ML20116D329

Rev 11 to QA Manual

ML20116D329
Person / Time
Site:	Clinton
Issue date:	03/04/1985
From:	ILLINOIS POWER CO.
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ML20116D328	List: ML20116D325 ML20116D329
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r 4E.100 Y-29026 March 4, 1985 IP Nuclear Power Construction Quality Assurance Manual Revision 11

SUMMARY

The revision to the Construction Quality Assurance Manual is being made to reflect the current IP organization and in order to comply with Amendment 32 of the FSAR.

EVALUATION The changes to the Construction Quality Assurance Manual fall under one of the following:

a. Correction of typographical or grar=tatical errors.

b. Personnel title changes. -

c. Organization changes that do not effect authority, independence, or management reporting levels.

d. Clarifications which do not effect requirements.

Based on the above, the changes to the Construction QA Program

) descriptions do not constitute a reduction in commitments previously submitted to the NRC.

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• IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11-MATRIX OF REVISIONS PAGE PARA. REASON FOR CIIANGE

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i N/A Update policy statement to agree with the policy statement in the CNP Manual.

iii N/A Define Appendix D as Appendix C iv

• N/A Define title as List of Effective Pages v N/A Correct Page Count vi N/A Correct Page Count

• Chapter 1

p. 2 of 16 B.3 Minor Editorial Change Chapter 1

p. 3 of 16 A.2 Nuclear Purchasing responsibility under a VP versus Project Manager Chapter 1 .

p. 3 of 16 N/A Comply with site organization deleted Senior Vice President

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.b IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE Chapter 1 p.4 of 16 A.4 Add " Nuclear Purchising" to V. P., responsibilities Chapter 1 p.4 of.6 A.6 ' Incorporated Manager-Nuclear program Coordination Chapter 1 -

p.4 of 16 A.7 Deleted site purchasing from Project Manager Chapter 1 p.4 of If N/A Comply with site organization - deleted Vice President

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Chapter 1 p.5 of 16 A.10 Comply with CPS project organization chart

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Chapter 1 p.5 of 16 A.11 Incorporated Manager - Nuclear Planning and Support Chapter 1 p.5 of 5 A.12 Incorporated Manager - Startup Chapter 1 '

p.6 of 16 A.16 Add Director - Nuclear Purchasing Section

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CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE Chapter 1 p.6 of 16 A.17 Re-number paragraph-number, minor editorial change Replace "IIe" or "liis" with Manager - Quality Assurance Chapter 1 p.7 of 16 A.17 Typographical error Chapter 1 p.8 of*16 A.17.1 Comply with new QA Department Organization Chapter 1 p.8 of 16 17.1.1 Comply with new QA Department Organization h4' 6kW-+h Me h.wW .-e Chapter 1 p.8 of 16 17.1.2 Comply with new QA Department Organization responsibilities Chapter 1 p.9 of 16 17.1.3 Comply with new QA Department Organization responsibilities Chapter 1 p.9 of 16 17.2 Re-number paragraph, Typographical error Chapter 1 p.9 of 16 17.2.1 Delete " Corporate" from QS training responsibilities

IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS

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PAGE PARA. REASON FOR CllANGE Chapter 1 p.10 of IE 17.2.2 Further define the Audit section responsibilities Chapter 1 p.10'of IC 17.3 Define new QA Department Organization Chapter 1 p.11 of IE 17.3 Define new QA Department Organization-Chapter 1 p.14 of 16 Fig.1-1 Comply with site organization chart Chapter 1 p.15 of 16 Fig.1-2 Comply with site organization chart Chapter 1 p.16 of 16 Fig.1-3 Comply with site organization chart Chapter 2 p.3.of 11 A.2 Consistant with IP QA Program Chapter 2 _

p. of 11 2.b.3 Comply with new QA Department Organization responsibilities

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IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE Chapter 3

p. 1 of 5 A Re-define design responsibility to IP NSED Chapter 3 Div. of

p. 3 of 5 Resp. Clarify design responsibility Chapter 3 *

p. 3 of 5 A.1 Define organizational responsibilities for control of design contractors Chapter 3

p. 3 of 5 A.2,3,4 Re-number paragraphs Chapter 3 Table

p. 5 of 5 3-1 Minor Editorial change Item 8 Chapter 3 ,

p. 5 of 5 Table Re-assign design control system element numbers 5 & 9 to IP 3-1 Chapter 4

p. 2 of 3 A.2,3,4 Minor Editorial changes Chapter 4 ,

p. 3 of 3 A. 5 Organization Title Change

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%) Nj IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS PAGE PARA. REASON FOR CllANGE Chapter 4

p. 3 of 3 A.6 Or3anization Title change Chapter 4

p. 3 of 3 A.8 Minor Editorial Change chapter 7

p. 1 of 3 A Added "within its scope" for clarity Chapter 7

p. 2 of 3 A.3 Organization Title change Chapter 9

p. 1 of 3 B Minor Editorial Change Chapter 9

p. 2 of 3 A Minor Editorial Change Chapter 10

p. 1 of 3 B Minor Editorial Change Chapter 11 .

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d IP NITCLEAR POWER CONSTRUCTION Q.A. MAtlUAL Revision 11 MATRIX OF REVISIONS _

PAGE PARA. REASON FOR CIIANGE Chapter 11

p. 1 of 3 B Minor Editorial Change Chapter 11

p. 2 of.3 A.1 Minor Editorial Change Chapter 12 -

p. 2 of.3 A Minor Editorial Change Chapter 13

p. 1 of 3 B Minor Editorial Change Chapter 14

p. 2 of 2 A.1 Minor Editorial Change Chapter 15

p. 1 of 1 A Re-defined AP as interfacing with vendors and subcontractors and BA interfaces with IP

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p. 2 of 3 B.6 Changed " accept as is" to "use as is" Chapter 15 *

p. 2 of 3 A.3,4,5 Added sections 3, 4& 5 for clarity

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IP NUCLEAR POWER CONSTRUCTION Q.A. MANUAL Revision 11 MATRIX OF REVISIONS PAGE PARA. REASON FOR Cl!ANGE Chapter 15 p'. 2 of 3 A.6 Re-number paragraph Chapter 15

p. 2 of 3 B.1 Added "as requested by IP" for clarity Chapter 15

p. 3 of 3 C.1 Added "as requested by IP" for clarity Chapter 15 s,

p. 3 of 3 D.3 Added " selected" and " dispositions" or for clarity Chapter 15

p. 3 of 3 D.3 Minor Editorial change ,

Chapter 17

p. 1 of 3 B.4 Reword with proper terminology Chapter 17

p. 2 of 3 A.2 Further define IP responsibilities Chapter 17 Clarification of responsibilities, deleted the filing and maintenance

p. 3 of 3 D.2 of IP generated records

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Page 1 of 1 ILLINOIS POWER COMPANY NUCLEAR POLICY STATEMENT Quality Assurance The Illinois Power Company (IP) Nuclear Power Construction, Operational, and American Society of Mechanical Engineers (ASME)

Ouality Assurance Programs have been developed by IP to assure that construction, operation and associated activities which affect the safety related functions of the Clinton Pouer Station (CPS) are conducted in a safe and reliable manner in compliance with the Code of Federal Regulations (10CFR50, Appendix B): the ASME Boiler and Pressure Vessel Code (Section III-Division 1); and other applicable regulations, codes, and standards. Control and surveillance requirements specified in the Construction, Operational and ASME Ouality Assurance Manuals are to be applied by IP organizations and contractors participating in CPS construction and operational activities.

The required aersonnel and resources are to be provided to assure that tae quality assurance (0A) programs are adequately planned, implemenced, and managed.

The Manager-Quality Assurance is responsible for developing,

/~'s establishing, and maintaining the quality assurance program

) manuals. IP Managers and Directors are responsible for implementing the quality assurance programs in accordance with the requirements conveyed in these manuals according to their assigned functional responsibilities. The Manager-Ouality Assurance has the organizational freedom and is responsible to identify problems, initiate corrective actions, verify implemen-tation and assure control of activities which affect quality.

When concerns related to quality matters are not satisfacto-rily resolved with immediate supervision, personnel have direct access to the next higher level of management in the organi:ation. If concerns are still not satisfactorily resolved, personnel have direct access to me for final reso-lution in accordance with applicable codes and standards.

Anyone that intimidates or interferes with any person per-forming Ouality Assurance and Quality Control' functions shall be subject to disciplinary action. Intimidation may take many forms ranging from verbal abuse to physical harm.

Personnel subject to or who perceive intimidation or inter-forence have direct access to the Executive Vice President, who has the authority and responsibility to take appropriate disciplinary action.

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AUTHORIZATION This document shall be used in activities related to design and construction of the Clinton Power Station. It shall be maintained and updated as required by the Manager-Quality Assurance. Personnel assigned controlled copies of this manual shall be responsible for their maintenance and update in accordance with the provisions of Appendix B.

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__IP_. NUCLEAR _ POWER CONSTRUGTION

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0 Introduction 1 Organization 2 Quality Assurance Program 3 Design Control 4 Procurecent Document Control 5 Instructions, Procedures, and Drawings -

6 Document Control 7 Control of Purchased Material, Equipment, and Services 8 Identification and Control of Matericls, Parts, and Components 9 Control of Special Processes 10 Inspection 11 Test Control 12 Control of Measuring and Test Equipment 13 Handling, Storage, Shipping 14 Inspection, Test, and Operating Status 15 Nonconforming Materials, Parts, or Components 16 Corrective Action 17 Quality Assurance Records 18 Audits Appendi.< A Quality Assurance Program Scope Appendix B Revisions to the IP Nuclear Power Construction Quality Assurance Manual Appendix C Supplemental Application O

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IP - Nuclesr Powar Construction QA MInuni List of Effectiva Pegos IP NUCLEAR P_0WER GONSTRIICTION q !\ [](UAIIITT AS$URANCE; f

MANUAL INDEX iIt fhEf e Pg N Revision The following pages and their indicated dates of issue are included in the currently authorized IP Nuclear Power Construct-ion Quality Assurance Manual.

Page No. Date Page No.

Late Page No.' Date 1 0370T/85 4-3 ot 3 OTTDT/85 A-1 037M/84 11 06/09/83 5-1 of 3 05/09/84 A-2 03/05/85 111 03/05/85 5-2 of 3 05/09/84 A-3 03/05/85 '

iv 03/05/85 5-3 of 3 05/09/84 A-4 03/05/85 v 05/09/84 6-1 of 2 05/09/84 A-6 03/05/65 vi 06/28/82 6-2 of 2 05/09/84 A-5 03/05/85 1-1 of 16 05/09/84 7-1 of 3 03/05/85 A-7 03/05/85 l-2 of 16 03/05/85 7-2 of 3 03/05/85 A-8 03/05/85 1-3 of 16 03/05/85 7-3 of 3 05/09/34 A-9 03/05/85 1-4 of 16 03/05/85 8-1 of 2 05/09/84 A-10 03/05/85 1-5 of 16 03/05/85 8-2 of 2 05/09/84 A-11 03/05/85

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\ 1-6 of 16 03/05/85 9-1 of 3 03/05/85 03/05/85 A-12 A-13 03/05/85 1-7 of 16 03/05/85 9-2 of 3 03/05/85 i 1-8 of 16 03/05/85 9-3 of 3 05/09/84 A-14 03/05/85 1-9 of 16 03/05/85 10-1 of 3 03/05/85 B-1 03/05/85 1-10 of 16 03/05/85 10-2 of 3 05/09/84 C-1 03/05/85 1-11 of 16 03/05/85 10-3 of 3 05/09/84 C-2 03/05/85 1-12 of 16 05/09/84 11-1 of 3 03/05/85 1-13 of 16 05/09/84 11-2 of 3 03/05/85 1-14 of 16 03/05/85 11-3 of 3 05/09/84 1-15 of 16 03/05/65 12-1 of 3 05/09/84

! 1-16 of 16 03/05/85 12-2 of 3 03/05/85 2-1 of 11 05/09/84 12-3 of 3 05/09/84 2-2 of 11 03/05/85 13-1 of 3 03/05/85 2-3 of 11 03/05/85 13-2 of 3 05/09/84 2-4 of 11 03/05/85 13-3 of 3 05/09/84 2-5 of 11 03/05/85 14-1 of 2 05/09/84 2-6 of 11 05/09/84 14-2 of 2 03/05/85 2-7 of 11 05/09/84 15-1 of 3 03/05/85 2-8 of 11 05/09/84 15-2 of 3 03/05/85 2-9 of 11 05/09/84 15-3 of 3 03/05/85 2-10 of 11 05/09/84 16-1 of 2 05/09/84 2-11 of 11 05/09/84 16-2 of 2 05/09/84 3-1 of 5 03/05/85 17-1 of 3 03/05/85 3-2 of 5 05/09/84 17-2 of 3 03/05/85

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3-5 of 5 03/05/85 18-2 of 3 05/09/84 4-1 of 3 05/09/84 18-3 of 3 05/09/84 4-2 of 3 03/05/85 iv 03/05/85

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j jyuVW" INTRODUCTION O l C/ The Illihois_P Jwer Company ~(IPT, as principal o r of the Clinton P5 iter Station (CPS), has developed and implemented the IP Nuclear Power Construction QA Program described in this manual for activities which affect the safety related functions of those structures, systems, and components which prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. IP will continue to fulfill its responsibility to ensure a composite effort consisting of its own quality assurance program augmented by the quality assurance program of its major contractors to cover appropriate CPS activities. The Nuclear Steam Supply System (NSSS) Vendor, the Architect Engineer (AE) and the Constructor are each responsible to IP for implementation of complementary quality assurance programs applicable to the scope of their individual areas of work. Each of these organizations will maintain a quality assurance program in compliance with appli-cable requirements. The IP Quality Assurance concept is that each party participating in CPS activities is responsible for its program and the program implementation to perform its designated work. IP monitors and audits the implementation of such programs to ensure total coverage and compliance.

This Manual is the basic governing IP document for the quality assurance of design, procurement, fabrication, and construction Q activities for CPS. A separate manual will cover the quality b assurance of pre-operational testing, operdtion, maintenance, and post-construction modifications activities. The program de-scribed herein requires preplanned systems of carefully document-ed checking, reviewing, qualifying, examining, insaecting, testing, auditing, or other verifying activities t1at provide reliable evidence of required quality. The objective of these activities is to obtain a plant which is in compliance with applicable regulatory, code, and technical standards require-ments.

The basic regulations applicable to the IP Nuclear Power Quality Assurance Program are Part 50 Appendix B of " Title 10 - Chapter 1, Code of Federal Regulations, (10 CFR 50)", and the State of Illinois regulations, which stipulate adherence to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.

In addition, ANSI N45.2, 1977, " Quality Assurance Requirements for Nuclear Power Plants", together with various interpretations and supplemental information in Nuclear Regulatory Commission Safety and Regulatory Guides, shall be applied as stated in the FSAR. These are the principal codes, standards, and technical bases for quality assurance requirements described herein.

This Manual is organized to follow the format of the "18 Crite-rion" of 10 CFR 50 Appendix B. Each chapter is divided into three main sections v

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i I Purpose -

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III Division of Responsibility i Section II of each chapter is further broken into two parts - a j discussion of (a) external interfaces, and (b) general require -

! ments to be satisfied by IP and its contractors as applicable to j their scope of work.

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IP - Nuclear Power CHAPTER 1 - ORGANIZATION Construction QA Manual K

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t Mgnager-QA Date PURPOSE:

This Chapter describes the organizational structures, functional responsibilities, and levels of authority of organizations related to the design, construction, procurement, inspection, and testing of safety related activities at the Clinton Power Station.

REQUIREMENTS:

A. Interface Illinois Power Company directs and is responsible for the quality assurance activities in the design and construction of the Clinton Power Station. This responsibility is retained by IP even when it is necessary to obtain design, procurement, fabrication, construction, inspection, and

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( ,f related testing, consulting, and associated QA services from other organizations external to IP. Upon completion of construction and turnover of structures, systems and compon-ents by the constructor, IP will direct and be responsible for performing the required checkout, initial start-up operation, pre-operational testing and associated quality assurance / control function. IP will obtain assistance from other organizations as necessary. Figure 1-1 depicts the organization of the Clinton Power Station project.

The major contractors involved with the design and construction of the Clinton Power Station are: Sargent

& Lundy (S&L) -

the Architect Engineer (AE): General Electric (GE) -

the Nuclear Steam System Supplier (NSSS) and Baldwin Associates (BA) - the Field Constructor (Constructor). The organizational interface relationship between IP and the najor contractors is reflected in Figure 1-2.

The relationships shown for the major contractors (S&L, GE, and BA) are equally applicable to other contractors. To accomplish the program objectives, the IP Quality Assurance organization monitors the QA organizations of the major con-tractors and consultants. This arrangement makes a wider range of skills available and decreases potential manpower limitations during periods of high activity.

O 1 of 16 05/09/84

IP - Nuclear Pow:r CHAPTER 1 Construction QA Manual (3 B. General

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The IP and contractors' organizations shall meet the following requirements:

1. The authority and responsibility of persons and orga-nizations performing activities which affect quality, including the quality assurance pe.rsonnel, shall be clearly established and delineated in writing.

2. Quality assurance organizations shall have sufficient freedom to identify quality problems, initiate, recom-mend, or provide solutions; to verify implementation of solutions; and to control further processing, delivery, installation, or utilization of nonconforming materials or items until proper dispositioning has occurred.

3. Any person (s) that intimidates or interferes with any personnel performing quality assurance or quality l control functions shall be subject to disciplinary action. Intimidation may take many forms ranging from verbal abuse to physical harm.

4. Quality problems shall be reported to appropriate management levels who will act to resolve the problems.

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(, 5. Those persons or organizations performing a checking, auditing, inspecting, or verification function shall not have a direct responsibility for performing the same work.

DIVISION OF RESPONSIBILITY:

Each organization participating in CPS activities is responsible for establishing a QA 1rogram and the implementation necessary to perform designated work. Each contractor's quality organization shall be established in a manner consistent with its particular role in the overall CPS activities as stimulated by IP. Each contractor's Quality Assurance Program s aall be reviewed and approved by IP to ensure consistency with the IP Nuclear Power Quality Assurance Program. The organizations may have significant differences as can be seen by comparison of the organization charts of IP, Sargent & Lundy, General Electric, and Baldwin Associates. To ensure effectiveness, IP Project Management and Quality Assurance shall function to coordinate interfaces among these organizations.

Quality assurance activities appropriate to their scope of work are assigned to Sargent & Lundy, General Electric, and Baldwin r~x Associates. This, however, does not imply delegation of ultimate

( ,) responsibility for overall quclity assurance which remains with IP.

2 of 16 03/05/85 l

IP - Nuclear Power CHAPTER 1 Construction QA Manual (x A. ILLINOIS POWER Q}

Figure 1-1 depicts the line and staff functions of the IP Clinton Power Station organizational structure.

1. Chairman and President The Chairman and President of IP has the overall responsibility for the engineering, design, procure-ment, construction modification, testing, operation and quality assurance at CPS. Execution of these respon-sibilities is delegated to two Executive Vice Presi-dents and a Senior Vice President.

2. Executive Vice President An Executive Vice President is responsible for the overall effectiveness of the Quality Assurance program and is responsible for establishing the quality assurance policies, goals, and objectives. The responsibilities to establish and maintain the IP Nuclear Power Quality Assurance Program as well as testing, startup, operations, nuclear support, nuclear purchasing, and engineering are delegated to a Vice President. The Executive Vice President is also Ox .

responsible for assuring that annual management reviews are conducted and documented on the status, adequacy and effectiveness of the overall QA program. The responsibilities for construction have been delegated l to the Project Manager. The Executive Vice President shall retain the responsibility for assuring that the authority and independence of Quality Assurance personnel are such that they can effectively assure the conformance to quality requirements and are independent of undue influences and responsibilities for schedule and costs.

3. Executive Vice President An Executive Vice President is responsible for quality related activities associated with environmental affairs. The responsibility to establish and maintain procedures which support the IP Nuclear Power Program on safety related matters has been delegated to a Vice Presidenc.

4. Vice President l A Vice President has been designated as the corporate officer responsible for overall direction of the IP q, Nuclear Power Quality Assurance Programs the testing, startup, nuclear support, nuclear purchasing, and l 3 of 16 03/05/85 l

1 IP - Nuclear Pow r CHAPTER 1 Construction QA Manual s commercial operation of Clinton Power Station and those (4/ ) activities associated with the engineering of Clinton Power Station. He reports to an Executive Vice President and has direct access to the President.

5. Vice President A Vice President has been designated as the corporate officer responsible for those activities associated with environmental affairs. The designated Vice .

I President reports directly to an Executive Vice Presi-dent. He has delegated this responsibility to the ,

Manager-Environmental Affairs. l l

6. Manager - Nuclear Program Cocrdination The Manager - Nuclear Program Coordination reports to a Vice President and is responsible for assisting the Vice President of the Nulcear group in meeting regulatory requirements, commitments and Illinois Power Company (IPC) goals and objectives as necessary to support construction, start-up, operation and modification of the Clinton Power Station (CPS) in an efficient and timely manner.

,_s 7. Project Manager l i

k/ ) A Project Manager has been designated as the person responsible for those activities associated with construction. The Project Manager reports to an Executive Vice President.

7.1 Construction Manager l The Construction Manager reports to the Project Manager and is responsible for the construction of the Clinton Power Station. He assures that construction interfaces between the constructor (BA) and IP are properly coordinated and documented such that effective communication and planning is maintained.

7.2 Assistant Project Managers l The Assistant Project Managers reports to the Project Manager and is responsible for advising the Project Manager on various management and quality assurance issues.

7.3 Manager - System Release / Turnover l

(~) The Manager - System Release / Turnover reports to

\_ / the Project Manager and is responsible for direction of the program for completion and turnover of all systems, components, and equipment from Baldwin Associates to Illinos Power Startup.

03/05/85 l 4 of 16 _ _ ._

IP - Nuclonr Pow r CHAPTER 1 Construction QA Manual I

7x 8. Manager of Nuclear Station Engineering

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) l The Manager of Nuclear Station Engineering reports to a Vice President and is responsible for the development, direction, and overall coordination of power plant engineering activities performed by the Nuclear Station Engineering Department (NSED) for the Clinton Power Station. These responsibilities include: the preparation of specifications and drawings for the accomplishment of new designs, design changes, and modifications; configuration management; design interpretation; the conduct of design checks and reviews; and the technical evaluation of contractors and suppliers. The Manager of NSED ensures that these activities are performed in accordance with the ree tirements of the IP Nuclear Power Quality Assurance Pro-ram.

9. Power Plant Manager The Power Plant Manager reports to a Vice President and is responsible for the safe, reliable, and efficient operation of the Clinton Power Station in accordance with the operating license. This includes ensuring that the IP Nuclear Power Quality Assurance Program is eg incorporated in plant procedures and implemented by the

( ,) Clinton Power Station organization.

10. Manager - Environmental Affairs The Manager-Environmental Affairs reports to a Vice l President and is responsible for providing technical support and assistance for ensuring that Clinton Power Station operations meet established guidelines and regulations regarding the plant's non-radiological effect on the environment.

11. Manager - Nuclear Planning and Support The Manager-Nuclear Planning and Support reports to a Vice President and is responsible for project controls, planning, programming and scheduling, nuclear purchasing, and nuclear support. The Manager-Nuclear Planning and Support ensures that these activities are performed in accordance with the requirements of the IP Nuclear Power Quality Assurance Program.

12. Manager - Startup The Manager - Startua reports to the Vice President and is responsible for Checkout and Initial Operation (C &

(-'s q ') IO), Preoperational and Acceptance testing and for providing assistance to the Power Plant Manager for Startup testing.

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u IP - Nuclear Powar' CHAPTER 1 Construction 0.A Manual I

l 13. Director - Project Controls l

O The Director of Project Controls reports to the Manager-Nuclear Planning and Support and is responsible l for directing activities related to estimaring total project cost, budgeting and cash flow, cost controls, material' expediting, field construction accounting, and

! administrative controls on the project.

! 14. Director - Nuclear Support The Director - Nuclear Support reports to the Manager-Nuclear Planning and. Support and is responsible for the j i

! direction and management of the Nuclear Support Staff.

F The organization ensures regulatory requirements, IPC ,

! commitments, and IP goals and objectives are l l accomplished in an efficient and timely manner.

15. Director - Nuclear Training

!' The Director - Nuclear Training reports to a Vice l President and is responsible for the direction and  ;

management of the Nuclear Training for Clinton Power l Station. Duties include developing training ,

standards,providing centralized training, providing

education support to Nuclear Manager / Directors and i maintaining operation of the simulator.

I 16. Director-Nuclear Purchasing l 4

j. The Director-Nuclear Purchasing reports to Manager-

! Nuclear Planning and Support and is responsible for the 1

procurement of items and services from approved

! supaliers in accordance with applicable commercial,

tecinical, and quality assurance requirements.

[ 17. Manager-Quality Assurance [

I The Manager Quality Assurance reports to a Vice Presi-dent and has direct access to the Executive Vice

! President. The Manager-Quality Assurance is responsi-ble for IP's overall Quality Assurance program defini-i- tion, direction, evaluation, and approval, including > ,

the IPC Nuclear Power Quality Assurance Program. The l Manager-Quality Assurance directs the Quality Assurance i

departmental activities related to the design procurement, construction, and operation of the Clinton Power Station. The Manager-Quality Assurance interfaces l with the Nuclear Regulatory Commission, Office of

Inspection and Enforcement, Region III and the

! Authorized Insaection Agency for quality assurance i activities. Tie Manager-Quality Assurance or a

! designated alternate has been delegated the

! res1onsibility and authority to stop unsatisfactory wort during plant operation as well as during plant 6 of 16 03/05/85 i

IP - Nuclear Pow:r CHAPTER 1 Construction QA Manual modification, maintenance and in-service inspection (f--)s periods, provided the health and safety of the public or impact on capability to safely shut down the plant is not affected. The qualifications of the Manager-Quality Assurance are at least equivalent to the education and experience requirements of Section 4.4.5 of ANSI /ANS 3.1-1978, " Selection and Training of Nuclear Power Plant Personnel," or Section 4.4.5 of proposed draft ANS 3.1-1979. Specifically, the Manager-Quality Assurance will meet at least one of the following:

1. At the time of initial core loading or assignment to the active position, the responsible person shall have six years experience in the field of quality assurance, preferable at an operating nuclear power plant, or operations supervisory experience.

At least one year of this six years experi-ence shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance orga-nization.) A maximum of four years of this six years experience may be fulfilled by

-s related technical or academic training; or,

'/

2. EDUCATION:

Bachelor Degree in Engineering or related science.

EXPERIENCE:

At the time of initial core loading or appointment to the active position, the responsible person shall have four (4) years experience in the field of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position preferably at an operating nuclear plant or a combination of the two. At least one (1) year of this four years experience shall be nuclear power experience in the implementation of the quality assurance program. Six (6) months of the one year experience shall be obtained within the quality assurance organization. He must possess a thorough working knowledge of 10CFR50 Appendix B, ANSI N45.2 and ANSI N18.7 and familiarity with the ASME Boiler and Pressure Vessel Code, and other applicable regulations, codes, and standards.

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IP - Nuclear Power CHAPTER 1

., Construction QA Manual

,r 17.1 Director - Quality Engineering and Verification

' ( .

The Director - Quality Engineering and Verification reports to the Manager - Quality i Assurance. He is responsible for direction and management of the Quality Operations and Maintenance, Quality Control, and Quality Technical Support staffs for defining, establishing, and verifying compliance with the IP Nuclear Power Quality Assurance Program.

1. QUALITY-TECHNICAL SUPPORT SECTION

The Quality-Technical Support Section is

supervised by the Supervisor-Quality Technical Support who reports to the Director-Quality Engineering and Verification. The Quality Technical Support Section assures that documents involving the following activities conform to the i applicable QA program requirements of regulatior.s, standards, codes, and other specific commitments

l Startup, engineering, radiation protection, and j chemistry. The section establishes quality control inspection points in the aforementioned documents, as applicable.

The Quality-Technical Support Section is

, responsible for the planning and performance of surveillances on the aforementioned activities, as

applicable, including ensuring timely and i responsive corrective action to IP surveillance j findings, and for advising management as to the effectiveness of quality assurance prograr implementation for those specific functions surveilled.

, If significant quality problems are identified,

, the Supervisor-Technical Support has the responsibility to recommend to IP management to STOP WORK pending satisfactory resolution of the identified problem.

2. QUALITY CONTROL SECTION l The Quality Control Section is supervised by the Supervisor - Quality Control who reports to the

Director - Quality Engineering and Verification.

The Quality Control Section is responsible for i conducting and reporting inspections and nondestructive examination of items or processes associated with startup, testing, maintenance, modification, nuclear fuel and 11 ant support 4 activities performed by IP whic'1 affect quality.

~!

The Quality Control Section is also responsible for initiating reports of nonconforming items or 1 conditions discovered during inspections.

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IP - Nuclcer Powar CHAPTER 1 Construction QA Manual L

() If significant quality problems are identified, the Supervisor-Quality Control has the authority i and responsibility to hold or curtail and control further processing, delivery, or installation of j nonconforming material, provided the ability to place the plant in a. safe and stable condition is not affected.

3. QUALITY-OPERATIONS AND MAINTENANCE SECTION i

The Quality Operations and Maintenance Section is

described in the IP Nuclear Power Operations Quality Assurance Manual.

17.2 Director - Quality Systems and Audits -l

The Director - Quality Systems and Audits reports i to the Manager - Quality Assurance and is responsible for providing direction and j administration of the Quality Systems and Audits L staffs in defining, establishing and verifying j- compliance with the IP Nuclear Power Quality

Assurance Program.

!. 1. QUALITY SYSTEMS SECTION

! The Quality Systems Section is supervised tur

the Supervisor - Quality Systems who '

reports to the Director - Quality Systems and 4 Audits. The Quality Systems Section is

! responsible for periodically assessing i departmental effectiveness in implementing the IP Nuclear Power Construction Quality Assurance Program, trending of conditions

adverse to quality, and coordination of

Quality Assurance reviews and approvals of QA program requirements associated with the QA manual and Corporate Nuclear Procedures. The j Quality Systems Section is responsible for the administration of tracking programs for 10CFR21 and 10CFR50.55(e) items. The section i is also responsible for the coordination and

. administration of QA/QC training programs for department personnel. l If significant quality problems are

, identified, the Supervisor - Quality Systems j has the authority and responsibility to j recommend to IP Management to STOP WORK

pending satisfactory resolution of the

{ identified problem.

t 1

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IP - Nuclear Powar CHAPTER 1 Construction QA Manual

2. AUDIT SECTION The Audit Section is supervised by the Supervisor - Audits, who reports to the Director - Quality Systems and Audits. The Audit Section is responsible for the planning, scheduling, and conduct of internal and external IP audits. The section ensures timely and responsive corrective action to IP audit findings and advises management as to the effectiveness of quality assurance program implementation for those specific functions audited.

If significant quality problems are identified, the Supervisor - Audits has the authority and responsibility to recommend to IP management to STOP WORK pending satisfactory resolution of the identified problem.

3. TRAVELER TRACKING SECTION

{.

4 The Traveler Tracking Section is supervised by the Supervisor - Traveler Tracking, who reports to the Director - Quality Systems and Audits. The Traveler Tracking Section is responsible for ensuring travelers are allotted, controlled and tracked in accordance with established guidelines and

procedures.

t j 17.3 Director-Contruction and Procurement Quality

Assurance

! The Director-Construction and Procurement Quality l Assurance reports to the Manager-Quality

'. Assurance. He is responsible for direction and l management of the Construction and Procurement QA i staffs. In this position he is responsible for-1

, defining, establishing, and verifying compliance

with the IP Nuclear Power Quality Assurance Program.

1. Construction Quality Assurance Section The Construction Quality Assurance Section is supervised by the Supervisor - Construction Quality Assurance who reports to the Director-Construction and Procurement QA.

O' The Construction QA Section is responsible for planning, scheduling, conducting and reporting surveillances of activities associated with the construction of Clinton 10 of 16 03/05/85 l

2 IP - Nuclear Power CHAPTER 1 Construction QA Manual Power Station. This section ensures timely i

)

and responsive corrective action to IP Construction QA surveillance findings and advises management of the effectiveness of QA program implementation for those specific functions surveilled. This section is also responsible for assuring that documents such as subcontractor QA manuals, procedures and instructions conform to codes, standards, regulations and other specific commitments.

Additionally, this section reviews reports of selected nonconformances and their dispositions.

If significant quality problems are identified, i the Supervisor-Construction Quality Assurance has the authority and responsibility to recommend to IP Management to STOP WORK pending satisfactory resolution of the identified problem.

2. Procurement Quality Assurance Section The Procurement Quality Assurance Section is supervised by the Supervisor-Procurement Quality Assurance who reports to the Director-Construction and Procurement QA. The Procurement Quality Assurance Section assures that procurement

! Os documents contain the QA requirements of the FSAR, establishes receipt inspection criteria, establishes source surveillance inspection plans, evaluates suppliers QA programs for meeting the FSAR commitments, performs surveys at suppliers facilities, processes procurement related nonconformances, performs source surveillances, performs receipt inspections, and reviews and approves vendor working procedures.

If significant quality problems are identified, the Supervisor-Procurement Quality Assurance has the responsibility to recommend to IP management to STOP WORK pending satisfactory resolution of the identified problem.

17.4 Supervisor - Welding /NDE/ Testing l

The Supervisor-Welding /NDE/ Testing reports to the Manager-Quality Assurance and is responsible for performing and reporting "overinspection" of accepted plant hardware, and the site testing laboratories for weld testing and NDE.

17.5 Administrative Supervisor

)

The Administrative Supervisor reports to the s

Manager-Quality Assurance. He is responsible for 11 of 16 03/05/85

_ _ _ _ _ _ _ _ _u _ . _ _ _ _ _ _ . . __

IP - Nucloer Power CHAPTER 1 l Construction QA Manual s the control, issuance and distribution of documents associated with the IP Nuclear Power

Quality Assurance Program, such as QA Manual, j departmental procedures and instructions.

B. Sargent & Lundy-

1. Sargent & Lundy has an organization which provides for the Balance of Plant design. Additionally, Sargent &

i- Lundy has available to IP, technical resources to assist in the review of the NSSS, provide engineering support for construction and startup, and provide technical assistance on engineering work and procurement activities.

2. Sargent & Lundy has a Project Manager assigned for CPS who interfaces between IP and the Sargent & Lundy organization. He is responsible for transmitting the IP requirements to the appropriate Sargent & Lundy organizations and assuring that the commitments have been met.

C. General Electric

1. General Electric has an organization which provides the design and fabrication of the NSSS and nuclear fuel.

b 2. General Electric has a Project Manager who administers 4

the contract for NSSS equipment through the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

j. Plant Warranty Run.

3. General Electric has a Project Manager who administers i

the contract for the nuclear fuel fabrication.

4. General Electric has a Site Construction Manager to coordinate field installation of General Electric scope ,

equipment.

D. Baldwin Associates

1. Baldwin Associates has an organization which provides j field construction. Construction activities contracted separately by IP and General Electric are not subject to control by Baldwin Associates, however Baldwin Associates retains cognizance and coordination of interfaces.

2. Baldwin Associates has a Clinton Station Project Manager who is the interface between IP and the Baldwin Associates organization. He is responsible for managing the construction forces to assure that CPS is O- built in accordance with the approved specifications and drawings.

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IP - Nuclear Power CHAPTER 1 Construction'QA Manual

' 3. Baldwin Associates has a Clinton Station Manager of Quality and Technical Services independent of the BA Clinton Station Project Manager. He is responsible for the activities of the Quality Assurance, Quality Control and Technical Services Departments.

The Baldwin Associates Manager of Quality and Technical Services is the interface between the Baldwin Associ-ates Quality organization and the IP Quality Assurance organization. The Baldwin Associates Manager of Quality and Technical Services receives project direc-tion from the IP Vice President on matters related to j quality.

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1 t

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.a IP-Nuclear Power

' Construction QA Manual NOTE: UP-TO-DATE DEPARTMENTAL ORGANIZATIONAL

' CHARTS AND FUNCTIONAL DESCRIPTIONS SHALL BE MAINTAINED AS PART OF CHAIRMAN AND DEPARTMENTAL DOCUMENTATION.

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\g APPROVED M8Mdead:7 Date 77##6' g, Manager-QA PURPOSE:

To describe the scope, function, and features of the Quality Assurance Programs of IP and its contractors governing design, i procurement, fabrication, construction, inspection, testing, and preparations for commercial operation of the Clinton Power Station.

REQUIREMENTS:

A. Interface The IP Nuclear Power Quality Assurance Program is composed of the internal Construction Quality Assurance Program of IP supplemented by the programs of its major contractors (Sargent & Lundy, General Electric, and Baldwin Associates).

IP has the overall responsibility for nuclear quality e' assurance applied to Clinton Station. IP has delegated to Is)s each of its contractors the responsibility for developing individual quality assurance programs covering their respec-l tive scopes of effort. These programs are approved by the Illinois Power Quality Assurance department for use at the Clinton Project.

The role of IP Quality Assurance is to direct the diverse efforts of IP and its contractors so that total program

implementation is effectively achieved. The IP program has t as its objective achieving a final plant which is demon-l strably planned, designed, built and tested in accordance l with applicable governmental regulations and appropriate codes, standards, and guides.

B. General i

! The Quality Assurance Programs of IP and its contractors

! have the essential elements as shown by Table 2-1 and meet

! the following requirements.

i j 1. The Quality Assurance Program is clearly described and documented.

i 2. There is an overall description of the Quality Assur-l , ance Program that describes the relationship of such j s

_) documents as directives, policies, and procedures I within the program.

l l

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IP - Nuclear Powar CHAPTER 2 Construction QA Manual 4

r'S 3. The scope of the program is delineated.

b 4. The organizations involved are identified and the scope.

of their functions and interfaces defined.

5. Activities affecting quality and the conditions under j which these activities function are controlled.

l

6. Special skills, processes, and equipment are applied as required.

4

7. Indoctrination and training is provided to assure that suitable proficiency is achieved and maintained.

J

8. The program satisfies applicable NRC regulations, and committed to codes, and standards.

9. There is management cognizance of the program.

C. Codes and Standards The Illinois Power Company and its contractors maintain Nuclear Quality Assurance Programs which conform to the ANSI

Standards and NRC Regulatory Guides listed in Table 2-2.

DIVISION OF RESPONSIBILITY:

f IP provides overall management of quality assurance activities at the Clinton Power Station. This manual is the principal document of the IP Quality Assurance program and sets forth the QA t

requirements to which IP and its contractors shall conform.

A. IP is responsible for:  !

1. The IP Nuclear Power Quality Assurance Program for the design, construction and related testing of the Clinton

! Power Station is based on a management endorsed,

formally documented, and implemented program which includes the following elements

a. Organization The Company has established an organization l responsible to top management for the design and

construction of CPS in accordance with applicable j regulations, codes, and standards.

b. Program A Quality Assurance Program description is docu-mented in this IP Nuclear Power Construction O Quality Assurance Manual which describes the obj ectives , requirements , interfaces, and division  :

of responsibility for implementing the program.

i i 2 of 11 03/05/85 l t

i IP - Nuclear Powsr CHAPTER 2 l Construction QA Manual '

O c. Procedures y/

Written procedures are approved by management for use in conducting activities within the scope of the QA program,

d. In-line Reviews In-line reviews of procedures, instructions, nonconformance reports, and overinspection of contractor activities are performed to provide additional assurance that QA program requirements are prescribed and achieved.

e. Surveillance and Audits Independent, systematic, documented surveillances and audits, are used to evaluate achievement of the objectives and the degree of compliance with program requirements.

2. The IP Nuclear Power Construction Quality Assurance Program is established and supported by three tiers of documents; each successive tier transmit requirements from a higher level of authority to the next successive lower document level.

(S

\'_) a. Nuclear Policy Statements, which are documents issued by Corporate Management to promulgate authoritative management directives establishing and defining Quality Assurance policies within the Illinois Power Company Nuclear Power Program.

b.1 IP Nuclear Power Construction Quality Assurance Manual, which describes the objectives, requirements, interface relationships, and assignment of responsibilities for accomplishing activities which affect the safety-related functions of systems, structures, or components.

It contains the minimum requirements to be applied by IP and contractors. The manual is developed, approved, and maintained current by the Manager -

Quality Assurance. The company management's endorsement of the IP Nuclear Power Construction Quality Assurance Program is signified in the

" Policy Statement" portion of the manual.

b.2 Corporate Nuclear Procedures (CNP), which are documents developed, approved, and issued to provide corporate direction and policy pertaining gS to appropriate Nuclear Program Activities. CNPs

( ,)

are reviewed by the Manager - Quality Assurance for compliance with regulatory Quality Assurance requirements and are approved by corporate level management.

3 of 11 03/05/85 l

4

-IP - Nuclear Power CHAPTER 2 Construction QA Manual b.3 IP Nuclear Power ASME Quality Assurance Manual, O which describes the objectives, requirements, interface relationships, and assignment of responsibilities for accomplishing activities which affect pressure vessels, piping systems, and associated equipment. It contains the minimum requirements to be applied by IP and contractors.

The manual is developed and maintained current by the Director - Construction and Procurement QA.

Authorization for use is signified by the signature of the Vice President (Nuclear). The company management's endorsement of the IP Nuclear Power ASME Quality Assurance Program is signified in the " Policy Statement" portion of the manual.

b.4 CPS Records Management Standards, which provide direction in the areas of records identification, preparation, collection / review, turnover / transfer, storage, preservation, and maintenance.

c. Departmental Procedures or Instructions, which are developed, approved, and issued within each organization to further implement the requirements of Corporate Nuclear Procedures and the IP Nuclear Power Construction Quality Assurance Manual.

O These departmental procedures or instructions provide more detailed direction to IP personnel engaged in Nuclear Power related activities.

3. The IP Nuclear Power Quality Assurance Program applies to those structures, systems, and components shown in Appendix A of this Manual. The IP Nuclear Power Construction Quality Assurance Manual requirements described herein apply to Clinton Power Station activities prior to turnover of systems, structures, and components by the constructor to IP. These activities include design, certain procurement activities, fabrication, construction, inspection, and related construction testing. After turnover, the IP Nuclear Power Quality Assurance Program requirements described in the IP Nuclear Power Operational Quality Assurance manual apply.

4. Changes to this Quality Assurance Manual are controlled

- by the provisions contained in Appendix B of this Manual. The Manager-Quality Assurance establishes and maintains a list of recipients of the IP Nuclear Power Construction Quality Assurance Manual.

5. The Manager-Quality Assurance periodically reports the O status and effectiveness of the quality assurance effort to the Executive Vice Presidents, Senior Vice President, Vice Presidents and Managers / Directors.

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IP - Nuclear Pow 2r CHAPTER 2 Construction QA Manual

6. Department Managers / Directors are responsible for (7~) establishing and maintaining formal training programs necessary to ensure proper qualification of his person-nel performing activities related to the quality of Clinton Power Station. Such training programs include indoctrination, lectures, formal schooling, job experience, and individual study, as appropriate.

7. Contractors' Quality Assurance Programs are reviewed and approved for compliance with applicable rules and regulations. Approval for use at the CPS site is documented in the IP Quality Assurance records and l approval notifications are sent to the contractors for l their Quality Assurance files.

B. Sargent & Lundy is responsible for: [

1. Sargent & Lundy maintains a suitable Quality Assurance Program which controls the design of the Balance of Plant, the review of the NSSS design, and auditing of its contractors and vendors.

2. The Sargent & Lundy Quality Assurance Program is described in the Sargent & Lundy Quality Assurance Manual. The Manual is supplemented by detailed g' procedures to implement the requirements of the program

(' and by written project instructions as determined by the Project Manager to be necessary for Sargent &

Lundy's work applicable to Clinton.

C. General Electric is responsible for: l

1. General Electric maintains a suitable Quality Assurance Program for design, fabrication, fabrication testing, and delivery of NSSS equipment and nuclear fuel.

2. The General Electric program is described in the NED BWR Quality Assurance Program Description. The program includes manuals and procedures necessary to provide quality surveillance and control for the GE scope of work. The General Electric Quality Assurance orga-nization is responsible for implementation of the GE program. The General Electric Policy Documents, Program Description, procedures, manuals, and imple-menting documents are applied to successively lower levels of GE work.

D. Baldwin Associates is responsible for: l

1. Baldwin Associates maintains a suitable Quality Assur-ance Program controlling its scope of construction and y -s) related activities for CPS.

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IP - Nuclear Power CHAPTER 2 i Construction QA Manual 1

2. The Baldwin Associates Quality Assurance Program is described in the Baldwin Associates Quality Assurance Manual. The Manual is supplemented by detailed proce-dures and written instructions, as needed for detailed

, work. It provides for systematic construction control which extends to special processes, materials control, i

procurement, field design control, inspection, con-struction, testing, records, and control of purchased components.

i l

'I O

t l

c O

l 6 of 11 05/09/84 1

u)

- J CHAPTER.2 '

IP - Nuclear Power Construction QA Manual TABLE 2-1 QUALITY ASSURANCE PROGRAM REQUIREMENTS Sargent General Baldwin Program Requirements IP

& Lundy Electric Associates 1.) Quality Assurance Organization x x x x 2.) Documented Quality Assurance Program x x x x and Procedures 3.) Design Control x x x x 4.) Control of Procurement Documents x x x x 5.) Instructions, Procedures, and Drawings x x x x 6.) Document Control x x x x 7.) Control of Purchased Items a.) Source Evaluation x x x x b.) Source Selection x x x x c.) Source Inspection and Audit x x x x d.) Receiving Inspection x x x 8.) Identification and Control of Materials, x x x Parts, and Components 9.) Control of Special Processes x x x 10.) Inspection Program x x x 11.) Test Control x x x 12.) Control and Calibration of Measuring x x x and Test Equipment 13.) Handling, Storage, Shipping and x x x Preservation 14.) Inspection, Test, and Operating Status x x x 15.) Control of Nonconforming Materials, x x x x Parts, and Components 16.) Corrective Action x x x x 17.) Quality Records x x x x 18.) Audits x x x x 7 of 11 05/09/84

IP Nuclocr Powar .

CHAPTER 2 Construction QA Manual TABLE 2-2 CODES AND STANDARDS ANSI STANDARD REG GUIDE ANSI N45.2 - 1977 RG 1.28 R/2(FEB 1979)

QUALITY ASSURANCE PROGRAM QUALITY ASSURANCE PROGRAM REQ.

REQUIREMENTS FACILITIES (DESIGN & CONST)

NOTE: The project QA programs , as committed in the -PSAR were in compliance with ANSI N45.2(1971) as endorsed by Regulatory Guide 1.28 Rev. O dated June 7, 1972. Later revisions of ANSI N45.2 and the associated Regulatory Guide were

.. incorporated in proj ect QA programs.

ANSI N45.2.1 - 1973 REG GUIDE 1.37 R/0 MARCH 1973 QA REQUIREMENTS FOR QUALITY ASSURANCE REQUIREMENTS CLEANING OF FLUID SYSTEMS FOR CLEANING OF FLUID SYSTEMS AND ASSOCLATED COMPONENTS AND ASSOCIATED COMPONENTS OF OF WATER-COOLED NUCLEAR WATERC00 LED NUCLEAR POWER POWER PLANTS. PLANTS.

ANSI N45.2.2 - 1972 REG GUIDE 1.38 R/2 MAY 1977 PACKAGING, SHIPPING, QUALITY ASSURANCE REQUIREMENTS RECEIVING, STORAGE AND FOR PACKAGING, SHIPPING, HANDLING OF ITEMS FOR RECEIVING, STORAGE, AND NUCLEAR POWER PLANTS DURING HANDLING OF ITEMS FOR THE CONSTRUCTION PHASE WATER-COOLED NUCLEAR POWER PLANTS ANSI N45.2.3 - 1973 REG GUIDE 1.39 R/2 SEPT 1977 HOUSEKEEPING DURING THE HOUSEKEEPING REQUIREMENTS FOR CONSTRUCTION PHASE OF WATER-COOLED NUCLEAR POWER NUCLEAR POWER PLANTS PLANTS O

• Denotes exceptions documented in Section 1.8 of the FSAR.

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i IP - Nuclear Powar CHAPTER 2 Construction QA Manual ,

TABLE 2-2 (Continued)

O ANSI STANDARD REG GUIDE ANSI N45.2.4'- 1972 REG GUIDE 1.30 R/0 AUGUST 1972

! INSTALLATION, INSPECTION, QUALITY. ASSURANCE REQUIREMENTS AND TESTING REQUIREMENTS FOR THE INSTALLATION, j FOR INSTRUMENTATION AND INSPECTION AND TESTING OF l ELECTRICAL EQUIPMENT DURING INSTRUMENTATION AND ELECTRICAL

THE CONSTRUCTION OF NUCLEAR EQUIPMENT POWER GENERATING STATIONS.

2

• ANSI N45.2.5 - 1974 REG GUIDE 1.94 R/l APRIL 1976 j QUALITY ASSURANCE REQUIREMENTS SUPPLEMENTARY QA REQUIRE- FOR INSTALLATION INSPECTION MENTS FOR INSTALLATION AND TESTING OF STRUCTURAL .

INSPECTION AND TESTING OF CONCRETE AND STRUCTURAL STEEL STRUCTURAL STEEL DURING THE DURING THE CONSTRUCTION PHASE CONST. PHASE OF NUCLEAR OF NUCLEAR POWER PLANTS POWER PLANTS.

• O ANSI N45.2.6 - 1978 REC GUIDE 1.58 R/l SEPT 1980 QUALIFICATIONS OF QUALIFICATION OF NUCLEAR POWER INSPECTION EXAMINATION AND PLANT INSPECTION, EXAMINATlGE TESTING PERSONNEL FOR AND TESTING PERSONNEL NUCLEAR POWER PLANTS ANSI N45.2.8 - 1975 REG GUIDE 1.116 R/O-R JUNE 1976 1

QUALITY ASSURANCE REQUIREMENTS SUPPLEMENTARY QUALITY FOR INSTALLATION INSPECTION, ASSURANCE REQUIREMENTS FOR AND TESTING OF MECHANICAL  :

INSTALLATION, INSPECTION EQUIPMENT AND SYSTEMS l AND TESTING OF MECHANICAL l

EQUIPMENT AND SYSTEMS FOR THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS.

• Denotes exceptions documented in section 1.8 of FSAR.

9 of 11 O

05/09/84

l

~IP - Nuclear Power CHAPTER 2 l

Construction QA MInual TABLE 2-2 (Continued) 4: O ANSI STANDARD REG GUIDE

~'

s ANSI N45.2.9 - 1974 REG GUIDE 1.88 R/2 OCT 1976 i

COLLECTION, STORAGE AND REQUIREMENTS FOR MAINTENANCE OF NUCLEAR POWER ,

i COLLECTION, STORAGE AND PLANT QUALITY ASSURANCE MAINTENANCE OF QA RECORDS RECORDS '

{ FOR NUCLEAR POWER PLANTS 1

! i i ANSI N45.2.10 - 1973 REG GUIDE 1.74 R/0 FEB 1974 i QA TERMS AND DEFINITIONS QUALITY ASSURANCE TERMS AND DEFINITIONS I ANSI N45.2.11 - 1974 REG GUIDE 1,64 R/2 JUNE 1976 ,

i i QUALITY ASSURANCE REQUIREMENTS

QA REQUIREMENTS FOR THE FOR THE DESIGN OF NUCLEAR

DESIGN OF NUCLEAR POWER POWER PLANTS  :

dp PLANTS 1

! ANSI N45.2.12 - 1977 REG GUIDE 1.144 R/l SEPT 1980 ,

REQUIREMENTS FOR AUDITING AUDITING OF QUALITY ASSURANCE QA PROGRAMS FOR NUCLEAR PROGRAMS FOR NUCLEAR POWER

! POWER PLANTS PLANTS l l

ANSI N45.2.13 1976 REG GUIDE 1.123 R/l JULY 1977 l

) QA REQUIREMENTS FOR CONTROL QUALITY ASSURANCE REQUIREMENTS FOR CONTROL OF PROCUREMENT OF i

! 0F PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER ITEMS AND SERVICES FOR NUCLEAR PLANTS POWER PLANTS

! ANSI N45.2.23 1978 REG GUIDE 1.146 R/0 AUGUST 1980 ,

! QUALIFICATIONS OF QA QUALIFICATION OF QA PROGRAM

! PR00 GRAM AUDIT PERSONNEL AUDIT PERSONNEL FOR NUCLEAR FOR NUCLEAR POWER PLANTS POWER PLANTS 1

O

• l

" Denotes exceptions documented in Section 1.8 of FSAR.

10 of 11 i 05/09/84

IP - Nuclear Power CHAPTER 2 Construction QA Manual TABLE 2-2 (Continued)  ;

ANSI STANDARD REG GUIDE I

ANSI N101.4 - 1972 REG GUIDE 1.54 R/0 JUNE 1973 QUALITY ASSURANCE FOR QUALITY ASSURANCE REQUIREMENTS PROTECTIVE C0ATING APPLIED FOR PROTECTIVE COATINGS TO NUCLEAR FACILITIES APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS

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O 11 of 11 05/09/84

IP - Nuclear Power CHAPTER 3 - DESTCN CONTROL Construction QA M'anual g

O h c h,f iusen

! E  !

e lsl Approved js/ J Mfjnd /-0%W fanager-QA Date PURPOSE:

To state the requirements for controlling design activities to assure design bases and regulatory requirements are correctly translated into design documents such as specifications, drawings, procedures, and instructions.

REQUIREMENTS:

A. Interface IP NSED is responsible for the design of the Clinton Power Station. The performance of design is assigned to contractors. General Electric will design the NSSS and nuclear fuel. Sargent and Lundy performs the design of the Balance of Plant and serves as the overall design x coordinator. In this capacity,.Sargent & Lundy receives and

. ) reviews applicable design documents from the other contractors, advises IP of design interface problems, and maintains configuration control. Baldwin Associates ensures that requests for design changes are forwarded to the appropriate design agent through IP.

B. General The design control systems of IP and its contractors will, as a minimum, have the scope and essential elements shown in Table 3-1 and shall meet the follow-ing requirements:

1. Appropriate design planning documents shall be developed to identify the specific design docu-ments, schedule their completion, and define major design milestones and other control points.

2. Design hases, regulatory requirements, saiety requirements, performance objectives, design margins, special processes, material and testing requirements, including acceptance criteria, quality assurance requirements, and operating objectives, shall be adequately translated into s various design documents. Design verification by testing when specified shall be identified in the design and purchase documents.

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IP - Nuclear Power CHAPTER 3 Construction QA Manual

3. Design documents shall describe quality related

(,_)s materials, components, systems, and structures in accordance with the design bases incorporated in the SAR. Design documents shall be based on applicable regulatory criteria and include identi-fication or cpecific engineering codes and stan-dards to be employed. Design deviations fron

required quality codes, standards, and regulations shall be documented, approved by appropriate authorities, and otherwise controlled.

, 4. Interfaces within and between each design orga-nization shall be controlled with adequate proce-dures to assure that there is no conflict in design objectives. The responsibility for the interface control shall be assigned.

5. A design review and verification system shall be established to assure adequacy and conformance of 1

~

materials, parts, equipment, and processes with design bases, regulatory requirements, and appli-cable codes and standards. The responsible design organization shall specify verifications. methods '

to be employed.

t When design is verified by review, the bases O a.

shall be documented and the work shall be conducted by personnel who did not perform the original design, but have technical qualifications equivalent to the minimum requirements for those performing the origi-( nal design work.

I i b. When design is verified by testing, the testing shall be specified to demonstrate adequacy of performance under the most adverse design conditions. Appropriate operating modes and environmental conditions -

in which the item must perform satisfactorily shall be considered in determining such conditions.

6. A design control system and procedures shall be established. They shall assure that participating design organizations review, approve, release, and distribute documents in a controlled manner. Changes to design documents shall be subjected to requirements equivalent to those for the basic document.

a. The design change record, or an accompanying document, shall idencify the other design O, documents which are affected by the change.

Such documents shall be suitably controlled or revised.

2 of 5 05/09/84

CHAPTER 3 IP - Nuclear Power Construction QA Manual

b. For significant design changes, the design i change record, or an accompanying document, will detail the reason and justification for the change.

4 i

j DIVISION OF RESPONSIBILITY:

IP maintains overall responsibility for the design of the Clinton j Power Station. In order to effectively fulfill this

. responsibility, IP has assigned organizational responsibilities which are summarized in Table 3-1. The assignment of these responsibilities are as follows:

1 1 A. IP is responsible for:

! 1. Control of design contractors. This responsibility is

( assigned to the Manager - Nuclear Station Engineering.

2. Translating requirements into design documents. The l verification of design document accuracy is assigned to

, the Manager - Nuclear Station Engineering and Director-Design Engineering.

s 3. The review and processing of design change requests. [

N The Supervisor-Construction and Startup Engineering has been assigned this responsibility.

4. Auditing contractors to determine whether their design l 3

control systems meet the specified requirements of this

[

Manual and are properly implemented.

l B .' Sargent & Lundy is responsible for:

1. Employing design control measures to assure design

intent is achieved in Balance of Plant design

, documents.

2. Producing and certifying appropriate Design j Specifications.

l 3. ASME Code related certifications (on behalf of IP) of

Design Specifications, Stress Reports, and other key documents for CPS.

4. Developing an intergrated equipment, system and component identification system for the entire station.

5. Specifying the special processes and the applicable i codes and standards for items of its design scope.

() 6. Specifying the inspection and related acceptance criteria applicable to Balance of Plant items.

4

, 7. Specifying the requiced tests and related acceptance I criteria for Balance of Plant equipment and systems.

3 of 5 03/05/85 l

IP - Nuclear Power CHAPTER 3 i Construction QA Manual

(

(,

8. Evaluation of design verification test results and verify for IP's permanent records that Balance of Plant equipment meets the designer's specified requirements.

1 I

9. Developing or specifying that suppliers provide the general requirements for special handling, storage, and shipping of Balance of Plant equipment.

C. General Electric is responsible for:

1. Employing design control measures assuring that design intent is achieved in NSSS and nuclear fuel design documents.

2. Producing code required Design Specifications and Stress Reports for NSSS equipment. and nuclear fuel.

D. Baldwin Associates is responsible for:

1. Employing field design control measures assuring conformance with the design intent as specified in design documents. BA shall refer design problems or change requests to IP for processing and resolution.

O l

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4 of 5 05/09/84

IP - Nuclear Power Chapter 3

, Construction QA Manual p(2) ,

i L

GENERAL DESIGN CONTROL SYSTEM ELEMENTS TABLE 3-1 Sargent General Baldwin Element IP & Lundy Electric Assoc.

1.) Design Planning x x 2.) Prepare Design Documents x x 3.) Identify and Resolve Inter- x x nal Design Interfaces l 4.) Identify and Resolve Exter- x x x nal Interfaces

. 5.) Perform Design Verification x x x l

1 6.) Review Design Documents for x x x incorporation of Regulatory 4

Requirements, Codes and

! Standards, Quality Require-

ments, Performance, Material

Application, Test Require-l ments, Acceptance Criteria, Inservice Inspection, Main-tenance, Special Processes 7.) Control Design Changes x x x x 8.) Provide Design Specs x x l

! and Strens Reports I i

9.) Review subcontractor and x x x lt Vendor Design Documents 10.) Audit Design Control System x x x x 1

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I t l Fage 5 of 5 03/05/85 i i

1-l IP-Nuclear!P5he*rQ3M e Construction o .l u u %g ui

}%

s 3h lCHAFT5R'%1DdOCUREMENT 4 U s QA$ManuaLU$u i !! d 0 0 % fjU Sa u lDdCUMENT CONTR i

! Approved [N dd /- 4~ ##

~

,l jf Manager-QA Date PURPOSE:

l

! To describe the requirements for review and control of

! procurement specifications, purchase orders, and associated i

documents so procurement of material, equi 7 ment, and services,

whether by IP, contractors, vendors, or subcontractors is l properly specified and controlled. l l  !

I j REQUIREMENTS:

! 1 l A. Interface )

I The main interface which exists for procurement docu-ment control is between IP, BA, and Sargent & Lundy. Under t

various conditions, S&L, BA and IP generate procurement documents and are responsible for conducting appropriate rev,iews to ensure that applicable technical and quality.

O assurance program requirements, etc. have been included.

Sargent & Lundy is responsible for the preparation and review of technical documents (drawings, specifications, ,

etc.). NSED is responsible for preparation of technical documents (drawings, specifications, etc.). IP and Baldwin Associates, normally are responsible for the review of bid-packages, the S&L prepared contractual documents, and the placement of the purchase orders. Coordination of changes to procurement documents after issuance of a purchase _ order or contract are by that organization issuing "

the purchase order or contract. A secondary interface exists between General Electric and S&L. GE furnishes S&L with information copies of all procurement documents released to GE subcontractors. GE also furnishes certain documents from its vendors and suppliers as they relate to j overall design coordination information. -

B. General IP and its contractors shall meet the following re- -

quirements:  :

1. Procurement documents shall specify the appropri- ,

ate quality requirements.  ;

(f 2. Procurement documents shall, when appropriate, require that the vendors and subcontractors have ,

quality assurance programs in compliance with 1 of 3 05/09/84  !

, IP - Nuclear Powar CHAPTER 4 Construction QA Manual g)

(

applicable codes, standards, rules and regulations.

Vendors and subcontractors 9111 be required to extend the applicable quality assurance requirements to their j lower tier suppliers.

3. Procurement shall be based on appropriate and j current specifications, drawings, and related i documents.

4. Procurement documents shall be reviewed to ensure that the correct specification, drawings, quality requirements,.and related documents are included or referenced.

5. Procurement shall be in conformance with approved written procedures.

6. Changes to procurement documents shall be subject to the same degree of control as the original procurement documents.

7. Requirement for establishing hold points and the release control shall be clearly identified in the procurement documents.

DIVISION OF RESPONSIBILITY:

IP has assigned proct.ement responsibilities as follows:

A. IP is responsible for:

1. Procurement of selected materials, equipment, and services for construction and installation at CPS.

2. Technical interpretation of design requirements for CPS, establishing the safety classification and the technical requirements for special procurements. These responsibilities are assigned to the Manager - Nuclear i Station Engineering.

3. Technical evaluation and technical approval of sources for special items and design services for CPS. These responsibilities are assigned to the Manager - Nuclear l Station Engineering.

4. Review of selected procurement documents generated by L S&L to assure that regulatory, technical, and quality assurance requirements are included. These s responsibilities are assigned to the Manager - Nuclear i Station Engineering.

5. Commercial aspects of procurement, including the control and placement of purchase orders and contracts 2 of 3 03/05/85 l

IP - Nuclear Power CHAPTER 4 Construction QA Manual for construction and installation related IP procure-Os ments. These designated responsibilities are assigned to the Director - Nuclear Purchasing.

6. Placing IP purchase orders and/or contracts with approved vendors and contractors. This responsibility is assigned to the Director - Nuclear Purchasing. l

7. Preparing the Quality Assurance program requirements of procurement documents for special items and services.

IP Quality Assurance is also responsible for evaluation and approval of the Quality Assurance programs of prospective vendors and suppliers of special items and services.

8. Periodical audit and/or survey of internal, vendor, and contractor purchasing procedures and practices to verify that the requirements of this Manual are being met, and are effectively providing procured items based on the correct purchasing documents. [

B. Sargent and Lundy is responsible for:

Preparation of procurement specifications and contracts for Balance of Plant materials, equipment, and services for

/T construction and installation.

V C. General Electric is responsible for:

Preparation and processing of procurement documents for NSSS equipment for construction and installation. General Electric is similarly responsible for procurement of selected material for the nuclear fuel.

D. Baldwin Associates is responsible for:

Procurement of selected BOP safety-related materials, equipment, and services for construction and installation at CPS.

l l

3 of 3 03/05/85 l

IP - Nucl ar? Pow:rg Construction-QA r3 - g 1 0 T u esn-Manual CHA Q INSTRUCTIONS, PROCEDURES &

l 1.1 ,~1- J 4 NG ;

>O>5gng,/ DRAWINGS v ,c ., ; , , ^ *u_. 'r,ql J _y O, j >

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anyJ,y

f N~ _

Approved MM/[md' J- d'- #d' jManager-QA Date

! PURPOSE:

To specify the requirements for use of instructions, procedures, sketches, drawings, and related material to control activities which affect quality.

REQUIREMENTS:

A. Interface Instructions, procedures, and drawings for execution of work are generated and implemented, where required within the using organization. Procurement specifications require that vendors and contractors, not assigned primary design

(~'

i responsibilities, submit drawings and procedures covering technical / quality portions of their work to S&L, GE, or BA as appropriate. Cleaning, handling, testing, and installa-tion procedures are originated by design organizations and/or manufacturers, and transmitted to BA for implementa-tion in the field.

B. General IP and its contractors shall meet the following re-quirements:

1. Written procedures, instructions, and drawings shall be developed and used, as appropriate, for activities affecting quality.

2. Instructions, procedures, and drawings shall include the applicable qualitative and quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

3. Where appropriate, instructions, procedures, and drawings for fabrication, installation, and testing shall indicate the sequential order of activities.

() 4. Separate records forming a part of instructions, procedures, and drawings shall have sufficient identification to relate the records to that specific instruction, procedure, or drawing.

1 of 3 05/09/84

w ue.a-w me 4

IP - Nuclear Power CHAPTER 5 Construction QA Manual DIVISION OF RESPONSIBILITY:

O

^

IP has assigned the responsibility for using instructions, procedures, and drawings as follows:

A. IP is responsible for:

l. Developing, approving, issuing and employing those

procedures, instructions, or drawings necessary to accomplish assigned tasks and responsibilities.

l

2. Determining the need for, developing, approving, issuing, employing and revising instructions related to each Supervisor / Manager's scope of effort.

3. Assuring that IP contracts or procurement documents assign responsibility for providing and using appropriate instructions, procedures, and drawings for control of activities performed which may affect quality.

4. In-line review and approval of selected Illinois Power,

! contractor and vendor procedures and instructions prior to implementation, to ensure compliance to codes,

! standards, regulations, SAR, and the requirements of

, this Manual.

l 5. Periodically audit internal, contractor, and vendor l activities to determine appropriate instructions, procedures, and drawings exist and are being properly implemented in accordance with the requirements of this Manual. '

B. Sargent & Lundy is responsible for:

1. Employing instructions, procedures, and drawings for its scope of effort.

2. Review drawings and procedures submitted by vendors and contractors prior to use at CPS.

C. General Electric is responsible for:

1. Employing instructions, procedures, and drawings for

[ its scope of effort.

2. Requiring subcontractors to employ instructions, procedures, and drawings for control of activities

! which may affect quality, i

O 2 of 3 05/09/84

I IP - Nuclear Power CHAPTER 5 i Construction QA Manual D. Baldwin Associates is responsible for:

l 1. Employing instructions, procedures, and drawings for 1 its scope of effort.

7

,i 2. Requiring it's' subcontractors to employ instructions,

procedures, and drawings for control of activities j which may affect quality.

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IP - Nuclear Power CHAPTER 6 - DOCUMENT CONTROL Constructio nQAgM u g (7 n,y bhje:LY.aJL.A b iU i As

,.o z., . .- y<..nw nvuw g@ea4 w e a:.a

)j a

I ,

Approved hx/b_dd,-d f-d"- 9lti~

jManager-QA Date PURPOSE:

To specify the requirements for approval, release, and changes of documents prescribing activities which may affect quality.

REQUIREMENTS:

A. Interface The principal document control interface is that of the transfer of design documents among the contractors and IP.

Specified design documents and technical procedures prepared and issued by other contractors, as well as those documents prepared and issued by S&L, are reviewed by S&L, for appro-val status. Each contractor and IP have measures

(}

\_, established to assure the receipt and use of approved and current documents.

i B. General IP and its contractors shall meet the following re-quirements:

1. Documents shall be reviewed for adequacy by appro-priately qualified personnel, approved for issue and use by authorized personnel, and distributed to/used at the location where the prescribed activity is performed.

2. Changes to documents shall be subjected to the same degree of control as applied to the original documents.

3. Organizations issuing documents related to design, fabrication, construction, inspection, and testing have and use a c'ontrol system which clearly identifies the document status such as preliminary, issued for information, approved for procurement, approved for construction, trial use, etc.

4. Document logs, index sheets, or other accountabil-Os_--

ity methods shall be prepared and maintained current.

1 of 2 05/09/84

i IP - Nuclear Power CHAPTER 6 Construction QA Manual

5. Measures shall be established to assure current

('")N

(, revisions of documents are distributed to the points of use and are used.

DIVISION OF RESPONSIBILITY:

IP has assigned document control responsibilities as fol-lows: ,

A. IP is responsible for:

1. Employing measures to receive, record, and internally distribute documents from contractors or other IP departments.

2. Generating and implementing written procedures for the control of documents produced by it.

3. Assuring that IP contracts or procurement documents require the contractors or vendors employ appropriate control of documents for those activities which may affect quality.

4. Periodically auditing internal, contractor, and vendor 4

/)

\,_,

activities to assure that appropriate document control measures are employed in accordance with this Manual.

B. Sargent & Lundy is responsible for:

1. Employing document control measures for chose documents related to its scope of effort.

2. Instituting a system for receipt and review of those documents required by contract or specification to be i

submitted.

C. General Electric is responsible for:

1. Employing document control measures for those documents related to its scope of effort.

2. Requiring that its subcontractors employ appropriate document control measures for the activities of those subcontractors which may affect quality.

D.- Baldwin Associates is responsible for:

1. Employing document control measures for those documents related to its scope of effort.

() 2. Requiring that its subcontractors employ appropriate document control measures for the activities which may

- affect quality.

2 of 2 05/09/84

I - ' - '

IP - Nuclearn Power , n p q n r CHAPTER '7 " i CONTROL OF Constructi'on?QA Manualu s PURCHASED' MATERIAL, EQUIPMENT,

/'N , d'"' AND' SERVICES

-I t_;a _. _. t a ..o .-"a .

Appraved Y W W $ e_/f Date f-[$5 pnager-QA PURPOSE:

To establish the requirements for a system to assure that pur-chased material, equipment, and services conform to procurement requirements.

REQUIREMENTS:

A. Interface Control of purchased m'aterial, equipment, and services is accomplished by evaluation and selection of procure-ment source and inspection of product or service at r~ either the vendor / contractors plant and/or upon receipt

(._,T

/ at the site. S&L interfaces with IP by performing bid evaluations, and reviewing vendor / contractor prepared documents. BA performs source evaluations within its scope such as QA program reviews and evaluations, procurement quality surveillance, source inspection, and/or receipt in-spection for BA purchased (BA issued purchase order or contract) material, equipment, or service. IP/QC performs receipt inspection of IP purchased (IP issued purchase order or contract) construction and installation related material, equipment and services.

B. General IP and its contractors shall meet the following re-quirements:

1. Procedures or instructions shall be utilized to effect control of purchased material, equipment, services, etc.

2. Source evaluation shall establish that contrac-tors, vendors, and subcontractors have demonstrable capability to provide a product, process, or service in accordance with the procurement documents.

(~]

V 3. Where valid knowledge or records of contractors',

vendors', and subcontractors' capability and performance are not available, a survey of the facilities, organization, process and inspection capabilities, and personnel skills will be made.

1 of 3 03/05/85 l

IP - Nuclear Power CHAPTER 7 Construction QA Manual r"N The results of such surveys shall be recorded and maintained.

b 4. Effectiveness of the control of quality by con-tractors, vendors, and subcontractors shall be assessed at intervals consistent with the impor-tance, complexity, method of purchase, and quality requirements of the product or service.

5. Receiving and/or source inspections shall be performed as necessary to ensure that purchased material, equipment and services conform to the requirements of the procurement documents.

6. Contractors, subcontractors, and vendors shall be required to provide documentary evidence of product conformance to procurement requirements.

This documentary evidence shall be present at the site prior to installation or use of the equipment or material.

DIVISION OF RESPONSIBILITY:

IP has assigned responsibilities for the control of pur-chased material, equipment, and services as follows:

( A. IP is responsible for:

1. Performance of technical reviews and evaluations of vendors and contractors capabilities prior to release for issuance of purchase order or contract for construction and installation related procurement.

This responsibility is assigned to the Manager-Nuclear Station Engineering.

2. Providing or assuring that pre-award and periodic evaluations of vendors and contractors quality assurance programs are accomplished for IP procurement of materials, equipment, and services.

3. Performance of commercial evaluations of vendors contractors and ensure that purchase orders or contracts are awarded only to approved vendors or subcontractors. This responsibility is assigned to the Director-Nuclear Purchasing.

4. Determining and designating receiving and/or source inspection requirements for IP procurement of material and services.

5. Periodical auditing and surveilling internal, O contractor, and vendor activities to assure that 2 of 3 03/05/85 l

b i IP - Nuclear Power- CHAPTER 7

. Construction QA Manual i

} .

control of purchased material, equipment, and services i - ) is in conformance with the requirements of this Manual.

B. Sargent & Lundy is responsible for:

1 Providing assistance to IP as required in control of purchased Balance of Plant material, equipment, and i services. This includes evaluations of vendor's technical i and quality assurance capabilities for furnishing the specified product (s).

4 C. General Electric is responsible for:

i 1. Control of purchased material, equipment, and services required for its scope of work.

! 2. Requiring that its subcontractors employ appropriate controls on purchased materials, equipment, and services required for their respective scopes of work. ,

[ -D. Baldwin Associates is responsible for:

l. Control of purchased material, equipment, and services j required for its scope of work.

i l 2. Subcontractors employing appropriate controls for j purchased materials, equipment, and services required for those subcontractors scope of efforts and perform-ance of source surveillances where required.

i

3. Performance of pre-award and periodic evaluations (including QA program evaluations) of vendors and/or contractors for BA procured construction and installation materials, equipment, and services.

4. Performance of receipt inspection for construction and i installation materials, equipment, and services received at the CPS site not procured by IP.

5. Documentary evidence of item conformance to procurement i requirements is available at the site prior to release i for installation or use.

lO .

1 3 of 3 05/09/84

l IP - Nuclear Power CHAPTE5'8 - IDENTIFICATION l Construction QA MaEualTO 310 " 7 TAND" CONTROL"OFrMATERIALS, y: 4 g< ,

1 , y 't 0 PARTS, AND: COMPONENTS O aL :a .o L 2,a J u u a . nua

• - < t g ,, a L ;j s., ,,

Approved / dv" penager-QA Date J-[ M PURPOSE:

To establish the requirements for a system of identification and control of materials, parts, and components so that traceability from arocurement, through installation, to end use, is assured and-the use of incorrect or defective items is avoided.

REQUIREMENTS:

A. Interface The identification and control of materials, parts, and components is primarily the function of the using organiza-tions; i.e., various fabricators, Constructor, and IP. In O addition, Sargent & Lundy interfaces with the various contractors and subcontractors in the assignment of identification information and the consolidation of random equipment identification systems into one intergrated identification system for the Clinton Station.

B. General IP and its contractors shall meet the following re-quirements:

1. Procurement documents shall specify an appropriate identity to be applied to items of purchase.

2. An inventory control system shall be employed for receipt of materials, parts, and components.

3. The identity of materials, parts, or components shall be on the item or on records traceable to the item. When physical marking is employed, the technique shall be indelible and not detrimental to the intended function of the item.

4. Identification shall be transferred to each part or piece of an item when it is subdivided into parts or O pieces.

5. Traceability shall be provided, when required by code or regulation.

1 of 2 05/09/84

IP - Nuclear Power CHAPTER 8 Construction QA Manual 1

N DIVISION OF RESPONSIBILITY:

]

IP has assigned the responsibility for identification and control of material, parts, and components, as follows:

A. IP is responsible for:

1. Incorporation of appropriate Quality Assurance program requirements for identification and control of materials, parts, and components into IP generated contracts or procurement documents.

2. Periodical auditing of contractors and vendors to assure that identification and control of materials, parts, and components is in accordance with the requirements of this Manual.

B. Sargent & Lundy is responsible for:

1. Incorporation of applicable requirements for identification and control of materials, parts, and components into technical and procurement documents generated. Sargent & Lundy shall also be responsible for specifying an equipment identification scheme.

C. General Electric is responsible for:

1. Identification of materials, parts, and components required for the NSSS equipment and nuclear fuel.

2. General Electric manufacturing organizations maintain-ing an identification and control system for materials, parts, and components.

3. General Electric's subcontractors employing ap3ropriate identification and control measures for the subcontrac-tors' scope'of effort.

D. Baldwin Associates is responsible for:

1. Establishing and maintaining the identification and control of materials, parts, and ccmponents delivered to the field.

2. It's subcontractors employing appropriate identifica-tion and control measures as required for the subcon-tractors' scope of effort.

O 2 of 2 05/09/84

I *

" 'j CHAPTER 9j PONTROL OF Construction;IP QA

- Fucleqr Power: o m onq Manual, , l ,

.,, ,, 3 y' SPECIAL PROCESSES

(

nu ,,d t a 22 - u - w = u OaGa is Approved jf//fM/dd# $ d~ fo~

/ Manager-QA Date PURPOSE:

To establish the requirements to assure that special processes are performad under adequate controls and that procedures govern-ing these processes are established in accordance with applicable codes and specifications, applied by qualified operators, and properly documented. Special processes are those activities such as welding, heat treating, plating, non-destructive examinations, etc., in which the quality of the product is heavily dependent upon control of the process and the skills of the personnel who perform the process.

REQUIREMENTS:

f'~ ') A. Interface Control of Special processes is normally the function of the fabricators and the Constructor.

Interfaces exist between the designing organizations, the fabricators, and the Constructor. Interfaces are controlled by the designing organization specifying the applicable special processes in design documents and subsequently reviewing the special process procedures submitted.

B. General IP and its contractors shall meet the following re- l quirements:

1. The need for special processes, and the codes or standards applicable thereto, shall be generally identified during design.

2. Fabricators and constructors shall utilize appropriate methods for the qualification and certification of special processes.

3. Personnel responsible for the performance and verifica-(~'sl tion of special processes will be qualified as required

( , by, and in accordance with, applicable codes and standards.

4. Special processes shall be accomplished under suitable, controlled conditions. This shall include the use of qualified equipment, adequate control of the 1 of 3 03/05/85 l

IP - Nuclear Pownr CHAPTER 9 Construction QA Manual r envitonment, and establishment of the proper prerequi-(_)S sites related to the process.

5. Records of procedure, personnel, and equipment quali-fication shall be maintained using suitable methods for storage and retrievability.

6. Records that special processes were performed in coupliance with qualified or approved procedures and with qualified personnel shall be maintained using suitable methods for storage and retrievability.

DIVISION OF RESPONSIBILITY:

IP has assigned responsibility for the control of special pro-cesses as follows:

A. IP is responsible for: 1

1. Assuring that IP contracts or require contractor or vendors' procurement documents to exercise control of special processes, as required, for equipment and materials.

/"'; 2. Measures to control special processes and ensure that i

t) personnel are cualified in accordance with applicable codes, standards, specifications, criteria and any other special requirements.

3. Periodical auditing of internal, vendor and contractor activities to assure control of special processes in accordance with this manual.

B. Sargent & Lundy is responsible for:

1. The review of the suitability and adequacy of submitted special process procedures.

2. Providing consultant service to assist IP in surveillance of special processes.

C. General Electric is responsible for:

1. Specifying the special processes and the applicable codes and standards for items of its design scope.

2. General Electric manufacturing organizations establish-ing systems to effect control of special processes for their scopes of supply.

(O,) 3. It's subcontractors exercising appropriate control of special processes.

2 of 3 03/05/85 l

! IP - Nuclear Power CHAPTER 9

Construction QA Manual j D. Baldwin Associates is responsible for: ,

, 1. Control of special processes performed in its i

construction activities. ,

l 2. It's subcontractors exercising appropriate control of

! special processes. 1 1

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! 3 of 3 05/09/84 -

1

IP - Nuclear Power CHAPTER.10 - INSPECTION i Construction QA Manual i i j

) .

\

Approved MMdd j/ Manager-QA Date

/-4~- #f I PURPOSE:

To establish the requirements for a program of inspection which provides assurance that the fabrication, construction, and installation activities conform to the requirements of the applicable instructions, procedures, and drawings.

REQUIREMENTS:

A. Interface The major responsibility for inspection is the function of various fabricators and Constructors. Acceptance criteria shall normally be specified or referenced in design

/~) and/or procurement documents, therefore the fabricators and the constructor will interface with the organizations

~'f issuing such documents regarding inspections.

B. General IP and its contractors shall meet the following require- I ments:

1. The general requirements for inspece. ions shall be identified and documented during design of parts, components, and systems.

2. The organization responsible for fabrication, construction, or installation of parts, compo-nents, and systems shall prepare a detailed inspection program responsive to the requirements established in the design and procurement docu-ments. Hold points, if required in purchase orders, shall be specified in the inspection program.

3. Persons implementing the inspection program, i.e.,

aerforming the actual inspection activity, shall ae organizationally independent of the persons performing the activity being inspected.

(<~}-

4. Inspection instructions shall contain or refer-ence, as a minimum:

1 of 3 03/05/85

, IP - Nuclear Powar CHAPTER 10 Ccnstruction QA MInual i .

a. A description of the inspection point (source, ys receiving, etc.) and, where applicable, the

, sampling system to be used.

b. The discrete identity of the part, component, j or system being inspected.

c. Applicable documents, drawings, and speci-fications pertaining to the activity or item ,

]

-under inspection. 1 i

d. The inspection method to be used for each operation.

l e. The type, range, and accuracy of the in-i spection instrument (s).

f. Criteria for acceptance.

l g. Qualification' requirements of the inspector.

5. Inspectors shall be qualified in accordance with

{ applicable codes or standards. .

I' 6. Where direct inspection or testing is impossible r~' or disadvantageous, indirect control by monitoring l process methods, equipment, and personnel 'shall be i employed. When necessary to provide an. adequate

! level of product quality assurance, both direct

. control (inspection and testing) and indirect i control (process monitoring) shall be utilized.

< When sampling plans are used, their applicability i shall be evaluated and justified in a documented

). manner.

t

7. Rework, repair, or replacement subsequent to

. inspections will require reinspection to the

extent necessary.to demonstrate acceptability and '

i conformance with'the rework / repair procedures.

i i 8. In-process and/or final inspections shall verify i that the specified requirements have been met.  ;

. DIVISION OF RESPONSIBILITY: i I IP has assigned responsibility for inspection as follows:

i

A. IP is responsible for:

c

1. Incorporating appropriate Quality Assurance program 4 eequirements for inspection into IP generated contracts j or procurement documents.

4 2 of 3 05/09/84 1

IP - Nuclear Powar CHAPTER 10 Construction QA Mtnusi

(N 2. Conducting "overinspection" of contractor and

\ ,) subcontractor activities. Overinspection shall be conducted on a sampling basis by qualified inspectors under the employment of IP who are indeaendent from the construction and inspection activities 'aeing reviewed.

3. Conducting periodic reviews and audits of contractor and vendor inspection programs and their implementation to ensure compliance with the requirements of this Manual.

B. Sargent & Lundy is responsible for:

1. Specifying inspection and related acceptance criteria in specifications and drawings it issues.

2. Providing consulting services to assist IP in surveillance of inspection activities or to perform special inspections.

C. General Electric is responsible for:

1. Specifying inspection acceptance criteria applicable to NSSS items and nuclear fuel.

r 2. Implementing inspection programs for the manufacture of

(_],/ NSSS equipment and nuclear fuel.

3. Requiring that its subcontractors establish and implement an inspection program for the subcontractors scope of effort.

D. Baldwin Associates is responsible for:

1. Inspection of it's construction and installation activities.

2. Its subcontractors establishing and implementing in-spection programs for the subcontractors' scopes of effort.

O b

3 of 3 05/09/84

IP - Nuclear Power CHAPTER 11 - TEST CONTROL Construction QA Manual 06 pm e-m nr n .

nn,p73 l i Approved ' M / W'[ ~J O/-4~- M/

i,/ Manager-QA Date 1

~- I PURPOSE:

To establish the requirements for control of the identification, performance, and evaluation of testing which will assure that the structures, systems, or components being tested will perform satisfactorily in service.

REQUIREMENTS:

A. Interface The designing organizations specify the tests and the acceptance criteria for equipment within their respective scopes of design. BA plans and performs tests associated ,

with construction. Checkout and initial operation tests t

will be directed / conducted by IP and supported by BA and l other applicable vendor personnel.

B. General IP and its contractors shall meet the following re- l quirements:

1. The tests and acceptance criteria necessary to assure satisfactory performance will be specified in design documents, technical specifications, or other related documents.

2. Test programs shall be developed to assure that required tests are performed in accordance with approved written procedures which incorporate or reference the design requirements, limits, end acceptance criteria ac specified by the appropri-ate design organization.

3. Written test procedures will be utilized to implement test programs. Individual test proco-dures shall contain or reference, as a minimum, the following provisions:

p,

( I a. Statement of the test objective

b. Prerecuisites to be fulfilled arior to the test, including availability of calibrated instrumentation and suitable environment.

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IP - Nuclear Pow:r CHAPTER 11 Construction QA M nual

c. Instructions for performance of the test, kT,) including requirement for verification that instruments selected are of correct type, range, and accuracy.

d. Data to be acquired,

e. Accept / reject criteria.

4. Test procedures and results shall be documented to facilitate evaluation and to provide a permanent record.

5. Adequate test evaluation shall follow testing to determine whether performance characteristics conform to design. The need for repair or rework and/or retesting shall be identified as necessary.

DIVISION OF RESPONSIBILITY:

IP has assigned test control responsibilities as follows:

A. IP is responsible for

(~' 1. Assurance that 'IP contracts or procurement documents

( require the contractor or vendor to establish and I implement an adequate program for testing equipment and materials.

2. Periodical auditing of internal, vendor, and contractor activities to assure that testing is controlled in accordance with the requirements of this Manual.

B. Sargent & Lundy is responsible for:

1. Identifying and specifying test requirements for certain systems and components. Establish specifications and descriptive material for such testing and related planning will be prepared in accordance with documented procedures, and systematically reviewed and aaproved by the same methods applicable to other phases of important safety related design.

2. Assistance to IP upon request, in testing and evalua-tion of test results.

C. General Electric is responsible fort n 1. Specifying the required tests and acceptance criteria

( ,) for NSSS equipment and nuclear fuel.

2 of 3 03/05/85

IP - Nuclocr Power CHAPTER 11 Construction QA Manuel O 2. Implementation of controlled programs for testing items (V in their scope of supply.

3. Evaluation of test results and certifications for IP's permanent records that NSSS equipment meets specified requirements.

4. It's subcontractors establishing and implementing adequate programs for control of test items in the subcontractors' scope of supply.

D. Baldwin Associates is responsible for:

1. Establishment and implementation of a controlled program for the static checkout of equipment and components it installs.

2. It's subcontractors to establish and implement adequate test control programs as appropriate.

O O

3 of 3 05/09/85 ,

IP - Nuclear _Powar. Chapter 12 -CONTROL OF Construction'QA Manual MEASURING

~

n .

., ,,AND TEST

r. . - ,

iEQUIPMENT

'Od U u-Lu, 2.eav u w gu h Approved by Y 2) @ D N J # " % % g .1C #[

fanager-QA vate d

PURPOSE:  !

To establish the requirements which will assure that tools, gauges, instruments, and other measuring and testing devices are adequately controlled and calibrated and that eccuracy is l maintained in order to verify conformance to requirements.

i REQUIREMENTS:

A. Interface i i

Control of measuring and test equipment is the function of organizations utilizing them.

B. General IP and its contractors shall meet the following re-

, quirements:

1. Measuring and test equi 3 ment shall be calibrated at scheduled intervals ay comparison with valid nationally recognized standards. If recognized standards are not available, the standards used shall be carefully preserved and available for traceability purposes.

2. Calibration intervals will be based upon the type of equipment, frequency of use, environment of .

use, and other conditions affecting accuracy.

3. Calibrations shall be performed using approved written procedures or appropriate manufacturers' manuals. Standards will be maintained and used in a controlled environment which will not adversely

,~

affcet the calibration procedure. ,

4. Required environmental controls may include such items as temperature, humidity, cleanliness, and (

radioactivity to levels compatible with the accuracy and operating characteristics of the standard as detailed in the calibration procedure.

5. The calibration of each item of measuring and test i

t equipment shall be controlled. Calibration control shall be visible, such as use of tags, labels, or decals attached to the equipment.

1 of 3 05/09/84

. - 1

. . -. .- .- -. = _ - - - - . _ _ _

}' IP - Nuclear Powar CHAPTER 12 4

Construction QA Manual I

/ 6. Controls shall provide for identification of measuring I (_-)/ and test equipment by appropriate records which shall contain.the calibration history. ,

i

{' 7. Equipment shall not be used past the expiration of the calibration period. If equipment is damaged, or' suspected to need recalibration, it shall be 4 rechecked as soon as possible, and, in any event,

prior to use. If equipment is found to be out of 4

calibration, an evaluation shall be made and documented of the validity of previous inspection i or test results based on that equipment and of the

acceptability of items previously inspected or tested.

j 8. Equipment found to be consistently out of cali-i bration shall be evaluated for repair and replace- ,

ment.

1

DIVISION OF RESPONSIBILITY: i IP has assigned responsibility for control of measuring and 1 test equipment as follows:

( ) LA. IP is responsible for

l 1. Incorporation of appropriate Quality Assurance program l

, requirements for the control of measuring and test 2 equipment into IP generated contractc or procurement i documents. i

2. Periodical auditing of internal, vendor,.and contractor procedures and practices to verify that effective control of measuring and test equipment is provided in accordance with the requirements of this Manual.

i B. Sargent & Lundy is responsible for:

i

! 1. Direction of activities which require a quality j assurance program for identification and control of

'l measuring and test equipment. However, Sargent & Lundy consulting service is provided to assist IP in surveillance of these activities.

{ C. General Electric is responsible for:

( 1. Implementation of effective measures for the control of j measuring and test equipment utilized for test and/or t

inspection of NSSS equipment and nuclear fuel.

( 2. It's subcontractors to establish and implement effective measures for control of measuring and test j equipment used.

! l i 2 of 3 03/05/85 I

. . . -. -. = . _ _ - - . _ _

l IP - Nuclear Power CHAPTER 12 Construction QA Manual D. Baldwin Associates is responsible for:

1. Establishment and the implementation of effective i measures for the control of measuring and test j equipment used by BA in construction, inspection, or test activities.

2. It's subcontractors to establish and implement i effective measures for control of measuring and test equipment used. 1 t

4 W

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1 l

1 1

1

.I i

6 f

i l

t 4

3 of 3 05/09/84 1

,,,-,,,-r--,_.,__,,-., ,.,.~,--m.,,- . . - . ~ . . . . - . . - . - - - - , , . , . , _ . - . , - . _ .

i -,

IP - Nuclear Power CHAPTER'13'-l HANDLING, STORAGE Construction QA Manual .& SHIPPING q Lu ..m u . _ . . .

QJ :m w 2

Approved M/MAeg J-#-#[

j/ Manager-QA Date PURPOSE:

i To establish the requirements for a system which will assure proper handling, storage, shipping, preservation and cleaning to prevent damage, deterioration, and loss of items.

REQUIREMENTS:

A. Interface Vendors are required to provide information relative to handling, storage, and shipping of material, parts , and I components to the Purchaser for use in storage and handling activities at the site. This information is contained in

() B.

purchasing or technical documents.

General IP and its contractors shall meet the following re- l quirements:

1. Written and approved procedures for handling, storage, shipping, preservation, and cleaning of materials, parts, and components within the scope of this program shall be used.

2. Procurement documents shall require vnndors and subcontractors to furnish procedures for handling, storage, shipping, preservation and cleaning of items supplied.

4

3. Shipping containers shall be marked to identify the contents, the sender, and the destination.

Tags securely attached to the shipping containers may be used if containers are too small or irregu-lar in shape to be marked directly with the required information. Handling shall be con-trolled by written procedures.

O

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4. Special markings shall be provided for packages containing items which are fragile or may sustain internal damage not readily detectable except by

disassembly.

1 of 3 03/05/85

IP - Nuclear Power CHAPTER 13 Construction QA Menuni rS 5. Written instructions shall be provided for the

(j preservation of items that are subject to deterioraticn or damage through exposure te air, moisture, radiation, or other environments during manufacturing and fabrication, storage, shipping, construction and installation.

6. Items shall be preserved by such methods as required to preclude damage, and which in them-selves have no deleterious effects on the items.

When special protective measures are provided by an agent which is consumed or rendered impotent, means shall be provided to periodically verify that protection is being maintained.

DIVISION OF RESPONSIBILITY:

IP has assigned responsibilities for handling, storage, and shipping as follows:

A. IP is responsible for:

1. Incorporation of appropriate Quality Assurance program requirements for controlling the handling, storage, and (r-'j) shipping of equipment and materials into IP generated contracts and procurement documents.

2. Assignment of Nuclear Station Engineering to assure that IP procurement documents require vendors to pro-vide information regarding proper handling, storage, and shipping with items they supply.

3. Periodical auditing of internal, vendor, and contractor activities to assure adequate handling, storage, and shipping in accordance with the requirements of this Manual.

B. Sargent & Lundy is responsible for:

i 1. Review of procedures for handling, storage, and shipping of equiptent and materials for adequacy.

C. General Electric is responsible for:

1. It's subcontractors to implement appropriate controls for their handling, shipping, and storage of NSSS equipment and nuclear fuel.

2. It's subcontractors to provide information for proper handling, storage, and shipping, tr w)#

3. Implementation of appropriate controls for handling, storage, and shipping of items they supply.

2 of 3 05/09/84

IP - Nuclear Powsr CHAPTER 13 Construction QA M:nual D. Baldwin Associates is responsible for:

1. Handling and starage of equipment received at the site for use in construction of the Station.

2. It's subcontractors and vendors to implement appro-priate controls for the handling, shipping, and storage of items in the subcontractors' scope.

3. It's subcontractors and vendors to arovide information for proper handling, storage, and siipping for items they supply.

O l

i

!O 3 of 3 05/09/84

IP - Fuclear Power _._ CHAPTER 14 - INSPECTION, TEST, Construction QA Manual _ ~ ~ '

~

~' ~

AND OPERATING

r. - - STATUS i i  !

J

'~

ganager-QA Date PURPOSE:

To establish the requirements for a system which identifies the status of material, parts, components, and assemblies through manufacturing and fairication, inspection, testing, construction, installation, and preoperational testing to assure that only items that have passed the required inspections and tests are used or installed.

REQUIREMENTS:

A. Interface l' ) Baldwin Associates interfaces with IP at the turnover x- ' of equipment, components, systems, and structures for checkout and initial operation. The systems employed by Baldwin Associates and IP for indicating status of inspection and tests also includes controls to clearly indicate jurisdiction and safety conditions.

B. General IP and its contractors shall meet the following re-quirements:

1. The inspection or test status of items shall be clearly identified. Markings which indicate status may include stamps applied directly to the item, tags, or labels attached to the item, routing cards that accompany the item, or records which are traceable to the item.

2. Visual evidence of status shall be documented and affixed to inspected items. A control stamp, signature, or initials shall be applied. If control stamps are used, a record of the assign-ment of control stamps shall be maintained.

(~'; 3. If markings are applied directly to the item,

\_- there shall be consideration given to the effect of the markings on the item. If impression stamping is used, it shall conform to the recuire-ments of applicabic specifications, codes anC standards.

1 of 2 05/09/84

IP - Nucleer Powar CHAPTER 14 Construction QA Manual

4. The method of indicating test or inspection status

()/

s, shall clearly and positively show whether or not the required test or inspection has been passed.

5. A system, such as tagging of valves and switches, shall be established that indicates the status of structures, systems and components to prevent inadvertent operation.

DIVISION OF RESPONSIBILITY:

IP has assigned responsibilities for the inspection and test status identification as follows:

A. IP is responsible for:

1. Assurance that IP contracts or procurement documents require contractors and vendors to establish and implement adequate measures to indicate inspections, tests and operating status.

2. Periodical auditing of internal, vendor, and contractor activities to assure that indication of status is in accordance with the requirements of this Manual.

() B. Sargent & Lundy is responsible for:

l '. Providing S&L consulting service to assist IP in sur-

veillance of inspection, tests, and operating status activities.

C. General Electric is responsible for:

1. Its subcontractors to estab'ish l and implement adequate measures to indicate inspection and test status of NSSS equipment and nuclear fuel.

2. Development and implementation of adequate measures for the indication of inspection and test status appropri-ate to their scopes of supply.

D. Baldwin Associates is responsible for

1. Its vendors and subcontractors to establish and implement adequate measures for indication of inspec-tion and test status during manufacture of equipment.

2. Development and implementation of a system to indicate inspection and test status during construction and p installation activities.

V 2 of 2 03/05/85 l

IP - Nuclear Power __ CHAPTER 15 ' . NONCONFORMING Construction QA Manual. MATERIALS, PARTS,:0R COMPONENTS Approved //e/M Md Map 6ger - QA Date

[- -#f PURPOSE:

To establish the requirements for positive-identification and disposition of materials, parts, or components which do not meet technical or quality requirements of drawings or design specifications and to prevent the inadvertent use of such nonconforming items.

REQUIREMENTS:

A. Interface Illinois Power interfaces with its vendors and subcontractors for the identification of nonconforming items. BA interfaces with IP for coordination with the O appropriate design organization, i.e., General Electric, Sargent & Lundy, for disposition of the nonconforming condition. General Electric advises IP and S&L of the disposition of nonconforming items in its scope of supply which may affect the Balance of Plant.

4 B. General i IP and its contractors shall meet the following re-2 quirements:

1. Procedures shall be established for the control of l nonconforming items.

2. Nonconforming items shall be clearly identified.

3. Nonconforming items shall be placed in a segregated

storage area when practical. Such storage areas

shall be cicarly identified as containing only nonconforming items.

4. Measures shall be established which control further use or installation of nonconforming items

pending disposition.

1

5. A technical review shall be performed to determine

! the disposition of nonconforming items. The i technical review shall be conducted by the same or l equivalent organization which established the I original design requirements.

1 of 3 03/05/85

i IP - Nuclear Power CHAPTER 15 Construction QA Manual 2

lT

\d

6. The disposition of nonconforming items may be one of the following: (a) use as ist (b) rework (to drawing l

, and specification requirements): (c) repair (to an acceptable condition) (d) reject (for this use): or .

. (e) non-hardware (for activities not affecting i permanent plant hardware.)

7. Repair and rework procedures shall be qualified and approved as required by the applicable procurement documents, specifications, codes and standards. Items  ;

which have been repaired or reworked shall be rein-i spected to appropriate acceptance criteria.

8. Procedures for control of nonconformances will include '

measures for notification to affected organizations.

9. Records shall be maintained to show objective evidence i that the procedures for controlling nonconforming items have been followed.

i 1

DIVISION OF RESPONSIBILITY:

i 4 'IP has assigned responsibilities for control of nonconform-ing materials, parts, or components as follows:

1 {

A.

IP is responsible for:

i 1. Establiahment and implementation of effective systems for the control of nonconformances encountered during

, their activities.

i 1

2. Designating in IP-generated contracts or procurement documents that contractors and vendors establish and ,

implement effective systems for disposition and control of nonconformances.

1

3. Reviewing recommended dispositions, if provided, for concurrence. Provides dispositions to selected Contractors Nonconformance Reports (NCRs).

4. Determining what additional review is required by the responsible design organization and reviews recommended dispositions made by the responsible design organization.

5. Providing in-line reviews and approvals of selected Contractors NCRs prior to implementation, to ensure compliance to the requirements of this manual.

O 6. Periodical audits of internal, vendors' and contractors' nonconformance systems to verify that control of nonconforming items is in accordance with l

the requirements of this Manual.

2 of 3 03/05/85

4 i

IP - Nuclear Po ar CHAPTER 15 Construction QA Manual B. Sargent & Lundy is responsible for:

1. Engineering justification for construction related nonconformances which are dispositi6ned " repair" or "use-as-is" or requirc a design document change as

requested by IP. S & L shall provide a similar l function for those BOP purchased items, materials, or i services when the purchase order specification requires i -that the nonconformance be referred to the purchaser.

C. General Electric is responsible for:

} 1. It's subcontractors to establish.and implement i effective nonconformance systems for NSSS equipment and

, nuclear fuel.

j 2. Establishment and implementation of an effective j nonconformance system for their scope of supply.

3. Disposition of nonconforming items related to the NSSS 4 and nuclear fuel as requested by.IP. l 4

l D. Baldwin Associates is responsible for:

i 1. It's vendors and subcontractors to establish and implement effective nonconformance systems for i

O equipment supplied or installed by those subcontractors.

I I

2. Establishment and the implementation of an effective system for the control of nonconformances encountered during construction and installation.

l 3. Establishment of a system which refers selected nonconformances to IP for dispositions or coordination

with the responsible design authority in obtaining i dispositions and for obtaining IP Quality Assurance review and approval of the nonconformance, t

~

l I

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!O 1

i 3 of 3 0'3/05/85 i

IP - Nuclear Power CHAPTER 16 - CORRECTIVE ACTION Construction QA Manual A

\~-)

1 Approved  ; @388M[ '

h-h ff I f,d"2nage{ g gg g g j3 j Daye,y L g l 1 PURPOSE:

To establish the requirements which assure that conditions determined to be adverse to quality are promptly corrected in a l manner which precludes recurrence of such conditions.

REQUIREMENTS:

, A. Interface Those departments which manage or direct contractors interface with those contractors for obtaining corrective action. Requirements for specific corrective action are transmitted by IP to the contractors.

O g B. General IP and its contractors shall meet the following re-quirements:

1. A corrective action system shall be established.

2. Conditions adverse to quality shall be promptly identified and corrected.

3. For significant conditions adverse to quality, the corrective action shall include measures to preclude repetition, when appropriate.

4. Conditions adverse to quality shall be systemat-ically analyzed for causes and referred to manage-ment for resolution.

5. Corrective action shall be evaluated to determine effectiveness.

6. Records shall be maintained which demonstrate that idcntified conditions adverse to quality have been corrected. The records shall document recommenda-tions for corrective action and the implementation f

O of corrective measures.

1 of 2 05/09/84

i i IP - Nuclear Power CHAPTER 16 l Construction QA Manual l gS DIVISION OF RESPONSIBILITY:

IP has assigned responsibilities for corrective action as fol-lows:

A. IP is responsible for:

1. Implementing and maintaining a Corrective Action System for activities performed within the scope of this manual.

2. Assurance that IP contracts or procurement documents incorporate in'such documents requirements for estab- ,

lishment of contractor or vendor corrective action '

systems.

3. Administration of an internal and external (on site contractors) trending program for the identification of conditions adverse to quality.

4. Ad' ministration of a Management Corrective Action Request (MCAR). Program, a management tool whereby the Vice President and management of the responsible organization (either internal or external to IP) are advised of adverse conditions which require immediate 1

-~ corrective' action.

(/ 5. Periodical auditing of internal, vendor, and contractor activities to assure that corrective action systems have b6en implemented in accordance with the require-ments of this Manual.

B. Sargent & Lundy is responsible for:

1. Implementing and maintaining a corrective action system gov'erning its scope of work.

C. General Electric is responsible for:

1. Implementing and maintaining a corrective action system governing its scope of work.

2. Its subcontractors to establish a corrective action system for the subcontractors' activities associated with NSSS equipment and nuclear fuel.

D. Baldwin Associates is responsible for:

1. Implementing and maintaining a corrective action system governing its ' scope of work.

A i

2. It's subcontractors to institute corrective action l

I]

\ systems governing activities associated with the l supply, construction, or installation of equipment by l those subcontractors.

\'

2 of 2 05/09/84

IP - Nuclear Power CHAPTER 17 - QUALITY ASSURANCE Construction QA Manual RECORDS i~- -

Approved I / #

/ Manager-QA - -

,Date,, '

~

t PURPOSE: i To establish the requirements for collection, compilation, storage, and retrieval of records necessary to' provide evidence of quality in the design, procurement, fabrication, construction, installation, inspection and testing activities related to the Clinton Power Station.

REQUIREMENTS:

A. Interface Interfaces regarding quality assurance records exist where there is a division of the record keeping responsibility and subsequently turnover of records to IP. Some quality es records are kept by manufacturers and are maintained on an

(' available basis for a specific period of time. IP requires that these quality records be transferred to IP as major milestones are completed or after the manufacturers no longer plan to keep them.

B. General IP and its contractors shall meet the following require-l ments:

i

1. Sufficient records shall be prepared as work is per-formed to provide evidence of the quality of items and of activities performed.

l

2. Quality records shall be consistent with applicable codes, standards, specifications, and contracts and I shall be adequate for use in management of the Clinton l Power Station.

3. Quality records shall be filed in a timely and orderly manner to allow for access and retrievability. They shall be maintained in a file, room, or area that provides controlled access and protection against fire, flooding, vermin, and decay.

(Oj

4. The original quality of'the records shall be preserved to maintain archival quality. The quality of the

information shall enable the observer to readily identify information contained on the record. t 1 of 3 03/05/85 l

IP - Nuclear Power CHAPTER 17 Construction QA Manual rs 5. Records shall typically include results of reviews,

,)

f inspections, tests, audits, monitoring of work perfor-mance, and materials analysis. They shall also include as appropriate, closely related data such as qualifica-tions of personnel, procedures, and equipment.

6. Records which correctly identify "as built" conditions of items in the plant shall be maintained for the service life of the items. These records include material certification and test data for traceability and quality verification; reports of inspections, examinations, and test results for conformance veri-i fications; specifications, drawings, and records of nonconformance with resolutions.

7. Inspection and test records shall identify the inspec-tor or data recorder, type of observation, results, acceptability, and action taken for any problems noted.

DIVISION OF RESPONSIBILITY:

IP has assigned the responsibilities for quality assurance records as follows:

~ A. IP is responsible for:

1. Assurance that IP generated contracts or procurement documents specify the following:

a. Requirements for the generation, maintenance and control of technical and quality records.

b. Bequirements for the retention of appropriate technical and quality records at vendors' plants.

c. Requirements for transfer of appropriate technical and quality records to IP at the end of the specified retention period.

2. Development and implementation of Records Management Program, procedures and standards covering the identification, preparation, collection, review, turnover / transfer, processing, retention, retrieval and control of records generated in performing activities within the scope of the program.

3. Verification of the EA-administered record maintenance system for IP during the construction phase of CPS.

4. Geordinating the management of site quality records to ensure that a smooth and timely turnover of records and

( S) responsibility to the operating staff occurs.

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IP - Nuclear Powsr CHAPTER 17 Construction QA Manual

5. Periodical auditing of internal, contractor, and vendor (S

l activities to assure that control of quality assurance records is in accordance with the requirements of this Manual.

6. Development and implementation of a quality assurance records verification program to assure that these records meet the requirements of this manual.

B. Sargent & Lundy is responsible for:

1. Development and implementation of a record-keeping system for the records it produces during design of the Balance of Plant and associated activities.  ;

2. Turnover to IP of appropriate quality records accumulated by S&L during design, construction, and testing of the plant.

C. General Electric is responsible for:

1. It's subcontractors employing appropriate controls of quality assurance records required for subcontractors' work on NSSS equipment and nuclear fuel.

2. Development and implementation of a record-keeping

(~3 y ) system for the documentation and quality records required for NSSS equipment and nuclear fuel.

3. Turnover of appropriate documents and quality records generated by GE and its subcontractors to IP.

D. Baldwin Associates is responsible for:

1. It's subcontractors and vendors employing appropriate controls of quality records as required for the supply, construction and installation of equipment by those contractors.

2. Development and implementation of a record-keeping system for the cuality records generated or received during construction and installation.

3. Turnover of appropriate documents and quality records generated by EA and its subcontracters to IP.

9 D

3 of 3 03/05/85

i IP - Nuclear Power CHAPTER 18 - AUDITS Construction QA Manual i .. i Approved 8M2dj# /- f ##

,g Manager-QA Date f

PURPOSE:

To establish the requirements for a planned system of periodic audits which verify compliance with the quality assurance program and measure its effectiveness.

REQUIREMENTS:

A. Interface Audits and surveillance are among the main interfaces between IP and other participants in the Clinton Power Station. IP Quality Assurance interfaces with each contractor at the operating level and at the management s quality assurance level. Each contractor's audit function

) is to perform independently within its scope of responsibility, interfacing similarly with sub-tier vendors or contractors.

B. General IP and its contractors shall meet the following re-quirements:

1. Organizations whose functions affect the quality of the safety related aspects of the Clinton Power Station shall institute a comprehensive system of planned, periodic audits. The audit system will be sufficient to include the full range of activities covered by the scope of the applicable quality I

assurance program. The audit system will include provisions for both internal and external audits.

2. The audit system plan shall provide for regularly scheduled audits based on the status and impor-tance of the activities.

3. Personnel conducting audits shall have no direct responsibility to the organization being audited.

The lead member of the audit team shall be a

(-~

qualified audit team leader and shall instruct the other members during audit preparation.

1 of 3 05/09/84

s IP - Nuclear Power CHAPTER 18 Construction QA Manual

4. Written audit plans shall be developed for each audit (3) to be performed. These plans shall identify the scope, the requirements, activities to be audited, organizations involved, applicable documents, schedule and written procedures or checklists.

5. Audit reports shall be generated and retained.

6. Audit reports shall be transmitted to and reviewed by the appropriate managerial level having respon-sibility for the area audited. These managers shall be responsible for determining and imple-menting suitable action in response to the audit findings.

7. Audited organizations shall respond to audit reports as requested, stating corrective action taken or planned to correct findings and prevent recurrence.

8. Audit findings shall be followed up to verify that corrective action has been completed. Results of this followup shall be documented.

DIVISION OF RESPONSIBILITY:

IP has assigned responsibilities for auditing as follows:

A. IP is responsible for:

1. Assurance that IP contracts or procurement documents require contractors and vendors to establish and

, implement appropriate audit programs.

2. Establishment of an internal audit program and audit each IP organization performing activities within the scope of this program.

3. Establishment of an external audit program and audit contractors and vendors performing activities within the scope of this QA program to verify compliance to their respective quality assurance programs, contract requirements, and applicable requirements of this manual.

4. Coordination for the Executive Vice President, the performance of independent audits of the IP Quality Assurance Department.

I i

2 of 3 05/09/84 )

! IP - Nuclear Power , CHAPTER 18 L

Construction QA Manual B. Sargent & -Lundy is responsible for:

q\ )

1. Instituting an audit program assuring that its safety related activities associated with CPS are in compliance with the Sargent & Lundy Quality Assurance Program and this manual.

C. General Electric is responsible for:

1. Instituting an audit program assuring that safety related activities associated with NSSS equipment and nuclear

, fuel are in compliance with the General Electric Quality. Assurance Program and this manual.

2. It's subcontractors to institute appropriate audit programs.

3. Audits of its subcontractors to assure that activities associated with the subcontractors' scopes of effort i are in compliance with the subcontractors' quality assurance programs.

l D. Baldwin Associates is responsible for: l

+

i

1. Instituting an audit program assuring that activities i associated with construction and installation effort

! are in compliance with the Baldwin Associates' quality assurance program and this manual.

j- 2. It's vendors and subcontractors to institute appropriate audit programs.

3. Audits of its vendors and subcontractors' to assure that activities associated with the subcontractors' scope of effort are in compliance with the-subcontractors' quality assurance programs, i

1 i

f

!.4 i

O

]

i 3 of 3 05/09/84

, ,--,,n, .

,,,--,---,--,-----..--,--,-.-----n~-,n~-,,--r,--, -,.- - - , - . --. .- -- -,- .. -- .----,r-.- - - ,..~ - .

i IP - Nuclear Power Appendix A Construction QA Manual

- - a n e n 7 si n 7 e g p p ' p D 5 n., .,' .~ l' F ,

, G ? q s ti ,j l

. ll 1 l' u a ' '

CPS APPENDIX A Quality Assurance Program Scope The scope of the Quality Assurance Program described in this Manual is based on Sargent & Lundy's Procedure GQ3.03 " Class-ification Criteria". A recent version of the Clinton Classifica-tion Criteria includes the tabulation on the following pages which is shown here for illustration only. If an authentic list I

is needed please refer to the current revision of S&L's Clinton Classification Criteria document.

The last column of each of the following pages shows the applicable QA Requirements of the structures, systems, and components. The applicable Quality Assurance Requirements are as follows:

l 1. " App. B" indicates that the structure, system, or component l

(s/s/c) must be designed, purchased, constructed, tested, etc. in accordance with the Quality Assurance requirements (g) of 10CFR50, Appendix B which is implemented by the Quality f-l Assurance Programs described in this Manual.

2. "N/A" indicates that the S/S/C is not applicable to the

, requirements of 10CFR50, App. B.

l The reader is cautioned that the attached list is furnished for illustrative purposes only. Information required in the performance of work should be obtained by consulting the current source document.

l l

l l

l-l l '

1 i

i A-1 05/09/84

IP - Nuclear Power Appendix A Construction OA Manual i

CMSSI?! CAT!CN CRI"'ERIA Identification and 01assificatien l gggggg CLI!OCN PCVER STATICN PROJECT NCS. 4536/4597 Od.3*I**7.~.R I 1* E S.1'7ctures, REY. -10 9-12-83 I i (v/ -

Table ?.1 - Classification of Principal Structures. Systems and ccuspenents SAFI""fd SEISMICd QUALITY I ELEC"RICALM QA RE0'WSYl TRINCIPAL STRUC"'URES, (LTasT1,2, (Category I (Group A,3. (Glass J. (App.5 or l SYSIEMS & CCMPoh0C3 3 or othe r) or N/A) C,D or N/A) Non. Class N/A) ,

IE or N/A  !

g ANSI N16.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide j (ANS-21), 1.29 1.26,ASME. 1 32 (IEEE. 1.2d (ANSI-5

REFERENCES:

ANS-22, Section III 30d)* N45.2), Peg g

• ANS-23 Guide 1.6 1 (ANSI- l*

N45.2.ll) i I Rescter System *

1. Reactor vessel 1 I A N/A B i

2. Reactor vessel support l skirt 1 I N/A N/A 3 l

'3. Reactor vessel appurtances, pressure retaining portions 1 I A N/A B

4. CRD housing supports 2 I N/A N/A 3

5. Reactor inter'tal

. structures, engineered safety features 2 I N/A N/A B

6. Reacter intamal structures, other Other N/A N/A N/A N/A

7. Control rods 2 I N/A N/A B

8. Control rod drives 2 I N/A N/A 3

9. Core support structure 2 I N/A N/A 3

10. Power range detector hardware 2 I N/A lE B

11. Fuel assemblies 2 I N/A N/A B II Nuclesr 3 oiler Systes 1... Vessels, level instrumenta- 1 I A N/A B tion condensing cha.itbers

2. Piping, relief valve dis- 3 I C N/A B (energe and vent. including

?ccuum ratief tcives ,,

/N $

, / 3. Piping, main steas within outboard isola-

\s f I

tion valve 1 I A N/A B

4. Piping, feedvater with-in cutbcard isolation valve 1 I A N/A 3

5. Piping, other within r

cutboard isolation I

valves 1 I A N/A B

6. Safety / relief valves 1 I A 13 3

7. valves, main steam isolatiort valves 1 I A 13 3

8. Valves, other than ,

3 ' A 13 3 isolation valves and l

within drywell I

9. Mechanical modules. 2 instr'imentatien, with I B 't/A B

safety function

10. Electrical Modules with

• I N/A 13 3 safety function

11. Cables, with safety

• function I N/A 1E 3 l 12. Cuencher. Discharge Device 3 I C N/A B

13. Piping, from outboard iso- I I d N/A 3 lation valve to shutoff valve

14. Valves, shutoff 2 I B IE B

15. Valves. feedwater isolation 1 I A 1E B

16. SRVM System

• I N/A lE B III Pecirenlation Systam

1. Piping A i

l

2. Pumps i I N/A 3 1 I A N/A B

! 3. Valves 1 I A Non-13 3' l a. Motor . pump

5. Electrical =odules, with ot.her I N/A Ncn-u 3 safety function I N/A IE a G. Cable with safety func-

• I N/A IE B i

t10n

[ 7. LFMG Set and Panel Other N/A N/A Non-lE N/A

8. RPT Circuit Breakers

• I N/A lE B l 9. Recirc Pep Switchgear except other N/A N/A Non-1E N/A j

[N RPT circuit breakers i i

\j l

t

/ -Par definitiens and ir.sWactions, see cectJnn 2.0 p,9, 13 og ;4 FOR ILLUSTRATION ONLY A-2 03/05/85 I t

p IP - Nuclear Powar Appendix A

, Constructior. OA Manual CLASS 7 FICA?'CN CRJTERIA CLINTON POWER STATION Ider.tifica l.on and classification l PROJEC; NCS. 4535/4597 of Jafety- Related Structures

[ IEI Systems aad Components REY. 10 9-12-83

,m

[ \ Table 3.1 - Classification of Principal Structures , Systeme and Components

/'

PR.NCIPAL STRUCTURES, SAFETN SEISMICd OUALITyd ELECTRICALW CA REQ'MTSY SY3TEMS & COMPCNENTS (Class (category (Group A,B, (Class IE. (App. B or 1,2,,

3 or other) I or N/A) C,D or N/A) Non-Class N/A) 1E or N/A

, ANSI N18.2 Reg. Guide Reg.Cuide Reg. Guide Reg. Guide o (ANS-21), 1.29 1.26,ASME- 1.32(IEEE- 1.28 (ANSI-j (EFERENCES: ANS-22, Section II: 308) N45.2), Reg.

• ANS-23 Guide 1.64 (ANSI-N45.2.11)

IV CRD Hydraulic System

1. Voided

2. Valves, scram discharge 2 I B IE B volume lines and contain-ment isolation

3. Valves insert and with- 2 I B N/A B drawal lines

4. Valves, other Other N/A D Non-lE N/A

5. Piping, scram discharge volume lines and contain- 2 I B N/A B ment penetration

6. Piping, insert and with- 2 I B N/A B drawal lines

7. Piping, other Other N/A D N/A N/A S. Hydraulic control unit

a. Scram solenoid valves, 2 I D Non-lE B g test switches, and associated wiring

b. All other electrical Other I D Non-lE B components

9. Electrical modules, with

• I N/A 1E B safety function .

10. Cable, with safety function

• I N/A lE B 11.CRD water pumps Other N/A D Nca-1E N/A (p\

t /

b}' V Standby Liquid Control System

1. Standby liquid control tank 2 I B N/A B

2. Pump 2 I B N/A B

3. Pump motor Other I N/A Non-1E B

4. valves, explosive 1 I A Non-1E B

5. Valves, drywell, isolation and within 2 I A N/A B

6. Valves, beyond drywell isolation valves 2 I B Non-lE B

7. Piping, dcwnstream of explosive valves 1 I A N/A B

8. Piping, upstream of explosive valves 2 I B N/A B

9. Electrical modules, with safety function

• I N/A 1E B

10. cable, with safety function I N/4 lE B VI Neutron Monitorina System

1. Piping, TIP 2 I B N/A B

2. Electrical modules, IRM .

• i and APRM I N/A lE B

3. Cable, IRM and APRM

• I N/A lE B

4. Valves, TIP isolation ~ 2 I B N/A B

5. Purge Valve 2 I B IE B VII Reactor Protection

1. Voided

2. Cable with safety function I N/A 1E B

3. Volded

4. Solenoid inverters, EPA's

• I N/A 1E B and output breakers

5. Solenoid inverters, except 4 O the r I N/A Non-lE B above, and solenoid distri-bution panels

. 6. Instrument inverters and

• I N/A 1E B fN distribution panels

[ 1 7. Electrical modules with I N/A lE B i%<j ; safety function s

1. tor definitions and instructions, see section 2.0 page 11 of 24 Notes (1) and'(g) - ses page 24 FOR ILLUSTRATION ONLY A-3 03/05/85 l

IP - Nuclear Power Appendix A Construction QA Manual CLASSIFICATION CRITEPIA - - - - .

CLINTCN POWER SIATICN IdentAIAcacion and Classification of Safety-Pelated Structures  !.

g} '

P RCL7ECT NOS. 4536/4597 Systams and Components REV. 10 9-12-83

,<,y (d ttble 3.1 - classification of principal st ructures , Systems and Components PRINCIPAL STRUCT"RES, SAFETYd SEISMICJ OUALITYd ELECTRICAL # QA REQ'MTSY SYSTEMS & CCMPCNENTS (Class i,2, (Ca tego ry (Gro6p A,B, iCiass lE, (App. s or 3 or other) I or N/A) C,D or N/A)' Non-Class N/A) 1E or N/A

, ANSI N18.2 Reg. Gaide Reg. Guide Reg. Guide Reg. Guida e (ANS-21), 1.29 1.2 6, ASME- 1.32(IEEE- 1.28 (ANSI-REFERENCES : ANS-22, Section III 308) N45.2),heg.

, ANS-23 Guide 1.64 (ANSI-N45.2.11)

VII4 Leak Oetection System

1. Temperature element 2 I N/A 1E B

2. Temperature and differemaal temperature switches 2 I N/A 1E B

3. Differential ficw switch 2 I N/A lE B

4. Dif ferential pressure l' switch 2 I N/A lE B

5. Differential flow summer &

square foot converter 2 I N/A lE B

6. Pressure transmitter and dif ferential pressure 2 I B lE B transmitter IX Process Radiatien Monitors

1. Electrical modules, main steam line, containment building, fuel transfer I N/A lE B vent plenum, containment building exhaust main control room intake

2. Cable, with safety funcdcn

• I N/A lE B g--ss X RHR System

\ 1. Heat exchangers,shell side 2 I B N/A B

% 2. Heat exchangers, tube side 3 I C N/A B

3. Piping within outboard isolation valves 1 I A N/A L

4. Piping, beyond outboard isolation valves 2 I B N/A B

5. Pumps 2 I B N/A B

4. Pump motors

• I N/A lE B

7. Valves, isolation LPCI line 1 I A lE B

8. Valves isolation,other 2 I B IE B

9. Pump suction from suppres-sion pool, piping,valv?s, including isolation valves 2 I B 1E B

10. Valves, beyond isolation valves 2 I B 1E B

11. Mechanical modules 2 I B N/A B i 12. Electrical modules, with l safety function

• I N/A lE B t 13. Cable with safety function

• I N/A lE B

[ 14. Containment spray piping and nozzles 2 I B N/A B l 15. Suction strainers (note f) O the r I D N/A B XI Lcw-Pressure Core Serag

1. Piping, within outboard isolation valve 1 I A N/A B

2. Piping, beyond outboard isolation valve 2 I B N/A B

3. Pump 2 I B N/A B l 4. Pump motor

• I N/A lE B

5. Valves, isolation and witMn 1 A lE B containment I

6. valves,beyond outboard isolation valves 2 I B lE B

7. Pump suction from suppres- 2 1 B IE B sion pool. piping, valves, i including isolation valves l 8. Electrical modules with

• I N/A lE B

(

• safety function l *'s 9. Cable,with safety fax 2131

• I N/A 1E B I j 10. Suction strainer (note fl othe r I D N/A B l ~~ /

8 For definitions and instructions, see section 2.0 Note (f) - see page 24 Page 12 of 24 FOR ILLUSTRATION ONLY ,

A-4 03/05/85 I

r IP - Nuclear Powar Construction QA Manual Appendix A CIASSIFICATION CR!*"ERM Idanti!1 cation ana G assification ggg CI.UTCN PCWER STATION of Safety-Related Structures ..

PROJECT NCS. 4536/4597 Pistems and C =cenents REV. 9 3-11-83 r~u Table ? 1 - Classification of PrinciDal Structures. Systems and Ceuconents

(

\~M

)-

SAFETYM SEISMICI QUALI"'YI ELEt'rRICALd QA REQ'CSI PRD CIPAL STRL'CTURES, ( TaaTs"1,2, (category I (Group A,B, (Glase M, SYOIMS & CCMPCNENTS @pp.5 or 3 orother) or N/A) C,D or N/A) Non-Class N/A) 12 or N/A g ANSI N18.2 Reg. Guide ' Reg. Guide a Reg. Guide Reg. Guide 8 (ANS-21), 1.29 1.26, ASME- 1 32 ANS-22, 1.2d (ANSI-a alma

- -.4ES.*

ANS-23 Section III 30t!) (IEEE-N45.2), 3eg.

Guide 1.64 (ANSI-N45.2.11)

XII Hirh-Pressure Core 3rrsy

1. Piping, within outboard isolation valve 1 I A

2. Pipirut, retum test line to N/A B RCIC storage tank beyond second isolation valve Other

'!. Piping beyond outboard N/A D N/A N/A isolation valve, other 2 I B

4. Pu=p 2 N/A B I B N/A

5. Pump motor

• B

6. Valves, outboard isolation I N/A lE B {

and within containment 1 I A

7. Valves, beyond isolation 1E B valves, motor operated 2

3. Valves, other 2 I B lE B

9. Pump suction from suppres-I B IE B sien pool, piping, valves, including isolation valver 2

10. Pump suction from .

I B lE B acIC storage tank, piping, valves 2 Ll. Electrical modules, with I B lE B g safety function

• I N/A

[

( )) L2. Electrical auxiliary equip- 1E B

# ment

• L3. Cable, with safety function

• I N/A lE B I N/A lE B

14. System XIII4.C!C suction strainer (note f) Other I D N/A B

1. Piping, within outboard isolation valves and up to the main steam 1 1 A

2. RCIC steam piping, beyond N/A B outboard isolation valve 2 I B N/A B

3. RCIC turbine exhaust to suppression pool 2 I B f+. RCIC pump suction from N/A B suppression pool, piping, valves, including isolation valves 2 I

5. RCIC pump discharge *,o con- B 13 B densate storage tank within second isolation valve, pip-ing, valves, including isolation valve 2 I

5. RCIC pump discharge to B lE B cendensate storage tank beWnd second isolation valve, piping, valves Other N/A D Non-lE N/A s

3 - For Defieltiens and Instructions, see Section 2.0 Note (f) - see page 24 r--

[ Page 13 of 24 v l FOR ILLUSTRATION ONLY A-5 03/05/85

IP - Nuclear Power Construction QA Manual App ndix A c' ASS!T! CAT!Cai C*CMRIA CL D TON PCVER STATICN Ident:11cata;n and ;1assification I PROJECT NOS. 4536/497 of Safety-Related Structures, ..

System and C:=penents RE7. 10 9-12-83 7%

/ \ Table 2.1 - Classification of Principal Structures. Systems and Camponents I  !

\ /

SAFETYd SEISMICI CUALITTI ELECTRICALI OA RE;"8'S$

RIMCIPAL C R"CTURES, (L'lais"1,2, (Gategory I (Group A,B, (class a , Mpp.5 or SYE D43 t CCXPONDITS 3 or Other) or N/A) C,3 or N/A) Non-Class N/A) 1E or N/A g ANSI N18.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide n (ANS-21), 1.26,ASME-1.29 1. (IEEE- 1.2d ANSI-neu : CES,. ANS-22, Section III 3 N45 2 , Reg a

ANS-23 Guide 1.64 (ANSI-N45.2.ll)

! i

.3.A-h'

=p=3 2 I B "/A B Cotor

• I N/A 13 3

9. /alves, isolation and

.tithin 1 I A

10. Valves, other lE B 2 I 3 lE B

11. Turbine 2 I N/A N/A B

12. .lectrical modules, with safety f.:nction

• N/A I 12 B

13. ;:able, with safety function

• I N/A 8

14. Suetien strainer (note f) Othe r I D p;A W 3 XIV Nel Service Ieuir=ent

1. Fuel preparation machine -3 I N/A N/A B

2. General purpose grapple Other N/A (h) N/A N/A N/A XV leactor vessel Service Ecuir=ent

1. Steamline plugs Other N/A N/A N/A .yjA

2. Oryer and separator strong- Other N/A back and RPV. head strongback N/A N/A B

[

t d XVI In-Vessel Service Tauir=*nt '

Y./ 1. Control rod grapple other N/A (h) g N/A yyg

XVII Refue* i .e Ecuiree*.t

1. Refueling equipment plat-form assembly 2 I N/A Non-lE B

2. Refueling be d ows other N/A N/A N/A N/A

3. Bellows, blind flange and spool pieces that form a part of containment boundary 2 I N/A A B

4. Puel transfer tube other N/A N/A A N/A

5. Isolation valves (fuel transfer tube) Other N/A D N/A N/A

6. Containment penetration sleeve assembly (fuel transfer tube) 2 I B N/A B (VIII Storage Equipment

1. ruel Storage Racks 2 I N/A N/A B

2. Defective Fuel Storage Container 3 I N/A N/A B

3. In-Vessel Rack ( "Wporary) 2 I N/A N/A B XI%Radweste 3vste=

1. Tanks. Atmospheric Other N/A D N/A B(6)

2. Heat Exenangers other N/A D N/A B

3. Piping and valves forming part of containment boundary 2 I B lE B

4. Piping, other Other N/A D N/A 3

5. Pu=ps Other N/A D N/A

[h 6. Valves. flow control and 3

?

\j) filter system Other N/A D Non- lE B i ~

0 - For Cefinitions and Instructions, see Section 2.0 Notes (6). (f), and (h), see page 24 Page 14 of 24 FOR ILLUSTRATIONS ONLY A-6 03/05/85 I

IP - Nuclear Power Construction OA Manual Accendix A CI.ASSIFICATION CWITERIA Id.ncification and Chw81fication gg CI.INTON POWER STATION of fafsty-R31sted Structures, PROJECT NOS. 4536/4597 Systems and Compenents l REV. 9 3-11-83 Table 3.1 - Classification of Princieal Structures, Systems and Components

_ (~ p.

l "

\ SAFETY 8 SEISMIC 8 QUAI,ITY8 hECTRICALS CA REQ'MTS.8

• PRINCIPAL STRUCTURES, (Class 1,2, (Category I (Group A,B,HClass'TE7 (App. a or SYSTEMS & COMPONENTS 3 or Other) or N/A) C,D or N/A) Don-Class N/A) jlEorN/A ANSI N18.2 Reg. Guide Reg. Guide geo. Guide l Reg. Guide w (ANS-21), 1.29 1.26, ASMEyl.32 (IEEF=ll.28 (ANSI-3

REFERENCES:

ANS-22, Se% ion II:303) 'N45.2), Reg.

m l ANS-23 Guide 1.64 (ANSI-N45.2.11)

7. Valves, other other N/A D Non=1E B

8. Mechanical modules Other N/A D N/A B

9. Pump Motors Other N/A N/A NonalE N/A XXl Peactor water Cleanuo System l1. Vessels: f ilte r/ deminer- Other N/A C N/A N/A alizer

2. Heat Exchangers Other N/A C N/A N/A

3. Piping within drywell and drywell to containment penetration guardpipe up 1 I 'A N/A B to outboard containment isolation valve

4. Piping from outboard con-tainment isolation valve to pumps, back to contain-ment. Excluding pene-tration. All pipir.g within contairment. Blowdown piping downstream of out-board containment isolation valve up to shut-off valves, Other I C N/A B

5. Pumps Other N/A C N/A N/A

6. Valves, drywell isolation valves and within drywell 1 I A 1E B

7. Valves, beyond outboard other N/A D Non-!E N/A

/n contain=ent isolation f.g

/, jb) 8.

valves Mechanical modules Other N/A C N/A N/A

%./ 9. Piping, return to reactor pressure vessel from in-board containment isolation valve up to juncticn with feedwater 2 I B N/A B LO. Piping, between i?.bcard and outboard contain.nent isolation valves 2 I B N/A B L1. Valves, contairment iso. 2 I B 1E B

12. Piping, downstream of blow-down shut-off valves to main condenser and radwaste Other N/A D N/A N/A L3. Filter /Demineralizer pre-coat subsystem Other N/A D N/A N/A L4. Sample station Other N/A D N/A N/A L5. Nonregenerative heat ex- Other N/A D N/A N/A changer shell and component cooling water piping L6. Pump motors

• N/A N/A Non-1E N/A XXI Fuel Pool coolinq and Cleanue System

1. Vessels, filter /demineral-isers Other N/A O N/A N/A

2. Vessels, other 3,0ther I.N/A C N/A B,N/A

. 3. Heat exchangers 3 I C N/A B

{ 4. Piping 3,other I.N/A C,D N/A B,N/A

5. Pumps 3 I C N/A B

6. Valves and piping, contain-ment isolation 2 I B 1E B

7. Valves and piping filter domineralizers Other N/A D Non-1E N/A

8. Makeup s/ stem, shutdown service water system 3 I C N/A B

9. Makeup to FPCC frcm conden-sate storage tanks Other N/A D No n-L E N/A LO. RHR Connection 3 I C N/A B L1. Fuel pool cooling pump other I N/A 1E 8 motors O '

L2. Cable with safety function

• I N/A 1E B s 13. Electrical modules with j i d safety function

• I N/A 1E B

'm /

8-For definitions and Instructions, see section 2.0 Page 15 of 24 FOR ILLUSTRATION ONLY

, A-7 03/05/85 y , - - . - . - - . , - . _ - - , - , . . - - < , - - ,n

, ,.y - _, _ - , , . . _ . _

.+ - _ . - - ,

IP - Nuclear Power Construction QA Manual Appendix A C!ASSIFICATION CRITERIA Identification and Classification of Safety-Related Structures, gggg CLINTON PCWER STATION y PROJECT NOS. 4536/4597 Systems and Components REV. 10 9-12-83 p

/ Table 3.1 - Classification of Principal Structures, Systerns and ComMnents SAFETY 8 SEISMIC 8 OUALITY8 ELEC*RICAL8 CA REQ'MTS.a PRINCIPAL STRUCTURES, dClass 1,2, (C.stegory I (Group A,8 (Claas 1E, (App. B or w SYSTEMS & CCMPONENTS l3 or Other) or N/7.) C,D or N/A)Non-Class N/A) j l 1E or N/A ANSI N18.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide TANS-21), 1.29 1.26 ASMB- 1.32 (IEEE- 1.28 (ANSI-

REFERENCES:

NS-22, Section II1308) N45.2), Reg.

(NS-23 Guide 1 64 (ANSI-p45.2.11)

XXIIIcontrol Room Panels f

j 1. Electrical modules, with

• I N/A lE B 6 saf ety function I 2. Cable, with safety

• I N/A 1E B t f unc tion KXIII Local Pay 1 s and Racks

1. Electrical modules, with

• I N/A LE B safety function Cable, with safety *

'2. I N/A 1E B function XXIV Off-Cas System

1. Tanks Other N/A D N4A B(6) 2, Heat exchangers Other N/A D N/A B

3. Piping O ther N/A D N/A B

4. Pumps Other N/A D N/A B

5. Valves, flow control Other N/A D No n-1E B

6. Valves, other Other N/A D No n-1E B

7. Voided

8. Pressure vessels Other N/A D N/A

[n)

B

9. Pump motors Other N/A N/A Non-lE N/A XXV shutdown Service Water Systems for Shutdown Ecuirenent Cooling

1. Piping 3 I C N/A B

2. Pumps 3 I C N/A B

3. Pump motors

• I N/A 1E B

4. Valves, isolation 2 I B lE B

5. valves, other 3 I C IE B

6. Electrical modules with

• I N/A lE B safety function

7. Cable, with safety function

• I N/A 1E B XXVI Plant Service Water Systeras

. for Other Purposes

1. Piping and valves, other Other N/A D Non-lE N/A

2. Pumps Other N/A D N/A N/A

3. Mo tors Other N/A N/A Non-lE N/A

(XVII Instrument. breathing and Ser-l vice Air systems

1. Vessels, accumulators l supporting S-R systems 3 I C N/A B

! 2. Piping & Valves in lines bet.

[ aa:umilatcrs & S-R Systers J I C lE B

! 3. Piping & Valves forming part of containmentbotridary 2 I B 1E B

4. Control Room Emergency Breathing Air Other  ! C 1E B

5. Remaining Air Systems N-S-R Cther N/A D Non-lE N/A OtVII2 Diesel Generator Systems

l. Fuel day tanks 3 I C N/A B

2. Diesel fuel storage tanks 3 I C N/A B i 3. Piping and valves, fuel 3 I C 1E B oil system

4. Pumps, fuel cil transfer 3 I C N/A B

5. Pump motors, fuel oil

• I N/A LE B transf er system 0-ror definitions and instructions, see section 2.0 Note (6) - see page 24 Page 16 of 24 l

FOR ILLUSTRATION ONLY l A-8 03/05/85 t

IP - Nuclear Pownr Construction OA Manual CIASSIFICATICN CRITERIA Accendix A CLINTON POWER STATION Id..ntifiestion and cl.gaification PROJECT NCS. 4536/4597 of Sttsty-Relatsd Structuras ggg Systems and Components g 7-03-81 REV. 8 Table 3.1 - Classification of Principal Structures. Systems and Connonents

[q' .[

k, '{~

PRINCIPAL STRUCTURES, SAFETY # SEISMIC # QUALITYJ EI.ECTRICALW CA REQ'MTSY SYSTEMS & COMPONENTS (CIIss"T,2, (Category (Group A,B, (class 1E, (App. B or 3 or Other) I or N/A) C.D or N/A). Non-Class N/4) lE or N/A

, ANSI N18.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide e 1.29 j

REFERENCES:

(ANS-21),

ANS-22, ANS-23 1.26,ASME-Section III 1.32(IEEE- 1.28 (ANSI-308) N45.2), Reg.

Guide 1.64 (ANSI-N45.2.11)

Diesel Generstor Systems (contd)

6. Starting Air System

a. Piping, valves & tanks 3 I C 1E B

b. Piping 6 valves upstream of check valve between Other I D Non-IE N/A compressor and air receiver

7. Diesel generators 3 I N/A 1E B

8. Diesel generator exhaust 2 I B N/A B to building boundaqr

9. D.G. exhaust outside of Othe r N/A N/A N/A N/A building boundary

10. voided *

11. Electrical modules, with

• I N/A LE B safety function

12. Cable.with safety function

• I N/A lE B

13. Diesel eagine cooling water system 3 I C IE B

14. Diesel engine lubrication system 3 I C 1E B

15. Ccatbustion air system 3 I C N/A B

16. Air dryers & associated piping, controls & cables Other N/A D N/A N/A XXIX Standby Cas Treatment Sy g

1. Filter units 2 I N/A N/A B ef 2. Air piping 2 I N/A N/A B

[ )O 3. Cable with safety function

4. Fans / Dampers I N/A lE B (M" 5. Electric heaters, instru-2 I N/A lE B mentation & control with 2 I N/A 1E B a safety function XXX Power Conversion System

1. Main steam piping from 2 I B N/A B second isolation valve to

& including first shutoff valve

2. Main steam branch piping 2 I B N/A B between the second isola-tion valve and the first shutoff valve, from branch point at main steam piping to 6 including the first valve in the branch line

3. Main steam piping between other N/A D N/A N/AI2) the shutoff valve & the turbine main stop valve

4. Turbine bypass piping Other N/A D N/A N/A

5. Main steam branch piping Other N/A D N/A N/A between the first shutof f valve downstream of the second isolation valve &

the turbine main stop valve

6. Turbine stop valves, turbine Other N/A D Non-1E N/A(3) control valves & turbine bypass valves

7. Main steam leads from Other N/A D N/A N/A turbine control valves to turbine casing

8. Feedwater & condensate systent Cther N/A D Non-lE N/A beyond third isolatica valw

9. Turbine generator other N/A N/A NonalE N/A

10. Valves , ins trumenta tion begrid Othe r N/A D Non-lE N/A outermost isolation valve a

8 For definitions and instructions, see section 2.0 Notes (2) ard (3), see Page 24 Page 17 cf 24 FOR ILLUSTRATION ONLY A-9 03/05/85 l

IP - Nuclear Construction QA Manual Appendix A CLAS'IF? CATION C3ITERIA

Identif acation and Classification i.l MMgM I -

CI.INTCN PCWER STATION of a fety-Related Structures, PROJECT NCS. 4536/4597  !

Systes and cemeonents REV.10 }

9-12-83 m i i Table 3.1 - Classification of Princiral Structures, Systems and Commnents v 3 i i SAFr*YS SEISMIC 8 tCUALITYS ELECTRICAL 8'CA REC'MTS.8 '

PRINICIPAL STRUC"URES, (Class 1,2, (Category I(Group A,B LClass lE,'(App. B or SYSTEMS & COMPONENTS 3 or Other)l or N/A) C,D or N/A) Non-Class N/A)

I i 1E or N/A w i .

3 ANSI N18.2

@  !(ANS-21), Reg.

1.29 Guide1.26, Reg.ASME-Guide fReg.

!1.32 Guide (IEEE- l Reg. Guide (ANSI-l 1.28 g z ANS-22, Section III 308) N45.2), Reg.:

REFERENCES:

ANS-23 g Guide 1.64 l l ((ANSI-

! ,N45.2.11)

I t  :

XXX;. Power Conversion System (cont.] i i 1

' e 11. Condenser , other N/A >

N/A N/A N/A I 12. Air ejection equipment I Other N/A D j Mon-lE N/A 13.

Feedwater treatment systemi Other N/A i N/A

14. Turbine bypass system N/A I D j Ncn-1E other D g Non-1E N/A beyond turbine bypass valve 15; Turbine gland sealing Other N/A D Non-1E N/A system components il16. Heater drain piping Other N/A D N/A N/A

17. Heater drain valves O ther N/A D Non-1E N/A XXXI ECCS Eculpment Area Cooling l L. Fans, & ductwork with safety function 3 I N/A 1E '

B

2. Heat exchanger pressure rea 3 I C N/A B

, taining components & valves i Ins trumentation and con- 3 I N/A le B

) {3. trol with safety function

4. Electrical modules & cable

• I N/A 1E B f I with a safety function II Condensate Storage and Transfe

, 1. RCIC condensate storage Other N/A D N/A N/A tanks

2. Condensate storage tanks Other N/A D. N/A N/A '

I 3. Piping and valves (d

s j

4. Piping and valves con-tainment penetrations Other 2

N/A I

D B

Non-1E 1E N/A B ,

+

I t

XXXIII Auxiliary A-C Power System l

1. All equipnent necessary

• I N/A 1E B for operation of Safety a

Class 2 Mechanical Systems .

2. All equipment necessary

• I N/A 1E B for operation of Safety

. Class 3 Mechanical Systems ,

i

3. Other Auxiliary A-C Power Other N/A N/A Non-1E N/A Equipnent i

XXXIV' Miscellaneous components l

, 1. Containment polar crane 3 I N/A Non-1E B 4

2. Fuel Building Crane 3 I N/A Non-1E B 3.

Turbine Building Crane Other N/A N/A Non-1E N/A i

XXXV Civil Structures ,

l 1. Contairrent N/A I N/A N/A B

2. 'CGCB structure N/A I I4) N/A N/A B

3. Auxiliary building N/A I N/A N/A B e

4. Fuel building N/A I N/A N/A B l S. Control building N/A I N/A N/A B -

6. Diesel generator and HVAC N/A I N/A N/A B .

building  ?

7. Radwaste substruccure N/A I N/A N/A B

8. Circulating water screen N/A I N/A N/A B house

, 9. Turbine building N/A N/A N/A N/A N/A

10. off-gas building N/A N/A N/A N/A N/A

11. Service building N/A N/A N/A N/A N/A ,

i 12. Ultimate heat sink N/A I N/A N/A B i 13. Radwaste building above N/A N/A N/A N/A N/A grade

14. RPV Pedestal gjg I N/A N/A B

15. Safety-related masonry i walls N/A I N/A N/A B g 16. Fuel pools a pool liners N/A I N/A N/A B U 8-For definitions and instructions, see section 2.0

Note (4) - see pace 24 Page 19 of 24 3 FOR ILLUSTRATION ONLY a A-10 03/05/85 l

IP - Nuclear Pownr Construction OA Manual Anoendix A C'JSS7FICATICN Cn1TERIA CI.INTON POWER STATION ldentific.ti< n and C1&alficition PROJECT NOS. 4536/4597 of S;fity-Rahtid Structur!,a Systems and Ccamponents l $NEMN I I i REV. 10 9-12-83 Table 3.1 - Classification of Principal Structures, Systems and comoonents

]

}. PRINCIPAL STRUCTURES, SAFE M SEISMICd QUALITYd ELECTRICALd CA REQ'MTSY

~/ SYSTEMS & COMPONENTS (Class 1,2, (Ca tegory (Group A,B, (Class 1E, (App. B or 3 or Other) I or N/A) C,D or N/A) Non-Class N/A) 1E or N/A ANSI N18.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide

$ (ANS-21), 1.29 1.26,ASME- 1.32(ICEC- 1.28 (ANSI-4

REFERENCES:

j ANS-22, ANS-23 Section III 308) N45.2), keg.

Guide 1.64 (ANSI-N45.2.11) 20ccrI Other Structures

1. Those supporting or protec-ting saf ety related equip.  !!/A I N/A N/A B

2. Cable trays & tray hangers, conduit & cendait hangers in Seismic Category I areas. Other I N/A N/A B XXXVII Miscellaneous

1. Component cooling water sys. 2/3/Other I,N/A B/C/D IE,Non-IE B.N/A

a. Valves & piping contain-ment isolation 2 I B IE B

b. Valves & piping for supplying shutdown ser-vice water to tne fuel pool heat exchangers 3 I C lE B

c. Valves & piping for supplying service water to the RR pumps seals Cther I C 1E B

d. Piping & valves Other N/A

e. Heat exchangers D N/A N/A Other N/A D N/A N/A

f. Storage tank Other N/A

g. Instrumectation & contzcis D N/A N/A with safety function 2/3 I N/A 1E B

2. Turbine building, cicsed cooling water system Other N/A D Non-1E N/A

3. Shutdown service water equipment area cooling GO a. Fans, ductwork & valves with safety function

b. Heat exchanger pressure-retaining components &

3 I N/A lE B valves 3 I C N/A B

c. Instrumentation & control with safety function 3 I N/A lE B

d. Electrical modules & caoles with safety function

• I N/A lE B

4. Switchgear heat removal

a. Fans, ductwork, dampers &

valves with safety functicn 3 I N/A lE B

b. Heat exchanger pressure-retaining componenus &

valves 3 I C N/A B

c. Instrumentation & centrol with safety function 3 I N/A lE B

d. Electrical modules & cables with safety function

• I N/A IE B

e. Refrigeration piping with safety function Othe r I N/A N/A B

5. Control Room HVAC

a. Fans, fan motors, dampers, ~

ductwork, valves. water chiller, chilled water pumps with safety functicn 3 I N/A 1E B

b. Heat exchanger pressure-retaining components and valves 3 I C N/A B

c. Electric heaters instru-mental & controls with safety function 3 I h/A lE B

d. Electrical modules &

cables with safety functico

• I N/A lE B

e. Filter units 3 I N/A lE B

~

l  ;-}

m 8 For definitions and instructicas, see section 2.0 Page 19 of 24 FOR ILLUSTRATION ONLY A-ll 03/05/85 l

IP - Nuclear Construction QA Manual Appendix A '

CIASSIFICAT!oM CRITERIA - ~ - . . - - CLINTON POWElt STATION Ident&tacation and Gassification g{g' PHOJECT NOS. ( g it,/ 4 *,9 7 or Satuty-pelated structurus

' ~ ~ * "

Systems and C:mponents REv. 10 9-12-83

/N Table 3.1 - Classification of Principal Structures, systems and comnonents PRINCIPAI. STRUCTURES, SAFETY # SEISMIC # MA!,TTyJ CTECTRICALE QA REQ'M?d l SYSTEMS & COMPONENTS (Class 1,2, (Ca tego ry 3 or other; I or N/A)

(Gr oup A. is , T lass 1C T5p. D or (C,D ur N/A) - Non-Clans N/A) 1 IF. or N/A

+

, ANSI N18.2 Reg. Cutde Rec.Cuide Reg. Cuide Rep. Cuide

• w (ANS-21), 1.29 1.26,ASML- 1.32(if1L- 1.28 (ANSI-4

REFERENCES:

ANS-22, Section II' 308) N4 5. 2) , Eey.

3 ANS-23 1 Cuade 1.64 (ANSI-iN45.2.11)

6. Diesel Generator HVAC

a. Fan and ductwork with safety function 3 I N/A LE B

b. Instrumentation & cxantrol with safety function 3 I N/A 1E B

c. Electrical modules & cables with safety function

• I N/A lE B

7. Combustible gas control system cooling

a. Fan, dirtwork w/mafety fmc. 3 I N/A 1E B

b. Heat exchanger pressure-retainingccryorants & valves. 3 I C N/A B

c. Instrumentation & control, with safety function l 3 I N/A lE B

d. Electrical modules & cables with safety function

• I N/A lE B mor/I Miscellaneous reone.

8. Fire protection system Other N/A N/A Non-lE B

9. Standby Cas Treatment Systen Equipment Area Cooling O, a. Fan & ductwork with '

( ) safety function 3 I N/A lE B i

-gj b. Heat exchanger pressure ~

retaining components and valves 3 I C N/A B

c. Instrumentation & con-trol with safety functicrt 3 I N/A lE B

d. Electrical modules and cables with a safety function

• I N/A lE B

10. MSIV Leakage Room Cooling

a. Fan & ductwork with safety function 3 I N/A lE B .

b. Heat exchanger pressure retaining components

, and valves 3 I C N/A B

[ c. Instrumentation & contzel with safety function 3 I N/A lE B

d. Electrical modules and cables with a safety function

• I N/A lE B

11. Meteorological cata l

Ccilection Equipment Other N/A N/A fon-1E N/A

12. Pcataccident Sample System

a. Sample analysis panel O ther N/A D Non-1E B

b. Sample monitor panel other N/A N/A Non-1E B

-c. Closed loop cooling i system N/A N/A D Non-1E B

d. Containment isolation valves 2 I B lE B

, e. Sample block and back I flush valves Other N/A B IE B l f. Dryvell floor and equip-ment drain sump sample pump Cther N/A D Non-lE B

g. Containment floor and I

equipment drain sump sample pump Othe r N/A D Non-LE B

'u -

8 For definitions and instructions, see section 2.0

/

FOR ILLUSTRAT10N UNLX A-12 03/05/85

- - - - m- y. ,=e - -

• c%- -

-wc ?w w- - .i m*i a e AP P w -

IP - Nuclear Powar Construction QA Manual Appendix A CIASSIFIC\ TION CRITERIA - CLINTON PmvEk STATION Id ncific:. tion and Cl&dificition [ PROJECT he 4 's h/ 4 59 7 of Saf ety-Related Structures Systems and Components #{ #

REV. 11 4-27 84 Table 3.1 - Classification of Principal Structures, Systems and comenents

.m l

PRINCIPAL STRUCTtJRES, SAFE M SEISMICd OUALITYJ CIACTHICAld QA RrQ'MTSY SYSTEMS e CCMPONENTS (Class 1,2, (Ca tego ry (G7s sup A,H, (Class IE, IA5p. D vr 3 or Othe r) I or N/A) C.H ot N/A) Non-CI.aMn N/A)

LE or N/A

, ANSI N18.2 Reg. Cuido Re.g . Cua de Ifey , Guadu Heq. Cuado e (ANS-21), 1.29 1.26,ASME- 1. 3 2 ( 16 M.- !.28 (ANSI-

REFERENCES:

ANS-22, Section III JOU) N45.2),kuq.

ANS-23 Guade 1.64 (ANSI-N45.2.11)

13. Postaccident Monitoring Systems

a. Piping, within contain-ment pressure bount'ary and/or with post ' JCA function 2 I N/A N/A B

b. Valves, within contain-sent pressure boundary and/or with post LOCA function 2 I N/A LE B

c. Electrical and instru-mentation modules with post LOCA function 2 I N/A lE B

d. Cables with safety function 2 I N/A lE B

14. Equipment for Emergency Response FacilitieL N/A N/A N/A Non-lE B

15. Fuel Building HVAC system dampers and ductwork with safety function 3 I N/A - lE B

EXVII) Combustible Gas control Lystem

1. DAragcri Itxxrbiner systan

2. Coc+aiceenr /drywell parge sys

a. Drywell Purge Filter Units Cther I N/A Non-lE N/A

\ t. Ductwo rk Other I N/A Non-lE N/A

1. c. Post-LOCA Purge (Backup 2/Other I B,N/A lE/Non-lE B to Hydrogen Recombiners) 11 Valves, Piping, Ductwork

3. Containment /dryvell mixing 2 I B lE B system

4. Containment /drywell moni-toring system 2 I B lE B

5. Electrical modules with safety function

• I N/A 1E B

6. Vacuum relief system 2 I B lE B UXIX Suppression Pool Make-up System (SM)

1. SM piping 2 I B N/A B

'. SP valves with safety function 2 I B IE B

3. Electrical modules with safety function

• I N/A lE B

4. Other valves Other I B Non-lE B XL Auxiliary DC Power System

1. Divisional batteries, charge and distribution panels

• I N/A lE B

2. Non-divisicnal batteries, chargers and distribution panels Other N/A N/A Non-lE N/A XLI Suppression Pool Clean-up System tsF)

1. Piping & valves forming part of containment bounda g 2 I B 1r B 1 Other ntnino a valvas Cther  !!/A D Non-lL N/A i , -

lY 8 For definitions and ins tructions, see section 2.0 Page 21 of 24 FOR ILLUSTRATION ONLY A-13 03/05/85

IP - Nuclear Power Construction QA Manual Appendix A CIASSIFICATIoN CRITERIA CLINTON P(MER STATIUN Id.nciltea LAon and Classification of safety-terlated Structures jf 4 ,

'Q r$ROJECT NOS- F,1f,/4 59 7 Systems and Components REV. 11 A-27-84 Table 3.1 - Classification of Principal S t ructures , systems and Comnonents 9

/ FRANCIPAL STRUCTURES, SAFE M SEISMICd OCA1. f TYd ClfCT R l t'Afd QA REQ'W!9.I SYSTEMS 6 COMPONENTS (Class 1,2, (Ca tego ry J or Other) I or N/A) 0;iI,up A.H. TTaMC GGtO ~ui"'

li :C,la e.

N/A){ Non -(* l.n s u N/A)

) 10 or N/A. -

, ANSI NIS.2 Reg. Guide Req.Cutde Huy. Calde He.g. Cuade v (ANS-21), 1.29 L.26,NJME- 1. 3 2 ( 11 1.E- 1.2H (ANS!*

REFERENCES ANS-22, Section N4S.2),Heq.

f.

t r

ANS-23 II} JO8) I t 1.b4 l  ! (iulde ANS!=

I lh45.2.lli XLII Demineralize r Make-to System

1. Piping and valves O the r N/A D Non-lE

2. Tanks N/A Other N/A D N/A N/A

3. Filters Othe r N/A 3 N/A N/A

4. Pumps and motors Other N/A D Non-LE N/A

5. Pretreated filtration components Other N/A D Non-lE

6. Demineralizing train N/A components O the r N/A D Non-lE N/A XLIII Main Steamline Isolation Valve Leaitace Control 57 stem

1. Piping and valves up to the first isolation valve of the inboard subsystem 1 I A lE B

2. Piping and valves, o ther 2 I S lE B

3. Blowers / motors

• I N/A lE B

4. Heaters Other I N/A 1E B

5. Electric modules with safety function

• I N/A lE B

6. Cables with safety function

• I N/A lE B s

XLIV Containment Isolation

1. Piping between the inside 2 I B IF B

' 9 and outside containment isolation valves including the isolation valves for systems with no safety function which penetrate the containment

2. Containment penetration 2 I B lE B assemblies

3. Dryvell Guardpipe Bellows Other I D N/A B 11 (1)

Notes (2) All inspection records shall be maintained for the life of the plant. These records shall include data pertaining to qualification of inspection personnel, examination procedures, and examination results.

(3) A program of quality assurance requirements unique to fire protection has been developed by Sargent 6 Lundy. This program is discussed in detail in Project Instruction PI-CP-'015.

l l

l l

l d I 1,/

4 For definitions and instructions, see section 2.0 Page 22 of 24 Note (i) - see Page 24 FOR ILLUSTRATION ONLY

( A-14 03/05/85

IP - Nuclear Power Appendix B Construction QA Manual

- v/ '

APPENDIX B Revisions to the IP Nuclear Power Construction Quality Assurance Manual Revisions to this Manual will be issued per Quality Assurance Procedure QAP-106.01. Control of issuance and maintenance of the Manual is the responsibility of the IP Manager-Quality Assurance. Persons who are assigned controlled copies of the Manual are responsible for maintaining them in accordance with the following:

1. For each revision issued, the manual holders will receive the revised material, a page roster, and an accompanying transmittal which will contain a detachable receipt to be signed and returned to the Quality Assurance Department.

This will verify receipt of revisions.

l

(~'s 2. When revised material is provided, the obsolete material in s_,/ each controlled copy shall be removed and destroyed by the assignee.

3. Requests for copies of the Quality Assurance Manual or any questions associated therewith shall be directed in writing to the IP Manager-Quality Assurance.

,.e"~

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,/

,/

/

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B-1 03/05/85

IP - Nuclear Power Appendix C Construction QA Manual 7

U APPENDIX C SUPPLEMENTAL APPLICATION IP NUCLEAR POWER CONSTRUCTION QUALITY ASSURANCE PROGRAM This appendix details in matrix form the chapters of this manual which are applicable in full or in part to:

Fire Protection Radwaste/ Augmented D Systems 10CFR50 Appendix B requires that a quality assurance program be established in writing and executed for activities affecting the safety related function of designated structures, systems and components to an extent consistent with their importance to safety. Table 3.2-1 in the Clinton Power Station FSAR identifies specifically those structures, systems, and components that are important to safety.

Fire Protection and Radwaste/ Augmented-D systems are specifically identified in Table 3.2-1 of the CPS FSAR and/or highlighted in "s several Regulatory Guides that define and clarify their impor-(Q tance to the plant.

Regulatory Guide 1.120, " Fire Protection Guidelines for Nuclear Power Plants," Revision 1 (November, 1977) states that "A quality assurance (QA) program is needed to identify and rectify errors in design, construction, and operation (of a fire protection system) and is an essential part of the defense in depth".

Regulatory Guide 1.143, Revision 0 (July, 1978) states... that,

... "to ensure that systems will perform their intended function a quality assurance program sufficient to ensure that all design, construction, and testing provisions are met should be estab-lished and documented."

The extent to which the IP Nuclear Power Construction Quality Assurance Program applies to each of the two areas varies as defined further under subsequent sections of this appendix. The attached matrix outlines which chapters of this manual apply to Fire Protection and Radwaste/ Augmented D systems.

~. .

l l

f g ._ _

- 1 C-1 03/05/85

IP - Nuclear Power Appendix C l Construction QA Manual ,

fD U MATRIX CHAPTERS OF THE IP NUCLEAR POWER CONSTRUCTION QUALITY ASSURANCE MANUAL APPLICABLE,TO FIRE PROTECTION AND RADWASTE/ AUGMENTED D CONSTRUCTION RADIOACTIVE QA MANUAL FIRE WASTE /

CHAPTER PROTECTION AUGMENTED D

1. YES YES

2. YES YES

3. YES YES

4. YES YES

5. YES YES

6. YES YES

7. YES YES

8. NO NO

9. NO YES

10. YES YES -

11. YES YES

12. NO NO

13. NO YES

14. YES YES O 15 . -

16.

YES YES YES YES

17. YES YES

18. YES YES NOTE: Structures, systems and components subject to the above requirement are described by FSAR Table 3.2.-l and further defined by engineering specifications, drawings, procedures, instructions, other documents, etc.

O C-2 03/05/85 l