared by cognizant personnel 0r>
O Procedures prescribe actmties and within NuclearTraining. Quality $m responsibilities within the Nuclear related procedures shall receive a E$% Training Organization quality related review. Approved Egg 4 by the Director, Training. 12
*l zgo issued and controlled by Site 5 z **
Business Services.. F$ El
'U>30
> -j I O' >
m> 1
==O yZyAm E
- 0mO3 c N
,"N-4z *4a>
.a .N o
4 l _____=______........_._... L_________ _=__.....-..
\'
QUALITY ASSURANCE PROGRAM DOCUMENTATION Identification Description Approval and Control
- 10. Nuclear Safety and A set of precedures which Prepared by cognizant -
Regulatory /. lairs presenbe activities and . . personne!within Nuclear Safety Procedures responsibilities within the Nuclear and Regulatory Affairs. Quality Sclaty and Regulatory Affairs ' . related procedures shall receive organization. a quality related review.- ~jg Approved by the Director, , Nuclear Safety and Regulatory Affairs. 12 l-Issued and controlled by Site -~ Business Services. p
- 11. Nuclear Training - A set of procedures which Prepared by cognizant personnel Procedures prescribe activities and . within_ Nuclear Training. Quality responsibilities within the Nuclear related procedures shall receive a Training Organization quality related review.' Approved by the Director. Training. Issued 12 l
- controlled by Site Business if Servu:es..
10 & 12 t 71f Materials, Purchasing ' A set of procedures, which Prepared by cognizant pers55nef-
& Contracts prescribe activities and within Materials, Purchasmg &
Administrative r responsibilities within the Materials, Contracts. Quality related 18
~-
Procedures - Purchas.og & Contracts orocedures shall receive a quality organization. related review.' App <oved by the Director, Materials, Purchasing &
' Contracts,. Issued and controlled by Materiais,' Purchasing & Contracts.
I Chapter 2'Rev.118 Attachment 7.1 (Page 4 of 4) 36
Y g WATERFORD 3 CHAPTER 4 REV.6.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 Id.tOGRAM MANUAL PAGE: 1OF6 TITLE: EFFECTIVE DATE: 06/04/97 PROCUREMENT DOCUMENT.
CONTROL PREPARED BY: Mhm C. Duk DIRECTOR, QUALITY: " REVIEWED B C VICE PRESIDENT, OPERATIONS:(f ,_ y 1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterford 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the originalitem. l 1.2 Services performed by other EOl sites (shared services) are obtained from those sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July i977 (which endorses ANSI N45.2.13-1976," Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants.") 2.2 USNRC Regulatory Guide 1.89," Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Plants." 3.0 DEFINITIONS 3.1 See Appendix C
WATERFORD 3 CHAPTER 4 REV. 6.0
- Ent QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 2OF6 4.0 RESPONSIBILITIES 4.1 DIRECTOR, bESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development of procedures for defining the performance and documentation of engineering evaluations, as requested or mandated; to establish requirements and controls when original te:hnical or quality requiremente cannot be determined for spare or replacement parts.
4.2 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Sepport is responsible for: 4.2.1 Ensuring the development of procedures for defining the vendor and contractor selection process and oefining the process for the preparation of purchase orders and contracts for site specific procurement; 4.2.2 Ensuring that approoriate procedures are developed and implemented for activities related to the preparation, review, approval, and control of requisitions; and procurement planning; 4.2.3 Vendor selection; coordination of contractor selection; preparation, review, and issuance of site specific purchase orders and contracts to support the procurement of material, equipment, spare, and replacement parts, and service; 4.2.4 Identifying quality classifications and establishing the related quality requirements, when applicable; 4.2.5 Administration of a receipt inspection program to assure acceptability and maintenance of quality related materials, parts, and components; 4.2.6 Coordinating the processing and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, including maintenance and design changes; and
Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control ' Revision 18 1,0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterford 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations, Inc. Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the original item.
'1.2 Services performed by other Entergy Operations, Inc. (EOl) sites (shared g & gl services) are obtained from those sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.89, " Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Plants" 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Director, Design Engineering The Director, Design Engineering is responsible for ensuring the development of procedures for defining the performance and documentation of engineering evaluations, as requested or mandated; to establish requirements and controls when original technical or quality assurance requirements cannot be determined for spare or replacement parts. 3l 75
,e 'l-g- Ent WATERFORD 3 QUAUTY ASSURANCE CHAPTER 4 ' REV. 6.0 - R-TYPE: C1.31 PROGRAM IWANUAL PAGE: 2 (F 6 4.0 RESPON8181UTIES 4.1 DIRECTOR, bESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the d:#,ep,T,6nt of procedures for defining the performance and documentation of engineering evaluations, as requested or mandated; to establish requirements and cxi,Luis when original technical or quakty requirements cannot be determined for spare or replacement parts. 4.2 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President, Operations Support is responsible for: 4.2/1 Eruuring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation of purchase ordws and contracts for site specific procurement; 4.2.2 Ensuring that appropriate procedures are developed and implemented for actMties related to the preparation, review, approval, and control of requisitions; and procurement planning;
- 4.2.3 Vendor n, election; coordination of contractor selection; preparation, review, and issuance of site specific purchase orders and contracts to support the procunement of material, equipment, spare, and replacement parts, a,1d service;
,41.4 = identifying quality classifications and establishing the related quality requiremente, when applicable;
' 4.2.5 Administration of a receipt inspection program to assure acceptability and maintcnance of quality related materials, parts, and components; 4.2.0 Coordinating the process 5ng and review of procurement documents for equipment, parts, matenals, and services in support of plant operations '
and station modifications, including maintenance and design changes; and
. t g- Ent WATdRFORD 3 QUALITY ASSURANCE CHAPTER 4 R-TYPE: C1.31 REV. 6.0 '
PROGRAM MANUAL PAGE: 3OF6 4.2.7 Establishing quality assurance and technical requirements in quality related procurement documents. 5.0 DETAILS 5.1 PREPARATION OF PROCUREMENT DOCUMENTS 5.1.1 Procedures are provided for the preparation, control, and review of procurement documents to ensure that quality requirements are correctly stated, inprocess and final inspection criteria are defined, and that appropriate controls are established. t 5.1.2 Entergy Operations personnel are responsible for the preparation of ' l procurement documents for safety related parts, components, systems, and services. Their responsibilities include procurement planning; preparation, review, approval, and control of procurement documentation; and > sisting in vendor selection. 5.1.3 Organizations preparing procurement documents shall determine the applicable quality classification in accordance with approved procedures, codes, standards or design bases. 5.1.4 Procurement documents, as applicable, shall:
- a. State the materials, parts, and components or the scope of work or services to be provi ed by the vendor;
- b. Identify the quality classification of the item or service being procured;
- c. Contain or invoke, by reference, the technical requirements, including drawings; test and specification requirements; special instructions for activities such as designing, handling, identification, special processes, fabrication, cleaning, erecting, packaging, shipping, extended storage, etc.; and applicable regulations, codes, and industrial standards;
=_ . _ - _ - - - _ . . ..
e Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control
~ Revision 18 J 4.2 Vice President, Operations Support The Vice President, Operations Support is responsible for:
_ . . . ~ 34.2.1 Ensuring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation of purchase orders and contracts for procurement; gl 4.2.2 Ensuring that appropriate procedures are developed and implemented for activities related to the preparation, review, approval, and control of requisitions; and procurement planning; 4.'2.3 ' Vendor selection; coordination of contractor selection; preparation, review, and issuance of purchase orders and contracts to support the procurement of 18l material, equipment, spare, and replacement parts, and services; 74.2.4 Identifying procurement or safety classifications and establishing the quality assurance and techrHeal requirements; 3 12.5: ' Administration of a quality control receipt inspection program to assure acc ptaMity and maintenance of quality related materials, parts, and con.,t.ients; and 4.2.6 Coordinating the processing and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station raodifications, including maintenance and design changes. M! mn
. no 76
g WATERFORD 3 CHAPTER 4 REV.8.0 /
- Ent QUALITY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 3OF6 4.2.7 ' Establishing quality assurance and technical requirements in quality related procurement documuats.
5.0 DETAILS 5.1 PREPARATION OF PROCUREMENT DOCUMENTS 5.1.1 Procedures are provided for the preparation, control, and review of procurement documents to ensure that quality requirements are correctly stated, inprocess and final inspection criteria are defined, and that appropriate controls are established. 5.1.2 Entergy Operations personnel are responsible for the preparation of procurement documents for safety related parts, components, systems, and services. Their responsibilities include procurement planning; preparation, review, approval, and control of procurement documentation; and assisting in vendor selection. ' 5.1.3 Orga;.izations preparing procurement documents shall determine the applicable quality classification in accordance with approved procedures, codes, standards or design bases. 5.1.4 Procurement documents, as applicable, shall:
- a. State the materials, parts, and corry ; ants or the scope of work or services to be provided by the venLar;
= bc identify'the quality classification of the item or service being procured;
- c. Contain or invoke, by reference, the technical requirements, including drawings; test and specification requirements; special instructions for activities such as designing, handling, identification, special processes, fabrication, cleaning, erecting, packaging, shipping, extended storage, etc.; and applicable regulations, codes, and industrial standards;
_.____________J
.)' [
Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control 5Rsvision118l g 5.0 PROCEDURE 5.1 Preparation of Procuremant Documents EU 3 Procedures are provided for the preparation, control, and review of procurement documents to ensure that quality assurance requirements are correctly 18 stated, inprocess and final inspection criteria are defined, and that appropriate
-l controls are established, i5.1;2f Entergy Operations, Inc. personnel are responsible for the preparation of .
procurement documents for safety related parts, structures, systems, 18 l components, and services. Their responsibilities include procurement planning!- preparation, review, approval, and control of prtcurement documentation; and j assisting in vendor selection. 7).1.37 Organizations preparing procurement documents shall determ!r.1 the applicable procurement or safety classification in accordance with approved procedures. Procurement and safety classifications are invoked to conform with _18
. committed to, codes, standards or design bases.
5.1.4 Procurement documents, as applicable, shall: 5.1.4.1 State the materials, parts, and components or the scope of work or services to be provided by the vendor; 1 {5.1114.2y Identify the procurement or safety classification of the item or service 18l
~ -
being procured; 5.1.4.3 Contain or invoke, by reference, the tachnical requirements, including drawings; test and specification requirements; special instructions for activities such as designing, handling, identification, special processes, fabrication, cleaning, erecting, packaging, shipping, extended storage, etc.; and applicable regulations, codes, and industry standards; 5.1.4.4 ldentify the documentation (e.g., drawiry, specifications, inspection and fabrication plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test results of material) to be prepared, maintained, and/or submitted to Entergy Operations, fr.c. for information, review, and/or approval; 77
a _ _ . _ . _ _ _ _ _ s . g WATERFORD 3 CHAPTER 4 REV. 6.0
- Ent QUAUTY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 4 OF 6
, d. Identify the documentation (a g., drawings, specifications, inspection and fabrication plans, inspecten and test records, personnel and procedure qualifications, and chemical and physical test results of ma:erial) to be prepared, maintained, and/or submitted to Entergy Operations for information, review, and/or
- approval;
- e. Identify the Entergy Operations Quality Assurance Program requirements which must be desenbod and implemented in the vendor / contractor and subtier vendor quality assurance programs;
- f. Identify those records to be retained, controlled, and maintained by the vendor and those to be delivered to Entergy Operations prior to use or installation of the item;
- g. Establish the right of access for Entergy Operations and its agents to the vendor's facilities and records for source inspection and audits; i
- h. Identify the storage requirements and retention periods for records to be retained by the vendor;
- i. Specify, for safety related procurement, the requirement for vendors to comply with 10CFR21 for reporting defects and noncompliances which could create a substantial safety hazard; J. Establish measures for the identificabon, control, and disposition of items and services that do not meet procurement document requirements; and
- k. Procuremerrt documents for on-site work by a veMor service representative shall require that any materials or replacement parts, and required documentation, shall be subjected to receiving I inspection, records review, and warehouse issue by Entergy Operations. l 1
i
s , Waterford 3 Quality Assurance Program Manual Chapter 4 Procuremont Document Control ' Revision 18 > 5.1.4.5 Ifentify the Entergy Operations, Inc. Quality Assurance Program requirements which must be described and implemented in the vendor / contractor and subtier vendor quality assurance programs; 5.1.4.6 Identify those records to be retained, controlled, and maintained by the vendor and those to be deliverec .o Entergy Operations, Inc. prior to use or installation of the item; 5.1.4.7 Establish the right of access for Entergy Operations, Inc. and its agents to the vendor's facilities and records for source inspection and audits; 5.1.4.8 Identify the storage requirements and retention periods for records to be retained by the vendor; , (5.1.4.9 Specify, for non commercial grade item safety related procurement, the 18 l requirement for vendors to comply with 10CFR21 for reporting defects anF noncompliances which could create a substantial safety hazard; 5.1.4.10 Establish measures for the identification, control, and disposition of items and services that do not meet procurement document requirements; and ! '5.1.4 11- Procurement documents for on-site work by a vendor service representative shall require that any materials or replacement parts, and required documentation, shall be subjected to receiving inspection, records review, and Stores Operations issue by Entergy Operations, Inc. 3l 5.1.5 Where commercial grade items are to be used in safety related applications, the procurement documents, inspection plan, or both shall specify special inspections, tests, verifications, documentation c'r otner methods required to 3l assure suitability for the intended safety related applicaticn. 3l 5.2 Preparation of Requisitions for Spare and Replacement Parts 5.2.1 Orders for spare and replacement parts shall be requisitioned to specifications and codes equivalent to those specified for the original equipment or those specified by a properly reviewed and approved change. 3l 5.2.2 In those cases where the original item or part is safety related and is found to be commercial grade and without specifically identified quality assurance requirements, equivalent spare and repla ement parts may be procured 3l commercial grade provided the items are properly evaluated and dedicated for safety related use. 78
g- Ent WATERFORD 3 QUALITY ASSURANCE CHAPTER 4 REV 6.0 R-TYPE: C1.31 PROGRAM MANUAL PAGE: 5 OF G 5.1.5 ' Where commercial grade items are to be used in safety related spplications, the procu*ement documents shall specify special inspections, tests, verifications, documentation or other methods required to assure suitability for the intended application. 5.2 PREPARATION OF REQUISITIONS FOR SPARE AND REPLACEMENT PARTS 5.2.1 Orders for spare and replacement parts shall be requisitioned to specifications and codes equivalent to those specified for the original equipment or those specified by a properly reviewed and approved revision. 5.2.2 In those cases where the original item or part is safety related and is found to be commercial grade and without specifically identified quality requirements, equivalent spare and splacement parts may be procured commercial grade provided the items are prc,perly evaluated and dedicated for safety related use. 5.2.3 in those cases where the technical and/or quality requirements of the original item cannot be determined, an engineering evaluation shall be con'!.ded and documented by qualified individuals to establish the reauirements and controls,
- a. This evaluation shall assure that interfaces, safety, i iterchangeability, fit, environmental compatibility, and function are not adversely affected or contrary to the FSAR, applicable codes, standards, and regulations.
-.5.2.4 Replacement electrical equipment in harsh environments shall be qualified in accordance with regulatory guides and specifications.
5.3 REVIEW AND APPROVAL 5.3.1 As a minimum, procurement documents shall be reviewed to verify that the procurement document contains the appropriate requirements identified in 5.1.4.
Waterford 3 Qual;ty Assurance Program Manual Chapter 4 a Procurement Document Control Revision 18 5.1.4.5 Identify the Entergy Operations, Inc. Quality Assurance Program requirements which must be described and implemented in the vondortcontractor and subtler vendor quality assurance programs; l 5.1.4.6 Identify those records to be retained, controlled, and mainte.ined by the vendor and those to be delivered to Entergy Operations, Inc. prior to use l or installation of the item; 5.1.4.7 Establish the rir ht of access for Entergy Operations, Inc. and its agents to the vendor's facilities and records for source inspection and audits; 5,1.4.8 Identify the storage requirements and retention periods f r records to be retained by the vendor; 5.1.4.9 Specify, for non commercial grade item safety related procuren/at, the 18 requirement for vendors to comply with 10CFR21 for reportin noncompliances which could create a substantial safety hazard; 5.1.4.10 Establish measures for !!.e identification, control, and disposition of items and services that do not meet procurement document requirements; and 5 1.4.11 Procurement documents for on-site work by a vendor service representative shall require tnat any materials or replacement parts, and required documentat!on, shall be subjected to receiving inspection, records review, and Stores Operations lesue by Entergy Operations, Inc. 3l 5.1.5 I Where commercial grade items are to be used in safety related applications, the procurement documents, inspection plan, or both shall specify special -18l Inspections, tesk <erifications, documentation or other methods required to assure suitubt.ity for the intended safety related application. 3l 5.2 Preparation of Requisitions for Spare and Replacement Parts 5.2.1 Orders for spare and replacernent parts shall be requisitioned to specifications and codes equivalent to those specified for the original equipment or those j specified by a properly reviewed and approved change. 3l 5.2.2 ' ' In those cases where the originalitem or part is safety releted and is found to be ccmmercial grade and without t,pecifically identified quality assurance requirements, equivalent spare and replacement parts may be procured 3l commercial grade provided the items are properly evaluated and dedicated for safety salated use. 78
Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control Revision 18 ;
^ 5.2.3 ? In those cases where the technical and/or quality assurance requirements of the originalitem cannot be determined, an engineering evaluation shall be
~l 18 4
conducted and documented by qualified individuals to establish the requirements and controls. 5.2.3.1 This evaluation shall assure that interfaces, safety, interchangeability, fit, environmental compatibility, and function are not adversely affected or contrary to the UFSAR, applicable codes, standards, and regulations. 5.2.4 > Replacement electrical and electronic equipment in harsh environments 18l shall be qualified in accordance with regulatory guides and specifications. 5.3 Review and Approval 5.3.1 As a minimum, procurement documents shall be reviewed to verify that the procurement document contains the appropriate requirements identified in 5.1.4. 5.3.2 Reviews of procurement documents shall be performed by personnel who have access to pertinent informetion and who have an adequate understanding of the requirements and intent of the procurement documents. Performance of reviews shal! be documented to provide objective evidence of accomplishment. 5.3.3 M indepe' ndent review of procurement documents and subsequent revisions shall be accomplished prior to issuance to the vendor or contractor to assuie that appropriate quality requirements have been imposed. 5.4 Procurement Document s'hangas Procurement document changes are subject to the same degiee of control as utilized in the preparation of the original documents.
- 6.0 RECORDS None 7,0 ATTACHMENTS None 79
g- Ent WATERFORD 3 CHAPTER 5 REY.6.0 QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 2 OF 7 4.2 DIRECTOR, QUALITY The Director, Quality is responsible for assunng that a quality review of safety related Waterford 3 procedures, instructions, drawings, and specifications, to ensure the inclucion of applicable Quality Assurance Program requirements, is 1- accomplished, j 4.3 PLANT OPERATIONS REVIEW COMMITTEE (PORC) The PORC is responsible for reviewing and meking recommendations concerning procedures required by Section 6.8 of the Technical Specifications and others which are used to assJre the proper operation and maintenance of safety related equipment as determined by the General Manager, Plant Operations. 5.0 DETAILS 5.1 PREPARATION OF INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.1.1 hrocedures shall be written and implemented in accordance with applicable codes, standards, and regulations to provide a controlled method for preparing, reviewing, changing, and approving instructions, procedures, and drawings. Each department shall have a goveming procedure which describes the appropriate method for procedure development to assure consistency in preparation. The governing procedure shallincorporate the requirements of the Quality Assurance Program. 5.2 CONTENTS OF INSTRUCTIONS AND PROCEDURES 5.2.1 Instructions and procedures prescribing safety related act;vities shall identify any special equipment and conditions required to perform the activity, responsibilities, applicable quantitative and qualitative acceptance criteria, and provisions for documenting that activities were accomplished __ in accordance with the instructions and procedures.
i 5 Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 10 5.0 PROCEDURE 5.1 Preparation of Instructions, Procedures, and Drawings 5.1.1 Procedures'shall be written and implemented in accordance with applicable codes, standards, and regulations to provide a controlled method for preparing, reviewing, changing, and approving instructions, procedures, and drawings. Each department shall use a governing procedure whbn gl describes the 6ppropriate method for procedure development to assure consistency in preparation. The governing procedure shallincorporate the requirements of the Quality Assurann Program. 5.2 Contents of Instructions and Proced.:res 5.2.1 Instructions and procedures prescribing safety related activities shall identify any special equipment and conditions required to perform the activity, responsibilities, applicable quantitative and qualitative acceptance criteria, and provisions for documenting that activities were accomplished in accordance with the instructions and procedures. 5.2.2 The format of procedures may vary; however, procedures should include, as appropriate, the following elements: 5.2.2,1 Title; 5.2.2.2 Statement of applicability; 5.2.2.3 References; 5.2.2.4 Prerequisites'; 5.2.2.5 Precautions; 5.2.2.6 Limitations and Actions; 5.2.2.7 Main Body; 5.2.2.8 Acceptance Criteria; and 5.2.2.9 Checklists. 81
, - m -
g - WATERFORD 3 CHAPTER 7 REV. 8.0
- Ent QUAllTY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 1OF7 TITLE: CONTROL OF PURCHASED EFFECTIVE DATE: 06/04/97 MATERIALS, EQUIPMENT AND SERVICES ,
PREPAhED BY pt% 0. 9a DIRECTOR, QUALITY:
/k/
REVIEWED BY - VICE PRESIDENT, GPERATIONS: h/ ), v ,. - vg 1.0 PURPOSE 1.1 Safety related material, equipment, and services, whether purchased directly or through others, conforms to procurement document specifications as described in Chapter 4. Provisions are made, as appropriate, for source evaluation and l selection, review for objective evidence of quality, inspection at source, and l inspection upon delivery. In addition, products may be accepted by pre / post installation testing or qualification testing by Entergy Operations or an approved test laboratory. 1.2 Vendors' Quality Assurance Programs are reviewed at periodic intervals commensurate with the importance, quantity, and complexity of the product or services being purchased. These reviews may employ audits, surveillances, source verifications, independent inspections, or tests to verify that documentation, such as inspection records and certifications, are reliable and valid. 1.3 Proposals (bids or quotations) by vendors are reviewed to er,sure that no exceptions are taken which would violate safety, technical, or quality requirements. The program requirements for control of purchased material, equipment, and services are contained in approved written procedures. 1.4 Services parformed by other EOl sites (shared services) are obtained from those sites in accordance with documented agreements between the sites
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976," Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power olants.")
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18. ? 1.0 PURPOSE 1.1 Safety related material, equipment, and services, whether purchased directly or through others, conforms to procurement document specifications as described in Chapter 4. Provisions are mado, as appropriate, for source evaluation and selection, review for ob,40tive evidence of quality, inspection at source, and inspection upon delivery. In addition, products may be accepted by pre / post installation testing or qualification testing by Entergy Operations, Inc. (EOl) or an approved test laboratory. 1.2 Vendors' Quality Assurance Programs are reviewed at periodic intervals commensurate with the importance, quantity, and complexity of the product or services being purchased. These reviews may employ audits, surveillances, source verifications, independent inspections, or tests to verify that documentation, such as inspection records and certifications, are reliabis and valid. 1.3 ' ? Proposals (bids or quotations) by vendors are reviewed to ensure that no exceptions are taken which would violate safety, technical, or quality assurance requirements. The program requirements for control of purchased material, "l 18 equipment, and services are contained in approved written procedures, 1.4 Services performed by other EOl sites (shared services) are obtained from those 7l sites in accordance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.12-1976," Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976," Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 3.0 ' DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 91
. . - .- --.J
g WATERFORD 3 CHAPTER 7 REY. R.0 l
- Ent QUALITY ASSURANCE R TYPE:C1,31 m l
PROGRAM MANUAL PAGE: 2 OF 7 i 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses l ANSI N18.71976, " Administrative Controls and Quality Assurance for the i Operational Phase of Nuclear Power Plants.") 3.0 DEFINITIONS 3.1 See Appendix C l 4.0 RESPONSIBILITIES 4.1 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for: 4.1.1 Assisting in the establishment of quality assurance and technica' requirements in quality related procurement documents; and - 4.1.2 Reviewing selected requests for spare and replacement parts designated EQ to determine their technical and quality requirements, if required. 4.2 VICE PRESIDENT, OPERATIONS SUPPORT The Vice President. Operations Support is responsible for: 4 4.2.1 Ensuring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation j of purchase orders and contracts for site specif;c procurement; 4.2.2 ' Vendor selection, the coordination of contractor selection, and the
- prenration and issuance of site specific purchase orders and contracts to support the procurement of material, equipment, spare and replacement parts, and services; 4.2.3 Performing inspections of site storage facilities; and 4.2.4 Establishing and maintaining a qualified suppliers list through the conduct of pre-award evaluations, annual evaluations, periodic audits and surveillances.
+ . . - - .,
D Wate' ford 3 Quality Assurance Program Manual Chapter 7 Cor, trol Of Purchased Materials, Equipment, and Services '
- Revision' 18 -
4.0 RESPONSIBILITIES 4.1 Director, Design Engineering The Director, design Engineering is responsible for: 4.1.1 Assisting in the establishment of quality assurance and technical requirements in quality related procurement documents; and 4.1.2 Reviewing selected requests for spare and replacement parts designated EQ to determine their tect.nical and quality assurance requirements, if required. 4.2 Vice Presider,t, Operations Support i . The Vice President, Operations Support is responsible for: 4.' 2.1 Enauring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation of purchase orders and contracts for procurement; 3l 4.2.21 Vendor selection, the coordination of contractor selection, and the preparation and issuance of purchase orders and contracts to support the procurement of 1G l material, equipment, spare and replacement parts, and services; 4.2.3 Performing inspections of site storage facilities; and , 4.2.4 Establishing and maintaining a qualified suppliers list through the conduct of pre-award evaluations, annual evaluations, periodic audits and surveillances. 4.3 Directors / Managers , Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in support of their departmental activities. 4.4 Director, Quality 8 The (airector, Quality is responsible for assuring that appropriate quahty standards are maintained throughout the procurement process. 92 4
.,--,s c -r- . . - ,%~,m --.e. , -, - ,_ .-e n_. - -. ,, , , . . . . -- - ...---v-- , , - . - .-- m-,.--e . . - ,
g- Ent WATERFORD 3 QUALUY ASSURANCE CHAPTER 7 REV. 8.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 3 OF 7 4.3 DIRECTORS / MANAGERS Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in support of their departmental activities. 4.4 DIRECTOR, QUALITY 8 The Director, Quality is responsible for assuring that appropriate quality standards are maintained throughout the procurement process. 5.0 DETAILS 5.1 QUALIFICATION OF VENDCRS 5.1,1 Safety related equipment, materials, and services shall be obtained from vendors, contractors, and consultants contained on a qualifed suppliers list (OSL), when required, to assure compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and consultants shall be qualifed for inclusion on the QSL through an evaluation of their technical and qualdy assurance capabilities for providing safety related items and services. Quality Assurance evaluations shall be conducted by appropriately certified personnel and the results documented and maintained in accordance with quality records management procedures.
5.1.2 criteria
The evaluation of venoors shall be based on one or more of the following a. The vendors ability to comply with the requirements of the Quality Assurance Program as applicable to the type of material, equiprnent or % vice being procured; b. A review of the records and performance of vendors who have previously provided items and services similar to the type being procured; or c. A survey of the vendors facilities and/or quality assurance program to determine the vendofa capability to provide a specified service or product which r9eets design, manufacturing and quality requirements.
0 g WATERFORD 3 CHAPTER 7 REV. 8.0 4
- Ent QUM ASSURANCE R TYPE: C1.31 m i I
PROGRAM MANUAL PAGE: 4 OF 7 l 5.1.3 Reevaluation and requali8 cation of vendors on the QSL shall be modo on a periodic basis, as specified in applicable procedures. 5.1.4 ' Suppliers of safety related structures, systems, components, and, services for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21, when l~ applicable, for reporting defects and noncompliances that could create a substantial safety hazard. 5.2 PROCUREMENT Pl.ANNINC i ? 5.2.1 Procurement planning is a shared responsibility between the Site i Business Services and Operations Support organizatiorw. [ 5.2.2 Based on the relative importanos, complexity, or quantity of the item or i servios, planning activities shall establish the following in accordance with approved procedures: e
- s. The need to perform surveillance (s) of the vendors /subtier vendors activities and/or products during the manefacturing proosss; i b.
l The need to participate in the inspection hold point program established by the vendor or to establish Entergy Operations
- mandatory hold points.;
- c. The identHication of documents, such as, qualifications of l
personnel or procedures to be generated and submitted to Entergy Operations for approval prior to start of work; 1 d. i Tim identNication of schedules, plans, drawings, design documents, test 4nspection results, etc., to be subm#tted to Entergy Operations for approval or information; t e. ! The method for acceptance ofiterr.: or services by Entergy l Operations; ' f. The scope and frequency of audits /surveillances required to monitor performance and/or maintain vendor qualifications; m
j Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 s 5.0 PROCEDURE 5.1 Qualification of Vendors , 15.1.1 Safety related I,not commercial grade) equipment, materials, and services 18l services shall be ebtained from vendors, c.ontractors, and consultants contained ~~ on a qualified suppliers list (OSL), when required, to assure compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and consultants shall bo qualified for inclusion on the QSL through an evaluation of their technical and quality assurance capabilities for providing safety related items and services. Quality Assurance evaluations shall be conducted by i appropriately certified personnel and the results documented and maintained in accordance with quality records management procedures. 5.1.2 The evaluation of vendors shall be based on one or more of the following criteria: 5.1.2.1 The vendor's ability to comply with the requirements of the Quality Assurance Program as applicable to the type of material, equipment or service being procured; 5.1.2.2 A review of the records and performance of vendors who have previously provided items and services similar to the type oeing procured; or 5.1.2.3 A survey of the vendor's facilities and/or quality assurance program to determine the vendor's capability to provide a specified service or product which meets design, manufacturing and quality assurance requirements, j 5.1.3 Re evaluation and requalification of vendors on the QSL shall be made on a periodic basis, as specified in applicable procedures. 15.1.4 ? Suppliers of safety related (not commercial grade) structures, systems, -18l components, and, services for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21 for reporting defects and noncompliances that could create a substantial safety 3l hazard. 93
k . g WATERFORD 3 CHAPTER 7 REV.8.0
- Ent QUAUTY ASSURANCE R TYPE: C1.31 %
PROGRAM MANUAL PAGE: 4 OF 7 5.1.3 Re-evaluation and requalification of vendors on the QSL shall be made on a periodic basis, as specified in applicable procedures. 5.1.4 Suppliers of safety related structures, systems, components, and, services for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21, when applicable, for reporting defects and noncompliances that could create a substantial safety hazard. 5.2 PROCUREMENT PLANNING 5.2.1 Procurement planning is a shared responsibility between the Site Business Services and Operations Support organizations. 5.2.2 Based on the relative importance, complexity, or quantity of tne item or service, planning activities shall establish the following in accordance with approved procedures: l
- a. m.
The need to perform surveillance (s) of the vendors /subtier vendors activities and/or products during the manufacturing process; b. The need to participate in the inspection hold point program established by the vendor or to establish Entergy Operations mandatory hold points.; c, The identification of documents, such as, qualifications of personnel or procedures to be generated and submitted to Entergy Operations for approval prior to start of work; d. The identification of schedules, plans, drawings, design documents, test / inspection results, etc., to be submitted to Entergy Operations for approval or information; e. The method for acceptance of items or services by Entergy Operations; f. The scope anti frequency of audits /surveillances required to 1 e monitor performance and/or maintain vendor qualifc' ations; O
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Rsvision~18 ' e 5.2 Procurement Planning
" 5.2.1 i Procurement planning is a shared responsibility between the Site g&3l Support and Operations Support organizaticns.
i 5.2.2 Based on the relative importance, complexity, or quantity of the item or service, ) planning activities shall establish the following in accordance with approved procedures: 5.2.2.1 The need to perform surveillance (s) of the vendors /subtier vendors activities and/or products during the manufacturing process; i 5.2.2.2 The need to participate in the inspection hold point program established by the vendor or to establish Entergy Operations, Inc, mandatory hold noints.; 5.2.2.3 The identification of documents, such as, qualifications of perso..nel or procedures to be generated and submitted to Entergy Operatione, Inc. for approval prior to start of work; 5.2.2.4 The identification of schedules, plans, drawings, design documents, ! test / inspection results, etc., to be submitted to Entergy Operations, Inc. for approval or information; 5.2.2.5 The method for acceptance of items or services by Entergy Operations, Inc.; . 5.2.2.6 The scope and frequency of audits /surveillances required to monitor i performance and/or maintain vendor qualifications; 5.2.2.7 The timing or schedule for each of the above, as applicable; and 5.2.2.8 The Entergy Operations, Inc. organization or authorized representative respor"lble for performing each of the above as applicable. 94
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c g- Ent - WATERFORD 3 QUALITY ASSURANCE CHAPTER 7 REV. 8.0 R-TYPE: C1.31 PROGRAM MANUAL PAGE: 5 OF 7
- g. The timing or schedule for each of the above, as applicab'e; and
- h. The Entergy Operations organization or authorized representative responsione for performing each of the above as spplicable.
5.3 AUDITS AND SURVEILt.ANCES OF SUPPLIERS
" 3.1 Audits and surveillances of safety related vendors during fabrication, inspection, testing, and shipment of materials, equipment, and components shall be planned and performed in accordance with written procedures to ensure vendor conformance to procurement re.;tilrements, These procedures snellinclude:
- a. Instructions that specify the characteristics or processes to be witnessed, inspected or verified, and accepted; i b.
The method of surveillance and the extent of documentation required; and
- c. The personnel responsible for implementing these instructions.
5.3.2 Iti-process surveillances should be performed when procurement requirements cannot be verified during receipt inspection. 5.3.3 The effectiveness of the vendor's quality assurance program shall be ' assessed by Entergy Operations at intervals consistent with the importance, complexity, and quantity of the item or service. 5.4 RECEIPT INSPECTION AND ACCEPTANCE 5.4.1 S Receipt inspection of safety related material, components, and equipment shall be performed in accordance with written procedures which provWe for the following: a. The material, ccmponcnt or equipment is properly identifiad and corresponds to the requirements of procurernent documentation; b. Material, cornponents, equipment, and records are inspected in accordance with procurement doeurnent requirements prior to installation or use; 1 i (
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.3 Audits and Surveillances of Suppliers 5.3.1 Audits and surveillances of safety related vendors during fabrication, inspection, testing, and shipment of materials, equipment, and components shall be planned and performed in accordance with written procedures to ensure vendor conformance to procurement requirements. These procedures e include: 6.3.1.1 Instructions that specify the characteristics or pror, esses to be witnessed, , inspected or verified, and accepted; 5.3.1.2 The method of surveillance and the extent of documentation required; and 5.3.1.3 The personnel lesponsible for implementing these instructions. 5.3.2 In-process surveillances should be performed when procurement requirements cannot be verified during receipt inspection. 5.3.3 The effectiveness of the vendor's quality assurance program shall be assessed by Entergy Operations, Inc. at intervals consistent with the importance, complexity, and quantity of the item or service. 5.4 Receipt inspection and Acceptrance - Quality control receipt inspection of quality related material, components,
~
,
- 5._4.1j s 18,l and equipment shall be performed in accordance with written procedures which
! provide for tne following: 5.4.1.1 The material, component or equipment is properly identified and
- corresponds to the requirements of procurement documentation
5.4.1.2 Material, components, equipment, and records are inspected in accordance with procurement document requirements prior to installation l or use; 5.4.1.3 As applicable, inspection records or certificates of conformance attesting to the quality of material, components, and equipment are available at Waterford 3 prior to installation or use; and 5.4.1.4 Accepted and released items have their inspection status Identified prior - . to being forwarded to a controlled storage area or released for installation or further work. 95
g- gf WATERFORD 3 QUAUTY ASSURANCE CHAPTER 7 REV. tUi-R TYPE: C1.31 m PROGF/CiMANUAL PAGE: 6 OF 7
- c. As applicable, inspechon records or certhicates of conformance attesting to the quality of material, components, and equipment are available at Waterford 3 prior to installatior, or use; and
- d. Accepted and released items have their inspection status id:mtified prior to being fonwarded to a controlled storage area or released for installabon or further work.
5.4.2 Methods br product acceptance include evaluation of the vendor's QA Program, souron innpoetion/ surveillance, receipt inspection, pre / post installatim testing, or quellfication testing by En' orgy Operations or a qualilled test laboratory. The methodology to control these acceptance methods shall be specified in procedures. Acceptance by vendor's l nortificate of conformance or compliance is satisfactory, provided means are available to verify the validRy of such certifications. 5.4.3 Aooeptance by post installation testing should be used when it is difficult to verify the quality of the item without it being installed or in use, m 5.4.4 Services, such as, engineering and consultant servloes or installation, repair, or maintenance work shall be accepted by one of the following 7 methods: technical verification of data; audit; inspection; surveillanos; or review of objective evidence for coniormance to procutament documents. 5.5 PROCUREMENT AND DED! CATION OF COMMERCIAL GRADE ITEMS I$.5.1 Commercial grade maiorial, parts, and equipment that are essential to the safsty related functions of structures, systems, and ccityctients shall be evaluated for suitability of application. The evaluation results shall be documented. i 5.5.21The preparer of the purchase requisition is responsibh for clearly identifymg the commercialitem to be procured and listing the receipt inspection requirements. The item selected shall be identical to the originalor an approved allemate. 5.5.3 If the part is different from or an addit:r:: to the original design and constitutes a plant modification, Design Engineering shall review the
- material application and venty the part's suitability for ths intended use.
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g WATERFORD 3 CHAPTER 7 REV. 8,0
- Ent QUAUTY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 7 OF 7 5.5.4 Additional source verification, inspection, or test requirements shall be specified in the procurement documents, as necessary, to dedicate the commercial grade item for use in a safety re!ated application.
5.6 SPARE AND REPLACEMENT PARTS 5.6.1 Spare and replacement parts for sofety related systems, structures, and components shall be subject to Waterford 3 Quality Assurance Program controls, and to codes, standards, and technical requirements at least equivalent to or better than those used for the original equipment. 5.7 RECORDS 5.7.1 Quality Assurance records, when required by procurement documents, shall be collected and retained by vendors of safety related items, i Suppliers shall furnish the following records, as a minimum, to Entergy Operations or its agent:
- a. Documentation that identifies the purchased material or equipment and the specific procuement requirements (e.g., codes, standards, specifications) met by the items; and
- b. Documentation that identifies any procurement requirements which have not been met, together with a description of those nonconformances dispositioned " accept-as is" or " repair,"
5.7.2 The review, evaluation, and acceptance of the required vendor records furnished to Entergy Operations shall be oescribed in procedures. 5.7.3 Records associated with qualification testing (inplace or test laboratory) shall also be considered QA records and shall be submitted to, or made available to Entergy Operations. 5.7.4 Required procurement documents shall be available at Waterford 3 prior to use nf purchased material, components, or equipment. The documentation shall be retained in ac,ordance with approved procedures. 6,0 ATTACHMENTS None
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.4.2 Methods for product acceptance include evaluation of the vendor's QA Program, source inspection / surveillance, receipt inspection, pre / post installation testing, or qualification testing by Entergy Operatirns, Inc. or a qualified test laboratory. The methodology to control these ace sptance methods shall be specified in procedures. Acceptance by vendor'3 certificate of conformance or compliance is catisfactory, provided means are available to verify the validity of such certifications. 5.4.3 Acceptance by post installation testing should be used when it is difficult to verify the quality of the item without it being installed or in use. 5.4.4 Services, such as, engineering and consultant services or installation, repair, or maintenance work shall be accepted by one of the following methods: technical verification of data; audit; inspection; surveillance; or review of objective evidence for conformance to procurement documents. 5.6 Procurement and Dedication of Commercial Grade items 5.5.1 Commercial grade items shall be evaluated for suitability of application. The gl evaluation results shall be documented. 5.5.2 The preparer of the purchase requisition is responsible for clear!y identifying the commercial grade item to be procured and the acceptance methods. The i item selected shall be identical to the original or an approved alternate or g equivalent. 5.5.3 If the part is different from or an addition to the original design and constitutes a plant modification, Design Engineering shall review the material application and ve'ify the part's suitability for the intended use. 5.5.4 Additional source verification, inspection, or test requirements shall be specified in the procurement documents or inspection plan, as necessary, to dedicate the commercial grade item for use in a safety related application. 3l 5.6 Spare and Replacement Parts 5.6.1 Spare and replacement parts for safety related systems, structures, and components shall be subject to Waterford 3 Quality Assurance Program controls, and to codes, standards, and technical requirements at least equivalent to or better than those used for the original equipment. 96
i ,P k O f i g - WATERFORD 3 CHAPTER 10 ;REV.7.0 % i - - Entefgy QUAUTY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 3 OF 9 l j ' 4.3.3 Reviewirg all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensure the inclusion i of quality requirements, and ensuring that quality reviews are conducted
! for all other initiated work authorizations; and a
4.3.4 Conducting or coordinating inspections of modifications and maintenance activities: i
- 4.4 VICE PRESIDENT, OPERATIONS SUPPORT 4.4.1 The Vice President, Operations Support is responsible for the
- performance of receipt and storage inspections.
i } 5.0 DETAILS i 5.1 INSPECTION PROGRAM l 5.1.1 Entergy Operations ha three sources of inspection personnel for safety related activities at Waterford 3: 1 a. Quality Assurance personnel;
- b. Line organization personnel (i.e. Peer / Maintenance inspectors); or
! c. Contract personnel. l l 5.1.2 Inspections snall be controlled as follows: i a. Inspections are performed in accordance with procedures approved by Entergy Operatior.s; t
- b. Inspection results are documented, evaluated and their acceptability determined by responsible personnel in accordance with approved procedures; l
1
- c. Inspection procedures, inspection pemonnel qualifications and certifications are concurred with by the Director, Quality; 7l 1
i l l l I
J k W t:rford 3 Qu lity Assurance Progr m Manual Chapt:r 10 Inspection Revision 18 5.0 PROCEDURE 5.1 Inspection Program 5.1.1 Entergy Operations, Inc. (EOI) has three sources of inspection personnel for safety related activities at Waterford 3: 5.1.1.1 Quality Assurance personnel; 5.1.1.2 Line organization personnel (i.e. Peer / Maintenance inspectors); or 5.1.1.3 Contract personnel. 5.1.2 Inspections shall be controlled as follows: 5.1.2.1 Inspections are performed in accordance with procedures approved by Entergy Operations, Inc.; I 5.1.2.2 Inspection results are documented, evaluated and their acceptability determined by responsible personnelin accordance with approved procedures; 5.1.2.3 Inspection procedures, inspection personnel qualifications and certifications are concurred with by the Director, Quality; [l _N_OTE: Stores inspection procedures, are controlled in accordance with the Materials, Purchasing and Contracts administrative procedures 3 manual. 5.1.2.4 Inspections are performed by certified individuals other than those who performed or directly supervised the activity being inspected; 5.1.2.5 Inspection of operating activities may be conducted by second-line supervisory personnel or by other certified personnel not assigned first-line supervisory responsibility for conduct of the work; and 5.1.2.6 Inspection activities not conducted by Quality Assurance are periodically reviewed by Quality Assurance. 5.1.3 Inspections of operating activities or work functions associated with normal operation of the plant, routine maintenance, and certain technical support services routinely performed by the plant staff may be conducted by qualified and certified personnel selected by plant management. 110
g WATERFORD 3 CHAPTER 15 REV. 8.0
- Entergy QUAUTY ASSURANCE R-TYPE: C1.31 PROGRAM MANUAL PAGE: 1 OF 5 TITLE: NONCONFORMING MATERIALS, 06/04/97 EFFECTIVE DATE:
PARTS OF COMPONENTS PREPARED BY:hm _ 0.Ch DIRECTOR, QUALITY: _, REVIEWED D b' I _ VICE PRESIDENT, OPERATIONS: l
~
M/b" ff 1.0 PURPOSE 1.1 The Waterford 3 Quality Assurance Program requires the control of nonco'1 forming materials, parte or components. This program controls the identification, documentation, segregat:on, review, disposition, notification to affected organizations, repair, rework, retest, and reinspection of nonconforming materials, parts, components, tctivities, and services. l 1.2 Nonconforming materials, parts, components, strudures and activities are controlled such that reliance on an unresolved nonconforming item to perform o safety function is not required. 2.0 REFEF ENCES 2.1 Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants.") 3.0 DEFINITIONS 3.1 See Appendix C
~ - '- ' '
s Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, 3 arts or Components . Revision 18 + 1.0 PURPOSE 1.1 The Waterford 3 Quality Assurance Program requires the control of nonconforming materials, parts or components. This prcgram controls the identification, documentation, segregation, review, disposition, notification to affected organizations, repair, rework, retest, and reinspection of nonconforming materials, parts, components, activities, and services. 1.2 Nonconforming materials, parts, components, structures and activities are controlled such that reliance on an unresolved nonconforming item to perform a safety function is not allowed. 3l
2.0 REFERENCES
2.1 Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Ope ations The General Manager, Plant Operations is responsible for the nonconformance control system at Waterford 3 for material, parts, and components under plant jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use-as-is". 4.1.1 Plant Operations Review Committee The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending approval to the General Manager, Plant Operations. 134
'e 4
g- Ent WATERFORD 3 ouatiTY ASSURANCE CHAPTER 15;. REV. 8.0 R TYPE: C1.31 m PROGRAM MANUAL PAGE: 4 OF 5 5.2,3 If a reportable event b identiflod pursuant to applicable NRC tegulations, required intomal and extemal notification and documentation shaN be Initiated as requirer? by procedures. 5.3 SEGREGATION 5.3.1 Nonce 'viming items shall be segregated, when practical, by placing them in a clearty ',dsntified and designated hold area untN property dispositioned. 5.3.2 When segregation is impractical or impossible due to physical conditions such as size, weight, or access limitations, other precautions shall be employed to preclude inadvertent use of a nonconforming item. 5.4 DISPOSITION A technical evaluation shall be made to determine whether a singular nonconforming condition cxists or it' the noncen',viinience represents a gmmric m condition. The evaluation shaN also determine whether the nonconforming item
- may be accepted, rejeded, reworked, repaired, use , s-is, or conditionally released. The action to be taken shaN be documented and an implementation schedule shes be generated as necessary. A description of changes, waivers, or deviations, that are accepted shaN be documented to iscord the change and denote the as-buut condition.
5.5 REINSPECTION 5.6.1 Reworked, repaired, or replaced items shaN be reinspected and ratested in accordance with the original inspection and test requirements or acceptable altematives. Nenesa',vriiiing items shal be reinspected per requiremente established by the technical ovaluation. The rework, repair, replacement, and inspection or test results shall be documented. 5.5.2 Rejected items shall be identdied by tag 9 i ng, and where practicai, removed from the area to preclude further use or installation. I 5.5.3 Final ahomative action may be to retum rejected material and equipment to the supplier or to scrap. Upon satisfactory reinspection and completion of associated documentabon, the initiating nonconformance document , shall be closed out.
. .a Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, Parts Or Components Revision 18 2
- 5.4 Disposition A technical evaluation shall be made to determine whether a singular nonconforming condition exists or if the nonconformance represents a generic condition. The evaluation shall also determine whether the nonconforming item may be accepted, rejected, reworked, repaired, used as is, or conditionally released. The action to be taken shall be documented and an implementation schedule shall be generated as necessary. A description of changes, waivers, or deviations, that are accepted shall be documented to record the change and denote the as built condition.
5.5 Reinspection 5.5.1 - Reworked, repaired, or replaced items shall be reinspected a::d retested in accordance with the original inspection and test requirements or acceptable alternatives. Nonconforming items shall be reinspected per requirements established by the technical evaluation. The rework, repair, replacement, and inspection or test results shall be documented. 5.5.2 Rejected items shall be identified by tagging, and where practical, removeo , am the area to preclude further use or installation. I 5.5.3 ' Final alternative action may be to return rejected material and equipment to the supplier or to dispose. lJpo 1 satisfactory reinspection and completion of 8 l
,1_8 associated documentation, the initiating nonconformance document shall be closed out.
5.6 Records 5.6.1 Documentation of nonconforming materials, parts or components shall be maintained in accordance with Entergy Op. rations, Inc. quality assurance records managemont procedures. Information contained in the documentation shall include ' ut may not ba I!mited to: 5.6.1.1 Disposition of the nonconformance; 5.6.1.2 Signature approval for disposition; - 5.6.1.3 Identification of the nonconforming item; 137
g - WATERFORD 3 APPENDIX C REV. 6.0 4
- Ent QUALITY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 10 OF 19 ~ PROCUREMENT CLASSIFICATIONS QUALITY CLASS I - Those items or services meeting the definition of safety related for which tfie supplier, manufacturer, or vendor assumes 10CFR21 reporting responsibility. The supplier QA program must include full 10CFR50 implementation.
QUALITY CLASS ll - Those items or services which do not meet the definition of safety related, but which fallinto the other quality related areas listed in the definition of quality related. The applicabla program requirements / exceptions are listed in the Special Scope procedures, procedures or procurement documents. QUALITY CLASS 111 - Those items meeting the definition of safety related and the definition of commercial grade, items purchased as Quality Class 111 are subject to the dedication process prior to being classified as a basic component. Entergy Operations assumes 10CFR21 reporting responsibility for QC lli purchases. 1 QUALITY CLASS IV ' hose items or services which do not include or are not a part of safety or quality related equipment, features or activities. QC IV includes safety or quality related services provided by suppliers or co,1 tractors under the Entergy Operations Quality Assurance Program. PROCUREMENT DOCUMENT A document including purchase requisitions, j specifications, drawings, instructions, contracts, letter of intent, work ordars, purchase j orders, or proposals and their acceptances, when applicable, which authorize the seller to perform services or supply equipment, materials, or facilities on behalf of the purchaser. l, m PURCHASE ORDER A document issued by a purchaser to a supplier which defines the requirements and conditions for furnishing material, components, or equipment. q PURCHASER The organization or organizations responsible for issuance and Cdministration of a contract, subcontract, or purchase order. I, m
PROCUREMENT CLASSIFICATIONS
- Procurement Classification Level 1 (L1) is assigned to those items that are procured as safety related under the responsibility of the suppliers approved 10CFR 50 Appendix B type quality assurance program with 10 CFR Part 21 reportability imposed on the supplier.
Procurement Classification Level 2 (L2) is assigned to those items that are safety related or items meeting the definition of commercial grade, procured under the responsibility of the site quality assurance program for which Entergy Operations, Inc. assumes the r:sponsibility defined in 10 CFR Part 21. Procurement Classification Level 3 (L3) is assigned to those iterns which are not safety- , r: lated but fallinto Augmented Quality /special scope as described in the site design basis licensing documents. Procurement classification Level 4 (L4) is assigned to those permanent plant items which are defined as non-safety related (Balance of Plant) for which no quality assurance r:quirements are imposed. 3 Procurement classification Level Pending (Li ) is assigned to those items pending review by 1/aterials Purchasing & Contracts for assigning the correct procuremem classifict Jon. Procurement classification Level Exempt (LE) is assigned to non permanent plant items (exempt). Below is a matrix relating former and current procurement classifications (procurement quality levels). FORMER CURRENT QC1/Q1 (SAFETY-RELATED) L1 (SAFEW RELATED) QC2/02 (SPECIAL SCOPE) L2 (SAFEW RELATED/ COMMERCIAL GRADE / DEDICATED) QC3/03 (SAFETY-RELATED/ COMMERCIAL L3 (AUGMENTED QUALITY) GRADE / DEDICATED) QC4/Q4 (BALANCE OF PLANT) L4 (BALANCE OF PLANT) OCE/QE (EXEMPT) LE (EXEMPT) i NONE LP (PENDING) PROCUREMENT DOCUMENT A document including purchase requisitions, specifications, drawings, instructions, contracts, letter of intent, work orders, purchase orders, or proposals tnd their acceptances, when applicable, which authorize the seller to perform services or supply equipment, materials, or facilities on behalf of the purchaser i, m
. Chapter 2 Rev.18 ; Attachment 7.4 (Page 10 of 19) 57 9
WATERFORD 3 APPENDIX C REV.6.0
" Ent QUAUrY ASSURANCE PROGRAM MANUAL R TYPE: C1.31 PAGE: 12 OF 19 QUALITY RELATED Waterford 3 uses the term Quality Related to describe the entire scope of structures, systems, components and activities which requirg some degree of 10CFR50 Appendix B, Quality Assurance criteria application. Quality related is divided into five major categories:'(ref: fig.1) o Safety Related o Special Scope o Non Nuclear Safer /
o Non Safety Selsmic o Other items idontified by FSAR table 3.21, note 17 or Waterford 3 procedures.
~ ~ -
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QUALITY RELATED Waterford 3 uses the term Quality Related to describe the entire scope of structures, systems, components and activities which require some degree of 10CFR50 Appendix B, Quality Assurance criterla application. Quality related is divided into five major categories: (ref: fig.1) o Safety Related o Special Scope o Non Nuclear Safety o Non Gafety Seismic o Other items identified by FSAR table 3.21, note 17 or Waterford 3 procedures. 4 QUALITY m 7 RELATED
+Q List
- 4 Q.RELATED LIST >I NOl64AFETY -
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Attachment 7.4 (Page 12 of 19) 59
QUALITY ASSURANCE PROGRAM CHANGE REVIEW FORM PROPOSED CHANGE: R2 vising the following " Terms and Definitions
- of the Quality Assurance Program Manual, Appendix *C', Revision 6 to maintain consistency of the Quality Assurance Prcgram Manuals within the Entergy Operations system: Adverse dondition, Cause (Root Cause), Conditions Adverse To Quality, Corrective Action, Nonconforming Condition. and Sip' Meant Adverse Co-dition. The current definitions and their proposed revisions are listed on the attached pages.
Note; *: < Caality Assurance Program Manualis being revised and Appendix *C" vill be moved to Chapter Two as an attachmd 100FR53.54 P3 VIEW:
- 1. Does tht proposed change represent a reduction of commitment to the C Yes " No QA Program description previously accepted by the NRC?
Explain: Th3 introduction to Appendix C, " Terms and Definitions", to the Wateford 3 QAPM, as approved t,/ the NRC, states in
, part that "They are provided as guidance to achieve standardization within Waterford 3 documents and as an aid in the l imphmentation of the Quality Assurance Program....it is the responsibility of the user of the terms and deinitions _
contained herein to ascertain that they are acpropriate for the intended application. Where a term is used to conysy a > diffJrent intent than that defined herein, c!anfication should be provided at the point of application." Terms and Difinitions contained in Appendix *C' are not considered to be commitments therefore, the revisions to the listed r d;finitions should not be considered reductions .in commitment.. j
- 2. If nem i above is YES, does the prog:osed change include the basis to Yes Nc- " N/A conclude that the revised program incorporating the change contlaues to meet the criteria cf 10CFR50 Appendix B and other previously acr9pted FSAk commitments?
Explain: JNM42 r>nw /0 $ D Reviewed Ey: 6 Representa'tivgf[ ^'
/ Dfate
\ j RECOMMENDATION:
" Does not represent a lessening of commitment and it can be impiefn snted !rt. mediately.
Representr a lessening of coramitment, however, the change has suihcient basis to demonstrate continued compliance with Appendix B and other FSAR commitments. Therefore,it should be submitted to the NRC for acceptance prior to im?!ementation. Represents a lessening of commitment with insufficient basis to determine continued compliance. g Therefore, the change s! ould not be proc _essed. 7 eV<[ a )o\nk, Recommended By: QA SupervisoE i3 Date DISFOSITION: a Approved for implementation C Disaporoved *
- Approved for submittal to NRC for acceptance
/ _b 3 20 ctr 91 Approved By: Difector[ Quality Date
- W2.300, Rev. O Attachment V Nge 1 of 1 I
- m d
CURRENT DEFINITIONS AND THEIR PROPOSED REVISIONS ADVERSE CONDITION Current Definition: ADVERSE CONDITION An event, Defect, characteristic. = tate or activity which negatively impacts the safe, efficient operation of Waterford 3. Adverse conditions include:
. Nonconforming Condition;
. Conditions adverse to quality;
- Industrial safety concerns; and '
. Plant reliability concerns.
l Proposed Revlalon: l ADVERSE CONDITION An event, defect, characteristic, stat 9, or activity which prohibits or detracts from the safe, efficient operation of Waterford 3. Adverse conditions include Nonconformances, Conditions Adverse to Quality, and Plant Reliability Concerns. CAUSE Current Definition: CAUSE A reason or contributing reason for the occurrence of a e overse condition. Causes are categonzed as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performing a formal root cause analysis. Root Cause - the most basic cause(s) y,;1ich, if corrected or eliminated, would prevent recurrence of the adverse condition. Root Lauses are generally identified through ine conduct of a formal root cause analysis.
Proposed Revision: CAUSE A reason or contributing reason for the occurrence of an adverse condition. Causes are categorized as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performing a formal Root Cause Analysis. Root Cause - the most basic factors which, if eliminated, would prevent recurrence of the adverse condition. Root causes are generally identified through the conduct of a formal root cause analysis performed in accordance with Entergy Root Cause Analysis Desk Guide. CONDITIONS ADVERSE TO QUALITY Current Definition: CONDITIONS ADVERSE TO QUALITY An adverse condition which prevents a @Jality related system, structure, component or activity from meeting license or design basis requirements. Proposed Revision: I l CONDITION ADVERSE TO QUALITY Failure of a Safet'f Related Structure, System or Component (SSC) to perform their intended safety function, and safety related process deficiencies and violations which cou!d result in a degradation or challenge to iluclear Safety. R y .
CORRECTIVE ACTION Current Definitionj s CORRECTIVE ACTION Measures taken upon the identification of an adverse condition to correct the condition and prevent recurrence. The basic etsments of the corrective action prograrfi are:
- 1. identification and immediate action;
- 2. review for impact / assignment
- 3. Investigate and analyze;
- 4. corrective action planning and implementation;
- 5. verification of completion; and
- 6. verification of long-term effectiveness Proposed Revision:
Corrective Action - measures taken upon the identification of an adverse condition to correct the deficiency. NONCONFORMING CONDITION Current Definition: NONCONFORMING CONDITION An adverse condition affecting a safety related, quality related, trip sensitive (or balance of plant, when feasible) system caused by a deficiency in characteristic, documentation, or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconforming conditions include, but may not be limited to:
. Unanticipated or unplanned entry into any Tech Spec 1.CO;
. Discovery of a condition of a system or component rcquired to be operable by Tech Spec, which ce!!s into question the current or past operabilitv (including missed surveillance testing);
. Failure of a component to mW a surveillance os post-modification test acceptance criteria (prior to performing ani -.rective maintenance);
. An uranticipated ESFAS signal or actuation of ESFAS equipraent;
. Identification of a discrepancy between a licensing document (i.e., FSAR, Tech Spec) or a design basis document, (i.e., drawings) and the actual configuration of the plant;
t
. Discovery of a valve or breaker in a position different from that required by the proper procedure;
. Unanticioe%d actuation of an over-current protective device, (i.e., blown fuse or tripped cicult breaker);
. Routine actua, tion of an over-pressurization protective device, such as a relief valve;
. Unexpected or unplanned reactor power, power distribution, or shutdown margin condition or transient; or,
. Issuance of incorrect or defective pans or material.
Proposed Revision: Nonconformance - an adverse condition affecting a safety-related, quality related or trip sensitive system caused by a deficiency in characteristic, documentation or procedure which renders the quality of an item unacceptable or indeterminate. SIGNIFICANT ADVERSE CONDITION Current Definition: SIGNIFICANT ADVERSE CONDITION a level of condition for which a Root Cause Analysis and action to prevent recurrence are required:
- 1. A condition will be classified as a Significant Adverse Condition when it meets one or more of the following criteria:
- a. The unplanned event, condition, or failure involves a system, structure, or component that has resulted in, or has the potential to cause:
- 1. a reactor or secondary system transient or
- 2. a significant degradation of a safety related or trip sensitive system.
- b. The condition or event is reportable per 10CFP50.72,10CFR50.73, 10CFR21 or 40CFR;
- c. The condition or event is cited by the Nuclear Regulatory Commission as a violation;
- d. The condition or event has reached an unacceptable level of severity or recurrence; i
s
i
- e. The condition is classified as a significant industrial safety concern (e.g., resulting in a lost time accident); or
- f. The condition or event is representative of a major noncompliance with, or major misunderstanding of Quality Assurance Program requirements (Usually determined by upper management).
Proposed Revision: Significant Condition Report: A classification of CRs determined by the Condition Review Group (CRG) that meets one or more of the be'ow cnteria: l a. A reportable event per 10CFR50.72 or 10CFR50.73 which requires a written follow-up reoort, or 10CFR Part 21 reporting criteria (routine reports to the NRC are excluded),
- b. A problem recognized as having a greater than acceptable recurrence rate as determined by the CRG.
. Any event or nonconformance that meets the definition of repetitive event is significant.
- c. An unplanned event or failure of a SSC that led or could have led to a reactor trip or plant transient.
- d. Near miss Industrial Safety incident or Serious Accident.
- e. - A major breakdown in processes that implement QA Program Requirements as determined by the CRG.
- f. Events or conditions designated as significant or considered important by management for reasons other than those which fall into the above categories.
CHANGE Revised the following Terms and Definitions of the Quality Assurance Program Manual, Appendix C Rev. 6 (now Attachment 7.4 of Chapter 2) to maintain consistency of the Quality Assurance Program manuals within the Entergy Operations, Inc. system: Adverse Condition, Cause (Root Cause), Ccnditions Aoverse to Quality, Corrective Action, Nonconforming Condition and Significant Adverse Condition. Adverse Condition revised from - An event, defect, characteristic, state er activity which negatively impacts the safe, efficient operation of Waterford 3. Adverse conditions include:
. Nonconforming condition; e Conditions adverse to quality;
. Industrial safety concerns; and
. Plant reliability concerns to An event, defect, characteristic, state or activity which prohibits or detracts from the safe, efficient operation of Waterford 3. Adverse conditions include: Nonconformances, Conditions Adverse to Quality, and Plant Reliability Concerns.
Cause revised from - A reason or contributing reason for the occurrence of an adverse condition. Causes are categonzed as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performinc a formal root cause analysis. Root Cause - the most basic cause(s) which, if corrected or eliminated, would prevent recurrence of the adverse condition. Root Causes are generally identified through the conduct of a formal root cause analysis to A reason or contributing reason for the occurrence of an adverse condition. Causes are categorized as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performing a formal root cause analysis. Root Cause - the most basic factors which, if eliminated, would prevent recuirence of the adverse condition. Root Causes are generally identified through the conduct of a formal root cause analysis performed in accordance with Eiitergy Root Cause Analysis Desk Guide. 9/ '
C nditinn3 Adv:rso t2 Quality rsvis:d from - An adverse condition which prevents a quality rels.ted system, structure, component or activity from meeting licenso or design basis requirements, to Failure of Safety Related Structure, System or Component (SSC) to perform their intended , safety function, and safety related process deficiencies and violations which could result in a l degradation or challenge to Nuclear Safety. Corrective Action Revised from - Measures taken upon the identification of an averse condition to correct the condition and prevent recurrence. The basic elements of the corrective action program are:
- 1. identification and immediate action;
- 2. review for impact / assignment;
- 3. investigate and analyze;
, 4. corrective action planning and implementation;
- 5. verification of completion; and
- 6. verificatica of long-term effectiveness, to Measures taken upon the identification of an adverse condition to correct the deficiency.
Nonconforming Condition revised from - An adverse condition Effecting a safety related, quality related. trip sensitive (or balance of plant, when feasible) system caused by a deficiency in characteristic, documentation, or A rocedure which renders the quality of an item unacceptable or indeterminate. Examples of
\ nonconforming conditions include, but may not be limited to:
. Unanticipated or unplanned entry into any_ Tech Spec LCO; Discovery of a condition of a system or component required to be operable by Tech Spec, which calls into question the current or past operability (including missed surveillance testing);
Failure of a component to meet a surveillance or post-modification test acceptance criteria (prior to performing any corrective maintenance); An unanticipated ESFAS signal or actuation or ESFAS equipment; e Identification of a discrepancy between a licensing document (i.e., FSAR, Tech Spec) or a design basis document, (i.e, drawings) and the actual configuration of the plant; e Discovery of a valve or breaker in a position different from that required by the proper procedure; 3 Unanticipated actuation of an over-current protective device, (i.e., blown fuse or tripped circuit breaker); Routine actuation of an over-pressurization protective device, such as a relief valve; Unexpected or unplanned reactor power, power distribution, or shutdown margin condition or transient; or
. Issuance of incorrect or defective parts or material.
i
to Nonconformance - an adverse condition affecting a safety related, quality related or trip sens;tive system caused by a deficiency in characteristic, documentation or procedure which renders the quality of an item unacceptable or indeterminate. Significant Adverse Condition revised from - A level of condition for which a Root Cause Analysis and action to prevent recurrence are required:
- 1. A condition will be classified as a Significant Adverse Condition when it meets one or more of the following criteria:
- a. The unplanned event, condition, or failure involve a system, structure, or component that has resulted in, or has tb3 potential to cause:
- 1. a reactor or seco.1dary system transient; or
- 2. a significant degradation of a safety related or trip sensitive system.
1 l b. The condition or event is reportable per 10CFR50.72,10CFR50.73, i 10CFR21 or 40CFR. l
- c. The condition or event is cited by the Nuclear Regulatory Commission as a violation;
, d. The condition or event has reached an unacceptable level of severity or recurrence;
- e. The condition is classified as a significant industrial safety concern (e.g., resulting in a lost time accident); or
- f. The condition or event is representative of a major noncompliance with, or major misunderstanding of Quality Assurance Program requirements (usually determined by upper management).
to Significant Condition Report: A classification of Condition Reports determined by the Condition Review Group (CRG) that meets one or more of the below criteria:
- a. A reportable event per 10CFR50.72 or 10CFR50.73 which requires a written 1
follow-up report, or 10CFR Pait 21 reporting criteria (routine reports to the NRC are excluded). I
)
, J
- b. A problem recogniz d cs h:ving e great:r th:n acceptabla recurrence rr.t3 es d t:rmin:d by ths CRG.
Any event or nonconformance that meets the definition or repetitive event is significant.
- c. An unplanned event or failure of a SSC that led or could have led to a reactor trip of plant transient,
- d. Near miss Industrial Safety Incident or Serious Accident.
- e. A major breakdown in processes that implement QA Program Requirements as determined by the CRG.
- f. Events or conditions designated as significant or corisidered important by management for reasons other than those which fall into the above categories.
BASIS FOR NC PEDUCTION OF COMMITMENT The introduction to Appendix C " Terms and Definitions"(now Attachment 7.4 of Chapter 2) to the Waterford 3 QAPM, as approved by the NRC, states in part that "They are provided as guidance to cchieve standardization within Waterford 3 documents and as an aid in the implementation of ihe Quality Assurance Program. It is the responsibility of the user of the terms and definit %., contained herein to ascertain that they are appropriate for the intended application. Where a te..n is used to convey a different intent than that defined herein, clarification should be provided at the point of application." Terms and Definitions contained in Appendix C (now Chapter 2 Attachment 7.4) are not considered to be commitments, therefore, the revisions to the listed definitions should not be considered reductions in commitment. QAPM SECTIONS AFFECTED BY THIS CHANGE Appendix C Rev.6 Adverse condition Lause (Root Cause) Conditions Adverse to Quality Corrective Action Nonconforming Condition Significant Adverse Condition 1 i
g- Ent WATERFORD 3 QUALITY ASSURANCE APPENDIX C R-TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 2 OF 19 ABNORMAL CONDITION Hardware deviations (i.e. conditions not meeting the threshold criteria of adverse conditions or nonconforming condition) observed in the course of inspections, testing, maintenance, operation, etc. ACCEPTANCE CRITERIA A limit or limits placed on the variation permitted in the characteristics of an item expressed in def;nitive engineering terms such as dimensional tolerances, chemical composition limits, density and size of defects, temperature ranges, time litnits, operating parameters, and other similar characteristics. e ACCEPT-AS-IS Same as Use-As-Is. q ACCURACY The degree of conformity of a measure to a standard or to a true value. (See Precision). q ADMINISTRATIVE CONTROLS Rules, orders, instructions, procedures, policies, practices and designations of authority and responsibilitv. c ADVERSE CONDITION An event, defect, characteristic, state or cctivity which negatively - impacts the safe, efficient operation of Waterford 3. Adverse conditions include: i Nonconforming conditiori; - Conditions adverse to quality; industrial safety concems; and Plant reliability concems. APPROVAL Ari act of endorsing or adding positive authorization or both, i APPURTENANCE A part that is attached to a component which has been completed.i AS-BUILT-DATA Documented data that describes the condition actually achieved in a product. l ASSEMBLY A combination of subassemblies or components, or both fitted together to form a unit. l AUDIT A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence. that epplicable ci:ments of the quality assurance program has been developed, documented, and effectively implemented in accordance with specified requirements. An audit should not be confused with surveillance or inspection for tha sole purpose of process control or product acceptance, i, n, o i
\
m . ABNORMAL CONDITION Hardware deviations (i.e. conditiens not meeting the threshold criteria of adverse conditions or nonconforming condition) observed in the course of inspections, testing, maintenance, operation, etc. ACCEPTANCE CRITERIA A limit or limits plac:d on the variation permitted in the characteristics of an item expressed in definitive engineering terms sucn as dimensional tolerances, chemical composition limits, density and size of defects, temperature ranges,- time limits, operating parameters, and other similar cheracteristics. e
= ACCEPT-AS-IS Same as Use-As-Is. q ACCURACY The degree of conformity of a measure to a standard or to a true value.
(See Precision). q ADMINISTRATIVE CONTROLG Rules, orders, instructions, procedures, policies, practices
. cnd designations of authority and responsibility. c -
IADVERSE CONDITION ?An event, defect, characteristic, state or activity which prohibits - or detracts from the safe, efficient operation of Waterferd 3. Adverse _ conditions include 18-Nonconformances, Conditions Adverse to Quality and Plant Reliability Concems.
- APPROVAL ~ An act of endorsing or adding positive authorization or both.- l APPURTENANCE A part that is attached to a component which has' been completed.i -
AS-BUILT-DATA C..icumented data that describes the condition actually achieved in a product. l - ASSEMBLY A combination of subassemblies or components, or both fitted together to form a unit. l AU_DIT A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence, that applicable elements of the quality assurance program has been developed, documented, and effectively implemented in accordance with specified requirements. An audit should not be confused with surveillance or inspection for the sole purpose of process control or - product acceptance.fi, n, o EChaptir 2Mf18 7 Attachment 7.4 (Page 2 of 13) 49
,y :
g-- Ent WATERFORD 3 QUALITY ASSURANCE APPENDIX C R-TYPE: C1.31 REV. 6.0 PROGRAM MANUAL PAGE: 3 OF 19 BASIC COMPONENT As it applies to Waterford 3, it is a component, structure, system or part thereof that is directly procured by Entergy Operations /LP&L, is subject to 10CFR21 and in which a defect or faihire to comply with 10CFR21, an NRC order, or license conditions could c'reate a substantial safety hazard r, q BID EVALUATION An evaluation of proposals or bids received in response to an inquiry (request for proposal or bid) to determine the vendor or contractor to whom the purchase order or contract will be awarded. q CAllBRATION Comparison of an item of Measuring and Teat Equipment and certain installed instrumentation and control devices with a reference standard or with an item of M&TE of required tolerance to detect and quantify inaccuracies and to report or eliminate those inaccuracies, q, t CAUSE ' A reason or contributing reason for the occurrence of an adverse condition. Causes are categorized as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performing a formal rcot cause analysis. Root Cause - the most basic cause(s) which, if corrected or eliminated, would prevent recurrenos of the adverse condition. Root Causes are generally identified through the conduct of a formal root cause analysis. CERTIFICATE OF COMPLIANCE A written statement, signed by a qualified party, ettesting that the items or services are in accordence with specified requirements and accompanied by addnionalinformatior; to substantiate the statement. l CERTIFICATE OF CONFORMANCE A written statement, signed by a qualified party, certifying that items or services comply with specific requirements.1 CERTIFICATION The action of determining, verifying and attesting, in writing, to the qualifications of pernr.nel or material. i CERTIFIED MATERIAL TEST REPORT A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual properties of items and the actual results of all required tests. i CHARACTERISTIC A.ty property or attribute of an item, process, or service that is distinct, describable, and measurat'e, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings, which describe the item, process or service.1
.o .
BASIC COMPONENT As it applies to Waterford 3, it is a component, structure, system or part thereof that is directly procured by Entergy Operations, Inc./LP&L, is subject to 10CFR21 and in which a defect or failure to comply with 10CFR21, an NRC order, or license conditions could create a substantial safety hazard r, q BID EVALUATION An evaluation of proposals or bids received in response to an inquiry (request for proposal or bid) to determine the vendor or contractor to whom the putchase order of contracMill be awarded. q CAllBRATION Comparison of an item of Measuring and Test Equipment and certain installed instrumentation and control devices with a reference standard or with an item of M&TE of required tolerance to detect and quantify inaccuracies and to report or elimmate those inaccuracies. q, t
^CAUSE A reason or contributing reason for the occurrence of an t.dverse condition.
Causes are categorized e.s either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition. The apparent cause is identified without performing a formal root cause analysis. Root Cause - the most basic factors which, if eliminated, would prevent recurrence of the adverse condRion. Root causes are generally identified
~~
through the conduct of a formal root cause analysis pedormed in accordance witri Entergy Root Cause Analysis Desk Guido., CERTIFICATE OF COMPLIANCE A written statement, signed by a qualified party, I attesting that the items or services are in accordance with specAd requirements and accompanied by additional inforrr.ation to substar,tiate the statement. i CERTiclCATE OF CONFORMANCE A written statemeilt, signed by a qualified party, certifying that items or services comply with specific requirements. I CERTIFICATION The action of detcmiining, verifying and attesting, in writing, to the qualifications of personnel or material. i CERTIFIED MATERIAL TEST REPORT A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual properties of items and the actual results of all required test.c.. i Chapter 2' Rev.'18 Attachment 7.4 (Page 3 of 19) 50 m --
.1 '
f ' g- Ent WATERFORD 3 QUALITY ASSURANCt:. APPENDIX C REV. 6.0 - R-TYPE: C1.31 s PROGRAM MANUAL PAGE: 4 OF 19 CLEANNESS A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other contaminating impurities. l COMMERCIAL GRADE Those items which (1) are not subject to design or specification requirements that are unique to facilities or activities licensed by the NRC and (2) are used in applicctions other than facilities or activities licensed by the NRC and (3) can be ordered from the manufacturer / supplier on the basis of information set forth in the manufacturer's published product information or nationally recognized non-nuclear codes or standards. (NOTE: Although an item is exempted from 10CFR21 being imposed on the manufacturer, supplier orvendor by the definition of "Commarcial Grade", the item may still have other QA requirements which need to be imposed in the procurement documents). r, q COMPONENT A piece of equipment such as a vessel, piping, pump, valve or core support structure, which will be combined with other components to form an assembly; or; it:ms from which electncal equipment is assembled,' for example, resistors, capacitors, wires, connectors, transistors, switches, springs, etc.i CONDITIONS ADVERSE TO QUALITY An adverse condition which prevents a quality r: lated system, structure, component or activity from meeting license or design basis requirements q CONSTRUCTION PHASE The period of time beginning with the start of construction activity and ending as each plant area is turned over to the plant operator.b,i CONTRACT A document such as a contract order, change order, agreement, addendum, work order or task authorization which defines the requirements and conditions for fumishing contract services. q CONTRACTOR Any organization under contract for fumishing items or services. It includes the terms Vendor, Supplier, Subcontractor, Fabricator, and subtier levels of these where appropriate. d, i CORRECTIVE ACTION Measures taken upon the identification of an adverse condition to correct the condition and prevent recurrence. The basic elements of the corrective cction program are:
- 1) identification and immediate action;
- 2) review for impact / assignment
- 3) investigate and analyze;
- 4) corrective action planning and implementation;
- 5) verification of completion; and
- 6) verification of long-term effectiveness
. - 0
/
CHARACTERISTIC Any property or attribute of an item, process, or service that is distinct. describable, and measurable, as conforming or nonconforming a specified ' C quality assuranca requirements. Quality assurance characteristics are generally identified { in specifications and arawings, wh: :h describe the item, process or service. l 1 CLEANNESS A state of being clean in accordance with predetermined standards, and usually implies freedom f. rom dirt, scale, heavy rust, oil or other contaminating impurities. l COMMERCIAL GRADE Those items which (1) are not subject to design or specification requirements that are unique to facilities or activities licensed by the NRC and (2) are used in applications other than facilities or activities licensed by the NRC and (3) can be ordered from the manufacturer / supplier on the basis of information set forth in the g manufacturer's published product information or nationally recognized non-nuclear codes E or standards. (NOTE: Although an item is exempted from 10CFR21 being imposed on 1 the manufacturer, supplier or vondor by the definition of " Commercial Grade", the item j may still have other QA requirements which need to be imposed in the procurement L_ documents), r, q R g COMPONENT A piece of equipment such as a vessel, piping, pump, valve or core L support structure, which will be combined with other components to form an assembly; or: [ items frorn which electrical equipment is assembled, for example, resistors, capacitors, wires, connectors, transistors, switches, springs, etc.l CONDITION ADVERSE TO.QUAO1Y Failure of Safety Related Structure, System or Component (SSC) to perform their intended safety function, and safety related prccess 1_8 deficiencies and violations which could result in a degradation or challenge to Nuclear - Safety. CONSTRUCTION PHASE The period of time beginning with the start of construction activity and ending as each plant area is turned over to the plant operator.b,1 CONTRACT A documerit such as a contract order, change order, agreement, addendum, work order or task authorization which defines the requirements and conditions for fumishing contract services. q CONTRACTOR Any organization under contract for fum!shing items or services. It ince des the terms Vendor, Supplier, Subcontractor, Fabricator, and subtier levels of these where appropriate. d, i Chapter 2 Rev.18 Attachnient 7.4 (Page 4 of 19) 51
J. CORRECTIVE ACTION Measures taken upon the identification of an adverse condition 18 to correct the deficiency DEDICATION The act of verifying tnat a Commercial Grade item is acceptable for a safety related application. Dedication occurs after receipt when that item is designated for use as a basic component, r, q DEFECTIVE MATERIAL A material or component which has one or more characteristics that do not comply with specified requirements. i DEFICIENCY An observed condition that is or appears to be adverse to quality or beyond a defined or approved qualitative or quantitative acceptance criterion. q DESIGN Technical and management processes which commence with idenlification of design input and which lead to and include the issuance of design output documents. h DESIGN CRITERIA Documents which establish overall plant design requirements including NSSS and BOP interfaces; they establish the overall system parameterc and design requirements for major portions of the BOP as necessary for the interrelationship of systems, components and machir'es. h DESIGN DOCUMENTS Engineering specifications, drawings, calculations and/or instructions. h DESIGN INPUT Those criteria, parameters, bases or other design requirements upon which detailed final design is based. h DESIGN INTERFACE The relationship between design organizations internal or external to a company. q DESIGN OUTPUT Documents such as drawings, specifications, and other documents defining technical requirements of structures, systems, and components as delineated in Section 4 of ANSI N45.2.11. h Chapter 2 Rev.18 Attachment 7.4 (Page 5 of 19) 52
j t '.' g- Ent WATERFORD 3 QUALITY ASSURANCE APDENDlX C :REV.- 6.0 R TYPE: C1.31 PROGRAM MANUAL PAGE: 8 OF 19 MATERIAL A substance or combination of substances forming components, pads, pieces, and equipment items. (Intended to include such as machinery, castings, liquids, formed steel shapes, aggregates, and cement.). I MEASURING AND TEST EQUIPMENT (M&TE) Devices or systems used to calibrate, measure, gage, test, inspect, or control in order to acquire research, development, test or operational data, or to determine compliance with design, specifications, or other t::chnical requirements. M&TE does not include permanently installed operating cquipment, nor test equipment used for preliminary checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation, t
. MODIFICATION A planned change in plant design or operation and accomplished in sccordance with the requirements and limitations of applicable codes, standards, specifications, licenses, and predetermined safety restric'.lons. l 1 NONCONFORMING CONDITION ?An adverse condition affecting a safety related, quality rslated, trip sensitive ~(or balance of plant, when feasible) system caused by a deficiency in characteristic, documentation, of procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconforming conditions include, but may not be limited to:
o Unanticipated or unplanned entry into any Tech Spec LCO o Discovery of a condition of a system or component required to be operable by Tech Spec, which calls into question the current or past operability (including I missed surveillance testing); l o Failure of a component to meet a surveillance or post-modification test acceptance criteria (prior to performing any corrective mainianance); o An unanticipated ESFAS signal or actuation of ESFAS equipment; o identification of a discrepancy between a licensing document (i.e., FSAR, Tech Spec) or a design basis document, (i.e., drawings) and the actual configuration of the plant; o Discovery of a valve or breaker in a position different from that required by the proper procedure; o Unanticipated actuation of an over-current protective device, (i.e., blown fuse or tripped circuit breaker); o Routine actuation of an over-pressurization p,otective device, such as a relief valve; o Unexpected or unplanned reactor power, power distribution, or shutdown margin condition or transient; or, e issuance of incorrect or defective pads or material t
.m
, . .y I-LEAD AUDITOR ' An individual qualified to organize and direct an audit, report audit findings, and evaiuste corrective action, n, o -
MANUFACTURER One wno constructs any class of component, part, or appurtenance - o to meet prescribed design requirements. l
- MASTiOR EQUIPMENT UST (MEL) The MEL identifies each component by a component identification number and provides a compilation of pertinent data. The MEL is a -
comprehensive on-line computerized listing of the components in the Waterford 3 SES. The MEL is a source of component data to be used by the station departments such as maintenance, operations, engineering and quality control and ef'er Entergy Operations, Inc. organizations during routine operation and maintenance of Waterford 3. q
- MATERIAL A substance or combination of substances forming components, parts, ,
pieces, and equipment items. (Intended to include such as machinery, castings, liquids, : formed steel shapes, aggregates, and cement.). l MEASURING AND TEST EQUIPMENT (M&TE) Devices or systems used to calibrate, measure, gage, test, inspect, or control in order to acquire research, development, test or operational data, or to determine compliance with desijn, specifications, or other t::chnical requirements. M&TE does not include permanently installed operating equipment, nor test equipment used for preliminary chocks where data obtained will not be used to determine acceptability or be the. basis for c er.!gn or engineering evaluation. t MODIFICATION A planned change in plant design or operation and accomplished in
' cccordance with the requirements and limitations of applicable codes, standards, specifications, licenses, and predetermined safety restrictions. l
' *:5NONCONFORMANCE An adsrae condition affecting a safety related quality , related or trip
, sensitive system caused by a deficiency in characteristic, documentation, or procedure 18 which renders the quality of an' item unacceptable or indeterrr. mate.
OBJECTIVE EVIDENCE Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements, or tests which can be verified.1 NChapter 2 RevE186 Attachment 7.4 (Pnge 8 of 19) 55 a
-M g- Ent WATERFORD 3 QUALITY ASSURANCE APPENDIX C IREV.8.0 R-TYPE: C1.31 PROGRAM MANUAL PAGE: 15 OF 19 The items included in the above section (Special Scope, Non-Nuclear Safety and Other. Itsms with FSAR Note 17) are identified on the Waterford 3 Q-F. elated List. Implementation of a 10CFR50, Appendix B QA Program is based on a graded approach. The applicable criteria is defined in either the Special Scope pocedures, procurement documents, work packages, or applicable procedures. The criteria selection and program scope are identified by Engineering & Constniction in concert wiQ Quality Assurance and the responsible management. SAFEGUARDS INFORMATION (SI) security related documents not classified as National Security Information or Restricted Data, but protected from disclosure to the public an unauthorized persons. With respect to Waterford 3 SES, Si is any document which contains detailed information pertaining to;
- 1. Security measures for the oFysical protection of special nuclear materials; or
- 2. Security measures for the phyucal protection and location of certain plant equipment vital to the, safety of production facilities.
SEISMIC QUALIFICATION which demonctrates an equipment's abliity to perform its ' requiied function during and after the time that it is subjected to the forces resulting from a seismic disturbance (design basis earthquake). SHALL, SHOULD, AND MAY Raference Nuclear Management Manual, Vol.1, Corporate Directive C2.101. The word "shall"is used to denote a requirement considered enforceable by the appropriate regulatory body; the word "should" is used to denote a rccommended action, but not an enforceable requirement. Each employee is to carry out any "should" statement unless circumstances prevent or necessitate a deviation; and the word "may"is used to denote an option, neither a recommendation nor a requirement. q, c SIGN'lFICANT ADVERSE CONDITION a level of condition for which a Root Cause
' Analysis and action to prevent recurrence are required:
- 1. A condition will be classified as a Significant Adverse Condition when 4 meets one or more of the followino criteria:
- a. The unple'.n xi event, conditior or failure involves a system, structure, u, component that has resulted in, or has the potential to cause:
A
\ . ,
l- g WATERFORD 3 APPENDlX C = REY.-6.0
- Ent QUALITY ASSURANCE R TYPE: C1.31 PROGRAM MANUAL PAGE: 16 OF 19.
- 1. a reactor or secondary system transient; or
- 2. ,
a significant degradation of a safety related or trip sensitive system,
- b. The condition or event is reportable per 10CFR50.72,10CFR50.73, 10CFR21 or 40CFR;
- c. The condition a wt is cited by the Nuclear Regulatory Commission as a viMation;
- d. The condition or event has reached an unacceptable level of severity or recurrence; ,
- e. -The condition is classified as a significant industrial safety concern
, (e.g., resulting in a lost time accident;; or
- f. The condition or event is representative of a major noncompliance with, or major misunderstanding of Quality Assurance Program requirements (Usually determined by upper management).
SOURCE ACCEPTANCE of a product of Entergy Operations orits designated agent at , tha supplier's plant, prior to shipment. 3 SOURCE SURVEILLANCE A review, observation, or inspection for the purpose of vsrifying that an action has been accomplished as specified at the location of material procurement or manufacture. l-Se 2CIAL PROCESSES Those processes that require interim in-process controls in rddition to final inspection to assure quality. c SPECIAL TEST Test that is developed with the intent of being utilized only one time and is normally contained within the applicable work package, q
-SPECIFICATION A concise statement of requirements to be satisfied by a product, a material or piocess indicating, whenever appropriate, the procedure by means of which it may be determined whether the requirements giveri are satisfied. l SUBSYSTEM A group of assemblies or components or both corrbined to perform a single function. ;
1 Lu _a
^e The items included in the above section (Special Scope, Non-Nuclear Safety and Other items with FSAR Note 17) are identified on the Waterford 3 Q-Related List, implementation of a 10CFR50, Appendix B QA Program is based on a graded approach. The applicable criteria is defined in either_the Special Scope procedures, procurement - documants, work packages, or applicable procedures. The criteria selection and program scope are identified by Engineering & Construction in concert with Quality Assurance and the responsible management. SAFEGUARDS INFORMATION (SI) security-related documents not classified as National Security Information or Restricted Data, but protected from disclosure to the . public an unauthorized persons. With respect to Waterford 3 SES, Si is any document which contains detailed information pertaining to:
- 1. Security measures for the physical protection of special nuclear materials; or l 2. Security measures for the physical protection and location of certain plant equipment vital to the safety of production facilities.
SEISMIC QUALIFICATION which demonstrates an equipment's ability to perform its
- required function during and after the time that it is subjected to the forces resulting from
.a seismic disturbance (design basis earthquake).
I SHALL, SHOULD,- AND MAY ' Reference Nucl ear Management Manual, Vcl.1, Corporate Directive C2.101. The word "shall"is used to doncte a requirement considered cnforceable by the appropriate regulatory body; the word "should" is used to denote a recommended action, but not an enforceable requirement. Each employee is to carry out any "should" statement unless circumstances prevent or necessitate a deviation; and the word "may" is used to denote an option, neither a recommendation nor a requirement. q, c ' y SIGNIFICANT CONDITION REPORT LA classification of Condition Reports dotermined = by the Condiilon Review Group (CRG) that meets one or more of the below criteria:
- a. - A reportable event pe; 10CFR50.72 or 10CFR50.73 which requires written follow-up report, or 10CFR Part 21 reporting criteria (routine reports to the NRC are excluded).
- b. A problem recognized as having a greater than acceptable recurrence rate as determined by the CRG.
o Any event or nonconformance that meets the definition of repetitive event is significant.
- Maptai2 ReK181 e # Attachment 7.4 (Page 15 of 19) 62
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- c. An unplanned event or failure of a SSC that led or could have led to a reactor trip or plant transient.
- d. Near miss Industrial safety incident or Serious Accident.
3
- e. A major breakdown in processes that implement QA Program Requirements as determined by CRG.
- f. Evets or conditions designated as significant or considered important by management for reasons other than those which fallinto the above categories.
SOURCE ACCEPTANCE' of a product of Entergy Operations, Inc. or its designated egent at the supplier's plant, prior to shipment. 3 SOURCE SURVElLLANCE A review, observation, or inspection for the purpose of f v;rifying that an action has been accomplished as specified at the location of material ( procurement or manufacture. l SPECIAL PROCESSES Those processes that require interim in-process controls in 9 addition to final inspection to assure quality, e SPECIAL TEST Test that is developed with the intent of being utilized only one time and is normally contained within the applicable work package q SPECIFICATION A concisa statement of requirements to be satisfied by a product, a material or procesc indicating, whenever appropriate, the procedure by means of which it may be determined whether the requirements given are satisfied. l SUBSYSTEM A group of assemblies or components or both combined to perform a single function. l SUPPLIER Any individual or organization who furnishes items or services in response to a procurement document. It inclu'ies the terms Vendor, Seller, Contractor, Subcontractor, Fabricator, Consultant, and subtier levels. m SURVEILLANCE The act of monitoring or observing to verify whether an item or activity conforms to specified requirements, q SURVEILLANCE TESTING Periodic testing to verify that safety-related structures, systems. and components continue to function or are in a state of readiness to perform their functions. c Chapter 2 Rev.-18 Attachment 7.4 (Page 16 of 14) 63
- _ _ _ - _ . . ]
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 1.0 PURPOSE 1.1 This Chapter defines the responsibilities of organizations and individuals engaged in the implementation of quality related activities at Waterford 3. Additional organizational information is contained in the Nuclear Management Manual, reference 2.E
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.8, Revision 1-R, September 1975 (which endorses ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel") 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 2.3 ANSI /ANS 3.1-1978, "American National Standard For Selection and Training of Nuclear Power Plant Personnel" 2.4 NUREG-0737, " Post TMI Requirements" 2.5 Nuclear Management Manual 3.0 DEFINITIONS 3.1 - See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Entergy Operations, Inc. (EOI) Management 4.1.1 Entergy Operations, Inc. management retains and exercises responsibility for the Quality Assurance program at Waterford 3. Management conducts regular meetings and makes every attempt to collectively coordinate and schedule activities within the various organizations to ensure that an effective Quality Assurance program is maintained. 4.1.2 Entergy Operations, Inc. management is responsible for the development and maintenance of procedures to direct or describe quality related activities performed by or for their organization as required by the Quality Assurance program. 2
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4 4.1.3 Entergy Operations, Inc. management is responsible for ensuring that implementing procedures within their department adequately implement Waterford 3 commitments and obligations. 4.2 Vice President, Operations 4.2.1 The Vice President, Operations is responsible for assuring the development and approval of Waterford 3 quality policies. Reporting to him are the: I 4.2.1.1 General Manager, Plant Operations; 4.2.1.2 Director, Plant Modification and Construction; 4.2.1.3 Director, Site Support; 4.2.1.4 Director, Nuclear Safety and Regulatory Affairs; gl
- 4.2.1.5 Director, Quality; 3l 4.2.1.6 Director, Training; and 15 4.2.1.7 Safety Review Committee.
12 & 157l 4.2.2 The Vice President, Operations is responsible for appointing the Chairman of the Safety Review Committee (SRC). The Vice President, Operations is also 11-responsible for oversight of the SRC. 4.2,3 The Vice President, Operations reviews trend reports, status summaries, and the results of management assessments to evaluate the effectiveness of the Waterford 3 Quality Assurance program. In addition, the Vice President,
- Operations or his designee, endorses the Waterford 3 Management Manual, and revisions thereto, which contain policies and procedures applicable to Waterford 3, 4.3 General Manager, Plant Operations 4.3.1 The Waterford 3 plant operations organization (hereinafter referred to as the Plant Operations Staff) is headed by the General Manager, Plant Operations.
The primary quality related responsibilities of the General Manager, Plant Operations include. - 4.3.1.1 Providing and maintaining a trained and qualified staff to safely operate and maintain the plant; 3 i 1
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization i Revision 18 4.3.1.2 Assuring the development and proper implementation of quality related procedures and instructions for activities such as plant operations, maintenance, sepair, test, radiation protection. fire protection, and safety to ersure plant and personnel safety; 4.3.1.3 Addressing matters brought to his/her attention by the Plant Operations . Review Committee (PORC), which is established to ensure on-site review and evaluation of plant operations, maintenance, and test programs. The PORC reports to the General Manager, Plant Operations and advises him/her on matters related to nuclear safety, including referral of topics , requiring review and potential action by the SRC. PORC membership and responsibilities are in accordance with this manual. The PORC is also , responsible for the review of design changes and site nonconformance documents which have been dispositioned as "use-as-is" or " repair,"; 4.3.1.4 Designating the Chairman of the Condition Review Board (CRB); gl 4.3.1.5 Analyzing conditions for trends regarding equipment failure, and publishing a quarterly trend report; 4.3.1.6 Approving design changes prior to implementation; 4.3.1.7 Developing and maintaining quality related operations and maintenance procedures; 4.3.1.8 Implementing Technical Specification controls and surveillances; 4.3.1.9. Identifying and performing required corrective and preventive maintenance; 4.3.1.10 Implementing a measuring raad test equipment calibration program; 4.3.1.11 Providing engineering /technit . upport for primary / secondary chemistry, environmental monitoring, raca.on protection, water treatment, and process controls; 4.3.1.12 Initiating, prioritizing, and performing acceptance testing of plant modification activities; 4.3.1.13 Reactor engineering and special nuclear material control and accountability controls; 4
. . _ . . _ _ - . _ _ _ _ _ . . _ _ . . .- - - __ _ _. . - _ _ ~ -_
Watedord 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.3.1.14 Coordinating the Fire Protection program; 4.3.1.15 Housekeeping inside the Radiation Controlled Areas; 4.3.1.16 ' On-site handling, storage, packaging, and shipping of radioactive wastes; i 4.3.1.17 Providing technical expertise to assist in the on-site handling, storage, i packaging, cleaning, and release for shipping to a transit carrier of i radioactive material; I 4.3.1.18 Developing and controlling the ALARA program; 4.3.1.19 Developing and controlling the Radiation Protection program, including Radiological Effluent Monitoring program; l 4,3.1.20 Managing or implementing the In-service Testing, Local Leak Rate Testing, and the Hydrcstatic Testing programs; 4,3.1.21 Acting as a liaison with regulatory agencies on technical issues involving
- plant chemistry; 4.3.1.22 Reviewing design changes and plant modifications from a radiological standpoint;
- 4.3.1.23 Assembling Work Authorization Packages including support documentation such as procedures, drawings, etc.;
4.3.1.24 Performing a quality review of all maintenance initiated work - authorizations not containing a hold point, not involving special processes, I or not classified as safety related, to ensure the inclusion of quality requirements; 4.3.1.25 Tracking controlled maintenance activities related to installed plant hardware to closure; 4.3.1.26 Directing the management of the Hazardous Waste / Hazardous Material
- programs;
]
4.3.1.27 Acting as a liaison with regulatory agencies on technical issues involving i i the environment; I 5 l
Waterford 3 Quality Assurancc Program Manual Chapter 1 Organization Revision 18 4.3.1.28 Developing and implementing Radiological and Non-Radiological Environmental Monitoring programs; and 4.? " 29 Implementing the Entergy Operations, Inc. welding program. 4.4 Utrector, Plant Modification and Construction 4.4.1 The primary quality related responsibilities of the Director, Plant Modification and Construction include: 4 A 1.1 Coordinating plant design changes; 4.4.1.2 Managing the plant modification process through the phases of design, implementation, testing, and acceptance; 4.4.1.3 Coordinating the development and review of departmental procedures; 4.4.1.4 Reviewing and processing assigned work authorizations and managing services for plant repair, modification, and construction which is under his jurisdiction; 4.4.1.5 Performing a quality review of all construction initiated work authorize +%ns not containing a hold point, not involving special processes, or not classified as safety related, to ensure the inclusion of quality requirements; 4.4.1.6 Ensuring proper completion of modifica' ion and construction work prior to acceptance; and 4.4.1.7 Coordinating construction tasks involved with outages and retrofitting. 4.5 Director, Site Support 4.5.1 The primary quality related responsibilities of the Director, Site Support include: 4.5.1.1 Managing the preparation and approval of the Waterford 3 Emergency Plan and implementing procedures; 4.5.1.2 Coordinating the preparation of emergency drill scenarios and performance of practice drills; Sl 6
' p se
A Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.5.1.3 Implementing the Security Plan and Safeguards Contingency Plan: 4.5.1.4 Controlling plant area access; 11,12,13 & 15 4.5.1.5 Overseeing the activities of the Employee Concerns Progrem; JT&] 4.5.1.6 Providing direction to on-site Materials, Purchasing and M acts group; 3l t 4.5.1.7 Providing support for records management, including execution of document controi and records storage programs; 4.5.1.8 Coordinating the development, preparation, and maintenance 11,12 & 15
-- ~
of Waterford 3 policies and procedures; and 4.5.1.9 Providing Medical Review Officer services (reviewing and interpreting presumptive positive test results) for the Fitness for Duty Program. 12 & "15 4.6 Director, Nuclear Safety and Regulatory Affairs 12 4.6.1 l oe primary quality related responsibilities of the Director, Nuclear Safety and ~ Regulatory Affairs include: 4.6.1.1 Coordinating and reviewing responses to Nuclear Regulatory Commission matters, as assigned; i 2.6.1.2 Managing the preparation of updates / revisions to the Final Safety Analysis Report and the Technical Specifications; 4.6.1.3 ,Aanaging the Waterford 3 Commitments Management System; , 4.6.1.4 Managing the preparation of responses to NRC bulletins, orders, inspection reports, generic letters, and Notices of Violation; i 4.6.1.5 Oversight of the administration of the Condition Report process, root l cause analysis and trend programs; 11,12 & 13 4.6.1.6 Analyzing conditions for human performance trends and publisfiing , quarterly trend reports; 4.6.1.7 Reviewing corrective action documents for determination of reportability; 4.6.1.8 Reviewing operating abnormalities and initiating Licensee Event Reports; 3 l 7 l
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization [ Revision 18 4.6.1'.9 Coordinating Nuclear Regulatory Commission interface; gl - 4.6.1.10 Reviewing plant system problems and performance concerns; 3&3l
- 4.6.1.11 Examining plant operating characteristics, NRC issuances C7cludes d
Information Notices), industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, involving units of similar des!gn, which may indicate areas for improving plant safety as part of the Independent TechMcal Review function. The Independent Technical Review functions include responsibility for: 12 & 13
- a. Making recommendations for improving plant safety including procedure revisions, equipment modifications, maintenance activities, operations i activities, or other means of improving plant safety.
*,13 12 & 18 L 4.6.1.12 --
Maintaining SRC charters; and i 4.6.1.13 Performing independent reviews, safety examinations, and other review 13
- activities in support of the SRC and Technical Specification requirements.--
) M & g l'
- 4.7 Director, Quality i
- j. 4.7.1 The Director, Quality is responsible for the direction and administration'of the-i- Quality Assurance organization.
4.7.1.1 . The qualifications of the Director, Quality include as a minimum:
- a. - Graduate of a college or university with a Bachelor's degree in an -
! engineering, science or related field, or equivalent capabilities;
-12 & 15 i b. A minimum of four years experience in quality assurance or a quality assurance related activity with at least two of those years in the nuclear power industry as a manager or supervisor;
- c. - Experience in development and implementation of quality assurance
_ programs, plans, and procedures; 4
- d. Expertise in interpretation and application of Appendix B to 10CFR50 and c related codes, standards, and regulatory guides;
- e. Knowledge of inspection and nondestructive testing requirements;
( i 8 a _ _ - _ . , , . . ,,.y_. _
. _ _ _ _ _ -. + -
J Waterford 3 Quality Assurance Program Manual Chapter 1 _ Organization Revision 18 i
- f. Ability to plan, organize, and administer a Quality Assurance program; and
- g. Ability to maintain an effective working relationship with employees, contractors, suppliers, government agencies, and the public, 4.7.1.2 The primary quality related responsibilities of the Director, Quality include:
- a. Planning, organizing, and administering the Quality Assurance program; o
d
- b. Developing, reviewing, and concurring with the content of the Waterford 3 Quality Assurance Program Manual and changes thereto;
- c. Developing Quality Assurance Procedures (QAPs);
- d. Assisting in establishing that portion of the Training program that 12 & 15 addresses quality assurance;
- e. Advising, reviewing, and concurring on the scope and content of quality assurance training and indoctrination programs for personnel performing quality related activities; 4
- f. Providing requested inspection training to personnel performing quality related activities;
- g. Certifying Lead Auditors and Inspectors;
, h. Assuring effective implementation of the Quality Assurance program through a comprehensive system of reviews, assessments, and the 4 performance or monitoring of nondestructive examinations and other
- special processes;
- i. Maintaining surveillance of plant activities to provide independent
- verification that these activities are performed correctiv and that human 18 errors are reduced as much as practical;
. J. - Ensuring that quality reviews are conducted for quality related implementing procedures and design changes, including drawings 12 & 15 and specifications, to ensure the inclusion of quality requirements; 9
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18
- k. Reviewing all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensure the inclusion of quality requirements, and ensuring that quality reviews are conducted for all other initiated work authorizations;
- l. Reviewing nonconformance work authorization packages;
- m. Assuring that the corrective action processes (results of audits, 12 & 15 assessments) under his/her jurisdiction are implemented according f5-approved procedures;
- n. Conducting reviews, assessments and monitoring of the various corrective action processes to ensure that the required program aspects are adequately addressed;
- o. Conducting an ongoing assessment of the radiation protection and radwaste programs;
- p. Establishing and maintaining documentation of Quality Assurance activities;
- q. Providing status information regarding the Qual:y Assurance program to the Vice President, Operations; and
- r. Interfacing with on-site and outside organizations such as the NRC, INPO, Quality Assurance, and equipment vendors to ensure quality is maintained.
12 & 15 4.7.1.3 Quality Assurance personnel have sufficient authority and organizational ~- freedom to effectively:
- a. Identify quality problems;
- b. Initiate, recommend or provide solutions through designated channels; and
- c. Verify implementation of solutions.
4.7.1.4 This organizational freedom includes sufficient independence from cost and schedule when opposed to safety considerations; 10
Waterford 3 Quality As,surance' Program Manual Chapter 1 Organization . Revision 18 , '4.7.1.5 The Director, Quality has the authority to stop unsatisfactory work - and/or contrrl *:rther processing, delivery, or installation of 12 & *15 nonconforming material through designated channels; I 4.8 Director, Training 15 4.8.1 The primary quality related responsibilities of the Director, Training include: 4.8.1.1 Providing training for Waterford 3 personnel, including training required by regulations, General Employee Training, and training for the Engineering Support Personnel; 4.8.1.2 Maintaining training records; and 4.8.1.3 Providing an instructor certification program.
~12 & 15 l
~
4.9 Safety Review Committee l 4.9.1 The Safety Review Committee (SRC) is responsible for providing Entergy _ , Operations additional assurance that Waterford 3 is operated and maintained in ' accordance with the Operating License, Technical Specifications, and applicable i Federal and state regulations which address nuclear safety. The SRC is 2 responsible for providing independent review and audit of Waterford 3 operations; reviewing changes or modifications which involve an unreviewed safety question; reviewing safety evaluations of changes made to the plant and plant procedures under the provisions of 10CFR50.59; maintaining oversight and assessing the effectiveness of the corrective action program; and performing special evaluations, reviews, and audits as may be requ6sted by the , Vice President. Operations. 4.9.2 The SRC shall function to provide independent review a'nd audit of designated activities in the areas of: 4.9.2.1 Nuclear power plant operations; 4.9.2.2 Nuclear engineering; 4.9.2.3 Chemistry and radiochemistry; 1 4.9.2.4 Metallurgy; 4.9.2.5 Instrumentation and control; 11
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.9.2.6 Radiological safety; 4.9.2.7 Mechanical and electrical engineering; and 4.9.2.8 Quality' assurance practices. 4.9.3 The SRC shall be composed of at least five members, including the Chairman.
- Members of the SRC may be from within the Entergy Operations Inc.
organization or from organizations external to EOl. The qualifications of - members selected for the SRC shall be in accordt.nce with Section 4.7 of ANSI /ANS3.1-1978. . 4.9.4 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time. 4.9.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advise to the SRC. 4.9.6 The SRC shall meet at least once per 6 months. gl 4.9.7 The quorum of the SRC necessary for the performance of the review and audit function shall consist of a minimum of five members or of not less than a majority of the composition of members in paragraph 4.9.3 above, whichever is greater, g l No more than a minority of the members shall have line responsibility for operation of the plant. ! 4.9.8 The SRC shall be responsible for the review of: l 4.9.8.1 The safety evaluations for (1) changes to procedures, equipment, or sptems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; I l 4.9.8.2 Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; l
- 4.9.8.3 Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; l 12 i
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.9.8.4 Proposed changes to Technical Specifications or the Operating License; 4.9.8.5 Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; 4.9.8.6 Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; 4.9.8.7 All REPORTABLE EVENTS; 4.9.8.8 All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and 4.9.8.9 Reports and meeting minutes of the PORC. 4.9.9 The SRC shall report to and advise the Vice President, Operations on areas of responsibility. 4.9.10 Records of SRC activities shall be prepared, approved, and distributed as indicated below: 4.9.10.1 Minutes of each SRC meeting shall be prepared, approved, and forwarded to the Vice President, Operations within 14 days following each meeting; 4.9.10.2 Reports of reviews encompassed in paragraph 4.9.8 above shall be _14l prepared, approved, and forwarded to the Vice President, Operations within 14 days following completion of the review; and 4.9.10.3 Audit reports encompassed by paragraph 5.2 of Chapter 18 shall be forwarded to the Vice President, Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization; 4.10 Plant Operations Review Committee (PORC) 4.10.1 The PORC shall function to advise the General Manager, Plant Operations on all matters related to nuclear safety. 13
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.10.2 The PORC shall be composed of site management members as assigned, in writing, by the GMPO. The GMPO will also indicate, in writing, the PORC
~
11 Chairman. 4.10.3 The PORC shall meet at least once per calendar month and as convened by the 3I PORC Chairman. Ml 4.10.4 The quorum of the POP.C necessary for the performance of the PORC responsibility rdsd authority provisions shall consist of the Chairman and three members. 3 4.10.5 The PORC shall be responsible for: 4.13.5.1 Review of (1) all plant administrative procedures required by Technical Specification 6.8 and changes thereto, (2) all programs required by Technical Specificatior 6.8 and changes thereto, (3) changes to the Waterford 3 Emergency Operating Procedures required to implement the requirements of NUREG 0737 and NUREG 0737, Supplement 1, as stated in Generic Letter 82-33, and (4) any other proposed procedures or changes thereto as determined by the General Manager, Plant Operations; 4.10.5.2 Review of all proposed tests and experiments that affect nuclear safety; 4.10.5.3 Review of all proposed changes to Appendix "A" Technical Specifications; 4.10.5.4 Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; 4.10.5.5 Review of investigations of all violations of the Technical Specifications including the prepcration and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager, Plant Operations and to the Safety Review Committee; 4.10,5.6 Review of all REPORTABLE EVENTS; ~ 4.10.5.7 Review of unit operations to detect potential hazards to nuclear safety; 14
Waterford 3 Quality Assurance Program Manual Chapter 1 Organh.ation Revision 18 4.10.5.8 Performance of special reviews, investigations, or analyses and reports thereon as requested by the General Manager, Plant Operations or the Safety Review Committee; 4.10.5.9 Review of the Security Plan and submittal of recommended changes to the Safety Review Committee; 4.10.5.10 Review of the Emergency Plan and submittal of recommended changes to the Safety Review Committee; 4.10.5.11 Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PORC meeting; 4.10.5.12 Review of proposed modifications to the CPC addressal:e constants based on information obtained through the Plant Computer-CPC data link; 4.10.5.13 eleview of any accidental, unplanned or uncontrolled radioactive release including reports covering evaluation, recommendations t.nd disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President, Operations and to the Safety Review Committee; 4.10.5.14 Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL, and major changes to radwaste treatment systems; 4.10.5.15 Review of the Fire Protection Program and submittal of recommended changes to the Safety Review Committee; and 4.10.5.16 Review of proposed procedures and changes to procedure,s which involve an unreviewed safety question as defined in 10CFR50.59. 4.10.6 The PORC shall: 4.10.6.1 Recommend in writing to the General Ff , Plant Operations, prior to implementation except for temporary ci , to procedures as provided in Technical Specification 6.8.3, at al or disapproval of items considered under paragraph 4.10.5.1 through 4 and 12; _14l 15
Waterford 3 Quality Assurance Program Manual Chapter 1 Organization Revision 18 4.10.6.2 Render determinations in writing, prior to implemer.tation except for temporary changes to procedures as provided in Specification 6.8.3, with regard to whether or not each item considered under pragraph 4.10.5.1 through 5 constitutes an unreviewed safety question; and g 4.10.6.3 Provide written notification within 24 hours to the Vice President, Operations and tne Safety Review Committee of disagreements between the PORC and the General Manager, Plant Operations; however, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1. 4.10.7 The PORC shall maintain written minutes of each PORC meeting that, at a
- minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Vice President, Operations and the Safety Review Committee.
4.11 Director, Design Engheering 4.11.1 The primary quality related responsibilities of the Director, Design Engineering, (who reports to the Vice President, Engineering, domiciled in Jackson and not part of the Waterford 3 site organization) include: 4,11.1.1 Being the design authority for changes to the design basis except for - nuclear fuel and core design; 4.11.1.2 Performing design evaluations to address plant problems; 4.11.1.3 Maintaining the design configuration documentation in an as-built condition; 4.11.1.4 Assessing the impact of changes to plant design and operation on the design basis accident analysis; 4.11.1.5 Supporting plant activities for environmental qualification (EQ); 4.11.1.6 Reviewing new or changed technical and quality requirements for spare and replacement part requisitions classified as EQ: 16
Waterford 3 Quality Assurance Prograrn Manual Chapter 1 Organitetion Revision 18 4.11.1.7 Maintaining the Waterford 3 EQ List; 4.11.1.8 Assisting in the establishment of quality assurance and technical requirements in selected quality related procurement documents; 4.11.1.9 Evaluating part substitutions; 4.11.1,10 Dedicating commercial grade items for use in safety related applications; 4.11.1.11 Supporting plant activities for ASME Section XI: 4.11.1.12 Developing and maintaining the following Waterford 3 programs:
- a. ASME Ten Year in-service inspection Program;
- b. Steam Generator Eddy Current Program;
- c. Erosion / Corrosion Prograri;
- d. Microbiologically Induced Corrosien (MIC) Program;
- e. Lifting Rig Assembly inspection Program; and
- f. - 10CFR50.49 Environmental Qualification of electrical equipment important to safety for nuclear power plants.
4.11.1.13 M&intaining the Waterford 3 Q-List and Q-Related List to define safety and quality classifications; 4.11.1.14 Maintaining the site tagging and labeling standard; and 4.11.1.15 Piping analysis. 4.12 Vict o resident, Engineering 4 4.12.1 The Vice President, Engineering reports directly to the Executive Vice President
& Chief Operating Officer, and is responsible for providing the direction and administration necessary to the Waterford 3 Design Engineering department and services including:
4.12.1.1 Reactor physics analysis; 17 1
Waterford 3 Quality Assurance Program Manual Chapter i Organization Revision 18 4.12.1.2 Plant transient analysis; 4.12.1.3 Thermal hydraulic analysis; 4.12.1.4 Nondestructive analysis; 4.12.1.5 Metallurgical evaluations; 4.12.1.6 Fuel fabrication and related sewices; 4.12.1.7 Reactor t.ngineering and special nuclear material control and accountability; and 6 4.12.1.8 Entergy Operations, Inc. welding program. 4.13 Vice President, Operations Support 4.13.1 The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for: 4.13.1.1 Administering corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operatior s, maintenance, outage management, security implementation (Access Authorization and Fitness For Duty), 13l emergency planning, technology transfer, and central licensing; providing-oversight of site Health Physics and Chemistry activities; and managing the Plant Support and Assessment, Information Systems, Material Requiremerits, and Materials, Purchasing and Contracts groups. It is 3 the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed in accordance with the requirements of the Waterford 3 Ouality Assurance program; and 4.13.1.2 Providing the direction and administration necessary relative to the following listed primary quality related responsibilities as they relate to the Waterford 3 Quality Assurance Program:
- a. Evaluating quality assurance programs and activities of Waterford 3 suppliers, contractors, and EOl shared services of quality related items, spare parts, and services through reviews, surveillances, and 3l audits; 18
Waterford 3 Quality Assurance Program Manual Chapter i Organization Revision 18
- b. Conducting pre-award evaluations for quality requirements of vendors, suppliers, and contractors where applicable; c, Maintaining a qualified suppliers list (QSL) for use in procuring safety a related items, spare parts, and services;
- d. Performing design review and fuel fabrication audits as necessary to ensure that nuclear fuel procured for use by Entergy Operations, Inc. is designed and fabricated in accordance with applbable codes, standards, and regulations;
- e. Selecting vendors and contractors based upon technical, quality and commercial cvaluations; 3l
- f. Purchasing and receipt of equipment, parts, materials, and supplies in support of Waterford 3 operations and station modifications;
- g. Administering a quality control receipt inspection program to assure acceptability of quality related materials, parts, and components; 3l
- h. Coordinating the process lng and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, including maintenance and design changes;
- i. Establishing quality assurance and technical reauirements in quality related procurement documents; s
J. Maintaining storage conditions necessary to sustain material quality; and
- k. Processing and securing material traceability data to support historical reference.
4.14 Waterford 3 Personnel Waterford 3 personnel are responsible for adherence to the requirements 11_ delineated in this QA Program Manual and its implementing procedures. WaterforT 3 personnel are also responsible for identify!ng and reporting conditions adverse to quality and for identifying program or procedural enhancements. 19 j .. . .
I Waterford 3 Quality Assurarece Program Manual Chapter 1 Organization Revision 18 4,15 Suppliers / Contractors Suppliers / contractors of quality related material, equipment, spare parts, and/or services shall be required, as appropriate, by procurement documents to have a quality program. In such cases, a line of communication shall exist between the supplier / contractor and the Waterford 3 or Headquarters Quality Assurance organization. The overa'l respcnsibility for quality at Waterford 3 remains with Entergy Operations, Inc. at all times. Services obtained from other EOl sites are initiated through documented agreements between the various EOl sites. 3 5.0 PROCEDURE 5.1 Organizations Performing Quality Assurance I unctions Attachment I shows the lines of authority for the major Entergy Operations, Inc. organizations that perform Quality Assurance functions at Waterford 3. 6.0 RECORDS None 7.0 ' ATTACHMENTS 7.1 Waterford 3 Organization Chart. 20
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r Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 1.0 PURPOSE 1.1 It is the objective of Entergy Operations, Inc. (EOl) to operate and maintain the Waterford 3 nuclear plant in the highest degree of functionalintegrity and reliability and to avoid undue risk to the health and safety of employees and the general public. It is the policy of Entergy Operations, Inc. that the programs for design, procurement, fabrication, installation, inspection, testing, operation, maintenance, repair, refueling, and modification of Waterford 3 comply with the requirements of 10CFR50, Appendix B and other related regulatory guidance. 1.2 This section of the QA Program Manual describes the overall Waterford 3 Quality Assurance Program which assures that quality related activities are performed in a controlled manner and are documented to provide objective evidence of compliance with NRC regulations ar' guidance. This program takes into account the need for trained personnel, approved procedures, special controls, processes, equipment, and skills necessary t7 attain the required quality, and the need for verification of quality by inspection, testing, and audit. 1.3 The Quality Assurance Program is implemented through the use of approved policies, procedurcs, and instructions which provide written guidance for the control of quality related activities. These documents incorporat; the requirements of the regulatory guides and the NRC endorsed ANSI Standards to which Waterford 3 has specifically committei
2.0 REFERENCES
2.1 - USNRC Regulatory Guide 1.33, Rev. 2, February 1978 (which endorses ANSI N18.7-1976," Administrative Controls and Quality Assurance foi the Operational Phase of Nuclear Power Plants") 2.2 Technical Specifications, Waterford Steam Electric Station, NUREG-1117 2.3 10CFR50, Appendix B," Quality Assurance Criteria for Nuclear Power Piants and Fuel Reprocessing Plants"
, 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. , 22
i Waterferd 3 Quality Assurance Program Manual Chapter 2 - Quality Assurance Program Revision 18 - 4.0 RESPONSIBILITIES 4.1 Vice President, Operations The Vice President, Operations is responsible for providing overall approval and direction for the Waterford 3 Quailty Assurance Program. 4.1.1 Safe *y Review Committee (SRC) The Safety Review Committee is responsible for functioning as the off-site independent review committee. The SRC is responsible for: providing independent review and audit of Waterford 3 operations, reviewing changes or modifications which involve an unreviewed safety question, and reviewing safety evaluations of changes made to the plant and plant procedures under the provisions of 10CFR50.59. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 4.2 General Manager, Plant Operations The General Manager, Plant Operations is responsible for ensuring the development of procedures or instructions for the implementation of the following functional units: Plant Operations Review Committee (PORC); Operations; Maintenance; Plant Engineering; Chemistry; Radiation Protection / Safety; and 10l Planning and Scheduling. The primary quality related responsibilities of the Geneial Manager,' Plant Operations are listed in Chapter 1. 4.2.1 - Plant Operations Review Committee (PORC) The PORC is responsible for functioning as the on-site independent review committee, and is responsible for reviewing plant operations items and procedures wh!ch are submitted to it; and for recommending approval by the General Manager, Plant Operations in accordance with appilcable procedures. Additional responsibilities are listed in Chapter 1 and the Waterford 3 Technical Specifications. 23
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Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 4.3 Director, Plant Modification and Construction The Director, Plant Modification and Construction is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Modification Control, Construction, and Project Management The primary quality related responsibilities of the Director, Plant Modificatior: and Construction are listed in Chapter 1. 4.4 Director, Site Support ' The Director, Site Support is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Security; Emergency 10,11 & 12 Planning, Site Business Services; and Employee Concerns Program. The Primary quality related responsibilities of the Director, Site Support are listed in Chapter 1, 4.5 Director, Nuclear Safety and Regulatory Affairs The Director, Nuclear Safety and Regulatory Affairs is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the follow lng programs and organizational units: Licensing; Operational 10 & 11 Experience Engineenng; and in-House Events Analysis. The primary
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quality related responsibilities of the Director, Nuclear Safety and Regulatory Affairs are listed in Chapter 1. 4.6 Director, Quality The Director, Quality is responsible for ensuring the devcs nment and maintenance of procedures or instructions for the implementation of the Quality Assurance 12 organization. The primary quality related responsibilities of the Director, Quality are-- listed in Chapter 1. 4.7 Director, Training 12 The Director, Training is responsible for ensuring the development and maintenance-- of procedures or instructions for the implementation of the following programs and organizational units: Operations Training; Simulator Training; Maintenance Training; Technical Training; and Engineering Training and Accreditation. The primary quality related responsibilities of the Director, Training are listed in Chapter 1. 3l 3&gl 24
Waterford 3 Quality Assurance Program Manual Chapter ? Quality Assurance Program Revision 18 4.8 Director, Design Engineering The Director, Design Engineering is responsible for ensuring the development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Safety and Engineering Analysis; Procurement / Programs Engineering; and Design Engineering. The primary quality related responsibilities of the Director, Design Engineering are listed in Chapter 1. 4.9 Vice President, Engineering The Vice President, Engineering reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for providing engineering services in support of the Waterford 3 Quality Assurance Program. The primary quality related responsibilities of the Vice President, Engineering are listed in Chapter 1. 4.10 Vice President, Operations Support The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of corporate support functions in the areas of radiological protection, radioactive waste management, chemistry, environmental services, operations, maintenance, outage management, security, emergency planning, technc.ogy transfer, and central licensing; oversight of site Health Physics and Chemistry activities; and management of the Plant Support and Assessment, Information Systems, Material Requirements, EOl shared services, and Materials, Purchasing 11 & 18l Purchasing and Contracts groups. It is the responsibility of the Vice President, Operations Support to assure that these functions performed for Waterford 3 are performed 17 accordance with the requirements of the Waterford 3 Quality Assurance program. 25
Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 S.0 PROCEDURE 5.1 Document Hierarchy 5.1.1 A'.lachment 7.1 depicts the hierarchy of docurients comprising the 'Naterford 3 Quality Assurance program. This attachment identifies vanous program documentation that controls quality related activities at Waterford 3. Quality Assurance program implementing documents define the responsibilities of 9 individuals and organizations participating in quality related activities. 5.1.2 The highest level of the Waterford 3 Quality Assurance program includes: 5.1.2.1 Federal and state regulations; 5.1.2.2 Industry codes and standards; 5.1.2.3 Licensing agreements and specifications; and 5.1.2.4 The Final Safety Analysis Report. 5.1.3 The next level of the document hierarchy includes: 5.1.3.1 Nuclear Management Manual; 5.1.3.2 Waterford 3 Management Manual; and 5.1.3.3 Waterford 3 Quality Assurance Program Manual (QAPM). 5.1.4 The succeeding level of documentation contains departmental level procedures and instructions. 5.1.5 This manual, as well as the Quality Assurance Prograi.i Manual (Special Scope), provides the media for informing responsible organizations and individuals that implementation of the Quality Assurance program is mandatory and that the Quality Assurance program shall be enforced. 26 j
Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 _ 5.2 Quality Assurance Program Manual { 5.2.1 This Quality Assurance Program Manual defines the responsibilities cc.d activities necessary to imt lement the quality requirements and commitments contained in the highest level documents including 10CFR50 Appendix B, the t regulatory guides, and the ANSI Standards as listed in Attachment 7.2 of this chapter. 5.2.2_ Chapters 1 and 2 of this manual address the Wateiford 3 quality related commitments in order to summarize the entire scope of the Quality Assurance program. 5.2.3 Chapters 3 through 18 of this manual have been developed to promulgate the safety related commitments only. 5.3 Quality Assurarice Program Manual (Special Scope) 5.3.1 The Quality Assurance Program Manual (Special Scope) defines the quality requirements for quality related items and activities not meeting the definition of safety related. The Quality Assurance Program Manual (Special Scope) has been developed to define the 10CFR50 Appendix B criteria applicable to specific activities. The Quality Assurance Program Manual (Special Scope) may_ address each criteria and its implementation; or reference the applicable chapter of this Quality Assurance Program Manual, stating that the safety related controls apply. 5.3.2 The chapters provide direction for the following special scope programs: 5.3.2.1 Fire Protection Quality Assurance; 5.3.2.2 Radiological Effluent and Environmental Monitoring; 5.3.2.3 Emergency Preparedness; 5.3.2.4 Security; 5.3.2.5 Radioactive Waste Management Quality Program; 5.3.2.6 Special Nuclear Material Control and Accountability; 5.3.2.7 Computer Software; 27
Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 5.3.2.8 ALARA Program; 5.3.2.9 Radiation Protection: 5.3.2.10 ATWS; and 5.3.2.11 Station Blackout. 5.4 Procedures and Instructions 5.4.1 The individual Er.tergy Operations, Inc. organizations assigned responsibilities by the Nuclear Management Manual, Waterford 3 Management Manual, and the QAPM shall be responsible for the development, maintenance, and implementation of procedures and instructions to detail the respective elements of program performance. 5.4.2 The procedure types listed in 5.4.3 have been developed at Waterford 3 to address required aspects of plant management and operations. These procedures will: 5.4.2.1 Implement the policy and direction of the Nuclear Management Manual, Waterford 3 Management Manual, and the QAPM to provide control over quality related operations and activities to a degree consistent with their importance to safety; 5.4.2.2 Provide a clear understanding of the operating philosophy at Waterford 3; and 5.4.2.3 Delineate the responsibilities and authorities of the Waterford 3 staff, 5.4.3 - The Waterford 3 procedures and instructions contained in this level are the: 5.4.3.1 Plant Operating Manual; 5.4.3.2 Quality Assurance procedures; 5.4.3.3 Site Support procedures; i 5.4.3.4 Design Engineering procedures:- 5.4.3.5 Design Engineering Administrative Manual (DEAM); 5.4.3.6 Plant Modification and Construction procedures; 28
Waterford 3 Quality Assurance Program Manual Chapter 2 Quahty Assurance Program Revision 18 5.4.3.7 Nuclear Safety and Regulatory Affairs procedures; 5.4.3.8 Nuclear Training procedures; and 5.4.3.9 Materials, Purchasing & Contracts Administrative Procedures. 3l 5.5 Identification of Safety Related Structures, Systems, and Components E 5.1 The QuaFty Assurance "rogram applies to all activities associated with quahty related structures, systems, and components to an extent commensurate with their importance to safety. FSAR Table 3.2-1, Chapter 2 Attachment 7.2, and the Waterford 3 Q-List ' rovide safety related classifications of plant structures, systems, and components; and identify those items subject to 10CFR50 Appendix B requirements. 5.5.2 Procedures provide further guidance for the identification of safety and quality related structures, systems, components and related activities to assure that the appropriate level of Quality Assurance program requirements are applied. 5.5.3 Procedures for the preparation and control of procurement documents provide guidance for spare and replacement part classification determination. These procedures invoke applicable codes, standards, regulations, FSAR requirements, and the Q List classifications for determining tha classification of spare or replacement parts or materials, 5.6 Resolution of Disputes 5.6.1 Disputes invo'"ing quality, arising from a difference of opinion between Entergy Operations m. departments, are normally resolved via direct interaction between tha inanagers involved, if a satisfactory resolution cannot be reached, the disputes are resolved through higher levels of management. The Director, Quality should be consulted for disputes involving the Waterford 3 Quality 12 Assurance program interpretation and implementation. 5.6.2 Disputes involving quality, arising from a differen" c aion between EOl entities, contractors, or suppliers, are normally resoM <hrough the appropriate manager. If a satisfactory resolution cannot be rear a, the disputes should be elevated to the Vice President, Operations, if necer ay. The Director, Quality 12l shoulo be consulted for disputes involving other EC i entiths. The Vice President, Operations Support and/or the Director, Quality should be consulted 3l for disputes concerning contractors or suppliers. 29 s
Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 5.6.3 Written notification shall be provided to the Vice President, Operations, and tho Safety Review Committee regarding disputes or disagreements ai sing from a difference of opinion between the Plant Operations Review Committee and the General Manager, Plant Operations. The General Manger, Plant Operations has responsibility for resolution of such disputes in accordance with the technical specifications. 5.7 Indoctrination, Training, and Qualification Programs 5.7,1 Indoctrination, training, and qualification programs shall be established for Entergy Operations, Inc. personnel performing quality related activities. These 4 programs shall be designed to ensure that personnel involved are knowledgeable in quality procedures and requirements, and have the necessary proficiency to perform the tasks. The scope, objective, and method of implementing the indoctrination and training program shall be documented in approved procedures. 5.7.2 Entergy Operations, Inc. manage:nent is responsible for assuring that personnel are properly trained to perform ac;ivities in a safe and effective manner. The Director, Training is responsible for providing professional, technical, and educational programs to support the indoctrination and training of Waterford 3 3l employees, contractors, and visitors to assure their safety and proficiency during the performance of their activities at Waterford 3. The Director, Quality reviews 3 l the content of quality related indoctrination and training programs to assure adequacy. 5.7.3 Indoctrination, training, and qualification programs require: 5.7.3.1 Personnel responsible for performing activities that affect quality are instrucksd on the purpose, scope, and implementation of quality related manuals, instructions, and procedures; 5.7.3.2 Personnel performing activities that affect quality are trained and qualified in the principles, techniques, and requirements of the activity being performed; 5.7.3.3 Proficiency and qualification of personnel performing or verifying activities are maintained by retraining, re-examining, and/or recertifying on a periodic basis, as applicable; 5.7.3.4 Proficiency testing is utilized to determine qualifications when education, experience, and training cannot be verified by other means; and 30 w .-a--_________: ._
Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 5.7.3.5 Training and qualification documentation is maintained whici describes the objec'.ives, content, attendance, tests, acceptance critena, and the functions personnel are qualified to perform. 5.7.4 The training program for Waterford 3 personnel is further described in Chapter 13 of the FSAR and in implementing procedures. 5.7.5 Waterford 3 Quality Assurance or the Entergy Operations, Inc. Material Requirements organization conducts audits of other organization units, 18 such as suppliers and contractors engaged in quality related activities at or for" Waterford 3 to verify that personnel are adequately Indoctrinated, trained and qualified. 5.8 Controlled Conditions For Performing Activities 5.8.1 Quality related activities shall be accomplished under controlled conditions by personnel with the necessary skills to attain the required quality. Activities shall be performed using appropriate equipment, under suitable environmental conditions and with the assurance that prerequisites for the given activity have been satisfied. 5.9 Management Review of the Quality Assurance Program 5.9.1 The Vice President, Operations ensures that a management assessment of the Quality Assurance program is conducted periodically (not to exceed 24 months) 12 l ~~ by a qualified independent e ganization. 5.9.2 The information from these management assessments, the trend seport, and summaries of the Quality Assurance program status are used by the Vice President, Operations to evaluate the effectiveness of the Quality Assurance program and to take action, as necessary, to assure that the program complies with applicable regulatory requirements. 31
I Waterford 3 Quality Assurance Program Manual Chapter 2 Quality Assurance Program Revision 18 5.10 Maintenance of the Quality Assurance Program 5.10.1 Revisions to the Quality Assurance Program Manual are issued ae necessary to support effective implementation of the Quality Assurance Program. The NRC shall be notified annually, or 6 months after each refueling outage provided the interval between successive updates does not exceed 24 months, of any changes to the Quality Assurance Program description that do not reduce the commitments previously accepted. The revisions must reflect all changes up to a maximum of 6 months prior to the date of filing. If a change is contemplated i which would reduce the commitments in the approved Quality Assurance Program description, the proposed change shall be submitted to the NRC for
- approval prior to implementing the change.
3 5.10.2 Revisions to the Quality Assurance Program Manual (Special Scope) are issued as necessary to support effective implementation of the Quality Assurance i Program. NRC notification regarding changes to the Quality Assurance Program l Manual (Special Scope) is not required. 5.10.3 Entergy Operations, Inc. requires principal contractors and suppliers to submit their QA Program descriptions to Entergy Operations, Inc. for evaluation and to provide notification of changes. Significant changes to such program descriptions shall be reported, a: applicable, to the NRC in writing. In addition, principal contractors and suppliers are required to provide notification of significant changes to their subcontractor's quality assurance program description which has the effoct of changing the quality assurance program of . the principal contractor or Entergy Operations, Inc. l 6.0 RECORDS None-7.0 ATTACHMENTS 7.1 Quality Assurance Program Documentation 7.2 Regulatory Guidance Documents 7.3 10CFR50, Appendix B Compliance I 7.4 Terms and Definitions I 32
QUALITY ASSURANCE PROGRAM DOCUMENTATION Identification Description Approval and Control
- 1. Quality Assurance Defines the Quality Assurance Prepared by Quality Assurance, Program Manual Program, assigns responsibilities to concurred with by the affected various organizations, and defines organizations and approved by the safety-related activities. Vice President, Operations, Waterford 3. Issued and controlled by Site Business Services. 3l
- 2. Nuclear Management A set of Policies and Procedures Prepared by cognizant personnel, Manual which prescribe activities and issued and controlled by responsibilities. Headquarters, Entergy Operations, Inc. and approved by Entergy Operations, Inc. Management.
- 3. Waterford 3 Management A set of Policies and Procedures Prepared by cognizant personnel,1_2 l Manual which prescribe activities and and approved by Waterford 3 Vice-~
responsibilities at Waterford 3. President, Operations. Issued and controlled by Site Business 10_ Services.
- 4. Waterford 3 Plant A manual consisting of a set of Prepared by cognizant plant staff Operating Manual procedures which prescribe organizational units. Quality related required aspects of plant procedures shall receive a quality management and operation. This related review. Approved by the manual provides the mechanism General Manager, Plant through which the administrative Operations. Issued and controls and quality assurance controlled by Site Business Services.
3 requirements are implemented during the operation of Waterford 3. The POM applies to all personnel ' when they are within the Waterford 3 protected area. Chapter 2 Rev.18 Attachment 7.1 (Page 1 of 4) ( 33 s
i s
- QUAUTY ASSURANCE PROGRAM DOCUMENTATION l Identification Description gproval and Control E Quality Assurance A set of procedures prepared and Prepared by Quality Assurance and Procedures Manual issued to specify and control the coordinated with other organizations activities of the Quality Assurance as applicable. Approved by the !
organization. Director, Quality. Issued and 12l l
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controlled by Site Business l Sennces 10 :
==
- 6. SRe Support Procedures A set of procedures which Prepared by cognizant personnel i prescribe activities and within the Site Support Group. l responsibilities within the Site Quality related procedures shali ;
Support Group. receive a quality related review. Approved by the Director, 12 & 18
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Site Support. Issued and l controlled by Site Business 10 i Services.
- 7. Design Engineering A set of procedures which Prepared by cognizant personnel [
Procedures prescribe activities and within Design Engineering. Quality ; responsibilities within the Design related procedures shall receive a ! Engineering organization. quality related review. Approved i by the Director, Design Engineering ; or Department Manager. Issued and controlled by Site Business 10 ; i Services. I Chapter 2 Rev.18 Attachrnent 7.1 (Page 2 of 4) l b N
, , - - __ _I
QUALITY ASSURANCE PROGRAM DOCUMENTATION Identification Descnption Approval and Control
- 8. Design Engineering A set of corporate level procedures Prepared by cognizant personnel Administrative Manual which prescribe activities and within Design Engineering. Issued responsibilities within the Design and controlled by the Manager, (DEAM)
Engineering organizations. Engineering Support, Central Desgn Engineering. Quality related procedures shall receive a quality related review. Concurred with by the Site Director, Design Engineenng for DEAM subsections applicable to their respective sites; and the Managers, Central Design Engineering. Approved by the Managers, Central Design ' Engineering for DEAM documents within their funchonal area of responsibility.
- 9. Plant Modification and A set of procedures which Prepared by cognizant personnel Construction Procedures presenbe activities and within Plant Modificabon and responsibilities within the Plant Construction. Quality related l
- Modification and Construction procedures shall receive a quaiity organization. related review. Approved by the Director, Plant Modificaton and Construction. Issued and controlled by Site Business Services. _10 l Chapter 2 Rev.18 Attachment 7.1 (Py 3 of 4) 35
QUALITY ASSURANCE PROGRAM DOCUMENTATION identification Description Approval and Control'
- 10. Nuclear Safety and - A set of procedures which Prepared by cognizant Regulatory Affairs presenbe actwities and personnelwithin Nuclear Safety Procedures responsibilities within the Nuclear and Regulatory Affairs. Quality Safety and Regulatory Affairs related procedures shall receive organization. a quality related review. 10 Approved by the Director, Nuclear Safety and Regulatory Affairs. .
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Issued and controlled by Site Business Services. _10
- 11. NuclearTraining A set of procedures which Prepared by cognizant personnel Procedures prescribe activities and within NuclearTraining. Quality responsibilities within the Nuclear related procedures shall receive a Training Organization quality related review. Approved by the Director, Training. Issued 12l controlled by Site Business f
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Sennces . 10 & 12
- 12. Materials, Purchasing A set of procedures, which Prepared by cognizant pers5nrC
& Contracts prescribe activities and within Materials, Purchasing &
Administrative responsibilities within the Materials, Contracts. Quality related - 18 Procedures Purchasing & Contracts procedures shall receive a quality organization. related review. Approved by the Director, Materials, Purchasing & Contracts,. Issued and controlled by Materials, Purchasing & Contracts. Chapter 2 Rev.18 Attachment 7.1 (Page 4 of 4)
'36
REGULATORY GUIDANCE DOCUMENT This document contains a listing of Regulatory Guides and ANSI Standards applicable to the Quality Assurance Program for Waterford 3. Reference FSAR Section 1.8 for a complete listing of regulatory guides and standards applicable to the design and operation of Waterford 3. Document Comment
- 1. Appendix B to 10CFR50 " Quality _1. Criterion Vil, Control of Purchased Assurance Criteria for Nuclear Materials, Equipment, and Services Power Plants and Fuel states that documentary evidence that Reprocessing Plants" material and equipment conform to the procurement requirements shall be available at the nuclear power plant or fuel reprocessing plant site prior to installation or use of such material and equipment.
The Waterfcrd 3 Quality Assurance Program requires that required documentary evidence be available at the site prior to use, but not necessarily prior to installation. This allows installation to proceed under specified conditions while any missing documents are being obtained, but precludes dependence on the item for safety purposes.
- 2. A. Regulatory Guide 1.8, 1. The qualifications of personnelin the Revision 1, September Health Physics, Radwaste, and 1975, " Personnel Selection Chemistry Departments are in and Training"(Endorses accordance with ANSI N18.1-1971 as ANSI N18.1-1971) endorsed by this Rag. Guide and/or as shown in FSAR Chapter 13.
Chapter 2 Rev.18 Attachment 7.2 (Page 1 of 8) 37
l l l Document Comment B. ANSI /ANS 3.1 1978, 2. The qualification of personnel other l " Standards for Selection than those in the Health Physics, and Training of Personnel Radwaste, and Chemistry for Nuclear Power Plants" Departments are in accordance with ANSI /ANS 3.1-1978. Specific commitments are shown in FSAR Chapter 13.
- 3. Personnel performing Independent Technical Review functions meet the qualification requirements of NUREG-0737-1980 instead of Section 4.7.2 5" l of ANSI /ANS 3.1-1978.
- 3. Regulatory Guide 1.30, August 1. Waterford 3 applies the provisions of 1972, " Quality Assurance this Regulatory Guide and its Requirements for the Installation, endorsed standard to Class 1E Inspection and Testing of equipment only.
Instrumentation and Electrical Equipment" (Endorses ANSI 2. Each safety related item of process N45.2.4-1972) instrumentation is identified with a unique number. This number is used in instrument maintenance records so that current calibration status, including data such as the date of the calibration and identity of the person that performed the calibration, can be readily determined. Such information may also be contained on tags or labels that may be attached to installed instrutnentation. Chapter 2 Rev.18 Attachment 7.2 (Page 2 of 8) 38
.- - . - - - . - - . _ . - - . . - - - . - - . . ~ _ . - -
i ! Document Comment a
- 4. Regulatory Guide 1.33, Rev. 2, 1. ANSI N18.7 references certain other February 1978, " Quality standards to which Entergy Assurance Program Operations, Inc. takes exception.
- Requirements (Operational)" Waterford 3 exceptions and (Endorses ANSI N18.7-1976) alternatives are listed in this table.
3 2. Waterford 3 complies with Regulatory l Position C.3 of Regulatory Guide 1.33, except under emergency _ i conditions in which case Entergy
- Operations, Inc. shall submit j proposed changes to Technical
! Specifications or license amendments in accordance with 10CFR50.54 and or 10CFR50.71. T
- 3. ANSI N18.7, Section 3.4.2, Requirements for the on-site operating organization, states that [the activities of the individual or organizational unit responsible for verifying that the administrative controls and Quality Assurance i Program is being effectively implemented) shall be periodically audited by designated personnel.
Wateiford 3 utilizes designated off-site personnel or an outside agency to i perform assessments of the entire
- QA Program including the activities of the on-site audit personnelin lieu of -
periodic audits. Assessment results and other program evaluation , documents such as the Trend l Analysis Report are forwarded to Entergy Operations, Inc. management for evaluation and determination of - corrective action. i Chapter 2 Rev.18 Attachment 7.2 (Page 3 of 8) ' 39
Document Comment
- 4. Regulatory Guide 1.33 4. ANSI N18.7, Section 5.2.7, (Continued) Maintenance and Modification:
Waterford 3 pre plans and performs maintenance of equipment in accordance with written procedures except in emergency or abnormal conditions where immediate actio.i is required to:
- a. Protect the health and safety of the public,
- b. Protect equipment or personnel.
- c. Prevent the deterioration of plant conditions to a potentially unsafe or unstable level
- 5. ANSI N18.7, Section 5.2.7.1, Maintenance Program: Repair of safety related equipment will be accomplished in accordance with approved procedures and/or vendor manuals.
- 6. Waterford 3 will provide procedures for the activities in Appendix A of Regulatory Guide 1.33 as discussed in Section C-1 of the regulatory guide.
However, Waterford 3 does not consider all activities listed to be
" safety related" (o.g., activities in 7.e).
- 7. ANSI N18.7, Section 5.2.15 states,
" Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years."
= Chapter 2 Rev.18 Attachment 7.2 (Page 4 of 8) 40
Document Comment
- 4. Regulatory Guide 1.33 Waterford 3 has programmatic control (Continued) requirements M place that initiate procedure revle.ws upon identification of new or revised source material that has a potential to affect the intent of the procedure.
A biennial audit is performed by the Quality Assurance Department to verify compliance with existing programmatic controls used to maintain procedures current.
- 5. Regulatory Guide 1.37, March No exceptions.
1973," Quality Assurance Requirements for Cleaning Fluid Systems and Associated Components of Water Cooled Nuclear Plants" (Endorses ANSI N45.2.1 1973)
- 6. Regulatory Guide 1.38, Rev. 2, For the storage of new fuel assemblies and May 1977," Quality Assurance neutron sources, Waterford 3 commits to the Requirements for Packaging, storage requirements of Level B of ANSI Shipping and Receiving, Storage N45.2.2-1972 less the flooding prevention and Handling of items for Water requirements and will minimize dust and Cooled Nuclear Power Plants" other particles contacting these items by (Endorses ANSI N45.2.2-1972) placing a fire retardant polyethylene cover over these items or the cell locations in which the items are stored.
ANSI N45.2.2 states that motors !a storage shculd have the insulation resistance checked on a scheduled basis. Waterford 3 conaucts complete insulation tests upon receipt of the motor and again before the g motor is installed in the plant. An extensive motor run-in is also performed before installation to verify operability. Chapter 2 Rev.18 Attachment 7.2 (Page 5 of 8) 41
Document Comment
- 7. Regulatory Guide 1.39, Rev. 2 The zone designations of Section 2.1 of September 1977, " Housekeeping ANSI N45.2.3-1973 and the requirements Requirements for Water Cooled associated with each zone are not consistent Nuclear Power Plants with the requirements for operating plant.
(Endorses ANSI N45.2.3-1973) Instead, procedures or instructions for housekeeping activities which include the applicable requirements outlined in Section 2.1 of ANSI N45.2.3 and which take into account radiation control considerations, security considerations, and personnel and equipment safety considerations are developed on a case basis.
- 8. Regulatory Guide 1.58, Rev.1, Personnel performing nondestructive testing September 1980, " Qualification of meet the qualification requirements of ASNT Nuclear Power Plant inspection, Recommended Practice No. SNT-TC-1 A-Examination and Testing 1980 and its applicable supplements.
Personnel" (Endorses ANSI N45.2.6-1978)
- 9. Regulatory Guide 1.64, Rev. 2, No exceptions.
June 1976," Quality Assurance Requirements for the Design of Nuclear Power Plants" (Endorses ANSI N45.2.11-1974)
- 10. Regulatory Guide 1.70, Rev. 2, No exceptions.
September 1975, " Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants"
- 11. Regulatory Guide 1.74, February No exceptions.
1974," Quality Assurance Terms and Definitions" (Endorses ANSI N45.2.10-1973) Chapter 2 Rev.18 Attachment 7.2 (Page 6 of 8) l 42 l
Document Comment
- 12. Regulatory Guide 1.88, Rev. 2, The interim storage of Quality Assurance October 1976, " Collection, Records will be conducted in accordance Storage and Maintenance of with approved procedures. At a minimum, Nuclear Power Plant Quality Quality Assurance Records stored on an Assurance Records"(Endorses interim basis will be afforded the protection ANSI N45.2.9-1974) of a one hour minimum rated facility or storage cabinet.
- 13. Regulatory Guide 1.94, Rev.1, No exceptions.
April 1976, "%ality Assurance Requireme,n for Installation, inspection, and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants" (Endorses ANSI N45.2.51974)
- 14. Regulatory Guide 1.116, No exceptions.
Rev. 0-R, May 1977, " Quality Assurance Requirements for installation, inspection and Testing of Mechanical Equipment and Systems"(Endorses ANSI N45.2.8-1975)
- 15. Regulatory Guide 1.123, Rev.1, No exceptions.
July 1977, " Quality Assurance Requirements for Control of Prccurement of items and Services for Nuclear Power Plants" (Endorses ANSI N45.2.13 1976) Chapter 2 Rev.18 Attachment 7.2 (Page 7 of 8) 43
Document Comment
- 16. Regulatory Guide 1.144, Rev.1, Waterford 3 takes exception to the following September 1980," Auditing of paragraphs of ANSI N45.2.12:
Quality Assurance Programs for Nuclear Power Plants" (Endorses 1. 2.3 - Training Technical Specialists ANSI N45.2.12-1977) who assist in performing audits in their area of special expertise will not necessarily be trained in audit techniques; however, they will always be accomponied by a trained and qualified auditor.
- 2. 4.4 - Reports - Audit reports will be issued within 30 working days of the post audit meeting. (Except audit reports required by the SRC Audit Program which are required within 30 days).
- 3. 4.3 - Conferences - Pre-audit and post audit conferences shall be held only when deemed necessary by Quality Assurance or when requested by the audited organization
- 17. Regulatory Guide 1.146, August No exceptions.
1980," Qualifications of Quality Assurance Program Audit. Personnel for Nuclear Power Plants" (Endorses ANSI N45.2.23-1978) Chapter 2 Rev.18 Attachment 7.2 (Page 8 of 8) 44
10CFR50, APPENDIX B COMPL!ANCE This document illustrates the relationship between 10CFR50, Appendix B and the Nuclear Safety Quality Assurance Policies. 10CFR50, Appendix B Criterion Nuclear Safety Quality Assurance Policy
- 1. Organization Chapter 1 - defines the organizational structure and delineates the authority and responsibilitiet of individuals and organizations performing quality assurance activities, ll. Quality Assurance Program Chapter 2 defines the scopo of the Quality Assurance Program and establishes that activities affecting safety related structures, systems, and components will be conducted in accordance with approved procedures.
Ill. Design Control Chapter 3 - defines requirements for the control of the design of safety related structures, systems, and components including the design of plant modifications. IV. Procurement Document Control Chapter 4 - defines requirements for the control of procurement of safety related structures, systems, components, materials, and services. V. Instructions, Procedures, and Chapter 5 - defines requirements for the Drawings development and control of instructions, procedures, and drawings. VI, Document Control Chapter 6 - defines requirements for the control of documents for safety related structures, systems, and components and identifies the type of documents to be controlled. Vll. Control of Purchased Material, Chapter 7 - defines requirements for control of Equipment, and Services purchased material, equipment, and services, including control of suppliers and receiving inspection. Chapter 2 Rev.18 Attachment 7.3 (Page 1 of 3) 45
j0_CFR50, Appendix B Criterion Nuclear Safety Quality Assurance Polley Vill. Identification and Control of Chapter 8 - defines requirements for control of Materials, Parts, and Components materials, parts, and components. IX. Control of Special Processes Chapter 9 - defines requirements for control of special processes including welding, heat treating, NDE, and chemical cleaning. X. Inspection Chapter 10 - defines requirements for inspection of materials and activities important to safety including criteria for determining when and how inspections are performed. XI. Test Control Chapter 11 describes the scope of the test control program and establishes requirements for test procedures and instructions. Xil. Control of Measuring and Test Chapter 12 - defines requirements for control Equipment of measuring and test equipment and for inspections, tests, and monitoring of quality related equipment and activities. XIll. Handling, Storage, and Shipping Chapter 13 - defines requirements for handling, storage, and shipping of safety related structures, systems, and components. XIV. Inspection, Test, and Operating Chapter 14 defines requirements for control Status of inspection, test, and operating status of safety related items and equipment. XV. Nonconforming Material, Parts, or Chapter 15 - defines requirements for Components identification, documentation, segregation, review, and disposition of nonconforming materials, parts, and components. XVI. Corrective Action Chapter 16 - defines requirements for establishment of an effective corrective action program with specified basic ;iarrective action elements. XVil. Quality Assurance Records Chapter 17 - defines requirements for a quality assurance records program including identification of types and content of records. Chapter 2 Rev.18 Attachment 7.3 (Page 2 of 3) 46
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! 10CFR50, Appendix B Criterion Nuclear Safety Quality Assurance Policy XVill. Audits Chapter 18 - defines requirements for audits f of safety related activities including audit
- program scope and methods. ;
t i i 1 1 4 ? l i l 1 i 4 i } j Chapter 2 Rev.18 _ Attachment 7.3 (Page 3 of 3) 47-
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TERMS AND DEFINITIONS This document providea a compilation of terms and definitions which are important to establishing the boundaries of the Waterford 3 Quality Assurance Program. They are provided as guidance to achieve standerdization within Waterford 3 documents and as an cid in the impku.entation of the Quality Assurance Program. The terms and definitions were selected irem those contained with'n the ANSI standards listed in Attachment 7.2 on the basis of most hequant usage.
- Those responsible fcr the Oyfiej As!rmice Program implementatica are reminded that thove terms and definitions providud! /y tho standards but not lis'ed herein should be regarded as valid. Therefore, the user is referred to the standards listed in Attachment 7.2 for additional guidance.
it is the responsibility of the user of the terms and definitions contained herein to ascertain that they are appropriate for the intended application. Where a term is used to convey a different intent then that defined herein, clarification should be provided at the point of cpplication. The subsenpt following each definition provides the source of the definition. An index of the subscripts is contained at the end of this document. Chapter 2 Rev.18 Attachment 7.4 (Page 1 of 19) 48
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ABNORMAL CONDITION Hardware deviations (i.e. conditions not meeting the threshold cri'.oria of adverse conditions or nonconforming condition) observed in the course of inspections, testing, maintenance, operation, etc. ACCEPTANCE CRITERIA A limit or limits placed on the variation permitted in the characteristics of an item expressed in definitive engineering terms such as dimensional tolerances, chemical composition limits, density and size of defects, temperature ranges, time limits, operating parameters, and other similar characteristics. e ACCEPT-AS-IS Same as Use As Is q ACCURACY The degree of conformity of a measure to a standard or to a true value. (See Precision). q ADMINISTRATIVE CONTROLS Rules, orders, instructions, procedures, policies, practice:: cnd designations of authority and responsibility. c ADVERSE CONDITION An event, defect, characteristic, state or activity which prohibits or detracts from the safe, efficient operation of Waterford 3. Adverse conditions include 18 Nonconformances, Conditions Adverse to Quality and Plant Reliability Concerns. APPROVAL An act of endorsing or adding positive authorization or both. l APPURTENANCE A part that is attached to a component which has been completed.i AS BUILT-DATA Documented data that describes the condition actually achieved in a product. l ASSEMBLY A combination of subassemblies or components, or both fitted together to form a unit. l Al JIT A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence, that applicable elements of the quality assurance program has been developed, documented, and effectively implemented in accordance with specified requirements. An audit should not be confused with surveillance or inspection for the sole purpose of process control or product acceptance. I, n, o Chapter 2 Rev.18 Attachment 7.4 (Page 2 of 19) 49 {
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BASIC COMPONENT As it applies to Waterford 3, it is a component, structure, system or part thereof that is directly procured by Entergy Operations, inc1LP&L, is subject to 10CFR21 and in which a defect or failure to comply with 10CFR21, an NRC order, or license conditions could create a substantial safety hazard, r, q BID EVALUATION An evaluation of proposals or bids received in response to an inquiry j (request for proposal or bid) to determine the vendor or contractor to whom the purchase order or contract will be awarded. q CAllBRATION Comparison of an item of Measuring and Test Equipment and certain installed instrumentation and control devices with a reference standard or with an item of M&TE of required tolerance to detect and quantify inaccuracies and to report or eliminate those inaccuracies, q, t J CAUSE A reason or contributing reason for the occurrence of an adverse condition. Causes are categorized as either apparent cause or root cause. Apparent Cause - the obvious reason for the occurrence of an adverse condition, j The apparent cause is identified without performing a formal root cause analysis. Root Cause - the most basic factors which, if eliminated, would prevent recurrence of the adverse condition. Root causes are generally identified 18 4 ~ through the conduct of a formal root cause analysis performed in accordance with Entergy Root Cause Analysis Desk Guide.. CERTIFICATE OF COMPLIANCE A written statement, signed by a qualified party, ! ctiesting that the items or services are in accordance with specified requirements and cccompanied by additional information to substantiate the statement. l . CERTIFICATE OF CONFORMANCE A written statement, signed by a qualified party, certifying that items or services comply with specific requirements. l CERTIFICATION The action of determining, verifying and attesting, in writing, to the qualifications of personnel or material. l CERTIFIED MATERIAL TEST REPORT A written and signed document, approved by a
- qualified party, that contains sufficient data and infumation to verify the actual properties of items and the actual results of all required tests. I Chapter 2 Rev.18 Attachment 7.4 (Page 3 of 19) 50 .
CHARACTERISTIC Any property or attribute of an item, process, or service that is distinct, describable, and measurable, as conforming or nonconforming to specified quality assurance requirements. Quality assurance chara:teristics are generally identified in specifications and drawings, which describe the item, process or service. l CLEANNESS A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil cr other contaminating impurities. l COMMERCIAL GRADE Those items which (1) are not subject to design or specification requirements that are unique to facilities or activities licensed by the NRC and (2) are used in applications other than facilities or activities licensed by the NRC and (3) can be ordered from the manufacturer / supplier on the basis of information set forth in the manufactuter's published product information or nationallv recognized non-nuclear codes or standards. (NOTE: Although an item is exempted from 10CFR21 being imposed on the manufacturer, supplier or vendor by the definition of " Commercial Grade", the item may still have other QA requirements which need to be imposed in the procurement documents). r, q COMPONENT A piece of equipment such as a vessel, piping, pump, valve or core support structure, which will be combined with other components to form an assembly; or: items from which electrical equipment is assembled, for example, resistors, capacitors, wires, connectors, transistors, switches, springs, etc.l CONDITION ADVERSE TO QUALITY Failure of Safety Related Structure, System or Component (SSC) to perform their intended safety functiun, and safety related process 18 deficiencies and violations which could result in a degradation or challer3a to Nuclear - Safety. CONSTRUCTION PHASE The period of time beginning with the start of construction activity and ending as each plant area is turned over to the plant operator.b,1 CONTRACT A document such as a contract order, change order, agreement, addendum, work order or task authorization which defines the requirements and conditions for furnishing contract services. q CONTRACTOR Any organization under contract for fumishing items or services. It includes the terms Vendor, Supplier, Subcontractor, Fabricator, and subtier levels of these where appropriate. d, i Chapter 2 Rev.18 Attachment 7.4 (Page 4 of 19) 51
CORRECTIVE ACTION Measures taken upon the identification of an adverse condition 18 to correct the deficiency DEDICATION The act of verifying that a Commercial Grade item is acceptable for a i safety related application. Dedication occurs after receipt when that item is designated '
'M use as a basic component. r, q l'
DEFECTIVE MATERIAL A material or compone.it 2h has one or more characteristics that do not comply with specified requirements. l L DEFICIENCY An observed condition that is or appears to be adverse to quality or beyond a defined or approved q alitative or quantitative ecceptance criterion, q DESIGN Technical and management processes which commence with identification of
- design input and which lead to and include the issu ance of design output documents h -
DESIGN CRITERIA Documents which establish ovecell plant design requirements including NSSS and BOP interfaces; they establish the nyerall system parameters and design requirements for major portions of the BOP as necessary for the interrelationship of systems, components and machines. h DESIGN DOCUMENTS Engineering specifications, drawings, calculations and/or instructions h DESIGN INPUT Those criteria, parameters, bases or other design requirements upon which detailed final design is based, h DESIGN INTERFACE The relationship between design organizations internal or external to a company. q DESIGN OUTPUT. Documents such as drawings, specifications, and other documents definlag technical requirements of structures, systems, and components as delineated in Section 4 of ANSI N45.2.11 h t Chapter 2 Rev.18 Attachment 7.4 (Page 5 of 19)
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l DESIGN REVIEW An analysis of design with respect to technical adequacy, interface control, inspectability, maintainability, and conformance to applicable codes, standards, regulations and design criteria. h DESIGN SPECIFICATION An engineering document describing function, design requirements, environmental conditiuns, code requirements, and boundary definition, and containing sufficient detail to provide a complete basis for construction in accordance with applicable codes and standards. q DESIGN VERIFICATION The process of checking, conforming, or substantiating the design by individuals or groups other than those who performed the original design to provide assurance that specified requirements have been met. Methods include design review, alternate calculations, and testing. h, q DISCREPANCY A condition which is at variance with requirements, q DOCUMENTATION Any written or pictorialinformation describing, defining, specifying, reporting, or certifying activities, requirements, procedures, or results, d, e, i ELECTRICAL CLASS 1E See Quality Related. EQUIPMENT QUAllFICATION (EO) The process or activities necessary to demonstrate by test, analysis or other suitable means, that specific devices are capable of performing their function in the specified environment, q EXAMINATION An element of inspection consisting of investigation of materials, supplies, parts, components, appurtenances, systems, processes, or structures to de' ermine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gaging, and meuurement. g, i, l EXEMPT ltems or services that have no effect on the operating plant, such as, office furniture, office supplies, and non permanent plant computers. EXPERIMENTS Performance of those plant operations carried out under controlled conditions in order to establish characteristics or values not previously known c Chapter 2 Rev.18 Attachment 7.4 (Page 6 of 19) 53
EXTERNAL AUDITS of those portions of an organization's quality assurance program not retained under its direct control and not within its organizational structure, n FUNCTIONAL TESTS performed, as required, after modification, meintenance, or significant changes in operating procedures to confirm that the maintenance, modification, or changes produce expected results. q GUIDELINES Particular provisions which are considered good practice but which are not mandatory in programs intended to comply with this standard. HOLDPOINT A point in the manufacturing / fabrication / erection sequence or in the maintenance process beyond which work may not proceed until the authorized inspector / purchaser / owner has observed or examined the work and has given consent to
. proceed, q INDEPENDENT REVIEW A documented review completed by personnel not having direct responsibility for the work function under review re;;ardless of whether they operate as a part of an organizational ur.it or as individual staff members (see Review). c, q INSPECTION A phase of quality control which by means of examination, observation, or measurement determines the conformance of matet.al, supplies, ;, t, components, eppurtenances, systems, processes, or structures to predetermined quality assurance requirements c, g, I, I INSPECTOR (OWNER OR INSTALLER) A qualified inspector employed by the Owner or Installer whose duties include the verification of quality related activities or installations or both. l lNSPECTOR (STATE OR CODE) A qualified inspector employed by a legally constituted egency of a Municipality or state of the United States, or Canadian Province, or regularly employed by an Authorized Inspection Agency and having authorized jurisdiction at the site of manufacture or installation. l -
INTERNAL AUDITS of those portions of an organization's quality assurance program retained under its direct control and within its organizational structure, n ITEM Any level of unit assembly, including structure, system, subsystem, subassembly, component, part, or material. d, e, I v. Chapter 2 Rev.18 Attachment 7.4 (Page 7 of 19) 54
l LEAD AUDITOR An individual qualified to organize and direct an audit, report audit findings, and evaluate corrective action, n, o MANUFACTURER One who constructs any class of component, part, or appurtenance : to meet prescribed design requirements. l MASTER EQUIPMENT LIST (MEL) The MEL identifies each component by a component identification number and provides a compilation of pertinent data. The MEL is a i comprehensive on line computerived listing of the components in the Waterford 3 SES. The MEL is a source of component data to be used by the station departments such as maintenance, operations, engineering and quality control and other Entergy Operations, Inc. organizations during routine operation and maintenance of Waterford 3. q MATERIAL A substance or combination of substances forming components, parts, pieces, and equipment items. (Intended to include such as machinery, castings, liquids, formed steel shapes, aggregates, and cement.). l l MEASURING AND TEST EQUIPMENT (M&TE) Devices or systems used to calibrate, measure, gage, test, inspect, or controlin order to acquire research, development, test or operational data, or to determine complianco with design, specifications, or other technical requirements. M&TE does not include permanently installed operating equipment, nor test equipment useJ for preliminny checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation. t MODIFICATION A planned change in plant design or operation and accomplished in accordance with the requirements and limitations of applicable codes, standards, specifications, licenses, and predetermined safety restrictions, l i NONCONFORMANCE An adverse condition affecting a safety related, quality related or trip I sensitive system caused by a deficiency in characteristic, documentation,- or procedure 18 l which renders the quality of an item unacceptable or indeterminato. 1 OBJECTIVE EVIDENCE Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, j measurements, or tests which can be verified. l i L Chapter 2 Rev.18 Attachment 7.4 (Page 8 of 19) 55
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ON SITE PERSONNEL Those personnel providing technical and operational support who are located within the Waterford 3 owner-controlled area. q OPERABLE / OPERABILITY A system, subsystem, train, component or device is operable or has operability when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical powei, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also caoable of performing their related support function (s). s OPERAT!ONAL PHASE That period of time during which the principal activity is associated with normal operation o(the plant. This phase of plant life is considered to begin formally with commencement of fuelloading and ends with plant decommissioning c OWNER ORGANIZATION The organization, including the on-site operating organization, which has overalllegal, financial and technical responsibility for the operation of one or moro nuclear power plants. a, c, i PEER / MAINTENANCE INSPECTOR An ANSI .N45.2.6 certified individual normally assigned to the line organization, but who reports to the QA Inspections unit during the inspection activity. This individualis not directly responsible for, or supervisor of, the activity being inspected, q PRECISION The relative consistency or repeatability of each measurement in a set of - measurements made under the same conditions. (See Accuracy). q PROCEDURE A document that specifies or describes how an activity is to be performed, it may include methods to be employed, equipment or materials to be used and sequence of operations. l
' Chapter 2 Rev.18 Attachment 7.4 (Page 9 of 19) 56
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PROCUREMENT CLASSIFICATIONS Procurement Classification Level 1 (L1) is assigned to those items that are procured as s fety-related under the responsibility of the suppFers approved 10CFR 50 Appendix B type quality assurance program with 10 CFR Part 21 reportability imposed on the supplier. Procurement Classification Level 2 (L2) is assigned to those items that are safety-related or items meeting the definition of commercial grade, procured under the responsibility of the site quality assurance program fc vhich Entergy Operations, Inc. assumes the r:sponsibility defined in 10 CFR Part ; . Procurement Classification Level 3 (L3) is assigned to those items which are not safety-related but fall into Augmented Quality /special scope as described in the site design basis licensing documents. Procurement classification Level 4 (L4) is assigned to those permanent piant items which cre defined as non safety-related (Balance of Plant) for which no quality assurance rcquirements are imposed. _18 Procurement classification Level Pending (LP)is assigned to those items pending review by Materials Purchasing & Contracts for assigning the correct procurement classification. Procurement classification Level Exempt (LE) is assigned to non permanent plant items (exempt). Below is a matrix relating former and current procurement classifications (procurement quality levels). FORMER CURRENT QC1/Q1 (SAFETY-RELATED) L1 (SAFETY-RELATED) QC2/Q2 (SPECIAL SCOPE) L2 (SAFETY-RELATED/ COMMERCIAL GRADE / DEDICATED) QC3/Q3 (SAFETY-RELATED/ COMMERCIAL L3 (AUGMENTED QUALITY) GRADE / DEDICATED) QC4/04 (BALANCE OF PLANT) L4 (BALANCE OF PLANT) QCE/QE (EXEMPT) LE (EXEMPT) NONE LP (PENDING) PROCUREMENT DOCUMENT A document including purchase requisitions, specifications, drawings, instructions, contracts, letter of intent, work orders, purchase orders, or proposals and their acceptances, when applicable, which authorize the seller to perform services or supply equipment, materials, or facilities on behalf of the purchaser, i, m Chapter 2 Rev.18 Attachment 7.4 (Page 10 of 19) 57
PURCHASE ORDER A document issued by a purchaser to a supplier which defines the requirements and conditions for furnishing material, components, or equipment. q PURCHASER The organization or organizations responsible for issuance and cdministration of a contract, subcontract, or purchase order. i, m Q-LIST A listing, by system, of all safety-related components in the Waterford 3 SES. For cach safety related component the Q-List indicates the safety clascification and seismic category along with the primary source documents which were used to determine if the component is safety-related. q Q-RELATED LIST A listing of items or activities considered to have a limited impact on publi: health and safety and receive an appropriate application of 10CFR50 Appendix B Criteria. These areas include; Special Scope; Non-Nuclear Safety, Seismic Category I and items designated by FSAR Table 3.2-1, Note 17. q QUALIFICATION (PERSONNEL) The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function. i QUALIFICATION TESTS performed to qualify the basic material source or manufacturer. These tests are mandatory unless current documentary test data are available to establish complete confidence in conformance to requirements. k QUALIFIED PROCEDURE A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose, i, k QUALIFIED SUPPLIERS LIST (OSL) A list of suppliers approved from a quality assurance standpoint, to furnish specified quality related items or services in accordance with procurement documents. Qualified suppliers are approved by Supplier QA, who maintains the Qualified Supplier's List. q QUALITY ASSURANCE All those planned and systematic actions necessary to provide assurance that a structure, system or component will perform satisfactorily in service. It applies to all activities associated with performing a job correctly as well as verifying and documenting the satisfactory completion of the work. i QUALITY ASSURANCE RECORDS Those records which furnish documentary evidence of the quality of items and of activities affecting the quality of quality related structures, systems or components. m, q QUALITY CONTROL Those quality assurance actions which provide a means to control and measure the characteristics of an item, process, or facility to established requirements. l Chapter 2 Rev.18 Attachment 7.4 (Page 11 of 19) 58
QUA!.lTY RELATED Waterford 3 uses the term Quelity Related to describe the entire scope of structures, systems, components and activities which require some degree of 10CFR50 Appendix B, Quality Assurance criteria application. Quality related is divided into five major categories: (ref: fig.1) o Safety Related o Special Scope o Non-Nuclear Safety o Non-Safety Seismic o Other items identified by FSAR table 3.2-1, note 17 or Wateiford 3 procedures. 2
' QUALITY -
RELATED
+Q-LIST N 4 Q-RELATEo LIST UI NON-SAFETY QA M SEISMIC ! NON-NUCLEAR NON-NUCLEAR BALANCE R A ED (SPECIAL SCOPE) (NSS) g SAFETY l SAFETY OF (SEsSMIC 1) y 11 over i WITH WITHOUT PLANT l o Fire Protection CHtoria -l TABLE 3.21 I TABLE 3.21 Quality Assurance o P6pe Supports NOTE 17 NOTE 17 o Safety Class 1 l o HVAC Supports )
o Sakty Clase 2 o RadiologicalEfRuent , o Safety Cises 3 and Environmental o Electrical j i g o IEEE Class 1E M0"80'i"9 I"PP0" BALANCE OF l o Emerjency o IAC Supports i C o Setemic Category 1 P parednees y o Safety Relate ( O "'D
! TABLE 3,21 !
(Le. Active / auto viv. NOTE 17 ! operators, snubbers, o Radioactive Weste l E Management QualMy S/R consumablee I Program d etc.) O SpecialNuclear j o ASME Clase *MC. g Material Control and Accountability j l o ComputerSoftware ! o ALARAProgram i O Radweste Protection i I o ATWS o Station Blackout i l I Fult 10CFR50 Applicable 10CFR$0 Reg Guide 1.26 No Quality I Appendix B Appendix B i Quality Group D Program I Program Program i' requirements only Requirements 8w at Note: The applicable crtteria eystem ecope and other gh requirements are defined in quality policies. ! w procedures, procurement documents, wort packages and other documentation, I
! i gg L1 and apply 1CFR21 L3 or L4 L3 ,
I L2 C relal Grade) L41s permitted for selected special scope Specla receipt i Ew and dedicate activttles if permitted by the applicable QAPM inspection ~ (Special Scope) procedures. ! Ee ' Chapter 2 Rev.18 Attachment 7.4 (Page 12 of 19) 59 t
Safety Related Based on the definition of basic component in 10CFR21, Safety related structures, systems, and components are those necessary to assure:
- 1. The integrity of the reactor coolant pressure boundary;
- 2. The capability to shut down the reactor and maintain it in a safe shutdown condition; or
- 3. The capability to prevent or mitigate the consequences of accidents which could result in potential off site exposures comparable to the guidelines of 10CFR100.
In all cases, safety related includes design, inspection, testing or consulting services important to safety that are associated with the component hardware, whether these services are performed by the component supplier or by others. Safety related is further divided into five categories: o Safety Class 1 o Safety Class 2 o Safety Class 3 o IEEE 1E o Seismic Category i Specific definitions Safety Class 1,2,3 and IEEE 1E may be obtained by referencing Regulatory Guide 1.26; ANSI N18.2 - 1973; ANSI N18.2a - 1975; and IEEE-308 - 1971. Supports that have a nuclear safety function shall be the same safety class as the components that they support. Seismic Category I includes those items that are designed to withstand the effects of a safe shutdown earthquake and remain functional. By definition, all of the safety related categories are designed to include the Seismic Category I requirements. Reference Regulatory Guide 1.29 - 1978. Seismic Category I design requirements extend to the first seismic restraint beyond the defined boundaries. Those portions of structures, systems, or components that form interfaces between Seismic Category I and non-Seismic Category I features are designed to Seismic Category I requirements. See Regulatory Guide 1.29 - 1978, Regulatory Position C3. Chapter 2 Rev.18 Attachment 7.4 (Page 13 of 19) 60
The safety related items listed above make up the Waterford 3 Q-List. These items and related activities require full 10CFR50 Appendix B implementation. Fullimplementation should not be construed to mean that each criterion necessarily applies, only that exceptions will not be given or taken when the criterion is applicable. For instance, a supplier that provides testing services only, cannot be expected to have a design program in place. However, that supplier will be required to implement the remaining applicable criteria in their QA Program. Special Scope - The Special Scope areas are listed in Chapter 2 of the Quality Assurance Program Manual and are addressed in the Quality Assurance Program Manual (Special Scope). Program implementation and applicable 10CFR50, Appendix B criteria are defined in EOMM policies and procedures. Reference Figure 1 to this document for a sample list of areas included as Specia! Scope. Non-Nuclear Safety (NNS)- applies to portions of the nuclear power plant not covered L . Safety Classes 1,2, or 3 that can influence safe normal operation or that may contain radioactive fluids. Design of non-nuclear safety components shall be to applicable industry codes and standards. This applies primarily to components of secondary systems and waste disposal systems not otherwise covered. Also included are safety system components whose failures would not degrade system performance or cause a release to the environment of gaseous activity normally required to be held for decay (e.g., small components). Non-Safety Seismic (NSS)- includes those items whose continued function is not required but whose failure could reduce the function of any safety related equipment to an unacceptable level or could result in an incapacitating injury to occupants of the control room and should be designed and constructed so that the safe shutdown earthquake would not cause such failure. See Regulatory Guide 1,29 - 1978, Regulatory Position C2. Other items (FSAR Table 3.2-1, Note 17)- Other structures, systems, and components identified on FSAR Table 3.2-1 and accompanied by note 17 receive applicable 10CFR50, Appendix B Quality Assurance. These areas have been evaluated to have some safety significance although they do not fallinto any of the other safety classifications. Applicable program requirements are included in policies, procedures, procurement documents and other documentation as required. Chapter 2 Rev.18 Attachment 7.4 (Page 14 of 19) 61
The items included in the above section (Special Scope, Non-Nuclear Safety and Other items with FSAR Note 17) are identified on the Waterford 3 Q-Related List. Implementation of a 10CFR50, Appendix B QA Program is based on a graded approach. The applicable criteria is defined in either the Special Scope procedures, procurement documents, work packages, or applicable procedures. The criteria selection and program scope are identified by Engineering & Construction in concert with Quality Assurance and . the responsible management. SAFEGUARDS INFORMATION (SI) security-related documents not classified as National Security information or Restricted Data, but protected from disclosure to the - , public an unauthorized persons. With respect to Waterford 3 SES, Si is any document which contains detailed information pertaining to:
- 1. Security measures for the physical protection of special nuclear materials; or
- 2. Security measures for the physical protection and location of certain plant equipment vital to the safety of production facilities.
SEISMIC QUALIFICATION which demonstrates an equipment's ability to perform its required function during and after the time that it is subjected to the forces resulting from a seismic disturbance (design basis earthquake). SHALL, SHOULD,- AND MAY Reference Nuclear Management Manual, Vol.1, Corporate Directive C2.101. The word "shall"is used to denote a requirement considered enforceable by the appropriate regulatory body; the word "should"is used to denote a recommended action, b Jt not an enforceable requirement. Each employee is to carry out any "should" statement Jnless circumstances prevent or necessitate a deviation; and the word "may"is used to denote an option, neither a recommendation nor a requirement. q, c SIGNIFICANT CONDITION REPORT A classification of Condition Reports determined
. by the Condition Review Group (CRG) that meets one or more of the below criteria:
- a. A reportable event per 10CFR50.72 or 10CFR50.73 which requires written follow-up report, or 10CFR Part 21 reporting criteria (routine reports to the NRC are excluded).
_18
- b. A problem recognized as having a greater than acceptable recurrence rate as detemiined by the CRG.
o Any event or nonconformance that meets the definition of repetitive event is significant. Chapter 2 Rev.18 Attachment 7.4 (Page 15 of 19) 62
)
- c. An unplanned event or failure of a SSC that led or could have led to a reactor trip or plant transient.
- d. Near miss Industrial safety Incident or Serious Accident.
3
- e. A major breakdown in processes that implement QA Program Requirements as determined by CRG.
- f. Events or conditions designated as significant or considered important by management for reasons other than those which fall into the above categories.
SOURCE ACCEPTANCE of a product of Entergy Operations, Inc. or its designated egent at the supplier's plant, prior to shipment. 3 SOURCE SURVEILLANCE A review, observation or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture. l SPECIAL PROCESSES Those processes that require interim in-process controls in cddition to finalinspection to assure quality c SPECIAL TEST Test that is developed with the intent of being utilized only one time and is normally contained within the applicable work package. q SPECIFICATION A concise statement of requirements to be satisfied by a product, a material or process indicating, whenever appropriate, the procedure by means of which it may be determined whether the requirements given are satisfied. l SUBSYSTEM A group of assemblies or components or both combined to perform a single function. l SUPPLIER Any individual or organization who furnishes items or services in response to a procurement document. It includes the terms Vendor, Seller, Contractor, Subcontractor, Fabr:cator, Consultant, and subtier levels. m SURVEILLANCE The act of monitoring or observing to verify whether an item or activity conforms to specified requirements. q SURVEILLANCE TESTING Periodic testing to verify that safety-related structures, systems, and components continue to function or are in a state of readiness to perform their functions. c Chapter 2 Rev.18 Attachment 7.4 (Page 16 of 19) 63
SYSTEM An integral part of a nuclear power plant comprised of components which may be operated or used as a separate entity to perform a specific function. Also, a group of subsystems united by some interaction or interdependence, performing many duties but functioning as a single unit. c, i SYSTEM PERFORMANCE TEST A test performed on a completed system including clectric, instrumentation, controls, fluid, and mechanical subsystems under normal or simulated normal process conditions such as temperature, flow, level, and pressure, b, i TESTING The determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental, or operating conditions. Performance of those steps necessary to determine that systems or components function in accordance with predetermined specifications. c, g, i, I (OLERANCE The allowable deviation from a specified or true value. q TRANSIT CARRIER (CLOSED) Trucks, trailers, railroad cars, barges, aircraft, or ships which do provide protection of items from the environment by nature of their closed design. e, l TRANSIT CARRIER (OPEN) Trucks, trailers, railroad cards, barges, aircraft, or ships which do not provide protection of items from the environment, e, i UNREVIEWED ENVIRONMENTAL QUESTION A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns: (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) above. q UNREVIEWED SAFETY QUESTION A proposed change, test, or experiment shall be deemed to involve an unreviewed safety question: (1)if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created or (3) if the margin of safety as defined in the basis for any technical specification is reduced q, r Chapter 2 Rev.18 Attachment 7.4 (Page 17 of 19) 64
USE-AS-IS A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit, and safety. (Same as Accept-as-is). I VERIFICATION An act of confirming, substantiating, and assuring that an activity or condition has been implemented in conformance with the specified requirements. i, l
. WAIVER An approved exception to established controls, q Chapter 2 Rev.18 Attachment 7.4 (Page 18 of 19) 65 i
r __.___m._.
l SUBSCRIPT INDEX SUBSCRIPT SOURCE OF DEFINITION a ANSI N18.1-1971/ANS3.1-1978 - b ANSI N45.2.4-1972/IEEE-336 - 1971 c ANSI N18.7-1976/ANS3.2. d ANSI N45.2.1-1973 e ANSI N45.2.2-1972 f ANSI N45.2.3-1973 g ANSI /ASME N45.2.6-1978 h ANSI N45.2.11-1974 1 ANSI N45.2.10-1973 J ANSI N45.2.9-1974 k ANSI N45.2.5-1974 i ANSI N45.2.8-1975 m ANSI N45.2.13-1976 n ANSI /ASME N45.2.12-1977 o ANSI /ASME N45.2.23-1978 p IEEE 308 - 1971/323 - 1983 q Entergy Operations, Inc. r Title 10 Code of Federal Regulations s Technical Specifications t IEEE 498 - 1980 Chapter 2 Rev.18 Attachment 7.4 (Page 19 of 19) 66
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18 1.0 PURPOSE 1.1 The purpose of the design control program is to assure that the activities associated with the design of plant safety related systems, components, structures, and equipment and modifications thereto, are executed in a planned, controlled, and orderly manner.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.64, Revision 2 (which endorses ANSI N45.2.11-1974 " Quality Assurance Requirements for the Design of Nuclear Power Plants") 2.2 10CFR50.59 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4 4.0 RESPONSIBILITIES 4.1 GeneraliVanager, Plant Operations The General Manager, Plant Operations is responsible for ensuring that the physical configuration of the plant remains in conformance with the approved design and for assuring that operating procedures reflect current design changes or modifications. The General Manager, Plant Operations is also responsible for approving design changes prior to implementation. 4.2 Director, Design Engineering The Director, Design Engineering is responsible for design activities, including the review of safety related changes in design to ensure the inclusion of quality assurance requirements, and for approval of final design documents and design changes at Waterford 3. 67 _ _---_-_ _a
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18 4.3 Plant Operations Review Committee The PORC is responsible for review and recommendations concerning selected design changes and their affect on safety. Specific PORC responsibilities are delineated in this manual. 4.4 - Director, Quality 4 The Director, Quality is responsible for ensuring that quality reviews of safety related changes in design are conducted. 68
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18
- 5,0 PROCEDURE 5.1 Design Process 5.1.1 The design control program involves the preparation, review and approval of design documents, including the translation of applicable regulatory requirements and design bases into design, procurement, and procedural documents. The design control program assures and controls such activities as field design engineering; physics, seismic, stress, thermal, hydraulic, radiation, and FSAR accident analyses; associated computer programs; compatibility of materials; accessibility for in-service inspection; maintenance and repair; quality standards; and safety significance. When a new design or design change is prepared, appropriate quality standards dall be specified in the design documents.
5.1.2 Procedural control shall be established for design documents that reflect commitments of the FSAR. Design documents subject to procedural:ontrol include specifications, calculations, computer programs, the FSAR when used as a design document, drawings including flow diagrams, piping and instrument drawings, control logic diagrams, electrical single line diagrams, structural drawings for major facilities, site arrangements, and equipment locations. 5.1.3 Design activities shall be prescribed and documented on a timet/ basis and to the level of detail necessary to permit the design process to be carried out in a correct and efficient manner, and to permit verification that the design meets requirements. 5.1.4 Procedures shall be provided for performing a documented check to verify the dimensional accuracy and completeness of design drawings and specifications. 5.1.5 Applicable design inputs and their sources shall be identified and their selection reviewed and approved. Design inputs shallinclude, but are not limited to, those listed in Reference 2.1. Changes from specified design inputs, including the reasons for the changes, shall be identified, approved, documented, and controlled. 69 l
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Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18 5.2 Interface Control 5.2.1 Internal and external design interface controls, procedures, and lines of communication shall be established and described in procedures for the review, approval, release, distribution, and revision of documents involving design interfaces to assure structures, systems, and components are compatible geometrically, functionally, and with processes and environment. 5.3 Design Analysis 5.3.1 Design analyses shall be planned, controlled, correct, legibly documented, and in a form suitable for reproduction, filing, and retrieval. Analyses shall be sufficiently detailed as to purpose, method, assumptions, design input, references, and units such that a person technically qualified in the subject can review and verify the adequacy of the results without recourse to the originator Calculations shall be identifiable by subject, originator, reviewer, and date, or by other data such that the calculations are retrievable. 5.3.2 Procedures shall be established to assure that verified computer codes are certified for use and that their use is specified. 5.4 Design Verification 5.4.1 Design verication processes such as design review, alternate calculations, and qualification testing shall be accomplished in accordance with approved procedures. 5.4.2 If design verification is by other than qualification testing, it shall normally be completed prior to drawing release. In cases where this cannot be done and design verification is deferred, the justification for such action shall be documented and the unverified portion of the design appropriately identified and controlled. Design verification shall be complete prior to relying upon the structure, system, or component to perform its safety related function. 5.4.3 Design reviews shall address the following items, where applicable, to assure that: 5.4.3.1 The design inputs were correctly selected; 5.4.3.2 The assumptions necessary to perform the design activity are adequately described and are reasonable; 70
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control-Revision 18 5.4.3.3 Applicable codes, standards, and specifications were utilized; 5.4.3.4 An appropriate design method was used; 5.4.3.5 The design inputs were correctly incorporated into the design; 5.4.3.6 The design output reasonably compares to design inputs; 5.4.3.7 Design characteristics can be controlled, inspected, and tested to ensure no adverse effect on safety; 5.4.3.8 Inspection and test acceptance criteria are identified; 5.4.3.9 Appropriate fire protection and security requirements have been met; and 5.4.3.10 The necessary design input and verification requirements for interfacing organizations were specified in the design documents or in supporting procedures or instructions. 5.4.4 Specialized reviews shall be used when uniqueness or special design considerations warrant. 5.4.5 When alternate calculations are used to verify the correctness of the original calculations or analyses, the appropriateness of assumptions, input data used, and the computer program or other calculation method used shall also be reviewed. 5.4.6 Procedures shall provide criteria that specify when verification should be by test. Test configurations and acceptance criteria shall be clearly defined and documented prior to starting the test. Prototype, component, or feature testing shall be performed as early as possible and shall be complete prior to the point when installation would be irreversible or prior to relying upon the structure, system, or component to perform its safety related function. 5.4.7 - When a test program is used to confirm design adequacy, a prototype unit shall be qualified under adverse design conditions. Operating modes and environmental conditions shall be considerea in determining the most adverse conditions. 71
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18 5.4.8 Where the test is intended to verify only specific design features, the other features of the design shall be verified by other means. Test results shall be documented and evaluated by the responsible d%gn organization to assure that tes': requirements have been met. 5.4.9 Regardless of title, individuals performing design verification shall not have: 5.4.9.1 Established the design inputs for particular design aspects being verified; 5.4.9.2 Specified a singular design approach; 5.4.9.3 Ruled out certain design considerations; or 5.4.9.4 Immediate supervisory responsibility for the individual performing the design except as provided for below. 5.4.10 The designer's immediate supervisor mey perform the verification if the following conditions apply: 5.4.10.1 The supervisor is the only technically qualified individual; and 5.4.10.2 The need is individually documented and approved in advance by the responsible management. 5.4.11 Quality assurance audits shall take into account the frequency and effectiveness of using supervisors as verifiers to guard against abuse. 5.F Design Changes 5.5.1 Safety related design and specification changes, including field changes, shall be subject to the same type of design controls and approvals as the original. Qualified organizations other than the original designer may be used to modify or develop designs. Individuals preparing design changes shall review, as appropriate, the original design or latest design changes, and/or secure original design information. The original design and/or design change analysis as appropriate, shall be verified to ensure the analyses are still valid. 72
Waterford 3 Quality Assurance Program Manual Chapter 3 ! Design Control Revision 18 5.5.2 Materials, parts, commercial grade items, and equipment which are catalogued (off the shelf), or which have been previously approved for a different application shall be reviewed for suitability. Such reviews shall be documented. 1 The organizations responsible for design reviews and other design activities shall be identified by written procedures which delineate the authority and responsibilities involved. Applicable industry standards and specifications shall be utilized in the process of selecting suitable parts and materials. 5.5.3 Working documents, such as drawings, specifications, and procedures, which are affected by design changes shall also be revised and controlled so that responsible parties remain informed. 5.6 Design Deficiencies 5.6.1 Errors and deficiencies in approved design documents, including design methods (such as design computer codes), that could adversely affect safety related structures, systems, and components shall be documented and action taken to ensure that all errors and deficiencies are corrected and that action is taken to prevent recurrence. Such corrective action shall be in accordance with Chapter 16 of this manual. 5.6.2 Malfunctions shall be promptly documented and evaluated to determine probable cause, If evidence indicates that common components in safety related systems have performed in an unsatisfactory manner, corrective measures shall be planned prior to replacement or repair of such components. Approved procedures for repair shall be available prior to actual performance. Replacement parts sha;l receive adequate evaluation and/or testing if they are not of a design which has been previously proven satisfactory. A phased replacement shall be considered, when possible, to permit in-service performance evaluation and minimize the possibility of a hidden deficiency developing into a systematic failure. An augmented testing and inspection program shall be implemented following a large scale component replacement or repair as necessary to demonstrate component reliability. 5.7 Maintenance and Modification 5.7.1 Inspection and performance testing shall verify that safety related structures, systems, and components are functioning adequately after maintenance or modifications are complete. The results shall be documented and maintained in accordance with applicable procedures. 73
Waterford 3 Quality Assurance Program Manual Chapter 3 Design Control Revision 18 5.7.2 Written safety evaluations of design changes shall be prepared in accordance with Reference 2.2. 5.8 Design Documentation and Records 5.8.1 Design documentation and records, which provide evidence that the design and design verification process were performed in accordance with the Quality Assurance Program requirements shall be collected, stored, and maintained in accordance with documented procedures. This documentation includes final design documents, such as drawings and specifications, and revisions thereto and documentation which identifies the important steps, including sources of design inputs that support the final design. 6.0 RECORDS None 7.0 ATTACHMENTS-
-None 74
l Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control Revision 18 1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, handling, and storage of documents used to obtain materials, spare and replacement parts, components, and services required to modify, maintain, repair, test, inspect or operate Waterford 3. Safety related vendors / contractors and subtier vendors are required, through procurement documents, to implement quality assurance programs consistent with the Entergy Operations, Inc. Quality Assurance Program. It is the Waterford 3 policy that the quality and design of purchased replacement materials, components, and spare parts are equal to or better than the originalitem. 1.2 Services performed by other Entergy Operatit a, Inc. (EOl) sites (shared 5&18l services) are obtained from those sites in accoidance with documented agreements between the sites.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.13-1976, " Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.89, " Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Plants" 3.0 DEFINITIONS 13.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Director, Design Engineering The Director, Design Engineering is responsible for ensuring the development of procedures for defining the performance and documentation of engineering evaluations, as requested or mandated; to establish requirements and controls when original technical or quality assurance requirements cannot be determined for spare or replacement parts. 3l 75
Waterford 3 Cuality Assurance Program Manual Chapter 4 Procurement Document Control Revision 18 4.2 Vice President, Operations Support The Vice President, Operations Support is responsible for: 4.2.1 Ensuring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation of purchase orders and contracts for procurement; 3l 4.2.2 - Ensuring that appropriate procedures are developed and implemented for activities related to the preparation, review, approval, and control of requisitions; and procurement planning; 4.2.3 Vendor selection; coordination of contractor selection; preparation, review, and issuance of purchase orders and contracts to support the procurement of material, equipment, spare, and replacement parts, and services; 3l 4.2.4 Identifying procurement or safety classifications and establishing the quality assurance and technical requirements; 3
-4.2.5 Administration of a quality control receipt inspection program to assure acceptability and maintenance of quality related materials, parts, and components; and 4.2,6 Coordinating the processirig and review of procurement documents for equipment, parts, materials, and services in support of plant operations and station modifications, including maintenance and design changes.
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o Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Cor, trol Revision 18 5.0 PROCEDURE 5.1 Preparation of Procurement Documents 5.1.1 Procedures are provided for the preparation, control, and review of procurement documents to ensure that quality assurance requirements are correctly
-18 l stated, inprocess and final inspection criteria are defined, and that appropriate controls are established.
5.1.2 Entergy Operations, Inc. personnel are responsible for the preparation of procurement documents for safety related parts, structures, systems, 18l components, and services. Their responsibilities include procurement planningi-preparation, review, approval, and contro: of procurement documentation; and assisting in vendor selection. 5.1.3 Organizations preparing procurement documents shall determine the applicable procurement or safety classification in accordance with approved procedures. Procurement and safety classifications are invoked to conform with 18
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committed to, codes, standards or design bases. 5.1.4 Procurement documents, as applicable, shall: 5.1.4.1 State the materials, parts, and components or the scope of work or services to be provided by the vendor; 5.1.4.2 Identify the procurement or safety classification of the item or service ,3l being procured; 5.1.4.3 Contain or invoke, by reference, the technical requirements, including drawings; test and specification requirements; special instructions for activities such as designing, handling, identification, special processes, fabricaan, cleaning, erecting, packaging, shipping, extended storage, etc.; and applicable regulations, codes, and industry standards; 5.1.4.4 Identify the documentation (e.g., drawings, specifications, inspection and fabrication plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test results of material) to be prepared, maintained, and/or submitted to Entergy Operations, Inc. for information, review, and/or approval; 77 1
Waterford 3 Quality Assurance Program Manual Chapter 4 o Procurement Document Control Revision 18 5.1.4.5 Identify the Entergy Operations, Inc. Quality Assurance Program requirements which must be described and implemented in the vendor / contractor and subtier vendor quality assurance programs; = 5.1.4.6 Identify those records to be retained, controlled, and maintained by the vendor and those to be delivered to Entergy Operations, Inc. prior to use or installation of the item; 5.1.4.7 Establish the right of access for Entergy Operations, Inc. and its agents to the vendor's facilities and records fer source inspection and audits; 5.1.4.8 Identify the storage requirements and retention periods for records to be retained by the vendor; g 5.1.4.9 Specify, for non commercial grade item safety related procurement, the 18 l --) requirement for vendors to comply with 10CFR21 for reporting defects anB~ L noncompliances which could create a substantial safety hazard; 5.1.4.10 Establish measures for the identification, control, and disposition of items and services that do not meet procurement document requirements; and 5.1.4.11 Procurement documents for on-site work by a vendor service representative shall require that any materials or replacement parts, and required documentation, shall be subjected to receiving inspection, records review, and Stores Operations issue by Entergy Operations, Inc. 3l 5.1.5 Where commercial grade items are to be used in safety related applications, the procurement documents, inspection plan, or both shall specify special inspections, tests, verifications, documentation or other methods required to 3l assure suitability for the intended safety related application. 3l 5.2 Preparatior, of Requisitions for Spare and Replacement Parts 5.2.1 Orders for spare and replacement pa:ts shall be requisitioned to specifications and codes equivalent to those specified for the original equipment or those specified by a properly reviewed and approved change. 3l 5.2.2 In those cases where the original item or part is safety related and is found to be commercial grade and without specifically identified quality assurance requirements, equivalent spare and replacement parts may be procured 3l commercial grade provided the items are properly evaluated and dedicated for safety related use. 78
Waterford 3 Quality Assurance Program Manual Chapter 4 Procurement Document Control Revision 18 5.2.3 In those cases where the technical and/or quality assurance requirements of the originalitem cannot be determined, an engineering1_8evaluation shall conducted and documented by qualified individuals to establish the requirements and controls. 5.2.3.1 This evaluation shall assure that interfaces, safety, interchangeability, fit, environmental compatibility, and function are not adversely affected or contrary to the UFSAR, applicable codes, standards, and regulations. 5.2.4 Replacement electrical and electronic equipment in harsh environments shall be qualified in accordance with regulatory guides and specifications. 3l 5.3 Review and Approval 5.3.1 As a minimum, procurement documents shall be reviewed to verify that the procurement document contains the appropriate requirements identified in 5.'l.4. 5.3.2 Reviews of procurement documents shall be performed by persornel who have access to pertinent information and who have an adequate understanding of the requirements and intent of the procurement documents. Performance of reviews shall be documented to provide objective evidence of accomplishment. 5.3.3 An independent review of procurement documents and subsequent revisions shall be accomplished prior to issuance to the vendor or contractor to assure that appropriate quality requirements have been imposed. 5.4 Procurement Document Changes Procurement document changes are subject to the same degree of control as utilized in the preparation of the original documents. 6.0 - RECORDS None 7.0 ATTACHMENTS None 79
Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 1.0 PURPOSE 1.1 Instructions, procedures, and drawings for the operational phase of Waterford 3 are developed to prescribe those activities that affect safety related functions. Activities affecting quality are accomplished in accordance with these documents. This Chapter defines the requirements for developing and controlling instructions and procedures for safety related activities.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Directors / Managers Directors and managers are responsible for the development and approval of safety related procedures and instructions which affect activities within their area of responsibility and ensuring that Waterford 3 commitments and obligations are adequately addressed. In addition, directors and managers are responsible for ensuring that the appropriate individuals are trained, prior to the implementation of each new and revised procedure. 4.2 Director, Quality 6
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The Director, Quality is responsible for assuring that a quality review of safety related Waterford 3 procedures, instructions, drawings, and specifications, to ensure the inclusion of applicable Quality Assurance Program requirements, is accomplished. 4.3 Plant Operations Review Committee (PORC) The PORC is responsible for reviewing and making recommendations concerning procedures required by Section 6.8 of the Technical Specifications and others which are used to assure the proper operation and maintenance of safety related equipment as determined by the General Manager, Plant Operations. 80
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Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 5.0 PROCEDURE 5.1 Preparation of instructions, Procedures, ano Drawings 5.1,1 Procedures shall be written and implemented in accordance with applicable codes, standards, and regulations to provide a controlled method for preparing, reviewing, changing, and approving instructions, procedures, and drawings. Eac;i department shall use a governing procedure which _18 l describes the appropriate method for procedure development to assure consistency in preparation. The governing procedure shallincorporate the requirements of the Quality Assurance Program. 5.2 Contents of Instructions and Procedures 5.2.1 Instructions and procedures prescribing safety related activities shall identify any special equipment and conditions required to perform the activity, responsibilities, applicable quantitative and qualitative acceptance criteria, and provisions for documenting that activities were accomplished in accordance with the instructions and procedures. 5.2.2 The format of procedures may vary; however, procedures should include, as appropriate, the following elements: 5.2.2.1 Title; 5.2.2.2 Statement of applicability; 5.2.2.3 References; 5.2.2.4 Prerequisites; 5.2.2.5 Precautions; 5.2.2.6 Limitations and Actions; 5.2.2.7 Main Body; 5.2.2.8 Acceptance Criteria; and 5.2.2.9 Checklists. 81
I Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 5.2.3 When procedures contain ("itical steps and additional assurance is desired for plant operation and routine maintenance, procedures should contain verification signoffs. Verification signoffs shall be accomplished by a qualified person who does not have responsibility for performing the work or directly supervising tha work with exception to plant operations activities by operators requiring verification by the SS/CRS who are direct supervisors. 5.3 Review and Approval 5.3.1 Instructions, procedures, and drawings prescribing safety related activities shall be reviewed and approved by the individual in charge of the organization engaged in that activity prior to use. Procedures shall be established to clearly delineate the review process of procedures and delineate . the approval cycle for procedures and procedure changes. 5.3.2 The reviewing organizations shall have access to pertinent background information upon which to base their approval and shall have adequate understanding of the requirements and intent of the document. 5.3.3 Whenever a safety related instruction, procedure, or drawing of one organization affects or involves the activities of another organization, the originating organization shall ensure that the affected organization reviews and concurs with the document content. 5.3.4 Comments generated by the reviewer shall be resolved by the authorizing organization, and the resolution concurred with by the reviewer prior to procedure approval. Comments which cannot be resolved by the author should be elevated to higher levels of management with the eventual resolution documented on the applicable comment sheet. 5.3.5 Referenced documents (such as drawings or manufacturer's technical manuals) in procedures shall be reviewed to determine their applicability and adequacy to satisfy the requirements of the procedure. 5.3.6 Procedures shall be reviewed to determine if the following conditions are satisfied: 5.3.6.1 The procedure / instruction is in compliance with upper tier procedures, the Quality Assurance Program, and the FSAR; 82 l l
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Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 ' 5.3.6.2 Appropriate qualitative and quantitative acce;.tance criteria are included for determining that safety relcted activities are satisfactorily accomplished; 5.3.6.3 The need for inspection, identification of inspection personnel, aad Jocumentation of inspection results have been properly specified; 5.3.6.4 The necessary inspectior; requirements, methods, and acceptance criteria have been identified; and 5.3.6.5 Inspection hold and verification points are clearly identified. 5.3.7 Procedure reviews are based on a dynamic process for assessing procedural adequacy by initiating procedure review,-change or revision, based on new ci revised source material potentially affecting the intent of procedures. 5.3.8 Applicable safety related procedures shall be reviewed following an unusual incident, such as an accident, unexpected transients, significant operator error, or equipment malfunction. The results of these reviews and any changes or corrective actions necessary shall be reviewed by the PORC. Applicable procedures shall be revised, as necessary, following any modification to a safety related system. 5.4 Plant Operations Review Committee (PORC) The PORC reviews shall ensure that in addition to technical adequacy, the safety review performed by the authorizing department or group is correct and that, when applicable, a 10CFR50.59 safety evaluation is completed and correct. 5.4.1 The safety review shall determine if the procedure, its change, or its deletion: 5.4.1.1 Changes the design, description, functian and/or operation of a system, structure, or component described in the FSAR; 5.4.1.2 Changes the procedures as described in the FSAR; 5.4.1.3 Conducts tests or experiments not described in the FSAR; or 5.4.1.4 Creates a condition or conducts an operation which exceeds, or could result in exceeding, the limits identified in the Technical Specifications. 83
Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 5.5 Technical Review and Controi Process 5.5.1 Procedures required by Technical Specification 6.8.1 and other , procedures which affect nuclear safety, as determined by the General Manager Plant Operations, and changes thereto, shall be reviewed as follows: 5.5.1.1 Each procedure or change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change. This review shall include a determination of whether or not additional cross disciplinary reviews are necessary. If deemed necessary, the reviews shali be performed by the wview personnel of the appropriate discipline (s). 5.5.1.2 Individuals performing these revies s shall meet the applicable qualifications of ANSI /ANS 3.1-1978, Section 4.0, excluding subsections 4.5.2 and 4.5.3, and be approved to perform these reviews in a given area by the General Manager P; ant Operations. 5.5.1.3 Those procedures and programs specified by paragraph 4.10.5 of
~5l Chapter 1, and changes in intent thereto, shall be reviewed by PORC and approved by the General Manager, Plant Operations prior to implementation.
5.5.1.4 Those procedures and programs specified by Technical Specification 6.8.1, and changes in intent thereto, with the exception of those specified in paragraph 4.10.5 of Chapter 1, shall be approved by the appropriate -5l Group Head as specified in station administrative procedures. 5.5.1.5 Review of the procedure or procedure change willinclude a determination f of whether or not an unreviewed safety question is involved. This determination will be based on the review of a written safety evaluation prepared by a qualified individual, or documentation that a safety evaluation is not required. PORC review 9RC review, and NRC approval of items involving unreviewed safety questons shall be obtained prior to station approval for implementation. 5.5.1.6 Written records of reviews shall be prepared and maintained in accordance with this manual. 84
Waterford 3 Quality Assurance Program Manual Chapter 5 Instructions Revision 18 5.6 Procedure Compliance 5.6.1 All personnel should be cognizant of their responsibility to adhere to procedures and instructions. Prior to performing any quality related activity, all personnel are responsible to ensure that: 5.6.1.1 Procedures or instructions have been developed to control the activity; 5.6.1.2 They understand the content of the procedure or instruction and are capable of following it without deviation; 5.6.1.3 They understand that work must be stopped when a procedure or instruction cannot be specifically followed; 5.6.1.4 They understand the process to change procedures and instructions or at a minimum, know to notify their supervisor if an inadequacy is discovered; and 5.6.1.5 They understand that management demand; that procedures and in.tructions be specifically followed or work must be stopped, regardless of cost or schedule. 5S.2 Supervisors should routinely discuss procedural compliance with the personnelin their departments. When it is discovered that a procedure is not deficient but could be improved (quality is not affected), then wntk niay contbue as applicable and a formal procedure change request should be initiated. Proceduralimprovements are encouraged. Personnel should notify their supervisor if a procedure change should be expedited to improve ongoing or near future work. 6.0 RECORDS None 7.0 ATTACHMENTS None 85 f
Waterford0 Quality Assurance Program Manual Chapter 6 Document Control Revision 18 1.0 PURPOSE 1,1 The requirement 4 and responsibilities for controlling the issuance of documents such as instructions, procedures, and drawings, and changes to these documents are established in this chapter. 1.2 Documents atid their revisions which control safety related systems, structures, components, and activities are prepared, reviewed, and approved by authorized personnel before release or issuance in accordance with written procedures. 1.3 Individuels participating in an activity use the latest approved and applicable directions for performing the activity. Document control procedures provide measures to prevent the use of outdated documents.
2.0 REFERENCES
2.1 Regulatory Guide 1,33. Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations 4.1.1 The General Manager, Plant Operations is responsible for ensuring that as-built drawings are utilized for plant operation and maintenance upon completion of a related modification, e1 4.2 Director, Design Engineering 4.2.1 The Director, Design Engineering is responsible for the revision and update of controlled drawings and configuration documents to reflect design changes. 86
Watedord 3 Quality Assurance Program Manual Chapter 6 Document Control Revision 18 4 4.3 Director, Site Support 4.3.1 The Director, Site Support is responsible for the development of a document control system which includes procedures and instructions for the processing and distribution of: 4.3.1.1 The Safety Analysis Report; 4.3.1.2 The Plant Operating Manual; 4.3.1.3 Design documents, including drawings and specifications; 4.3.1.4 The Waterford 3 Management Manual; 6&Z 4.3.1.5 Fabrication, constructiori, installation, inspection, test, maintenance, modification, and operation procedures; 4.3.1.6 Vendor technical manuals and service bulletins 4.3.1.7 Safeguards information; 4.3,1.8 Safety related departmental procedures; and 4.3.1.9 Other documents as assigned. 4.4 Directors / Managers 4.4.1 Directors / Managers are responsible for the development and implementation of: 4.4.1.1 Safety related departmental procedures, as applicable; and 4.4.1.2 Other documents .w assigned. 87
Waterford 3 Quality Assurance Program Manual Chapter 6 Document Control Revision 18 5.0 PROCEDURE 5.1 Document Control 5.1.1 Document control measures shall be prescribed by procedure and shall provide for: 5.1.1.1 The preparation, review, approval and issuance of documents, including their revisions, by authorized individuals or organizations; 5.1.1.2 Assuring that proper documents are used in performing an activity; and 5.1.1.3 Establishing and implementing a system for distribution control. 5.1.2 As built drawings shall be stored in a controlled facility, with reproducible copies of those drawings available for use during op6 ration and maintenance activities. 5.1.3 Controlled copies of documents shall be appropriately identified (e.g., stamped " CONTROLLED"). Obsolete, or superseded copies of controlled documents shall either be clearly identified as such, destroyed, or appropriately segregated (such as, entry into the records management system) to preclude their inadvertent use. 5.2 Document Review 5.2.1 Documents shall be reviewed in accordance with Chapter 5 of the Quality Assurance Program Manual. After review comments have been resolved, the documents shall be approved by the management of the responsible organization, effective dates shall be assigned, and the documents shall be distributed in accordance with applicable procedures and instructions. 5.2.2 Changes to safety related documents shall be reviewed and approved by the same organization that performed the original review and approval or by other responsible organizations delegated by Entergy Operations, Inc. Approved changes shall be included in the instructions, procedures, drawings, and other appropriate documents. 88
Waterford 3 Quality Assurance Program Manual Chapter 6 Document Control Revision 18 5.2.3 Field drawings and sketches which are prepared by Entergy Operations, Inc. personnel to clarify or provido additional details for operation, maintenance, or testing shall be controlled. They shall be reviewed for accuracy by at least one qualified person other than the originator and shall be reviewed and approved by the originating group management before issuance. Revisions shall be handled in the same manner as the original issue. 5.3 Distribution Control 5.3.1 The distribution control system shall include: 5.3.1.1 Procedures that describe how documents are received, distributed, and controlled; 5.3.1.2 The identification of documents to be controlled; 5.3.1.3 Documents to be distributed in accordance with distribution lists; 5.3.1.4 Methods for dispositioning outdated documents to preclude inadvertent use; 5.3.1.5 Distribution and maintenance of a controlled document list to aid in the identification of document status; and 5.3.1.6 Methods to identify controlled documents; e.g., stamping with a control number. 5.3.2 Controlled documents shall be distributed prior to starting an activity and, if necessary, the controlled documents shall be available at the locations where the activities r.re performed. 5.3.3 Master lists of controlled documents shall be available at specific locations to preclude the use of superseded documents. The lists shall be prepared and updated in accordance with applicable procedures. The lists shall identify the current revision number of the instructions, procedures, specifications, drawings, interim changes, and procurement specifications. 5.4 Types of Controlled Documents 5.4.1 The documents controlled under the Waterford 3 Quality Assurance Program include: 5.4.1.1 Safety Analysis Report; 89
Waterford 3 Quality Assurance Prograrn Manual Chapter 6 Document Control Revision 18 5.4.1.2 Design documents including calculations, drawings, field drawings and sketches, specifications, change requests, and analysis; 5.4.1.3 Vendor Manuals; 5.4.1.4 Waterford 3 Management Manual; 5.4.1.5 Inspection and test procedures for test, fabrication, construction, installation, maintenance, modification, and operation; 5.4.1.6 As built documents; 5.4.1.7 Quality Assurance Program Manual; 5.4.1.8 Emergency Plan; 5.4.1.9 Physical Security Plan; 5.4.1.10 Plant Operating Manual; 5.4.1,11 Qualhy Assurance Procedures; 5.4.1.12 Engineering Procedures; 5.4.1.13 Training Procedures; 5.4.1.14 Site Support Procedures; 5.4.1,15 Plant Modification and Construction Procedures; 5.4.1.16 Nuclear Safety Procedures; and 5.4.1.17 Approved Interim Change Documents. 6.0 RECORDS None
= = =
7.0 ATTACHMENTS None 90
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 1.0 PURPOSE 1.1 Safety related material, equipment, and services, whether purchased directly or through others, conforms to procurement document specifications as described in Chapter 4. Provisions are made, as appropriate, for source evaluation and selection, review for objective evidence of quality, inspection at source, and inspection upon delivery. In addition, products may be accepted by pre / post installation testing or qualification testing by Entergy Operations, Inc. (EOl) or an approved test laboratory. 1.2 Vendors' Quality Assurance Programs are reviewed at periodic htervals commensurate with the importance, quantity, and complexity of the product or services being purchased. These reviews may employ audits, surveillances, source verifications, independent inspections, or tests to verify that documentation, such as inspection records and certifications, are reliable and valid, 1.3 Proposals (bids or quotations) by vendors are reviewed to ensure that no exceptions are taken which would violate safety, technical, or quality assurance 18 requirements. The program requirements for control of purchased material, "l equipment, and services are contained in approved written procedures. 1.4 Services performed by other EOI sites (shared services) are obtained from those 7l sites in accordance with documented agreements between the sites. 2.0- REFERENCES 2,1 USNRC Regulatory Guide 1.123, Revision 1, July 1977 (which endorses ANSI N45.2.131976," Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 91 l J
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 4.0 RESPONSIBILITIES 4.1 Director, Design Engineering The Director, Design Engineering is responsible for: 4.1.1 Assisting in the establishment of quality assurance and technical requirements in quality related preurement documents; and 4.1.2 Reviewing selected requests for spare and replacement parts designated EQ to determine their technical and quality assurance requirements, if required. 4.2 Vice President, Operations Support The Vice President, Operations Support is responsible for: 4.2.1 Ensuring the development of procedures for defining the vendor and contractor selection process and defining the process for the preparation of purchase orders and contracts for procurement; 3l 4.2.2 Vendor selection, the coordination of contractor selection, and the preparation and issuance of purchase orders and contracts to support the procurement of gl material, equipment, spare and replacement parts, and services; 4.2.3 Performing inspections of site storage facilities; and 4.2,4 Establishing and maintaining a qualified suppliers list through the conduct of pre award evaluations, annual evaluations, periodic audits and surveillances. 4.3 Directors / Managers Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in support of their departmental activities. 4.4 Director, Quality 8 The Director, Quality is responsible for assuring that appropriate quality standards are maintained throughout the procurement process 92
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.0 PROCEDURE 5.1 Qualification of Vendors 5.1.1 Safety related (not commercial grade) equipment, materials, and services 18 services shall be obtained from vendors, contractors, and consultants conta on a qualified suppliers list (OSL), when required, to assuro compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and consultants shall be qualified for inclusion on the QSL through an evaluation of their technical and quality assurance capabilities for providing safety related items and services. Quality Assurance evaluations shall be conducted by appropriately certified personnel and the results documented and maintained in accordance with quality records management procedures. 5.1.2 The evaluation of vendors shall be based on one or more of the following criteria: 5.1.2.1 The vendor's ability to comply with the requirements of the Quality Assurance Program as applicable to the type of material, equipment or service being procured; 5.1.2.2 A review of the records and performance of vendors who have previously provided items and services similar to the type being procured; or 5.1.2.3 A survey of the vendor's facilities and/or quality assurance program to determine the vendor's capability to provide a specified service or product which meets design, manufacturing and quality assurance requirements. 5.1.3 Re-evaluation and requalification of vendors on the QSL shall be made on a periodic basis, as specified in applicable procedures. 5.1.4 Suppliers of safety related (not commercial grade) structures, systems,
-18l components, and, services for Waterford 3 shall be informed through procurement documents of their requirement to comply with 10CFR21 for 18l
~
reporting defects and noncompliances that could create a substantial safety hazard. O 93
Waterford 3 Quality Assurance Program Manual Chapter 7 Pntrol Of Purchased Materials, Equipment, and Services Revision 18 5.2 Procurement Planning 5.2.1 Procurement planning is a shared responsibility between the Site 6&
"" 18 l Support and Operations Support organizations.
5.2.2 Based on the relative importance, complexity, or quantity of the item or service, planning activities shall establish the following in accordance with approved procedures: 5.2.2.1 The need to perform surveillance (s) of ths vendors / subtler vendors activities and/or products during the manufacturing process; 5.2.2.2 The need to participate in the inspection hold point program established by the vendor or to establish Entergy Operations, Inc. mandatory hold points.: 5.2.2.3 The identification of documents, such as, qualifications of personnel or procedures to be generated and submitted to Entergy Operations, Inc. for approval prior to start of work; 5.2.2.4 The identification of schedules, plans, drawings, design documents, test / inspection results, etc., to be submitted to Entergy Operations, Inc. for approval or information; 5.2.2.5 The method for acceptance of items or services by Entergy Operations, Inc.; 5.2.2.6 The scope and frequency of audits /surveillances required to monitor performance and/or maintain vendor qualifications; 5.2.2.7 The timing or schedule for each of the above, as applicable; and 5.2.2.8 The Entergy Operations, Inc. organization or authorized representative responsible for performing each of the above as applicable. 94 1
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Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.3 Audits and Surveillances of Suppliers 5.3.1 Audits and surveillances of safety related vendors during fabrication, inspection, testing, and shipment of materials, equipment, and components shall be planned and performed in accordance with written procedures to ensure vendor conformance 0 ocurement requirements. These procedures shallinclude: 5.3.1.1 Instructions that specify the characteristics or processes to be witnesaed, inspected or verified, and accepted; 5.3.1.2 The method of surveillance and the extent of documentation required; and 5.3.1.3 The personnel responsible for implementing these instructions. 5.3.2 In process surveillances should be performed when procurement requirements cannot be verified during receipt inspection. 5.3.3 The effectiveness of the vendor's quality assurance program shall be assessed by Entergy Operations, Inc. at intervals consistent with the importance, complexity, and quantity of the item or service. 5.4 Receipt Inspection and Acceptance 5.4.1 Quality control receipt inspection of quality related material, components, and equipment shall be performed in accordance with written procedures which 3l provide for the following: 5.4.1.1 The material, component or equipment is properly identified and corresponds to the requirements of procurement documentation; 5.4.1.2 Material, components, equipment, and records are inspected in accordance with procurement document requirements prior to installation or use; 5.4.1.3 As applicable, inspection records or certificates of conformance attesting
.to the quality of material, components, and equipment are available at
.Waterford 3 prior to installation or use; and
~
5.4.1.4 Accepted and releasod items have their inspection status identified prior to being forwarded to a controlled storage area or released for installation or further work.- 95
Waterford 3 Quality Assurance Program Manua! Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.4.2 Methods for product acceptance include evaluation of the vendor's QA Program, source inspection / surveillance, receipt inspection, pre / post installation test!ng, or qualification testing by Entergy Operations, Inc. or a qualified test laboratory.
'i he methodology to control these acceptance methods shall be specified in procedures. Acceptance by vendor's certificate of conformance or compliance is satisfactory, provided means are available to verify the validity of such certifications.
5.4.3 Acceptance by post installation testing should be used when it is difficult to verify the quality of the item without it being installed or in use. 5.4.4 Services, such as, engineering and consultant services or installation, repair, or maintenance work shall be accepted by one of the following methods: technical verification of data; audit; inspection; surveillance; or review of objective ovidence for conformance to procurement documents. 5.5 Procurement and Dedication of Commercial Grade Items 5.5.1 Commercial grade items shall be evaluated for suitability of application. The evaluation results shall be documented. 3l 5.5.2 The preparer of the purchase requisition is responsible for clearly identifying the commercial grade item to be procured and the acceptance methods. The i item selected shall be identical to the original or an approved alternate or 3 equivalent. 5.5.3 If the part is different from or an addition to the original design and constitutes a plant modification, Design Engineering shall review the material application and verify the part's suitability for the intended use. 5.5.4 Additional source verification, inspection, or test requirements shall be specified l in the procurement documents or inspection plan, as necessary, to dedicate gl the commercial grade item for use in a safety related application. 5.6 Spare and Replacement Parts 5.6.1 Spare and replacement parts for safety related systems, structures, and components shall be subject to Waterford 3 Quality Assurance Program controls, and to codes, standards, and technical requirements at least equivalent to or better than those used for the original equipment. 96 l _
Waterford 3 Quality Assurance Program Manual Chapter 7 Control Of Purchased Materials, Equipment, and Services Revision 18 5.7 Records 1 5.7.1 Quality Assurance records, when required by procurement documents, shall be
- collected and retained by vendors of safety related items. Suppliers shall furnish the following records, as a minimum, to Entergy Operations, Inc. or its agent:
5.7.1.1 Documentation that identifies the purchased niaterial or equipment and the specific procurement requirements (e.g., codes, standards, specifications) met by the items; and 5.7.1.2 Documentation that identifies any procurement requirements which have not been met, together with a description of those nonconformances dispositioned " accept as is" or " repair." 5.7.2 The review, evaluation, and acceptance of the required vendor records furnished ! to Entergy Operations, Inc. shall be described in procedures. 5.7.3 Records associated with qualification testing (inplace or test laboratory) shall also be considered QA records and shall be submitted to, or made available to Entergy Operations, Inc. i 5.7.4 Required procurement documents shall be available at Waterford 3 prior to use of purchased material, components, or equipment. The documentation shall be retained in accordance with approved procedures. 6.0 RECORDS None 7.0 ATTACHMENTS None 1 97
Waterford 3 Quality Assurance Program Manual Chapter 8 Identification And Control Of Materials, Parts And Components Revision 18 1.0 PURPOSE Identification and control of safety related materials, paris, t.nd components are accomplished in accordance with approved procedures and apply to materials, parts, or components in all stages of fabrication, storage, installation, ut e or removal from use. This chapter defines requirements for the identification and control of materials, parts, and components.
2.0 REFERENCES
2.1 10CFR50.55a 2.2 ASME Boiler and Pressure Vessel Code Section 111 g 2.3 10CFR50 Appendix B 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Director, Quality 6 The Director, Quality is responsible for verifying adherence to applicable procedures for the identification and control of materials, parts, and components through the performance of periodic audits, surveillances, and inspections. 4.2 Vice President, Operations Support The Vice President, Operations Support is responsible for: 4.2.1 Ensuring the development and maintenance of procedures for the identifcation and control of safety related items which are received, stored, and issued at the plant site; 4.2.2 Implementation of procedural controls necessary to ensure proper identification of items in storage, items issued for installation, and the control of items in storage which have limited' shelf lives; 98
j !
- Waterford 3 Quality Assurance Program Manual Chapter 8 [
ldentification And Control Of Materials, Paris And Components Revision 18 ! ! 4.2.3 Verifying that materials, parts, and components are oroperly identified at I l receipt; and i 4.2.4 Verifying the transfer of required identification or traceability information .
- prior to items being subdivided while in stores control or at the time of issue from stores control.
3 1 4.3 Directors / Managers Directors and Managers are responsible for the inclusion of appropriate identification and control requirements in purchase or contract requisitions in order 4 to ensure compliance with requirements of the Waterford 3 Quality Assurance . Program and applicable codes, standards, and regulations. Directors and [ Managers are also responsible for developing and maintaining procedures for the identification and control of items drawn from stores, installed, or used. 4 4 l J i 99 e ,~~-,-,-er,-w,-, ,cr-r---, ,---n w- - - . , - - - , - - n- - - - ---,- --nm-,, --,--e,- - - - - - + ~ , - - - , - - e-,,----a
Waterford 3 Quality Assurance Program Manual Chapter 8 Identification And Control Of Materlab, Parts And Components Revision 18 5.0 DETAILS 5.1 Identification and Control 5.1.1 The identification of applicable safety related mat als, parts, and components shall be by means of heat numbers, serial numbers, date coding, lot numbers, part numbers, or other appropriate means. Where physical identification on the item is impracticable or insufficient, physical separation, procedural control or other appropriate means shall be employed. However, physical identification shall be utilized to the maximum extent possible. 5.1.2 When identification markings are employed, they shall be clear, unambiguous, indelible, and not detrimental to the service life of the item. 5.1.3 The inclusion of identification requirements in design documents shall be checked during design verification by the design organization. 5.1.4 Items of production (batch, lot, component, part, etc.) shall be identified from the initial receipt or fabrication of the item up to and including installation and use. This identification shall ren.le the item to applicable design or other specifying documents. 5.1.5 Procedures shall include previsions to prevent the use of incorrect or defective items by requiring that identification be maintained either on tho item or on records traceable to the item. The identification of materials, parts, and components shall be verified and documented prior to release from storage areas to ensure that only correct and accepted items are used and int.talled. 5.2 Traceability 5.2.1 Inventory and issuance controls shall be established to ensure material traceability to storage and plant !ocations. 5.2.2 - Procedures shall be established and maintained to ensure that material identification is specified on procurement documents. Since marking requirements vary between specifications for different materials and g construction codes, procedures must be established to ensure material to be used has been purchased in accordance with the requirements of the proper specification and construction code for the application. 100
Waterford 3 Quality Assurance Program Manual Chapter 8 Identification And Control Of Materials, Parts And Components Revision 18 S.3 Maintaining Identification and Traceability 5.3.1 Procedures shall be established and maintained to provide continued cross referencing between the various identifications that have been used for traceability during an item's life (i.e., between the Architect Engineer's system, the NSSS supplier's system, manufacturer's systems, and the Waterford 3 - Station Information Management System) in order to ensure continued retrievability of pertinent records. 5.3.2 Procedures shall be established and maintained for the control of item identification consistent with the planned duration and conditions of storage, such as: 5.3.2.1 Provisions for the maintenance or replacement of markings due to damage during handling or aging; 5.3.2.2 Protection of markings on items subject to excessive deterioration due to environmental exposure; and 5.3.2.3 Provisions for updating existing plant records. 5.3.3 Identification of the item shall be maintained by heat number, part number, serial number, or other appropriate means, either on the item or on records traceable to the item, throughout fabrication, erection, installation, and use of the item, All means of traceability of material shall be maintained to the maxinum extent possible. Where identification or markings must be destroyed, hidden or removed from an item, traceability must be maintained to documents and records associated with the material. 5.3.3.1 Class 1,2 or 3 Code material: Where bulk material will be g cut, each piece of material shall be marked to include all means of traceability to the maximum extent possible. The marking shallinclude the material specification and grade, the heat number or heat code. For class 1,2 or 3 Code material with less than 1 inch in any direction available for marking, the item must be packaged in a container that is marked with the material specification and grade and the heat number or heat code. 5.3.3.2 Non Code material: Where bulk material will be cut, each piece of material should be marked for traceability to the stockcode, purchase order and Material Receiving Inspection Report. 101
^ Waterford 3 Quality Assurance Program Manual Chapter 8 Identification And Control Of Materials, Parts And Components Revision 18 5.3.4 Stamping is allowed on 1/4" or thicker material. If identification of material by metal stamping is performed, low stress stamps (sometimes referred to as blunt nosed or round faced stamps) with minimum radius of 1/32" shall be used. QA (not other department employees acting as inspectors) is the only group allowed to use interrupted dot die stamps. When vibrating marking tools are 5 used, they shall be fitted with carbide marking tip or equivalent and shall be designed to provide a rounded impression not to exceed 0.010 inches in depth. Etching shall not be performed on nickel alloys or on weld areas or sensitized areas of stainless steel. Electric arc markers shall not be used. 5.4 Limite.d Life Items 5.4.1 Items having limited shelf or operating life shall be identified and controlled to preclude the use of items whose shelf or operating life has expired. Use of such items beyond the specified limits shall be evaluated and documented justification provided. ' 6.0 RECORDS None 7.0 ATTACHMENTS None l 102
Waterford 3 Quality Asst ranc.e Program Manual Chapter 9 Controlof Special Processes Revision 18 1.0 PURPOSE Safety related activities identified as special processes are controlled to ensure they are accomplished in accordance with approved written procedures. Procedures and personnel performing special processes are qualified in accordance with applicable codes and standards and, where no appropriate standards exist, to Waterford 3 - Quality Assurance Program requirements.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.37,3/73, " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants" (which endorses ANSI N45.2.1-1973," Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 2.3 SNT-TC 1 A-1980, " Recommended Practice for NDE Personnel Qualification and Certification" 2.4 USNRC Regulatory Guide 1.58, Revision 2, September 1980 (which endorses ANSI N45.2.61978, " Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants") 2.5 ASME, Section XI,1980 Edition through Winter 1981 Addenda (In-Service inspection Program commitment) 2.6 ASME, Section V,1980 Edition through Winter 1981 Addenda 2.7 ASME, Section V,1989 Edition 2.8 ASME, Section IX, latest Edition and Addenda or as otherwise specified in applicable instructions, procedures, or specifications 2.9 AWS D1.1, latest edition or as otherwise specified in applicable instructions, procedures, or specifications 2.10 ANSI B31.1, latest edition or as otherwise specified in applicable instructions, procedures, or specifications 103
Waterford 3 Quality Assurance Program Manual Chapter 9 Control of Special Processes Revision 18 2.11 UNT 010-004, " Control of Chemical Chroning" 2.12 MM 006-100,
- Maintenance Painting" 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4.
4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for the establishment, approval, and implementation of plant staff special processes and procedures and implementing the Entergy Operations, Inc. welding program. 4.2 Director, Plant Modification and Construction The Director, Plant Modification and Construction is responsible for the establishment, approval and implementation of procedures for selected special processes. 4.3 Director, Quality 6 The Director, Quality is responsible for assuring the establishment of the control of" special processes program and for verifying the effectiveness of its implementation through reviews, inspections, audits and surveillances. Additionally, the Director, 6 Quality is responsible for approving NDE and inspection personnel certifications, and for the development and implementation of nondestructive examination and inspection procedures. 4.4 Vice President, Engineering The Vice President, Engineering is responsible for the administrative, programmatic, and operational control of the Entergy Operations, Inc. welding program. 104
Waterford 3 Quality Assurance Program Manual Chapter 9 Control of Special Processes { Revision 18 5.0 PROCEDURE 5.1 - - Special Processes Subject to Controls 5.1.1 - Special processes are those safety related special processes or operations that require specialin process controls and verification of essential characteristics. Acceptance may not be determined solely by inspection, test, or examination. Assurance that all steps of the process were properly carried out depends in part on the skill of the operator, use of specific equipment, and adherence to the qualified process procedures and controls. 5.1.2 6pecial processes include, but may not be limited to, the following as they are applied to safety related items: 5.1.2.1 Welding; 5.1.2.2 Heat treating: 5.1.2.3 NDE; 5.1.2.4 Chemical cleaning; 5.1.2.5 Concrete and grout placement (selsmic applications); 5.1.2.6 Reinforcing steel cadwelding (seismic application); 5.1.2.7 Brazing; and 5.1.2.8- Protective coatings (Level i Application). 5.1.3 - . The above listed processes, and other activities requiring special controls as determined by Entergy Operations, Inc. management, shall be designated in approved procedures, drawings, or sper.itications, as appropriate. 5.2 - Special Process Procedures 5.2.1 Special process procedures shall be qualified and approved before use and shall describe or reference documents pertaining to the following, as applicable: 5.2.1.1 Qualificatioh/ certification requifements for personnel involved with , the performance of the special process; 105 I
Mterford 3 Quality Assurance Program Manual Chapter 9 Control of Special Processes Revision 18 5.2.1.2 Calibration, certification, or qualification requirements of equipment used in the performance of the special process; 5.2.1.3 Identification requirements for consumables to be utilized in the performance of the special process; 5.2.1.4 Documentation of the methods and results required to qualify the process; 5.2.1.5 Documentation of the activity and process results; 5.2.1.0 Process parameters and environmental conditions to be established or maintained; 5.2.1.7 Codes and standards applicable to the activity or process; 5.2.1.8 The activity and process acceptance criteria; and 5.2.1.9 The methods and sequences, when necessary, for the performance of the special process. 5.3 Qualification of Personnel, Procedures, and/or Equipment 5.3.1 Qualification and certification may be provided by authorized agencies or by designated individuals, in writing, within Entergy Operations, Inc. Certification shall include necessary training followed by an examination of each individual. The period of validity for certification of personnel shall be in accordance with criteria described in applicable codes, standards, and specifications. 5.3.2 Personnel failing retest shall not be allowed to perform the special process until they have been recertified. 5.3.3 ^ ' evel 111 shall review and concur with procodures to assure they are in wordance with applicabla requirements of governing codes, standards, and specifications. A Level lll shall provide and/or assure training, examination, and qualification and recommend certification of Level I, ll, and lll personnel. 5.3.4 For special processes not covered by existing codes or standards, or when the quality assurance requirements exceed the requirements of established codes or standards, the necessary qualifications of perso.'nel, procedures, and/or equipment shall be defined. 106
Waterford 3 Quality Assurance Program Manual Chapter 9 Control of Special Processes Revision 18 5.4 Documentation / Records 5.4.1 A certified Level 11 or higher in the applicable discipline, shall evaluate and approve test / inspection results. Documentation of this evaluation and approval shall be maintained and controlled as a quality assurance record. Documents prepared by contractor personnel shall be independently reviewed and approved by an Entergy Operations, Inc. Level ll or Ill certified in the applicable discipline. The Entergy Operations, Inc. review of contractor reports may be waived but only as approved in writing by the Director, Quality. 6l 5.4.2 Qualification, certification, or calibration records of special process personnel, procedures, and equipment, or other records relating to the 1 performance of special processes shall be prepared and maintained as quality assurance records. The Quality Assurance organization shall verify their , existence and adequacy through reviews, audits, surveillances and inspections. 5.4.3 Special process control records of vendors may be retained or submitted ; to Entergy Operations, Inc. as directed in procurement documents. 6,0 RECORDS None 7,0 ATTACHMENTS None 107 e v- -r---,wme-n-.n-w w-,-m- m-e,, r-----:-~, .,m., ,-c.,--e --e-, -w -~---n , m-w.,,-- ,, x -- ms n-,-------w-r--m-rw
W;t:rford 3 Qu:lity Assurcnce Progrcm M:nu 1 Ch:pt:r 10 inspection Revision 18 1.0 PURPOSE 1,1 Inspections of maintenance, modification, repair, material receipt and storage activities for safety related items and activities are conducted in accordance with the requirements contained in this chapter and applicable codes, standards, and specifications. 1.2 in accordance with the Waterford 3 Quality Assurance (QA) Program, inspections are planned and executed as required to assure conformance of an item to specified requirements. Characteristics to be inspected and inspection methods to be employed are specified and inspection results documented, inspections are performed by persons other than those who performed or directly supervised the work being inspected.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976," Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.58, Rev. 2, September 1980 (which endorses ANSI N45.2.6 - 1978, " Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants") 2.3 ASME Code, Section XI,1980 Edition through Winter 1981 Addenda 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 3.2 PEER / MAINTENANCE INSPECTOR - An ANSI N45.2.6 certified individual normally assigned to the line organization, but who reports to the QA Inspections unit during the inspection activity. This individual is not directiy responsible for, or supervisor of, the activity being inspected. 108 i
W:t:rford 3 Qunlity Assurance Progrcm M:nual Ch: pint 10 Inspection Revision 18 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for: 4.1.1 The control and maintenance of ANil interfaces involving inspections related to modifications, repairs, and replacements under the American Society of Mechanical Engineers (ASME), Boller and Pressure Vessel Code (Code), Section XI, Section 111 Division l Class 1,2,3, and MC components and their supports; 4.1.2 Support of the Peer inspection program by recommending and providing personnel to be certified and to perform peer inspections; and 4.1.3 Preparing maintenance and modification work instructions which contain the required inspection holdpoints and crheria. 4.2 Director, Design Engineering I 4.2.1 The Director, Design Engineering is responsible for the control and maintenance of the Waterford 3 ASME Ten Year in-service Inspection Program. The Director, ! Design Engineering is also responsible for all ANil interfaces in matters related i to the In service Inspection Program. l 4.3 Director, Quality 7 The Director, Quality is responsible for: 4.3.1 The development and administration of the plant inspection program at l Waterford 3; 3 4.3.2 Certifying inspection personnel; I 4.3.3 Reviewing all safety related work authorizations (WAs), WAs containing hold points, or WAs involving special processes, to ensure the inclusion of quality 1 - requirements, and ensuring that quality reviews are conducted for all other initiated work authorizations; and
.4.3.4 Conducting or coordinating inspections of modifications and maintenance activities.
{ 4.4 Vice President, Operations Support j 4.4.1- The Vice President, Operations Support is responsible for the performance of ! receipt and storage inspections. 109 i l
)
W;terford 3 Quality Assurcnce Progrcm M:nual Chapt 3r 10 inspection Revision 18 5.0 PROCEDURE 5.1 Inspection Program i 5.1.1_ Entergy Operations, Inc. (EOI) has three sources of inspection personnel for
- safety related activities at Waterford 3
5.1.1.1 Quality Assurance personnel; 5.1.1.2 Line organization personnel (i.e. Peer / Maintenance Inspectors); or 5.1.1.3 Contract personnel. 5.1.2 Inspections shall be controlled as follows: , 5.1.2.1 Inspections are performed in accordance with procedures approved by Entergy Operations, Inc.; 5.1.2.2 Inspection results are documented, evaluated and their acceptability determined by responsible personnel in accordance with approved procedurns; 5.1.2.3 inspection procedures _ inspection personnel qualifications and certifications are concurred with by the Director, Quality; {l NOTE: Stores inspection procedures, are controlled in accordance with the Materials, Purchasing and Contracts administrative procedures 3 manual. 5.1.2.4 Inspections are performed by certified individuals other than those who performed or directly supervised the activity being inspected; 5.1.2.5 Inspection of operating activities may be conducted by second-line supervisory personnel or by other certified personnel not assigned first line supervisory responsibility for conduct of the work; and 5.1.2.6 Inspection activities not conducted by Quality Assurance are periodically reviewed by Quality Assurance. 5.1.3 Inspections of operating activities or work functions associated with normal operation of the plant, routine maintenance, and certain technical support services routinely performed by the plant staff may be conducted by qualified and certified personnel selected by plant management. I 110
- W:t:rford 3 Qu:lity Assurcnca Program M:nual Ch::ptar 10 inspection Revision 18 5.1.4 Receipt and storage inspections are performed by qualified and certified personnel. For specialinspections, such as nuclear fuel receiving, qualified and certified personnel reporting to the General Manager, Plant Operations may be utilized. ,
5.1.5 Inspections requiring expertise in a particular area, such as in service inspection, certain nondestructive testing, and containment vessel leak rate tests and inspections, may be conducted by off site Entergy Operations, Inc. or contractor personnel, in such instances, the inspection activities shall be conducted under the Waterford 3 Quality Assurance Program or an approved contractor program. 5.1.6 Individuals performing inspections shall be responsible for verifying that the M&TE used in the inspection meetc the criteria noted in the procedure and that inspection results are within the specified acceptance critt ria stated. 5.1,7 Inspections conducted by persons during on the-job training shall be under the direct observation and supervision of a person certified to Level 11 or higher in the appropriate discipline. Verification of conformance is by the certified Level 11 until certification is achieved. 5.2 Inspection Procedures, instructions, and Checklists 5.2.1 Inspection requirements shall be implemented using applicable procedures, instructions, checklists, drawings, and specifications. 5.2.2 Procedures, instructions, and checklists governing inspections shall provide for the rohowing, as applicable: 5.2.2.1 Criteria for determining when inspections are required and how they are performed; 5.2.2.2 Identification of individuals or groups who established inspection requirements; 5.2.2.3 Acceptance and rejection criteria; 5.2.?.4 Identification of individuals or groups responsible for performing inspections; 5.2.2.5 Identification of the points where inspections are required; 5.2.2.6 Identification of characteristics to be inspected; 5.2.2.7 A description of the inspection method; 111
W;t:rford 3 Ouality Assurance Progrcm Manu:1 Chapt:r 10 Inspection Revision 18 5.2.2.8 'dentification of required measuring and test equi t. ment (M".TE); 5.2.2.9 Accuracy, precision and calibration requirements for M&TE; 5.2.2.10 A method for recording the identity of the recording inspector or data recorder and recording the inspection results and/or observations; 5.2.2.11 A method for recording evidence of completing and verifying a manufacturing inspection or test operation; 5.2.2.12 Identification of procedures, drawings, and specifications, including revision level used to conduct the inspection: 5.2.2.13 Identification of specialized qualifications ',ertifications, or skills required by codes or standards for personnet pe.rf ning inspections; and 5.2.2.14 Verification of material acceptability prior to installation or use. 5.2.3 Safety related inspection procedures shall be reviewed to verify the inclusion of the above requirements. 5.2.4 The procedure originator shall be responsible for ensuring that the accuracy and precision requirements of inspection equipmen' are sufficient to obtain reliable data. Accuracy and precision requirements shall be based on procurement and/or plant technical specifications. Indisiduals performing inspections shall be responsible for assuring the equipment used meets the criteria noted in the procedure. 5.2.5 Quality Assurance shall be responsible for verifying that inspection equipment meets the criteria of the procedure and that inspection results are within the acceptance criteria. 5.3 Inspector Qualifications 5.3.1 Inspectors shall be qualified through experience, education, and training programs to perform their assigned inspection tasks. Where requirer, inspectors shall be formally examined and certified. A file shall be maintained containing the credentials for each inspector. Inspector qualifications and certifications shall be kept current. Procedures shall contain qualification criteria for inspection personnel for the various types of inspections. 5.3.2 Procedures shall be developed to define the training programs / curriculum iur inspection personnel. 112
Waterford 3 Quality Assuranco Program Manual Chapter 10 Spection Revisior '8 5.3.3 The inspector qualification program shall be reviewed and concurred with by the Director, Quality or his cssignee. The Director, Quality shall be responsible -7, l for approving the certification of inspectors. 5.4 Inspection By Sampling Methods Sampling inspection methods may be used when tests are destructive or when cuality assurance records and inherent characteristics of the item indicate that a reduction in items inspected or tewed can be achieved without jeopardizing the assurance of quality. When a sampling method is used to verify acceptability, the sampling procedures shall prcvide justification for the sample size and selection process and shall be concurred with by the Director, Quality or his designee. [l 5.5 Indirect inspection 5.5.1 When it is not possible or practical to verify conformance of processed material or products by direct inspection, indirect control may be employed by observation of processing meeods, equipment, and personnel. To ensure adequate control, both direci nspection and process monitoring shall be provided when control by only one method is considered inadequate. 5.5.2 A combination of inspection and procass monitoring methods, when used, shall be performed in r qAen atic manner to assure that the specified requirements for control of the pmceo 6J quality of the item are being achieved throughout the duration of the process. 5.5.3 Controls, where required, shall be established and documented for the coordinati:cq and sequencing of these activities at established inspection points during successive stages of the process or construction. 5.6 Receiving Inspection Receiving inspection of purchased items and materials shall be performed by qualified and certified personnel in accordance with written procedures / instructions / checklists. 5.7 Identification of Hold Points 5.7.1 Work plans, procedures, and instructions for maintenance, modification or test of safety related structures, systems or components shall be reviewed to verify inclusion of inspection requirements, criteria, and hold points. Work in process shall not proceed past the identified hold points without satisfaction of inspection requirements. 113 1
Wat::rford 3 Quility Assurance Program Manuti CI' apter 10 inspection Revision 18 5.7.2 Safety related supplists and vendors shall be required through procurement documents, where applicable, to submit their manufacturing plans to Entergy Operations, Inc. This shall be done prior to manufacture in their shops or shops of their suppliers so that EOl has the opportunity to identify mandatory inspection hold points for witness by an EOl representative. Work may not proceed beyond these hold points without Entergy Operations, Inc consent. 5.7.3 Approval for deleting or waiving a hold point shall be received prior to continuing work past the hold point. Approval to delete or waive the inspection requirement shall be documented and shall be made in the same manner in which the inspection requirement was originally approved. 5.8 in-Service inspections 5.8.1 The ASME In-service Inspection (ISI) Program is implemented for the purpose of periodically verifying the structural integrity or safety related pressure retaining components and their supports. - 5.12 l'he ISI Program identifies the applicable components, examination methods and evaluation criteria necessary to fulfill the requirements of the ASME Code, Section XI,1980 Edition through the Winter 1981 Addenda. Resulting data from the program shall be submitted to the Authorized Nuclear In-service inspector (ANil) for review and acceptance. A summary of the results shall be submitted to the USNRC for review. 5.9 Authorized Nuclear in-Service Inspector Interfaces ; 5.9.1 Authorized Nuclear In-service Inspectors (ANlls) shall be given full access to receiving inspection areas where code items and material undergo receiving inspection. All records relating to the procurement of Code items, as provided by suppliers and manufacturers shall be made available for review. ! 5.9.2 Work packages involving station modifications, repairs, or replacements of code items shall be presented to the ANil for establishment of ANil hold / witness points prior to commencement of work. ANil hold / witness points shall not be passed without prior written consent or a documented telephone conversation from the ANil. Waived hold points shall be documented. 5.9.3 The results of examinations performed under the Code during in-service inspections shall be presented to the ANil for review and acceptance. Inspection and examination data from code manufacturers which support the in-service inspection programs shall also be made available for ANil review. 114
W:t:rford 3 Qu lity Assuranca Program Manual Ch pter 10 Inspection Revision 18 5.10 Records 5.10.1 Records of inspections, as a minimum, shall identify the: 5.10.1.1 Item inspected; 5.10.1.2 Date of inspection; 5.10.1.3 Inspector; 5.10.1.4 Type of observation; 5.10.1.5 Results or acceptability; 5.10.1.6 Person approving inspection; and 5.10.1.7 Reference to information on action taken in connection with nonconformances. 6.0 RECORDS None 7.0 ATTACHMENTS None 115
Waterford 3 Quality Assurance Program Manual Chapter 11 Test Control Revision 18 1.0 PURPOSE 1.1 This Chapter defines the requirements for the control of functional, surveillance, and special tests. Testing is performed in accordance with appropriate procedures to - demonstrate that safety related equipment and systems will perform satisfactorily in service and malfunctions aie identified and corrected in a timely manner. Records document test results in accordance with the Waterford 3 Quality Assurance Prograni requirements. 1.2 Procedures include criteria for determining when a test is required and how testing activities are to be performed. Test procedures require a review of applicable specifications, test guidelines, and equipment technical manuals in order to determine required test equipment accuracy.
2.0 REFERENCES
2.1 Waterford 3 "In-Service inspection (ISI) Program." 2.2 NUREG-1117, " Technical Specifications." 2.3 10CFR50.59, " Changes, Tests and Experiments." p 2.4 USNRC Regulatory Guide 1.30, August 1972 (which endorses ANSI N45.2.4-1972,
" Quality Assurance Requirements for the Installation, Inspection and Testing of -
Instrumentation and Electrical Equipment.") , 2.5 USNRC Regulatory Guido 1.94, Revision 1, April 1976 (which endorses ANSI N45.2.5-1974, " Quality Assurance Requirements for installation, inspection, and TL 'g of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants.") 2.6 USNRC Regulatory Guide 1.116, Revision O-R, May 1977 (which endorses ANSI N45.2.8-1975, " Quality Assurance Requirements for Installation, inspection and Testing of Mechanical Equipment and Systems;.") 2.7 USNRC Regulatory Guide 1.8, Revision 1-R, September,1975 (which endorses ANSI /ANS 3.1-1978, " Standard for Selection and Training of Personnel for Nuclear Power Plants.") 116
. Waterford 3 Quality Assuranco Program Manual Chapter 11 Test Control Revision 18 2.8 USNRC Regulatory Guide 1.58, Revision 1, September,1980 (which endorses ANSI N45.2.6-1978, " Qualification of Nuclear Power Plant inspection, Examination and Testing Personnel.")
2.9 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls end Quality Assurance for the Operational Phase of Nuclear Power Plants.") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for ensuring the development and implementation of procedures for the Plant Operations staff testing activities. 4.2 Plant Operations Review Committee (PORC) PORC is responsible for the review of test results which result in a change to the Technical Specifications or involve an unreviewed safety question. 117
l Waterford 3 Quality Assurance Program Manual Chapter 11 Test Control Revision 18 5.0 PROCEDURE 5.1 Test Requirements 5.1.1 Test procedures shall be prepared in accordance with Quality Assurance Program requirements and the Technical Specifications and provide, as required, for the following: 5.1.1.1 Requirements and acceptance limits contained in applicable design and procurement documents; 5.1.1.2 Instructions for performing the test; 5.1.1.3 Identification of necessary references; 5.1.1.4 Test prerequisites such as:
- a. Personnel protection and/or access limitation;
- b. Calibrated instruments;
- c. Adequate and appropriate equipment;
- d. Trained, qualified, and licensed or certified personnel; 4
- e. Completeness of item to be tested;
- f. Suitable and controlled environmental conditions;
- g. Provisions for data collection and storage;
- h. Status of the system; and
- i. Protection of connected or adjacent equipment; 5.1.1.5 Criteria for determining accuracy requirements of test equipment; 5.1.1.6 Inspection hold points:
5.1.1.7 Acceptance criteria; 118
Waterford 3 Quality Assurance Program Manual Chapter 11 Test Control Revision 18 5.1.1.8 Methods of documenting or recording test data and results; 5.1.1.9 Provisions for assuring test prerequisites have been met; and 5.1.1.10 Provisions for assuring system arrangement is acceptable after test. 5.1.2 Modified, repaired or replaced items of safety related equipment shall be tested in accordance with the original design and testing requirements or acceptable alternatives. 5.2 Evaluation of Completed Tests 5.2.1 Completed tests and test results shall be documented and evaluated by a qualified individual or group. This evaluation determines that: 5.2.1.1 Test results are adequate and need not be repeated; 5.2.1.2 Recorded data reveals the adequacy of the equipment or system to meet the specified requirements; and 5.2.1.3 Nonconforming conditions are reported, evaluated, and justified or corrected. 5.2.2 Functional and surveillance test results shall be reviewed by the Plant Operations staff to verify that the requirements of the Technical Spec,fications have been met. 5.2.3 The results of special tests that result in a change to the Technical Specifications or involve an unreviewed safety question shall be reviewed by the PORC and the Safety Review Committee in accordance with the Technical Specifications. 5.3 Anomalous Indications If an anomalous indication is observed or detected during a test, the Shift Supervisor and/or Control Room Supervisor shall be notified immediately and the identifying individual shall initiate the required documentation. In the event that the anomalous indication is the result of a failure to meet the acceptance criteria, an investigation shall be performed and the complete test, or that portion which failed, shall be repeated and documented. 119
Waterford 3 Quality Assurance Program Manual Chapter 11
- Test Control Revision 18 5.4 Technical Specifications Surveillance Testing 5.4.1 A Technical Specification Surveillance Testing progra' i irc!uding in-service Inspection shall be established in written approved procedures, or other appropriate documents, to ensure that safety related structures, systems, and components will continue to operate or function within technical specification and other operating license requirements; or, will act to put the plant in a safe condition if they violate requirements.
5.5 Test Records 5.5.1 All test records shall be retained whether the test was completed or not, and whether the results were acceptable or not. Test records, as a minimum, shall identify the: 5.5.1.1 Item tested; 5.5.1.2 . Date of test; 5.5.1.3 Tester or data recorder; 5.5.1.4 Type of test / observation, 5.5.1.5 Results and acceptability; 5.5.1.6 Test procedure; 5.5.1.7 Action taken in connection with any deviations noted; and 5.5.1.8 Person evaluating test results. 6.0 RECORDS None 7.0 ATTACHMENTS None 120
I Waterford 3 Quality Assurance Program Manual Chapter 12 Control of Measurir'g and test Equipment Revision 18 1.0 PURPOSE 1.1 Measuring and test equipment (M&TE) utilized in or related to the operation of safety related structures, systems, and equipment is controlled in accordance with written procedures or instructions. This Chapter defines the requirements for the control of M&TE (including measuring instruments, test instruments, tools, gauges, reference standards, transfer standards, and nondestructive test equipment) used in the measurement, inspection, and monitoring of safety related structures, systems, and components. 1.2 Requirements for the control of M&TE apply to M&TE used by individuals or organizations participating in safety related activities. In addition, they include chemical / radiochemical, and health physics and radiological environmental monitoring M&TE. The extent to which these requirements apply depends upon the nature and scope of work to be performed and the importance of the item or service.
2.0 REFERENCES
2.1 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.") 2.2 USNRC Regulatory Guide 1.30, August 1972 (which endorses ANSI N45.2.4-1972/IEEE Std. 336-1971, " Installation, inspection, and Test Requirements for Instruments and Electrical Equipment During the Construction of Nuclear Power Generating Stations.") 2.3 NUREG-1117, " Technical Specifications," Section 4.02. 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 3.2 MEASURING AND TEST EQUIPMENT (M&TE)- Devices or systems used to calibrate, measure, gage, test, inspect, or control in order to acquire research, development, test or operational data; or to determine compliance with design, specifications, or other technical requirements. M&TE does not include permanently installed operating equipment or test equipment used for preliminary checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation. 121
)
Waterford 3 Quality Assurance Program Manual Chapter 12 Control of Measuring and test Equipment Revision 18 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for ensuring the establishment and implementation of procedures by the Plant Operations staff for the calibration, control, and use of M&TE in safety related activities. 4.2 Directors / Managers Directors and Managers are responsible for the development, maintenance, and implementation of procedures for activities related to calibration, control, and/or use of M&TE in safety related activities. 4.3 Director, Quality 3
~
The Director, Quality is responsible for the review and audit of the program for control of measuring and test equipment and for ensuring the establishment and implementation of procedures for the calibration and control of M&TE employed in safety related activities. 122
i Waterford 3 Quality Assurance Program Manual Chapter 12 Control of Measuring and test Equipment Revision 18 5.0 PROCEDURE 5.1 Calibration 5.1.1 The calibration program shall be designed to ensure the accuracy cf M&TE. The calibration program shall provide for the prompt detection of inaccuracies and timely, effective corrective action. 5.1.2 The calibration program shall provide for procedures which require the following as a minimum: 5.1.2.1 Lists of M&TE under the calibration program shall be developed and maintained; 5.1.2.2 Reference standards, sequential instructions, and the identity of equipment to be used for calibrating M&TE shall be identified. Manufacturers published standard practices, written instructions that accompany purchased equipment, or other approved instructions may be used; 5.1.2.3 M&TE shall be stored, calibrated, and used in environments which will not adversely affect its accuracy; 5.1.2.4 M&TE calibration standards shall have an accuracy of at least four times greater than the required accuracy of the equipment being calibrated. When this is not possible, standards shall have an accuracy that assures the equipment being calibrated will be within required tolerances as specified in the implementing procedure. The basis for the calibration is documented and approved by the cognizant manager; 5.1.2.5 Calibrating standards have greater accuracy than standards being olibrated. Calibrating standards with the same accuracy may be used if it can be shown to be adequate for the application and the basis of acceptance is documented and authorized by responsible management; 5.1.2.6 M&TE shall be calibrated at prescribed intervals to verify the required accuracy. The interval between calibrations is based upon experience, manufacturers' recommendations, inherent stability, purpose or degree of use, and the accuracy required of the equipment. M&TE instruments shall be recalled for recalibration on or before the designated calit' ration date. Reference standards shall be calibrated by qualified organizations; 123 I
Waterford 3 Quality Assurance Program Manual Chapter 12 Control of Measuring and test Equipment Revision 18 5.1.2.7 M&TE shall be calibrated using reference standards whose calibration has a known valid relationship to nationally recognized standards or accepted values of natural physical constants. If no national standard exists, the basis for calibration shall be documented and approved by the cognizant manager; 5.1.2.8 M&TE shall be labeled to indicate its control status. The label shall signify acceptable calibration, and indicate when the next calibration is
. due. When labeling is not practical, an identifying code may be used, if neither labeling or coding is practical, calibration procedures shall require
( monitoring of records to ensure control; 5.1.2 9 M&TE shall be identified to provide traceability to calibration test data. The methods to be used for identifying M&TE shall be specified in applicable procedures; 5.1.2.10 M&TE found to be out of calibration shall be identified as nonconforming and removed from service until corrective measures are taken. Equipment tested or calibrated by the nonconfondng equipment since the last calibration shall be identified and sufficient investigations and reinspections performed to either re-establish the acceptability of the equipment or to confirm the nonconformance. The results of such investigations are documented; 5.1.2.11 M&TE subjected to possible damage shall be identified as nonconforming and removed from service until corrective measures are taken.- M&TE consistently found to be out of calibration shall be identified as nonconforming, removed from service, and reworked or replaced; 5.1.2.12 Lost M&TE shall be treated the same as M&TE found to be out of calibration; and 5.1.2.13 Calibration and control measures may not be required for rulers, tape measures, levels and other such devices, if normal commercial manufacturing practices provide adequate accuracy. 5.1.3 The following measures are taken for M&TE to maintain accuracy and obtain consistent results: 5.1.3.1 Environmental and handling controls are proceduralized; 124
Waterford 3 Quality Assurance Program Manual Chapter 12 Control of Measuring and test Equipment Revision 18 5.1.3.2 Personnel are trained and qualified; 5.1.3.3 Calibration status is checked before use; 5.1.3.4 Damaged M&TE is documented and recalibrated; and 5.1.3.5 Use is limited to authorized personnel. 5.2 Selection of M&TE Selection of measuring and test equipment shall be controlled to assure that such items are of proper type, range, accuracy, and tolerance to accomplish the function of determining conformance to specified requirements. 5.3 Documentation and Records 5.3.1 An index or log shall be maintained to identify: 5.3.1.1 Each piece of M&TE; 5.3.1.2 The individual and date of the last calibration; 5.3.1.3 The calibration interval; and 5.3.1.4 The items inspected, tested, examined, or calibrated through the calibration program. 5.3.2 Equipment and identification lists, procedures, calibration records, personnel qualifications, and nonconformance reports shall be retained as required by codes, standards, and specifications. 6.0 RECORDS None 7.0 ATTACHMENTS None 125 l
Waterford 3 Quality Assurance Program Manual Chapter 13 Handling, Storage, Packaging, and Shipping Revision 18 1.0 PURPOSE Safety related items are handled, stored, cleaned, packaged, and shipped in a manner to prevent deterioration, contamination, damage, or loss of identification. Procedures are provided for handling, cleaning, storing, maintaining while stored, and shipping specific items, equipment or material.
2.0 REFERENCES
2.1 10CFR71, Packaging and Transportation of Radioactive Material 2.2 49 CFR USDOT, Parts 171 through 178 2.3 USNRC Regulatory Guide 1.37, Revision 2 (which endorses ANSI N45.2.1-1973," Quality Assurance Requirements for Cleaning Fluid Systems and Associated Components of Water Cooled Nuclear Plants") 2.4 USNRC Regulatory Guide 1.38, Revision 2 (which endorses ANSI N45.2.2-1972, " Quality Assurance Requirements for Packaging, Shipping and Receiving, Storage and Handling of items for Water Cooled Nuclear Plants") 2.5 USNRC Regulatory Guide 1.39, Revision 2, September 1977 (which endorses ANSI N45.2.3-1973, " Housekeeping Requirements for Water Cooled Nuclear Power Plants") 2.6 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 126
Waterford 3 Quality Assurance Program Manual Chapter 13 Handling, Storage, Packaging, and Shipping Revision 18 4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for: 4.1.1 ' Ensuring controls are established for handling, shipping (radioactive waste and spent fuel), cleaning, preservation, housekeeping, and preventive maintenance of safety related items (after installation); 4.1.2 The establishment and implementation of procedures required to perform preventive maintenance of items in storage and those that are installed; 4.1.3 Handling, preservation, and cleanliness of parts and components i released for operation; 4.1,4 The establishment of cleanliness classifications (or zones) when opening components or systems for maintenance purposes which require specific internal cleanliness levels; 4.1.5 Flushes or chemical cleaning of plant systems; 4.1.6 Assuring that systems and components are appropriately placed and maintained in lay-up condition, when required; 4.1.7 Handling and storage of nuclear fue!; and 4.1.8 Housekeeping inside of the radiation controlled area and for the on-site handling, storage, packaging, cleaning and release for shipping to a transit carrier of radioactive wastes, and is responsible for providing technical expertise to assist in the on-site handling, storage, packaging, cleaning and release for shipping to a transit carrier of radioactive material. 127
V/aterford 3 Quality Assurance Program Manual Chapter 13 Handling, Storage, Packaging, and Shipping Revision 18 4.2 Director, Plant Modification and Construction The Director, Plant Modification and Construction is responsible for: 4.2.1 Assuring the establishment and/or implementation of controls for handling safety related items released for construction; 4.2.2 The establishment and/or implementation of procedures required for handling and the maintenance of items withdrawn from storage and those that are installed but are not yet released to plant operations; and 4.2.3 The establishment of required cleanliness classifications (or zones) when opening components or systems for modification purposes which require specific internal cleanliness levels. 4.3 Director, Quality E. The Director, Quality is responsible for performing audits, and surveillances of Waterford 3 activities associated with handling, shipping, storage, and preventive maintenance of safety related items in storage. 4.4 Vice President, Operations Support The Vice President, Operations Support is responsible fer: 4.4.1 Handling, cleanliness, storage, preservation and inspection of items within storage and warehouse areas in accordance with Quality Assurance Program requirements; and 4.4.2 Packing and shipping outgoing items (except radioactive waste and spent fuel) and for housekeeping within the receiving and warehouse areas. } 128
Waterford 3 Quality Assurance Program Manual Chapter 13 Handling, Storaga, Packaging, and Shipping Revision 18 5.0 PROCEDURE 5.1 Material Handling, Stoiage, Packaging, and Shipping 5.1.1 Under normal circumstances, the manufacturer's instructions or recommendations shall be followed and shall be implemented to maintain materialintegrity and protection. Deviations from manufacturer's recommendations shall be justified by an engineering evaluation and documented. Where documented manufacturer instructions do not exist, engineering shall establish and document appropriate handling, storing, cleaning, packaging, and shipping instructions. 5.1.2 Personnel performing handling, storage, packaging, and shipping activities shall be knowledgeable of the work to be performed and the procedures employed, 5.1.3 When required for particular items, special equipmeru es, special protective environments shall be specified, provided, and their existence verified. 5.1.4 When required for critical, sensitive, perishable, or high-value articles, specific procedures shall be developed to ensure that proper handling, storage, packaging, shipping, and preservation methods are used. 5.2 Radioactive Material Shipping Containers The containers used for shipping radioactive material shall be in accordance with 49 CFR Parts 171 through 178 and 10CFR71. If a USNRC licensed container is required then the container will be leased from a USNRC licensed supplier of containers. 5.3 Consumables Procedural controls shall be established for the control of chemicals, reagents, fuels, (excluding nuclear fuel) oil, lubricants, and other consumables to assure proper storage, handling, utilization, and disposition. 129 o
Waterford 3 Quality Assurance Program Manual Chapter 13 Handling, Storage, Packaging, and Shipping Revision 18 l 5.4 Material Handling Equipment Procedures shall be established for the testing of special handling tools and equipment such as cranes, forklifts, and cables. Procedurcs for material handling equipment shall establish requirements for inspections, frequency of inspections, and type of inspections. Lifting equipment used for handling safety related items shall have their rated capacity clearly marked. 5.5 Marking Instructions for marking and labeling items during packaging, shipment, handling, and storage shall be established as necessary to adequately identify, maintain, and preserve the items, including indication of the presence of special environments or the need for special controls. 5.6 Preventive Maintenance 5.6.1 Preventive maintenance on items and equipment in storage shall be procedurally controlled and shall be in accordance with manufacturers recommendations, applicable codes, regulations, and standaro. Deviations from these requirements shall be documented and an engineering justification provided. 5.6.2 Material receiving and storage areas shall be situated and controlled to minimize the possibility of damage, loss, loss of identification, or deterioration, from tne time of receipt until the material is released for installation or use. 5.7 Records Applicable procedures, instructions, and manufacturers information shall be prepared, reviewed, released, and controlled in accordance with applicable codes, regulations, and standards. 6.0 RECORDS None 7.0 ATTACHMENTS None 130
Waterford 3 Quality Assurance Program Manual Cnapter 14 Inspection, Test and Operating Status Revision 18 1.0 PURPOSE / Inspection, test, and operating status of safety related structures. systems, and components are conspicuously indicated in accordance with written procedures, to assure that required inspections and tests are not inadvertently bypassed, or to assure that equipment under a controlled status is not inadvertently operated.
2.0 REFERENCES
None 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES
- 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for the development and maintenance of procedures which define the responsibilities and controls required for identifying the test and operating status of installed safety related equipment, components, and systems.
4.2 Director, Quality 2
~
The Director, Quality is responsible for the development and administration of procedures which define the responsibilities and controls required for inspections of safety related plant equipment, components, and systems, s 131
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I Waterford 3 Quality Assurance Program Manual Chapter 14 Inspection, Test and Operating Status Revision 18 5.0 PROCEDURE 5.1 Inspection and Test Status - 5.1.1 Pr9cedures shall require that the status of inspections and tests performed on systems, structures, and components at Waterford 3 be indicated by the use of markings such as stamps, tags, labels; or routing cards, work authorization packages or other suitable means. 5.1.2 Status indicators shall be placed either on the items or in documents traceable to the items where it is necessary to assure that required inspections and tests are performed and to assure that items which have not passed the required inspections and tests are not inadvertently installed, used, or operated. 5.1.3 Status indicators shall provide for indicating the operating status of systems and components at Waterford 3, such as by tagging valves and switches, to prevent inadvertent operation. 5.1.4 Inspections and tests shall be documented and shall indicate acceptability or cause for rejection. 5.1.5 Procedures shall require documentation of authorization for the application or removal of status indicators. 5.1.6 In cases where documentation of required inspections or tests is not available, the associated equipment or materials shall be considered nonconforming. Until suitable documentary evidence is available to prove that the equipment or material is in conformance, affected systems shall be evaluated for operability in accordance with the Waterford 3 Technical Specifications. 5.2 Operating Status 5.2.1 Turnover checklists, status boards, diagrams, logs, or other tracking methods shall be developed and maintained to the extent necessary to assure effective communication concerning plant status with Control Room personnel. 5.2.2 Plant instructions that require equipment to be reraoved from service for maintenance, testing, or modification shall specify the affected equipment to ensure that the appropriate clearance is issued. Control Room authorities shall be informed of equipment changes. 132
l Waterford 3 Quality Assurance Program Manual Chapter 14 Inspection, Test and Operating Status Revision 18 5.2.3 The Technical Specifications define operability requirements for safety related structures, systems, and components for the safe operation of the plant, including provisions for periodic tests and inspections of various instruments, structures, components, systems, or parts of systems. The status of equipment / systems declared inoperable with respect to Technical Specification requirements shall be maintained by the Shift Supervisor / Control Room Supervisor. 5.2.4 Limited operating functions and operating parameters or temporary alterations that are installed, removed, or utilized shall be identified on the system or equipment and shall be controlled by approved procedures. These procedures shall include the requirements for an independent verification by either a second person or by a functional test to determine operability. Documented evidence of the current status of such temporary modifications shall be provided. 5.2.5 Equipment shall be returned to service in accordance with the Waterford 3 Technical Specifications. 5.3 Documentation and Records Procedures shall be established to define the requirements for the development and maintenance of the documentation and records of the inspection, test and operating status of the plant. 6.0 RECORDS None 7.0 ATTACHMENTS None 133
Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Meterials, Parts Or Components Revision 18 1.0 PURPOSE 1.1 The Waterford 3 Quality Assurance Program requires the control of nonconforming materials, parts or components. This program controls the identification, documentation, segregation, review, disposition, notification to affected organizations, repair, rework, retest, and reinspection of nonconforming materials, parts, components, activities, and services. 1.2 Nonconforming materials, parts, components, structures and activities are controlled such that reliance on an unresolved nonconforming item to perform a safety function is riot allowed. _18 l
2.0 REFERENCES
2.1 Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants")
- 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4.
4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for the nonconformance control system at Waterford 3 for material, parts, and components under plant jurisdiction. Additionally, the General Manager, Plant Operations is responsible for approving nonconformances dispositioned " repair" or "use-as-is" 4.1.1 Plant Operations Review Committee The PORC is responsible for reviewing safety related nonconformances dispositioned " repair" and "use-as-is" and recommending approval to the General Manager, Plant Operations. 134 1 i e- - -
Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, Parts Or Components Revision 18 4.2 Director, Design Engineering i The Director, Design Engineering is responsible for reviewing nonconformances ' with recommended dispositions of " repair" or "use-as-is", and for evaluating and processing changes to resulting design drawings The Director, Design Engineering is also responsible for dispositioning other nonconformances assigned to his organization. Q,1 & 8 l 4.3 Director, Nuclear Safety and Regulatory Affairs
- ~ ~
The Director, Nuclear Safety and Regulatory Affairs is responsible for: 4.3.1 Ir.:tiating Licensee Evont Reports under 10CFR50.73; @&Z 4.3.2 The on-site Independent Technical Review fun: tion which includes providing a random independent review of nonconformance dispositions and closures during the operations phase, and 4.3.3 The screening, evaluation, tracking, and reporting of nonconformances to the NRC as required by 10CFR21. 4.4 Director, Quality E The Director, Quality is responsible for conducting reviews or assessments to monitor satisfactory implementation of the Corrective Action Program at Waterford 3.
- 4. 5 Waterford 3 Personnel All Waterford 3 personnel are responsible for identifying and reporting nonconforming items on the appropriate nonconformance document (Condition Report).
135 9
Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, Parts Or Components Revision 18 5.0 PROCEDURE The following actions are required when safety related materials, parts, components, systems, activities or services do not conform to drawings, specifications, workmanship standards or other applicable documents: 5.1 Identification 5.1.1 Nonconformances observed in the course of inspection, testing, operations, maintenance, modifications, etc. shall be documented, in cases where required documentary evidence is not available that items have satisfactorily passed - necessary inspections and tests, the associated hardware shall be considered nonconforming. 5.1.2 Nonconformances shall be clearly and thoroughly described, documented and controlled. 5.2 Notification 5.2.1 Organizations affected or potentially affected by a nonconforming item shall be notified upon identification of the nonconformance. 5.2.2 Until suitable documentary evidence is available to show the affected material or equipment is in conformance, affected systems shall be evaluated for operability in accordance with the Waterford 3 Technical Specifications and other license agreements (i.e., Equipment Qualification program). 5.2.3 If a reportable event is identified pursuant to applicable NRC regulations, required internal and external notification and documentation shall be initiated as required by procedures. 5.3 Segregation 5.3.1 Nonconforming items shall be segregated, when practical, by placing them in a clearly identified and designated hold area until properly dispositioned. 5.3.2 When segregation is impractical or impossible due to physical conditions such as size, weight, or access limitations, other precautions shall be employed to preclude inadvertent use of a nonconforming item.
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136
Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, Parts Or Components Revision 18 5.4 Disposition A technical evaluation shall be made to determine whether a singular nonconforming condition exists or if the nonconformance represents a generic condition. The evaluation shall also determine whether the nonconforming item may be accepted, rejected, reworked, repaired, used-as-is, or conditionally released. The action to be taken shall be documented and an implementation schedule shall be generated as necessary. A description of changes, waivers, or deviations, that are accepted shall be documented to record the change end denote the as-built condition. 5.5 Reinspection 5.5.1 Reworked, repaired, or replaced items shall be reinspected and retested in accordance with the original inspection and test requirements or acceptable alternatives. Nonconforming items shell be reinspected per requirements established by the technical evaluation. The rework, repair, replacement, and inspection or test results shall be documented. 5.5.2 Rejected items shall be identified by tagging, and where practical, removed from the area to preclude further use or installation. 5.5.3 Final alternative action may be to return rejected material and equipment to the supplier or to dispose. Upon satisfactory reinspection and completion of associated documentation, the initiating nonconformance document shall be 3l closed out. 5.6 Records 5.6.1 Documentation of nonconforming materials, parts or components shall be maintained in accordance with Entergy Operations, Inc. quality assurance records management procedures. Information contained in the documentation shall include but may not be limited to: 5.6,1.1 Disposition of the nonconformance; 5.6.1.2 Signature approval for disposition; 5.6.1.3 Identification of the nonconforming item; 137
Waterford 3 Quality Assurance Program Manual Chapter 15 Nonconforming Materials, Parts Or Components Revision 18 5.6.1.4 Description of the nonconformance; and ' 5.6,1.5 Inspection requirements. 6.0 RECORDS None 7.0 ATTAL;iMENTS : None 138
Waterford 3 Quality Assurance Program Manual Chapter 16 Corrective Action Revision 18 1,0 PURPOSE The Corrective Action Program assures that adverse conditions are promptly identified ar;d corrected.
2.0 REFERENCES
2.1 10CFR50, Appendix B, Criterion XVI," Corrective Action" 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") ' 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES
- 4.1 General Manager, Plant Operations j 4.1.1 The General Manager, Plant Operations is responsible for:
4.1.1.1 Designating the chairman of the Condition Review Board; gl 4.1.1.2 Analyzing conditions for trends regarding equipment failure, and publishing a quarterly trend report; 4.1.1.3 Performing immediate notification determinations and making appropriate notifications in accordance with 10CFR50.72 for identified adverse conditions; and 4.1.1.4 Performing reportability determinations and making appropriate notifications in accordance with 40CFR for identified environmental adverse conditions. 139
Waterford 3 Quality Assurance Program Manual Chapter 16 Carrective Action Revision 18 4.2 Director, Nuclear Safety and Regulatory Affairs I 4.2.1 The Director, Nuclear Safety and Regulatory Affairs is responsible for: 4.2.1.1 Assuring the performance of reportability reviews of Condition Ql Reports (CRs) in accordance with 10CFR50.73 and 10CFR21; and
- 4.2.1.2 Oversight of t e administration of the Condition Report process, g,[&g root cause ana,ysic and trend programs.
4.3 Director, Quality
--7&9l 9
4.3.1 The Director, Quality is responsible for: 4.3.1.1 Requesting or ensuring periodic independent assessments of the corrective action program to ensure that the process elements are adequately implemented; {&9 4.3.1.2 Auditing and reviewing the Corrective Action Program to ensure acceptable implementation; and el 4.3.1.3 issuing Stop Work Orders when conditions warrant. 4.4 Directors and Managers 4.4.1 Directors and Managers are responsible for: 4A.1.1 Assuring that procedures are developed and maintained to implement the Corrective Action Program; 4.4.1.2 Assuring that personnel are familiar with the requirements of the Corrective Action Program; and 4.4.1.3 Assuring departmental responsiveness to the Corrective Action Program, through problem identification and resolution. 140
Waterford 3 Quality Assurance Program Manual Chapter 16 Correctivo Action Revision 18 I 4.5 In Hout,e Events Analysis Supervisor 4.5.1 The In House Events Analysis Supervisor is responsible for: 4.5.1.1 Administering il ) Condition Report Process; and 6 4.5.1.2 Administering a root cause investigation and trend analysis progmm for corrective action documents and for publishing a w:itten or electronic trend report. 4.0 Safety Review Committee The Safety Review Committee (SRC) is responsible for maintaining oversight and assessing the effectiveness of the Corrective Action Program at Waterford 3. The ) SRC ." sessment shallinclude, at a minimum, the review of the trend reports and signha ant adverse conditions. 4.7 Condition Review Board The CRB is responsible for reviewing Controlled Maintenance Condition Identifications and Ccndition Reports to ensure adverw conditions receive the proper significance classification, priority, and dedication of resources. 4.8 Waterford 3 Personrial 6 Waturford 3 personnel are responsible for promptly identifying and documenting adverse conditions on correctivo action ducuments. Waterford 3 personnel are also I responsible for reccamending that an activity be stopped if the specific work is not being done in accordance with approved procedures, drawings, specifications, or regulatory requirements. 141 t-
Walerford 3 Quality Assurance Program Manual Chapter 16 Corrective Action Revision 18 5.0 ' PROCEDURE 5.1 Procedural Requirements 5.1.1 Procedures and instructions for correcting adverse conditions shall include provisions for: 5.1.1.1 Defi.iancy identification and immediate action: 5.1.1.2 Review for impact and assignment; 5.1.1,3 Investigate and analyze; 5.1.1.4 Corrective action planning and implementation; 4 5.1.1.5 Prioritization of corrective action; 5.1.1.6 Verification of completion; and 5.1.1.7 Verification of effectivenese
- 5.1.2 Implementing procedures shall assign responsibility to each individual employed by Entergy Operations, Inc. to promptly identify adverse conditions.
5.1.3 Implementing procedures shall be developed to ensure that each ! individual has the appropriate corrective action documents and guidance necessary to properly document adverse conditions. , 5.1.4 Procedures shall also address corrective actions identified external to Entergy Operations, Inc. and through internal programs such as trend analysis.
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5.2 Stop Work Order (SWO) 5.2.1 When an individual determines that specific work is not being performed in accordance with approved drawings, specifications, procedures, or regulatory l requirements, the individual should recommend to the appropriate supervisor, that the activity be stopped until adequate corrective action is taken. The Director, Quality shall be notified if the activity does not cease, e g 5.2.2 The Director, Quality or his designee should verbally request that the adverse activity be stopped at the next safe stopping point. 142 )
Waterford 3 Quality Assurance Program Manual Chapter 16 l Corrective Action Revision 18 5.2.3 If work is not stopped as requested, a Stop Work Order shall be issued by _ the Director, Quality or his designee, to the organization responsible for n_ot 9l terminating the work that is adverse to quality. Work shall not proceed until the - Stop Work Order is released by the Director, Quality. 9l 5.3 Contractor Responsibility Contractors performing services or activities pertaining to safety related systems, structures, or components shall identify adverse conditions according to this manual or their Entergy Operations, Inc. approved QA Program. 5.4 Records Corrective action reports and supporting documentation shall become quality assurance records. 6.0 RECORDS None 7.0 ATTACHMENTS None _ = 143
b i Waterford 3 Quality Assurance Program Manual Chapter 17 Quality Assurance Records Revision 18
- 1.0 PURPOSE
- 1.1 Quality assurance records are those completed records that furnish documented evidence of the quality of items or of activities affecting quality and those records required by the Technical Specifications. This chapter defines requirements for the control of quality assurance records.
2.0 REFERENCES
4 2.1 USNRC Regulatory Guide 1.88, Revision 2, October 1976 (which endorses ANSI N45.2.91974, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants") 2.2 USNRC Regulatory Guide 1.33, Revision 2, February 1978 (which endorses ANSI N18.7-1376, " Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants") 3.0 DEFINITIONS J 3,1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Director, Site Support , The Director, Site Support is responsible for: 5&6" 4.1.1 Assuring the preparation of procedures for the execution of a document
- control and records storage program; and 4.1.2 Providing support for the records management program.
4.2 Directors / Managers
- Directors and managers are responsible for preparing and effectively implementing orocedures which fulfill the applicable requirements of this chapter and applicable h codes, regulations, and standards.
144
i Waterford 3 Quality Assurance Program Manual Chapter 17 Quality Assurance Records Revision 18 i i 5.0 PROCEDURE 5.1 Procedural Controls !
- 5.1.1 Procedures shall be developed for processing, preservation, retrieval, transmittal, inspection, correction, retention, storage, and disposition of quality
- assurance records; and, as a minimum, shall address the following
1 5.1.1.1 Quality assurance records which are to be generated in accordance with 1 applicable procedures, codes, standards, and regulations shall be specified; d 5.1.1.2 Quality assurance records shall be legible, completely filled out with all applicable data, reproducible, and adequately identifiable to an item or activity; and 5.1.1.3 Quality assurance records shall be validated by stamping, initialing, signing, or otherwise authenticating and dating by authorized personnel. 5.2 Types of Records 4 l 5.2.1 Quality assurance records shall include, but are not limited to, the following: 1 5.2.1.1 Design and construc', ion documents, such as:
- a. Design drawings, specifications and work packages; i
- b. Results of reviews, inspections, tests, surveillances and audits;
- c. Procurement documents; and
- d. Material certifications, etc.
5.2.1.2 Operational documents, such as:
- a. Operating logs; b .- Maintenance and modification records;
- c. Reportable occurrences;
- d. Results of reviews, inspections, audits, tests, and material analysis;
- e. Personnel qualification records; 145
Waterford 3 Quality Assurance Program Manual Chapter 17 Quality Assurance Recotds Revision 18 i i
- f. Procedures and equipment qualification records;
- g. Procurement documents and specifications;
- h. Calibrat on records; and I. Nonconformance and a oMe action documents.
5.3 Corrections and Supplements Quality assurance records required by procedures, codes and regulations shall be corrected or supplemented only in accordance with written procedures which shall provide for appropriate review and approval by the originating organization. The correction or supplement shall include the date and the identification of the person authorized to issue each correction or supplement. 5.4 Retention and Storage of Records 5.4.1 Records shall be maintained current and complete in facilities that provide a suitable environment to minimize deterioration and to prevent damage or loss. 5.4.2 Quality assurance records stored on an interim basis shall be stored and controlled in a manner that protects them from damage or loss until they are submitted to permanent storage. Procedures shall define the interim storage requirements. 5.4.3 Procurement dccuments shall provide requirements for records storage and maintenance by contractors and suppliers when the required records are not submitted to Entergy Operations, Inc. 5.4.4 When quality assurance records have been lost, a search for copies shall be made to replace the lost records. If copies cannot be found, the lost records may be reconstructed if sufficient evidence exists to substantiate the reconstruction. If reconstruction is not possible, the original item or activity depicted by the record shall be evaluated and, when necessary, the activity shall be repeated and/or items replaced or requalified. 5.4.5 Quality assurance records shall be identifiable and retrievable. Procedures for retendon and storage shall include requirements for maintenance, preservation, and protection against destruction by causes such as fire or flooding. Procedures shall also provide for the control of, access to, and accountability of records. 146
Waterford 3 Quality Assurance Program Manual Chapter 17 Quahty Assurance Records Revision 18 5.4.6 A satisfactory alternative to the establishment of a single record storage facility is the maintenance of a duplicate copy of records in a remote location. Where duplicate storage is employed, measures shall be taken to minimize the risk of damage or destruction from natural disasters, environmental extremes, or vermin. 5.4.7 Listings or indexes of the required records shall be developed and maintained. Retention times for records and location of record copies shall be indicated in a records index. Records may be retained by the suppliers and contractors and may include the following: 5.4.7.1 Permanent records -
- a. Design calculations;
- b. Verifications of design calculations; and
- c. Technical evaluations, analyses, and reports.
5.4.7.2. Non permanent records -
- a. Quality Assurance audit reports;
- b. Vendor audit reports; and
- c. . Pre award quality assurance surveys.
5.4.8 Quality assurance records that are received from outside organizations shall be revie. .ed for technical adequacy, completeness, and legibility and their acceptance documented. Identified record deficiencies shall be documented for resolution. 5.4.9 Procurement documents shall specify the retention requirements when a manufacturer, supplier, consultant, or contractor are to retain radiographs, and when they are to transmit such radiographs to Entergy Operations, Inc. 6.0 RECORDS None _ 7.0 ATTACHMENTS None 147
Waterford 3 Quality Assurance Program Manual Chapter 18 ! Audits Revision 18 1.0 PURPOSE 1.1 Audits are performed to verify compliance with the Quality Assurance Program requirements and to determine the program effectiveness. This chapter defines the requirements of the Waterford 3 Quality Assurance Audit Program.
2.0 REFERENCES
2.1 Waterford 3 Quality Assurance Program Manual, Chapter 16," Corrective Action" 3.0 DEFINITIONS 3.1 See Chapter 2 - Attachment 7.4. 4.0 RESPONSIBILITIES 4.1 Vice President, Operations Support The Vice President, Operations Support is responsible for planning, scheduling and conducting audits and surveillances of suppliers, contractors, and EOl 7 shared services which provide mate n s, components, parts and services to be used in safety related applications. 4.2 Director, Quality 8 The Director, Quality is responsible for planning, scheduling, and conducting audits of the Waterford 3 Quality Assurance Program, and its implementing procedures. 4.3 Management of the Audited Organization Management of the audited organization is responsible for investigating audit findhgs, scheduling corrective action including measures to prevent recurrence, and notification of the Quality Assurance organization in writing, of action planned or taken. 148
Waterford 3 Quality Assurance Progr ,m Manual Chapter 18 Audits Revision 18 5.0 PROCEDURE . t 5.1 Audit Program j 5.1.1 The objectives of the audit program are: 5.1.1.1 To ensure that the Waterford 3 Quality Assurance Program requirements are established in appropriate documents; 5.1.1.2 To verify on a regular basis by examination and evaluation of objective } evidence that established requirements, methods, procedures, and instructions are being implemented;
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5.1.1.3 To assess the effectiveness of the Quality Assurance Program; 5.1.1.4 To identify program weakness and nonconformances; and 5.1.1.5 To verify correction of conditions adverse to quality identified during an audit. 5.1.2 Audits shall be performed in accordance with this manual, management requirements, and in areas where 1_0CFR50, Appendix B, requirements are being implemented. These areas shall include, as a minimum, the safety related 1 activities associated with: 5.1.2.1 Operation, maintenance, and modification; 5.1.2.2- The preparation, review, approval, and control of designs, specifications, procurement documents, instructions, procedures, and drawings; ' 5.1.2.3 Receipt inspection; 5.1.2.4 Indoctrination and training programs; 5.1.2.5_ Implementation of opera *hg and ;est procedures; 5.1.2.6 Calibration of measuring and test equipment;
-5.1.2.7 Interface control among Entergy Operations, Inc. organizations and contractors / consultants; and 5.1.2.8- Procurement, vendors, manufacturers, and suppliers.
149
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Waterford 3 Quality Assurance Program Manual Chapter 18 Audits Revision 18 5.1.3 in addition to the above, audits shall be conducted of other activities defined as a special scope quality assurance related activity in this manual. 5.2 Safety Review Committee (SRC) Audit Program 5.2.1 The following audits of unit activities shall be performed under the cognizance of the SRC. These audits shall encompass: 5.2.1.1 The conformance of unit opeiation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. 5.2.1.2 The performance, training, and qualifications of the entire unit staff at least once per 12 months, 5.2.1.3 The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months. 5.2.1.4 The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50, at least once per 24 months. 5.2.1.5 Any other area of unit operation considered appropriate by the SRC or the Vice President Operations. 5.2.1.6 The fire protection programmatic controls including the implemenSng procedures at least once per 24 months by qualified licensee QA personri9l. 5.2.1.7 The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.
-5.2.1.8 The Primary Coolant Sources Outside Containment Program at least once per 24 months.
5.2.1.0 The In-Plant Radiation Monitoring Program at least once per 24 months. 5.2.1.10 The Secondary Water Chemistry Program at least once per 24 months. 150 i
Waterfard 3 Quality Assurance Program Manual Chapter 18 Audits Revision 18 5.2.1.11 The Post-Accident Sampling Program at least once per 24 months. 5.2.1.12 The Basemat Monitoring Program at least once per 24 months. 5.2.1.13 The radiological environmental monitoring program and the results thereof at least once per 12 months. 5.2.1.14 The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months. 5.2.1.15 The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. 5.2.1.16 The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months. 5.3 Pre-Audit Activities 5.3.1 Quality Assurance shall provide an audit notification letter signed by the Director, Quality or appropriate supervisor. The letter shall be submitted to the 8l organization to he audited, and shallidentify the audit dates and the areas to be ~ audited. 5.3.2 Quality Assurance audits shall be planned and conducted in accordance with approved procedures. Audit planning shallinclude preparation of checklists or procedures that will ensure consistency and completeness in the audit evaluation. The Audit Checklist shall be a guide and shall not restrict the audit scope when additionalinvestigation is needed. 5.3.3 Unresolved items noted during previous audits shall be reviewed prior to i checklist preparation and included for re-audit as appropriate. 5.3.4 The organization being audited shall make every effort to have personnel E.ad other necessary resources available for the scheduled audit. Any change in scope or schedule of the audit is coordinated with the organization being audited. 5.3.5 Quality Assurance should determine the need for scheduling a pre-audit conference with the organization being audited. 151
l Waterford 3 Ouahty Assurance Program Manual Chapter 18 Audits Revision 18 L 5.4 Audit Performance 5.4.1 Audits should include objective evaluation of work areas, activities, and processes including a review of selected atsociated documents and records. Audits shall also include an objective evaluation of safety related practices, procedures, and instructions; the effectiveness of their implementation; and compliance with quality assurance policies. 5.4.2 Any potential problem areas identified during the audit shall be immediately brought to the attention of the management of the responsible organization. 5.5 Audit Personnel 5.5.1 Audits shall be conducted by qualified auditors who are experienced, traincd, and familiar with the requirements and standards applicab!e to the area or activity being audited. 5.5.2 Audit team members shall be independent of any direct responsibilities for the activities which they audit. 5.5.3 Lead Auditors shall participate in an auditor training program and maintain proficiency through training, review and study of codes 6nd standards related to quality assurance, or through active participation in the audit program. 5.5.4 Lead auditors shall be certified. Audit teams may include consultants or technical specialists as auditors under the supervision of a lead auditor. 5.6 Post-Audit Activities 5.6.1 Upon completion of an audit, the audit team shall determine the need for and coordinate a post-audit conference, which shallinclude the presence of those individuals with the authority to effect corrective action (if required) for findings identified during the audit. 5.6.2 Audit findings shall be presented in written form. Written acknowledgment should be obtained from the audited organization for each audit finding. 152 l o
I Waterford 3 Quality Assurance Program Manual Chapter 18 8 Audits Revision 18 5.6.3 Formal audit reports shall be issued within 30 working days of the post-audit conference or completion of the audit. Audit reports required by the SRC Audit Program shall be issued within 30 days. Distribution includes: 5.6.3.1 The Director, Quality; 8l 5.6.3.2 The manager of the audited organization; 5.6.3.3 The SRC (receives only operations audit reports); 5.6.3.4 The manager (s) responsible for corrective action; and 5.6.3.5 The Vice President, Operations por audit reports required by the SRC ] Audit Program). 5.6.4 It shall be the responsibility of the audited organization to review the audit report and to take action as necessary to ensure that corrective action is accomplished in a timely manner. 5.6.5 The Director, Quality, supervisor, or the audit team leader shall be responsible
-Pl for follow up action (including re audits) as required to ensure that corrective action has been taken anc' !s effective. Audit findings shall be documented in corrective action documents and noted in the audit report. Corrective actions and re-audits shall be documented with reference to the original audit.
5.7 Corrective Action Plan 5.7.1 If, after investigation or evaluation of an audit finding, it is determined that a violation of specified requirements has occurred, the required response shall provide a corrective action plan which contains at a ndn! mum the requirements of QAPM, Chapter 16 and inc:ade the following, as applicabic-5.7.1.1 The methods and, when applicable, the results of investigations or evaluations used to identify all affected hardware and software items; 5.7 1.2 . The methods and, when applicable, the results of investigations or evaluations used to determine the root cause(s); 5.7.1.3 The action taken, or to be taken, to correct each affected hardware and software item; 153 A
.Waterford 3 Quality Assurance Program Manual Chapter 18 Audits Revision 18 5.7.1 A The actions taken, or to be taken, to preclude the recurrence of the violation; 5.7.1.5 The scheduled completion date(s) for each of the applicable items identified above; and 5.7.1.6 The status of each uncompleted item at the time of response submittal.
5.7.2 In cases where the presented objective evidence does not support the conclusion that a violation of specified requirements has occurred, the response shall clearly state that fact, along with complete justification and objective evidence for the response. 5.7.3 At any time when required response dates or proposed implementation dates < cannot be reasonably met, the audited organization shall develop a response, advising the Director, Quality or appropriate supervisor of the new response 8l date. 5.8 Aanalysis of Audit Data Audit data shall be analyzed by the Director, Quality or appropriate supervisor, who shall report any significant quality assurance problems, including the need for re-audit of deficient areas, to the Director, Quality and the Vice President, 6 & 8 Operations. 5.9 Process Surveys (Surveillances) 5.9.1 Entergy Operations, Inc. Quality Assurance may conduct process surveys (surveillances) to verify that an item or activity conforms to specified requirements. These process surveys (surveillances) shall supplement regular audts. They are usually limited in scope, and usually involve: 5.9.1.1 A specific activity being performed; 5.9.1.2 A procedure or portion of a procedure; or 5.9.1.3 A specific area w' a a program. 5.9.2 - Distribution of process survey (surveillance) reports include the Director, Quality 8 l ~ and the affected organization. 154
Waterford 3 Quality Assurance Program Manual Chapter 18 Audits Revision 18 5.10 Records Audit records shall include audit plans, reports, written replies, and documentation
- of completion of correcti.e action. Other documentation, such as checklists, may be retained as quality assulance records as necessary to support audit results.
6.0 RECORDS None 7,6 ATTACHMENTS
.i None b(
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