ML20126B632

Rev 2 to QA Program Manual

ML20126B632
Person / Time
Site:	Waterford
Issue date:	11/01/1992
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20126B630	List: ML20126B625 ML20126B632
References
NUDOCS 9212220155
Download: ML20126B632 (146)

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{{#Wiki_filter:.. WATERFORD._3 gEntergy. TABLE OF CONTENTS-P2V./2.0 QUALITY ASSURANCE R-TYPE:- C1.31' , Operations PROGRAM MANUAL- -Page-1 of 1 Ci-TITLE-P2 VISION-DATE' Forward and Policy _ Statement 1.0- -.04/22/92 Chapter 1- -Organization 2.0 11/01/92 Chapter 2 Quality Assurance Program 2.0 11/01/92' Chapter 3 Design Control 0.0. 04/01/91-Chapter 4 Procurement Document control 1.0 04/22/92 Chapter 5 Instructions, Procedures, and 1.0 04/22/92 Drawings Chapter 6 Document Control 2.0 11/01/92' Chapter 7 Control of Purchased Materials, 2.0 11/01/92 Equipment, and Services Chapter 8 Identification-and Control of Materials, 1.0 04/22/92 Parts, and Components Chapter 9 Control of Special Processes 1.0 04/22/92 ~ Chapter 10 Inspection 2.0 ~11/01/92- .l Chapter 11 Test Control 0.0 04/01/91-- Chapter 12 Control of Measuring and Test Equipment 1.0 04/22/92 Chapter 13 Handling, Storage, Packaging and Shipping 1.0 04/22/92 d ~ hapter 14 Inspection, Test, and Operating Status 0.0~ 04/01/91-C Chapter 15-Nonconformance Materials, Parts or 2.0 11/01/92 Components-Chapter 16 Corrective Action '2.0 11/01/92 -Chapter 17 Quality Assurance Records 1.0 04/22/92 Chapter-18 Audits 1.0 11/01/92-Appendix A Regulatory Guidance Document 2.0 11/01/92. 'Appindix.B 10CFR50, Appendix B Compliance 0.0 04/01/91- . Appendix C Terms and Definitions-2.0 11/01/92_ l l. l l l 9212220155 921216 -- PDR eDOCK 05000302 K PDR .D

b WATERFORD 3 &,Entergy-FOREWORD -REV.71.0-QUALITY ASSURANCE -R-TYPE: - C1.31 ~ 7 Operations-L PROGRAM MANUAL Page 1--of-2 'O A FOREWORD AND POLICY STATEMENT Waterford-3 has been designed,-built, inspected, tested, and is being operated:in - accordance with applicable regulations, codes, and standards. Above the requirements, however, Waterford-3 has achieved the status of industry leader. It is a_ source of pride for Entergy Operations employees. To_ continue our success, Entergy Operations has developed a document hierarchy consisting of programs, policies, directives, and procedures which communicate the goals and objec'tives of the company and provide controls to assure safe, efficient, and reliable operation of the nuclear stations. It is.the policy of Entergy Operations to maintain and operate Waterford-3 in accordance with the pc'icies and standards set forth -in the Entergy Operations Management Manual ( EOMM ). --the technical specifications, the Final Safety Analysis Report -and the various other-- programs required by our operating license agreement, including this Quality-Assurance Program Manual, t The achievement of our goals and objectives, including the successful implementation of the Quality Assurance Program, is the responsibility of everyone involved -- operators, engineers, mechanics, secretaries, warehousemen, managers, inspectors, vendors, etc. All must clearly understand that producing the desired results, in whatever role they play, is a _ basic and ~ inescapable _ day _-to-day responsibility that is necessary for the team's success. The _Waterford-3 Quality _ Assurance Program Manual' (QAPM)- has been established _ to - provide a consolidated overview of the: quality program controls'which govern the operation and maintenance of Waterford-3 quality related items and activities. It _- I defines the quality related, organizational responsibilities and interfaces of -. Ente rgy Operations as they relate. to % arford-3. Specifically, > the-Quality Assurance: Program includes " Nuclear SafU x uality Procedures" which describe-the i Waterford-3 program that implements 10CFR50, Appendix B for safety-related items - and services. l l 0 D e, - -..

1 WATERFORD 3 g Entergy - -FOREWORD REV. 1,~ 0, QUALITY ASSURANCE R-TYPE:- cl.31 w Operations. PROGRAM MANUAL Page 2 of 2 C 1 i "Special Scope Quality Procedures" which are an extension of the QAPM, define a limited application of 10CFR50, Appendix B. The Special Scope Quality Procedures ar' applicable to any activity where it has been determined to be prudent to define quality policy, but not implement a full 10CFR$0, Appendix B application. These Quality Procedures state in general terms the necessary elements of the Quality l Program along with the responsibilities and organizations for their implementation. All chapters of the QAPM have received concurrence by the Waterford-3 Directors and the General Manager, Plant Operations. The requirements and commitments contained in the QAPM are mandatory and must be implemented, enforced, and adhered by ali individuals and organizations. Employees are encouraged to actively participate in the continued development of the Quality Assurance Program as well as its implementation. Changes should be promptly communicated when identified. The success of Waterford-3 is dependent upon the active participation of all members of the nuclear staff in all phases of operation. I am confident that I can depend on each and every person associated with the operation of Waterford-3 to continue its success as a showcase for the industry. G UA R. P. Barkhurst Vice President Operations l O l j 'i ~

WATERFORD 3 CHAPTER 1 REV. 2.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Page 1 F 17 O TITLE: ORGANIZATION EFFECTIVE DATE: 11/01/92 PREPARED B M' DIREC, TOR, NUCLEAR SAFETYk (4 v QA MANAGER: ) VICE PRESIDENT, OPERATIONS: f, d s_ M s 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 Entergy Operations Management Manual, reference 2.5

2.0 REFERENCES

2.1 FSAR 17.2.1. 2.2 USNRC Regulatory Guide 1.8, Revision 1-R, September 1975 (which endorses ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel") 2.3 ANSI /ANS 3.1-1978, "American National Standard For Selection and Training of Nuclear Power Plant Personnel" 2.4 NUREG-0737, " Post TMI Requirementa" 2.5 Entergy Operations Management Manual 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 ENTERGY OPERATIONS MANAGEMENT 4.1.1 Entergy Operations management retains and exercises responsit.ility 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 program is maintained. 1 J

-WATERFORD 3' S,Entergy CHAPTER 1 REV. 2.0-QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL. Page 2 OF 17 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. 4.2 VICE PRESIDENT, OPERATIONS 4.2.1 The Vice President, operations is responsibic for assuring the development and approval of Waterford-3 quality policies. Reporting to him are thes a. General Manager, Plant Operations; b. Director, Plant Modification and Constra~ s,n ; c. Director, Site Support; I d. Director, Nuclear Safety; and e. Safety Review Committee. 4.2.2 The Vice-President, Operations is responsible for appointing the chairman and members of the Safety Review Committee. 4.2.3 The Vice President, Operations reviews trend reports, status summaries, and the results of annual management assessments to evaluate the effectiveness of the Waterford-3 Quality Assurance Program. In addition, the Vice President, Operations or his designee, endorses the Entergy Operations Management Manual (EOMM), Vol. IV and_ revisions thereto, which 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-quality related responsibilities of the General Manager, Plant Operations include a. -Providing 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,

c WATERFORD 3 - CHAPTER 1-REV. 2.0 Entergy-QUAL.lTY ASSURANCE n-TYPE: C1.31 e Operations PROGRAM MANUAL Page 3 OF 17-eC repair,. test, radiation' protection,-fire protection, and safety to. ensure plant and personnel. safety; Addrescinq matters brought to his attention by the Plant Operctions Review Committee (PORC); d. Assuring that the corrective action processes under his jurisdiction are implemented-in accordance with-approved procedures; e. Analyzing conditions for trends and publishing quarterly trend reports; and f. Approving design changes prior to implementation. 4.3.2 Reporting directly to the General Manager, Plant Operations are the a. _ Operations and Maintenance Manager; b. Technical Services Manager; c. Planning and Scheduling Manager; ~ d. Security and General Support Manager; and e. Plant Operations Review Committee. 4.3.3 OPERATIONS AND MAINTENANCE MANAGER The primary quality related responsibilities of the Operations and Maintenance Manager includes Development and maintenance of quality related-a. operations and maintenance procedures; b. Implementing Technical Specification controls and surveillances; c. Identifying and performing required corrective and preventive maintenance; and -d. Implementation of a measuring and test equipment calibration program. 4.3.4 TECHNICAL SERVICES MANAGER The primary quality related responsibilities of the-Technical. Services-Manager include:

p WATERFORD 3-e Entergy CHAPTER 1 REV. 2.0 QUALITY-ASSURANCE R TYPE: C1.31 w Operations PROGRAM MANUAL-Page_4 OF 17 a. rroviding engineering / technical support for primary / secondary chemistry, environmental monitoring, radiation protection, water treatment, and process controls; b. Initiate, prioritize and perform acceptance testing of plant modification activities; c. Reactor engineering and special nuclear matorial control and accountability controle; d. Coordination of the Fire Protection program; e. Housekeeping inside the Radiation Controlled Area; f. On-site handling, storage, packaging, and-shipping of radioactive wastes and sources; g. Development and control of the ALARA program; h. Development and control of the Radiation Protection program; i. Administering a root cause investigation and trend analysis program for identified conditions adverse to 1 quality; and j. Managing or implementing the In-service Testing, Local Leak Rate Testing, and the Hydrostatic Testing programs. k. Acting as a-liaison with regulatory agencies on technical issues involving plant chemistry issues. 4.3.5 PLANNING AND SCHEDULINC MANAGER The primary quality related responsibilities of the Planning and Scheduling Manager includes a. Assembling Work Authorization Packages including l ~ support documentation such as procedures, drawings, etc.; and

b..

Tracking nonconformances related to installed plant hardware to closure. l

WATERFORD 3 -CHAPTER 1 REV. 2.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL P'98 5 0F 17 4.3.6 SECURITY AND GENERAL SUPPORT MANAGER The primary quality related responsibilities of the Security and General Support Manager includes a. Implementing the Secuc.ty Plan ar.d Safeguards Contingency Plan; b. Controlling plant area acceses c. Implementing the Fitness For Duty Program; d. Providing supporr for the records management program; e. Directing the management of the hazardous waste / hazardous materiti programs; f. Acting as a liaison with regulatory agencies on technical issues involving environmental issues; and g. Developing and implementing a Radiological Effluent and Environmental Monitoring Program. 4.3.7 PLANT OPERATIONS REVIEW COMMITTEE (PORC) The PORC 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 on matters related to nuclear safety, including referral of topics requiring review and potential action by the Safety Review Committee. PORC membership and responsibilities are in accordance with section 6.0 of the Technical Specifications. a. 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." 4.4 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responalble for the direction and administration of the following organizational units and individuals. 4.4.1 Reporting to the Director, Plant Modification and Construction are thes a. Modification Control Manager;

g WATERFORD 3 I CHAPTER 1 REV. 2.0 Entergy QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL Page 6 OP-17 -{

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Construction Manager; and c. Project. Management Coordinator- -l 4.4.2 MODIFICATION CONTROL MANAGER The primary quality related responsibilities of the Modification Contro1~ Manager include a. Coordinating plant design changes; b. Managing the plant modification process, through the phases of design, implementation, testing, and acceptance; and c. Coordinating the development and review of departmental procedures. 4.4.3 CONSTRUCTION MANAGER The primary quality related responsibilities of the Construction Manager includes a. Reviewing and processing assigned work tasks and managing services for plant repair, modification, and construction which is under his jurisdiction; b. Reviewing completed modification and construction work prior to acceptance to ensure proper completion; and-- c. Coordinating construction tasks involved with outages and retrofitting. 4.4.4 PROJECT MANAGEMENT COORDINATOR -There are no quality related responsibilities specific to this position. l 4.5 DIRECTOR, SITE SUPPORT The Director, Site Support is responsible for the direction and administration of the following organizational units and i-individuals. 4.5.1 Reporting to the Director, Site Support are thes a. Site Business' Services Manager;

-WATERFORD 3 ggy, 2,g &_Entergy cyx,7,3 1 QUALITY ASSURANCE R-TYPE: C1.31 ~ Operations. PROGRAM MANUAL Page 7 OF 17 h b. Training Manager; c. Emergency P2anning and Administration Manager; d. Management Programs and Excellence Coordinator; and e. Materials, Purchasing, and Contracts Manager. 4.5.2 SITE BUSINESS SERVICES HANAGER There tre no quality related responsibilities specific to this position. 4 4.5.3 TRAINING MANAGER The primary quality related responsibilities of the Training Manager includes a. Providing training for Waterford-3 personnel, including training required by regulations, General Employee Training, and training for the technical staff and management; b. Faintaining training records; and c. Providing an instructor certification program. 4.5.4 EMERGENCY PLANNING AND ALMINISTRATION MANAGER The primary quality related responsibilities of the Emergency Planning and Administration Manager includes a. Managing the preparation and approval of the Watsrford-3 Emergency Plan and impletaenting-procedures; L. Coordinating the preparation of' emergency drill scenarios and performance of practice drills; and Providing support for records management including c. execution of document' control and records storage programs. 1 4.5.5 MANAGEMENT PROGRAMS AND EXCELLENCE COORDINATOR There are no quality related responsibilities specific to this position.

A,Entergy-- WATERFORD 3 - -CHAPTER 1-REV. 2.0.L QUALITY ' ASSURANCE R-TYPE: C1.31 ~_ Operations PROGRAM MANUAL. Page 8 OF 17 O. 4.5.6 MATERIALS, PURCHASINC, AND CONTRACTS MANAGER. The primary quality related responsibilities of the Haterials, Purchasing, and Contracts Manager. include:- a. Selecting site specific vendors based upon technical, quality, and commercial evaluations; b. Purchasing and receipt of equipment, parts, materials, and supplies in support of Waterford-3 operations and station modifications; c. Coordinating the selection of site. specific. contractors based upon technical, quality, and commercial evaluations; d. Administration of a receipt inspection program to assure acceptability of quality related materials, parts, and components; e. Coordinating the processing and review of procurement documents for equipment, parta, materials, and services in support of plant operations and station modifications, including maintenance and design changes; f. Establishing quality assurance and technical requirements in quality related procurement documentes g. Maintaining storage conditions necessary to sustain material quality; and h. Processing and securing material traceability-data-to-support historical reference. I 4.6 DIRECTOR, NUCLEAR SAFETY The Director, Nuclear Safety is responsible for the direction and administration of the following organizational units and individuals. 4.6.1 Reporting.to the Director,. Nuclear Safety are thes-a. ' Licensing Managers. b. Safety Review Manager; c. Policy and Directives Coordinator;

WATERFORD 3 A ntergy-' CHAPTER l-REV. 2.0 E QUALITY ASSURANCE R-Tyres-C1.31 ~ Operations PROGRAM MANUAL-Page 9 OF_17 (f d. Qualiry Assurance Manager;_and-e.- Operational Experience Engineering Manager. l 4.6.2 LICENSING MANAGER The primary quality related responsibilities of the Licensing Manager 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 ant; 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; and e. Reviewing corrective action documents for determination of reportability. 4.6.3 SAFETY' REVIEW MANAGER The primary quality related responsibilities of the safety Review Manager includes a. Maintaining Safety Review Committee charters; b. Performing independent reviews, safety examinations, and other review activities _in support of:the safety Review committee and Technical Specification . requirements; and c. -Overseeing tne activities of the Quality Team (Q-Team). 4.6.4 POLICY AND DIRECTIVES COORDINATOR The primary quality related responsibilities of the Policy and Directives Coordinator includes a. Coordinating the development, preparation, and maintenance of Waterford-3 policies and directives.

LWATERFORD 3-CHAPTER 1: REV. 2.O Entergy) QUALITY ASSURANCE n-TYPE: cl.31 y - Operations PROGRAM MANUAL Page 10 OF 27- / 4.'6.5 QUALITY ASSURANCE MANAGER 4.6.5.1 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; b. Initiate, recommend or provide solutions through designated channels; and c. Verify implementation of solutions. 4.6.5.2 This organizational freedom includes sufficient independence from cost and schedule when opposed to safety considerations. f 4.6.5.3 The Quality Assurance Manager and his staff have-the authority to stop unsatisfactory work and/or control further processing, delivery or installation of nonconforming material through designated channels. 4.6.5.4 The primary quality related responsibilities of the Quality Assurance Manager includes 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 ~, quality related policies, directives, and implementing procedures, and changes thereto; c. Advising on the scope and content of quality assurance training courses for personnel performing quality related j activities; i l l [: i

-WATERFORD 3-4 ntergy CHAPTER 1 REV.-2.0 E QUALITY ASSURANCE R-Tyre -cl.al y Operations PROGRAM MANUAL P*9* 11 or 17 d.- Assuring effective implementation of the Quality Assurance Program through a comprehensive system of reviews, audits, surveillances, and inspections including storage facility inspections and the performance or monitoring of nondestructive examinations and other special processes;- e. Enouring that quality reviews are conducted for design changes including drawings and specifications to ensure the inclusion of quality requirements; f Reviewing work plans, procedures, and instructions for maintenance, modifications, inspections, and tests of quality related structures, systems or components to verify the inclusicn of quality requirements, inspection criteria, and holdpoints; g. Developing and maintaining Quality Assurance Procedures (QAPs); h. Providing status information regarding the Quality Program to the Director, Nuclear safety and the Vice President, operations;. 1. Reviewing and concurring with the conter.t of the quality assurance indoctrinatitn and training programs-for-personnel performing quality related activities;- 3 Providing requested inspection training to personnel performing quality related activities; k. Reviewing nonconformance work authorization packages; 1. Certifying Lead Auditors and Inspectors; 4 m. Assisting in establishing that portion of, the Training Program that addresses quality assurance; n. Establishing and maintaining documentation of Quality Assurance activities;

mm ' l 1 .q WATERFORD 3 CilAPTER 1. REV.-2.0 Entergy - QUALITY ASSURANCE a-TYPE: C1.31. - ~g Operations PROGRAM MANUAL. Page-12 OF_17 o. -Reviewing corrective-action documents to determine'if-aJcondition adverse-to quality is reportable or significant;- p. Assuring that the corrective action processes under his/her jurisdiction are-implemented according to approved procedures; and q. Conducting.an ongoing assessment of the radiation protection and radwaste programs. r. Conducting reviews, assessments and monitoring the various corrective action processes to ensure that the required program aspects are adequr,tely addressed. 4.6.6 OPERATIONAL EXPERIENCE ENGINEERING MANAGER The primary quality related responsibilities of the Operational Experience Engineering Managar includes a. Interfacing with on-site-and outside organizationo ]_ such as the NRC, INPO, Quality Assurance,fand ---E / equipment vendors to ensure quality is maintained; b. Reviewing-plant system problems ~and performance concerns;. c. Reviewing operating abnormalities and Licensee Event Reports; and d. Examining plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other~ sources of-plant design and operating experience information, indicating 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 fers-1. Making recommendations for. improving plant safety including procedure revisions, equipment 1 modifications, maintenance activities, operations activities, orlother means'of improving plant safety; m. m .-. AA- - m i. s.- -i-y er-y a v

~ klllgEntergy WATERFORD 3 CHAPTER 1 REV.-2.0 e QUALITY ASSURANCE R-TYPE: C1.31 Operations ' PROGRAM MANUAL P89* 13 J 17 h. 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. 4.7 SAFETY REVIEW COMMITTEE 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 Federa) a~d state. regulations which address nuclear safety. The SRC is responsible for providing independent review and audit of Waterford-3 operations; reviewing changes or modifications which involve an unreviewed safety questions 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 perf rming special evaluations, reviews, end audits as may be requov.ed by the Vice President, Operations. The Technical Specificati ns further deserthe the responsibilities of the SRC. 4.8 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering, who reports to the Vice President, Engineering domiciled in Jackson and not part of the Waterford-3 site organization, is responsible for the direction and administration of the following organizational units and individuals. 4.8.1 Reporting to the Director, Design Engineering are thes a. Safety and Fngineering Analysis Manager; b. Procurement /Programa Engineering Manager; and c. Design Engineering Manager. 4.8.2 SAFETY AMD ENGINEERING ANALYSIS MANAGER The primary quality related responsibilities of the Safety and Engineering Analysis Manager includes-a. Assessing the impact of changes to plant design and operation on the design basis accident analysis.

gEntergy: WATERFORD 3 CnAPTER 1 REv. 2.o; QUALITY ASSURANCE R-TYPES-C1.31 -e Operations ~ PROGRAM MANUAL. Page 14 or 17. ). 4.8 3 PROCUREMENT / PROGRAMS ENGINEERING MANAGER The primary quality related responsibilities of the Procurement / Programs Engineering Manager includes Assisting in the establishment of quality ~ assurance a. and technical requirements in selected quality related procurement documents). b. evaluate part substitutions; c. dedicate commercial grade items for use in safety-related applications; d. Supporting plant activities for ASME Section XI and environmental qualification (EQ); e. Reviewing new or changed technical and quality requirements for spare and replacement part requisitions classified as EQ; i f. Developnent and maintenance of the following Waterford-3 programes 1. ASME Ten Year In-service Inspection Program 2. Steam Generator Eddy current Program 3. Erosion / Corrosion Program 4. Microbiologically Induced corrosion (MIC) Program 5. Lifting Rig Assembly Inspection Program 6. 10CFR50.49 Environmental Qualification of electrical' equipment important to safety for nuclear power plants 7. 10CFR Part 50, Appendix A,' General Design Criteria 4 for safety related mechanical equipment located in a harsh environment g. Maintaining-the Waterford-3 Q-List and Q-Related List' to define safety and quality classifications; and h. Maintaining the Waterford 3 EQ List ~l L. Maintaining the site tagging and labeling standard.

'WATERFORD 3 A ntergy: CHAPTER 1 REY.-2.0 E QUALITY ASSURANCE R-TrPE: C1.31 m Operations PROGRAM MANUAL. Page 15 OP.-17 4.8.4 DESIGN ENGINEERING MANAGER The primary quality related responsibilities of the Design Engineering Manager includes i a. Managing design activities including materials and ^ document revisions; b. Managing outside contracted engineering resources for-selected engineering activities; and Providing design of drawings and documents describing c. plant design. 4.9 VICE PRESIDENT, PLANNING AND ASSURANCE The Vice President, Planning'and Assurance is responsible for providing the direction and administration necessary relative to the follawing 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 and contractors of quality related items, spare parts, and services through reviews, =. surveillancet,.and audits; b. Conducting pre-award evaluations for quality requirements of vendors, suppliers,-end contractors where applicable; c. Maintaining a qualified suppliers list (QSL) for use in procuring safety related items, spara parts, and services; d. - 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;;and' o. Supplementing Watarford-3 teams during Quality Assurance audits and surveys. 4.10. VICE PRESIDENT, ENGINEERING The Vice President, Engineering is responsible:for.providing the direction and' administration necessary to the Waterford-3 Design Engineering group and services including a. reactor phyaica analysis; .g.

~._ WATERFORD 3 ' eEntergy CHAPTER 1 REV. 2.0-w QUALITY ASSURANCE R-TYPE: - C1.31-T Operationsi . PROGRAM MANUAL Page 16 OF 17 h b. plant transient analysis; c. thermal hydraulic analysis; d. piping analysis; i e. nondestructive analysis; f. metallurgical evaluations; and g. fuel fabrication and related services. 4.11 VICE PRESIDENT OPERATIONS SUPPORT The Vice President Operations Support is responsible for providing the direction and administration necessary relative to the following listed primary quality related responsibilities as they-relate to the Waterford 3 Quality Assurance programs a. Reviewing design changes and plant modifications from'a radiologleal standpoint; b. -Preparing long-term collective dose' evaluations and projections for ALARA planning; and_- c. -Performing as a voting member on the Waterford 3 ALARA Committee. 4.12 ENTERGY OPERATIONS PERSONNEL Entergy Operations personnel are responsible.for adherence to the requirements delineated in this QA Program. Manual and-its implementing procedures. Entergy Optrations personnel are also responsible for identifying and reporting conditions: adverse to; quality and for. identifying program or procedural enhancements. 4.13 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 la e of-communication shall exist-between-the supplier / contractor an the Waterford-3 or Corporate Quality Assurance organization. Th e overall responsibility for quality at 'Waterford-3 remains = with - Entergy Operations-at all times. p l.p ~

4 lL-44by b 4m aw B + - - ,4-k'-,6 3-e 6., <hm-- 4.25--+:- --4 -s-,4 -e& r,166w WATERFORD-3 A ntergy1 cuAvTER 1 REv. 2'.o E QUALITY ASSURANCE R-TYPE: C1.31 ~ i Operations PROGRAM MANUAL Page 17 OF 17' ' ~ 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.O ATTACHMENTS Attachment I.- Waterford-3 Organization Chart, s 1. i != l

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1 i WATERFORD 3 CHAPTER 2 REV. 2.0 Entergy QUALITY ASSURANCE R-Tyre C1.31 e Operations PROGRAM MANUAL Page 1 of 10 0 TITLE: OUALITY ASSURAN1E PROGRAM EFFECTIVE DATE: 11/01/92 PREPARED BY: M k DIRECTOR, NUCLEAR SAFETf h-W QA MANAGER: \\ VICE PRESIDENT, OPERATIONS: h\\ vv N 1.0 PURPOSE 1.1 It is the objective of Entergy Operations to operate and maintain the Waterford-3 nuclear plant in the highest degree of functional integrity 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 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 and guidance. This program takes into account the need for trained personnel, approved procedures, cpecial controle, processes, equipment, and skills necessary to 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, directives, procedures, and instructions which provide written guidance for the control of quality related activities. These documents incorporate the requirements of the regulatory guides and the NRC endorsed ANSI Standards to which Waterford-3 has specifically committed.

2.0 REFERENCES

2.1 Waterford-3 FSAR 17.2.2. 2.2 USNRC Regulatory Guide 1.33, Rev. 2, February 1978 (which endorses ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power P) ants"). 2.3 Technical Specifications, Waterford Steam Electric Station, NUREG-1117. i 1

WATERFORD 3 CHAPTER 2 REV. 2.0 Entergy QUALITY ASSURANCE R-TTPE: C1.31 v Operations PROGRAM MANUAL Page 2 of 10 ( ~ 2.4 10CFR50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants". 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 VICE PRESIDENT, OPERATIONS The Vice President, Operations is responsible for providing overall approval and direction for the Waterford-3 Quality Assurance Program. 4.1.1 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 changos or modifications which involve an unreviewed safety question, and reviewing f safety evaluations of changes made to the plant and plant s-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 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. 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.

n- . ~.- -~. ~ WATERFORD 3 eEntergy: CHAPTER 2 REV. 2.0 QUALITY ASSURANCE r TrPE: C1.31 = Operations PROGRAM MANUAL Page 3 of 10 II l 4.3 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construc*lon 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 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 unitet. Site Business Services; Training; Emergency Planning and l Administration; Management Programs and Excellence; and Materials, Purchasing, and Contracts. The primary quality related responsibilities of the Director, site Support are listed in Chapter 1. I 4.5 DIRECTOR, NUCLEAR SAFETY The Director, Nuclear Safety is responsibl1 for ensuring the C-) development and maintenance of procedures or instructions for the implementation of the following programs and organizational units: Licensing; Safety Review; Policy and Directives; Quality Assurance; and Operational Experience Engineering. The primary l quality related responsibilities of the Director, Nuclear Safety are listed in Chapter 1. 4 4.6 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. 4.7 VICE PRESIDENT, PLANNING AND ASSURANCE The Vice President, Planning and Assurance is responsible for the direction of the following organizational units and' individuals which.have responsibilities relative to the Waterford-3 Quality Assurance Program Nuclear Safety Oversight; Supplier QA; and Services QA. The primary quality related responsibilities of the Vice President, Planning'and Assurance are listed in Chapter 1. C.'/- h d -,gr, v w - -, - -ww v v ,r .v_e, e-

..- -~ ~ WATERFORD 3-- CHAPTER 2 REV. 2.0 a Entargy QUALITY ASSURANCE R-TYPE: C1.31

Operations

O.

- PROGRAM MANUAL. Page 4 of 10 4.8 VICF PRESIDENT, ENGINEERING' The Vice President, Engineering is responsible for providing nuclear 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. 4.9 VICE PRESIDENT OPERATIONS SUPPORT The Vice President Operations Support is responsible for providing operations support to the Waterford 3 Quality Assurance' Program. The primary quality related responsibilities of the-Vice President' Operations support are listed in Chapter 1. 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 (including Chapter 17.2 of which contains the latest NRC approved QA Program description). 5.1.3 The next level of the document hierarchy includes the a. Entergy Operations Management Manual (EOMM)-(Volumes I and IV) and I j b. Waterford Quality Assurance Program ' Manual (QAPM). 5.1.4 The succeeding level of documentation contains departmental -level procedures and instructions. O u I ll' l

I WATERFORD 3 e Entergy - CHAPTER 2 REV. 2.0 QUALITY ASSURANCE R-TYPE: C1.31 w (_ ) _ - Operations PROGRAM MANUAL Page 5 of 10 5.1.5 This manual, as well as, the Special Scope Quality Procedures, provide the media for informing responsible organizations and individuals that implementation of the-Quality Program is mandatory and that the Quality Program shall be enforced. 5.2 QUALITY ASSURANCE PROGRAM MANUAL 5.2.1 This Quality Assurance-Program Manual (QAPM), defines the responsibilities and activities necessary to implement the-quality requirements and commitments contained in the highest level documents including 10CFR50 Appendix B, the regulatory guides, and the ANSI Standards as listed in 7 Appendix A of this manual. 5.2.2 Chapters 1 and 2 of this Quality Assurance Program Manual-address the Waterford-3 quality related commitments in order to summarize the entire scope of the quality assurance program. 5.2.3 Chapters 3 through 18 have been developed to promulgate the-safety-related commitments only. 5.3 SPECIAL SCOPE QUALITY PROCEDURES 5.3.1 The Special Scopo Quality Procedures define the quality requirements for quality related items and activities not meeting the definition of safety related. The Special Scope Quality Procedures should be developed to define the IOCFR50 Appendix B criteria applicable to the specific activity. The Special scope Quality Procedures may address each criteria and its implementation; or, reforence the applicable chapter of th8.c Quality Assurance Program Manual, stating that the safety related controls apply.' 5.3.2 The procedures provide direction for the following special scope programas 1 a. Fire Protection Quality Assurance b. Radiological Effluent and Environmental Monitoring c. Emergency Preparedness d. Security-Radioactive Waste Management Quality Program e. f. Special Nuclear Material Control and Accountability. 1

l WATERFORD 3 CHAPTER 2 REV. 2.0 ,,Entergy QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Page 6 of 10 /~ \\ N- ] g. Computer Software h. ALARA Program 1. Radiation Protection j. ATWS 5.4 PROCEDURES AND INSTRUCTIONS 5.4.1 The individual Entergy Operations organizations assigned responsibilities by the EOMM and the QAPM shall be responsible for the development, maintenance, and tmplementation 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 e.spects of plant management and operations. These procedures wills a. Implement t.3 policy and direction of the EOKM 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 opsrating philosophy at Waterford-3; and c. Delineate the responsibilities and authorities of the Waterford-3 staff. 5.4.3 The Waterford-3 procedures and ini ructionb contained in this level are the: a. Plant Operating Manual b. Quality Asburance procedures c. Site Support procedures d. Design Engineering pro edures v Plant Modification and Construction procedures, and Nuclear Safety procedures () 4 l

~ 9 i WATERFORD 3 e Entergy CHAPTER 2 REV. 2.0 w QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Page 7 of 10 l h 5.5 IDENTIFICATION OF SAFETY RELATED STRUCTURES, SYSTEMS, AND COMPONENTd 5.5.1 The Quality Assurance Program appliws 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 telated classifications of plant structures, systems, and components and identifies 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 Program requirements are applied. 5.5.3 Procedures for the preparation and control of procurement documents provide guidance for spara and replacement part classification determination. These procedures invoke applicable codes, standards, 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 essurance program interpretation and implementation. 5.6.2 Disputes invo2ving quality, arising from a difference of opinion between Entergy entities, contractors, or suppliers l are normally resolved through the appropriate manager.. If a i satisfactory resolution cannot be reached, the disputes should be elevated to the Vice President, Operations, if necessary. The Quality Assuranca Manager should be r consulted for disputes involving other Entergy entlties. The Manager, Quality (Supplier) and/ortheQualityAssurancel . Manager should be consulted for disputes concerning contractors or suppliers.

I WATERFORD 3

l.,. f ntergy CHAPTER 2 REV. 2.0 E

QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL Page 8 of lo O 5.6.3 Written notification shall be provided to the Vice President, Operations, and the safety Review Committee (SRC) regarding disputes or disagreements arising from a difference of opinion between the Plant operations Review Conmittee (PORC) and the General Manager, Plant Operations. The General Hanger, 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 proceduros. 5.7.2 Entergy Operations management is responsible to assure that personnel are properly trained to perform activities in a I safe and effective manner. 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 st 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 thats a. Personnel responsible for performing activities that affect quality are instructed on the purpose, scope, and implementation of quality related manuals, instructions, and procedures; b. Personnel performing activities that 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; 4

l WATERFORD 3 A ntergy CHAPTER 2 REV. 2.0 E QUALITY ASSURANCE R-TrPE: C1.31 w Operations PROGRAM MANUAL Page 9 of 10 () 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, the content, attendance, tests, acceptance criteria, and the i 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 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. 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 C 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' audit / assessment of the Quality Arsurance Program is conducted annually by a qualified independent organization. 5.9.2 The information from these management essassments, 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 PROGRAM 5.10.1 Amendments to FSAR 17.2 and' 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 of any changes to the Quality Assurance Program -n,r y -,-r-- -v e -s-e ~ w 4 .~ 4 a e

WATERFORD 3 e% CilAPTER 2 REV. 2.0 Entergy QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL P*9' 20 f 10 O description that do not reduce the commitments previously accepted. If a change is contemplated which would reduce the commitments in the app..sved Quality Assurance Program description, the proposed change shall be submitted to the NRC for approval prior to implementing the change. 5.10.2 Entergy Operations requires principal contractors and suppliers to submit their QA Program descriptions to Entergy Operations for evaluation and to provide notification of changes. Significant changes to such program descriptions shall be reported, as applicabin, 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 effect of changing the quality assurance program of the principal contractor or Entergy Operations. 6.0 ATTACIIMENTS 6.1 Attachment I - Waterford-3 Document literarchy

O _Q V V h % a a g CUALITY ASSURA!fCE PROGFJM LwuramTION y 'T s S ", c=% ' Islentification E12sription Aroroval and Control

• a E

1. PSAR Chapte.c 17.2, "Qua*Lty A description of the Quality Prepared by Quality Assurance and Assurance During the Operating Assurance Program. coordinated with plant operatiens 5 Phase" and support organizations. Approved by the Vice President, Operations, waterford-3 and controlled by O Licensing. gg N > </ O r- > 2. Quality Assurance Prograa Defines the Quality Assurance Prepared by Quality Assurance, OQ Manual Program, assigne responsibilities to concurred with by the effected various organizations, and defines organizations and approved by the 2 Ml', safety-related activities. Vice President, Operations, p waterford-3. They are issued and controlled by the Site Support 3 (f) y (f) Q >C Z 'D ;C croup. t; 3. Entergy Operations Management A set of Policies and Directives Prepared by cognizant personnel, 9 Manual which prescribe activities and issued and controlled by corporate pg rseponsibilities. Entergy operations or site and m approved by Entergy Operations Management. 4. Waterford-3 Plant Operating A stant a1 consisting of a set '2 Prepared by cognizant plant staff Manual procedures which preecribe rcquired organtastional units. Reviewed by aspects of plant management and PORC. Approved by the General fO operation. This manual provides the Manager Plant Operations. Issued yy mechanism through which the and controlled by p12-t h-..t Qgy administrative controls and quality control. - :o assucance require:eents are

c u impismented during the operation of 90, waterford-3. The POM applice to all M*

personnel when they are within the w waterford-3 protected area. c e H M O O m M

= . = _. l V v t QV.AZ,ITY ASSURANCT PROCPmt DOCUMINTATION Om %3 [ Identification Descriotion Aroroval and control k9 ,i I,W 5.' Quality Assurance Procedures A set of procedures prepared and Prepared by Quality Accurance and E te: Manual issued to specify and control the coordinated with other organizations [ activities of Quality Assurance. as applicable. Approved by the p Quality Assurance Panager. Issued and controlled by Site Support. O 6. Site Support Procedures A set of procedures which prescribe Prepered by cognizant personnel C O b *I activities and responsibilities within the Site support Group. within the Site Support Group. Approved, issued, and controlled by g l the Director, Site Support and 3 >-{ l concurred with hy the Quality ff! I Assurance Manager. E>% [ M *T1 I EMO l 7. Design Engineering Procedures A set of procedures which prescribe Prepared by cognizant personnel y activities and responsibilities within Design Engineering. Issued g l 4 within the Design Engineering and controlled by the Director, Site C> organization. Support. Quality related procedures >ZW f are concurred with by the Quality IO f Assurance Manager. Approved by the Director, Design Engineering. l }. 8. Plant Modification and A set of procedures which prescribe Prepared by cognizant personnel Construction Procedures activities'and responsibilities within Plant Modification and I within the Plant Modification and Construction. Issued and controlled > 38 O f [ Construction organization. by the Director, Site Support and Nkh [ i concurred with by the Quality $y$ f Assurance Manager. Approved by the jfy Director, Plant Modification and M i construction. ko" i s* t=8 9. . Nuclear Safety Procedures A set of procedures which prescribe Prepared by cognizant personnel activities and responsibilities within the organization. Issued and

• tr g

j i within the Nuclear Safety . controlled by the Director, Site 4 e "W organization. , Support and concurred with by the Quality Assurance Manager. Approved M w by the Director, Nuclear Safety. O o t i N t f I l j [ l i

WATERFORD 3 g Entergy CHAPTER 3 R E V.- 0. 0 QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL PAGE 1 OF 7 - O b TITLE: DESIGN CONTROL EFFECTIVE DATE: 04/01/91 PREPARED BY: 4 DIRECTOR, NUCLEAR SAFETY: / < wd* 3 QA MANAGER: ( & VICE PRESIDENT OPERATIONS: dbl 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 end modifications thereto, are executed in a planned, controlled, and orderly manner.

2.0 REFERENCES

2.1 PSAR Section 17.2.3. 2.2 USNRC Regulatory Guide 1.64, Revision-2 (which endorses ANSI ) N45.2.11-1974 ' Quality Assurance Requirements for the Design of Nuclear Power Plants.') v 2.3 10CFR50.59. 3.0 DEFINITIONS None

• .0 RESPONSIBILITIES 4.1 GENERAL MANAGER PLANT OPERATIONS 9'

The General Manager, Plant Operations is responsible for ensuring that the physical configuration of the plant remains r.: conformance with c 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 ENGINEERING The Director, Engineering is responsible for design activities.and for approval of final design documents and design changes at Waterford-3. ~

WATERFORD 3 gEntergy CHAPTER 3 REV. 0.0 QUALITY ASSURANCE R-TYPE: cl.31 w p Operations PROGRAM MANUAL PAGE 2 OF 7 (J 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 the Waterford 3 Technical Specifications. 4.4 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for reviewing safety related design change packages to ensure inclusion of quality assurance requirements. 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 p applicable regulatory requirements and design bases into ( design, procurement, and procedural documents. The design U 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 inservice 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 arrangements, and equipment locations. 5.1.3 Design activities shall be prescribed and documented on a timely 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 v drawings and specifications.

WATERFORD 3' gEntergy cnAPTER 3 REv. 0.0 i w QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL _ PAGE 3 OF-7 5.1.5 Applicable design inputs and their sources shall be identified and their selection reviewed and approved. Design inputs shall include, but are not limited to, those listed.in Reference 2.2. Changes from specified design

inputs, including the reasons for the changes, shall be identified, approved, documented and controlled.

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 - reproductio_n, filing, C) 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 verification 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 ' relense. 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.

1

WATERFORD 3 gEntergy CilAPTER 3 REV.0.0 QUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL PAGE 4 OF 7 5.4.3 Design reviews shall address the following items, where applicable. to assure thats a. The design inputs wore correctly selected: b. The assumptions necessary to perform-the design activity are adequately described and are reasonable c. Applicable codes, standards, and-specifications were utilized: d. An appropriate design method was used e. The design inputs were - correctly incorporated into the designs f. The design output reasonably compares to design inputs:: g. Design characteristics can be controlled, inspected, and tested to ensure no adverse effect on safety: h. Inspection and test acceptance criteria are identified:

i. Appropriate fire protection and security requirements have been mets and j.

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 Nerify 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. O

. _. _ _ _ _ _ _ _ _ _ _ ~. WATERFORD 3 gEntergy cl! APTER 3 REV. 0,0 QUALITY ASSURANCE R-TYPE: c1,31 w Operations PROGRAM MANUAL PAGE 5 OF 7 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 considered in determining the most adverse conditions. 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 design organization to assure that test requirements have been met. 5.4.9 Regardless of

title, individuals performing design verification shall not haves a.

established the design inputs for particular design aspects being verified. b. specified a singular design approach: c. ruled oct certain design considerations or d. immediate supervisory responsibility for the individual s./ performing-the design except as provided for below: 5.4.10 The designer's immediate supervisor -may perform -the-verification if the following conditiona apply: a. The supervisor is the only technically qualified individuals and i b. 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. I 5.5 DESIGN CHANGES 5.5.1 Safety related design and - specification : changes, = including field changes, shall-be subject to the same type ofi design - controls and-approvals as the-original'.. Qualified' organizations other than the original desi,;ner 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-v analysis as appropriate,: shall be. verified to. ensure' the= analyses are still valid. o

WATERFORD 3 h ntergy CHAPTER 3 REV. 0.0 E '. 0ALITY. ASSURANCE R-TYPE: C1.31 .4 e Operations >ROGRAM MANUAL PAGE 6 OF 7 g'O 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 g suitability. Such reviews shall be documented. 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. 5.5.5 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, t 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 thst N all errors and deficiencies are corrected and that: action is-V taken to prevent recurrence. Such corrective. action shall-be in accordance -with Chapter 16 of this Quality Assurance Manual. 5.6.2 Malfunctions shall be promptly documented and evaluated to determine probable cause. If evidence -indicates that common components in-saf ety related-systems - have performed in < an i unsatisfactory manner, corrective measures shall be planned-- prior to replacement or repair? of such components. Approved procedures for repair shall be. available prior to ac tual -- . performance. Replacement- ' parts shall 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 inservice performar.ee evaluation and minimize the possibility of a hidden deficiency developing into a systematic failure. An augmented testing and inspection. program shall 'ae is.plemented following a large scale component replacement or repair as necessary to demonstrate component reliability. 5.7 MAINTTNANCE AND MODIFICATION 5.7.1 Inspection and performance testing shall verify that safety relcted structures, systems, and components are functioning adequately af ter maintenance or modifications - are complete. The results shall be documented and maintained in accordance-vfth applicable procedures. 1 3 'l

WATERFORD 3 A ntergy CliAPTER 3 REV. 0.0 E QUALITY ASSURANCE R.-T Y PE : C1.31 w Operations PROGRAM MANUAL PAGE 7 0F 7 5.7.2 Written safety evaluations of design changes shall be prepared in accordance with Reference 2.5, 100FRSO.59. 5.8 DESIGH DOCUMENTATION AND RECORDS 5.8.1 Design documentation and records, which provide evidence that the design and design verification process were performed in j accordance with the Quality Assurance Program requirements chall be collected, stored, and maintained in accordance with I documented procedures. This cocumentation 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 ATTACIIMENTS None t P 4 f , _.. -...,,,.~_ _.-,,. _,,

. ~ _.. _ _. _ i i l WATERTORD 3 e Entergy gggp7gg 4 ggy,1,o QUALITY ASSURANCE n TYPE: cl.31 l w Operations PROGRAM MANUAL Page 1 of 5 C TITLE: PROCURP7ENT DOCtHENT CONTROL EFFFCTIVE DATE: 4/22/92 ~ . PREPARED BY: DIRECTOR, NUCLEAR SAFETY: w 4 } l. Ah,( ( VICE PRESIDENT, OPERATIONS:

• \\Tt M tf QA MANAGER: _vq 1.0 PURPOSE 1.1 Procurement document control applies to the preparation, review, approval, and handling of documents used to obtain materials, spare

?nj replacement parts, components, and services required to modify,- .aintain, repair, test, inspect or operate Vaterford-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 iw the Waterford-3 policy that the quality 4.nd design of purchased replacement materials, components, and spare parts are equal to or better than the original item.

2.0 REFERENCES

2.1 FSAR 17.2.4. 2.2 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"). 2.3 USNRC Regulatory Guide 1.89,

• Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear' Power Plants.'

3.0-DEFINITIONS None. 4.0 RESPONSIBILITIES 4.1 DIRECTOR. SITE SUPPORT The Director. Site Support is responsible for. 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 site specific procurement. I o ~ ~..

WATERFORD 3 g Entergy Cl! APTER 4 REV.1.0 QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL Page 2 of 5 y i j The Hateriais, Purchasing, and Contracts Manager is responsible fort. i 4.1.1 Ensuring that appropriate procedures are developed and ) implemented for activities related to the preparation, l

review, approval, and control of requisitions:

and-procurement planning: 4.1.2 Vendor selections coordination of contractor selections preparation,

review, and issuance of site specific purchase orders and contracts to support the procurement

.j of material, equipment, spare, and replacement parts, and service: 4.1.3 Identifying quality classifications and establishing the related quality requirements, when applicables 4.1.4 Administration of a receipt inspection program to assure acceptability and maintenance of quality related materials, parts, and components: 4.1.5 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 4.1.6 Establishing quality assurance and technical requirements in quality related procurement documents. 4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible for ensuring the development of procedures for definini the performance and documentation of engineering evaluations, as requested or mandated: to establish requirements and controls when. original technical or quality requirements cannot be determined for spare or replacement parts. 3 5.0 DETAILS. 5.1 PREPARATION OF PROCUREMENT DOCUMENTS 5.1.1 Procedures are provided for the preparation control, and= i-review of procurement documento to ensure that: quality-l requirements are correctly stated, inprocesscand final l-inspection criteria are. defined, and that appropriate l. controls are established. O -... -, ~,.. ~....

h WATERFORD 3 gEntergy CHAPTER 4 REV.1,0 QUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL Page 3 of 5 O 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 documentations and assisting in vendor selection. 5.1.3 Organizations preparing procurement documents shall determine the applicable quality classification in accordance with approved procadures, codes, standards or design bases. 5.1.4 Procurement documents, as applicable, shalir a, State the materials, parts, and components or the scope of work or services to be provided 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 applicabic regulations, codes, and industrial standards:

d.- Identify _ the -documentation -(e.g.,

drawings, specifications - inspection and fabrication plans, inspection and test records, parsonnel and procadure qualifications, and_ chemical and physical test results of material) to be prepared, maintained, and/or arbmitted to ;Entergy. Operations for information, review, and/or approval:-

l e. Identify the Entergy Operations Quality Assurance Program _ requirements which must. be described 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 d_elivered to Entergy Operations prior to use or installation of the items e_

WATERFORD 3 gEntergy CHAPTER 4 REV.1.0 QUALITY ASSURANCE R TYPE: cl.31 w Operations PROGRAM MANUAL Pago 4 of 5 g. Establish the right of access for Entergy Operations and its agents to the vendor's facilities and records for source inspection and audits: h. Identify the storage requirements and retention periods for records to be retained by the vendor 1.

Specify, for safety related procurement, the requirement for vendors to comply with 10CTR21 for reporting defects and noncompliances which could create a substantial safety hazards y

j. Establish measures for the identification, control, and disposition of items and services that do not meet procurement document requiremenses and k. Procurement documents for on-site work by a vendor service representative shall require that any materials or replat.ement parts, and required documentation, shall be subjected to receiving inspection, records review, and warehouse issue by Entergy Operations. 5.1.5 Where commercial grade items are to be used in safety related applications, the procurement 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 replacement parts may be procured commercial grade provided the items are properly evaluated and dedicated for safety related use. 5.2.3 In those cases where the technical aM/or qt.ality requirements of the original item cannot bt aetermined, an engineering evaluation shall be conducted and documented by qualified individuals to establish the requirements and controls. O

I WATERFORD 3 (q C}1 APTER 4 REV.1.0 / Entergy QUALITY ASSURANCE n TYPE: ci,31 Operations PROGRAM MANUAL Pago 5 of n e a. This evaluation shall assure that interfaces. safety, interchangeability, fit, environmental compatibility, and function are not adversely affected or contrary. to the FSAR, applicable codes, standards, and regulations. 5.2.4 Replacement electrica? equipment in narsh 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 i document contains the verify that the procurement. l appropriate requirements identified in 5.1.4. 5.3.2 Reviews of procurement documents shall be performed by personn:1 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 'y 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 CIIANC.ES f Procurement document changes are subject to -the 'same degree of-control as utilized in the preparation of the original documents. 6.0 ATTACl!!iENTS None CL

_['< ( WATERFORD 3 A ntergy CHAPTER 5 REV. 1.0 E QU.f\\LITY ASSURANCE R-TYPE: C1,31 w i Operations PROGRAM MANUAL Page 1 of 5 AGF ' TITLE) JfM2@]{QNS. ?ROCEDURES EFFECTIVE DATE: 4/22/92 t h.DB M IN1! A[ ' DIRECTOR. NUCLEAR SAFETY W4 PREPARED B u_ QA HANAG E.0,, a . )di N VICE PRESIDENT. OPERATIONS: - - m Udf y 1.0 PURPOS[ 1.1 Instrwtict::, procMures, and drawings for'the operational phase of Waterford4 are developed to prescribe thos9 activities that affect safety related functions. Activittas affecting quality are accomplished in accordance with these dot:uments. This Chapter defines the requirements f or developing and controlling instructions and procedures for safety related activities.. 2.0 REFERENCEE 0.1 PSAR 17.2.5. 2.2 USNRC Regulatory Guide 1.33 Revision 2, February 1978 (which endorseo ANSI N10.7 1976, ' Administrative Controls and Quality C. Assurance for the Operational Phase of Nuclear Power Plants.') 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 DIRFCTORS/MANACERS Directors and managers are responsible for che ' development and approval of safety related procedures and instructions which affect activities within their' area of responsibility. In addition, directors and managers are responsible for ensuring that the appropriate individuals are trained, prior to the implementation of 1, each new and revised procedure. 4.2 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is' responsible for the review of' -. safety related Waterford-3. procedures, instructions, drawings, and specifications to ensure the inclusion of applicable ~ Quality Ass.urance Program requirements. e

WATERFORD 3 g Entergy CHAPTER 5 REV. 1.0 OUALITY ASSURANCE n-TYPE: C1.31 = Operations PROGR AM MANUAL Page 2 of 5 4.3 PLANT OPERATIONS Ri: VIEW 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 accordanc6 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 daccribes the appropriate method for procedure development to assure consistency in preparation. The governing procedure shall incorporate 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: a. Title b. Statement of applicability c. References d. Prerequisites e. Precautions f. Limitations and Actions g. Main Body

1 WATERFORD 3 CHAPTER 5 REV. 1.0 &_Entergy QUALITY ASSURANCE R-TYPE: C1.31 ~ Operationu PROGRAM MANUAL-pago 3 f5 o h. Acceptance criteria 4 1. Checklists 5.2.3 When procedures contain critical steps and additional assurance is desired for plant operation and routine maintenance, procedures should contain verification i signoffs. Verification signoffs shall be accomplished by a qualified person who does not have responsibility for performing the work or directly supervising the work with exception to plant operations activities by operators requiring verification by he SS/CRS who are direct supervisors. 5.3 kEVIEW AND APPROVAb 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 t enerated by the reviewer shall be resolved by the authoriuing erganization, 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. O -y., e,.

WATERFORD 3 gEntergy cilAPTER 5 REV, 1.0 QUALITY ASSURANCE R-TYPE: C1,31 w 0 Operations PROGRAM MANUAL Pago 4 of 5 5.3.6 Procedures shall be reviewed to determine if the following conditions are satisfied a. The procedure / instruction is in compliance with upper tier procedures, the Quality Assurance Program, and the FSAR: b. Appropriate qualitative and quantitative acceptance criteria are included for determining that safety related activities are satisfactorily accomplished c. The need for inspection, identification of inspection personnel, and documentation of inspection results have been properly specified d. The necessary inspection requirements, methods, and acceptance criteria have been identified: and e. 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 or revised source C 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 REVI!M 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 deletions a. Changes the design, description, function and/or -operation of a system, structure, or component described in the FSAR: b. Changes the procedures as described in the PSAR _____A_-_ _...--a._--_.J

WATERFORD 3 g CHAPTER 5 REV. 1.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Page 5 of 5 c. Conducts tests or experiments not described in the FSAR: d. Creates a condition or conducts an operation which I exceedw. or could result in exceeding, the limits identified in the Technical Specifications. 5.5 PROCEDURE COMPLIANCE 5.5.1 All personnel should be cognizant of their responsibility to adhere to pro,:edures and instructions. Prior to performing any quality related activity, all personnel are responsible to ensure thats a. procedures or instructions have been developed to control the activity: b. they understand the content of the procedure or instruction s.nd are capable of following it without deviations c. they understand that work must be stopped when a procedure or instruction cannot be specifically followed; d. they understand the process to change procedures and instructions or at a minimum, know to notify their supervisor if an inadequacy is discovered and e. they understand that management demands that procedures and instructions be specifically followed or work must be stopped, regardless of cost or

schedule, 5.5.2 Supervisors should routinely discuss procedural compliance with the personnel in their departments.

When it is discovered that a procedure is not deficient but could be improved (quality is not affected), then work may continue as applicable and a formal procedure change request should be initiated. Procedural improvements are encouraged. Personnel should notify their supervisor if a procedure change should be expedited to improve ongoing or near future work. 6.0 ATTACHMENTS None J

WATERFORD 3 CHAPTER 6 REV. 2.0 = Entergy OUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL P"9* 1 of 6 h~ TITLE: DOCUMENT.CONTRQL EFFECTIVE DATE: 11/01/92 PREPARED BY DIRECTOR, NUCLEAR SAFETY: 41 QA MANAGER: l VICE PRESIDENT, OPERATIONS: W ig v 1.0 PURPOSE I 1.1 The requirements 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 and 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 Individuals 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 FSAR 17.2.6. C 2.2 ANSI N18.7-1976, " Administrative Controls and. Quality Assurance for the Operational Phase of Nuclear Power Plants." 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is respunsible for a document control system which includes the development and implementation of procedures and instructions for the processing and distribution of: =r**- t,ap

WATERFORD 3 e_ Entergy CHAPTER 6 REV. 2.0 QUALITY ASSURANCE R-TrPE: c1.31 ~ Operations PROGRAM MANUAL Page 2 of s a. Test procedures for maintenance, modification, and operation of equipment and systems; b. Safeguards information; c. The Plant Operating Manual; and d. Other documents as assigned. 4.1.2 The General Manager, Plant Operations is also responsible for ensuring that as-built drawings are utilized for plant i 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 l procedures and instructions for the processing and distribution oft a. The safety Analysis Report; b. Design documents, including drawings and specifications; c. The Entergy Operations Management. Manual, Vol. IV; d. Fabrication, construction, installation, inspection, test, maintenance, modification, and operation procedures; e. Vendor technical manuals and service bulletins; f. Safeguards informations g. Safety related departmental-procedures; and h.. Other documents as assigned. 4.3 DIRECTOR, DESIGN-ENGINEERING 4.3.1 The Director,-Design Engineering is responsible for the -revision and update of-controlled drawings and configuration documents to reflect design changes.

_ =. 4 WATERFORD 3 eEntergy CllAPTER 6 REV. 2.0 w QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL P*S* 3 f6 4.4 DIRECTORS / MANAGERS 4.4.1 Directors / Managers are responsible for the development and implementation of: a. Safety related departmental procedures, as applicables. and b. Other documents as assigned. 5.0 DETAILS 5.1 DOCUMENT CONTROL 5.1.1 Document control measures shall be prescribed by procedure and shall provide fort a. The preparation, review, approval and issuance of documents, including their revisions, by authorized individuals or organizations; b. Assuring that proper documents are used in perfonning an activity; and c. Establishing and implenienting 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 operation 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. Aftar review comments have been~ resolved, the documents shall be epproved-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. l r e f%.e. -*p, +am W

~ __. i WATERFORD 3 e_Entergy caArTra e arv. 2.o QUALITY ASSURANCE a-Types ca.31 ~ Operations PROGRAM MANUAL P*S* 4 '6 I 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. Approved changes shall be included in the instructions, procedures, drawings, and other appropriate documents. 5.2.3 Field drawings and sketches which are prepared by Entergy operations personnel to clarify or provide 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 includes a. Procedures that describe how documents are received, distributed, and controlled; b. The identification of documents to be controlled;. c. Documents to be distributed in accordance with distribution lists; d. Methods for dispositioning outdated documents to -preclude inadvertent uses e. Distribution and maintenance of a controlled document list to aid in the identification of document status;- and f. 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 are performed.

WATERFORD 3 e.Entergy CHAPTER 6 REV. 2.0 QUALITY ASSURANCE R-TYPE: cl.31 ~_ Operations PROGRAM MANUAL Paga 5 of 6 _g 5.3.3 Hatter lists of controlled documents shall be available at specific locations to preclude the uc, 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, spweifications, 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 includes a. Safety Analysis Report; b. Design documents including calculations, drawings, field drawings and sketches, specLfications, change requests, and analysis; c. Vendor Manuals; d. Entergy Operations Management Manual, Vol. IV; e. Inspection and test procedures for test, fabrication, [} construction, installation, maintenance, modification, \\s,/ and operation; f. As-built documents; g. Quality Assurance Program Manual; h. Emergency Plan; i. Physical Security Plan; j. Plant Operating _Hanual; k. Quality Assurance Procedures; no 1. Engineering Procedures; m. Training Procedures; n. Site Support Procedures; o. Plant Hodification and Construction Procedures; s '[O

- (~'y t - WATERFORD 3 -caAPrra e arv. 2.oL be En ergy QUALITY ASSURANCE R-TYPE:- ' C1. 31 -- ~ Operations -

PROGRAM MANUAL Page 6 of 6

...:g - p.- Nuclear Safety Procedures; and- ~ q. -Approved Interim Change Documents. 60 ATTACHMENTS None i i d. 4 1 d 4 -j. -[ s J U. 4 w a+4 c =

' WATERFORD 3 A ntergy CHAPTER 7 REV. 2.0 E w QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL Page 1 of 7 s TITLE: CONTROL OF PURCHASED MATERIALS, EFFECTIVE DATE: 11/01/92 EOUIPMENT AND SEly1Q31 h# DIRECTOR,. NUCLEAR SAFETY: 1 JPARED BY -- u b QA MANAGER: c VICE PRESIDENT, OPERATIONS: A V'N 1.0 PURPOSE 1.1 Safety related material, equi.pment, and services, whether purchased directly or through others,. conforms to procurement document specifications as described in Chapter 4. Provisions are nado, 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 post installation teating 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 verily that documentation, C

such as inspection records and cortifications,.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 sorvices are contained in approved written procedures.

2.0 REFERENCES

2.1 FSAR 17.2.7 2.2 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.') 2.3 ANSI N18.7-1976, ' Administrative Controle and Quality Assurance for the Operaticaal-Phase of Nuclear Power Plants." in i a

. WATERFORD 3 eEntergy CHAPTER 7 REV.'2.0 -QUALITY ASSURANCE R-TrPE:- C1.31 ~ Operations PROGRAM MANUAL .Page 2 of 7 1 3.0 DEFINITWONS None 4.0 RESPONSIBILITIES 4.1 DIRECTOR, SITE SUPPORT The Director, Site Support is -responsible for 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 site specific procurement. 4.1.1 MATERIALS, PURCHASING AND CONTRACTS MANAGER The Materials, Purchasing and Contracts Manager is responsible for vendor selection, the coordination of contractor selection, and the preparation and issuance of site specific purchase orders and contracts to support the procurement of material, equipment, - spare and replacement parts, and services. 4.2 DIRECTOR, DESIGN ENGINEERING The Director, Design Engineering is responsible fors 4.2.1 Assisting in the establishment of quality assurance and technical requirements in quality related procurement documents. 4.2.2 Reviewing selected requests for spare and replacement parts designated EQ to determine their technical and quality requirements, if required. 4.3-DIRECTORS / MANAGERS Directors / managers are responsible for ensuring the initiation of procurement documents for equipment, materials, and services in suppcrt of their. departmental activities.- 4.4 QUALITY ASSURANCE MANAGER 4.4.1 The-Quality Assurance Manager is responsible for assuring that appropriate quality standards are maintained throughout the procurement process. 4.4.2 The Quality Assurance Manager is also responsible for performing inspections of site storage facilities.

WATERFORD 3 & ntergy CHAPTER 7 REV. 2.0 =E QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Page 3 of 7 i 4.5 MANAGER, QUALITY (SUPPLIER) The Manager, Quality (Supplier) is responsible for establishing and maintaining a qualified suppliers list through the conduct of pre-award evaluations, annual evaluations, periodic audits and in-process surveillances. 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 (QSL), when required, to assure compliance with codes, standards, and regulatory commitments. Suppliers, contractors, and i 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 tha results documented and maintained in accordance with quallsf records management procedures. 5.1.2 The evaluation of vendors shall be based on one or more of the following criteria a. The vendor's ability to comply with the requirements of the Quality Assurance Program as applicablw 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 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. 1

WATERFORD 3 S,Entergy ' CHAPTER 7 REV. 2.0 QUALITY ASSURANCE R-TYPE: C1.31 Op'erations PROGRAM MANUAL. Page 4 of 7 O \\u ) systems, components, ~5.1.4 Suppliers of safety related structures, 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 shall be a joint activity betweens the cognizant and/or originating department; Purchasing, Materials-& Contracts; and the supplier Quality Assurance l departments. 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 a. The need to perform surveillance (s) of the vendors /subtier sendors 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. V 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 and frequency of audits /surveillances - L required to monitor performance and/or maintkin vendor qualifications. g. The timing or schedule for each of the above, an applicable, h. The Entergy Operations organization or authorized representative responsible for performing each -of the above as applicable. ,-s '(w) i

WATERFORD 3 eEntergy CHAPTER 7 REV. 2.0 QUALITY ASSURANCE R-rrPE: ci.31 Operations ' PROGRAM MANUAL Page 5 of 7 p V 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 shall includes a. Instructions that specify the characteristics or processes to be-witnessed, inspceted or verified, and accepted; b. The method of surveillance and the extent of documentation required; and c. 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 at intervals \\s - consistent with the importance, complexity, and quantity of the item or service. 5.4 RECEIPT INSPECTION AND ACCEPTANCE 5.4.1 Receipt inspection of safety related material, components, and equipment shall be performed'in accordance with written procedures which provide for the followings a. The material, component or equipment is properly identified and corresponds to the raquirements of procurement documentation; b. Material, components, equipment, and records are-inspected in accordance with procurement document' requirements prior to installation or use; c. As applicable, inspection records or certificates of conformance attesting to the quality of. material, components, and equipment are available at Waterford prior to installation or use; and -~() b4

WATERFORD 3 CHAPTER 7 REV. 2.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 e Operations PROGRAM MANUAL P"9* 6 f7 9 d. 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. 5.4.2 Methods for product acceptance include evaluation of the vendor's QA Program, source inspection / surveillance, receipt inspection, post installation testi.ig, or qualification testing by Entergy operations or a qualified test laboratory. The methodology to control these acceptance methods shall be specified in procedures. Acceptance by --3 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 E 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 tb following methods: technical verification of data; auditi inspection; surveillance; or review of objective evidence for conformance to procurement documents. O 5.5 PROCUREMENT AND DEDICATION OF COMMERCIAL GRADE ITEMS 5.5.1 Commercial grade material, parts, and equipment that are essential to the safety related functions of structures, systems, and components shall be evaluated for suitability of application. The evaluation results shall be documented. } 5.5.2 The preparer of the purchase requisition is responsible for clearly identifying the commercial item to be procured and listing the receipt inspection requirements. The item selected shall be identical to the original or an approved alternate. 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 in the procurement documents, as necessary, to dedicate the commercial grade item for une in a safety related application. e

WATERFCRD 3 e% CHAPTER 7 REV. 2.0 Entergy QUALITY ASSURANCE R-TrPE: cl.31 Operations PROGRAM MANUAL Page 7 of 7 5.6 SPARE AlO REPLACEtCNT PARTS 5.6.1 Spare and replacement parts for safety related systems, etructures, 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. Suppliers shall furnish the following records, as a minimum, to Entergy Operations or its agents a. Documentation that identifies the purchased material or equipment and the specific procurement 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 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. 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 acce; dance with approved procedures. 6.0 ATTACHMENTS None

WATERFORD 3 gEntergy CHAPTER-8 REV. 1.0 QUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL Page 1 of 3 D TITLE: IDENTIFICATION AND CONTROL OF EFFECTIVE DATE: 4/22/92 MATERIALS. PARTS AND COMPONENTS PREPARED DIRECTOR, NUCLEAR SAFETYr m4 QA MANAGE Nk VICE PRESIDENT, OPERATIONS: h p 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 FSAR 17.2.8 i. 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 DIRECTOR, SITE SUPPORT The Director, Site Support.is responsible for ensuring the development and maintenance of procedures for the identification and control of safety related items which are received, stored, and-issued at the plant site. 4.1.1 MATERIALS, PURCHASING AND CONTRACTS MANAGER l l P The Materials, Purchasing and Contracts Manager is j responsible for: a. 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. /S b. Verifying that materials, parts, and components are C properly identified at receipt

1 WATERFORD 3 CHAPTER 8 REV. 1.0 Entergy QUALITY ASSURANCE R-TYPE: cl.31 e Operations PROGRAM MANUAL Page 2 of 3 s V c. Verifying the transfer of required identification or traceability information prior -to items being subdivided. 4.2 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 inspections. 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 to ensure compliance with requirements of the Waterford-3 Quality Assurance Program and applicable codes, standards, and regulations. Directo~s and managers are also responsible for developing and mainu ining procedures for the identification and control of items drawn from stores, installed, or used. O 5.0 DETAILS N.j 5.1 IDENTIFICATION AND CONTROL 5.1.1 The identification of applicable safety related materials, 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 ver!fication 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 tre item up to and including installation and use. This icentification shall relate the item to (m. applicable design or other specifying documents. t\\__- _---____---._-.__-____--_-.-_-_.__.___,_._.-_--.__________-__.-.-_---__.___..__._-_____--____--.____---_a

WATERFORD 3 A ntergy CHAPTER 8 REV. 1.0 E QUALITY ASSURANCE R-TYPE: cl.31 m gs Operations PROGRAM MANUAL Page 3 of 3 .-t 5.1.5 Procedures shall include provisions to prevent the,use of incorrect er 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. 5.3 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 fo: traceability during an item's life (i.e., between the Architect Engineer's

system, the _- NSSS supplier's-system.

manufacturer's

systems, and the Wa te rf o rd Station Information Management -System) in' order to ensure-d 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 ass a. Provisions for ' the maintenance or replacement. of-markings and due to damage during handling or aging; b. Protection of markings on items subject to excessive deterioration due to environmental exposure; and-Provisions for updating existing plant-records. c. 5.4-LIMITED LIFE ITFMS 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-ms

WATERFORD 3-A ntergy. CHAPTER 9 REV. 1.0 E QUALITY ASSURANCE n TYPE: cl.31 y Operations PROGRAM MANUAL Page 1 of 5 O TITLE: CONTROL OF SPECIAL PROCESSES EFFECTIVE DATE: 4/22/92 PREPARED B I DIRECTOR, NUCLEAR SAFETY: tu <d. Luh N QA MANAGER / l&L VICE PRESIDENT, OPERATIONS: v v 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 FSAR 17.2.9. 2.2 USNRC Regulatory Guide 1.37, 3/73, ' Quality Assurance Requirements C-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.") 2.3 SNT-TC-1A-1980, " Recommended Practice for NDE Personnel Qualification and Certification." 2.4 Regulatory Guide 1.58 Revision 2, September 1980 (which endorses ANSI N45.2.6-1978, " Qualifications of Inspection, Examination, and-Testing Personnel for Nuclear Power Plants.") i 2.5

ASME, Section. XI, 1980 Edition through Winter 1981 Addenda (In-service Inspection Program commitment).

2.6 ASME, Section V, latest Edition and Addenda, as applicable. 2.7 ASME, Section IX, latest Edition and Addenda or.as otherwise specified in applicable instructions,- procedures, or specifications. j-2.8 AWS D1.1, latest edition or as otherwise specified in applicable instructions, procedures, or specifications. 2.9 ANSI B31.1, latest edition or as otherwise specified in applicable instructions, procedures, or specifications. LO v

WATERFORD 3 gEntergy. CHAPTER 9 REV. 1.0 QUALITY ASSURANCE R-TYPE:. cl.31 . ~. _ Operations-PROGRAM MANUAL Page 2 of.5 3.0 DEFINITIONS None 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. 4.2 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION Tha Director, Plant Hadification and Construction is responsible for the establishment, approval and implementation of procedures - for selected special processes as listed in 5.1.2. 4.3 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is -. responsible for assuring the establishment of the control of spe.cial processes program and for verifying the effectiveness of its implementation through reviews, inspections, 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.. 5.0 DETAILS 5.1 SPECIAL PROCESSES SUBJECT TO CONTROLS 5.1.1 Special processes are those. safety related 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; 3-w m-, 7 -u.,

)WATERFORD 3 g Entergy CHAPTER 9 REV, - l '. O QUALITY ASSURANCE R; TYPE: cl.31-e Operations: PROGRAM MANUAL Page 3 of 5 O c. NDE d. Chemical cleaning - e. Concrete and grout placement (seismic applications): l f. _ Reinforcing steel cadwelding (seismic application) g. Brazing and h. Protective coatings. 5.1.3 The above listed processes, and other-activities requiring-- special controls as determined-by Entergy Operations management, shall be designated in approved procedures, drawings, or_ specifications, 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 applicables C.' a. Qualification / certification requirements .for personnel involved with; the' performance 'of the special process b. Calibration, certification, or qualification requirements of equipment used in the performance of the.special processi c. Identification _ requirements :for consumables: to be utilized in the performance of the special processi - d. Documentation of the methods and results required to qualify the process; e. Documentation of the a'ctivity and process results; f. Process _ parameters and environmental conditions to be established or maintained; g. Codes _ and standards applicable to the activity or process; h. The activity and process acceptance-criteria; and 1. The methods and sequences, when necessary, for the: performance of the special process. 4

WATERFORD 3 C11 APTER 9 REV. 1.0 g Entergy QUALITY ASSURANCE R-TYPE: cl.31 - Operations PROGRAM MANUAL Page 4 of 5 d _E 4 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 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 failing retest shall not be' allowed to perform I the special process until they have.been recertified. 5.3.3 A Level III inspector shall review and concur with NDE procedures to assure that procedures are in accordance with-applicable requirements of_ governing

codes, standards, and specifications.

A Level III inspector shall provide and/or assure training, examination, and qualification and recommend certification of Level I,'II, and III inspection personnel. 5.3.4 ~For special processes not covered by existing codes or standards, or when the quality-requirements exceed the requirements of established codes or standards, the I necessary qualificationa of personnel', procedures, and/or equipment shall be defined. 5.4 DOCUMENTATION / RECORDS 5.4.1 An NDE inspector certified as. Level II or; higher in--the applicable discipline, shall ' evaluate and approve the results of nondestructive examinations. Documentation of-this evaluation and approval shall be maintained and controlled as a quality assurance record. _NDE documents _ prepared _by contractor personnel shall be' independently-reviewed and approved ~ by _an Entergy Operations Level II or III inspector certified in the applicable discipline. The Entergy Operations review of contractor reports mt.y be waived but only as approved-in writing-by-the Waterford-3 QA Manager. 5.4.2 Qualification, certification, or calibration records _ of. special process personnel, procedures, and equipment, _o r other records relating to the performance of special processen shallJ be prepared and maintained as quality assurance records. .The Quality Assurance organization shall verify their existence and adequacy through reviews, audits, surveillances and inspections. C') u

WATERFORD 3-gEntergy CHAPTER 9 REV. 1.0 QUALITY ASSURANCE R TYPE: cl.31 _~ Operations PROGRAM MANUAL Pago 5 of 5 0 5.4.3-Special process coatrol records of vendors may be retained or submitted ~ to Entergy Operations as directed in procurement documents. 6.0 ATTACIDIENTS None C o v s

WATERFORD 3 a,Entergy CHAPTER 10 REV. 2.0-QUALITY ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL Page 1 of 9 (m TITLE: INSPECTION EFFECTIVE DATE: 11/01/92 h 44 h PREPARED D DIRECTOR, NUCLEAR SAFETY: QA MANAGER VICE PRESIDENT, OPERATIONS:\\\\ V' M l.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 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. tV

2.0 REFERENCES

2.1 FSAR 17.2.10 2.2 ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants." 2.3 Regulatory Guide 1.58, Rev. 2, September 1980 (which endorses ANSI N45.2.6 - 1978, "Qualificatione of Inspection, Examination, and Testing Personnel for Nuclear Power Plants.") 2.4 ASME Code, Section XI, 1980 Edition through Winter 1981 Addenda 3.0 DEFINITIONS 3.1 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 directly responsible for, or supervisor of, the activity being inspected. p u ( l

WATERFORD 3 e_Entergy CHAPTER 10 REV. 2.0 QUALITY ASSURANCE R-TYPE: C1.31 ~~ Operations PROGRAM MANUAL Page 2 of 9 i !.%d 4.0 RESPONSIBILITIES 2 i 4.1 CENERAL MANAGER, PLANT OPERATIONS The General Manager, Plant Operations is responsible fort 4.1.1 the control and maintenance of ciWII interfaces involving inspections related-to mod!'ications,-repairs, and replacements under the American Society of Mechanical 4 Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, Section III, Division I Class 1, 2, 3, and MC components and their supports; 4.1.2 support of the Peer Inspection program by recommenoing and providing personnel to be certified and to perform peer inspections; 4.1.3 preparing maintenance and modification work instructions which contain the required inspection holdpoints and criteria. 4.2 DIRECTOR, DESIGN 2NGINEERING 4.2.1 The Director, Design Engineering is responsible for the .[ j control and maintenance of the Waterford-3 ASME Ten Year In- \\%/ service Inspection Program. The Director, Design Engineering is also responsible for all ANII interfaces in matters related to'the In-service Inspection 1:rogram. 4.3 MATERIALS, PURCHASING AND CONTRACTS MANAGER 4.3.1 The Materials, Purchasing and contracts Manager is responsible for the performance of receipt inspections. 4.4 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for 4.4.1 The development and administration of the plant f.nspection program at Waterford-3; 4.4.2 certifying inspection personnel; 4.4.3 reviewing maintenance-and modification work instructions, inspection and test plans, and procedures to assure that appropriate inspection criteria has been included; m - \\V { - i + w g v v w er---w awa-en. ,w--

WATERFORD 3- &,Entergy: CHAPTER 10 REV. 2.0. QUALITY ASSURANCE R-TYPE: ci.31 Operations PROGHAM MANUAL- - Page 3 of 9 T 4.4.4 conducting or coordinating inspections of modifications and maintenance activities; 4.4.5 conducting inspectione of materJals in storage. '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 performed in accordance with procedures approved by Entergy Operations; ) = b. Inspection results are documented, evaluated and their acceptability determined by responsible personnel in accordance with approved procedures;- c. Inspection procedures,= inspection personnel qualifications and certifications are concurred with by the Quality Assurance Manager; d. Inspections are performed by certified' individuals other than those who performed or directly supervised the activity being inspected;- e. Inspectien 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. Inspection..ctivities not conducted by Quality Assurance are periodically reviewed by Quality. Assurance. J y + m .~

WATERFORD 3-' H 8_ Entergy CHAPTER 10' REV. 2.0 QUALITY ASSURANCE R-TYPE: C1.31. ~ Operations PROGRAM MANUAL P89* 4 f9 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 inspections are performed by qualified and certified personnel, while storage inspections are performed by qualified and certified QA-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 inspection, certain nondestructive testing, and containment vessel leak rate tests and inspections, may be conducted by off-site Entergy Operations, or contractor personnel. In such instancee, 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 meets the criteria noted in the procedure and that inspection results are within the specified acceptance criteria 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 II or higher in the appropriate discipline. Verification of conformance is by the' certified Level II 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, c and specifications. 5.2.2 Procedures, instructions, and checklists governing inspections shall provide for the-following, as applicables a. Criteria for determining when inspections are required and how they are performed; b. Identification of individuals or groups who established inspection requirements;

I -WATERFORD 3- -CHAPTER 10 REV. 2.0 ,Entergy-QUALITY ASSURANCE a-nPE: cl.31 Operations PROGRAM MANUAL P"9's 5 of 9 jkihP c.- Acceptance and rejection criteria; d. Identification of individuals or groups responsible for performing: inspections; e. Identification of the points where inspections are required; f. Identification of characteristics to be inspected; g. A description of the inspection method; h. Identification of required measuring and test equipment (M&TE); i. Accuracy, precision and calibration requirements for M&TE; j. A method for recording the identity of.the recording inspector or' data recorder and recording the inspection results and/or observations; I k. A method for recording evidence of completing and i verifying a manufacturing inspection or test l_ l operation; l L 1. Identification of procedures, drawings, and l specifications, including revision level used to-L conduct the inspection; m. Identification of specialized qualifications,- certifications, or skills required by codes or standards for personnel performing inspections; and n. Verification of material acceptability prior to-installation or use. 5.2.3 Quality Assurance shall review safety related inspection procedures to verify the inclusion of the above r I requirements. s 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 data. Accuracy and precision requirements shall be banod 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. L

WATERFORD 3 e,Entergy CHAPTER 10 REV. 2.0 QUALITY ASSURANCE n-TYPE: C1.31 Operations PROGRAM MANUAL Page 6 of 9 ,m t 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 required, 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 for inspection personnel. 5.3.3 The inspector qualification program shall be reviewed and concurred with by the Quality Assurance Manager or his designee. The Quality Assurance Manager shall be responsible for approving the certification of inspectors. 5.4 INSPECTION BY SAMPLING METHODS p i j \\_j 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 approved by the Quality Assurance Manager or his designee. 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 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, shall 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. ("~ ( )/

WATERFORD 3' CHAPTER 10 = REV. 2.0-Entergy QUALITY ASSURANCE R-TYPE: C1.31 =, Operations : PROGRAM MANUAL - Page 7 of 9-fm t'- 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. I 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. 5.7.2 Safety related suppliers and vendors shall be required through procurement documents, where applicable, to submit their manufacturing plans to Entergy Operations. This-shall be done prior to manufacture in their shops or shops of- .'} their suppliers no that Entergy Operations has-the (' (s,- opportunity to identify mandatory-inspection hold points for witness by an Entergy Operations' representative. Work may not proceed beyond these hold points without Entergy Operations 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 waivo the inspection requirement shall-be documented and shall be made in the same manner in which the inspection requirement was origi'nally approved. S.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 of safety related pressure retaining components and their supports. '\\_p{ v

WATERFORD.3 CHAPTER-10 REV. 2.0 Entergy QUALITY: ASSURANCE R-TYPE: C1.31 e Operations PROGRAM MANUAL Page 8 of 9 - l-o 5.8.2 The-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 (ANII) 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 (ANIIs) 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 ANII for establishment of ANII hold / witness-points prior to commencement of work. ANII hold / witness points shall not be passed without_ prior written consent or a documented telephone conversation from the ANII. Walved hold points ~~s i shall'be documented. ( 5.9.3 The results of' examinations performed under the Code during in-service inspections shall be presented to the ANII for review and acceptance. Inspection and examination data from code manufacturers which support the in-service inspection programs shall also be made available for ANII review. 5.10 RECORDS 5.10.1 Records of inspections, as a minimum, shall identify the -a. Item inspected; b. Date of inspection; c. Inspector; d. Type of observation; e. Results or acceptability; o

n.- g WATERFORD 3 a_Entergy . CHAPTER 10 REV. 2.0 QUALITY. ASSURANCE R-trPz ci. 31 - ~ Operations PROGRAM MANUAL P"9* S f' f._ Person approving inspection; and g. Reference to information on action taken in ~ connection with nonconformances.. 6.0 ATTACHMENTS None O O

WATERFORD 3 gEntergy CHAPTER 11 REV, 0.0 - QUALITY ASSURANCE RTYPE: cl.31 Operations PROGRAM MANUAL - Page 1 of 5 1'.%d TITLE: TEST CONTROL EFFECTIVE DATE: 04/01/91 ewI PREPARED BY: c[b DIRECTOR, NUCLEAR SAFETY:L a QA MANAGER: A [ 48/ VICE PRESIDENT, OPERATIONS: Mf d 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 = nervice and malfunctions are identified and_ corrected in a timely manner. Records document test 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 guidelines, and [. equipment technical manuals in order to determine required test N/ equipment accuracy.

2.0 REFERENCES

2.1 FSAR 17.2.11. 2.2 Waterford 3 " Inservice Inspection (ISI) Program." 2.3 NUREG-1117 " Technical Specifications." 2.4 10CFR50.59, " Changes, Tests and Experiments.' 2.5 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.") 2.6 USNRC, Regulatory Guide 1.94, Revision 1, April 1976 (which endorses. ANSI N45.2.5-1974, " Quality Assurance Requirements.for-Installation, Inspection, and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants.") 2.7 USNRC, Regulatory Guide 1.116, Revision 0-R, May 1977 (which endorses ANSI N45.2.8-1975, " Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems.")

~ i(- WATERFORD 3 gEntergy-CHAPTER 11 REV. 0.0 QUALITY' ASSURANCE RTYPE: cl.31 w Operations PROGRAM MANUAL Page -2 of 5 _,m 3M 2.8 USNRC.-Regulatory Guide 1.8,-Revision 1-R, September,~1975. 2.9 ANSI /ANS 3.1-1978, " Standard for Selection and Training of Personnel for Nuclear Power Plants." 2.10 USNRC, Regulatory Guide 1.58 - Revision 1 September, 1980 (which: endorses ANSI. N45.2.6-1978, " Qualification of Nuclear Power - Plant Inspection. Excmination and Testing Personnel.') 2.11 ANSI /N18.7-1976, " Administrative Controls and Quality - Assurance for-the Operational Phase of Nuclear Power Plants." 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS r The General Manager, Plant Operations is responsible for ensuring the (V development and implementation of procedures for-the Plant Operations staff testing activities, the approval of PORC recommended test procedures and results. 4.2.1 PLANT-OPERATIONS REVIEW COMMITTEE-(PORC) PORC is responsible for the review and recommendation to the General Manager, Plant Operations of 2

sting procedures

- that af fect _ systems / equipment : classified. as safety related prior to implementatiN; ar.d. for the review of test results which result in a change to the Technical Specifications or involve an unreviewed safety question. 5.0 DETAILS -5.1; TEST REQUIREMENTS 5.1.1 . Test procedures shall be prepared in accordance with Quality -Assurance Program xequirements-and the Technical Specifications _and provide, as required, for the following: Requirements Lnd acceptance limits contained in applicable a. design and procurement documents;

, -m.

=6 ) y

WATERFORD 3 g Entergy citAPTER 11 REV. 0.0 QUALITY ASSURANCE RTYPE: C1.31 , Operations PROGRAM MANUA.L Page 3 of 5 O-b. Instructions for performing the tests i c. Identification of necessary referances: d. Test prerequisites such as:

1) Personnel protection and/or access limitation:

2) calibrated instruments:

3) Adequate and appropriate equipment:

4) Trained, qualified, and licensed or certified personnel:

5) completeness of item to be tested:

6) Suitable and controlled environmental conditions: 7) Provisions for data collection and storage 8) Status of the systems and )

9) Protection of connected or adjacent equiptaent.

e. Criteria for determining accuracy requirements of tost equipments f. Inspection hold points g. Acceptance and rejection criteria h. Methods of documenting or recording test data and m ults: 1. Provisions for assuring test prerequisites have - mets and j. 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.

O

WATERFORD 3 e Entergy CHAPTER 11 REV, 0.0 QUALITY ASSURANCE RTYPE: cl.31 w Operations PROGRAM MANUAL Page 4 of 5 C t 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: a. That the test results are adequate and need not be repeated: b.

• aat the recorded data reveals. the adequacy of the equipment or system to meet the specified requirements:

and c. That 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 Specifications have been met. 5.2.3 The results of special tests 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. 5.4 TECliNICAL SPECIFICATIONS SURVEILLANCE TESTING 5.4.1 A Technical Specification Surveillance Testing. program including Inservice Inspection shall be established in written approved procedures, or other appropriate documents, to ensure that safety related ' structures. systems, and corponents 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. lO l w s r e,- ,,w,- -mw,.-,-- --.,---n-d.e-e--w. <-,m ,+n ww ,w m w

WATERFORD 3 gEntergy CilAPTER 11 REV. 0.0 QUAllTY ASSURANCE RTYPE: C1.31 w Operations PROGRAM MANUAL Page 5 of 5 'm 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 thes a. Item tested: b. Date of testi c. Tester or~ data recorders d. Type of test / observations e. Results and acceptability: f. Test procedures g. Action taken in connection with any deviations noted: and h. Person evaluating test results. 6.0 ATTACHMENTS Note l O b-l' ,e..., ,,,y..

WATERFORD 3 gEntergy CHAPTER 12 REV. 1.0 QUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL Page 1 of 5 0 TITLE: CONTROL OF HEASURING AND TEST EFFECTIVE DATE: 4/22/92 EQUIPMENT ^ PREPARED BY ._iLE DIRECTOR, NUCLEAR SAFETY: ( QA MANAGER: 8 A dlD VICE PRESIDENT, OPERATIONS: m M v v 1.0 PURPOSE 1.1 Heasuring and test equipment (HETE) utillaed 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 HETE apply to H&TE used by individuals or organizations participating in safety _ related C) activities. In addition, they include chemical / radiochemical H&TE, installed radiation monitoring I&C devices,.and health physics and radiological environmental monitoring HETE. 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 FSAR 17.2.12. 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 USNRC Regulatory Guide 1.30, August 1972 (which endorses ANSI l 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.') 2.4 NUREG-1117,_' Technical Specifications,' Section 4.02. 3.0 DEFINITIONS one

WATERFORD 3 Cl! APTER 12 REV. 1.0 l' Entergy QUALITY ASSURANCE R-TYPE: C1.31 w Operationo PROGRAM MANUAL Pago 2 of 5 C 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 and installed ILC devices used in safety related activities. 4.2 DIRECTOR 0/ MANAGERS Directors and Managers are responsible for the development, c maintenance, and impleme.1tation of procedures for activities related to calibration, control, and/or use of M&TE and installed 1&C devices, used in safety related activities. 4.3 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for the review and audit of the program f or control of measuring and test equipment and for ensuring the establishment and implementation of pro;edures for the calibration and control of M&TE employed in safety related activities by the Quality Assurance staff. 5.0 DETAILS 5.1 CALIBRATION 5.1.1 The calibration program shall be designed to ensure the accuracy of METE. 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: a. Lists of METE under the calibration program shall be developed and maintained; b. Ref erence standards, sequential instructions, and the identity of equipment to be used for calibrating HETE shall be identified. Manufacturers published standard practices, written instructions that accompany purchased equipment, or other approved instructions may be used: O

WATERFORD 3 gEntergy CHAPTER 12 REV. 1.0 QUALITY ASSURANCE n TYPE: C1.31 w Operations PROGRAM MANUAL Page 3 of 5 O c. H&TE shall be stored, calibrated, and used in environments which will not adversely affect its accuracy: d. H&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 e. H&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 j: degree of use, and the accuracy required of the equipment. Recalibration shall be performed on or. r before the designated calibration date. Reference standards shall be calibrated by qualified organizations: f. H&TE shall be calibrated using - reference standards whose calibration has a known valid'relationthip to nationally recognized standards or accepted va7.ues of natural physical constants. 'If no national standard exists, the basis for calibration shall be documented and approved by the cognizant managers g. H&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. h. H&TE shall be identified to provide traceability to calibration test data. The methods to be used for identifying H&TE shall be specified in applicable procedures 1. H&TE found' to be out of calibration shall be identified ao nonconforming and removed from service. Equipment tested or calibrated by the nonconforming equipment-since the last calibration shall be identified and sufficient investigations and C). reinspections performed to either re-establish the

t WATERFORD 3 & ntergy CHAPTER 12 REV, 1.0 E QUALITY ASSURANCE n-TYPE: cl.31 e Operations PROGRAM MANUAL Page 4 of 5 acceptability of the equipment or to confirm the nonconformance. The results of such investigations are documented j. 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: and k. Lost H&TE shall be treated the same as H&TE found to be out of calibration. 5.1.3 The following measures are taken for M&TE to c.aintain accuracy and obtain consistent results: a. Environmental and handling controlo are proceduralized: b. personnel are trained and qualified: c. Calibration status is checked before uses d. Damaged M&TE is documented and recalibrated: and e. 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,<ECORDS 5.3.1 An index or log shall be maintained to identifyi a. each piece of H&TE and installed I&C device: h. the individual and date of the last calibration c. the calibration interval; and d. the items inspected, tested, examined, or calibrated through the calibration program. O

i ATEWORD 3 h ntergy CilAPTER 12 REV. 1.0 E OUALITY ASSURANCE R TYPE: C1.31 w Operations PROGR AM MANUAL Page 5 of 5 J $ 3.2 Equipment and identification

lists, procedures, calibration

records, personnel qualif d. cations, and nonconformance reports sh611 be retained as required by codes, standards, and specifications.

6.0 ATTACilMENTS Hone C O u -~ __~ ~

i .WATERFORD 3 gEntergy CliAPTER 13 REV. 1.0 OUALITY ASSURANCE R TYPE: C1.31 w Operations PROGRAM MANUAL Page-1 of 5 TITLE: ilANDLING. STORAGE. PACKAGING. EFFECTIVE DATE: 4/22/92 AND SHIPPING PREPARED BY: il ' DIRECTOR NUCLEAR SA?ETY QA MANAGER:

1. (

4k VICE PRESIDENT, OPERATIONS: h i 'd 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 FSAR 17.2.13 2.2 10CFR71, Packaging and Transportation of Radioactive Material 2.3 USHRC Regulatory Guide 1.37. Revision 2 2.4 ANSI N45.2.1-1973, ' Quality Assurance Requirements for ' Cleaning Fluid Systems and Associated Components of Water' Cooled Nuclear Plants

• 2.5 US'iRC Regulatory Guide 1.38, Revision 2 2.6 ANSI N45.2.2-1972, " Quality Assurance Requirements for Pachaging, Shipping and Receiving, Storage and Handling of Items for Water Cooled Nuclear Plants' 2.7 USNRC Regulatory Guide 1.39. Revision 2. September 1977 2.8 ANSI N45.2.3-1973

' Housekeeping Requirements for Water Cooled Nuclear Power Plants' 2.9 USNRC Regulatory Guide 1.33, Revision 2, February 1978 2.10 ANSI N18.7-1976, ' Administrative Controls and Quality Assurance Requirements for the Operational Phase of Nuclear Power-Plants

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WATERFORD 3 gEntergy CllAPTER 13 REV. 1.0 OUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL Page 2 of 5 C 3.0 DEFINITIONS None ] 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER. PLANT OPERATIONS The General Manager. Plant Operations is responsible for ensuring controls are established for. handling, shipping (radioactive waste-and spent fuel), cleanin5 Preservation, housekeeping, and preventive maintenance of safety related items-(af ter installation). 4.1.1 OPERATIONS & MAINTENANCE MANAGER The 0;erations & Maintenance Manager is responsible for - a. tl e establishment and implementation of procedures required to perform preventive maintenance ofLitems in storage and those that are installed: b. handling, preservation, and cleanliness of parts and components released for-operations c. the establishment of cleanliness classifications (or zones) when opening components or systems for maintenance purposes which require specific internal cleanliness levels d. flushes or chemical cleaning of plant systems and e. assuring that systems and' components are appropriately placed and maintained in lay-up condition. when required. 4.1.2 TECHNICAL SERVICES MANAGER l: The Technical Services Manager is responsible for L housexeeping inside of the radiation controlled area and for the on-site handling, storage, packaging.. cleaning and j. release for shipping to a transit carrier of radioactive wastes,'and radioactive sources, r. I i 1 I. m

l WATERFORD 3 gEntergy CHAPTER 13 REV. 1.0 l QUALITY ASSURANCE R-TYPE: cl.31 w Operations PROGRAM MANUAL Page 3 of 5 4.2 DIRECTOR, PLANT MODIFICATION AND CONSTRUCTION The Director, Plant Modification and Construction is responsible for assuring the establishment and/or implementation of controls for i handling safety related items released for construction. 1 4.2.1 CONSTRUCTION MANAGER The Construction Manager is responsible for the establishment and/or implementation of procedures required for handling and the maintenance of items withdrawn from storage and those that are-installed buc are not yet released to plant operations, The Construction Manager is also responsible for 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, SITE SUPPORT The Director, Site Support is responsible for ensuring controls are established for

handling, shipping,

cleaning, preservation, housekeeping, and preventive maintenance of-safety related items in storage.

4.4 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for performing audits, surveillances and inspections of Waterford-3 activities associated with handling -. shipping, storage, and preventive maintenance of safety related items in storage. 4.5 MATERIALS MANAGEMENT SUPERINTENDENT The Materials Management Superintendent is responsible for handling, cleanliness, storage, and preservation of items within storage and warehouse areas in accordance with Quality Assurance. Program requirements. In addition, the Materials. Management Superintender.t is responsible for packing and shipping outgoing items (except radioactive waste and spent fuel) and for housekeeping within the receiving and warehouse areas. l-5.0 DETAILS 5.1 MATERIAL HANDLING, STORAGE, PACKAGING, AND SHIPPING (. 5.1.1 Under normal circumstances, the manufacturer's instructions or recommendations shall be followed and wm +1-q- s-pg r -y sr-e 'i--i-- y e s w'y-,eg, w t u v .d--e

p WATERFORD 3 g Entergy CHAPTER 13 REV. 1.0 QUALITY ASSURANCE R-TYPE: C1.31 e Operations PROGRAM MANUAL Pago 4 of 5 C, shall be implemented to maintain material integrity 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 equipment and 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 l developed to ensure that proper. handling.. storage, packaging, chipping, and preservation methods are used.

5.2 RADIOACTIVE MATERIAL SHIPPING CONTAINERS 1 The containers used for shipping radioactive -material shall be ' pre-certified containers as purchased from Fabricators.' Waterford-3 is not a fabricator of such containers, and will only use NRC licensed containers provided by approved fabricators. 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.

5.4 MATERIAL HANDLING EQUIPMENT Procedures shall be established for the testing of special. handling tools and equipment such as cranes, forklifts, and cables. Procedures-for material handling equipment shall establish requirements for inspections, frequency of inspections, and type of. inspections. Lif ting equipment used for handling safety related items shall have their rated capacity clearly marked. l 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

WATERFORD 3 gEntergy CHAPTER 13 REV. 1.0 QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL Page 5 of 5 indication of the p esence of special environments or the need for special controls. 5.6 PREVEllT1VE MAINTE!!ANCE 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 standards. 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 the time of receipt until the material is released for installation or use. 5.7 RECORDS Applicable procedures. Inst. ructions, and manufacturers information shall be prepared, reviewed, released, and controlled in accordance with applicable codes, regulations, and standards. 6.0 ATTACHHDITS None O v

l WATERFORD 3 gEntergy CHAPTER 14 REV. 0,0 QUALITY ASSURANCE RTYPE: C1.31 e Operations PROGRAM MANUAL Page 1 of 3 Ce TITLE: INSPECTION, TEST, AND EFFECTIVE DATE: 04/01/91 OPERATING STATUS -PREPARED BY: NmMM DIRECTOR, NUCLEAR SAFETY:

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WATERFORD 3 aEntergy CIIAPTER 14 REV. 0.0 QUALITY ASSURANCE RTYPE: C1.31 ^ m Operations PROGRAM MANUAL page 2 of 3 O t 5.0 DETAILS 5 5.1 INSPECTION AND TEST STATUS 5.1.1 Procedures 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, tage, 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 prev 9nt inadvertent operation. 5.1.4 Inspections and teste 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 i evidence is available to prove that the equipment or material is in conformance, affected systems shall be evaluated for i 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 to all Control Room personnel. O ,n-. --.,,,,----y,,,- y- -,y.,- a gm ,.,~g.r- .,.,,..en'y .na .,-9 ,.ga ,e - e g - ~

WATERFORD 3 g,Entergy-C11 APTER 14 REV. 0.0 QUALITY ASSURANCE RTYPE: C1.31 Operations PROGRAM MANUAL Page 3 of 3 C 5.2.2 Plant instructions that require equipment to be. removed 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. 5.2.3 The Technical Specifications define -operability requiremer.to for safety related structures, systems, and' components for the safe operation of the plant, including provisions for periodic tests-and inepections 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 1.imited 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 intlude the requirements for an independent verification by ~ either a second person or by a functional test to determine f operability. Documented evidence of the current. status o 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 DoctMENTATION AND RECORDS Procedures shall be estat.11shed to define - the-requirements for the development and maintenance of the documentation and records of the inspection, test and operating statur of the plant. - 6.0 ATTACIMENTS None-ro q +he fMy'm- =P g-t TF-W T-- f P"'T N r*NTt v $"-+*v*- -N'"r F v4 -tr N

WATERFORD 3 CHAPTER 15 REV. 2.0 ,Entergy QUALITY ASSURANCE R-TrPE: C1.31 Operations _ PROGRAM MANUAL P'9a 1 *f 4 O TITLE: HQE2NFORMANCE MATERIALS. FARTS EFFECTIVE DATE: 11/01/92 OR COMP _9MM IS PREPARED B DIRECTOR, NUCLEAR SAFETY: U f QA MANAGER VICE PRESIDENT, OPERATIONS: ~ a* N 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, notifiention to affected crganizations, 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 required.

3.0 REFERENCES

) 2.1 FSAR 17.2.15 3.0 DErtNITIONS None 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. The General Manager, Plant operations is also responsible for ensuring the screening, ovaluation, tracking and reporting of nonconformances to the NRC as required by 10CTR21. Additionally, the General Manager, Plant operations is responsible for approving nonconformances dispositioned " repair" or,"use as is", O

WATERFORD 3 4 CnAPTER is REv. 2.0 t Entergy QUALITY ASSURANCE R-TYPE: C1.31 1 ~ Operations PROGRAM MANUAL. page 2 of 4 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 DI RECTC), DESIGN ENGINEERING r 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 Director, Design Engineering is also responsible for dispositioning other nonconformances assigned to his organization. 4.3 DIRECTOR NUCLEAR SAFETY The Lirector Nuclear Safety is respandble for the review and audit of the nonconformance control system, and for initiating Licensee Event Reports under 10CFR50.73. 4.4 QUALITY ASSURANCE MANAGER The Quality Assurance Manager is responsible for the on-site Independent Technical Review function which includes providing a random independent review of nonconformance dispositions and closures during the operations phase. 4.5 ENTERGY OPERATIONS PERSONNEL All-Ente gy Operations personnel are responsible for identifying-and reporting nonconforming items on the appropriate nonconformance document. 5.0 DETAILS The following actions are required when safety related materials, parts, components,' systems, activities or services.do not conform to drawings, wpecifications, 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 3 necessary inspections and tests,: the associated hardware ) - shall-be considered nonconforming, e-3 --p-9 a p y e y y+w-*-w-' 9 gy -ry gg7g y - sp rae-- -M- <,9rr

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m. ~.. - .. m WATERFORD 3 CHAPTER 15 REV. 2.0 Entergy QUALITY ASSURANCE n-TrPsi C1.31 ~g Operations PROGRAM MANUAL Page 3 of 4 C 5.1.2 Nonconfomances shall be clearly and thoroughly described, documented and controlled. 5.2 NOTIFICATION 5.2.1 Organir.ations affected or potentially affected by a nonconforming item shall be notified upon identification of the nonconformanco. 5.2.2 Until suitable documentary evidence is available to show the affected material or equipment is in conformance, affected systems shall M evaluated for operability in accordance j with the Waterford-3 Technical Specifications and other license agreements (i.e., Equipn.ent Qualification program). 5.2.3 If a reportable event is identified pursuant to applicable NRC regulationst, required internal and external notification and documentation shall be initiated as required by procedures. 53 SEGREGATION 5.3.1 Nonconforming iterr.s shall be se*jregated, when practical, by placing them in a cleurly identiffied and designated hold area until properly dispositinned. 5.3.2 When segregation is impractical or impossibl 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 det'armine 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. O

i WATERFORD 3 A ntergy CHAPTER 15 REV. 2.0 E QUALITY ASSURANCE x-nrE ca.31 w Operations PROGRAM MANUAL P*9* 4 f4 Q 5.5 REINSPECTION-5.5.1 Reworked, repaired, or replaced items chall be reinspected and retssted in accordance with the original inspection and test rertirements 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, removed from the area to preclude further use er_ installation. 5.5.3 Final alternative action may be to return rejected material and equipment to the supplier or to scrap. Upon-satisfactory reinspection and completion of 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 Operations quality assurance records management proccdures.- [-s, Information contained in the documentation shall include but \\- may not be limited tot a. Disposition of the nonconformance; b. signature approval for disposition; c. Identification of the nonconforming items d. Description of-the nonconformance; and e. Inspection: requirements. 6.0 ATTACHMENTS Nono W 10 o i L

WATERFORD 3 CHAPTER 16 REV. 2.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 ~a Operations PROGRAM MANUAL Pege 1 of s O TITLE: R9EPl9.UYE_AQUQM EFFECTIVE DATE: 11/01/92 DIRECTOR, NUCLEAR SAFETY: PREPAREC B /\\ QA MANAGER VICE PRESIDENT, OPERATIONS: \\ A \\!dk i v 1.0 PURPOSE The Corrective Action Program assures that conditions adverse to quality, significant_ industrial safety concerns and significant plant reliability concerns are promptly identified and corrected.

2.0 REFERENCES

2.1 PSAR 17.2.16 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 GENERAL MANAGER, PLANT OPERATIONS 4.1.1 The General Manager, Plant Operations is responsible fort a. administering a root cause and trend analysis program for corrective action documents and for issuing a-periodic trend analysis report; b. reviewing corrective action documents to determine if the identified condition (s) represents a'significant condition adverse to quality; and c. performing reportability reviews for identified' conditions adverse to quality in accordance.with 10CFR21. =l O r

WATERFORD 3 A. Entergy CHAPTER 16 REV. 2.0 QUALITY ASSURANCE R-trPEi. Ca.31 ~ Operations PROGRAM MANUAL Page 2 of 5 9 4.2 DIRECTOR, NUCLEAR SAFETY 4.2.1 The Director, Nuclear Safety is responsible fort a. conducting reviews and assessments of the corrective action processes to ensure that the following program aspects are adequately addressed: 1. root cause determinations are completed; 2. corrective actions address root causes; 3. the_ appropriate schedule and level of management responsibility are identified as warranted by the safety significance of the specific items. and 4. performing reportability reviews for identified conditions adverse to quality in accordance with 10CFR50.73. b. monitoring individual tracking mechanisms to ensure that corrective actions for identified conditions are being implemented in a timely manner; and c. monitoring closure processes to ensure that at closure, corrective actions are complete and documentation adequately reflects completion. 4.3 DIRECTORS AND MANAGERS 4.3.1 Directors and Managers are responsible fore s a. assuring that procedures are developed and maintained to Lmplement the Corrective Action Program; b. assuring that personnel are familiar with tho' requirements of the Corrective Action Program; c. assuring departmental responsiveness to the corrective Action Program, both through problem identification and resolution when required; i d. verifying the completion'and adequacy'of corrective actions for. assigned corrective action documents; and e. processing and tracking corrective actions to assure prompt resolution for assigned corrective action document systems.

l WATERFORD 3 e_ Entergy CHAPTER 16 REV. 2.0 ? OUALITY ASSURANCE R-TrPE: C1.31 Operations-PROGRAM MANUAL Page a of s i 4,4 QUALITY ASSURANCE MANAGER f 4.4.1 Tho Quality Assurance Manager is responsible fors t a. auditing and reviewing the Corrective Action Program-to ensure acceptable implementation; and ) b. issuing stop Work Orders when conditions warrant. t 4.5 SAFETY REVIEW COMMITTEE l The safety Review Convoittee (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 conditions adverse to quality which have safety significance. 4.6 - ENTERGY OPERATIONS PERSONNEL Entergy Operations personnel are responsible for promptly: identifying and documenting conditions adverse to quality,- significant industrial safety concerns and significant plant reliability concerns on the appropriate corrective action documents. Entergy Operations personnel are also responsible for recommending that an activity be stopped if the specific. work is not being done ir, accordance with approved procedures, drawings,. specifications, or regulatory requirements.- 5.0 DETAILS 5.1 PROCEDURAL REQUIREMENTS - i 5.1.1 Procedures and instructions for correcting conditions adverse to quality,=significant industrial safety concerns and significant plant' reliability concerns shall include provisions fort a. deficiency identification-and immediate action; b. root cause determination; c. corrective action determination; d. prioritir,ation of corrective action; and-e. tracking and closure. A ie +~-s e g n ew J 4 w eaw e ,*-<---rr-wwar+----= .+-%v e +e er r - w, E r e vt +- e --wsw rM e- .w ir & es v em+w=ceur 9 y* e v-r 1 -1

} WATERFORD 3 8 ntergy cnAPTER is aEv. 3.o E QUALITY ASSURANCE R-TrPE: c1.31 1 ~ Operations PROGR AM MANUAL Page 4 of S-- t l 5.1.2 It is the responsibility of each individual employed by Entergy operations to promptly identify conditions adverse i to quality, significant industrial safety concerns or significant plant reliability concerns. 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 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 oft a. root cause determinations; b. corrective actions which address root causes; c. assignment of priority and level of management attention; d. tracking and closure. 5.3 STOP WORK ORDER (SWO) 5.3.1 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.1 The Quality Assurance Manager shall be notified if tho activity does not cease. 5.3.2 The Quality Assurance Manager or his designee should verbally request that the adverse activity be stopped at the-next safe stopping point. l. 5.3.3 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. Quality Assurance will notify. the appropriate management if it is ordered to stop work. -Work shall not proceed until the Stop Work order'is released by the Quality Assurance Manager. l --

WATERFORD 3 CHAPTER 16 REV. 2.0 Entergy QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL Page 5 of 5 0 5.4 CONTRACTOR RESPONSIBILITY Contractors porforming services or activities pertaining to safety related systems, structures, or components shall identify conditions adverse to quality, significant industrial safety concerns and significant plant reliability concerns according to Entergy Operations approved procedures. 5.5 RECORDS Corrective action reports and supporting documentation shall become quality assurance records. 6.0 ATTACHMENTS None O O

WATERFORD 3 gEntergy. CllAPTER 17 REV. 1.0 QUALITY ASSURANCE R-TYPE:..cl.31 , Operations PROGRAM MANUAL Page 1 of 5 p L TITLE: QUALITY ASSURANCE RECORDS _ EFFECTIVE DATE: 4/27/92 auI PREPARED BY [ N DIRECTOR NUCLEAR SAFETY: / QA MANAGER: E v$ $ dl I VICE PRESIDENT, OPERATIONS: ~ O M N y 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

2.1 FSAR 17.2.17 2.2 USNRC Regulatory Guide 1.88, Revision 2, October 1976 g 2.3 ANSI N45.2.9-1974 ' Requirements for Collection. Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants' 3.0 DEFINITIONS ~ None 4.0 RESPONSIBILITIES 4.1-DIRECTOR. SITE SUPPORT The Director, Site Support is responsible for assuring. the preparation of procedures for the execution of a document control and records storage program. 4.1.1 EMERGENCY PLANNING AND ADMINISTRATION MANAGER The Emergency Planning and Administration Manager is responsible-for providing. support for.the records management program. .CQ

WATERFORD 3 gEntergy CimPTER 17 REV. 1.0 QUALITY ASSURANCE R-TYPE: Cl.31 m Operations PROGRAM MANUAL Page 2 of 5 4.2 SECURITY AND GENERAL SUPPORT MANAGER The Security and General Support Manager in responsible for developing and implementing procedures controlling the Plant Staff record storage and document control systems. 4.3 DIRECTORS / MANAGERS Directors and managers are responsible for preparing and effectively implementing procedures which fulfill the applicable requirements of this chapter and applicable codes, regulations,'and standards. 5.0 DETAILS 5.1 PROCEDURAL CONTROLS 5.1.1 Procedures shall be developed for processing, preservation, retrieval, transmittal, inspection, correction, retention, storage, and dispssition of quality assurance records and, as a minimum, shall address the following: Quality assurance records which are to be generated a. in accordance with applicable procedures,. codes, standards, and regulations shall be.specified; b. -Quality assurance records shall. be

legible, completely filled out with all applicable data, reproducible, and adequately identifiable to an item or activity: and c.

Quality assurance records shall be validated by

stamping, initialing,

signing, or otherwise authenticating and dating by authorized personnel.

5.2 TYPES OF RECORDS 5.2.1 Quality assurance records shall include,. but are not limited to, the followings a. Design and construction' documents, such as: 1. design' drawings, specifications and work packages O

WATERFORD 3 gEntergy CHAPTER 17 REV. 1.0 OUALITY ASSURANCE R-TYPE: C1.31 w Operations PROCRAM MANUAL Page 3 of 5 9 2. results of

reviews, inspections,

tests, surveillances and audits:

3. procurement documents: 4. material certifications; etc. b. Operational documents, such as: 1. operatinE, 10888 2. maintenance and modification records; 3. reportable occurrences: 4. results of

reviews, inspections,

audits, tests, and material analysis 5.

personnel qualification records: 6. procedures and equipment qualification records: 7. procurement documents and specifications: 8. calibration records: and 9. nonconformance and corrective 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 originatir.g 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 stcred 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 documents shall provide requirements for records storage and maintenance by contractors and suppliers when the required records are not submitted to Entergy Operations.

f te= w e WATERFORD '3 - a,Entergy' CHAPTERD17L REV.L1,0-QUALITY ASSURANCE a_ Type : - cl. 31. Operations PROGRAM MANUAL page 4 of 5 i k./ . hen. quality assurance records have_ been _ lost, a search 5.4.4 W 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 { s_ substantiate the reconstruction. If reconstru' ton is not l possible, the original item or activity depit..sd, by the record shall be evaluated and, when necessary, repeated and/or items replaced or_requalified. 1 5.4.5 Quality assurance records shall be:.tdentifiable _and retrievable. Procedures for retention 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. 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 stor; age is employed, measures shall be taken to minimize the risk of damage or destruction from natural disasters, environmental a tremes, or vermin. b 5.4.7 Listings or inderes of cae required records. shall be 'V 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 followings a. Permanent records - 1. Design calculations: 2. Verifications of design calculations; and-Technical evaluations, analyses, and reports. D. .on-grmanent records - 1. ' Quality Assurance audit reports; 2. Vendor audit reports: and 3. Pre-award quality assurance surveys. 5.4.8 Quality assurcnce records that are received from outside organizations shall be. reviewed for technical adequacy,- compl etenes s, and. legibility and their-acceptance doct nted. Identified-record-deficiencies shall. be docu axed for resolution.

WATERFORD 3 CHAPTER 17 REV. 1.0 ,Entergy. QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL Fage 5 of 5 p; y 5.4.9 Procurement documents shall specify the retention-requirements when a manufacturer, supplier, consultant, or - contractor are to retcin radiographs, and when they are to transmit such radiographs to Entergy Operations. 6.0 ATTACIDENTS None 1 y i l i i i ~_ u 'l

1 WATERFORD 3 A ntergy . 3,o j cy,,,g,13

ggy, E

-QUALITY ASSURANCE R-TrPE: C1.31 4 ~ Operations - PROGRAM MANUAL Page 1 of 6 -TITLE: AUDITS EFFECTIVE DATE: -11/01/92 h DIRECTOR, NUCLEAR SAFETY: 44 4 PREPARED B A QA MANAGER: ( VICE PRESIDENT, OPERATIONS: L Lab 1.0 PURPOSE 1.1 In accordance with FSAR and Technical Specifications commitments, 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 FSAR 17.2.18 2.2 Waterford-3 Quality Assurance Program Manual, Chapter 16, " Corrective Action" ) 3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 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. 4.2 MANAGER, QUALITY (SUPPLIER) l The Manager, Quality (Supplier) is responsible'for planning, scheduling and conducting audits and surveillances of suppliers and contractors which provide materials, components, parts and services to be used in safety related applications. L l s (

WATERFORD 3 A ntergy CHAPTER 18 REV. 1.0 E QUALITY ASSURANCE R-TrPE: C1.31-w OpePations PROGRAM MANUAL : Page 2 of 6 l l 4.3 MANAGEMENT OF.THE AUDITED ORGANIZATION Management of the audited organization is responsible for investigating audit findings, scheduling corrective action including measures to prevent recurrence, and notification of the Quality Assurance organization in writing, of action planned or taken. 5.0 DETAILS 5.1 AUDIT PROGRAM 5.1.1 The object i ves of the audit program are a. To ensure that the Waterford-3 Quality Assurance Program requirements are established in appropriate documents; b. To verify on a regular basis by examination and evaluation of objective evidence that established requirements, methods, procedures, and instructions-are being implemented; } c. To assess the effectiveness of the Quality Assurance-Program; d. To identify program weakness and nonconformances; and e. To verify correction of identified conditions adverse to quality. 5.1.2 Audits-shall be performed in accordance with the Technical Specifications, management requirements, and in areas where. 10CFR50, Appendix B, requirements are being tmplemented. These areas shall include, as a minimum, the safety related activities associated withs a. Operation, maintenance, and modification; b. The preparation, review, approval,-and control of designs, specifications, procurement documents, instructions, procedures, and drawings;- c. -Receipt inspection; d. Indoctrination and training programs; l. I e. Implementation of operatiny end test procedures; )

f WATERFORD 3 a Entergy CHAPTER 18 REV. 1.0 QUALITY ASSURANCE R-TYPE: cl.31 e Operations PROGRAM MANUAL Page 3 of 6 f. Calibration of measuring and test equipment; g. Interface coatrol among Entergy Operations organizations and contractors / consultants; and h. Procuremers, vendors, manufacturers, and suppliers. 5.1.3 In addition to the above, audits shall be conducted of other activities defined as a special scope quality related activity in the Entergy Operations Management Manual. 5.2 PRE-AUDIT ACTIVITIES 5.2.1 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. 5.2.2 Quality Assurance audits shall be planned and conducted in accordance with approved procedures. Audit planning shall include 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 additional investigation is needed. 5.2.3 Unresolved items noted during previous audits shall be reviewed prior to checklist preparation and included for re-audit as appropriate. 5.2.4 The organization being audited shall make every effort to have personnel and other necessary resources available for the scheduled audit. Any change in scope or schedule of the audit is coordinated with the organization being audited. 5.2.5 Quality Assurance should determine the need for scheduling a pre-audit conference with the organization being audited. 5.3 AUDIT PERFORMANCE 5.3.1 Audits should include objective evaluation of work areas, activities, and processes including a review of selected associated 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 policies. i 1iiiinsii,iir-

WATERFORD-3 A_Entergy ~ CHAPTER 18 REV.-1.0-QUALITY ASSURANCE n-TrPEr cl.31 ~ Operations PROGRAM MANUAL Page 4 of 6 g 5.3.2lAny potential problem areas identified during the audit shall be immediately brought to the-attention of the management of the responsible organization.- 5.4 AUDIT PERSONNEL 5.4.1 Audits shall' be conducted by qualified auditors reho are experienced, trained, and f amiliar with the requirements and standards applicable to the area or activity _being audited. 5.4.2 Audit team members shall be independent cf any direct responsibilities for the activities which they audit. 5.4.3 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. 5.4.4 Lead auditors shall be certified. = Audit teams may, include-consultants or technical specialists as auditors under the supervision of a lead auditor. 5.5 POST-AUDIT ACTIVITIES C 5.5.1 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. 5.5.2 Audit findings shall be presented in written form. Written acknowledgement should be-obtained'from the audited organization for each' audit finding. 5.5.3 Formal audit reports shall be' issued within 30 working days of the post-audit conference or completion of the' audit. (operations QA audit reports shall be issued within 30 days am required by the technical rpecifications). Distribution includes a. the Quality Assurance Manager; b.- the manager of-the audited organization;- c. - the SRC (receives only operations-audit reports); and-d. the manager (s) responsible for corrective action.

WATERFORD 3 & ntergy CHAPTER 18. REV._1.0 E QUALITY ASSURANCE R-TYPE: cl.31 w - Operations PROGRAM MANUAL .Page 5 of 6 5.5.4 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. 5.5.5 The Quality Assurance manager,- supervisor or the audit teon leader shall be responsible for follow-up action (including re-audits) as required to ensure 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 shall be documented with reference to the original audit. 5.6 CORRECTIVE ACTION PI.AN 5.6.1 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 applicables 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; 4 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. 5.6.2 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' WATERFORD 3 & ntergy CHAPTER 18 REV. 1.0 E QUALITY ASSURANCE a-TypEi C1.31 e Operations PROGRAM MANUAL .Page 6 of 6 l 5.6.3 At any time when required response dates or proposed implementation dates cannot be reasonably met, the audited organization shall develop a response, advising the appropriate QA manager or supervisor of the new response date. 5.7 ANALYSIS OF AUDIT DATA Audit data shall be analyzed by the appropriate Quality Assurance manager or supervisor, who shall report any significant quality problems, including the need for re-audit of deficient areas, to the DL?ector, Nuclear Safety and the Vice President, Operations. 5.8 SURVEILLANCES 5.8.1 Entergy Operations Quality Assurance may conduct surveillances to verify that an item or activity conforms to specified requirements. These surveillances shall supplement regular audits. They are usually limited in scope, and usually involves a. A specific activity being performed; b. A procedure or portion of a procedure; or ) c. A specific area within a program. 5.8.2 Distribution of surveillance reports include the appropriata Quality Assurance manager and the affected organization. 5.9 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 1

1 WATERFORD 3 gEntergy APPENDIX: A. REv. 2.0 QUALITY ASSURANCE R-TYPE:.C1.31 w Operations PROGRAM MANUAL Page 1 of 7 .s ' TITLE: REOULATORY GUIDANCE DOCUMENIR EFFECTIVE DATE: 11/01/92 PREPARED BY Ab DIRECTOR, NUCLEAR SAFETY: (4 l VICE PRESIDENT, OPERATIONS: W \\ QA MANAGER: FM 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 -

1. Criterion VII, Control of Purchased " Quality Assurance Materials, Equipment, and Services Criteria for Nuclear states that documentary evidence Power Plants and Fuel that material and equipment conform Reprocessing Plants" 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 availeble at the site prior to use, but not necessarily prior to installation. This allows installation to proved 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 Revision 1-R, the Health Physics, Radwaste, and September 1975, Chemistry Department are in " Personnel Selection accordance with ANSI N18.1-1971 as and Training" endorsed by this Regulatory Guide (Endorses ANSI and/or as shown in FSAR Chapter 13. -N18.1-1971) f

WATERFORD 3 g Entergy APPENDIX A REv. 2.0 QUALITY ASSURANCE R-TrPE: C1.31 ~,. ~ Operations . PROGRAM MANUAL Page 2 of 7 Document Comment .B. ANSI /ANS 3.1-1978, 2. The qualification of personnel other " Standard for than those in the Health Physics, Selection and Radwaste, and Chemistry Departments Training of Personnel are in accordance with ANSI /ANS for Nuclear Power 3.1-1978. Specific commitments are Plants" 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, 1.

Waterfe-d-3 applies the provisions August 1972, " Quality of this Regulatory Guide and its Assurance Requirements endorsed standard to Class 1E for the Installation, equipment only. Inspection and Testing of Instrumentation and 2. Each safety related item of_ process-Electrical Equipment" instrumentation is identified with a (Endorses ANSI unique number. This number is used N45.2.4-1972) in instrument maintenance records so j 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, 1.

ANSI N18.7 refarences certain other Rev. 2, February 1978, standards to which Entergy " Quality Assurance operations' takes exception. Program Requirements Waterford-3 exceptions and (Operational)" (Endorses alternatives are' listed in this ANSI N18.7-1976) table. 2. Waterford-3 complies with Regulatory Position C.3 of Regulatory Guide 1.33 except under emergency conditions in which case-Entergy ' operations shall submit proposed changes to Technical Specifications-or license amendments in accordance with 10CFR50.54 and/or 10CFR50171. ) 7

WATERFORD-3 ' A REV. 2.0 A ntergy-APPENDIX E QUALITY ASSURANCE R-TYPE: C1.31 y Operations PROGRAM MANUAL Page 3 of 7-L Document Comment ~. Regulatory Guide 1.33 3. ANSI N18.7, Section 3.4.2, 4 (Continued) Requirements for the on-site operating organization,' states that (the activities of the individual or organizational _ unit responsible for verifying that the administrative. controis and Quality Assurance Program is being effectively implemented) shall be periodically audited by designated' personnel. Waterford-3 utilizes designated off-site personnel or an outside agency to perform annual assessments. of the entire QA Program including the activities of the on-site' audit personnel.in lieu of periodic-audits. Assessment results and-other program evaluation documents such as the Trend Analysis Report- ~are forwarded to Entergy. Operations management for evaluation _and-determination of corrective action. 4. ANSI N18.7, Section 5.2.7, Maintenance-and Modification: Waterford-3-preplans and performs maintenance of_ equipment'in accordance with written procedures except in emergency or abnormal conditions where immediate' action is required tot a. Protect the-health and safety of-the public. b. Protect equipment or personnel. c. Prevent thefdeterioration of-plant conditions to a potentially unsafe or unstable level. 5. -ANSI N18.7, Section.5.227.1, Maintenance Program Repair of safety related equipment will'be. accomplished'in-accordance with approved procedures and/or vendor' manuals. 1

WATERFORD 3 - A,Entergy. APPENDIX: -A-REV.12.0 QUALITY ASSURANCE R-TYPE: C1.31- ~ ~ Operations -PROGRAM MANUAL Page '4 of 7 i Document Comment

4. Regulatory Guide 1.33 6.

Waterford-3 will provide procedures (continued) for the activities.in Appendix A of Regulatory Guide 1.33 as discussed in Section c-1 of this regulatory guide. However, Waterford-3 does not consider all activities listed to be " safety related" (e.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." 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, No exceptians.

March 1973, " Quality Assurance Requirements for Cleaning Fluid Systems and Associated components of Water cooled Nuclear Plants" (Endorses ANSI N45.2.1-1973) )

WATERFORD 3 A ntergy. -QUALITY _ ASSURANCE R-TYPE: C1.31 APPENDIX: A REV. 2.0 E m - Operations PROGRAM MANUAL Page: 5 of 7 ppeument comment

6. Regulatory Guide 1.38, For the storage of new fuel assemblies Rev. 2, May 1977, and neutron sources, Waterford-3 commits

" Quality Assurance to the storage requirements of Level B Requirements for of ANSI N45.2.2-1972 less the flooding. Packaging, Shipping and prevention requirements-and will Receiving, Storage and minimize dust and other particles Handling of Items for contacting these items by placing a fire Water Cooled Nuclear retardant polyethylene cover over these Power Plants" items or the cell locations in which the (Endorses ANSI items are stored. N45.2.2-1972)

7. Regulatory Guide 1.39, The zone designations of Section 2.1 of Rev. 2, September 1977, ANSI N45.2.3-1973 and the requirements

" Housekeeping associated with each zone are not Requirements for Water consistent with the requirements for Cooled Nuclear Power operating plant. Instead, procedures or Plants" instructions for housekeeping activities (Endorses ANSI which include the applicable N45.2.3-1973) 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, Personnel performing nondestructive Rev.

1, September 1980, training meet the qualification " Qualification of Nuclear requirements of ASNT Recommended Power Plant Inspection, Practice No. SNT-TC-1A-1980 and its Examination and Testing applicable'aupplements. Personnel" (Endorses ANSI N45.2.6-1978)

9. Regulatory Guide 1.64,

_No exceptions. Rev. 2, June 1976, " Quality Ansurance Requirements for the Design of Nuclear Power Plants" (Endorses ANSI N45.2.11-1974)

3 - WATERFORD 3- ~ APPENDIX: A REV.-2.0-Entergy-QUALITY ASSURANCE R-TrPc C1.31 2 g Operations - PROGRAM MANUAL-_ Pages 6 of 7 k,/ s Decument facng.nl

10. Regulatory Guide 1.70, No exceptions.

Rev. 2, September 1975, " Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants" t

11. Regulatory Juide 1.74, No exceptions.

February 1974, " Quality Assurance Terma and Definitions" (Endorses ANSI N45.2.10-1973)

12. Regulatory Guide 1.88, The interim storage of Quality Assurance Rev. 2, October 1976, Records will be conducted in accordance

" Collection, Storage and with approved procedures.- At a minimum, Maintenance of Nuclear Quality Assurance Records stored on an Power Plant Quality interim basis will be afforded the Assurance Records" protection of a one-hour minimum rated (Endorses ANSI-facility or storage cabinet. 'f' N45.2.9-1974)

13. Regulatory Guide 1.94, No exceptions.

Rev. 1, April 1976, " Quality Assurance Requirements for l Installation, Inspection, and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power-Plants" (Endorses ANSI N45.2.5-1974)

14. Regulatory Guide 1.116, No exceptions.

Rev. 0-R, May 1977, " Quality Assurance Requirements for Installation,. Inspection L _and Testing of Mechanical Equipment and Systems" (Endorses ANSI N45.2.8-1975)' l n_ -(/ L-l -hh4- '~y er -

. WATERFORD 3 eEntergy-- QUALITY ASSURANCE R-TYPE:_ cl.31 APPENDIX: A-KEV. 2.0 e Operations-' PROGRAM MANUAL: Pages.7 of L Document' Comment

15. Regulatory Guide 1.123, No exceptions.

Rev. 1, July 1977, " Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants" (Endorses ANSI N45.2.13-1976)

16. Regulatory Guide 1.144, Waterferd-3 takes exception to the Rev. 1, September 1980, following paragraphs of ANSI N45.2.32:

" Auditing of Quality Assurance Programs for 1. 2.3 - Training - Technical Nuclear Power Plants" Specialists who assist in performing (Endorses ANSI audits in their area of special-N45.2.12-1977) experties will not necessarily be trained in audit techniques;- however, they will always be accompanied by a trained and qualified auditor. )

16. Regulatory Guide 1.144 2.

-4.4 - Reports - Audit reports will (Continued) be issued within.30 working days of-the-post-audit meeting. (Except audits "Flants" required by Technical Specification 6.5.2.8 which are required within 30-days.) 3. 4.3 - Conferences - Pre-audit and post-auditLeonferences shall be. held only when deemed necessary by Quality Assurance or when requested by.the audited organization.

17. Regulatory Guide 1.146, No exceptions.

August 1980, " Qualifications of Quality Assurance Program Audit Personnel for Nuclear Power Plants" (Endorses ANSI N45.2.23-1978)- e -+ v

WATERFORD 3 APPENDIX : : B REV. 00 , Entergy-QUALITY ASSURANCE RTYPE: cl.31 Operations. PROGRAM MANUAL PAGE: 1 of 4 - pC TITLE: 10CFR50. APPENDIX B COMPLIANCE EFFECTIVE DATE: 04/01/91 PREPARED Bia db DIRECTOR, NUCLEAR SAFETY: u b .QA MANAGER: l' 4.AA VICE PRESIDENT, OPERATIONS: Ax This appendix illustrates the relationship between 10CFR50, Appendix B and the Nuclear Safety Quality Policies. 10 CFR 50, Appendix B Criterion Nuclear Safety Ouality Policy I. Organization Chapter 1 - defines the organizational h. structure and delineates the authority and v responsibilities of individuals and organizations performing quality assurance-activities. 1 II. Quality Assurance Chapter _2 - defines the. scope of the Quality. Program Program and establishes that activities-affecting safety related structures, systems, and components will be conducted in accordance with approved procedures. III. Design _ Control -Chapter 3 --defines requirements for the control of the design of-_ safety related i structures, systems, and components including the design of plant modifications. p l

~ p)Entergy: ~ APPENDIX: = B REV. 00 WATERFORD 3 -y QUALITY ASSURANCE RTYPE: cl.31: Operations - PROGRAM MANUAL ~ PAGE: 2 of 4 m ./9 10 CFR 50, Appendix B Criterion Nuclear Safety Ouality Policy IV. Procurement Document Chapter 4 - defines requirements'for the-Control control of procurement of safety related structures, systems, components, materials, and services. V. Instructions, Procedures, Chapter 5 - defines requirements _for the and Drawings development and control of instructions,- procedures, and drawings. /T -- (s /' VI. Document Control Chapter 6 - defines requirements for the control of documents for-safety related-structures, systems, and components and identifies the types of-documents _to be= controlled. VII. Control of Purchased Chapter 7 - defines requirements for-control' Material, Equipment, of purchased material, equipment, and' and Services-services, including control-of suppliers and receiving inspection, ~ j VIII. Identification and Chapter 8 - defines requirements for control Control of Materials, of materials', parts and components. I Parts, and Components L'v / i:

9 gEntergy' WATERFORD 3 APPENDIX: a REv. 00 QUALITY ASSURANCE RTYPE: cl.31 w ' Operations - ' PROGRAM MANUAL - PAGE: 3 of 4

10 CFR 50 Appendix B Criterion Nuclear Safety'Ouality Policy IX.-

Control of Special Chapter 9 - defines requirements for control Processes 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. XII. Control of Measuring Chapter 12 - defines requirements for-and Test Equipment control of measuring and test equipment used for inspections, tests, and monitoring of quality related equipment and activities. XIII. Handling, Storage, and Chapter 13 . defines requirements for Shipping handling, storage, and shipping of safety-related structures, systems and components. XIV. Inspection, Test, and Chapter 14 - defines requirements for 1 Operating Status control of inspection, test, and operating status of safety related items and equipment.

WATERFORD 3 & ntergy 3ppggoxx,g:. ngy, og - E QUALITY: ASSURANCE RTYPE: C1.31 ~ Operations PROGRAM MANUAL PAGE: 4 of 4 -10 CFR_50, Appendix B Criterion Nuclear Safety Ouality Policy XV. Nonconforming Material, Chapter 15 - defines requirements for Parts, or Components identification, documentation, segregation, review, and disposition of nonconforming nmterials, parts, and components. 1 XVI. Corrective Action Chapter 16 - defines requirements for establishment of an effective corrective action program with specified basic corrective action elements. XVII. Quality Assurance Records Chapter 17 - defines requirements for a quality records p ogram including identification of types and content of records. XVIII. Audits Chapter 18 - defines requirements for audits - of' safety related activities including audit-program scope and methods. v r- ,5-

= -. - I WATERFORD 3 8 ntergy APPENDIX: C REV. 2.0 E QUALITY ASSURANCE R-TYPE: C1.31 e Operations ' PROGRAM MANUAL Page: 1 of 17 TITLE: TERHS AND DEFINITIONS EFFECTIVE DATE: 11/01/92 g PREPARED BY: _3 j Dd * ~ DIRECTOR, NUCLEAR SAFETY: 7 _ 4444 QA MANAGER h/ VICE PRESIDENT, OPERATIONS: 1\\ \\ ~ y This appendix provides 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 standardization within Waterford-3 documents and as an aid in the implementation of the Quality Assurance Program. The terms and definitions were selected from those contained within the ANSI standkrds 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 re:-Terred 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. C) Where a term is used to convey a different intent than that defined herein, clarification should be provided at_the point of application. The subscript following each definition provides the cource of the definition. An index of the subscripts in contained at the and of this appendix. ( 0

WATERFORD 3 A,Entergy APPENDIX: C REV. 2.0 QUALITY-ASSURANCE R-TrPE: C1.31 Operations PROGRAM MANUAL Pages-2 of 17 g v .. A limit or. limits placed.on the variation permitted in. -ACCEPTANCE CRITERIA' the characteristics of an item expressed in definitive engineering terms such ~ as dimensional tolerances, chemical composition-1Lmits, density and size of - defects, temperature ranges, time limits, operating parameters, and other similar characteristics.. ACCEPT-AS-IS Same as Use-As-Is., ACCURACY The degree of conformity of a measure to a standard or to a true value. (See Precision)., ADMINISTRATIVE CONTROLS Rules, orders, instructions, procedures, policies, practices and designations of authority and responsibility.. APPROVAL An act of endorsing or adding positive authorization or both. 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. i ASSEMBLY A combination of subassemblies or components, or both fitted O together to form a unit. i V AUDIT 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. gg, BASIC COMPONENT As it applies to Waterford-3, it is a component, structure,- oystem or part thereof that is directly procured by.Entergy Operations /LP&L, is subject to 10CFR21 and in which a defect or failure to comply with 10CFR21, en NRC order, or license conditions could create a substantial safety hazard.,,, 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., CALIBRATION Comparison of an item of Measuring and Test Equipment and certain l 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.,, i ~.[d-lp ~

-WATERFORD 3! 8 ntergy. APPENDIX: C REV. 2.0 E QUALITY ASSURANCE R-TYPE: -C1.31 w Operations . PROGRAM MANUAL Pages 3 of 17 CERTIFICATE OF COMPLIANCE A written statement,' signed by a qualified party, cttesting that the items or services are in accordance with specified requirements and accompanied by additional information to_eubstantiate the otatement. CERTIFICATE OF CONFORMANCE A written statement, signed by a qualified party,. certifying that items or services comply with specific requirements, i CERTIFICATION The action of determining, verifying and attesting, in writing, to the qualifications of personnel or material. CERTIFIED MATERIAL TEST REPORT A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the cetual properties of items and the actual results of all required tests, i CHARACTERISTIC Any property or attribute of an item, process, or service that is distinct, describable, and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings, which describe the item, process or cervice i CLEANNESS A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other /"'s _ contaminating impurities. COMMERCIAL GRADE Those items which (1) are not subject to design or opecification requirements that are unique to facilities or activities licensed by the NRC~and (2) are used in applications other than facilities or-cctivities licensed by the NRC and (3) can be ordered from the manufacturer / -cupplier 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 in exempted from 10CFR21 being imposed on the manufacturer, supplier or vendor by the definition of " Commercial Grade", the Litem may still have other QA requirements which need to be imposed in the procurement documents). 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 essembly; ort items from which electrical equipment is assembled, for example, resistors,_ capacitors, wires, connectors, transistors, switches,. springs, Ctc. CONDITIONS ADVERSE TO QUALITY-Such conditions include failures, malfunctions,- deficiencies, deviations, defective material and equipment, and deviations -from management systems. Such conditions shall be promptly identified to management and corrected. _ ( s \\)

WATERFORD 3 APPENDIX: C REV. 2.0 Entergy-QUALITY-ASSURANCE R-TrPE: C1.31 w Operations. PROGRAM MANUAL Page: 4 of 17 _,s f ( 4 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. gi 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.

CONTRACTOR Any organization under contract for furnishing items or services. It includes the terms Vendor,' Supplier, Subcontractor, Fabricator, and subtier levels of these where appropriate. (i i CORRECTIVE ACTION Measures taken after the identification of a condition adverse to quality in order to determine the significance of-the condition, to determine appropriate rectification measures, to establish a date for completing the predetermined measures taken, and to determine appropriate measures'to prevent recurrence of the condition. g, DEDICATION The act of verifying that 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. DEFECTIVE MATERIAL. A material or_ component which has one or more (l' characteristics that do not comply with specified requirements. i

Q

DEFICIENCY An observed condition that is or appears to be adverse to quality or beyond.a defined or approved qualitative or quantitative. acceptance' criterion..

DESIGN Technical and management processes which commence with identification of design input and which lead to and include the issuance of design output documents, n DESIGN CRITERIA. Documents which establish overall plant design-requirements - including NSSS and BOP interfaces; they establish the overall-system-parameters and design requirements for major portions of the BOP as necessary for the interrelationship of systems, components and machines. 6 i DESIGN DOCUMENTS Engineering specifications, drawings, calculations and/or ' instructions. 3 DESIGN INPUT Those criteria, parameters, bases or other design requirements' upon which detailed final design is based.. - DESIGN INTERFACE The relationship between design organizatione internal or L oxternal to a company., i: \\s_/ 1 n, ~ +

WATERFORD 3' APPENDIX: 'C REV. 2.0 'e Entergy QUALITY ASSURANCE R-TrPE: C1.al Operations PROGRAM MANUAL. Page 5 of 17 . (% "w ' 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.ll. 6 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. 6 DESIGN SPECIFICATION An engineering document describing function, design requirements,. environmental, conditions, code requirements, and boundary definition, and containing sufficient detail to provide a complete basis for construction in'accordance with applicable codes and~ standards., 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. y DEVIATION-A nonconformance or departure of a characteristic from specified-requirements. DISCREPANCY A condition which is at variance with requirements., f. DOCUMENTATION Any written or pictorial information describing, defining, specifying, reporting, or certifying activities, requirements, procedures, or results. m ELECTRICAL CLASS lE See Quality Related. EQUIPMENT QUALIFICATION.(EQ) 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., EXAMINATION An element of inspection consisting of investigation of materials, supplies, parts, components, appurtenances, systems, processes, or . structures to determine conformance to.those specified requirements which can .be determined by such investigation. Examination is usually. nondestructive and includes eimple physical manipulation,-gaging, and measurement. m EXEMPT Items 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.. m v,,- .. ~,.---

WATERFORD 3 A ntergy APPENDIX: C REV. 2.0 E QUALITY ASSURANCE R-TYPE: C1.31 w Operations PROGRAM MANUAL Pages 6 of 17 l EXTERNAL AUDITS of those portions of an organization's quality ensurance program not retained under its direct control and not within its organizational structure.. FUNCTIONAL TESTS performed, as required, after modification, maintenance, or ,significant changes in operating procedures to confirm that the maintenance, modification, or changes produce expected results., 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., INDEPENDENT REVIEW A documented review completed by personnel not having direct responsibility for the work function under review regardless of whether they operate as a part of an organizational unit or as individual staff members (see Review).,, INSPECTION A phase of quality control which by means of examination, observation, or measurement determines the conformance of material, supplies, appurtenances, systems, processes, or structures to ' ') parts, components, predetermined quality requirements, sou 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. i INSPECTOR (STATE OR OODE) A qualified inspector employed by a legally constituted agency 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,i INTERNAL AUDITS of those portions of an organization's quality assurance program retained under its direct control and within its organizational structure., ITEM Any level of unit assembly, including structure, system, subsystem, subassembly, component, part, or material. 4,i LEAD AUDITOR An individual qualified to organize and direct an audit, report audit findings, and evaluate corrective action.,, KANUFACTURER One who constructs any class of component, part, or appurtenance to meet prescribed design requirements. i ) l l

WATERFORD 3 e_ Entergy APPENDIX: e nEv. 2.o QUALITY ASSURANCE R-TYPE: cl.31 ~ Operations PROGRAM MANUAL Page 7 of 17 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 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 other Entergy Operations organizations during routine operation and maintenance of Waterford-3., 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.). i MEASURING AND TEST EQUIPMENT (M&TE) Devices or systems used to calibrate, measure, gage, test, inspect, monitor, or control in order to acquire research, development, test, inspection, or operational data to determine compliance with design, specification, or other established requirements.,, MODIFICATION A planned change in plant design or operation and accomplished g in accordance with the requirements and limitations of applicable codes,. standards, specifications, licenses, and predetermined safety restrictions,i NONCONFORMANCE A deficiency in characteristic, documentation, or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformance includes physical defects, test failures, incorrect or ) inadequate documentation, or deviations from prescribed processing, inspection or test procedures. i OBJECTIVE EVIDENCE Any statetaent of f act, 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. i ON-SITE PERSONNEL Those personnel providing technical and operational support who are located within the Waterford-3 owner-controlled area., 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 power, 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 capable of performing their related support function (s).. OPERATIONAL PHASE That period of time during which the principal activity is associated with normal operation of the plant. This phase of plant life is considered to begin formally with commencement of fuel loading and ends with plant decommissioning.,

=_WATERFORD 3 -APPENDIX: C REV.T2.0 v.Entergy-- QUALITY ASSURANCE R-TYPE: C1.31 Operations PROGRAM MANUAL-Pages-8 of 17 f OWNER ORGANIZATION-- The organization, including the on-site operating organization, which has overall legal, financial and technical responsibility for the operation of one or more nuclear power plants.,gi PRECISION The relative consistency or repeatability of each measurement in a , set of measurements made under the same conditions.. (See Accuracy)., l FROCEDURE A document that specifies or describes how an activity is to be .i J performed. It may include methods to be employed, equipment or-materials to be used and sequence of operations. i y -l PROCUREMENT CLASSIFICATIONS ] QUALITY CLASS I - Those items er services meeting the definition of safety related for which the supplier, manufacturer, or vendor assumes 10CFR21 reporting responsibility. The supplier QA. program must -include full 10CFR50 implementation. QUALITY CLASS II - Those items or services which do not meet the definition of safety related, but which fall into the other quality related areas listed in the definition of quality related. The applicable program requirements / exceptions are listed in the Special Scope _ procedures, directives, procedures or procurement documents. ) QUALITY CLASS III - Those items meeting the definition of safety related and the definition of commercial grade. Items purchased as Quality Class III are subject to the dedication process prior to being-classified as a basic component. Entergy Operations assumes 10CFR21 reporting responsibility for QC III purchases. QUALITY CLASS IV - Those 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 contractors under the Entergy Operations Quality Assurance Program. 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. g. PURCHASE ORDER A document issued by a purchaser to a supplier which defines the requirements and conditions for furnishing material, components, or equipment., PURCHASER-The organization or organizations responsible for issuance and 4 administration of a contract, subcontract, or purchase order. g,

- -. - = - i WATERFORD 3 eEntergy APPENDIX: C REV. 2.0 QUALITY ASSURANCE R-TYPE: C1.31 e Operations PROGRAM MANUAL Page: 9 of 17 C -Q-LIST A listing, by system, of all safety-related components in the Waterford-3 SES. For each safety-related component the Q-List indicates the safety classification and seismic category along with the-primary source documents which were used to determine if the component-is safety-related., , Q-RELATED LIST A listing of items or activities considered to have a limited impact on public health and safety and receive an appropriate application of 10CFR50 Appendix B Criteria. These areas include; Special Scope; Non-Nuclear Safety, seismic Cctegory I and items designated by FSAR Table 3.2-1, Note 17. 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 cc nfidence in conformance to requirements. g 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. u QUALIFIED SUPPLIERS LIST (QSL) 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., 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 ao verifying and documenting the l 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. y 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. 3

WATERFORD 3 G_ Entergy APPENDIX: C REV. 2.0 QUALITY ASSURANCE R-TrPs C1.31 i Operations PROGRAM MANUAL P'9 10 f 17 QUALITY RELATED Waterford-3 uses the term Quality Related to describe the entire scope of structures,t stems, components and activities which require some degree of 10CFR50 Appendix B, Quality Assurance criteria application. Quality related is divided into five major categories: (reft fig. 1) o safety Related o special scope o Non-Nuclear Safety r> Non-safety seismic o Other items identified by TSAR table 3.2-1, note 17 or Waterford-3 procedures. OUAUTY l4 l RE. LATED t l 4 - 04.lST - - - > 4 041 ELATED UST 5I Not+8AFETY NON4AICLEAR NOTHA > CLEAR SAFETY SOSA4C SAFETY l SAFTTY BALANCE OAPM RELATED (NSS) WITH I WTTHOUT OF (9PEC64 $ COPE) (CDSit01) I over i TABLE 32-1 TABLE 32-1 PLANT Cetteria NOTE 17 NOTE TT l ae a-P.e - . saisir C.. i o sty - ..c.,,,,,,,

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Note: The appecable criteria, system scope, and I other temmements are dehned h Qualty po8cies, procetkees, precurement documents, work packages g 9 and other documentatm y g m 8 l 1 OC 2 or OC 4 l 00 l and apply 10CFR21l 1 OC 2 or i OC 4 le perfNtted for selected special i y OC4 00 4 OC 3! Commercial Grado)l ecope activttes if permitted by the Special recept - i l apphenbio OAPM (Special and ce1cate rispecton acoDe) procedLrea. t

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i WATERFORD 3 e,Entergy APPENDIX: C REV. 2.0 QUALITY ASSURANCE R-TrPE: c1.31 Operations PROGRAM MANUAL Pages 11 of 17 ] 1 grigtv 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 i 3. The cepability 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, tanting or consulting services important to safety that are assor4.ated 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; ANs! N18.2a - 1975; and IEEE-308 - 1971. Supports that have a nuclear safety function shall be the same safety class as the componente 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 -11978, Regulatory Position C3. 'The safety related items listed above make up the Waterford-3 Q-List. These items and related activities require full 10CFR50 Appendix B implementation. Full implementation should not be construed to mean that each criterion 1 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 applicabis criteria in their QA Program. w.. - -,

l WATERFORD 3 & ntergy APPENDIX: C REV. 2.0 E QUALITY ASSURANCE R-Tyre C1.31 e Operations PROGRAM MANUAL Page 12 of 17 O Special Scong - The Special Scope areas are listed in Chapter 2 of the Quality Assurance Program Hanual. Program ireplementation and applicable 10CFR50, Appendix B criteria are defined in EOMH policies and directives. Reference Figure 1 to this appendix for a sample list of areas included as special Scope. Non-Nuclear Safety (NNSl - applies to portions of the nuclear power plant not covered by Safety Classes 1, 2, or 3 that can influence safe normal operation or that may contain radioactive fluids. Design of non-nucisar safety components shall be to applicable industry codes and standards. This applies primarily to components of secondary systems and waste disposal systomr not otherwies covered. Also included are safety system components whose failures would not degrade system performance or cause a release to the environment 01 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 by whose failure could reduce the function of any safety related equipment to an unacceptable level or could result in incapacitating injury to occupants of the control r9om and should be designed and constructed so that the safe shutdown earthquels would not cause such failure. See Regulatory Guide 1.29 - 1978, Regulatory Position C2. Other ftems IFSAR 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 beer. evaluated to have some safety significance although they do not fall into any of the other safety classifications. Applicable program requirements are included in policies, procedures, procurement documents and other documentation as required. 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 Engineeririg & 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 tos

3 WATERFORD 3 i aEntergy APPENDIX: C REV. 2.0 QUALITY ASSURANCE a-rYPE: C1.31 w Operations PROGR AM MANUAL Pare: 13 of 17 i \\ / 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 at:d after the time that it is subjected to the forces reculting from a seis.nic disturbance (design basis earthquake). - SHALL, SHOULD, AND KAY Reference Entergy Operations 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, but not an enforceable requirements. 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.,, SIGNIFICANT CONDITION ADVERSE-TO QUALITY A condition adverse to quality, the ultimate effects of which if uncorrected, would include at least one of the following: 1. The nuclear power plant, including its principal safety barriers, ) being seriously degraded; or results in the nuclear power plant beings a. In an unanalyzed condition that significantly compromises plant safety; b. In a condition that is outside the design basis of the plant; or c. In a condition not covered by the plant's operating and~ emergency procedures. 2. A condition that alonc could have prevented the fulfilleent of the safety function of structures or systems that are needed tot a. Thut down the reactor and maintain it in a safe shutdown eondition; b. Remove decay heat; c. Control the release of radioactive material; or d. Mitigate the consequence of an accident. 3. An .i.11 threat to the safety of the nuclear power plant or a conni ;on which significantly hampers site personnel in. the performance of duties necessary for the safe operacion of the nuclear power plant including fires, toxic gas releases, or radioactive releases. ---~a~--, -,a. -.,n,-m, ,...n, w

i WATERFORD 3 A ntergy APPENDIX: C REV. 2.0 E OUALITY ASSURANCE R-TYPE: C1.31 e Operations Ph0c= RAM MANUAL Pa9*' 14 of 17 0 4. A liquid effluent releas6 that exceeds two times the limiting combines Maximum Permissible Concentration (HPC) (see Note 1 of Appendix B to 10CFR20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides. 5. An airborne radioactive release that exceeds two times the applicable concentrations of the limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas, when averages over a time period of one hour. 6. Failure of completed corrective action to prevent recurrence in a safety-related system / activity. 7. Significant adverse safety consequences not : overed under 1 through 6, SOURCE ACCEPTANCE of a product of Entergy Operations or its designated agent 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., SPECIAL PROCESSES Those processes that require interim in-process controir in f addition to final inspection to assure quality., 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. SUBSYSTEM A group of assemblies or components or both combined to perform a single function. SUPPLIER Any individual or organization who furnishes items or services in response to a procurement document. It includes the terms Vendor, Seller, contractor, Subcontractor, Fabricator, Consultant, and subtier levels., SURVEILLANCE The act of monitoring or observing to verify whether an item or activity conforms to specified requirements., 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. i O w-e-a e. w---enw-s ,~ vm,,,, y v -n- - -,, - - - -,--,n

WATERFORD 3 APPENDIX: C REV. 2.0 Entergy QUALITY ASSURANCE R-TrPE: C1.31 m Operations PROGRAM MANUAL P*9a' 25 of 27 SYSTEM PERFORMANCE TEST A test performed on a completed system including electric, instrumentation, controls, fluid, and mechanical subsystems under normal or simulated normal process conditions such as temperature, flow, level, and pressure. y 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., 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 condition?. Performance of those steps necessary to determine that systems or components function in accordance with predetermined specifications.ss u s or ue value., TOLERANCE The allowable deviation fra, s Jf-lS' cond cars, barges, aircraft, TRANSIT CARRIER (CLOSED) Trucks, trailhts. v or ships which do provide protection of itema i;;n the environment by nature of their closed design. TRANSIT CARRIER (OPEN) Trucks, trailers, railroad cards, barges, aircraft, or ships which do not provide protection of items from the environment. 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 Boardt 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) acove., UNREVIEWED SAFETY QUESTION A proposed change, test, or experiment _shall be decmed to involve an unreviewed safety questions (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 mey be increased or (2) if a possibility for an accident or malfunction of a difference type than any evaluated previously in the esfoty analysin report may be created or (3) if the margin of safety as defined in the basis for any technical specification is reduced., USE-AS-IS A disposition which may be imposed for a noncont'ormance when it can be established that the discrepancy will result in no adverne 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.)

WATERFORD 3 gEntergy ArrenoIxi e arv. 2.o QUALITY ASSURANCE n-ryrz c1.31 w Operations PROGRAM MANUAL rages 16 of 17 VERIFICATION An act of confirming, substantiating, and assuring that an activity or condition has been implemented in conformance with the specified requirements.u WAIVER An approved exception to established controls., l O O

WATERFORD 3 gEntergy AprENoIx e nEv. 2.0 QUALITY ASSURANCE R-Tyre c1.31 ~ Operations PROGRAM MANUAL P'9*' 27 ' 27 C SUBSCRIrT INDEX $UDSCRIPJ SOURCE OF DEFIlilT.I.Qti a ANSI N18.1-1971/ANS3.1-1978 b ANSI N45.2.4-1972/IEEE-336 - 1971 c ASHI N18.7-1976/ANS3.2 d ANSI N45.2.1-1973 e ANSI N45.2.2-1972 f ASNI N45.2.3-1973 g ASNI/ASME N45.2.6-1978 h ANSI N45.2.11-1974 i ANSI N45.2.10-1973 ) j ANSI N45.2.9-1974 k ANST N45.2.5-1974 1 ASNI N45.2.0-1975 m ASNI N45.2.13-1976 n ANSI /ASME N45.2.12-1977 o ANSI /ASME N45.2.23-1978 p IEEE "' - 1971/323 - 1983 q Entergy Operations r Title 10 code of Federal Regulations e Technical Specifications t IEEE 498 - 1980 0 _.}}