ML20137R904
| ML20137R904 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/08/1985 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20137R888 | List: |
| References | |
| NUDOCS 8512060113 | |
| Download: ML20137R904 (100) | |
Text
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. Q-02784 October 8, 1985 IP Nuclear Power Construction Quality Assurance Manual, Revision 14 Summary Revision 14 of the IP Nuclear Power Construction Quality Assurance Manual (CQAM) reflects recent changes to the i Illinois Power Organization and responsibilities. Editorial changes are also made throughout the CQAM.
Evaluation The changes made to the QA program described in revision 14 of the CQAM do not involve a reduction in commitment previously submitted to the NRC. The CQAM should be submitted within 90 days in accordance with 10CFR50.55. cC l Submitted by D ra ' tidl /
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9tpervisor LQuality Techni' cal Support Approved by / #d / /It Manage [-QA i i l l I Ov
- 8512060113 851125 PDR ADOCK 05000461 A PDR
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c , (3 (" O I, 1 IP 'L CLEAR POWER ( CONSTRUCTION Q.A. Manuni Ravicion 14 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE Chapter 2 A.5 Clarify responsibility for distribution list for Construction QA 5 of 11 Manual Chapter 3 3 of 5 A.2 Clarified responsibilities Chapter 3 3 of 5 A.3 Organization title change Chapter 4 3 of 3 A.5 Organization title change Chapter 7
. 2 of 3 A.3 Org;anization title change Chapter 11 ,
1 of 3 I Further defined the purpose of chapter 11 Chapter 14 Deleted pre-operational testing. 1 of 2 I Pre-op testing is covered under the operations QA program Appendix B N/A Redefined responsibilities to comply with new organization (LCF) e 4
IP CLEAR POWER '/ CONSTRUCTION Q.A. Manual Ravicica 14 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE Chapter 1 Reassigned responsibilities for tracking 10CFR21 and 10CFR50.55(e) 10 of 17 A.15.2.1 items to Manager - Nuclear Station Engineering Chapter 1 10 or 17 A.15.2.2 Clarify responsibilities for timely and responsive corrective action Chapter 1 11 of 17 A.15.3.1 Clarify responsibilities for timely and responsove corrective action Chapter 1 12 of 17 A.15.3.2 Clarify receipt inspection and source surveillance responsibilities Chapter 1 12 of 17 A.15.4 Added Director - Operations Monitoring Program Chapter 1 12 of 17 A.15.6 Redefined Responsibilities Chapter 1 15 of 17 Fig 1-1 Comply with site organization Chapter 1 16 of 17 Fig 1-2 Comply with site organization Chapter 1 17 of 17 Fig 1-3 Comply with site organization Chapter 2 Deleted reference to preparations for commercial operations 1 of 11 I Added " construction" to define testing as construction testing
IP M CLEAR POWER CONSTRUCTION Q.A. Manual Revicicn 14 MATRIX OF REVISIONS PAGE PARA. REASON FOR CHANGE V N/A Incorporated the reference to chapter 17.1 of the FSAR Chapter 1 2 of 17 B.5 Clarify to read as all inclusive of QA functions Chapter 1 3 of 17 A.1 Comply with site organization - Deleted Senior Vice President Chapter 1 5 of 17 A.7.2 Clarified responsibilities Chapter 1 5 of 17 A.7.3 Organization change Chapter 1 A.8 Reassigned Configuration Management to Nuclear Program 5 of 17 Coordination. (Section A.6) Chapter 1 6 of 17 A.ll Redefined responsibilities to comply with new organization Deleted Director - Project Controls, Director - Nuclear Support Chapter 1 N/A and Director - Nuclear Purchasing. Responsibilities are under 6 of 17 Manager - Nuclear Planning and Support Chapter 1 A.14 Added Manager - Licensing and Safety 6 of 17 Chapter 1 Clarified responsibilities & authority to Stop Work during all 7 of 17 A.15 phases of the plant.
Date MPS Mo. 1 A May 24, 1984 Revision,1 l-Page 1 or 1 L U l ILLIMOIS POWER COMPANY NUCLEAR POLICY STATEMENT Quality Assurance l The Illinois Power Company (IP) Nuclear Power Construction, l Operational,-and American Society of Mechanical Engineers (ASME) l 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 Power I Station (CPS) are conducted in a safe and reliable manner in l compliance with the Code of Federal Regulations (10CFR50, l Aopendix 3): the ASME Boiler and Pressure Vessel Code (Section l I'II-Diviston 1): and other applicable regulations, codes, and l standards. Control and surveillance requirements specified in the Construction, Operationel 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 t1e quality assurance (OA) programs are adequately planned, implemented, and managed. The Manager-Ouality Assurance is responsible for developing,
- establishing, and maintaining the quality assurance program l 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. Tae Manager-Ouality Assurance has the organizational freedom and is responsible to identify problems, initiate corrective actions, verify implenen-tation and assure control of activities which affect quality.
When concerns related to quality matters are not satisfacto- ,W l rily resolved with immediate supervision, personnel have a*w s ern, direct access to the next higher level of management in the organization. If concerns are still not satisfactorily resolved, personnel have direct access to me for final'reso-pd l lution in accordance with applicable codes and standards. ==w Anyone that intimidates or interferes with any person per- #"n. ' forming Quality Assurance and Quality Control' functions shall be subject to disciplinary action. Intimidation may take many C% forms ranging from verbal abuse to physical harm. % Personnel subject to or who perceive intimidation or inter. atC[ ference have direct accenn to the Executive Vice President, ac~~$ who has the authority and responsibility to take appropriate g**** i disciplinary action. C$ p APPROV Q C&M xn Lk. I chairman and Preiftdent f/ ,"""g
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i Revision 11
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~a AUTIIORIZATION This document shall be used in activitics related to design and construction of the Clinton Pouer Station. It shall be maintained and updated as required by the Manager-Quality Assurance. Personnel assi;ned controlled copics of this manual shall be responsibic for t'acir maintenance and updato in accordance with the provisions of Appendix B.
l- e W W.G. Gerstner, Executive Vice President bl4lY7 Date e i< ruRM alg op y I w N-. o
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il Revision 8 L.
IP NUCLEAR POWER CONSTRUCTION QUALITY ASSURANCE MANUAL TABLE OF CONTEMTS Cha1ter Num)er 0 Introduction 1 Organi::ation 2 Quality Assurance Program 3 Design Control 4 Procurement Document Control 1 5 Instructions, Procedures, and Drawings l 6 Document Control 7 Control of Purchased Material, Equipment, and Services 8 Identification and Control of Materials, Parts, and Components 9 Control of Special Procesecs 10 Inspection O v 11 Test Control 12 Control of Measuring and Tuot 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 Appendix A Quality Assurance Program Scope Appendix B Revisions to the IP Nuclear Power Construction Quality Assurance Manual 1 Appendix C Sapplemental Application a de Revision 11 L L
IP - Nucicer Pcwar List of Effective Pages Conotruction QA Manun1. n IP Nuclear Power Coastruction Quality Assurance Manual Inde:: Revision 14 The following pages and their indicated revision number are included in the currently authorized IP Nuclear Power Construction Quality Assurance Manual. Pnne No. Rev, i 11 11 8 iii 11 iv 14 v 11 vi 6 1-1 17 12 2-1 11 12 3-1 5 14 l \'() 4-1 5-1 4-3 5-3 12 10 1 6-1 2 10 7-1 3 12 8-1 2 10 9-1 3 11 10-1 3 11 11-1 3 12 12-1 3 11 13 13-3 11 14-1 2 12 15-1 3 12 16-1 2 10 17-1 3 11 18 18-3 10 A A-14 11 ' 15 - 1 12 l C C-2 11 INF0MA?!0N Dirty o _ iv Revision 14
INTRODUCTION l i (O) The Illinois Power Ccmpany (IP), as principal owner of the Clinton Power 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 sapropriate CPS activities. The Nuclear Steam Supply System (SSSS) Vendor, the Architect Engineer (AE) and the Constructor are cach responsible to IP for implementation of complementary quality assurance programs applicable to the scope of their individual areas of work. Each of these organi::ations will maintain a quality assurance program in compliance with ap)11-cable requirementa. The IP Quality Assurance concept is t1at i cach party participating in CPS activities is responsible for its l program and the program implenentation to perform its designated , work. IP monitors and audits the implementation of such programs l to ensure total coverage and compliance. Thtu Manual represents chapter 17.1 of the FSAR and is the basic l governing IP document for the quality assurance of design, procurement, fabrication, and construction activities for cpl.
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l [v; l separate manual will cover the quality assurance of pre-operational testing, operation, maintenance, and
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'"""g post-construction modifications activities. The program de-scribed herein requires preplanned systems of carefully docunenkd ed checking, reviewing, qualifying, examining, insincting, fm) testing, auditing, or other verifying activities tant provide %r reliable evidence of required quality. The objective of thes a activities is to obtain a plant which is in compliance with .mi applicable regulatory, code, and technical standards require- . .n-i ments. {g The basic regulations applicable to the IP Nuclear Power Qual Assurance Program are Part 50 Appendix B of " Title 10 - Chaptert {f"****
- 1. Code of Federal Regulations, (10 CFR 50)", and the State o:
Illinois regulations, which stipulate adherence to the American g d Z 6 Society of Mechanical Engineers Boller and Pressure Vessel Cot e .g In addition, ANSI N45.2, 1977, " Quality Asnurance Requiremener for Nuclear Power Plants", together with various interpretatic nt O7.o and supplemental information in Nuclear Regulatory Commission Safety and Regulatory Guides, shall be applied as stated in t *) - FSAR. These are the principal codes, standards, and technicahe {Le b( l l l l bases for quality assurance requirements described herein, y" ', ) This Manual is organi::ed to follow the format of the "18 Crit o-rion" of 10 CFR 50 Appendi:: B. Each chapter is divided into p three main sectionn: G v Revision 11 .
i 4 , I l I Purpose 9 II III Requirements Diviolon of Responsibility l Section II of each chapter ic further broken into tuo parta - a ' discussion of (a) external interfaces, and (b) general require-monts to be satisfied by IP and its contractors as applicable to their scope of work. l f l O i
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4 vi Revision 6 I
IP - Nuclear Power Chapter 1 - ORGANIZATION Construction QA linnual .- I
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Approved /(([ d,s/// /"/ 6ed / 9hM janager-yA Datt I. PURPOSE: This chapter describes the organizationni_t,tructures, functional responsibilities, and levels of authority of ; organizationa related to the design, construction, procurement, inspection, and construction tenting of ' safety related activities at the Clinton Power Station.
- 11. REQUIREMENTS:
A. Interface , Illinois Power Company directs and is renponsible for u-the quality assurance activition in the design and construction of the Clinton Power Station. This responsibility in retained by IP oven when it la e necennary to obtain design, procurement, fabrication, construction, inspection, rnd related testing, 4e%# d consulting, and nasociated (A services from other m.m] organizations external to IP. Upott completion of
--p construction and turnover of t.tructures, systems, and
": L -' componenta by the constructor, IP will direet and Le
(""') responsible for performing the required checkout, initial start-up operation, pre-o and associated quality nanurance/perntl6 ant testing, control functions.
'" P IP will obenin annistance from other orgsnizations an 9' necousnry. Figure 1-1 depicta the organi:'.ntion of the C ,,.J Clinton Power Station project. ,
w , y ma The major contractorn involved with the design and 4 conntruction of the Clinton Power Station are
%... he Sargent & Lundy (S&L) - the Architect Engineer (AE):
*c.:. M General Electric (GE) - the Nuclear Steam System ,'
rr/~l . Supplier (NSSS): and Baldwin Ansociaten (LIA) ~ - the
" 1 Field Conntructor (Constructor). The organizational
('%f),' interface relationship between IP and the mnjor (,, , contractorn is reficcted in Figure 1-2. Ed '.1
.6, The relationuhipn shown for the major contrnetors (S&L, GE, and liA) are equally applicabic to other
- contractors. To accomplinh the program objectiven,
_ _ . _ _ . _ the IP Quality Annurance organization monitorn the QA organizntiona of the major contractora and Page 1 of 17 hvision 12
IP - Nuclear Power Chapter 1 Construction QA Manual 7 4 y consultants. This arrangement makes a wider range of skills available and decreases potential manpower limitations during periods of high activity.
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B. General The IP and contractors' organizations shall meet the following requirements: v! 1. The authority and responsibility of persons and organizations performing activities which affect y/ quality, including the quality assurance person-nel, shall be clearly established and delineated in writing. j
, 2. Quality assurance organizations shall have suffi-
/ .
cient freedom to identify quality problems, initiate, recommend, or provide solutions: to verify implementation of solutionsi and to
,5 control further processing, delivery, installa-
~ tien, or utilization of nonconforming materials or items until proper dispositioning has occurred.
[) 3. Any person who intimidates or interferes with any
- personnel performing quality assurance or quality control functions shall be subject to disciplin-ary action. Intimidation may take many forms ranging from verbal abuse to physical harm.
.- 4. Quality problems shall be reported to approariate A management levels who will act to resolve tie 9 problems.
k6 5. Those persons or organizations performing quality verification functions shall not have direct p responsibility for performing the same work, r:,
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Ill. DlVISION OF RESPONSIBILITY:
+ Each organization aarticipating in CPS activities is re-j sionsible for esta)lishing a quality assurance program and v' tle implementation necessary to perrorm designated work.
Each contractor's quality organization uhall be esta-
# blinhed in a manner consistent with its particular role in
' ' the overall CPS activities as stipulated by IP. Each contractor's quality assurance program shall be reviewed and approved by IP to ensure consistency with the IP A huclear Power Quality Assurance Program. The V organizations may have significant differences as can be acen by comparison of the organitation charts of IP, j , Page 2 of 17 Revision 12 l
4 . IP ' Nuclear. Power' . 1 Chapter 1 Construction QA Manual vm_
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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' Associates. This, however, does not imply delegation of-ultimategresponsibility for overall quality assurance which remains with IP.
A.'
. Illinois Power
, ,$ Figure 1-1 depicts the line and staff functions of
- the IP Clinton Power Station organizational structure. ,
, 1. Chairman and President
't 5 3The Chairman and President of IP has the overall
, responsibility for the engineering, design, wprocurement, construction modification, testing, operation, and quality assurance at CPS.
Execution of these responsibilities is delegated j ]) .to'two Executive Vice Presidents. l
- 2. -Executive Vice President
-An Executive Vice-President is responsible for the overall effectiveness of the quality
' assurance program and for establishing quality assuranc'e policies, goals,.and objectives. The~
responsibilities to establish and r.aintain the IP
-Nuclear Power Quality Assurance Prrgram as well as testing, startup, operations, nuclear support,
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nuclear purchasing, and engineering are delegated to a Vice. President. The-Executive Vice President is also responsible for assuring that annual; management reviews are conducted and yo documented.on the status, adequacy, and 3 effectiveness of the overall QA program. The responsibilities for construction have been delegated to the Project Manager. The Executive Vice President shall retain the responsibility for assurin of quality!gassurance that the authority personneland areindependence such that they can effectively assure the conformance to quality
~requirementh and are independent of. undue influences and responsibilities for schedule and
.-o 3-costs. fl Y x t Page 3 of 17 Revision 12 m
IP - Nuclear Power Chapter 1 Construction QA Manual A_)
- 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 Quality Assurance Program on safety related matters has been delegated to a Vice President.
- 4. Vice President A Vice President has been designated as the corporate officer responsible for overall direction of the IP Nuclear Power Quality Assurance Program: the testing, startup, nuclear support, nuclear purchasing, and commercial operation of Clinton Power Station and those activities associated with the engineering of Clinton Power Station. He reports to an Executive Vice President and has direct access to the President.
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- 5. Vice President V' A Vice President has been designated as the corporate officer responsible for those activities associated with environmental affairs.
The designated Vice President reports directly to an Executive Vice President. He has delegated this responsibility to the Manager-Environmental Affairs.
- 6. Manager-Nuclear Program Coordination The Manager-Nuclear Program Coordination reports to a Vice President and is responsible for assisting the Vice President of the nuclear group in meeting regulatory requirements, commitments, and Illinois Power Company goals and objectives as necessary to support construction, start-up, operation, and modification of the Clinton Power Station in an efficient and timely manner.
- 7. Project Manager A Project Manager has been designated as the person responsible for those activities associated with construction. The Project rx Manager reports to an Executive Vice President.
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Page 4 of 17 Revision 12
I 7, IP - Nuclear Power Chapter 1 Construction QA Manual 7-() 7.1 Construction Manager 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 An Assistent Project Manager reports to the Project Manager and is responsible for advising the Project Manager on various quality assurance issues. An Assistant Project Manager reports to the Project Manager and has been assigned the responsibility for Baldwin Associates' Cost and Scheduling Departments. 7.3 Manager-System Release and Completion The Manager-System Release and Completion reports to the Construction Manager and is responsible for direction of the program for completion and (~)N
\- turnover of all systems, components, and equipment from Baldwin Associates to Illinois Power Startup.
- 8. Manager-Nuclear Station Engineering The Manager-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 for the Clinton Power Station. These responsi-bilities include: the preparation of specifica-tions and drawings for the accomplishment of new designs, design changes, and modifications; l design interpretation; the conduct of design checks and reviews; and technical evaluation of
- contractors and suppliers. The Manager-NSED ensures that these activities are performed in accordance with the requirements of the IP Nuclear Power Quality Assurance Program.
- 9. Power Plant Manager The Power. Plant Manager reports to a Vice
(< w) President and is responsible for the safe, reliable, and efficient operation of the Clinton Page 5 of 17 Revision 12
IP Nuclear Power Chapter 1 Construction QA Manual
)
Power Station in accordance~with the operating license. This includes ensuring that the IP Nuclear Power Quality Assurance Program is incorporated into plant procedures and. implemented by the Clinton Power Station organization. 110. Manager-Environmental Affairs The Manager-Environmental Affairs reports to a Vice 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 & Support The Manager-Nuclear Planning & Support reports to a Vice. President and is responsible for schedule coordination and integration, human resources, support services, materials. management, maintenance services, budgeting, site accounting, t
(~h and program planning and scheduling. The x> 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-Startup reports to a Vice President.
and is responsible for. Checkout and Initial Operation (C&IO) preoperational and acceptance testing, and for providing assistance to the Power Plant Manager for startup testing.
- 13. Director-Nuclear Training.
The Director-Nuclear-Training reports to a-Vice President and is responsible for the direction and management of the Nuclear Training department
.for Clinton Power Station. Duties include developing training standards, providing centralized training, providing education support-to Nuclear Managers / Directors and maintaining operation of the simulator.
)
- 14. Manager-Licensing and Safety
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The Manager-Licensing and Saftey reports to a Page 6 of.17 Revision 12
IP . Nuclear Power Chapter 1 Construction QA Manual v Vice President and is directly responsible for providing representation and interface with regulatory agencies to obtain operating licenses for CPS, management of the Final Safety Analysis Report (FSAR) and the Environmental Report (ER), including certification and amendment submittals, management of the resolution of licensing issues, conduct of licensing reviews and studies, perform saftey studies and analysis,-conduct of Independent Safety Evaluation Group (ISEG) efforts for significant operating data, provida representation to safety groups, support of the Nuclear Review and Audit Group (NRAG) and the administration of tracking programs for 10CFR21
- and 10CFR50.55(e) items.
- 15. Manager-Quality Assurance The Manager-Quality Assurance reports to a Vice President and has direct access to the Executive Vice President. The Manager-Quality Assurance is responsible for IP's overall quality assurance program definition, direction, evaluation, and 7,s approval, including the IP Nuclear Power Quality
('~' ) Assurance Program. The Manager-Quality Assurance directs the Quality Assurance departmental activities related to the design, procurement, construction, and operation of the Clinton Power Station. The Manager-Quality Assurance interfaces with the Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region III, and the Authorized Inspection Agency for quality assurance activities. The Manager-Quality Assura'nce or a designated alternate has been delegated the responsibility and authority to stop unsatisfactory work during design, procurement, construction and operation provided the health and safety of the public or impact on capability to safely shut down the plant are 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 l 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 7-N assignment to the active position, the
(_) responsible person shall have six years experience in the field of quality assurance, preferably at an operating nuclear power Page 7 of 17 Revision 12
IP - Nuclear Power Chapter 1 Construction QA Manual G 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 si:: years experience may be fulfilled by 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 _ 7_s ( ) nuclear power experience in the N> 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 ASNE Boiler and Pressure Vessel Code, and other applicable regulations, codes, and standards. 15.1 Director-Quality Engineering & Verification The Director-Quality Engineering & Verification reports to the Manager-Quality Assurance. He is responsible for direction and management of the Quality Operations & 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 g- The Quality Technical Support Section is
(_j) . supervised by the Supervisor-Quality Technical Support who reports to the Page 8 of.17 Revision 12
-IP - Nuclear Power. Chapter 1 Construction QA Manual g
V Director-Quality Engineering & Verification. The Quality Technical Support Section assures that documents involving the following activities conform to the applicable QA program requirements of regulations, standards, codes, and other specific commitments: startup, engineering, radiation protection, and 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 responsive corrective action to IP surveillance findings, and for advising management as to the effectiveness of quality assurance progran 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. (_s}
- 2. QUALITY CONTROL SECTION The Quality Control Section is supervised by the Supervisor-Quality Control who reports to the Director-Quality Engineering & Verifica-tion. The Quality Control Section is responsible for conducting and reporting inspections and nondestructive examination of items or processes associated with startup, testing, maintenance, modification, nuclear fuel, and plant support activities performed by IP which affect quality. The Quality Control Section is also responsible for initiating reports of nonconforming items or conditions discovered during inspections. If significant quality problems are identified, the Supervisor-Quality Control has the authority and responsibility to hold or curtail and control further processing, delivery, or installation of nonconforming material, provided the ability to place the plant in a safe and stable condition is not affected.
, m. I Page 9 of 17 Revision 12
l IP - Nuclear Power Chapter 1 Construction QA Manual
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- 3. QUALITY OPERATIONS & MAINTENANCE SECTION The Quality Operations & Maintenance Section is described in the IP Nuclear Power Operational Quality Assurance Manual.
15.2 Director-Quality Systems & Audits The Director-Quality Systems & Audits reports to the Manager-Quality Assurance and is responsible for providing direction and administration of the Quality Systems, Audits, and Traveler Tracking staffs in defining, establishing, and verifying compliance with the IP Nuclear Power Quality Assurance Program.
- 1. QUALITY SYSTEMS SECTION The Quality Systems Section is supervised by the Supervisor-Quality Systems who reports to the Director-Quality Systems & Audits. The Quality Systems Section is responsible for periodically assessing departmental effectiveness in implementing the IP Nuclear Power Construction Quality Assurance Program,
.(~sI 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 section is also
. responsible for the coordination and g administration of QA/QC training programs for department personnel.
If significant quality problems are identified, the Supervisor-Quality Systems has the authority and responsibility to recommend to IP management to STOP WORK pending satisfactory resolution of the identified problem.
- 2. AUDIT SECTION The Audit Section is supervised by the Supervisor-Audits who reports to the Director-Quality Systems & Audits. The Audit Section is responsible for the planning, scheduling, and conduct of internal and external IP audits. The section performs followup action to ensure that the audited s organization provides timely and responsive
!) corrective action to IP audit findings. The section also advises management as to the effectiveness of quality assurance program Page 10 of 17 Revision 12
IP - Nuclear Power Chapter 1 Construction QA Manual p L) 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. TRiVELER TRACKING SECTION The Traveler Tracking Section is supervised by the Supervisor-Traveler Tracking who reports to the Director-Quality Systems &
Audits. The Traveler Tracking Section is responsible for ensuring travelers are allotted, controlled, and tracked in accordance with established guidelines and procedures. 15.3 Director-Construction & Procurement Quality Assurance ( ') The Director-Construction & Procurement Quality Assurance reports to the Manager-Quality Assurance. He is responsible for direction and management of the Construction QA and Procurement QA staffs. In this position he is responsible for 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 & Procurement QA. The Construction QA Section is responsible for planning, scheduling, conducting, and reporting surveillances of activities associated with the construction of Clinton Power Station. The section performs followup action to ensure that the organization surveilled provides timely and responsive corrective action to IP Construction QA surveillance findings. The section advises management of the effectiveness of QA program implementation
(~)T i s for those specific functions surveilled. The section is also responsible for assuring that Page 11 of 17 Revision 12
IP - Nuclear Power Chapter 1 Construction QA Manual
'~') 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, 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 & Procurement QA. The Procurement Quality Assurance Section assures that procurement documents contain the QA requirements of the FSAR, evaluates f') suppliers' QA programs for meeting the FSAR k/ 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. 15~4
. Director-Operations Monitoring Programs The Director-Operations Monitoring Programs reports to the Manager-Quality Assurance. He is responsible for providing assistance to the Manager-Quality Assurance in the development and implementation of Quality Assurance Operations Monitoring Programs that meet regulatory requirements, commitments, and support the safe and reliable operation of CPS.
(3 (_) l Page 12 of 17 Revision 12
IP .. Nuclear Power Chapter 1
~ Construction QA Manual n
15.5 Supervisor-Welding, NDE & Testing 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. 15.6 Administrative Supervisor The Administrative Supervisor reports to the Manager-Quality Assurance. He is responsible for the administrative functions of the Quality Assurance department. B. Sargent & Lundy
- 1. Sargent & Lundy has an organization which provides for the Balance of Plant (BOP) design.
Additionally, Sargent & 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 pro-vides the design and fabrication of the NSSS and nuclear fuel.
- 2. General Electric has a Project Manager who administers the contract for NSSS equipment through the 100 hour Plant Warranty Run.
- 3. General Electric has a Project Manager who administers the contract for the nuclear fuel fabrication.
- 4. General Electric has a Site Construction Manager to coordinate field installation of General Electric scope equipment.
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Page 13 of 17 Revision 12 L
IP - Nuclear Power Chapter 1 Construction QA Manual
!v) D. Baldwin Associates
- 1. Baldwin Associates has an organization which provides 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 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 built in accordance with the approved specifications and drawings.
- 3. Baldwin Associates has a Clinton Manager of Quality & Technical Services independent of the BA Clinton Project Manager. He is responsible for the activities of the Quality Assurance, Quality Control, and Technical Services Departments. The Baldwin Associates Manager of Quality & Technical Services is the interface between the Baldwin Associates quality f
'- organization and the IP Quality Assurance organization. The Baldwin Associates Manager of Quality & Technical Services receives. project direction from the IP Vice President (Nuclear) on matters related to quality.
Page 14 of 17 Revision 12
--__c, _.___.7 O l O
i i IP-Nuc ear Power (#
'- 'd
- IP ORGANIZATIONAL CHART OF CPS PROJECT chapter 1 construction oh manual NOTE: UP-TO-DATE DEPARTMENTAL ORGAN 12ATIONAL CHARTS AND FUNCTIONAL DESCRIPTIONS SHALL BE MAINTAINED AS PART OF CHAIRMAN AND DEPARTMENTAL DOCUMENTATION.
PRESIDENT k I EXECUTIVE EXECUTIVE VICE VICE PRESIDENT PRESIDENT k L w u, O H I I 4 i VICE PRESIDENT VICE PROJECT MANAGER MANAGER PRESIDENT NUCLEAR PROGRAM k COORDINATION I I I I I I MANAGER A ER MANAGER MANAGER ASSI PROJ. CONSTRUCTION LICENSING POWER PLANT NUCLEAR STATION ENVih0NMENTAL
" L Ty MANAGERS MANAGER ASSURANCE MANAGER ENGINEERING AFFAIRS AFETY W M N ER DIRECTOR MANAGER o SYSTEM MANAGER NUCLEAR NUCLEAR PLANNING g,
RELEASE & STARTUP TRAINING AND SUPPORT COMPLETION m P-O D
- W THIS FUNCTION HAS DLRECT ADVISORY REPORTING H RESPONSIBILITY TO THE COMPANY EXECUTIVE VICE PRESIDENT THIS SYMBOL DESIGNATES OFF SITE ORGANIZATICa L
FlCllRF l= l
m ('~h ; IP-Nuc car Power 1 (V Construction QA Manual Chaoter 1 IP ., ,, , , , , , , PRESIDENT X X EXECUTIVE V .P . XXXX XX X X (_ 3-------- -------------------------------..------------- , y
. l l 1 I
g BA CHAIRMAN IP IP I l l OF THE BOARD
---- - - - - PROJECT MANAGER PRESIDENT VICE -
x -. I s, m 0 ^ l I MANAGER 3 I NUCLEAR v
^
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- I I
. I i CO O RDIN ATION X
" i I X BA MANAGER X l l v ,, ,, , ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, ,, g g o a TS - - - o - n n n n - n n n n n n n n n n x i 1 l l M i i GE POWER MANAGER IP MANAGER IP MANAGER BUSINESS S&L PLANT NUCLEAR NUCLEAR QUALITY - GROUP PARTNERS MANAGER PLANNING AND STATION ASSURANCE RtJPPORT ENGINEERING MANAGER BA' PROJECT LICENSilvG MANAGER DIRECTOR MANAGER AND STARTUP HUCLEAR SAFETY TRAINING LINE SUPERVISION 3- --e------ CONTRACT RESPONSIBILITY n y M X X ADVISORY FUNCTION s ORGANIZATION INTERFACE RELATIONSHIP-l IP AND MAJOR CONSTRUCTION CONTRACTORS FIGURE 1-2 PuRPLTt-CLTI4, 10-29 _-- - -. ._ -_______ -_______ --
('T C) Chapter IP Nuclear IPQA ORG NIZATION Construction QA Manual . PRESIDENT EXECUTIVE v VICE n PRESIDENT VICE PRESIDENT X s
/
w k ?.'AflAGER-QUALITi v _, ACSUR ANCE A w af RECTOR-QUALIT'Y DIRECTOR DIRECTOR '
'I -
SUPERVISOR- OPERATIONS 31R ECTCRCUALIT Y
, Ef4GINEERING CONSTRUCTIOfJ 8 WELDING, rJDE, aDMINIST R ATION & VER;FICATION 'YSTEf
> S S AUDG'c PROCUREMENT QA Rt,tjG S TESTING I'fR g SUPERVISOR SUPERVISOR PROCUREMENT CONSTRUCTION QA OA o s- .;
- e T
8 SUPERVISOR- SUPERVISOR- SUPERVISOR - SUPERVISOR- l SUPERVISOR-QUALITY OUALITY QUALITY QUALITY SUPERVISOR-AUDITS TRAVELER SYSTEMS ] TECH. SUPPORT CONTROL OPS B MAINT. TR ACKIN G X, X X ADVISORY FUNCTION FIGURE l-3
IP - Nuclear Power ' Chapter 2 - QUALITY ASSURANCE Construction QA Manual PROGRAM 7 v' Approved /t/}/4Ld'$xeW H 0&d '99Y Date Hanager-QA I. PURPOSE: To describe the scope, function, and features of the Quality Assurance Programs of IP and its contractors governing design, procurement, fabrication, construction, inspection, and construction testing, of the Clinton Power Station. l II. REQUIREMENTS: A. Interface The IP Nuclear Power Quality As'surance 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 ('N M
%m overall responsibility for nuclear quality assurance applied to Clinton Station. IP has delegated to each V of its contractors the responsibility for developing g individual quality assurance programs covering their respective scopes of effort. These programs are D, 1 approved by the Illinois Power Quality Assurance department for use at the Clinton Project.
'#m 4 i i
The role of IP Quality Assurance is to direct the diverse efforts of IP and its contractors so that Cm)
x I
total program implementation is effectively achieved. b'a ; The IP program has as its objective achieving a final plant which is demonstrably planned, designed, built, quy I and tested in accordance with applicable governmental regulations and appropriate codes, standards, and h guides. G*en Qd B. General The Quality Assurance Programs of IP and its bb contractors have the essential elements as shown by g Table 2-1 and meet the following requirements:
- 1. The Quality Assurance Program is clearly described
-a and documented.
- 2. There is an overall description of the Quality Assurance Program that describes the relationship Page 1 of 11 Revision 12
IP.-1 Nuclear Power- . Chapter 2 ' Construction QA Manual r~g 'V - of;such documents as directives, policies, and procedures within the program. ;
- 3. The scope ~of the program is delineated.
- 4. The organizations involved are identified and the scope of their functions and interfaces defined.
- 5. .
Activities affecting quality and!the conditions
-under which these activities function are controlled. - 6. ~Special skills, processes, and equipment arc applied:as required.
~' 7.- Indoctrination and training are provided to assure that suitable proficiency is achieved and maintained.
- 8. The program is in compliance with the code of Federal Regulations (10CFR50, Appendix B) and other applicable codes, standards and regulations.
- 9. .There is management cognizance of the program.
k/ C. -Codes and-Standards The Illinois Power Company and its contractors maincain Nuclear Quality Assurance Programs which conform to the' ANSI' Standards and NRC Regulatory = Guides listed in Table 2-2. dII. DIVISION'OF RESPONSIBILITY: 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 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, procurement, 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:
Page 2 of 11 Revision 12
t IP - Nuclear Power Chapter 2 Construction-QA Manual x
'~ ' '/ .
- a. Organization The Company has established an organization responsible to top management for the design, procurement and construction of CPS in accordance with applicable regulations, codes, and standards.
- b. Program-A Quality Assurance Program description is documented in this IP Nuclear Power Construction Quality Assurance Manual which describes the obj ectives , requirements ,
interfaces, and division of responsibility for implementing the program.
- c. Procedures Written procedures are approved by management for use in conducting activities within the scope of the QA program.
- d. In-line Reviews
.f~)
(/ 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. Surveillances 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 transmits requirements from a higher level of authority to the next successive lower document level.
- a. Nuclear Policy Statements are documents issued by Corporate Management to promulgate authoritative management directives establishing and defining quality assurance policies within the Illinois Power Company
()
,s-Nuclear Power Program.
Page 3 of 11 Revision 12 t
\
IP - Nuclear Power Chapter 2 Construction QA Manual (nl' b.1 The IP Nuclear Power Construction Quality Assurance Manual describes the obj ectives, 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) are documents developed, approved, and issued to provide corporate direction and policy pertaining 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. (x ~ (-) b.3 The IP Nuclear Power ASME Quality Assurance Manual describes the obj ectives , 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 & Procurement QA. Authorization for use is signified by the signature of the Vice President (Nuclear). The company management's endorsement of the IP Nuclear Assurance Program is Power ASME signified Quality' Policy Statement" portion of in the the manual. b.4 CPS Records Management Standards provide direction in the areas or records identification, preparation, collection / review, turnover / transfer, storage, preservation, and maintenance. gg c. Departmental Procedures or Instructions are (j developed, approved, and issued within each organization to further implement the Page 4 of 11 Revision 12
IP - Nuclear Power Chapter 2 Construction QA Manual m
\
'"J requirements of Corporate Nuclear Procedures and the IP Nuclear Power Construction Quality Assurance Manual. 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 c of this manual.
The IP Nuclear Power Construction Quality Assurance Manual requirements described herein l apply to Clinton Power Station activities prior to - turnover of systems, structures, and components from 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 Appendi'x
(,_') B of this manual. The Manager-Quality Assurance k/ reviews and authorizes any changes to the list of recipients for the IP Nuclear Power Construction Quality Assurance Manual.
- 5. The Manager-Quality Assurance periodically reports the status and effectiveness of the quality assurance effort to the Executive Vice Presidents, Vice Presidents, and Managers / Directors.
- 6. Department Managers / Directors are responsible for establishing and maintaining formal training programs necessary to ensure proper qualification of personnel 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 approval notifications are sent to the contractors for their quality assurance files.
gS
%-)
Page 5 of 11 Revision 12
IP - Nuclear Power Chapter 2 Construction QA Manual-q
\#~ B. Sargent & Lundy:
- 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 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:
- 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
\_)N . necessary to provide quality surveillance and control for the GE scope of work. The General Electric Quality Assurance organization is responsible for implementation of the GE program.
The General Electric Policy Documents, Program Description, procedures, manuals, and implement-ing documents are applied to successively lower , levels of GE work. D. Baldwin Associates:
- 1. Baldwin Associates maintains a suitable quality
-assurance program controlling its scope of construction and related activities for CPS.
- 2. The Baldwin Associates quality assurance program is described in the Baldwin Associates Quality Assurance Manual. The manual is supplemented by detailed procedures and-written instructions as needed for detailed work. It provides for systematic construction control which extends to special processes, materials control, procurement, field design control, inspection, construction, testing, records, and control of r_ purchased components.
3.J Page 6 of 11 Revision 12
g CHAPTER 2 IP - Nuclear Power Construction QA Manual TABLE 2-1 QUALITY ASSURANCE PPOGRAM REQUIREMENTS Sargent General Baldwin Program Requirements IP
& Lundy Electric Associates Quality Assurance Organization x x x x 1.) x x 2.) Documented Quality Assurance Program x x and Procedures x Design Control x x x 3.)
Control of Procurement Documents x x x x 4.) Instructions, Procedures, and Drawings x x x x 5.) x x x 6.) Document Control x 7.) Control of Purchased Items x x a.) Source Evaluation x x x x x x b.) Source Selection x x x c.) Source Inspection and Audit x x x x d.) Receiving Inspection Identification and Control of Materials, x x x 8.) Parts, and Components Control of Special Processes x x x 9.) x 10.) Inspection Program x x x x x 11.) Test Control x x 12.) Control and Calibration of Measuring x and Test Equipment llandling, Storage , Shipping and x x x 13.) Preservation Inspection, Test, and Operating Statue x x x 14.) x x x 15.) Control of Nonconforming Materials, x Parts, and Components x x x x 16.) Corrective Action x x x x 17.) Quality Records x x x 18.) Audits x g g 11 Revision 12 g
I IP - Nuclear Powar CHAPTER 2 Construction QA Manual-g U 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-project 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 ASSOCIATED-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-()
- Denotes exceptions documented in Section 1.8 of the FSAR.
8 of 11- Revision' 12
IP - Nuclear Power CFAPTER 2 Construction QA Manual em TABLE 2-2 (Continued) b-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, FOR INSTRUMENTATION AND INSPECTION AND TESTING OF ELECTRICAL EQUIPMENT DURING INSTRUMENTATION AND ELECTRICAL THE CONSTRUCTION OF NUCLEAR EQUIPMENT POWER GENERATING STATIONS. ANSI N45.2.5 - 1974 REG GUIDE 1.94 R/l APRIL 1976 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 PHASD, CONST. PHASE OF NUCLEAR OF NUCLEAR POWER PLANTS POWER PLANTS.
- C ANSI N45.2.6 - 1978 REG GUIDE 1.58 R/l SEPT 1980 QUALIFICATIONS OF QUALIFICATION OF NUCLEAR POWER INSPECTION EXAMINATION AND PLANT INSPECTION, EXAMINATION TESTING PERSONNEL FOR AND TESTING PERSONNEL NUCLEAR POWER PLANTS t ANSI N45.2.8 - 1975 REG GUIDE 1.116 R/O-R JUNE 1976 QUALITY ASSURANCE REQUIREMENTS SUPPLEMENTARY QUALITY FOR INSTALLATION INSPECTION, ASSURANCE REQUIREMENTS FOR AND TESTING OF MECHANICAL INSTALLATION, INSPECTION EQUIPMENT AND SYSTEMS AND TESTING OF MECHANICAL
. EQUIPMENT AND SYSTEMS FOR THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS.
- Denotes exceptions documented in section 1.8 of FSAR.
OO 9 of 11 Revision 12
IP - Nuclear Power CHAPTER 2 Construction QA Manual
^3 TABLE 2-2 (Continued)
Q ,i ANSI STANDARD REG GUIDE ANSI N45.2.9 - 1974 REG GUIDE 1.88 R/2 OCT 1976 COLLECTION, STORAGE AND REQUIREMENTS FOR MAINTENANCE OF NUCLEAR POWER
, COLLECTION, STORAGE AND PLANT QUALITY ASSURANCE MAINTENANCE OF 0A RECORDS RECORDS FOR NUCLEAR POWER PLANTS ANSI N45.2.10 - 1973 REG GUIDE 1.74 R/0 FEB 1974 QA TERMS AND DEFINITIONS QUALITY ASSURANCE TERMS AND DEFINITIONS ANSI N45.2.11 - 1974 REG GUIDE 1.64 R/2 JUNE 1976 QUALITY ASSURANCE REQUIREMENTS QA REQUIREMENTS FOR THE FOR THE DESIGN OF NUCLEAR , ,' DESIGN OF NUCLEAR POWER POWER PLANTS
,(v)' PLANTS ANSI N45.2.12 - 1977 REG GUIDE 1.144 R/1 SEPT 1980 REQUIREMENTS FOR AUDITING AUDITING OF QUALITY ASSURANCE QA PROGRAMS FOR NUCLEAR PROGRAMS FOR NUCLEAR POWER POWER PLANTS PLANTS ANSI N45.2.13 1976 REG GUIDE 1.123 R/1 JULY 1977 QA REQUIREMENTS FOR CONTROL QUALITY ASSURANCE REQUIREMENTS OF PROCUREMENT OF ITEMS AND FOR CONTROL OF PROCUREMENT OF 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 o s
- Denotes exceptions documented in Section 1.6 or FSAR.
10 of 11 Revision 12
IP - Nuclear Power CHAPTER 2 Construction QA Manual-73 TABLE 2-2 (Continued) ANSI STANDARD REG GUIDE ANSI N101.4 - 1972 REG GUIDE 1.54 R/0 JUNE 1973 QUALITY ASSURANCE FOR QUALITY ASSURANCE REQUIREMENTS PROTECTIVE COATING APPLIED FOR PROTECTIVE COATINGS TO NUCLEAR FACILITIES APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS O O 11 of 11 Revision 12
IP - Nuclear Power Chapter 3 - DESIGN CONTROL Construction QA Manual
~ _
Approved /l///.k/2&sgW W 044 M/95
,/ Manager-QA Date I. 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. II. REQUIREMENTS: A. Interface IP Nuclear Station Engineering Department (NSED) is . responsible for the design of the Clinton Power Station. The performance of design in assigned to contractors. General Electric will design the NSSS and nuclear fuel. Sargent & Lundy performs the' design of the Balance of Plant and serves as the overall design 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 g,,had changes are forwarded to the appropriate design agent ro mj i through IP.
.u - ;
cCI Co B. General s a- The design control systems of IP and its contractors , will, as a minimum, have the scope and essential
"*T7' elements shown in Table 3-1 and shall meet the follow-
'?D? ing requirements:
9 g[i?$ rJ 1. Appropriate design planning documents shall be developed to identify the specific design docu- {oc3u _., ments, schedule their completion, and define major Gl,i., design milestones and other control points.
,e ,xs n2d(?, 2. Design bases, regulatory requirements, safety g7. a requirements, performance objectives, design margins, special processes, material and testing .
(,,.[g)f requirements, including acceptance criteria, 3 b, ^y4"' quality assurance requirements, and operating objectives shall be adequately translated into I various design documents. Design verification by k $[<3$ testing when specified shall be identified in the ensum design and purchase documents. Page 1 of 5 Revision 14 ,
IP - Nuclear Power . Chapter 3- DESIGN CONTROL
- Construction QA Manual m
Design documents shall describe quality related 3.
-- materials, components, systems, and structures in accordance with the design bases incorporated in the Safety Analysis Report (SAR). Design documents shall be based on applicable regulatory e criteria and include identification or specific et - engineering codes and standards to be employed.
Design deviations from 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 v design objectives. The responsibility for(n the 7 interface control shall be assigned.
L s. 5. A design review and verification system shall be e established to assure adequacy and conformance of
' - materials, parts, equipment, and processes with
- -design bases, regulatory requirements, and appli-cable codes and standards. The responsible design organization shall specify the verification
, (~') methods to be employed. u_/
- a. When design is verified by review, the bases shall be documented and the work shall be conducted by personnel who did not parform the n original design, but have technical qualifications equivalent to the minimum requirements for those performing the original design work.
- 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. r~N / l !' ,) a. The design change record, or an accompanying l document, shall identify the other design documents which are affected by the change. l f '[-- ' Page 2 of 5 l Revision 14 L /
. ~ _
~
y Chapter 3- DESIGN CONTROL
~
-IP - Nuclear Power .
l Construction QA Manual-r - NJ -, Such. documents shall be suitably controlled or a revised. V 't b. For'significant design changes, the design T change record, or an accompanying document, l will detail the reason and justification for the change.
- 7. A prog' ram shall be' established which describes the design control and verification elements that ensure that the as-built configuration of the
, safety-related structures, systems, and components of the plant conforms to'the final design and meets regulatory requirements, u
III.V DIVISION OF RESPONSIBILITY:
.a y IP maintains overall responsibility for the design of the Clinton PowerJStation. 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:
- A. IP is responsible for:
'd~
s 1.. Control of design contractors. This responsi-bility is assigned to the Manager-Nuclear Station Engineering.
- 2. Translating requirements into design documents.
g' The responsibility for design document accuracy is W assigned to the Manager-Nuclear Station Engineering.
- 3. The review and processing of design change 4
j requests. The Director-Construction & Startup Engineering has been assigned this responsibility. [
- 4. Auditing contractors to determine whether their design control systems meet the specified requirements of this manual and are properly implemented.
- 5. Assurfug that design documents reflect the actual as-built configuration of CPS.
B. Sargent & Lundy is responsible for:
- 1. Employing design control measures to assure design (S ., intent is achieved in Balance of Plant design
(,,/ s documents.
' Revision 14 6 Page 3 of 5 3
IP - Nuclear Power . Chapter 3- DESIGN CONTROL
. Construction QA Manual.
f~g U -2. ' Producing and certifying appropriate Design Specifications.
- 3. Preparing ASME Code related certifications (on behalf of IP) of Design Specifications, Stress Reports, and other key documents for CPS.
- 4. Developing an integrated equipment, system, and component identification system for the entire station.
- 5. Specifying the special processes and the applicable codes and standards for items of its design scope.
- 6. Specifying the inspection and related acceptance criteria applicable to Balance of Plant items.
- 7. Specifying the required tests and related acceptance criteria for Balance of Plant equipment and systems.
- 8. Evaluating design verification test results and
,,,s verifying for IP's permanent records that Balance
(
)
of Plant equipment meets the designer's specified requirements. l
- 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.
[D x_/ Page 4 of 5 Revision 14
Chapter 3
- IP - Nuclear ~ Power Construction QA Manual
'm
(_) 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 4.) Identify and Resolve Exter- x x x nal Interfaces 5.) Perform Design Verification x x x 6.) Review Design Documents for x x x incorporation of Regulatory Requirements, Codes and
[~D# Standards, Quality Require-J' ments, Performance, Material Application, Test Require-ments, Acceptance Criteria, Inservice Inspection, Main-tenance, Special Processes 7.) Control Design Changes x x x x 8.) Provide Design Specs x x and Stress Reports
- 19. ) Review subcontractor and x x x Vendor Design Documents 10.) Audit Design Control System x x x x i.
i-O Page 5 of 5 Revision 14
3 IP - Nuclear Power Chapter 4 - PROCUREMENT Construction QA. Manual DOCUMENT CONTROL .n k) Approved /t/hi/d/fuggV/ // G tt m g f Date
/ Manager-yA I. PURPOSE:
To describe the requirements for review and control of procurement specifications, purchase orders, and associated documents so procurement of material, equipment, and services, whether by IP, contractors, vendors, or subcontractors, is properly specified and controlled. II. REQUIREMENTS: A. Interface The main interface which exists for procurement docu-ment control is between IP, BA, and S&L. Under various conditions S&L, BA, and IP generate procurement documents and are responsible for O conducting appropriate reviews to. ensure that applicable technical and quality assurance program v h requirements, etc. have been included. Sargent &
%=I Lundy is responsible for the preparation and review of
%iN technical documents (drawings, specifications, etc.).
NSED is responsible for preparation of technical () documents (drawings, specifications, etc.). normally are responsible for the review of bid IP and BA
=g packages, the S&L prepared contractual documents, and 4 the placement of the purchase orders. Coordination of changes to procurement documents after issuance of a ce=~Y
- purchase order or contract are by that organization
%*N issuing the purchase order or contract. A secondary interface exists between GE and S&L. GE furnishes S&L with information copies of all procurement documents q1 *J released to GE subcontractors. GE also furnishes
$ certain documents from its vendors and suppliers as they relate to overall design coordination fe$$$ information.
B. General L6 Maas IP and its contractors shall meet the following re-Q quirements:
- 1. Procurement documents shall specify the appropri-(y ,
ate quality requirements. Page 1 of 3 Revision 12
IP - Nuclear Power Chapter 4 - PROCUREMENT Construction QA Manual DOCUMENT CONTROL p
\'~ /
- 2. Procurement documents shall, when appropriate, require that the vendors and subcontractors have quality assurance programs in compliance with
~
applicable codes, standards, rules and regu-lations. Vendors and subcontractors will be required to extend the applicable quality assur-ance requirements to their lower tier suppliers.
- 3. Procurement shall be based on appropriate and current specifications, drawings, and related documents.
- 4. Procurement documents shall be reviewed to ensure that the correct specifications, 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 A/ release control shall be clearly identified in the procurement documents. III. DIVISION OF RESPONSIBILITY: IP has assigned procurement 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 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 Station Engineering, g- 4. Review of selected procurement documents generated
(,)j by S&L to assure that regulatory, technical, and quality assurance requirements are included. Page 2 of 3 Revision 12
P . g io) TIP -fNuclear' Power Chapter 4 - PROCUREMENT i
' Construction ~QA; Manual DOCUMENT CONTROL LOL -These responsibilities are assigned to the J Manager-Nuclear Station Enginearing.
- 5. Commercial aspects of procurement, including the.
control and placement of purchase orders and contracts for construction and installation-related IP procurements. 'These responsibilities are assigned to the Manager-Nuclear Planning and Support.
- 6. Placing IP purchase orders and/or contracts'with approved vendors and contractors. This responsi-bility is assigned to the Manager-Nuclear Planning and Support.
- 7. Preparing the quality assurance program
-requirements or procurenent documents for special.
items and services. IP Quality Assurance is also responsible for evaluation and approval of the qualit'y assurance programs of prospective vendors i and suppliers 'of special items and services.
- 8. Periodic' 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 & Lundy is responsible for: Preparation of procurement specifications and contracts for Balance of Plant materials,. equipment, and services for construction and installation. 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 installa-tion at CPS.
/
(.)/ Page 3 of 3 Revision 12 - a~~~,w~
s
. IP - Nuclear Power Chapter 5 - INSTRUCTIONS, Construction QA Manual PROCEDURES &
DRAWINGS _/ Approved Y S A f$st d W 066 fffi Date j/ Manager-QA I. PURPOSE: To specify the requirements for use of instructions, procedures, sketches, drawings, and related material to control activities which affect quality. II. REQUIREMENTS: A. Interface Instructions, procedures, and drawings for execution of work are generated and implemented where required within the using organization. Procurement specifica-tions require that vendors and contractors who are not assigned primary design responsibilities submit drawings and procedures covering technical / quality portions of their work to S&L, GE, or BA as g, appropriate. Cleaning, handling, testing, and p?Aan installation procedures are originated by design organizations and/or manufacturers and transmitted to d [7. .,,^n BA for implementation in the field. (Aru g preg B. General w IP and its contractors shall meet the following re-
% quirements:
c;..: ,,
.g,
("""73 1. Written procedures, instructions, and drawings ej[Qg shall be developed and used for activities affecting quality. CG2[' 2. Instructions, procedures, and drawings shall e-M include the applicable qualitative and quantitative acceptance criteria for determining cyggp gygg j that important activities have been satisfactorily accomplished. gy
$N ;u g E") 3. Where appropriate, instructions, procedures, and m{ pes drawings for fabrication, installation, and an;[j testing shall indicate the sequential order of activities.
Page 1 of 3 Revision 10 i
i IP - Nuclear Power Chapter 5 - INSTRUCTIONS, Construction QA Manual PROCEDURES & DRAWINGS ry i~- 'I
- 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.
III. ~ DIVISION OF RESPONSIBILITY: IP has assigned the responsibility for using instructions, procedures, and drawings as follows: A. IP is responsible for:
- 1. Developing, approving, issuing, and employing those procedures, instructions, or drawings necessary to accomplish assigned tasks and respon-sibilities.
- 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. Inline review and approval of selected Illinois Power, contractor, and vendor procedures and in-structions prior to implementation to ensure compliance to codes, standards, regulations, the SAR, and the requirements of this manual.
- 5. Periodically audit internal, contractor, and vendor 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 'tse at CPS.
O d Page 2 of 3 Revision 10 l
a
. IP - Nuclear Power Chapter 5 - INSTRUCTIONS, Construction QA Manual PROCEDURES & 1 DRAWINGS 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.
D. Baldwin Associates is responsible for:
- 1. Employing instructions, procedures, and drawings for its scope of effort.
- 2. Requiring its subcontractors to employ instructions, procedures, and drawings for control of activities which may affect quality.
Page 3 of 3 Revision 10
'a IP - Nuclear Power ' Chapter 6 - DOCUMENT CONTROL Construction-QA Manual (9 .)
Approved /t/4Wddd # 8dd'9#8 Date
/ Manager-QA I. PURPOSE:
To specify the requirements for approval, release, and changes of documents prescribing activities which may affect
-quality.
II. 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 proce-dures prepared and issued by other contractors, as well as those documents prepared and issued by S&L, are reviewed by S&L for approval status. IP and each . (] contractor have measures established to assure the
"' '- receipt and use of approved, current documents.
b B. General metn$ W IP and its contractors shall meet the following re-- N* quirements:
- l. Documents shall be reviewed for adequacy by appro-
%, priately qualified personnel, approved for issue
.cdC,,, and use by authorized personnel, and distributed to/used at the location where the prescribed mmq !
ved activity is performed. m:am [** 2. Changes to documents shall be subjected to the q'j same degree of control as applied to the original documents. a g%, 3. Organizations issuing documents related to design, Q6d fabrication, construction, inspection, and testing have and use a control system which clearly b+= , identifies the document status such as bLu
'a
" preliminary", " issued for information", " app' roved for procurement", " approved for construction ,
# =w= " trial use", etc.
/m\ Document logs, index sheets, or other accountabil-(j -
-4.
ity methods shall be prepared and maintained current. Page 1 of 2 Revision 10
F IP - Nuclear Power Chapter 6 - DOCUMENT CONTROL Construction QA Manual O O 5. Measures shall be established to assure current revisions of documents are distributed to the points of use and are used. III. 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 activities to assure that appropriate (s) document control measures are employed in accordance with this manual.
B. Sargent & Lundy is responsible for:
- 1. Employing document control measures for those documents related to its scope of effort.
- 2. Instituting a system for receipt and review of those documents required by contract or specification.
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: ("3 1. Employing document control measures for those
\J documents related to its scope of effort.
- 2. Requiring that its subcontractors employ appropriate document control measures for the activities which may affect quality.
Page 2 of 2 Revision 10
+-
IP - Nuclear Power Chapter 7 - CONTROL OF Construction QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES
,G
)
Approved M//gdd/ // de6 <9db' fianager-QA Date I. PURPOSE: To establish the requirements for a system to assure that purchased material, equipment, and services conform to procurement requirements. II. REQUIREMENTS: A. Interface Control of purchased material, equipment, and services is accomplished by evaluation and selection of procure-ment source and inspection of product or service at either the vendor / contractor's plant and/or upon receipt at the site. S&L interfaces with IP by performing bid evaluations and reviewing vendor / contractor prepared m- documents. BA performs source evaluations within its
! I scope such as QA program reviews and evaluations,
[Aun - procurement quality surveillance, source inspection, and/or receipt inspection for BA purchased (BA issued 7d
,r;{
purchase order or contract) material, equipment, or service. IP/QA performs receipt inspection of IP purchased (IP issued purchase order or contract) kwe),
- m. construction and installation related material, equipment and services.
6%, B. General em 4 IP and its contractors shall meet the following re-p quirements: Cff" 1. Procedures or instructions shall be utilized to _ ,j effect control of purchased material, equipment, services, etc. qg O3d 2. Source evaluation shall establish that contractors, vendors, and subcontractors have Q demonstrable capability to provide a product, N process, or service in accordance with the g
===masu procurement documents.
, f Page 1 of 3 Revision 12
y IP - Nuclear. Power Chapter 7 - CONTROL OF Construction'QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES l
- 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.
The results of such surveys shall be recorded and maintained.
- 4. Effectiveness of the control of quality by con-tractors,. vendors, and subcontrcctors 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. III. 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 vendor's contractors and ensure that purchase orders or contracts are awarded only to approved vendors or subcontractors. This responsibility is assigned to the Manager-Nuclear Planning and Support.
- 4. Determining and designating receiving and/or source inspection requirements for IP procurement Page 2 of 3 Revision 12
IP' -Nuclear Power Chapter 7 - CONTROL OF Construction QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES
. ;-y V
of material and services.
- 5. Periodic auditing and surveilling internal, contractor, and vendor activities to assure that control of purchased material, equipment, and services is in conformance with the requirements of this manual.
'Sargent & Lundy is responsible for:
B. Providing assistance to IP as required in control of purchased Balance of Plant material, equipment, and services. This includes evaluations of vendor's technical and quality assurance capabilities for furnishing the specified product (s). C. General Electric is responsible for
- 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 g
respective scopes of work. D.- Baldwin Associates is responsible for:
- 1. Control of purchased material, equipment, and services required for its scope of work.
- 2. Subcontractors employing appropriate controls for purchased materials, equipment, and services l
required for those' subcontractors' scope of effort, and performance of source surveillances where required.
- 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. l
- 4. Performance of receipt inspection for construction
[ and installation materials, equipment, and l services received at the CPS site not procured by l IP. l 5. Documentary evidence of item conformance to f"' procurement requirements is available at the site l1\ prior to release for installation or use. l < Page 3 of 3 , Revision 12
w IP - Nuclear Power . Chapter 7 - CONTROL OF Construction QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES l v Approved M//ddd/ // de6 /92fi Date jtlanager-QA I. PURPOSE: To establish the requirements for a system to assure that purchased material, equipment, and services conform to procurement requiremettes. II. REQUIREMENTS: A. Interface Control of purchased material, equipment, and services is accomplished by evaluation and selection of procure-ment source and inspection of product or service at either the vendor / contractor's plant and/or upon receipt at the site. S&L interfaces with IP by performing bid evaluations and reviewing vendor / contractor prepared documents. BA performs source evaluations within its (N scope such as QA program reviews and evaluations, N- procurement quality surveillance, source inspection,
, 1*" and/or receipt inspection for BA purchased (BA issued
,,,,J purchase order or contract) material, equipment, or nu-p service. IP/QA performs receipt inspection of IP nel.dka purchased (IP issued purchase order or contract) c"=5 construction and installation related material,
'*- equipment and services.
*n'*y B. General ca un
()(() ns:2 ,2 IP and its contractors shall meet the following re-quirements: f'emn 1. Procedures or instructions shall be utiliced to CD) effect control of purchased material, equipment, i:unga services, etc. n0A , c 2. Source evaluation shall establish that ! k 'a" w
'" contractors, vendors, and subcontractors have
((([) demonstrable capability to provide a aroduct, g,g, process, or service in accordance wita the
, ,, procurement documents.
.cm.
nu=us s-) Page 1 of 3 Revision 12
P IP - Nuclear Power Chapter 7 - CONTROL OF Construction QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES s
- 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. The results of such surveys shall be recorded and maintained.
- 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
', ~s site prior to installation or use of the equipment
) or material.
III. 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 vendor's contractors and ensure that purchase orders or contracts are awarded only to approved vendors or subcontractors. This responsibility is assigned to the Manager-Nuclear Planning and Support.
- 4. Determining and designating receiving and/or source inspection requirements for IP procurement Page 2 of 3 Revision 12
a 7 IP - Nuclear Power Chapter 7 - CONTROL OF Construction QA Manual PURCHASED MATERIAL, EQUIPMENT, AND SERVICES L /~Y L of material and services. !~
- 5. Periodic auditing and surveilling internal, contractor, and vendor activities to assure that control of purchased material, equipment, and services is in conformance with the requirements of this manual.
B. Sargent & Lundy is responsible for: Providing assistance to IP as required in control of purchased Balance of Plant material, equipment, and-services. This includes evaluations of vendor's technical and quality assurance capabilities for furnishing the specified product (s). C. General Electric is responsible for:
- 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.
. /~3 - (_)
D. Baldwin Associates is responsible for:
- 1. Control of purchased material, equipment, and services required for its scope of work.
- 2. Subcontractors employing appropriate controls for purchased materials, equipment, and services '1 required for those subcontractors' scope of effort, and performance of source surveillances where required.
- 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 installation materials, equipment, and services received at the CPS site not procured by IP.
- 5. Documentary evidence of item conformance to procurement requirements is available at the site (3) prior to release for installation or use.
Page 3 of 3 Revision 12 L o
i g Chapter 8 - IDENTIFICATION IP - Nuclear Power . Construction QA Manual AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS (D v
; Approved [A&g((m df /V 846 'ffi
/ tanager-yA Date I. PURPOSE:
To establish the requirements for a system of identification and control of materials, parts, and components so that traceability from procurement through installation to end use is assured and the use of incorrect or defective items is avoided. II. REQUIREMENTS: A. Interface The identification and control of materials, parts, and components is primarily the function of the using organizations, i.e., various fabricators, the Constructor, and IP. In addition, Sargent & Lundy interfaces with the various contractors and Ci k# subcontractors in the assignment of identification information and the consolidation of random equipment at M:
- identification systems into one intergrated em,w) '
identification system for the Clinton Station. ma.p Cm z B. General
- IP and its contractors shall meet the following re-quirements:
"h th)
- 1. Procurement documents shall specify an appropriate identity to be applied to items of purchase, w2m
[amwu 2. An inventory control system shall be employed for
., s p receipt of materials, parts, and components.
e% 3.
'et'f 8 The identity of materials, parts, or components c R(-., shall be on the item or on records traceable to 3,ree the item. When ahysical marking is employed, the
({d" technique shall 3e indelible and not detrimental
'(d to the intended function of the item.
As ey 4. Identification shall be transferred to each part es*a or piece of an item when it is subdivided into
"'a== parts or pieces.
p_ Page 1 of 2 Revision 10
IP - Nuclear Power . Chapter 8 - IDENTIFICATION-Construction QA Manual AND CONTROL OF MATERIALS, PARTS,'AND COMPONENTS A D 5. Traceability shall be provided when required by code or regulation. III. 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. Periodic 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, 7_s and components into technical and procurement
'kJ 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 maintaining an identification and control system for materials, parts, and components.
- 3. General Electric's subcontractors employing appropriate identification and control measures for the subcontractors' scope of effort.
D. Baldwin Associates is responsible for:
- 1. Establishing and maintaining the identification and control of materials, parts, and components delivered to the field.
- 2. BA subcontractors employing appropriate
(~T identification and control measures as required (J for the subcontractors' scope of effort. Page 2 of 2 Revision 10 i
s IP - Nuclear Power Chapter 9 - CONTROL OF
-Construction QA Manual SPECIAL PROCESSES p
t/ Approved //WM/d fianager-QA
// Gd%' /9fe' Date I. PURPOSE:
To establish the requirements to assure that special processes are performed under adequate controls and that procedures governing 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. II. REQUIREMENTS: 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 t% controlled by the designing organization specifying the SS) ,, applicable special processes in design documents and enanj subsequently reviewing the special process procedures c$3.;cs submitted.
- m. ,
General (] B. IP and its contractors shall meet the following re-
,;gg; quirements:
! (.arn) cy 1. The need for special processes, and the codes or anan standards applicable thereto, shall be generally [rxm identified during design.
,',.a;ra
*4h 2. Fabricators and constructors shall utilize 5:35j appropriate methods for the qualification and cC32n certification of special processes.
pei
"""" Personnel responsible for the performance and 3.
($I[) verification of special processes will be qualified as required by, and in accordance with, gy?,, r- applicable codes and standards. U} c% m;num7 2 am:u.a Page 1 of 3 Revision 11 1-
IP - Nuclear Power . Chapter 9 - CONTROL OF
.- -Construction QA. Manual SPECIAL PROCESSES ,~,. l
- 4. Special processes shall be accomplished under
- suitable, controlled conditions. This shall include the use of qualified equipment, adequate control of the environment, and establishment of the proper prerequisites related to the process.
- 5. Records of procedure, personnel, and. equipment qualification shall be maintained using suitable methods for storage and retrievability.
- 6. Records that special processes were performed in compliance with qualified or approved procedures and with qualified personnel shall'be maintained using suitable methods for storage and retrievability.
III. DIVISION OF RESPONSIBILITY IP has assigned responsibility for the control of special processes as follows: A IP is responsible for:
- 1. Assuring that IP contracts or procurement documents require contractor or vendors to
(~}/ L- exercise control of special processes, as required, for equipment and materials.
- 2. Measures to control special processes and ensure that personnel are qualified in accordance with applicable codes, standards, specifications, criteria, and any other special requirements.
- 3. Periodic 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.
i%_. Page 2 of 3 Revision 11
= IP - Nuclear Power Chapter 9 - CONTROL OF Construction QA Manual SPECIAL PROCESSES k
- 2. General Electric manufacturing organizations establishing systems to effect control of special
-processes for their scopes of supply.
- 3. GE subcontractors exercising appropriate control of special. processes.
D. Baldwin Associates is responsible for:
- 1. Control of special processes performed in its construction activities.
- 2. BA subcontractors exercising appropriate centrol of special processes.
O LO Page 3 of 3 Revision 11
~
1 l
. 1 o.
IP - Nuclear Power Chapter 10 - INSPECTION Construction QA Manual l l Approved /L/$//Wl$nd// // OL'L' '985
/ Manager-QA Date 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. II. 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; s therefore, the fabricators and the constructor will
) interface with the organizations issuing such documents regarding inspections.
. General
" '1 * *
/ IP and its contractors shall meet the following i
,4r.ej i requirements:
a .,
'F 1. The general requirements for inspections shall be
' ')
f.:aC[ identified and documented during design of parts, components, and systems.
,J C;* 2. The organization responsible for fabrication, f T g' construction, or installation of parts, compo-
'.,y
/ nents, and systems shall prepare a detailed j3- :,
/ inspection program responsive to the requirements
~
c ' :, established in the design and procurement docu-ments. Hold points, if required in purchase e"un3a orders, shall be specified in the inspection (([ . , Program. (Jh 4 3. Persons implementing the inspection program, i.e.,
-m./ 3erforming the actual inspection activity, shall
(% ae organizationally independent of the persons [;}na) , performing the activity being inspected. f**.a
%m w 4. Inspection instructions shall contain or refer-d ence, as a minimum:
Page 1 of 3 Revision 11
IP - Nuclear Power Chapter 10 - INSPECTION 9 Construction QA Manual q
~
- a. A description of the inspection point.(source, receiving, etc.) and, where applicable, the sampling system to be used.
- b. The discrete identity of the part, component, or system being inspected.
- c. Applicable documents, drawings, and speci-fications pertaining to the activity or item under inspection.
- d. The inspection method to be used for each operation.
- e. The type, range, and accuracy of the in-spection instrument (s).
- f. Criteria for acceptance.
- g. Qualification requirements of the inspector.
- 5. Inspectors shall be qualified in accordance with applicable codes or standards.
l'~') 6. Where direct inspection or testing is impossible
' or disadvantageous, indirect control by monitoring process methods, equipment, and personnel shall be employed. When necessary to provide an adequate level of product quality assurance, both direct control (inspection and testing) and indirect control (process monitoring) shall be utilized.
When sampling plans are used, their applicability shall be evaluated and justified in a documented manner.
- 7. Rework, repair, or replacement subsequent to inspections will require reinspection to the extent necessary to demonstrate acceptability and conformance with the rework / repair procedures.
- 8. In-process and/or final inspections shall verify that the specified requirements have been met.
III. DIVISION OF RESPONSIBILITY IP has assigned responsibility for inspection as follows: A. IP is responsible for: (^) 1. Incorporating appropriate quality assurance (,/ program requirements for inspection into IP generated contracts or procurement documents. Page 2 of 3 Revision 11
0 o ' 0 - IP - Nuclear Power Chapter 10 - INSPECTION Construction QA Manual m J
- 2. Conducting "overinspection" of contractor and subcontractor activities. Overinspection shall be conducted on a samaling basis by qualified inspectors under the employment of IP who are independent from the construction and inspection activities being 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: 7-
- l. Specifying inspection acceptance criteria (3) applicable to NSSS items and nuclear fuel.
- 2. Implementing inspection programs for the manufacture of NSSS equipment and nuclear fuel.
- 3. Requiring that its subcontractors establish and imalement an inspection program for the subcontractors scope of effort.
D. Baldwin Associates is responsible for:
- 1. Inspection of its construction and installation ,
activities.
- 2. Its subcontractors establishing and implementing inspection programs for the subcontractors' scopes of effort.
(w_/ Page 3 of 3 Revision 11
IP - Nuclcar Power Chapter 11 - TEST CONTROL Construction QA Manual Approved /t/k $$ W $ & # H & & M nc Date
^
,/ Manager-QA I. PURPOSE:
To establish the requirements for control of the identification, pertormance, and evaluation of construction testing which will assure that the structures, systems, or components being tested will perform satisfactorily in service. After turnover, the IP Nuclear Power Quality Assurance Program requirements described in the IP Nuclear Power Operational Quality Assurance Manual apply. II. 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 will be directed / conducted by f-- q IP and supported by BA and other applicable vendor personnel. J ==Q B. General a. c~9 %m IP and its contractors shall meet the following re-(j{]) uirements:
- 1. The tests and acceptance criteria necessary to f77]d assure satisfactory performance will be specified in design documents, technical specifications, or (l l' f)'
. other related documents.
e:. - f [a~a., .a 2. Test programs shall be developed to assure that m, required tests are performed in accordance with 6 approved written procedures which incorporate or 4 '. 9 reference the design requirements, limits, and acceptance criteria as specified by the j (";'o f p7j49 appropriate design organization. k.Ill) 3. Written test procedures will be utilized to implement test programs. Individual test proco-
&3,y
- - dures shall contain or reference, as a minimum, r , the following provisions:
um '%h Page 1 of 3 Revision 12
7 . t . ,
~
/
IP - Nuclear Power Chapter 11 - TEST CONTROL , , Construction-QA Manual. i
. = .
( -
- a. Statement of the test objective.
! b. PrerequisitestobefulfilledpriortotheI i test, including availability of calibrated ~ . instrumentation and suitable environment.
- c. Instructions-for performance of the test,
- including requirement for verification that instruments selected are of the 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 fellow testing to determine whether performance characteristics ' ~
conform to design. The need for repair or rework . and/or ratesting shall be identified as necesecary. ~ , - III. DIVISION OF RESPONSIBILITY: , IP has assigned construction test control responsibilities as follows: A. IP is responsible for: %-
- 1. Assurance that IP contracts or procurement documents recuire the contractor or vendor to
~
establish anc, implement an adequate program for testing equipment and maceriais.
- 2. Periodic 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. Specifications and descriptive material for such testing and related planning will be prepared in accordance with documented procedures, and systematically .,, reviewed and approved by the same methods applicable to other phases of important safety *
.u re ated design.
?
- 2. Assistance to IP upon request in testing and ,
S evaluation of test results. Page 2 of 3 Revision 12
19- ' I7-1 IP - Nuclear Power Chapter 11 - TEST CONTROL pI9. Construction QA Manual i C. General Electric is responsible for:
- 1. Specifying the required tests and acceptance
+f criteria for NSSS equipment and nuclear fuel.
L(- -
- 2. Implementation of controlled programs for testing items in their scope of supply.
q l # 4-c' 3. Evaluation of test results and certifications for ! IP's permanent records that NSSS equipment meets specified requirements. p 4. GE subcontractors establishing and implementing 7 adequate programs for control of test items in the
'- subcontractors' scope of supply.
t L D. Baldwin Associates is responsible for: i 1. Establishing and imalementing a controlled program b, for the static checcout of equipment and !' components it installs.
- 2. BA subcontractors establishing and implementing adequate test control programs as appropriate.
i. L i j t ( i l Page 3 of 3 Revision 12 i r:
s, IP - Nuclear Power . Chapter 12 - CONTROL OF . Construction QA Manual MEASURING AND TEST EQUIPMENT Approyed by ,//$/.4Wfo,e&G // Occ' M$a~ JManager-QA Date I. 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 accuracy is maintained in order to verify conformance to requirements. II. REQUIREMENTS: A. Interface Control of mea'suring and test equipment is the function of ' organizations utilizing them. B. General IP and its contractors shall meet the following nN requirements: 6 f dA / 1. Measuring and test equipment shall be calibrated at cQ i scheduled intervals by comparison with valid
% nationally recognized standards. If recognized
%,;. f standards are not available, the standards used shall (p f be carefully preserved and available for traceability purposes.
jSD 2. Calibration intervals will be based upon the type of Af equipment, frequency of use, environment of use, and Q)7 other conditions affecting accuracy. [%
=cu j
- 3. Calibrations shall be performed using approved written procedures or appropriate manufacturers' manuals.
g% , Standards will be maintained and used in a controlled
'tO*a ;
f environment which will not adversely affect the W 1. Incorporation of appropriate quality assurance program requirements for the control of measuring and test .
equipment into IP generated contracts or procurement documents.
- 2. Periodic 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.
B. Sargent & Lundy-is responsible for:
- 1. Directica of activities which require a quality assurance program for identification and control of 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 measuring and test equipment utilized for test and/or inspection of NSSS equipivnt and nuclear fuel.
r^ 2. Its subcontractors establishing and implementing
- (_)x effective measures for control of measuring and test equipment used.
Page 2 of 3 Revision 11
9 . IP - Nuclear Power . Chapter 12 '
- - ' Construction QA Manual !
D. Baldwin Associates is responsible for: l'. Establishing and implementing effective measures for the control of measuring and test equipment used-by BA in > construction, inspection, or test activities.
- 2. Its sub' contractors establishing and implementing effective measures for control of measuring and test equipment used.
O: f i I. I LO l-l Revision 11 l Page 3 of 3 l-
IP - Nuclear Power Chapter 13 - HANDLING, Construction QA Manual STORAGE, & SHIPPING Appraved YY#s(bst/rieW
~
ff Asd /9f.E j/ Manager-QA Date I. PURPOSE: To establish the requirements for a system which will assure proper handling, storage, shipping, preservation, and clean-ing to prevent damage, deterioration, and loss of items. II. REQUIREMENTS: A. Interface Vendors are required to provide information relative to handling, storage, and shipping of material, parts, and
'N components to the Purchaser for use in storage and
..) handling activities at the site. This information is contained in purchasing or technical documents.
B. General s IP and its contractors shall meet the following re-
,, ,,j quirements:
Eaarrcsta ae 1. Written and approved procedures for handling, storage, gur . shipping, preservation, and cleaning of materials, parts, and components within the scope of this program ugyps shall be used. c.wm
- 2. Procurement documents shall require vendors and
(["*) ca!L subcontractors to furnish proccdures for handling, e A n,,,_, storage, shipping, preservation, and cleaning of items supplied. W$ en -a 3. Shipping containers shall be marked to identify the contents, the sender, and the destination. Tags edifl* j securely attached to the shipping containers may be bjgg mma used if containers are too small or irregular in shape to be marked directly with the required information. ([{]) Handling shall be controlled by written procedures. l [j(([ 4. Special markings shall be provided for packages , mm containing items which are fragile or may sustain internal damage not readily detectable except by disassembly. Pace 1 of 3 Revision 11
IP - Nuclear Power Chapter 13
' Construction QA Manual Ov Written instructions shall be provided for the 5.
preservation of items that are subject to deterio-ration or damage through exposure to 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 themselves 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.
III. 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
-l,,) requirements for controlling the handling, storage, N/ and 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. Periodic 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:
- 1. Review of procedures for handling, storage, and shipping of equipment and materials for adequacy.
C. General Electric is responsible for:
- 1. Its subcontractors implementing appropriate controls for their handling, shipping, and storage of NSSS equipment and nuclear fuel.
- 2. Its subcontractors providing information for proper Os handling, storage, and shipping.
- 3. Implementing appropriate controls for handling, storage, and shipping of items they supply.
Page 2 of 3 Revision 11
i
.s IP - Nuclear Power Chapter 13 Con'struction-QA Manual ,
gS
%)
D. Baldwin Associates is responsible for:
- 1. liandling and storage of equipment received at the site for use in construction of CPS.
- 2. Its subcontractors and vendors implementing appropriate controls for the handling, shipping, and storage.of items in the subcontractors' scope.
- 3. Its subcontractors and vendors providing information for proper handling, storage, and shipping for items they supply.
O t o l Page 3 of 3 Revision 11
o 4 IP - Nuclear Power ' Chapter 14 - INSPECTION, TEST
/
Construction QA Manual AND OPERATING STATUS I i
\ J Approved / V f/-rlM / / $ w ff H &cd /9fJ'
/' Manager-QA Date I. PURPOSE:
To establish the requirements for a system which identifies the status of material, parts, components, and assemblies through manufacturing and fabrication, inspection, testing, construction and installation to assure that only items that have passed the required inspections and tests are used or installed. II. REQUIREMENTS: A. Interface g( ) Balduin Associates interfaces with IP at the turnover of ( equipment, components, systems, and structures for
- - - - ~
checkout and initial operation. The systems employed by
- Baldwin Associates and IP for indicating status of
' gepulu svs9"" - [fi inspection and tests also include controls to clearly indicate jurisdiction and safety conditions.
chf+' se-*
.;g, B. General
' f"Ih!# '
IP and its contractors shall meet the following requirements: i
, w;p .-
# The inspection or test status of items shall be
'Yh7? l.
(;,;jf> l clearly identified. Markings which indicate status sn#me ! may include stamps applied directly to the item, tags, [2ees or labels attached to the item, routing cards that
';,,.;d j accompany the item, or records which are traceable to w ! the item.
oMy i
- Cs.xg 2. Visual evidence of status shall be documented and i frag e# , affixed to inspected items. A control stamp, signature, or initials shall be applied. If control f
' "'y[' ) ,
(gg stamps are used, a record of the assignment of control p.:i*4 4 stamps shall be maintained. ux-tat W gd- . g??a p 3. If markings are applied directly to the item, there ( eard F shall be consideration given to the effect of the markings on the item. If impression stamping is used, it shall conform to the requirements of applicable specifications, codes, and standards. Page 1 of 2 Revision 12
- d IP - Nuclear Power Chapter 14
/ Construction QA Manual (3 V
- 4. The method of indicating test or inspection status 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.
III. 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. Periodic auditing of internal, vendor, and contractor activities to assure that indication of status is in
;f-accordance with the requirements of this manual.
Q) \J B. Sargent & Lundy is responsible for:
- 1. 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 establishing and implementing adequate measures to indicate inspection and test status of NSSS equipment and nuclear fuel.
2' . Developin'g and* implementing adequate measures for the indication of inspection and test status appropriate to their scopes of supply. D. Baldwin Associates is responsible for:
- 1. Its vendors and subcontractors establishing and implementing adequate measures for indication of inspection and test status during manufacture of equipment.
- 2. Developing and implementing a system to indicate ,d
(~ ' inspection and test status during construction gh le installation activities. Page 2 of 2 Revision 12
" IP - Nuclear Power Chapter 15 - NONCONFORMING Construction QA Manual MATERIALS, PARTS, OR COMPONENTS A
V Approved 8 //ev/ d es29 # 8d /9f;I'
)(anager - QA Date I. 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. II. REQUIREMENTS: A. Interface Illinois Power interfaces with its vendors and f- ~., subcontractors for the identification of nonconforming
! items. BA interfaces with IP for coordination with the C(! appropriate design organization, i.e., General Electric, Sargent & Lundy, for disposition of the nonconforming
. condition. General Electric advises IP and S&L of the 7l-{ disposition of nonconforming items in its scope of supply
- 75. ...lN i which may affect the Balance of Plant.
gh mqp >i,; i 1 B. General ~ { eMk:t I IP and its contractors shall meet the following re-ggt;}g. ; quirements: x. J. Procedur,es sha,ll be established for the control of
@4D c'- nonconforming items.
I (,N e.gud ; 2. Nonconforming items shall be clearly identified. I hihw' s
- 3. Nonconforming items shall be placed in a segregated
! hj storage area when practical. Such storage areas shall rWQ be clearly identified as containing only nonconforming re gh Q items.
1 bmy~h V 4. Measures shall be established which control further (h j;j use or installation of nonconforming items pending disposition. O . . ' l:K{.'. ( 'Q/ 1 y g
- 5. A technical review shall be performed to determine the disposition of nonconforming items. The technical review shall be conducted by the same or equivalent 4 organization which established the original design requirements.
Page 1 of 3 Revision 12
e. IP - Nuclear Power Chapter 15 Construction QA Manual
\-)
- 6. The disposition of nonconforming items may be one of the following: a. use as is, b. rework (to drawing and specification requirements, c. repair (to an acceptable condition, d. reject (for this use), or e.
non-hardware (for activities not affecting 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 reinspected 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 that the procedures for controlling nonconforming items have been followed.
III. DIVISION OF RESPONSIBILITY IP has assigned responsibilities for control of nonconform-((7_s) ing materials, parts, or components as rollows: \ A. IP is responsible for:
- 1. Establishing and implementing effective systems for the control of nonconformances encountered during their activities.
- 2. Designating in IP-generated contracts or procurement documents that contractors and vendors establish and implement effective systems for disposition and control of nonconformances.
3l Reviewing
- recommended dispositions, if provided, for concurrence. Provides dispositions to selected contractors' nonconformance reports (NCRs).
Engineering justification for construction related nonconformances which are dispositioned " repair" or "use-as-is" or require a design document change.
- 4. Determining what additional review is required by the responsible design organization.and reviewing recommended dispositions made by the responsible design organization.
(" (w,)/
- 5. Providing in-line reviews and approvals of selected contractors' NCRs prior to implementation to ensure compliance to the requirements of this manual.
Page 2 of 3 Revision 12
IP - Nuclear Pow r Chapter 15 Construction QA Manual v) 6. Periodic audits of internal, vendors' and contractors' nonconformance systems to verify that control of nonconforming items is in accordance uith the requirements of this manual. B. Sargent & Lundy is responsible for:
- 1. Engineering justification for construction related nonconformances which are dispositioned " repair" or "use-as-is" or require a design document change as requested by IP. S&L shall provide a similar function for those BOP purchased items, materials, or services when the purchase order specification requires that the nonconformance be referred to the purchaser.
C. General Electric is responsible for:
- 1. Its subcontractors establishing and implementing effective nonconformance systems for NSSS equipment and nuclear fuel.
- 2. Establishing and implementing an effective nonconformance system for their scope of supply.
rf ly) u
- 3. Dispositioning nonconforming items related to the NSSS and nuclear fuel as requested by IP.
D. Baldwin Associates is responsible for:
- 1. Its vendors and subcontractors establishing and implementing effective nonconformance systems for equipment supplied or installed by those subcontractors.
- 2. Establishing and implementing an effective system for the control of nonconformances encountered during construction an,d installation.
- 3. Establishing a system which refers selected nonconformances to IP for dispositions or coordination with the responsible design authority in obtaining dispositions and for obtaining IP Quality Assurance review and approval of the nonconformance.
t e Page 3 of 3 Revision 12
Ifs! IP - Nuclear Power . Chapter 16 - CORRECTIVE Construction QA Manual ACTION 4 t, Approved /u[/ fits / d w g/ N der # /9ff
~
~, Manager-QA Date I. PURPOSE:
To establish the requirements which assure that conditions determined to be adverse to quality are promptly corrected in a manner which precludes recurrence of such conditions. II. REQUIREMENTS: A. Interface Those departments which manage or direct contractors will interface with those contractors for obtaining corrective action. Requirements for specific corrective action are e trr.nsmitted by IP to the contractors. e ( B. General n IP and its contractors shall meet the following f yg.f 1 j I requirements: v eNhu g
- l. A corrective action system shall be established.
[ygv. d"* 5, 2. Conditions adverse to quality shall be promptly g;g[fy identified and corrected. g%
,t r; G $
9 '
- 3. For significant conditions adverse to quality, the corrective action shall include measures to preclude repetition, wh,en appropriate.
! rw% ,^
I wwp ..
' " r38' 4. Conditions adverse to quality shall be systematically 5 "** *b analyzed for causes and referred to management for eg 8 resolution.
WS
*'eru
- 5. Corrective action shall be evaluated to determine effectiveness.
O ,r> wm
- 6. Records shall be maintained w5$ich demonstrate that Ncrwg rw , identified conditions adverse to quality have been
. fe:-km 1.; corrected. The records shall document recommendations for corrective action and the implementation of w
h-i p @s:i corrective measures.
- reminiuse y i
~_ n Page 1 of 2 Revision 10
a 7' . , ti- l IP - Nuclear Power . Chapter 16 Construction QA Manual
?,
sj-III. DIVISION OF RESPONSIBILITY: IP has assigned responsibilities for corrective action as follows: 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 requirements for establishment 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. Administration of a Management Corrective Action Request (MCAR) Program, a management tool whereby the Vice President (Nuclear) and management of the respon-sible organization (either internal or external to IP) are advised of adverse conditions which require r^3 immediate corrective action.
{/ Periodic auditing of internal, vendor, and contractor 5. activities to assure that corrective action systems have been implemented in accordance with the require-ments of this manual. B. Sargent & Lundy is responsible for:
- 1. Implementing and maintaining a corrective action system governing its scope of work.
C. General Elec,tric i,s responsible for:
- 1. Implementing and maintaining a corrective action system governing its scope of work.
- 2. Its subcontractors establishing 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.
(
);)s 2. Its subcontractors instituting corrective action systems governing activities associated with the supply, construction, or installation of equipment by those subcontractors.
- Page 2 of 2 Revision 10
/
Chapter 17 - QUALITY IP - Nuclear Power Construction QA Manual ASSURANCE RECORDS Approved [4f/ M [ M N Cc6 /9#I f/ Manager-QA Date I. PURPOSE: 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. II. REQUIREMENTS: A. Interface Interfaces regarding quality assurance records e::ist where there is a division of the record keeping responsibility
. ,cs and subsequent turnover of r cords to IP. Some quality 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
--- - - - manuracturers no longer plan to keep them.
m > J MM . _13 B. General
%;.gjg$ g IP and its contractors shall meet the following require-craflaan; ments:
- 1. Sufficient records shall be prepared as work is per-l '
formed to provide evidence of the quality of. items and sc-573 - ; of activities p'erformed. 41.sw 1 l j) (a((uu[ma ;f
- 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 pin =a3 Q;s i Power Station.
p L'a l g ecps52 2 3. Quality records shall be filed in a timely and orderly { egk@$$ f manner to allow for access and..retrievability. They
;i shall be maintained in a file, room, or area that i gnesof ua""*' i provides controlled access and protection against j (Q;$h fire, flooding, vermin, and decay, bb' 4. The original quality of the records shall be preserved 113k means it ,
to maintain archival quality. The quality of the record shall enable the observer to readily identify i
- information contained on the record.
Page 1 of 3 Revision 11
,;[ * .
a IP - Nuclear Power Chapter 17 Construction QA Manual
- 5. Records shall typically include results of reviews, inspections, tests, audits, monitoring of work perfor-mance, and materials analysis. They shall also include as appropriate, closely related data such as qualifications 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-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.
III. -DIVISION OF RESPONSIBILITY: IP has assigned the responsibilities for quality assurance [ s records as follows: A. IP'is responsible for:
- 1. Assuring that IP generated contracts or procurement documents specify the following:
- a. Requirements for the generation, maintenance, and control of technical and quality records.
- b. Requirements 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. Developing and implementing the 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. L ,n 3. Verifying the BA administered record maintenance system for IP during the construction phase of CPS. 4'. Coordinating the management of site quality records to ensure that a smooth and timely turnover of records and responsibility to the operating staff occurs. Page 2 of 3 Revision 11 {
o Chapter 17
; IP - Nuclear Power
' Construction QA Manual L
-5. Periodic auditing of internal, contractor, and vendor '
i activities to assure that control of quality assurance i records is in accordance with the requirements of this manual. 6 ', Developing-and implementing a quality assurance records verification program to assure that these i records meet the requirements of this manual. B. Sargent & Lundy is responsible for:
; 1. Developing and implementing 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 j testing of the plant.
C. General Electric is responsible for: 1 1 1. Its subcontractors employing appropriate controls of quality assurance recoros required for subcontractors' fs work on NSSS equipmenc and nuclear fuel. I" 2. Developing and implementing a record-keeping system for the documentation and quality records required for NSSS equipment and nuclear fuel. ! 4
- 3. Turnover of appropriate documents and quality records generated by GE and its subcontractors to IP.
D. Baldwin Associates is responsible for:
- 1. Its subcontractors and vendors employing appropriate controls of quality records as required for the supply, construction and installation of equipment'by those contractors.
- 2. Developing and implementing a record-keeping system
' for the quality records generated or received during construction and installation. 4
- 3. Turnover of appropriate documents and quality records generated by BA and its subcontractors to IP.
1 A i Page 3 of 3 Revision 11
4 g Chapter 18 - AUDITS ( IP - Nuclear Power Construction QA Manual
.V Approved //A/WAA&/ # Oc6 '9W
,7 Manager-QA Date I. PURPOSE:
To establish the requirements for a planned system of periodic audits which verify compliance with the quality assurance program and measure its effectiveness. II. REQUIREMENTS:
'A. Interface Audits and surveillances are among the main interfaces betJeen IP and other participants in the Clinton Power Ste: 2on. IP Quality Assurance interfaces with each fs contractor at the operating level and at the management fd q'uality 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 23Me i M.h IP and its contractors shall meet the following re-
, pfg quirements:
y:ez pMW ' Organizations whose functions affect the quality of c l. rrr '$ i the safety related aspects of the Clinton Power Station shall institute a comprehensive system of
=~1(g i planned,~' periodic audits. The audit system will be I r7?p A sufficient to include the full range of activities kj!/ f5 h covered by the scope of the applicable quality assurance program. The audit system will include
;j,,A]-a... $jf provisions for both internal and external audits.
" % as ig j .yp 2. The audit system plan shall provide for regularly
@babd l 'c scheduled audits based on the status and importance of cy=s834 the activities. ._
licCf , b 3. Personnel conducting audits shall have no direct
'bd"g,s '$; responsibility to the organization being audited. The lead member of the audit team shall be a qualified (i ( h audit team leader and shall instruct the other members Q !, ggj -[ ..
during audit preparation.
<L d v
"'" Page 1 of 3 Revision 10
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Chapter 18 { IP - Nuclear Power Construction QA Manual.
- 4. Written audit plans shall be developed for each audit to be performed.- These plans shall identify the scope, 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 responsibility for the area audited. These managers shall be responsible for determining-and implementing 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.
fs III. DIVISION OF RESPONSIBILITY:
- k, IP has assigned responsibilities for auditing as follows
A. IP is responsible for:
- 1. Aseuring that IP contracts or procurement documents require contractors and vendors to establish and implement appropriate audit programs.-
- 2. Establishing an internal audit program and audit each IP organization performing activities within the scope of this program.
- 3. Establishing ~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. Coordinating the performance of independent audits of the IP Quality Assurance depar.tment for the Executive Vice President.
k-Page 2 of 3 Revision 10
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Chapter 18 { IP - Nuclear Power Construction QA Manual _g V B. Sargent & Lundy is responsible for:
- 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 !!SSS equipment and nuclear fuel are in compliance with the General Electric Quality Assurance Program and this manual.
- 2. Its subcontractors instituting appropriate audit programs.
- 3. Auditing its subcontractors to assure that activities associated with the subcontractors' scopes of effort are in compliance with the subcontractors' quality assurance programs.
D. Baldwin Associates is responsible for: 1( ,) 1. Instituting an audit program assuring that activities ( .- associated with construction and installation effort are in compliance with the Baldwin Associates' quality assurance program and this manual.
- 2. Its vendors and subcontractors instituting appropriate audit programs.
- 3. Auditing its' vendors and subcontractors' to assure that activities associated with the subcontractors' scope of effort are in comp?.iance with the subcontractors' quality assurat.ce programs.
h t Page 3 of 3 Revision 10
i
~
IP - Nuclear Power. Appendix A Construction QA Manual .
.n 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 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 ar,licable Quality Assurance requirements are as follows:
- 1. " App. B" indicates that the structure, system, or component (s/s/c) must be designed, purchased, constructed, tested, etc. in accordance with the Quality Assurance requirements
., of 10CFR50, Appendix B which is implemented by the Quality -( ) 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.
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 i source document. N '
;? % '
~
~
*i!.
. !b14 %n
%MA!QU!Omn Qi 1 O)m ,
/
A-1 Revision 11
IP - Nuclear Power Ancendix
~^ A Construction OA Manual e C!.ASSF* A?!?N ORI- 9IA jI .aAn eE2TML.- 3Y l CL,I:.*TC.:I .F.CVER
- STAT! N Iden:1.aca:::n ana Jiassificatica #-o~"-..* "C3* 6 "~ 5/6=s97
* " * *
- guy. - 10
.O.f. _S a_f.e t.y .R a.l.a_t
. - e.d .S t.:.ac tur e s . - 9-12-83 Table ?.1 - Classifiestien of Princiesl St:-:etures. ?/ste-S *nd C:- ae= ant s _
SA?i"."I d SE!!MI0 d 0"A LI"Y EI.I""RICA!/ OA?IO'WSI PRIN0!?AL 2"R'JC"'JRIS. (w aas 1.2 (ca:agory I (G rcup A,3. (class .I. ppp.5 at 1 3YCIDf3 is CCMPCNI:iTS 3 or Ctner) or 3/A) C,3 or N/A) Non-Class N/A) i 1E or 'f/A y AN3: N13.2 Reg. Guide Reg. Guide Reg. Guide Reg. Guide a (ANS-21), 1.29 1.26,AS G- 1 32 1.2d (ANSI-3 REFERENCIS: AN3-22, Secticn III 3Od) (IIII- Nu5.2 ), s eg, a ANS-23 Guide 1. - (ANSI-N45.2.11) I 3eseter Iv*t?O
- 1. Reacter vessel 1 : A N/A 3 I
- 2. Reacter vessel support skirt 1 N/A ll/A 3 'l
'3. React:r vessel .;purtances.
1 I A N/A 3
- 4. pressure CR.D nousingretaining supports portiens 2 I N/A N/A 3
- 5. Reactor internal s-- -*- -as ,
engineeres safety features 2 I N/A N/A 3
- 6. Reactor internal st.-a:tures, otner Cther N/A N/A N/A N/A
- 7. Centrol rods 2 : N/A N/A 3
- 8. Central roc d. rives 2 : N/A :!/A 3
- 9. Core support st:acture 2 : N/A : /A 3
- 10. P0wer r::nge detector harcware 2 : N/A lt S
- 11. Fuel assenclies 2 : N/A N/A 3
!! 5:elasr ht!=r Sv?t=5 1.. Vessels level tastru.menta- 1 I A N/A a tien ecedens:ng ent..cers
- 2. Ptptng.- relief valve dis- 3 : C N/A 3
.castge and vent. Including
* -cctu rai:ef t dvus ,,
- 3. Piping, nain stean within autteard isola-m tien valve 1 : A N/A 3
- 4. Piping, feedwater with;.
in :ut::ard isolation valve 1 I A N/A 3
- 5. Piping, other within cut::ard isolatten L valves 1 : A N/A 3 !
- 6. Safety / relief valves 1 I A 12 3 .
- 7. Valves, nain stean l 1 solation valves 1 I A la 3 3 k g .
- 8. Valves, other than 1 I A 12 3 WD isolation valves and !
g within d.rpell NN':J 9. Me hanical nodules. 2 3 I N/A 3 rE N inst: mentati:n. with d 992 safet'/ functi n LSis a L3
- 10. Electrical M:dules with
- I N/A 12 3 P, safety functi:n
%gj% ,for 11. Cables, with safety
- I N/A 12 3 function
- 12. Ouencher. ischarre evice 3 I C N /A 3 J
- 13. P:psag, ::n out card saa-
;a-1:n valve to saatoff
- g 3 N/A .
,,f,
, valve ,_
3
'Ja.ves, snutoff 2 3 i-g# -'! ,, f_9 ^4 *4. I
- 15. Valves. feecwater tsolati:n 1 : A E ~3 h~^..g? ,16. Sr.N sys em
- I N/A 1: 3 n _.. . x. . 1
!!! ?actr-:3-- ?" v 9, e I t J 1 Pi;ing 1 A N/A 3 U . -Z3 l2. ?'z;s 1 I
- A N/A 3
'J ,3. Valves 1
A .:n-13 3 C .. U.
-.. M ::r . Fu 9 o t".e r I N/A . :n- 13 3 9 Ilectri:al n:t.;es. with ; N/A " 3
.N safety t :.:n:n *-'
E:
. '. _ r 2 (i.Ca:;ewitt.
t safety f n:-
- I N/A ;g 3 C. 9 l n3
(, 3 i*. trvG set and Panel other N/A N/A Non*lE N/A
' -} !3. ?PT ::: 21 3 :e a.< a r s *
- N/A 1: 3 J. 7ee::: P p swtte..-ear except Ciner tu A N/A Ncn-lI N/A
~N I?? ::: uat crea<ers wn i
J - ? .r ia.finati:na 2na ins : a:ti:ns see .7scCan 2.0
-...,4 .
,ase ,3,,,,.
. 4 dC'd
'1"~' FOR ILLUSTRATICM ONLY A-2 Revision 11
IP - Nuclear Power - Appendix A Construction OA Manual C ;NTCN Pc ER STAII;N C!aSSIFICATION C?ITERIA _ Identaficatacn ana Classificat10A gggggg PROJECT NCS. 4536/4537 of Safety-Belated Structures _,,,,,,,,,,a Systems and Ccmconents REV. 13 9-12-83 Table 3.1 - C!s ssi fiese ton of Princieal S t ru cture s . Svste=s and Cwnenents y ,,. -
~ i PRINCIPAI STRUCTURES, SAFETYJ SEISMIC d OCAI.I"Y d ELEC'*RI CAI.d IC A itEO 'MTSY SYSTE..S & COMPCNENTS (CIAJs 1,2.,(Category (dtcup A,3, gC; ass is, (App. 3 gr 3 or other) I or N/A)
IC ,0 or N/A) Non-Class N/A) 1E or N/A ANSI N18.2 Reg. Guide Reg.Cuide Reg. Guide Reg. Cuide
. (ANS-21), 1.29 1.06.ASME- 1.32(IEEE- 1.23 (ANSI-j RETERENCES: ANS-22 Section 117 308) N45.2), Reg.
ANS-23 Guide 1.64 2 (ANSI-N45.2.111 IV C C Mfdraulle Svstem
- 1. Vcided
- 2. Valves, scram discharge 2 I a lE a volume lines and contain-r.ent isolation
- 3. Valves insert and wi.th- 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 rent penetration
- 6. Paping, insert and with- 2 I B N/A 3 drawal lines
- 7. Paping, otae O the r N/A D N/A N/A
- 8. Hydraulic control unit
- a. Scram solenoid valves, 2 I D Non-1E 3 g test swatenes, and associated wiring
- b. All cther electrical Cthe r I D Non-lE 3 cenponents
- 9. Electrical :.odules, with
- I N/A lE 3 safety functica 13.Caole, witn saf ety f unction
- I N/A 15 3 ll.Ca3 water purps Othe r g N/A D Nc n- lE N/A L V Sta.dbv ti uid Centrel Svstem
- 1. Standdy liquid centr:1 tans 2 I 3 N/A 3 2.?=p 2 I 3 N/A 3
- 3. Pu p rotor Cthe r I N/A Mon-15 3
- 4. Valves, explcsive 1 I A Non-LE 3
- 5. Valves, drfsell, isolation and within 2 I A N/A 3
- 6. Valves, beyond efsell isolation valve 2 I B Non-lE B
- 7. Piping, dcwns t: 3 of explestve valve. 1 I A N/A 3
- 8. Piping, upstreas of ex;10sive valves 2 I B N/A S
- 9. Electrical =odules, with safety function
- I N/A lE 3 13.Casle, with safety functica
- I N/A lE B i
VI Neutren M0nitori c Svstem
- 1. Pip ne, TIP 2 ! 3 N/A 3
,2. Electrical mcdules. IFM
'I and AP?M I N/A lE 3 I
I?M and APFM I N/A lE 3 l3.Cacle, 4 Valves, TIP :solatica 2 I 3 N/A 3
- 5. Purge valve 2 I 3 lE 3 VII ?e seter ?retettir, l
- 1. Volded
- f N/A lE 3 i
- 2. Camle with safety functicn I l i
- 3. Vc:ded I, l
- 4. Solenc;d inverters, EPA's I N/A lE 3 i
and cut =ut c re a s e rs l l
- 15. salenoid :nverters, except 4l C t".e r I N/A Non-LE 3 i acove, and solenoid distri- I cutica panels l
'._ 16. Instru ent anverters and
- I N/A lE 3 districutten panels
- 7. Electrical rocules with
- I N/A lE 3
, saf ety f uncticn A rcr definttions and instructicns, see section 2.0 +,4 Page 11 of
';otes til anc (;j - ses page 24 FOR ILLUSTRATION ONLY A-3 povicinn 11
IP - Nuclear Power Accendix A Construction OA Manual C uss:r:CA:::s ca: n.,rA c: u.m ,.; ca nAr::a
.F __.._I PROCECT NCS. 4536/4537 Icents:sca tion .ano Glassification of Safety-Pelated structures :I SARCENT,2 LUMDY !
~*""**"*" 10 9-12 33 Systems and C:mponents RIV.
Table 3.1 - (*! a s s t fi e g t t en o f pyt-e: Sal 9trretures. M *e-s ar.d Cc recen ts PRINCIPA1. STPCCTURES, SAFI Yd S E!!'* ! Cd Ot'A!.! YJ E_LE CT9 !CA L OA SEO'v?S J SYSTE.v.S 6 COMPCNENTS (C; ass . 2 ' tcateco r f (Crcup a.3.) ic.ns 14, i i4 p . L or 3 or Ctt.ern I or N/A) C No* lass 6 N/A) I ! D cr N/A){ IE) I N/At a i ANS: N18.2 l. Re2 Calde Res.Cutde I t*teg. Cnde l Req . Cutde w a (ANS-21), 1.29 1. 26, ASME- 6 1. 3 2 (ICEL : 1. ;3 ( A:.S I-j 2 RITERINCES: ANs-22. ANS-23 Section II:l 308) l N45.2),aeg. Guide 1.64 i ( A:.S I-I
.N45.2.!!)
VII ' Lean Oetect n 3vste9
- i. TeTeerature eierent 2 I l N/A l' 3
- 2. Te-:erature and 2: f f erernal !
\ tercerature swit:nes I . , . A II 3 1 3. D;f'erent:a1 f;cw sett:5 ' '
N/A lE 3 f 2 I
- 4. Dif ferential pressure l swaten 2 .
I N/A i 1E 3
- 5. Ctf ferentral f; w su.mer &,
square foot converter l 2 I N/A 1E S
- 6. Prassure transnitter and l dt!f erent:21 p ressure 2 : 3 IE 3 trans stter .
I i . . 1 IX Precess Msdistica y miters ' 1
; I i
- 1. Electr: 21 -odules, rain I
' l l steam line, ntain.ent build:ng, fuel transfer i
- I : N/A 1 !E 3 vent plene centatn. ent i I I butiding exnaust natn t l
centrol ::cm intaxe j ! l l
- 2. Cable, wtta sa f et/ funct tni *
. : i /A 'I
' 3
' I I l
X l MP Sfste, l l l O( . - i t 8
- 1. He a t exenancers.snell side i
- 2. Heat ex:nancers,tume s;de
- 3. 7:p;ng wLtnin cat: car 4 2
3 e l i I 3 C i i N/A
/A i
3 3 l isolat;en valves ! 1 l' . , a /A 3 I
- 4. h ptng, cejend cut: card l l tsolation valves 2 l I : 3 6/A I 3
- 5. Pu ps 2 . : 3 ./A l 3
- 6. Pw p -oters
- I ./ A 1 3
I 7. Valves. solat::n !PC line 1 : A II 3
- 8. Valves tsolatten,etner 2 I B II B
- 9. Pump suction fr:m suppres-sica peol, piping, valves, includtnq tsclatten valves 2 I 3 1E B
- 10. Valves, beyond isolatica valves 2 I B IE 3
- 11. Mechantcal redules 2 I B N/A 3
- 12. Electrical odules, with I safety funct:cn
- I N/A lE S
- 13. Casle with safety functicn.
- I N/A 1E 3
- 14. Centatament spray piping and noz:les 2 I B N/A B
- 15. Suetten strainers tr.ote f) C the r I D N/A B x: - s
';w-Prassure C:re r- -rav-I i.
I L t
- 1. Piping, within outtcard : i -
I ' ' ' A '
./A 3 solat:cn valve f
- 2. Pip;ng, eycnd cat: card l ; {
l tsoiat:cn valve 2 I 3 i ./A 3
' 3
! 3. Pu. p 2 I J 3 ./A !
- 4. Pu p .oter .i
- I : , N/A ,
II 3
- 5. Valves,;solatt:n and wit:tni j i !
c o n t a ;..P e n t l
- ' A II 3
- 6. Valves, cyond cut: card 'I !'
tsolation valves ! 2 ! t 3 f II, 3 l 3 17. 3
. 7. Pu p sucticn :::n suteres-t 2 ! ; ! l i
! sten pool.ptptn:, valves. ' 1
! In:12 nng 1:c12t; n valves i ; g
- 3. E;e:trical rc.:Mes wata I
* , ; N/A II 3 l '
aatety func ::n I
). Cacle stta safet, fr: : n l ' N/A 1- 3
- 13. 3ecta:n stra:ner snote il Cther : 3 N/A 3 I
I. l, , l l 1 ! 8 Tor dettnatiers and anstructicns, see sectten 2.3 Note 1: - see pace ;4 Page .3.. Cf .,4 FOR ILLUSTRATICN ONLY . . ..
IP - Nuclear Power Construction QA Manual Accendix A Cuzs-::ri; : r aman
; cent;;;;at;;n ana Gaasificati0n l "* 7E ITS EDY l CLn: TON PCVIR STA!!::t of 2afety-Related St:; tures c- o PROJECT 3CS. 45%/b597 e".*--s " C: renents g7
- 9
- 3, y g, g
, Tsbie 1.1 - Classifiestien of Pr*.netes.1 Ott-actures, ?rste-s and C:-senent s SAFE""f d SE!E.'C0 d LrR!'iCl?AL 3 T10"*JRES, ( E ,2, (ca:egpry I CUALI"Y (Grcup A,3 ELIO*?!OALI OA E0'WN
- 6. ass .4, (App.J sr SYO!rt3 is CO:GCNI:iTS 3 or Cther) or N/A) C,3 or N/Af Ncn-Class N/A)
~
15 er 'r/A S-ANSI N19.2 Reg. Guide Reg. Guide I Ouiae 3 (A*:3-21), Reg. 1.29 Guide l1.26,ACiE. 1 32 (!III-lFeg. 1.23 (AN3I-
@ m,__"'"*,.,__ ANS-22, Secticn !!! 3Cd) N*5.2), Reg.
a AN3-23 Guide 1.6 4 (ANSI-
, N45.2.ll)
%1 lii rn-Fr* * *'l-a C:ra N r' *
- 1. Pi;ing, within cutteard isolatten valve
- 2. P1;in.;, retum test line to 1 : 1 A :;/A 3 RC:0 .:: rage tank be"end second isolation va1ve Cther N/A D
- 3. Piping beycnd cutt ard :;/A N/A isolation valve, etner 2 3 N/A 3
/ . PJ:P 2 I 3 :;/A 3
- 15. P;:p :oter *
- r/A
- 4. Valves, outtoard isolatica I 12 3 and within co n ta ir. .en t 1 : A ;; 3
- 7. Valves, teyend isolatica valves. :::or cperatec 2 : 3 12 3
- 9. Valves, other 2 : 3 12 3
- 9. Pu:p suctica 'r:s su;;res-si:n pool, pipin;, valves.
including isolation valves 2 3
- 13. Pu=p su::1:n fr:s I 12 3 RC C stcrage tank, piping, valves 2 3 12 3
, I'1.Ile:ri:al::dules,with sa ety aun:: :n * : r/A 12 3 i .
- 10. 21ectrical auxiliary equi;-
- v sen *
- T/A (3.Catie,vi-hsafetyfuncti:n I N/A 12
'?
3
- 14. Su::::n strainer (n:le f)
X:::.:~ 0 ' =9: O t.'.e r : 3 :/A 3 1
- 1. Piping, within cutt:ard 1.312:1:n valves and up to .ne rain steas 1 I A N/A 3
- 2. RC 0 stean piping, beycnd cutt 0ard isolation valve 2 I 3 N/A 3
- 3. RCIC t'artine exhaust to su;;ressicn pool 2 3 N/A f.. RCIC pu:p suctica fres 3 su;;ressien ; col, piping, valves, including isola:1cn valves 2 I 3
- 5. R:'!O ;u=p discharge to cen- 12 3 densate st: rage tand within sec:nd isolati:n valve, pi;-
ing, valves, including isolati:n valve 2 I 3 12 3
- 5. ROIC pu o dis:nirge to c:nden: ate storage ta.4 teyen Jec:nd 1:012:100 valve, pip:;, valves C her :r/A 0 Nen-i.I :;/A I
I I J . 7:r :efiniti:ns ins Inst:-20:1:ns, see Iecti:n 2.0
- .o t e (f) - see page 24 l 1
f. m j
)
i
-. Pace 13 et 24 v.s FOR ILLUSTRATIO!! ONLY n-a Revision 11
IP - Nuclear Power Construction QA Manual Appendix A
-.-.--......I i"u3 .^. .. e
%._.. 3_A e w
-..~. w.4..-,...e."L.c...--.a.a6-.d f # a-aint;; ca:;.r. ana Jiassification *e %8 g gU-PFcJE ? NCS. 4535/!.597 cf 3afety-Related Structures. * ~ " " ~
Systes a-d C:::: an u R E"/. 13 9-12-93 Tsble S.1 - Classiftentien ef Pr*n: tral Stmetures. Syste=s and Cc senent s SArr"Y d s!!!MICd C"Alin d E!.!C"?!CALI OA ?E:' C i RINCIPAL CR*.*C"".*RES, (l"aia'"1,2 (category I (Grcup A,3 Waasa s. (App.a or SYrDt3 k 00:00322.;S 3 or Otherl or N/A) C,3 or N/Ah Ncn-Class N/A) II or 'f/A t ANs: N19.2 Reg. Guide Reg. Guide laeg. Guide a (ANS-21), Reg. 1.29Guide {1.26, A :G.- 1.32 (IIII. 1.2d (ANSI-3
! "- -' _'. " - -*. ANS-22, !iection I*I 3Cd) Nd5.2) Eeg AN3-23 Guide 1.5 (AN3I-Nd5.2.11) f l
- e. 2 3 "/A 3
;7. 3. h=c;sCotor
- I N/A n a
- 9. selves, isolaticn and within
- 13. !tilves, other 1 : A n 3 2 3 n 3
- 11. h rtine 2 I !i/A N/A 3
- 12. ..lectri 31 Codules, with jai 4 y functi:n
- I :;/A E 3 l13.
- 14. 'Jacle, Su ttenwith safety(note strainer function
)
Cther I :;/A n
- a A 3
3 XIV Fu al : -it : = h :- e .
. Fuel preparsti:n caenine 3 : N /A N/A 3
. General purpose gra;;1e C nce N/A (h) N/A NjA sjA XV nate??? Ve" al '+rrita Trut--ar.
. Stea.311ne plugs C tt.e r N/A N/A N/A *r/A
'2. Or/er snd separator stren<r* cener N/A back and RFv.tead strongeack r/A N/A 3
,- ~ ri n-'/a n a! **-etee I -t-:-nt I w .' {.Centrolrodgra;;1e other N/A m) 3 N/A 3/A ri!! Fafuelin- ? ui ar.: t
- 1. Refueling e ut;:ent ;lat-f:r's asse tly 2 :T/A Non- 12 3
- 2. ReJueling : ell:ws Cther :i/A N/A N/A N/A 3 3 ell ws, blind flange and spool rieces that form a part oJ centain=eni boundary 2 I N/A {T/A 3 4 Fuel transfer tute Cther N/A N/A J/A lT/A
- 5. Isolation valves (fuel transfer tute) Other N/A D N/A :T/A
- 6. Containment ;enetraticn sleeve assenbly (fuel transfer tute) 2 I 3 N/A 3 c/::: Sterne rtuu ent
- 1. ?;el Storace Packs 2 : N/A N/A 3
- 2. :eiective Tuel 5 Orage C o..n .e. . .
3 I N/A N/A 3
- 3. In-Vessel 7ta:4 ( "tztera:7) : I N/A */A 3 XC::':vaeta *ian fl.2.n/.s.Anastneri
- 2. :-: eat ex:nsngers Cther Ctner N/A N/A 3
0
.. /A $51 N/;. s
- 3. 51;174 and v117es feming part of ::nts n=ent touncary 2 I 3 12 3
- p. 11;;ng, atner C her N/A ~;
N/A 3 iS . . :;s other N/A 3 N/A a is .1alves. fi:v centrol and filiar syste:s Other N/A 0 .an 12 s J - 7:r :eriniti:ns sna Instructi s, see Mcticn 2.3 Notes (6). (f), and th). see pa?e 24 p g4 og ;4 m FOR ILLUSTRATIONS ONLY
._- Revision 11
IP - Nuclear Power Construction OA Manual Annand4.e A CLASS!TTCA?!rs :?:?!?!A Identatacation and Giaastfication , SARGENT$LUNDY ll CLIN;CN PcwtR S:ArzcN of Safety-Related Structures, .,,,,,,,,9 PROJECT NCS. 4536/4597 Systems and Comoo<.ents REV. 9 3 11 33 f Ta Y. s 3.1 - Classifiestien of Set .eiral Structuras, Svste=s and Cemeenents e '~sie m
\ 1 Ni SAT!?Y3 S!!?MIC3 CUAL!?Y3 TtECTRICALJ!CA ?!?'MTS.J PRINCIPAL STRUCT'JRES, (Cidas 1,2, (Category I (Groun A,8,hCiass iE, (App. e or SYSTEMS & COMPCNENTS 3 or other) or N/A) C,3 or N/AD;on-Class N/A) l1EorN/A ANSI N13.2 Reg. Guide Reg. Guide Reg. Guide iReo. Guide w (ANs-21), 1. 29 1.26, ASME-1.32 (IEIT- il . S (ANSI-V ANS-22. Section II 308) 'N45.2), Reg.
j RETT!ENCES: ANS-23 Guide 1.64 m (ANSI-N45.2.11)
- 7. -Valves, other f Other N/A D Non-1E 3
- 8. .iechanteal modules
- 9.
- Pump Motors j Cther
. Cther N/A N/A D
N/A N/A Non-LE 3 N/A XX.Reseter Water Cleanup Svsten ji. Vessess t ai ter/ cumaner- Other N/A C N/A N/A atizer
- 2. Heat Exchanger s Other N/A C N/A N/A
- 3. Piptng within drywell and drywell to contatnment
?
penetratten quardptpe up 1 I A N/A B to outboard containment isolation valve k 4. Piptag frem outboard con- /' tainment isolation valve to pumps, tack to contain-ment. Excludtag pene- l tration. All piping wathini containment. Sicwdo-n l piping downstream of out- , l board containment isolattens valve up to shut-off valveu Other I C N/A 3
- 5. Pumps ! Other N/A C N/A N/A
- 6. Valves, drywell isolation valves and within drywell 1 I A LE S
- 7. Valves, beyond outboard Cther N/A D Mon-IE N/A
/"'s pa% Containment isolat1Cn
(,'
- j-i - 'i
/
5. 9. valves Mechanical mcdules Piping, return to reactor Other N/A C N/A N/A
. pressure vessel f rca in-toard centainment isolatten6 valve up to ; unction with feedwater 2 I 3 N/A 3
- 10. Piping, tetween inboard and outbcard containment isolation valves 2 I 5 N/A 3
,1. valves, centainment iso. 2 I B 1E B L2. Piping, dcwnstream of bicv-down shut-off valves to main cendenser and radwaste Other ?*/A D N/A N/A L3. T11ter/:estneralizer pre-coat subsystem Cther N/A 3 N/A N/A L4. -Sample station other N/A D F/A N/A
- 15. Nenregenerative heat ex- o ther N/A D N/A N/A changer shell and component I
, eccling water paping
- 16. Pump maters
- N/A N/A Non-1E N/A XXI: Tuel Peol Croli T and C!eanus Sys +,
- 1. Vessels, filter /lemineral-
- trers other N/A D N/A N/A i 2. Vessels, other 3,C ner I ../A I C i M/A l 3.N, A
; 3. Neat exenangers 3 I 8
C l N/A 3
- 4. Piping 3,other I N/A C,3 N/A 3 N/A
- 5. Pumps 3 I C N/A 3
- 6. Valves and piping, cuntai,-'
ment isolation 2 1 3 1E 3
- 7. valves and paping filter demineralizers Other N/A 3 Ncn-!E N/A
- 4. Makeup system, shutdown I service water system 3 I C N/A 3
- 9. Makeun to TPCC frem canden-4 g
f
, sate storage tanas Cther ./A ! D Non-13 N/A
- 10. RER Cennection 3 I C N/A 3
- 11. Tual pool ecoling pumo Other I N/A LE 3 I meters
_ g- s 12. Cacle with safety functicn *
- N/A it 3
) ',
I
. 13. Electrical medules wtta
( _,/ l
-safety functten
- 1 N/A l
1E 3 J-Fer definitiens and Instructicns. see section 2.3 Pace 15 of 24 FOR ILLUSTRATION ONLY A-7 Revision 11 __ _ _ .~ __ , _ ___ , . . _ _ _ __ __ - _ _ __
IP - Nuclear Power Construction QA Manual - Appendix A C u ss:r::AT?:r C9::Es:A 14ents:tcation ana classtfication ll $ ARGENT *duMDY q C NTCN POWER STATION of Safety-Related Structur s.
. ....o PPCJECT ';CS. 4536/4597 Systens and 0:mrenents REV. 10 9-12-33 Table 3.1 - 013sstfirstion of ?rireira l S tr.:ct* ras . Svs?*-s sed Cearere*its l'eAyr;Y2 SEI N IC3 C'_' A t. !TY O hEECTPICA!.J CA 3ro'MTS.2 /
PRINCIPAI. STRCC-"?ES. 30. ass . 2. (Cate;u y I (Gr:cP i.31 W_ ass iE. LA:P. 3 cr w SYSTEMS 6 CCMPCNE:.TS l3 or Cther) or N/A) C.D or N/A b n-Class N,A) j l l15 or N/A e
- t 2 ANS: N19.2 Reg. Gaide Reg. Guide Reg. Caide - GJide gA33 l.;? 1. 2 6. ASMD- l . 3 2 (IEEE-l Reg. 1.03 (ANSI-AN3-:.gt), . Seesten :::3:si N45.2>. Rev.
REFERENC,Si - W3-23 Guide 1.64 W.5t= L
? 45.2.11)
~~
i , XXI! 0:nt:01 Sac 9 ?snels i t. Electrical cdules, with j e I N/A lE S l safety funetten ; I 2. Cable, with safety
- I N/A lE 3 f unc tio n l I
xxii:.leest ?inals ira siews I l
- N/A a k1 . Electrical safety functt:ncdules, with I lE l 2. Cable, wata safety * . I N/A LE 3' l function ]
' i XXIV'Cf?-71s Syst*9 ,
i
'. 1. Tanas Cther N/A D M4A 3 j 2. Heat exchangers l Cther N/A D N/A . J, B i 3. Paping , Cener N/A D N/A 3
;4. Pcp s Other LA D N/A 3
- 5. Valves. fl:w control Cther N/A D ' Non-lE 3 Valves, other 6.
- 7. Votded l Cther .
N/A D f Non-iE S
- 3. Pressure vessels Other N/A D N/A B
- 9. Pt: p mot:rs "'. N/A l Cther g.
a N/ A i N n-lE xxv s% te:v, s e r.n -. w e -r n . --- s ! i i
- . . r- , _- : -- .. - i, I
- t. Platn, l 3 I' : C N/A '
3 I l 2. Peps g 3 l
! C N/A i 3
- 3. P2 p rotors *
, I ! N/A > 10 ; 3
.4. valves. 1831a t te n 2 I 3 LE 3
' 5. Valves, other 3 I C lE 3
- 6. Elect tcal =cdules with
- I N/A lE S safety function
- 7. Cable, with saf ety functioni
- I N/A lE S XXVI: Plant Sernee wster syste-s fer . rer recses
- 1. Pipin, and valves, other Other N/A D Non-lE N/A
- 2. P=p s Other N/A D N/A N/A
- 3. Mot =rs Other N/A N/A Non-lE N/A XXVI:: !?str*r ent 3ra n ta tr7 a-1 Sar-vi:? Air _7s s i I i
' 1. Ves sels . a::=ula su.;0rtin? t: s
$-R syste s j 3 I C 1 N/A l 5
' 2. P t atng 6 Valves in lines bet.. l ' '
2.: .aters s 3-R syste.-s 3 C j iE '3
,3.
- P1;tne s Valves fa. ming I
l
, part o f centatn ent oeze.ary 2 I 3 ! LE ! 3
- 14. C ntroi Peen I. er;ency j l l 3restatn2 Ai r Cther I C -
lE ! 3
- 5. Femaining AAr systems.N-s-R Cther N/A D Non-iE N/A l
i 1 1
! l l
1 - T.' :: 0;u =1 9-a-iter ~*ta s i i l , I 4 I
- 1. Tuel lav tants ! 3 ! ! ! C l N/A 3
- 2. Otesel d;ei at: rage tanas 3 i'
- C i N/A l 3
- 3. Pt;tni ara valves, feel , 3 : , C '
lE 3 cal syste, I i
- 4. P2 s, f.el 011 transfer 3 i . s. mA 3
". Pu o .Ot:rs, fuel oli I e I i I
7/A l' lE 3 trans:er s y s t a., 1 I i l l J F:r defintti:ns and .rstructtens, see secst:n 2.3 scia .4> - see ;a s 2 4 Pi e 16 :e :4 FOR ILLUSTRATICN ONLY ,
;_; Revision 11
IP - Nuclear Power Construction OA Manual AnrmM i x- A l CLASS:r:CATIO's CFITERI A - C L;;. !r.,:4 et..Ed a ;A!! u:4 IdentAsication and ClassificattCn gyggg PRCJECT NCS- 4536/4597 o f Saf ety-Rela ted Structures .L '~ Systems and Ccmcor.ents
?IV . 8 7-03-11 Table 3.1 - C?nstificitten of Principal s*ructures. Svsters tnd Cc cocents I i P RINCIP AI, STRUCT';RES , SAFE M S EISMICJ OUAr.I M Q.ECT?!C' 913 m .uTsJ S YSTE.*.3 6 CCMPCNENTS (Class 4,2. (ca te go ry (Grcup 4,3,j sc;ada .6,,iApp, a er 3 o r C t.he r) I or N/A) IC,D or N/Al{ Non-classi N/A) i 1E er 'UAl 8
, ANSI N19.2 Reg. Calde Pe1.Cuide !e P eg. Ca&de, Reg. Calde a ( A?.S- 21) , 1.23 1. ; 6, A.:ME- l 1.32(IEEE-.1.;s ( A;.S I-3 RITERENCES: ass-22 Section !!! 303) N45.D.Jeq.
A:.5-23 I 2 cas de 1.64 ( A'.31-
?:4 5. 2.11)
- t esel (*-arit o r Sys teas (a nts) l i
- 6. Starting Aar System ;
- a. PLpang, valves a tanks 3 I C -
IE 3
- b. P&ptng 5 valves unstrea l o f enees valve between , other I D i Non-!E WA c rpressor and atr l recetver
- 7. Diesel generators 3 I N/A LE 3
- 8. Diese L 4enerator exhaust 2 I a N/A 3 to butldtn7 tcunda Y ,
- 3. 0.C. exnaust outstce of Cthe r N/A N/A N/A N/A building boundary
- 10. Vonded *
- 11. 21ect rical modales , wt ta
- I ./A l :.E 3 safety functicn l
- 12. Caole.with aafety functs:n . I ?v A i 1E 3
- 13. Diesel encane ecoling water system 3 I C IE 3
- 14. Otesel engine lubricatten system 3 : C ;E 3
- 15. C .mbustten a tr sys tem 3 I C N/A B
- 16. Air dryers 6 associated paping, centrola 6 c. tale s Cther N/A D N/A N .* A XXIX. Standby Cas Trestreit Systa,
- 1. Filter untts 2 I N/A N/A 3 9- 2. Att Ftptna
- 3. Cable with safety functten
- 4. Tans /::2.*pers
- 5. Electra: neaters, instru-2 2
I I I s/ A
. s N/A -
I LA lE II 3 3 3
- tentatten 6 contro1*vtta 2 : N/A l lE 3 a sa!ety !unctien XXX Pevar Crnvers ten sys t=m
- 1. Mata stea., ptptng frc:3 2 I 3 N/A 3 second isolatten valve to
& including first shutoff valve
- 2. Main steam branen piping 2 I 3 N/A 3 between the second isola-tion valve and the first shutoff valve, frcm branch potne at main stea:s piping to 6 including the first valve in the branen line ,,
- 3. Main s team ptp t: q between C the r N/A D N/A N/A
- the sautof f valve 6 ene turoine natn st:p valve
- 4. Turstne bypass ptptnq C ther N/A D N/A '* / A
- 5. Main steam cran:n ptptne Ctner N/A D './ A 'U A tetween tne first sautoff e i valve dcwnstream of tne I se n1 isolatten valve 6 g tne tur tne sin st:p valves -
- 6. "'ur:tne st p valves,turcanei Cthe r N/A D NCn-l: 'U A '
- I centr:1 valves 6 turerne bypasa valves :
- 7. Main steam Leads frem Other N/A D N/A .'A tur=Ine c:ntr:1 valves to l tarctne castn2 1
- 3. Teacwater 5 c:n dens ate systal Cther N/A D SCn-lE ,A te'/Ond enard .sc.ata:n 'eal.n j 1 Tur:ane generat:r I Cther './ A N/A N0n-lE -A 13 C ner './ A D N n-lE ,s f . Valves, outer cst instrisolata:n entata:nvalve cerndi I
s a J Ter de:Anittans anJ anatre:ttens, see aec tten 2.J
'r tc.s d i and t ') , ree P re 2 4 E 3" O E4 FOR ILLUSTRATION ONLY A-9 Revision 11
IP - Nucl. car Construction QA Manual Append.tx a, C* ASS!?! OAT!^'t C?!?!?!N i- a Icent at icatacn and Classif teation !SARGENTMUDY ! 'N of Saf ety-Rela ted Structures, >
. ...J pp""*"Ca'45367' C' *F.m'i P%'E R S"Pia 7 sys?==s ied Teacomants P E'/ .10 9-12-43 '
O Table 3.1 - Cla ssific3 tion of ?rinciral S t ruc tu ras . S v s t e.a s ird C mroments I i t S W *YJ I SE!!M!CJ : CUAI.!TYJ (Class 1.2. (Ca ta cc r */ U houp A,3 [E'.EET*!OA*.3 8 ?E0*MTS.J CA PRINICIPAI STRUCT"RES. SYSTE:4S & CCMPCNENTS .a cr
, 3 or Other)l cr N/A) 'C,0 or N/A)j tJiass .Non-Class 4 E, , Ll N/A) A::p. t 1
b :lE cr N/A I I j E ANSI N18.2 Reg. Guide Reg, Guide i Reg. Guide ) Reg. Cuide , I S
'f ANS-21) , 1.29 1.26, ASME l.32 (IEEE-il.23 (ANSI ,l RET ERE'""S
" ' '
- 3*CE10^ II
- ANS-23 l
l N * '1.64
;Cnde j (ANSI-l .
N45.2.11) I i l XXX;. Powar Cenversion Svsta.9 (cont.] , 4 i , e
' 11. Condenser j e l I k other N/A N/A N/A
! 12. Air e:ection eculpment ; N/A i Other N/A D I Ycn-l: N/A
' 13 . Teedwa ter trea t:.ent sy s te.*.; Other N/A l l ' 14 . Turbine bypass system . D N0n-LE N/A Other i
I N/A D N0n-lE l beyond turbine bypass N/A j valve ; s I l t 15; Turbine gland sealing Other N/A D Non-lE e l syste.9 ccmponents N/A e 16. Heater drain piping Other
- 17. Heater crain valves N/A D N/A N/A Other i N/A D Non-LE
' XXXI ECCS E:uta-ent Area C:olins N/A I i. ians. . a ctwors watn f safety function I l 3
j g 2. Heat exchanger pressure re= I N/A I lE 3 3 l C l
)
tainteg ecmconents & vales I i I N/A l 3
- 3. Instrumentatien and con- 3 '
i I ! N/A
- i 4.
trol watn safety function , I 1 T. 3 e i Electrical modules 6 cable. *
' I j N/A 15 L
with a safety function i I 3 XXXII; Ce-ia sata Storiaa and Tri-sfer\ * ! ! l 1. AC;C concensate storage Other N/A l ( tanks l l' D l N/A N/A i I 1
- 2. Condensate stcrage tanks ! Other l
, 3. Piptr.g and valves N/A } D ) N/A i M/A
! N/A 3 : NCnalE '
N/A l
- 4. Piping and valves con- l Ocher 2 I 6
B ! lE 3 j tain:ent penetrat;or.s i
- 3X:::: Auxillarr we ?avar ?vstc I
- 1. All ecut; ment .- _*/* y
- f r Operation - } 4 N/A II 4 3
f 7 Class 2 Mechan. 4 ~ bjt e ,
- 2. All eculpeent ni essary
- for operation of Safety l I N/A lE B Class 3 Mechanical Systemsl
- 3. Cther Auxiliary A-C Power Other Equipment N/A N/A NCn-lE N/A '
l , I ! ; XXX:7 Miscella eeus Ce- conents l h1. Containment polar crane 3 N/A Non-lE g 2. I Tuel 3u11 ding Crane 3 N/A f 3
- 3. Turbine Building Crane I ':en-lE 3 Other N/A N/A Non-lE N/A XXX*/: Civil structures '
' t Cantairrent l.
- 2. C*,03 structure N/A I, I !;/A f :UA ! 3
- 3. Aux:,liary butlhag N/A e : 14I . M/A ; N'A . 3 4 Tuel tuildana NfA l ! N/A t N/A ' 3
- 5. Control building NjA i I M/A N/A j 3 a 6. Diesel genera tor and M'/AC NfA 3 I N/A N/A r 3 building N/A I N/A N/A l 3 t . ,
, - 7 Padwaste sucstructure '
i i ! 3. Circulating water screen NfA I N/A N/A 3 N/A N/A l house . I ! N/A : 3 ' i ' 9 i Turbine building N/A N/A
- 13. Cff-gas building l, f N/A 1 A '
N/A
- 11. Service tuziding NfA /A . N/A I N/A /A i N/A N/A N/A j i12. Ultimate heat str< l N/A .A a 13. 3adwaste building . cove [
NfA : - N/A j /A
, 3 i grade N/A '
N/A N/A l N/A I N/A
! t 14 ? ?'I Pedestal '
- i N/A l
% 11. Sa f e ty-related .?.ssenry 9~ fA l ; './ A i 3
~* alls iO N/A ; l
- 16. Tuel pcols 6 pcol liners
; , N/A 1 ./A 3 N/A : I ! N/A l l */A i 3 l
i
. - I '
'I
' J-Tcr definttiens and in s t ru:;1c ns , see sect:an 2.3 t
rat. 4) . s** pace 24 P 50' II Of 24 FOR ILLUSTRATION C::LY A-10 Revision 11
IP - Nuclear Power Construction OA Manual AnnnMi. M class:r:CA::cs ca:TE9:A c;;NT N etwea 2:A::;u li.ntliacacicn and Claalificition SARG TSLUMOYN 'RCJECT " ** 4526'4587 of Safety-Related Structures Systems and Components REV. 10 9-12-83 Table 3.1 - Clas s 2 fication o f Primetcal S t ructures . Svsta.s and Cemnonents
,* PRINCIP AL STPECTURES, SATETY# SE!!MICJ CUALITYd E LECTRI CA L#f.0A 3EO'"TSY SYSTEMS & CCMPCNENTS (Class 1.2. ( Ca t e go ry (Group n,3, LC14=s ;E.iinpp. a ur 3 o r C Lhe r) I or N/A) Non-Classi N/A) lC.D or N/A) 1E or N/Al ANSI N18.2 Reg. Guide Reg. Guide Reg. Cutde Reg. Cuade
$ (ANS-21), 1.23 1.26,ASME- 1.32(ICE - 1.23 (ANSI-1 REFE RENCES : ANS-22, Section II: JOS) N45.23,Feg.
3 ANS-23 Cuade 1.64 (ANSI-
. N45.2.11)
- Ccc/I Cthar Structures
- 1. Those supporting or protec-ting safety related equip. N/A I N/A N/A 3
- 2. Cacle trays s tray hangers, conduit 6 cenduit hangers in Seismic Categcry I areas. C the r I N/A N/A 3 lCCc/I:! Miscella neou s
- 1. Ccmponent cooling water sys. 2/3/Cther I.N/A s/C/D II,Non-!E a.N/A
- a. Valves & ptptng centatn-ment isolation 2 I B IE 3
- b. Valves & piping for supplying shutdcwn ser-vice water to the fuel pool heat exen ange rs 3 I C IE 3
- c. Valves 6 piping for supplytnq service water to the RR pu=ps seals Cther I C II 3
- d. piping & valves Other N/ A D N/A N/A
- e. Heat excnancers Other N/A D N/A N/A
- f. Sterage tank Other N/A D N/A N/A
- g. Instrumentaticn 6 cont 2:Is with safety function 2/3 I N/A 1E 3
- 2. Turbine building, closed cooling water system C the r N/A D Ncn-1E N/A
_ _ . 3. Shutdcwn service water equ:prent area cooling i
"')' a. Tans, ductwors & valves with safety functica
, 3 I N/A 1E 3
- b. Heat exchanger pressure-retaining ccmponent's &
valves l 3 I C i N/A i 3
- c. Instrumentatica a centrol with safety functica 3 I N/A 1E 3
- d. Ilectrical modules & caolas witn safety fcncticn
- I N/A 1E 3
- 4. Switchgear heat removal
- a. Fans, ductwork.darpers &
valves with safety e xni=n 3 I N/A 1E B
- b. Heat exchanger pressure-retaining ccmponents 4 valves 3 I C N/A B
- c. Instrumentation & centrol with safety function 3 I N/A lE 3
- d. Electrical rodules & cablez with safety function
- I N/A 1E 3
- e. Refrigeration piping with safety f unction O ther I N/A N/A B
- 5. Ccatrol Room HVAC
- 3. Tans. fan .otors, da=pers, ,
~~
ductwor',s valves, water challer, entiled water l l puros with saf ety $2rtics 3 I i N/A 1 . 3
- b. Heat exenanger pressure- , !
retaining ccmpenents and valves ' { ' 3 '3/A 3
- c. Electric heaters instru- j eental & centrcis with .
I safety fanctica 3 I l N/A 1E 3
- d. Electrical mccules 6 ' l caoles with sa f e ty e.rct1=s
- I N/A 1E 3
- e. Tilter units 3 I N/A 1E '
3 i l
. i I.
I I A Tor defintstons and instructicns, see secticn 2.0 pase 19 of I4 FOR ILLUSTRATION ONLY A-11 ffe. . . . vision 11
IP - Nuclear - Construction QA Manual . Accendix A. C:.assiricar:cs e,ir ara cListen ecwea star:cu Identa t Acat wn and Gaas tf icataun og Saruty-kulated Structa' rcs y g' L*ltVR.CT NOS' 4 'a lf*/ 4'e9 7 Systems and Ccmponents 'l~-~~~'***"""****" REY. 10 9-12-83
- m. 4
[> l Table 3.1 - Class t fiestt en of orineteal S t ructures . 'Jystems and Cornonents v. PRINCIPAt. STRUCTilRES.
$YS1LMS & CcMPCNENTS S A? E""YJ SEISMICJ OUA!.ftvd 1:f#C?DI CAld a RQ'M (Class . 2, ( Ca tu go ry ; ( 4 ,up ...u l l ass-{
3 or Ctner) I or N/A) C u we N/Al Non-Cla{s.15p. n N/A)a or 1E or N/Ap
, ANSI N18.2 Rec. Cuade Ren.Cuide fteg . Calce Rei. Cando
- a LANS-21), 1.29 1.26.ASML-4 1.32(11.II- 1.23 (ANSI-d REFERENCES : ANS-22. Section II: J08) Ih45.23.ceq.
3 ASS-23 Cuade 1.64 (ANSI-I .N45.2.11) 56 . Diesel Generator KYAC '
- 4. Tan and ducrwcrx with !
safety functran 3 I N/A 1E 3
- b. Ins trumentation & cent =::1 1 with safety function 3 I N/A i 1E 3
- c. Electrical modules s caalasi
- with safety function
- I N/A 1: 3
- 7. C =bustible gas control system cooling
- a. Tan, dirt.crt w/ safety fmc. 3 I N/A lE B
- b. Heat exchanger pressure-retatning e. . ants 1 salves 3 I C N/A B
- c. Instrumentation & controll with safety funetton i 3 .
I N/A 1E B
- d. Electra:31 =cdules & cables '
i wita safety function
- I N/A 1E 8
.C<rII: Mtseellar.cous feert.) '
l { 8.' Fire protect:sn system Other N/A N/A Mon-1E 3
- 9. Standby Cas Treat-.ent Systert Equiptent Area Cooling
[~') ( j
- a. Tan t ductwork with safety funct:en j N.s 3 I N/A . IE 3
- b. Heat exenanger pressure ;
retaining ccrponents " 6 and valves 3 I C l N/A 3
- c. Instrumentata:n & con- .
trel with safety function ' 7 3 I N/A ' 1: 3
- d. Electrical ecdules and '
casles with a safety function
- I N/A 1E S
- 10. P.SIV Eeakage Poom Cooling
- a. Tan & doctwork with
. safety functicn 3 I N/A 1E 3 *
- b. Heat exchanger pressure retaining 'ccmponents and valves 3 I C N/A 3
- c. Instrumentation & ccnt:01 with safety f uncticn 3 I N/A 1E a
- d. Electr: cal ecdules and cables with a safety functica
- I N/A 1E S
- 11. Metecrole;1 cal :ata
-- i
, Cs11e:ti:3 Iqut; ten t C ther N/A N/A Non-1E N/A i i
- 12. Pcstaccident Sarple System
- a. Jarple analysts panel Cther N/A 3 Mon-1E 3
- b. Sample =catter panel Ctaer N/A N/A i Non-1E 3
- c. Closed 1 cop ccoling !
system N/A N/A 3 l Ncn-1: B
- d. C:ntainment isolatton valves l 2 I 3 i 1: 3
- e. Sarple bicct and bac's flusa valves C the r N/A S j IE 3
- f. Crywell ficor and equip-y rent drata su=p sample. .
p urp Ciner N/A 3 l Non-1E 3
- g. C:ntaan.ent f!:or and ! l eqat;nent drain su p I sa ple purp C tte r '. " A 3 Ncn-1E 3 i
C h 1 - t i i
\._/ !
l l
# rar definttiens and instructacns. see secttan 2.0 page 20 of 24 FOR iL L U :5 I Rit .10.. v..w li-12 Revision 11
7_ IP - Nuclear Power Construction OA Manual Annendix A CIAsSIFICAt!UN CRITERI A - C1.ANTON Pt eut.M sTATit,N Ident sfication and CIJ sst fication I~"~~-' PHW CC7 N@- 4 'J 3 b/ 4'49 7 of Saeety-setaceo Structures Systems and Components "[$ARGENTRUNDY] C- 3 REv. p 4 27 84 f G - Table 3.1 - Classification of Principal Structures. Systems and Comonents
\ 2 .
\ /.
PRINCII'AI. STftUCTtlRES, SAFE M SEISMICJ OUA!.t TyJ r!AC"ruicAIM ca ug-Q'wTsd SYSTEM $ h CCMPONCNTS (Class 1,2, (Ca tego ry ( 6e ,up A,3 ( C 1.e a s 16. . [Ah s. J ur 3 or otherl I or N/A) e,s> or N/A)- Non-C1.aari N/A) It! us N/A ANSI N18.2 Reg. Guido Reis.Cuide lieg . Cutdu Heq. Cuade
. $ (ANS-21), 1.29 1. 26, AUNic- 1.32(1u:1.- 3.23 (ANSI-4
REFERENCES:
ANS-22, 1 ection 11d J05) N4b 2).keit. N ANS-23 Cu t tle 1.64 (A.W1-N45.2.111
- 13. Pcstacendent Mcnttoring Syster:s
- a. Piping, wtthin contain-ment pressure boundary and/or with post LCCA function 2 I N/A N/A 3
- 5. Valves, within contain-ment pressure boundarf and/or with post u:CA functten 2 I- N/A 1E 3
- c. Electrical and instru-mentation modules with post LCCA function 2 I N/A 1E 3
- d. Cables wath saf ety function 2 I N/A 1E 3-
- 14. Equipment for E:rergency Response Facilities N/A N/A N/A Non-1E 3
- 15. Fuel Butidina sivAC system dampers and ductworn witn safety function 3 I N/A 1E 3 ric.ill C.--tus tible c s s C:ntrol '.,ys te.m '
' 1. !%~xen *cxxr*.sirer systas
- 2. coow reen. / dry.eil purte sys
~[ T
- a. Dr/well Purge Filter Cr.tts
- b. Cuctwork Cther Othe r I N/A Ncn-LE N/A
; ("-
I N/A ' t'en*1E N/A
# c. Pcst-ZCA Purge (Each; 2/Cther I 3,::/ A 1E/icn-1E 3 to Hydrogen Recenciners) 11 Valves, Piping? Cuctwork J. '"catairment/drywell sixing 2 I 3 IE 3 systen
- 4. Contair.,ent/drywell :tont-toring system 2 1 3 it 3
- 5. Electrical :-cd les with safety function
- I N/A IE B
- 6. Vacuum relief syste:3 2 I B IE B T*%IX Sup;res sion Pcol Malte-ue Syste- t i:0
- 1. SM piping 2 I B N/A 3
'. SM valves with safety function 2 I B 1E 3
- 3. Electrical medules with safety funciten e g N/A .lg 3
- 4. Cther valves Cthe r I B !!on-1E 3 x:, Auxiliarv Oc 7ever syst m
- 1. Otvistenal tatteries, enar;e and distratation panels e g N/A 13 j, 3
- 2. ::cn-divisicnal hatteries.
chargers and distribution panels Cther N/A N/A ::en-12 ;;/A X:,I Sc;;ragsten F?ol Clein a-
- i v s t e .aio
- 1. Pt; tag 6 valves ferntng part of centaterena scur.dary 2 ! 3 1r 3
- s. Grear ninero 4 velvas Cthe /A 3 *onalE ::/A I l I
i 1 h G ! Ov l l. - A For Jefangtsons and instrwet cns, see sectten 2.J Page 21 of 24 FOR ILLUSTRATIOI O.';LY A-13 N M%, P A 99 $
.- .- . _ _ . -~ . ,
u - M1 Clear t'OWer Construction Qn danual ADpenC1% a l c:.us :F:eA: ton ent=s: A ' ~ ~~~__, e:.tNn.N ma . s r.u t o . IusnLa s teaLaon and C; ass tfication ' l'HOJ t.CT NGs . 4 ', Jt./.5 0 4 7 of sarety-setatea Structures ! SARGENT?iLUNDY'l} Systufns and Ccmoonents I ~~'"""*""***d REV. 11 A-27-34 Table 1.1 - C!assification of Prineical Structures. Systems and Comnonents . rv ( i
~ '%./ PRINCIPA1. STRUC"'URES, S AFE*"Vd J O UA L. t TYJ CIICTP t t'Af
~ y G ut. s'.H, ~ U a l "~I C' I QApte. A R tr.i ' *rN'.'
l SYSTEMS 6 COMPONENTS (Class i,2. (Ca SEISMIC teco ry a w a' l J or Othern I or N/Al .C.is or N/Al{ Non -(' t.t s k - N/A)
! l 3 l LC or N_/A. - -
k , , ANSI NIS.2 Reg. Cuide Itco .Cu a rte Hen. Ca tste H. t . C u t aa.
. w (ANS-21), 1.29 t.26.ASML- 1. 3 2 f i t s.t.- 1. 3 ( ,m s t .
-3
REFERENCES:
ANS-22, St.ct ton II: 10 8) N4b2).Meo. l ANS-23 3 1.b4
. I Giuta t l a.ANs 45.2.11) t-e XI.II ' Oemineralizer Malce-to Svste-i
- 1. Piping and valves other N/A D Non-LE N/A
' 2. Tanks Othe r N/A D N/A N/A
- 3. Tilters other N/A I D N/A N/A
- 4. Pt.='ps and moters Cther N/A D Ncn-1E N/A
- 5. Pretreated filtratton c:=ponents . Other N/A D Non-1E N/A
- 6. Cemineralizing train conponents Cthe r N/A D Nca-1E N/A X:111 Main Stesmline Isolation va.ve Wasa:e C:ntrol T/stert i 1. Piping and valves up to the '
first isolatten valve of the intcard sutsystem 1 I ! A 1E 3 ( 2. Piping and valves, other' 2 I 3 1E 3
- 3. Sitwers/=otors I i N/A 1E 3
- 4. Heaters Other I I N/A 1E 3
- 5. Electric =cdules with I safety function
- I N/A 1E 3
- 6. Cables with safety function
- I N/A 1E S l
X. VI C:ntat ent Nelatt:n --
} %-[ . 1. Piping between the inside i 2 1 ,
3 1E 3 and cussade contat. en isolatt:n valves including d the tsolatten valves f or
'syste s with no safety functicn watch penetrate the centainrent
- 2. Contatn=ent penetratien 2 1 3 1E B asse-alies
- 3. Crivell Cuardpipe Se11cws Other I D N/A B 11 (1)
Notes (2) All inspecti n records shall be .aintained for the life of the plant. These records a sna11 include data pertaining to qualification of Inspectt:n persennel, examinatica procedures, and examination results. f(3) A pr grimped devel of quality assurance 37 Jartent 6 : c.cy .require This pre:entstunicue ram is discussedto fire protection in detati inhas been Project
- nstructica P*-CP-015.
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IP - Nuclear Power Appendix B Construction ~QA Manual
,3 \.j APPENDIX-B Revisions to the IP Nuclear Power Construction Quality Assurance Manual Revisions to this manual will be distributed per Nuclear Planning and Support Procedure NP&S2.51. Controlled Distribution of the Manual is the responsibility of the IP Manager-Nuclear I
Planning and~ Support. Persons who are assigned controlled copies
-of the manual are responsible for maintaining them in accordance with the-following:
- l. For each revision issued, the manual holders will receive the revised material, a page tester, and an accompanying transmittal which will contain a detachable receipt _to be signed and returned to the Nuclear Planning and Support department. This will verify receipt of revisions.
n 2. .When revised material is provided, the obsolete material in
, ) each controlled copy shall be removed and destroyed by the assignee.
- 3. Requests for copies of the Construction Quality Assurance Manual shall be directed'in writing to the IP Supervisor -
Nuclear Records. All requests shall be authorized by the IP Manager-Quality Assurance. qqppe ;' ug u%gg g\J B-1 Revision 12
l , IP --Nuclear. Power- ' Appendix C
-Construction;QA Manual
- m.
- b APPENDIX C Y
SUPPLEMENTAL APPLICATION 11P NUCLEAR; POWER CONSTRUCTION QUALITY ASSURANCE' PROGRAM t 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 I established in writing and executed for activities affecting the safety related function of designated structures,-systems, and r- : components- to an extent consistent with their. -importance .t:o .
. safety. Table 3.2-1 in the Clinton Power Station FSAR identifies specifically those structures, systems, and components that are
[ ~important to safety. b Fire Protection and Radwaste/ Augmented-D systems are specifically i' identified in Table 3.2-1 of the CPS FSAR and/or highlighted-in several Regulatory Guides that' define and clarify their impor- - tance,.to..the plant. Regulatory Guide 1.120, " Fire Protection Guidelines for Nuclear 3 ! Power Plants," Revision 1-(November, 1977) states that "A quality
. assurance (QA) program is:neededito identify and rectify errors.
4 in design, construction, and operation (of a fire protection * - system).~and Lis an ' essential part of the defense in depth". , Regulatory Guide 1.143, Revision 0 (July, 1978) states that, "to i- ensurefthat systems.will perform their' intended function a 3
. quality assurance program sufficient to ensure.that all_ design,
~
e construction, and. testing provisions are met should be estab-lished and documented." Y j 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, d
! w C-1 Revision 11-
IP - Nuclear Power Appendix C Construction QA Manual 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 4
- 15. YES YES
- 16. 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.
4
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