ML17325A217

Updated QA Program Description for Facility

ML17325A217
Person / Time
Site:	Cook
Issue date:	07/31/1987
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17325A216	List: ML17325A215 ML17325A217
References
NUDOCS 8707240306
Download: ML17325A217 (120)

Text

DONALD C.

COOK NUCLEAR PLANT.

UNIT NUMBERS 1 AND'2 4

DOCKET NOS. 50-315 AND 50-316 LICENSE NOS. DPR-58'AND'PR'-74 UPDATED QUALITY ASSURANCE PROGRAM DESCRIPTION, FOR THE DONALD C.

COOK NUCLEAR PLANT JULY, 1987 Prepared by the AEPSg Quality Assurance Department APPROVED BY:

AE anager ua.sty 'surance IIÃCO Controlled

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QUALITY ASSURANCE PROGRAM DESCRIPTION FOR THE DONALD C.

COOK NUCLEAR POWER PLANT TABLE OF CONTENTS Section 1.7 1.7.1 1.7.2 1.7.3 1.7.4 1.7.5 1.7.6 1.7.7 1.7.8 1.7.9 1.7.10 1.7.11 1.7.12 1.7.13 1.7.14 1.7.15 1.7.16 1.7.17 1.7.18 1.7.19 Appendix A Appendix B

Title igure 1.7-4...........................

Fgure 1.7-5...........................

Regulatory and Safety Guide/ANSI Standa AEPSC/ISMECo Exceptions to Operating Ph and Regulatory Guides..................

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ase Standards Table of Contents Quality Assurance Policy for the Donald C.

Cook Nuclear Plant Quality Assurance Program...

0rganization..............................

Quality Assurance Program.....".........................

0 4

esign Control.........................................

Procurement Document Control...........................

Instructions, Procedures, and Drawings....

Document Control..........................

Control of Purchased Items and Services.......,.........

Identification and Control of Items'....................

Control of Special Processes.......'....................

I 4

nspection.......................................

est Control...........................................

T Control of Measuring and Test Equipment................

Handling, Storage, and Shipping........

Inspection, Test, and Operating Status.

Nonconforming Items....................................

Corrective Action......................................

Quality Assurance Records...................'...........

udits.................................................

A Fire Protection QA Program.............................

Figure 1.7-1...........................................

F 1

'7 igure 1.7-i........

Figure 1.7-3............................;.......;......

~Pa e I 1.7-1 1.7-3 1.7-33 1.7-41 1.7-46 1.7-49 1.7-51 X.~-S4 1.7-58 1.7-59 1.7-62 1.7-65 1.7-67 1.7-69 1.7-71 1.7-73 1.7-75 1.7-76 1.7-78 1.7-82 1.7'-89 1.7-90 1.7-91 1.7-92 1.7-93 1.7.A-94 1.7.8-98

July, 1987

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1. 7 QUALITY ASSURANCE AMERICAN ELECTRIC POlN ER Company.

Inc.

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W. S. 8'HITE. JR.

Chairman ofrhe Board and Chief Executive Ogicer cdlep 'ss-Isoo r'I Rivcrsidc'laza (614) 223-1000 P.O. Box 16631 "

Columbus, Ohio 43216-6631 STATEMENT OF POLZCY FOR THE DONALD C.

COOK NUCLEAR PZANT QUALZTY ASSURANCE PROGRAM4 I,

4 4

POYYCY American Electric Power Company, Znc4r recognizes the fundamental importance of controlling the design, modification'and operation of Zndfana 8 Michigan Electrfc Company's Donald C. Cook Nuclear Plant (Cook Plant) by implementing a planned and documented Quality Assurance-Program, fncluding Quality Control, that complies with applicable regulations, codes and standards.

The Quality Assurance Program has been established for safety-related activities performed during the operations of, or in support of the Cook Plant.

The Quality Assurance Program supports the goals of maintaining the safety and reliability of the Cook Plant at the highest level, and conducting safety-related activities in compliance with applicable regulations,

codes, standards and established corporate policies and practfces.

4 As Chairman of the Board and Chief Executive Officer of American Electric Power Company, Znc4r Z maintain the ultimate responsibility for the Quality Assurance Program associated with the Cook Plant.

Z have, delegated functional responsibility for the Quality Assurance Program to the American Electric Power Service Corporation (AEPSC) Vice'Chairman-Engineering and Construction.

He has, with my approval, delegated further responsibilities as outlined in this statement.

ZMPLEMENTATZON The AEPSC Manager of Quality Assurance, under the direction of the AEPSC Vice Chairman-Engineering and Construction, has been assigned the overall responsibility for specifying the Quality Assurance Program require-ments for the Cook Plant and verifying their implementation.

The AEPSC Vfce Chairman-Engineering and Construction has given the AEPSC Manager of Quality Assurance authority to stop work on any quality-related activity that does not meet applicable administrative, technical and/or regulatory requirements.

The AEPSC Manager of Quality Assurance does not have the authority to stop unit operations, but shall notify appropriate plant and/or corporate management of conditions not meeting the aforementioned criterfa, and recommend that unit operations be terminated.

Revised 4-I5-85

" 1.'7-1

July, 1987

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The Vice President-.Nuclear Operations and the Executive Vice President and ChiefEngineer, under the direction of the AEPSC Vice Chairman<< Engineering and Construction, have been delegated responsibility for effectively implement-ing the Quality Assurance Program.

~ The Donald C. Cook PIant Manager, under the direction of the AEPSC Vice PiesidenE'-'Nuc1ear Opera'anions, i's'delegated the responsibility for establishing

'- Cook.~plqnt gua+gy CoqtroI:,and~implementing the Quality Assurance Program at

. the Cook Plant.

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~,t; The= AEPSC.panqger,,pf Quality Assurance is responsible for providing technical direction to the Plant Manager for matters relating to the Quality

• Assurance'Program

'at'-'tho'ok 'Plant.

The AEPSC Manager of Quality Assurance is

- ~a2soresponsible"-for maintai~ng y Quality Assurance Section at the Cook Plant to perform required reviews.and audits, and to provide technical liaison

<<>>'edki ces~'to-the i Plant'anager.

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'The implementation of the Quality Assurance Program is described in th& AEP9B General -Procedures and subtier department/division procedures,

%I'" D."Cook Plant. Manager's Instructions (PMI) and subtier Department Head Ins'6ructions and 'Procedures, which in total, document the requirements for implementation of'he Program.

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, Each AEPSC and,Cook Plant organization that is, or becomes, involved

in'afety-'related ACt'ivities for the Cook Plant has the responsibility to

~ ~wP r'mplemen't pthe,go2xcies'nd',requirements of the Quality Assurance Program

~<'--"',~.that are applicable tio,thpir respective area(s) of responsibility.

AEPSC

>""and'Cook'PISnd'per's'onneI'involved'in safety-related activities shall be

'geZamitliar.with',-'and:.comply:-.with',

the requirements of the applicable Quality

<. Assurance Program.requi remits.

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g., )p,ZOMPLIANCE R"~"'he AEPSC Manager of Quality Assurance shall monitor the compliance

-,.with.the established Quality Assurance Program.

Audit programs shall be established to ensure that AEPSC and Cook Plant activities comply with established program requirements, identify deficiencies or noncompliances, and obtain effective and timely corrective actions.

, Any, employee.,engaged Lin saf'ety-related activities who believes that

-'th'e Quality Assurance Program is not being complied with, or that a deficiency

'-in:quelled'y existsi'-'should n'ot'ify his or her supervisor, the AEPSC Manager of

- Quality Assurance.and/or the Plant Manager. If the notification does not in

'"'"~ the 'employee's opinion receive prompt attention, the employee should contact succdssiv'eely hi'gh'er'evels ofmanagement.

Employees reporting such conditions

-"kshalI., not.,be,discpipunated against by companies of the American Electric

'Power System.

Discrimination includes discharge or other actions relative to

<'dbnfpensation,

'tdi'ms','"condi 2i'ons'or privileges of employment.

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Chairman of the Board American Electric Power Company, Inc.

Revised 4-15-85

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July, 1987

1.7. 1 ORGANIZATION 1.7.1.1 SCOPE

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Icy'merican Electric Power Service Corporation (AEPSC) is.responsible,.for establishing and implementing the'Quality Assurance Program forth'e"~

operational phase of the D.C.

Cook Nuclear Plant (Cook Plant).

Although authority for development and execution of variobs portions o'f the program may be delegated to others,. such as contractors, agents or.

consultants, AEPSC retains overall responsibility.

AEPSC sha'll-'evaluate work delegated to such organizations.

Evaluationsshall'bebased,an, the status of safety importance of the activity being performed and shall be initiated early enough to assure effec'tive. quality, assurance'uriqg.

the performance of the delegated activity.-

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This section of the Quality Assurance Program Description identifies the AEPSC organizational responsibilities for activities affecting the quality of safety-related nuclear power plant structures,'systems;'and components, and describes the authority and duties assignees 'to>them.'t addresses responsibilities for both attaining quality objectives.and for the functions of establishing the Quality Assurance

Program, and

'erifying that activities affecting the quality of safety-related items are performed in accordance with QA Program requirements.

II 1.7.1. 2 IMPLEMENTATION 1.7.1.2.1 Source of Authorit The Chairman of the Board and Chief Executive Offic4&'of Amer>can Electric Power Company, Inc.

(AEP) and AEPSC is responsi,ble for,safe operation of the Donald C.

Cook Nuclear Plant.

Authority and 4

responsibility for effectively implementing the QA Pro'gram for.plant,-

modifications, operations and maintenance are del'egate'd 'through the-'AEPSC Vice Chairman - Engineering and Construction, to the,AEPSC Vice President

- Nuclear Operations (Manager of Nuclear Operations) and the AEPSC Executive Vice President and Chief"Engineer (reference John E. Dolan letter dated November 1, 1984,

Subject:

Support Organization for Donald C.

Cook Nuclear Plant).

1.7-3

July, 1987

- ~, Jn the. operqtiog. of.y nue'J.eap power plant the licensee is required to establish cleaI,apd,direct lines of,responsibility, authority and accoun-

.;,,tability.

Thiq. requirement is applicable to the organization providing support.to-the plant, as well as to the plant staff.

The AEPSC corporate support of the Cook Plant is the responsibility of the entire organization under the direction of the Manager of Nuclear Operations who maintains, primary responsibility for the Cook Plant within

- the, corporate organization.

The AEPSC Vice President - Nuclear

,, Operafions,,is, the, Manager, of Nuclear Operations.

All other AEPSC

~,divisions, and departments other than the guality Assurance Department, z

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. having a, supporting,.role for the Cook Plant are functionally responsible Po, the; Manager. of Nucl,ear Operations (reference Figure 1.7-1).

In order to facilitate a more thorough understanding of the support

,,.functipqs, some.of. the, responsibilities, authorities, and accountabilities within the organization are as follows:

,.g)... The responsibi,lities of the Manager of Nuclear Operations shall be dedicated to the area of nuclear plant operations and support.

2)

. The Manager of Nuclear Operations shall be responsible for, and has the authority to direct all nuclear operational and support matters within t)e corporation and shall make or concur in all final decisions regarding significant nuclear safety matters.

3)

AEPSC division and department managers responsible for nuclear matters shall be familiar with activities within their scope of responsibility that affect plant safety and reliability.

They shall

~ be cognizant of and sensitive to internal and external factors that might affect the operations of the Cook Plant.

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AEPSC division and department managers responsible for nuclear matters have a commitment to seek and identify problem areas and take corrective, action to eliminate unsafe conditions, or to improve trends that will upgrade plant safety and reliability.

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July, 1987

5)

The Manager of Nuclear Operationh shall 'ens'ure"thYit pla6t pe'rsonnel are not requested to perform ~happropH'ate

'cwork'or tatsk's-'by"'orporate personnel and shal'1 contr'ol'*a's'signments and'e'qu'casts that have the potential for diverting the attention of'he Plant-'Manager from the primary responsibility for safe and reliable plant operation.

6)

AEPSC division and department managers having nuclear support responsibilities as well as the Plant Manager -and plant department managers shall be familiar with the poli'cy statements'rom"higher management concerning nuclear safety and operatibnhl piiortities.

They shall be responsible for ensuring that acHv)ties %nder their direction are performed in accordance with these'-'po'licies and the referenced subject letter.

1.7.1.2.2 Res onsibilit for Attainin ualit 'b'ectives "in AEPSC'uclear

~0eratioos The American Electric Power Company, Inc., (AEP)'"Chairman o'f the Board and Chief Executive Officer has delegated the functional responsibility of the guality Assurance Program to the American Electric Power Service Corporation (AEPSC) Vice Chairman - Engineering andaConstruction.

The AEPSC Manager of guality Assurance, under the direction of the AEPSC Vice Chairman - Engineering and Construction, is r'esponsible for speci-fying guality Assurance Program requirements and verifying their implementation.

The AEPSC Vice President - Nuclear Operations and AEPSC Executive Vice President and Chief Engineer, under the direction of the AEPSC Vice Chairman - Engineering and Construction, ar'e respori'sible for effectively implementing the guality Assurance Program.

The Plant Manager, under the direction of the AEPSC Vice President-Nuclear Operations, is responsible for establi'shing'Cook Plant guality Control and implementing the (}uality Assurance Program at'the Cook Plant.

July, 1987

Management/supervisory personnel receive functional training to the level necessary to plan, coordinate, and administrate those day-to-day verifi-cation activities of thh gA Program for which they are responsible.

AEPSC has established an independent off-site Nuclear Safety and Design Review Committee (NSDRC) which has been established pursuant to the requirements of the Technical Specifications for the Cook Plant.

The function of the NSDRC is to oversee the engineering, design, operation, and maintenance of the Cook Plant by performing audits and independent "reviews'f activities'hich are specified in the Facility Operating Licenses..

'The Gook Plant on-.site review group is the Indiana 5 Michigan Electric pn ~. "'Company-'(I8MECo) Plant Nuclear Safety Review Committee (PNSRC).

This coranittee has been established pursuant to the requirements of the Cook x: ePlant

.TedhnicalSpecifications.

The function of the PNSRC is to review plant operations on a continuing basis and advise the Plant Manager on matters related to nuclear safety.

1.7.1.2.3 Cor orate Or anization American Electric Power Com an AEP, the parent holding company, wholly owns the common stock of all AEP System subsidiary (opepating) companies.

The major operating companies and generation subsidiaries are shown in Figure 1.7-2.

The Chairman of the Board of AEP is the Chairman of the Board of AEPSC and is the Chief Executive Officer of AEPSC and all operating companies.

The responsibility for the functional management of the major operating

.companies is vested in the President of each operating company reporting to the AEPSC President and Chief Operating Officer who reports to the AEPSC Chairman of'he Board.

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July, 1987

American Electric Power Service Cor oration

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AEPSC provides management:

and technological services to the various AEP System companies."

0 eratin Com anies

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The operating facilities of the AEP System are.owned'and.operated~by the respective operating companies.

The responsibility for executing,.the engineering, design, construction, specialized technical training, and certain operations supervision is vested in AEPSC whi1e>all.or part of the administrative functional responsibility; is assigned'o,the;,operating companies.

In the case of Cook Plant, ISMEGo.general-.office staff (headquarters) provides public affairs, accounting,'indudtria1:.~safety direction and procurement support.

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Cook Nuclear Plant is owned and operated by ISMECo which is part of the AEP System.

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1.7.1.2.4 ual it Assurance Res onsibil it of AEPSC 1)

AEPSC provides the technical direction of the Cook Plant, and as such makes the final decisions pertinent to safety-related

.changes in plant design.

Further, AEPSC reviews NRC letters, bulletins, notices, etc., for impact on plant design, and 'the need for design changes or modifications.

2)

AEPSC furnishes licensing, NRC correspondence, fuel management and radiological support activities.

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AEPSC provides additional service in matters such as supplier qualification, and spare and replacement part procurement, to the extent established by AEPSC and plant procedures.

July, 1987

4)

The AEPSC gA Department provides technical direction in quality assurance matters to AEPSC and the Cook Plant, and oversees the

~.adequacy and implementation of the gA Program through review and audit activities.

5)

Cognizant Engineer - The AEPSC engineer that provides overall engineering and design responsibility, including implementation of quality assurance and quality control measures, for a system, item of equipment, or structure.

ualit Assurance Res onsibilit of ISMECo - Cook Plant I8MECo's plant staff operates the Cook Plant in accordance with licensing requirements, including the. Technical Specifications and such other commitments as established by the operating licenses.

The Plant Manager Instruction

(,PMI) system and subtier instructions and procedures describe the means by which compliance is achieved and responsibilities are

assigned, including interfaces with AEPSC.

Figure 1.7-3 indicates the

!.:.;,~ organizational relationships within the AEP System pertaining to the operation and support of the Cook Plant.

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. 1.7.1.2.5 Or anization AEPSC

,- The Chairman of the Board'and Chief Executive Officer is ultimately responsible for the guality Assurance Program associated with the Cook Plant.

This responsibility has been functionally delegated to the AEPSC Vice Chairman - Engineering and Construction.

The AEPSC Vice Chairman-Engineering and Construction has further delegated responsibilities which are administered through the following division and department management personnel:

AEPSC Manager of guality Assurance AEPSC Vice President - Nuclear Operations AEPSC Executive Vice President and Chief Engineer (i-;I!7-8

July, 1987

ualit Assurance De artment The AEPSC Manager of guality Assurance reports to the AEPSC Vice Chairman

- Engineering and Construction and is responsible for the guality Assurance Department.

The guality Assurance Department consists of the following positions and sections (Figure 1.7-4):

guality Assurance Engineering Section Audits and Procurement Section guality Assurance Staff Specialist(s) guality Assurance Section (Site)

The guality Assurance Department is organizationally independent and is responsible to perform the following:

Specify gA Program requirements.

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Identify quality problems.

Initiate, recommend, or provide solutions through designated'hannels.

Verify implementation of solutions, as appropriate.

Prepare, issue and maintain guality Assurance Program documents, as'equired.

Verify the implementation of the guality Assurance Program through scheduled audits and surveillances.

Review engineering,

design, procurement, construction and oper-ational documents for incorporation of, and compliance with appli-cable quality assurance requirements to the extent specified by the AEPSC management approved gA Program.

Organize and conduct the gA orientation, training, certification and qualification of AEPSC personnel.

Provide direction for the collection, storage, maintenance, and retention of quality assurance records.

Establish and maintain, on data

base, a gualified Suppliers List (gSL) of nuclear (N) items and services, plus other selected catagories of suppliers.

Identify noncompliances of the established gA Program to the respon-sible organizations for corrective actions and report significant occurrences that jeopardize quality to senior AEPSC management

" "'1.'7-9

July, 1987

Follow up on corrective actions identified by gA during and after disposition implementation.

Review the disposition of conditions adverse to quality to assure that action taken will preclude recurrence.

Conduct in-process gA surveillance at supplier's facilities, as required.

Assist and advise other AEP/AEPSC groups in matters related to the equality Assurance Program.

Maintain a list of nuclear grade items (N-List) for the D.C.

Cook Plant.

Establish a mechanism for identifying, tracking and closing out gA programmatic comnitments.

Conduct audits as directed by the Nuclear Safety and Design Review Committee (NSDRC).

Review AEPSC originated Problem Reports and associated corrective action recommendations.

Maintain cognizance of industry and governmental quality assurance requirements such that the guality Assurance Program is compatible with requirements, as necessary.

Recommend for revision to, or improvements in the established gA Program to senior AEPSC management.

Issue "Stop Work" orders when significant conditions adverse to safety-related items are identified to prevent unsafe conditions from occurring and/or continuing.

Provide AEPSC management with periodic reports concerning the

status, adequacy and implementation of the gA Program.

Prepare and conduct special verification and/or surveillance programs on in-house activities, as required or requested.

Routine attendance and participation in daily plant work schedule and status meetings.

Provide adequate gA coverage relative to procedural and inspection

controls, acceptance

criteria, and gA staffing and qualification of personnel to carry out gA assignments.

Establish and maintain a central file for equipment environmental qualification documentation.

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July, 1987

Am lification of S ecific Res onsibilit'ies ualification of the AEPSC Mana er of ualit Assurance The AEPSC Manager of guality Assurance shall possess the following position requirements:

Bachelor's degree in engineering, scientific or related discipline.

Ten (10) years experience in one or a combination of the following areas:

engineering, design, construction, operations, maintenance of fossil or nuclear power gene-ration facilities or utility facilities guality Assurance, of which at least four (4) years must be exper'ience in nuclear quality assurance related activities.

Knowledge of gA regulations, polic'ies,- practices and standards.

The same or higher organization reporting'evel as the highest line manager directly responsible for'performing-activities affecting quality such as engineering, procure-ment, construction and operation, and is sufficiently independent from cost and schedule.

Effective communication channels with other senior manage-ment positions.

Responsibility for approval of gA Manual(s).

Performance of no other duties or responsibilities unre-lated to gA that would prevent full attention to gA matters.

Il kO The AEPSC guality Assurance Department is responsible for ensuring that activities affecting the quality of safety-related items are performed in a manner that meets applicable administrative, technical, and regulatory requirements.

In order to carry 'out this responsibility, the AEPSC Vice Chairman - Engineering and Construction has given the AEPSC Manager of guality Assurance, the authority to stop 1.'7~11

July, 1987

work on any activity affecting the quality of safety-related items that does not meet the aforementioned requirements.

Stop work authority has been further delegated by the AEPSC Manager of Quality Assurance to the AEPSC Quality Assurance Supervisor (site).

I

'he AEPSC Manager of Quality Assurance and the AEPSC Quality Assurance Supervisor do not have the authority to stop unit operations, but will notify appropriate plant and/or corporate management of conditions which do not meet the aforementioned

criteria, and recommend that unit operations be terminated.

A Orientation, Trainin,

ualification and Certification

~Pro rom a) b)

AEPSC QA shall be responsible for establishing, maintaining and making avai.lable to AEPSC management a

general QA orientation and training program for AEPSC personnel engaged in activities affecting the quality of safety-related items.

This prooram includes the AEPSC QA philosophy and any specific programs as may be required by facility or regulatory requirements.

AEPSC has established and maintains a

QA auditor training and certification program for all AEPSC QA auditors.

Problem identification, Re ortina and Escalation AEPSC QA has established mechanisms for the identification, reporting and escalation of problems affecting the quality of safety-related items to a level of management whereby satisfactory resolutions can be obtained.

Nuclear 0 erations Division The AEPSC Vice President - Nuclear Operations (Manager of Nuclear Oper-ations) reports to the AEPSC Vice Chairman - Engineering and Construction r

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July, 1987

and is responsible for the Nuclear Operations Division.

Reporting to the AEPSC Vice President - Nuclear Operations are the following:

Donald C.

Cook Plant Manager Assistant Division Manager - Nuclear Engineering (not charted)

Assistant Division Manager - Nuclear Operations (not charted)

Consulting Nuclear Engineer - Nuclear Operations (not charted)

Staff Engineer - Nuclear Operations (not charted).

The organization and responsibilities of the Donald C.

Cook Plant Manager d fi d f h

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d 1.7.1.2.6

~0 Cook Plant The AEPSC Assistant Division Manager - Nuclear Engineering is responsible for two of the four sections within the Nuclear Operations Division, as follows (not charted):

Nuclear Safety and Licensing (NS&L) Section Nuclear Material and Fuels Management (NMFM) Section

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'he AEPSC Assistant Division Manager - Nuclear Operations is responsible for the remaining two sections, as follows (not charted):

Nuclear Operations Support (NOS) Section Radiological Support (RS)Section I

The Nuclear Operations Division (NOD) is responsible for the following:

Formulate policies and practices relative to safety, licensing, operation, maintenance, fuel management, and radiological support.

Provide the Plant Manager with the technical and managerial

guidance, direction and support to ensure the safe operation of the plant.

Provide direction to all other AEPSC engineering divisions on engin-eering matters pertaining to the Cook Plant.

Maintain liaison with the AEPSC Manager of guality Assurance.

Implement the requirements of the AEPSC guality Assurance Program.

Maintain knowledge of the latest safety, licensing, and regulatory requirements,

codes, standards and federal regulations applicable to the operation of Cook Plant.

1.7-13

July, 1987

Accomplish the procurement, economic, technical, licensing and quality assurance activities dealing with the reactor core and its related fuel assemblies and components.

Prepare bid specifications, evaluate bids, and negotiate and administer contracts for the procurement of all nuclear fuel and related components and services.

Maintain a special nuclear material accountability system.

Provide analyses to support nuclear steam supply system operation including reactor physics, fuel economics, fuel mechanical

behavior, core thermal hydraulic and LOCA and non-LOCA transient safety analy-sis and other analysis activities as requested, furnish plant Technical Specification changes and other licensing work, and participate in NRC and NSDRC meetings as required by these analyses.

Perform reactor core operation follow-up activities and other reactor core technical support activities as requested, and arrange for support from the fuel fabricator when needed.

Develop, maintain and implement a quality assurance program both for the specific fabrication of nuclear fuel and related components and

=for auditing the ouality program of the vendors of these products.

Contract for, and provide technical support for, disposal of both high level and low level radioactive waste.

Coordinate the development of neutronics and thermal hydraulic safety codes and conduct safety analyses.

Conduct studies of the Cook Plant licensing bases to determine the optimal changes to support unit operations at a lower primary pressure and temperature.

Coordinate NOD computer code development and provide the interface control for NOD with the AEPSC Information System Department and Cook Plant.

Obtaining and maintaining the NRC Operating License and Technical Specifications for the Cook Plant.

Act as the communication link between the NRC, AEPSC, and the plant staff.

July, 1987

Perform and coordinate efforts involved in gathering information, performing calculations and generic studies, prepare criteria,

reports, and responses, reviewing items affecting safety, and inter-'reting regulations.'1~

Review, coordinate, and resolve all matters pertaining to nuclear safety between Cook Plant and AEPSC.

This includes, but is not limited to: the review of certain plant modifications to ensure that the requirements of 10CFR50.59 are met; the preparation of safety evaluations or reviews for any designated subject; the preparation

'~

of safety evaluations or reviews for any designated subject; the preparation of changes to, and appropriate interpretation of, the plant Technical Specification submittals of license amendments; and" the analysis. of plant compliance with regulatory requirements.

'rimary corporate contact for most oral'and written communication with the NRC.

Provide the support in key areas of expertise such as nuclear engi='eering, probabilistic analysis, thermohydraulic analysis, chemical<<

engineering, mechanical engineering, electrical engineering, and technical writing.

ak Interface with vendors and other outside organizations on matters connected with the nuclear steam supply system and other areas affecting the safe design and operation of nuclear plants.

Participate as appropriate in the review of nuclear plant operating experiences, and relate those experiences to the design and safe operation of Cook Plant.

Review, evaluate, and respond to HRC requests for information and NRC notifications of regulatory changes resulting in plant modifica-tions or new facilities.

Such responses are generated in accordance with appropriate AEPSC Administrative Procedures.

Develop, specify, and/or review conceptual nuclear safety criteria for Cook Plant, in accordance with established regulations.

This includes all information contained in the FSAR, as well as special-ized information such as environmental qualification and seismic criteria.

Review and evaluate performance requirements for systems, equipment and materials for compliance with specified safety criteria.

1.7-15

July, 1987

Review, on a conceptual

basis, plant reports and proposed plant safety-related design changes (Request for Changes),

to the extent that they are related to the ultimate safe operation of the plant, for compliance with safety regulations, plant Technical Specifi-

cations, the FSAR design basis, and with any other requirements under the Operating License and to determine if there are any unreviewed safety questions as defined in 10CFR50.59.

Perform reviews of Problem Reports and 10CFR21 reviews in accordance with corporate requirements.

Coordinate design changes for the Cook Plant acting as a focal point within AEPSC.

This program primarily involves project management responsibilities for scheduling and implementing Request for Changes (RFCs) and includes extensive interfacing with engineering,

design, construction, and Cook Plant.

Provide working level coordination with INPO.

This effort includes providing AEPSC access to INPO resources such as NUCLEAR NETWORK and

NPRDS, and effectively integrating AEPSC and Cook Plant efforts towards utilizing INPO recommendations contained in operating experience reports to improve Cook Plant performance.

Coordinate the AEPSC review of completed plant Condition/Problem Reports and provide organizational services and record keeping for review work performed by the NSDRC Subcommittee on Plant Occurrences.

Coordinate daily communication with the Cook Plant, provide AEPSC management with a daily plant status report, and make presentations

. to senior management at regularly scheduled construction staff meetings.

Process incoming vendor information.

Coordinate development of the Cook Plant Facility Data Base.

Contributing to the annual FSAR updates through reviews of Licensee Event Reports, design changes and the Annual Operating Report.

Radiological, emergency and security planning.

Corporate support of the Cook Plant's radiation protection and health physics program, technical service and advice on the radio-1.7-16

July, 1987

logical aspects of design

changes, modifications or capital improve-

ments, the ALARA program, the radiation monitoring system, the environmental radiological monitoring and sampling program, dose and shielding analysis, radiochemistry review, and meteorological monitoring.

Cook Plant and corporate emergency planning including procedure development, exercise scheduling, facility procurement and mainten-~

ance, and the liaison with off-site emergency planning groups such as FEMA and the Michigan State Police.

k II Interface with the plant's security department providing support for the security plan, reviewing security facilities, maintaining security document files, and developing the employee fitness for duty/background screening program.

Provide Nuclear General Employee Training (NGET) for AEPSC personnel.

Participate on ALARA subcommittees.

I Prepare responses to the NRC on radiological, emergency planning and'ecurity issues.

Serve as technical advisors on plant audits.

Remain cognizant of current decommissioning practices and developments.

Environmental En ineerin Division The AEPSC Executive Vice President and Chief Engineer, reporting to the AEPSC Vice Chairman - Engineering and Construction, is responsible for the Environmental Engineering Division through the AEPSC Vice President-Environmental Engineering.

The Environmental Engineering Division provides a nonsafety-related function for the Cook Plant with exception of its participation on the Nuclear Safety and Design Review Committee (NSDRC).

En ineerin and Desi n

The AEPSC Executive Vice President and Chief. Engineer, reporting to the AEPSC Vice Chairman - Engineering and Construction, is responsible for

'.7-17

July, 1987

certain engineering and design functions through the AEPSC Vice President;

- Engineering and Design.

The AEPSC~ Vice President - Engineering and Design is responsible for the following divisions:

Civil Engineering Division Design Division Materials Handling Division Civil En ineerin Division The AEPSC Division Manager - Civil Engineering, reporting to the AEPSC Vice President - Engineering and Design, is responsible for the Civil Engineering Division.

The Civil Engineering Division consists of the following (not charted):

Structural Engineering Section Civil Engineering Laboratory Section Geotechnical Engineering Section Survey and Mapping Group The Civil Engineering Division is responsible for the following:

Make recommendations and assist in the formulation of policies and practices relating to the structural design and engineering of office and service buildings, and miscellaneous structures, and provide the general supervision of the structural engineering of such facilities and structures.

Arrange for outside engineering and consulting assistance as required.

Prepare and review improvement requisitions for capital expenditures.

Approve invoices for outside services.

Approve purchase requisitions and contracts as authorized.

Prepare and approve Request for Changes (RFCs) pertaining to Cook Plant.

Initiate and maintain a program of development and training for personnel in the division.

Prepare specifications, procurement of civil/structural works and modifications to same relative to the Civil Engineering Division.

1.7-18

July, 1987

Direct and coordinate the preparation of specifications and instruc-tions to bidders for general construction and structura1 features of Cook Plant and evaluate proposals received; make recommendations for the award of contracts.

Direct and coordinate the preparation of contracts for the structural phases of Cook Plant and building design and cW construction.

Provide services to the field organizations, including the assignment of personnel to the field during construction, normal or emergency

outages, or as requested.

Assist in planning and execution of maintenance work on buildings and other structures.

Prepare site studies.

Arbitrate disputes which arise between construction forces and outside suppliers of materials and services.

Coordinate structural consultant's reports with design.

Participate in periodic inspections of contractors'ork.

Check of structural drawinqs submitted for review.

Review and recommend concrete mix formulations for all new construction.

Supervise maintenance and repairs of all masonry and concrete work at Cook Plant, including supplying trained inspection personnel.

Direct testing of materials used in concrete and testing of soils to be used in work at the Cook Plant.

Desi n Division The AEPSC Division Manager - Design, reporting to the AEPSC Vice President - Engineering and Design, is responsible for the Design Division.

There are two (2) Assistant Division Managers (not charted) reporting to the AEPSC Division Manager - Design who are responsible for various sections as follows (not charted):

1.7-19

July, 1987

Assistant Division Manager Architectural Design Section Mechanical Design Section Structural Design Section Assistant Division Manager Electrical Plant Section Control Services Section The Design Division is responsible for the following:

Formulate, administer, and implement policies and practices relating to the design of Cook Plant.

Direct the development, maintenance, procedural review and implemen-tation by which the Design Division adheres to the gA Program elements as established by AEPSC General Procedures.

Identify and report deficiencies in the division's functions,

duties, and responsibilities.

Conduct periodic management reviews and surveillances of division activities to ensure compliance with gA Program objectives, and external surveillances as necessary, of consultants outside organi-zations and vendors for. which the division is cognizant.

Conduct functions of the division so as to be in conformance with the operating licenses of the Cook Plant.

Coordinate the review and/or answering of corrective actions issued and assigned to the Design Division.

Coordinate special projects and studies, as required.

Establish and maintain files of design documents for record purposes.

Initiate and/or implement and control design changes and modifications.

Coordinate the development and maintenance of the computerized Design Drawing Control (DDC) and the Vendor Drawing Control (VDC) programs which include coordinating the programs with interfacing divisions/departments.

Control the issuance and distribution of drawings for the Cook Plant including monitoring of the Aperture Card Microfilm Program.

1.7-20

July, 1987

Supervise and control the work of consultants, Architect/Engineers and outside design agencies supplying services to AEPSC in their discipline and process notification of defects in accordance with company requirements.

Also perform detailed reviews of design work

'ubmitted by outside agencies.

Supervise the identification of critical design decisions and ensure appropriate analyses and reviews are provided.

Review and approve design drawings prior to issuance.

Provide to the field organizations such services as required during construction, normal or emergency outages or as requested, including

'ssigning design personnel to the field.

Naintain an up-to-date list of major approved materials and specifications used within the division s scope of responsibility.

Initiate and/or aid in the responses of reportable items as W

described in AEPSC General Procedures and division procedures.

Schedule, develop, coordinate and control design studies, calcu-lations/analysis,

drawings, purchase documents, specifications and

other design activities, as assigned for system, components or structures within the division's responsibility.

Review and update applicable sections of Cook Plant FSAR as assigned.

Perform functions related to the Cook Plant as required in response to NRC requirements.

Participate on committees that review nuclear activities as appointed or assigned.

Coordinate and resolve design comments made by interfacing departments/divisions.

Prepare, review approve and administer design specifications and purchase documents for design services and/or materials.

Participate in the Initial Assessment Group (IAG) and provide assistance to on-site personnel and other divisions.

Coordinate the implementation of division commitments.

1.7-21

July, 1987

Materials Handlin Division The AEPSC Division Manager - Materials Handling, reporting to the AEPSC Vice President - Engineering and Design, is responsible for the Materials Handling Division.

The Materials Handling Division contains one (1) section that performs safety-related work as follows (not charted):

Coal and Materials Handling Section The Coal and Materials Handling Section is responsible for the following:

Develop policies and practices relating to the engineering of materials handling installations for Donald C.

Cook Nuclear Plant.

Review the activities of materials handling systems for the Cook Plant and approve, as required, all design changes and modifications including the preparation of specifications, procurement of equipment and modifications to equipment.

Arrange for outside engineering and consulting services, as required.

'Provide training and development programs necessary for personnel of the division (including the company's safety and health program),

which are consistent with the written policy of American Electric Power Company and American Electric Power Service Corporation.

Prepare and administer erection and service contracts.

Review and evaluate proposals and make recommendations for., awards of purchase orders and contracts.

Prepare, review and approve specifications, purchase and change documents,

sketches, drawings, design input, design verifications and calculations, as required.

Initiate and/or review approval and control of laboratory and field investigations, feasibility studies, improvement requisitions, reports and cost estimates pertaining to the Cook Plant.

Provide field services to the Cook Plant including the assigning of personnel as are required during construction, normal or emergency

outages, or as requested.

Direct the review of, and response to assigned corrective actions.

Identify critical engineering and design input and ensure that appropriate analysis and reviews are conducted.

117-22

July, 1987

Implement a corrective action system with regard to all activities of the division affecting quality of safety-related items that will control and document all items, services, or activities which do not conform to requirements.

Maintain a surveillance program in support of the Quality Assurance+

Program and review and approve the activities of this program which.

can be separated into the following two (2) areas:

Internal management review of the Materials Handling Division.

External technical surveillance of consultants, outside materials handling organizations and vendors over which the division is cognizant.

Assist in planning and execution of'aintenance work on equipment and facilities.

~

'eview and approve manufacturer's equipment 'drawings prior to fabrication.

~I Prepare design criteria, engineering standards, conceptual

layouts,

~

studies and procedures in conjunction with materials handling equipment at the Cook Plant.

Assist in the preparation of applications for federal, state and local permits relative to installations being made which require such permits.

Perform shop and field inspections on equipment being fabricated or installed which is within the scope of the division's responsibility.

Provide input for special studies and reports which may be requested by other divisions or governmental agencies such as the Nuclear Regulatory Commission.

Provide technical guidance when requested in support of maintenance

'nd operations activities at the Cook Plant.

Conduct periodic management reviews of the activities of the division to ensure compliance with the objectives of the Quality Assurance

Program, and external technical surveillance, as necessary, of consultants, outside materials handling organizations and vendors over which the division is cognizant.

Establish and maintain a permanent file for QA records.

107-23

July, 1987

Process RFCs in accordance with AEPSC General Procedures and division procedures.

Electrical En ineerin De artment The AEPSC Executive Vice President and Chief Engineer, reporting to the AEPSC Vice Chairman - Engineering and Construction, is responsible for the Electrical Engineering Department through the AEPSC Senior Vice President - Electrical Engineering and Deputy Chief Engineer.

Reporting to AEPSC Senior Vice President - Electrical Engineering and Deputy Chief Engineer is the AEPSC Manager - Generation and Telecommunications Engineering Division.

The Generation and Telecommunications Engineering Division (not charted) is the only division within the Electrical Engineering Department that"is responsible for performance of electrical oriented safety-related activities.

The AEPSC Assistant Manager-Generation and Telecommunications Engineering Division reports to the AEPSC Manager - Generation and Telecommunications Engineering Division and is responsible for the one (1) section within the Electrical Engineering Department that is responsible for safety-related activities as follows (not charted):

Electrical Generation Section The Electrical Generation Section is responsible for the following:

Plan and engineer, in conjunction with other specialists, sections and divisions, electrical facilities inside Cook Plant up to the high voltage (HV) bushings of the main generator transformers, and the relaying and controls on breakers associated with the generator and auxiliary system, including:

determination of general layout and design; advising on selection of major electrical equipment; preparation of one-line diagrams, and; coordination of inside and outside electrical plant facilities.

July, 1987

Engineer and design all electrical controls for operation and protection of steam generator, turbine generator, and auxiliary equipment and general plant protection, including checking and approving elementary and one-line drawings.

Prepare cost estimates and improvement requisitions for electrical plant facilities, including review of improvement requisitions and cost estimates prepared by others.

Review and approve all procedures, correspondence, requests for design changes or modifications as appropriate.

Obtain, review and perform engineering evaluations including equip-.;

ment qualification.

Provide technical support to Nuclear Safety and Licensing (NS&L) and to Cook Plant Operations and Maintenance Departments.

Perform and evaluate economic studies, investigations, analysis

and, reports for electrical facilities pertaining to the design, operation and maintenance of the generating plants.

Maintain a constant awareness for improvements and more economic design of equipment, electric facilities, maintenance and operating methods or procedures.

Assign section members to the NSDRC subcommittees to participate in~

matters covered in the subcommittees'harters.

Participate in the evaluation and remedy of any situation requiring activation of the emergency response organization.

Prepare and/or approve specifications and purchase requisitions, and perform drawing review of electrical equipment, including control and protective relays.

Assist field personnel in installation, start-up and the subsequent.

locating of problems in protective and control electrical equipment and in determining proper operation of equipment during normal or after emergency operations.

Assist with the establishing of relay and control standards.

Maintain a constant awareness of activities to ensure compliance with all applicable procedures, initiating, when required, training or retraining programs.

Review and approve responses to NRC correspondence as required.

1.7-25

July, 1987

Closely follow manufacturers'ngineering and designs to ensure provision of adequate and,reliable equipment, and circuitry in the areas of turbine-generator protective controls, switchgear, elec-trical auxiliaries, mechanical equipment and protective devices upon which depend the safety, reliability, economy and performance of the unit and plant.

Perform calculations for proper application and settings of protec-tive relays.

Interface with the Mechanical Engineering Division to ensure that all electrical devices purchased with mechanical equipment conform to accepted standards and fulfill the desired function.

Mechanical En ineerin Division The AEPSC Executive Vice President and Chief Engineer,'eporting to the AEPSC Vice Chairman - Engineering and Construction, is responsible for the Mechanical Engineering Division through the AEPSC Vice President-Mechanical Engineering.

Reporting to the AEPSC Vice President-Mechanical Engineering, are the following (not charted):

AEPSC Assistant Division Manager(s)

Consulting Mechanical Engineer - Nuclear Staff Engineer - Chief Metallurgist Further, the AEPSC Assistant Division Manager - Nuclear is responsible for the following positions and sections (not charted):

Nuclear Project Engineer(s)

Turbine and Cycle Evaluation Section Chemical Engineering Section Heat Exchangers and Pumps'ection

Piping, HVAC and Fire Protection Section Instrumentation and Control Section Analytical and RSD Section The Mechanical Engineering Division is responsible for the following:

Provide technical engineering support.;in areas of operation and maintenance, including:

the Inservice Inspection (ISI) Program; the 1.7-26

July, 1987

guality Assurance Program; the AEP ALARA Program covering radiation protection, and; the corporate and plant Industrial Safety Program.'".

Provide engineering support for the other AEPSC engineering divisions, as well as for the manufacturers, suppliers, or constructors of equipment and systems.

Provide engineering support to the AEPSC Nuclear Operations Division.

Preparation of equipment specifications and purchase requisitions for plant equipment, major spare parts and services related to specific areas of responsibility of h1ED.

Provide technical direction and assistance to the AEPSC Design Division in the layout and arrangement of equipment,

piping, systems, controls, etc., for the development of drawings.

Develop system flow diagrams and progressive reviews to determine the adequacy of system designs.

Provide technical assistance to the Cook Plant for use and control '

of special processes, including welding, heat treating, nondestruc-~

tive examination, etc.

Initiate and develop design changes in areas of responsibility of the tlechanical Engineering Division.

Develop System Descriptions and Descriptive Articles.

P" Provide support personnel for the emergency response organization.

Provide analytical support in engineering disciplines (e.g.,

heat

transfer, thermodynamics, fluid dynamics).

Review and approval of mechanical design drawings.

Provide engineering evaluations for Condition/Problem Reports,

LERs, INPO SOERs and NRC Bulletins.

Plant Construction Division The AEPSC Assistant Vice President - Plant Construction Division reports to the AEPSC Vice Chairman - Engineering and Construction, and is respon-sible for the Plant Construction Division.

The Plant Construction Division consists of the following sections (not charted):

Administrative Section Construction Contracts Section 1.7-27

July, 1987

The Plant Construction Division is responsible for the following:

Provide a Construction Manager,~reporting administratively to the AEPSC Assistant Vice President - Plant Construction Division and functionally to the Cook Plant Manager, to perform major modifica-

" tions and maintenance work.

Scope, bid and make recommendations relative to construction contracts.

Administer contracts throughout the construction period.

Purchasin and Stores De artment (not charted)

The AEPSC Executive Vice President - Operations reporting to the AEPSC President and Chief Operating Officer is responsible for the Purchasing and Stores Department through the AEPSC Vice President - Purchasing and Stores.

The Purchasing and Stores Department is responsible for the following:

Purchasing "N" items only from suppliers appearing on the gualified Suppliers List (l}SL).

Provide ordering and stocking descriptions of "N" items and include these descriptions in the Cook Plant inventory catalog including necessary communications with suppliers, cogn'izant engineers, the Cook Plant Stores Supervisor and other appropriate personnel.

Coordinate procurement activities with AEPSC Nuclear Operations, AEPSC engineering and design divisions/department, ISMECo Purchasing Department, the AEPSC guality Assurance Department and Cook Plant personnel.

Prepare and issue requests for quotations, contracts, service orders and purchase orders for "N" items.

Establish a system to implement corrective action as described in the AEPSC General Procedures for the Cook Plant.

Establish a system of document keeping, and transmittal.

Establish a system. of document control for controlled procedures, instructions, and purchasing documents for "N" items.

E 1.7-28

July, 1987

Conduct training sessions involving purchasing personnel and others-on an annual basis or,more frequently, as required, and ascertain

hat training sessions include complete responsibilities associated with the purchase of safety-related items.

Notify suppliers of their status regarding the gSL, e.g., inclusion, exclusion, conditional approval, etc.

Notify the I&MECo Purchasing Department and the Cook Plant Stores of changes in the gSL.

Receipt inspection, handling, storage and control of stores items.

1.7.1.2.6 Or anization Cook Plant The Plant Manager, reports functionally and administratively to the AEPSC'"

Vice President - Nuclear Operations Division (Manager of Nuclear Operations) and is responsible for the Cook Plant activities.

Reporting to the Plant Manager are the following (Figure 1.7-5):

Assistant Plant Manager - Production Assistant Plant Manager - Technical Support Assistant Plant Manager - Organization and Administration II Licensing Activity Coordinator Safety and Assessment Superintendent (reports functionally to the Plant Manager) tl Radiation Protection Manager (reports functionally to the Plant Manager (this is an assigned function and is currently being performed by the Technical Physical Science Superintendent))

The the Cook Plant organization, under the Plant Manager is responsible for following:

Ensure the safety of all facility employees and the general public relative to general plant safety, as well as radiological safety by maintaining strict compliance with plant Technical Specifications, procedures and instructions.

Recomnend facility engineering modification and initiate and approve plant improvement requisitions.

Ensure that work practices in all plant departments are consistent with regulatory standards,

safety, approved procedures, and plant Technical Specifications.

1.7-29

July, 1987

Provide membership, as required, on the Plant Nuclear Safety Review Committee.

Naintain close working relationships with the NRC as well as local,

state, and federal government regulating officials regarding condi-tions which could affect, or are affected by Cook Plant activities.

Set up plant load schedules and arrange for equipment outages.

Develop and efficiently implement all site centralized training activities.

Administer the centralized facility training complex, simulator, and programs ensuring that program development is consistent with the systematic approach to training, maintain INPO accreditations, regulatory and corporate requirements.

Ensure that human resource activities include employee support programs (i.e., fitness for duty) consistent with INPO/NUMARC guidelines, company policies, and regulatory requirements and standards.

Administer the NRC approved physical Security Program in compliance with regulatory standards, Nodified Amended Security Plan, and company policy.

Supervise,

plan, and direct the activities related to the maintenance and installation of all power plant equipment, struc-

tures, grounds, and yards.

Prepare and maintain records and reports pertinent to equipment maintenance and regulatory agency requirements.

Administer contracts and schedule outside contractors'ork forces.

Enforce and coordinate plant regulations, procedures,

policies, and objectives to assure safety, efficiency, and continuity in the operation of the Cook Plant within the limits of the operating license and the Technical Specifications and formulation of related policies and procedures.

, Plan, schedule, and direct the activities relating to the operation of the Cook Plant and associated switchyards; cooperate in planning and scheduling of work and procedures for refueling and maintenance

,of the Cook Plant; direct and coordinate fuel loading operations.

Review reports and records and direct general inspection of operating conditions of plant equipment and investigate any abnormal 1.7-30

July, 1987

conditions, making recommendations foi repairs.

Establish and administer equipment clearance procedures consistent with company,

plant, and radiation protection standards; authorize and arrange for equipment outages to meet normal or emergency conditions.

Provide the shift operating crews with appropriate procedures and instructions to assist them in operating the plant safely and efficiently.

1 Approve operator training programs administered by the Cook Plant Training Department designed to provide operating personnel with the knowledge and skill required for safe operation of the facility and for obtaining and holding NRC operator licenses.

Coordinate training programs in plant safety and emergency procedures for Cook Plant Operating Department personnel to ensure that each shift group will function properly in the event of injury of personnel, fire, nuclear incident, or civil disorder.

Advance planning and overall conduct of scheduled and forced

outages, including the scheduling and coordination of all plant activities associated with refueling, preventive maintenance, corrective maintenance, equipment overhaul, Technical Specification surveillances, and design change installations.

Coordinate all plant activities associated with the initiation, review, approval, engineering,

design, production, examination, inspection, test, turnover, and close out of design changes.

Develop and implement an effective guality Control Program.

This encompasses, but is not limited to, the planning and directing of quality control activities to assure that industry codes, Nuclear Regulatory regulations, and company instructions and policies regarding quality control for Cook Plant are implemented, qualified'ersonnel perform work, and that these activities are properly documented.

Prepare reports of reportable events which are mandated by the NRC and the Technical Specifications.

Direct the activities of contractor gC/NDE personnel assigned to the gC Department and provide inspections of work performed.

"Prepare statistical reports utilized in Nuclear Regulatory Appraisal Meetings and Enforcement Conference.

1.7-31

July, 1987

Coordinate the efforts of outside agencies such as American Nuclear Insurers (ANI), INPO, and third, party inspector programs.

Maintain knowledge of developments and changes in NRC requirements, industry standards and codes, regulatory compliance activities, and quality control disciplines and techniques.

Stop plant operation in the event that conditions are found which are in violation of the Technical Specifications or adverse to quality.

gualification and certification of inspection, test, and examination personnel ensuring compliance to Regulatory Guide 1.8, ANSI N18.1, Regulatory Guide 1.58, ANSI N45.2.6, the ASME BSPV Code, and SNT-TC-as applicable, except as noted in Appendix B hereto, item 9.

Perform peer inspections of work completed by ISMECo, personnel by persons qualified and certified to ANSI N18;7.

Conduct of the Inservice Inspection (ISI) Program.

Procurement, receiving, quality control receipt inspection,

storage, handling, issue, stock level maintenance, and overall-control of stores nuclear, fire protection and standard grade items.

Provide material service and support in accordance with policies and procedures required by AEP Purchasing and Stores, AEPSC guality Assurance, and the Nuclear Regulatory Commission (NRC), which are administered and enforced in a total effort to ensure safety and plant reliability.

Plan and direct engineering-and technical

studies, nuclear fuel management, equipment performance, instrument and control mainte-

nance, on-site computer systems, Shift Technical Advisors, and emergency planning for the Cook Plant.

These activities support daily on-site operations in a safe, reliable, and efficient manner in accordance with all corporate policies, applicable laws', regul-ations, licenses, and Technical Specification requirements.

Implement station performance testing and monitor programs to ensure optimum plant efficiency.

1A, 10732

July, 1987

Direct programs related to on-site fuel management and reactor core physics testing and ensure satisfactory completion.

Establish testing and preventive maintenance programs related to station instrumentation, electrical

systems, and computers.

Recommend alternatives to plant operation, technical or emergency procedures, and design of equipment to improve safety of operations'~'nd overall plant efficiency.

Implement the corporate Emergency Plan as it pertains to the D.C.

Cook Plant site.

Provide technical and engineering services in the fields of chemis-"

try, radiation protection, ALARA, and environmental in support of the safe operation of the plant and the health and safety of the employees and the public.

Plan and schedule the activities of the Technical Physical Science Sections of the plant in support of operations and maintenance.

4 Establish chemistry, radiochemistry, and health physics criteria which ensure maximum equipment life and the protection of the health and safety of the workers and the public.

Establish sampling and analysis programs which ensure the chemistry'",

radiochemistry, and health physics criteria are within the estab-lished criteria.

Establish and direct investigations, responses, and corrective actions when outside the established criteria.

Administer and direct the plant's radioactive waste

programs, including volume reduction, packaging and shipping.

Administration of the QA Records Program.

Develop and maintain the Cook Plant Facility Data Base.

1.7.2 1.7.2.1.

QUALITY ASSURANCE PROGRAH SCOPE Policies that define and establish the D.C.

Cook Nuclear Plant Quality Assurance Program are summarized in the individual sections of this document.

The program is implemented through procedures and instructions responsive to provisions of the QAPD, and will be carried out for the life of the plant.

1.7-33

July, 1987

guality assurance controls apply to activities affecting the quality of safety-related structures, systems and components, to an extent based on the importance of those structures,

systems, or components to safety.

Such activities are performed under controlled conditions, including the use of appropriate equipment, environmental conditions, assignment of qualified personnel, and assurance that all applicable prerequisites have been met.

Safety-related structures, systems or components are defined as items:

which are associated with the safe shutdown (hot) 'of the reactor; or isolation of the reactor; or maintenance of the integrity of the reactor coolant system pressure boundary.

or whose failure might cause or increase the severity of a design basis accident as described in the FSAR; or lead to a release of radioac-tivity in excess of IOCFR100 limits.

In general, items are classified as safety-related if they are:

Seismic Class I, or Electrical Class IE; or associated with the Engineered Safety Features Actuation System; or associated with the Reactor Protection System.

A special gA program has been implemented for Fire Protection items (Section 1.7.19 herein).

guality Assurance Program status,

scope, adequacy, and compliance with 10CFR50, Appendix 8, are regularly reviewed by AEPSC management through

reports, meetings, and review of audit results.

The implementation of the guality Assurance Program may be accomplished by AEPSC and/or Indiana 5 f1ichigan Electric Company or delegated in whole 1.7-34

July, 1987

or in part to other AEP System companies or outside parties.

However, AEPSC and/or Indiana E Michigan Electric Company retain full responsi-bility for all activities affecting safety-related items.

The performance of the delegated organization is evaluated by audit or surveillances on a

frequency commensurate with their scope and importance of assigned work.-"V 1.7.2.2 IMPLEMENTATION 1.7.2.2.1 The Chairman of the Board of AEPSC, as Chief Executive Officer, has stated in a signed, formal "Statement of Policy", that it is the corporate policy to comply with the provisions of applicable codes, standards and regulations pertaining to quality assurance for nuclear power plants as required by the Donald C.

Cook Nuclear Plant operating licenses.

The statement makes this gAPD and the associated implementing procedures and instructions mandatory, and requires compliance by all responsible organizations and individuals.

The statement also identifies'he management positions within the companies vested with responsibility "

and authority for implementing the program and assuring its effectiveness.

1.7.2.2.2 The guality Assurance Program at AEPSC and the plant consist of controls exercised by organizations responsible for attaining quality objectives, and by organizations responsible for assurance functions.

The gA Program effectiveness is continually assessed through management review of various reports, NSDRC review of the gA audit program and shall'lso be periodically reviewed by independent outside parties as deemed necessary by management.

The gA Program described in this i}APD is intended to apply for the life of the D.C.

Cook Nuclear Plant.

1.7-35

July, 1987

~e 's0'>>

The QA Program applies to activities affecting the quality of safety-related structures,

systems, components, and related cons'umables during plant operation, maintenance,

testing, and all design changes.

Safety-related structures, systems and components are identified in the N-List/

Facility Data Base and other documents which are developed and maintained for the plant.

iO h

As deemed necessary by the AEPSC Manager of Quality Assurance, or the Plant Manager, applicable portions of the QA Program controls will be applied to nonsafety-related activities associated with the implementa-tion of the QA Program to ensure that committments are met (e.g.,

off-site records

storage, training services, etc.).

1.7.2.2.3 This QAPD, organized to present the Quality Assurance Program for the D.C.

Cook Nuclear Plant in the order of the 18 criteria of 10CFR50, Appendix B, states AEPSC policy for each of the criteria, and describes how the controls pertinent to each are carried out.

Any changes made to this QAPD that do not reduce the commitments previously accepted by the NRC must be submitted to the NRC at least annually.

Any changes made to this QAPD that do reduce the commitments previously accepted by the NRC must be submitted to the NRC and receive NRC approval prior to implemen-tation.

The submittal of the changes described above shall be made in accordance with the requirements of 10CFR50.54.

0 The program described in this QAPD will not be intentionally changed in any way that would prevent it from meeting the criteria of 10CFR50, Appendix B and other applicable operating license requirements.

1.7.2.2.4 Documents used for implementing the provisions of this QAPD include the foll'owing:

1.7-36

July, 1987

Plant Manager Instructions (PMIs) establish the policy for compliance with specified criteria, and assign responsibility to the various depart-

ments, as required, for implementation.

Department Head Procedures (DHPs),

and in some cases Department Head Instructions (DHIs), have been prepared to describe the detailed activities required to support safe and effective plant operation as per the PMIs.

The PMIs are reviewed by the AEPSC guality Assurance Supervisor for concurrence that they will satisfactorily implement regulatory require-ments and commitments.

They are then reviewed by the Plant Nuclear Safety Review Committee (PNSRC) prior to approval by the Plant Manager.

Safety-related DHPs and DHIs are reviewed by the department head of origination, AEPSC guality Assurance Supervisor, PNSRC and Plant Manager prior to use.

AEPSC General Procedures (GPs) are utilized to define corporate policies>;

and requirements for quality assurance, and to implement certain guality.

Assurance Program requirements within AEPSC.

AEPSC division/department and/or section procedures are also used to implement guality Assurance Program requirements.

GPs may also be used to define policies which are nonprocedural in nature.

i(hen contractors perform work on-site under their own quality assurance

programs, the programs are reviewed for compliance and consistency with the applicable requirements of the plant's guality Assurance Program and the contract, and are approved by the AEPSC guality Assurance Supervisor prior to the start of work.

1.7.2.2.5 Provisions of the guality Assurance Program for the D.C.

Cook Nuclear Plant apply to activities affecting the quality of safety-related 1.7-37

July, 1987

structures,

systems, and components.

Appendix A to this gAPD lists the Regulatory/Safety Guides and ANSI Standards that identify AEPSC's commit-ment.

Imposition of these guides/standards on AEPSC/ISMECo suppliers and subtier suppliers will be on a case-by-case basis depending upon the item or service to be supplied.

Appendix B describes necessary exceptions and clarifications to the requirements of those documents.

The scope of the program and the extent to which its controls are applied, are established as follows:

a)

AEPSC uses the criteria specified in the D.C. Cook Plant Final Safety Analysis Report (FSAR) for identifying structures, systems and components to which the guality Assurance Program applies.

b)

This identification process results in the N-List/Facility Data Base for the D.C.

Cook Nuclear Plant.

This N-List/Facility Data Base are controlled documents, issued to designated personnel.

N-List/Facility Data Base items are determined by engineering analysis of the function(s) of plant structures, systems and compo-nents in relation to safe operation and shutdown.

c)

The extent to which controls specified in the guality Assurance Program are applied to N-List/Facility Data Base items is determined for each item considering its relative importance to safety.

Such determinations are based on data in such documents as the plant Technical Specifications and the FSAR.

1.7.2.2.6 Activities affecting safety are accomplished under controlled conditions.

Preparations for such activities include consideration of the following:

a) b)

c) d)

Assigned personnel are qualified.

Work has been planned to applicable engineering and/or Technical Specifications.

Specified equipment and/or tools are available.

Materials and items are in an acceptable status.

1.7-38

July, 1987

e) f)

g) h)

Systems or structures on which work is to be performed are in the proper condition for the task.

Proper instructions/procedures for the work are available for use.

~.

Items and facilities that could be damaged by the work have been protected, as required.

1 Provisions have been made for special controls, processes, tests and verification methods.

1.7.2.2.7 Responsibility and authority f'r planning and implementing indoctrination and training of AEPSC and plant staff personnel are specifically designated, as follows:

a)

The training and indoctrination program provides for on-going training and periodic refami liarization with the guality Assurance

~

Program for the D.C.

Cook Nuclear Plant.

b)

Personnel who perform inspection and examination functions are qualified in accordance with requirements of Regulatory Guide 1.8, ANSI N18.1, Regulatory Guide 1.58, ANSI N45.2.6, the ASt1E 88PV Code, or SNT-TC-IA, as applicable and with exceptions as noted in Appendix 8 hereto.

c)

AEPSC guality Assurance Department auditors are qualified in accordance with Regulatory Guide 1.146 and ANSI N45.2.23.

d)

Personnel assigned duties such as special cleaning processes, welding, etc.,

are qualified in accordance with applicable

codes, standards, regulatory guides and/or plant procedures.

e)

The training, qualification and certification program includes, as applicable, provisions for retraining, reexamination and recertification to ensure that proficiency is maintained.

1.7-39 Ju'ly, 1987

f)

Training, qualification, and certification records including docu-mentation of objectives, content of program, attendees and dates of attendance are maintained at least as long as the personnel involved are performing activities to which the training, qualification and certification is relevant.

I g)

Personnel responsible for performing activities that affect safety-related items are instructed as to the purpose, scope and implementation of the applicable manuals, instructions and procedures.

Management/supervisory personnel receive functional training to the level necessary to plan, coordinate and administer the day-to-day verification activities of the gA Program for which they are responsible.

Training of AEPSC and plant personnel is performed employing the following techniques, as applicable:

I) on the job and formal training administered by the department or section the individual works for; 2) formal training conducted by qualified instructors from the plant Training Department or other entities (internal and external to the AEP System);

and 3) formal, INPO accredited training conducted by the plant Training Department.

Records of training sessions for such training are maintained.

Where personnel qualifications or certifications are required, these certifica-tions are performed on a scheduled basis

{consistent with the appropriate code or standard).

Plant employees receive introductory training in quality assurance usually within the first two weeks of employment.

In addition, AEPSC personnel receive training prior to being allowed unescorted access to the plant.

This training includes management's policy for implementation of the guality Assurance Program through Plant Manager and Department Head Instructions and Procedures.

These instructions also include a

description of the equality Assurance

Program, the use of instructions and procedures, personnel requirements for procedure compliance and the systems and components controlled by the guality Assurance Program.

1.7-40

July, 1987

1.7.2.2.8 The AEPSC Information System Department (ISD) (not charted) has established a Computer Software guality Assurance Section.

Procedures have been developed to establish gA requirements for safety-related computer software.

The Computer Software gA Section is subject to periodic audit by the AEPSC gA Department.

1.7.3 DESIGN CONTROL 1.7.3.1 SCOPE Design changes to structures, systems and components are accomplished in accordance with approved design.

Activities to develop such designs are controlled.

Depending on the type of design

change, these activities include design and field engineering; the performance of physics, seismic, stress, thermal, hydraulic and radiation evaluations; update of' the FSAR; review of accident analyses; the development and control of associated computer programs; studies of material compatibility; accessibility for inservice inspection and maintenance; determination of'uality standards; and requirement for equipment qualification.

The controls apply to preparation and review of design documents, including the correct translation of applicable regulatory requirements and design bases into design, procurement and procedural documents.

1.7.3.2 IMPLEMENTATION 1.7.3.2.1 Design changes to the plant are controlled by instructions and procedures.

All design changes are reviewed as required by 10CFR50.59.

1.7.3.2.2 A Change Control Board has been established within AEPSC to perform the review and authorization for safety-related design changes (Request for 1.7-41

July, 1987

Changes (RFCs)).

The Change Control Board is comprised of members of the Engineering, Design, Nuclear, Operations, and guality Assurance divisions/departments within AEPSC and is supplemented by other AEPSC organizations or individuals as required.

1.7.3.2.3 Plant originated RFCs are reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and approved by the Plant Manager prior to submission to the Change Control Board.

The cognizant member of the Change Control Board assigns a lead engineer for each RFC.

The lead engineer is respon-sible for coordinating the RFC activities within AEPSC.

The AEPSC Nuclear Safety and Licensing Section reviews RFCs to determine their impact on nuclear safety and to determine if the proposed changes involve an unreviewed safety question as defined by 10CFR50.59.

RFCs are then returned to the PNSRC for subsequent review prior to submission to the Change Control Board. If an RFC were to involve an unreviewed safety question, it would not be approved by the Nuclear Safety and Licensing Section until the required approval was received from the NRC.

1.7.3.2.4 Proposed design changes which require emergency processing are originated at the plant, reviewed by the PNSRC and approved".by the Plant Manager.

Plant management then contacts the AEPSC Nuclear Operations Division, and other AEPSC management, as required, describes the change requested and implements the change only after receiving verbal AEPSC management authorization to proceed.

These reviews and approvals are documented and become a part of the RFC Packet.

1.7.3.2.5 When RFCs involve design interfaces between internal or external design organizations, or across technical disciplines, these interfaces are controlled.

Procedures are used for the review, approval, release, 1.7-42

July, 1987

distribution and revision of documents involving design interfaces to ensure that structures, systems and components are compatible geometri-cally, functionally, with processes and the environment.

Lines of communication are established for controlling the flow of needed design

~'nformation across design interfaces, including changes to the information as work progresses.

Decisions and problem resolutions involving design interfaces are made by the AEPSC organization having responsibility for engineering direction of the design effort.

1.7.3.2.6 Checks are performed and documented to verify the dimensional accuracy and completeness:,of design drawings and specifications.

1.7.3.2.7 RFC design document packages are reviewed by AEPSC gA to assure that the%

documents have been prepared, verified, reviewed and approved in accor-dance with company procedures.

1.7.3.2.8 The extent of and methods for design verification are documented.

The extent of design verification performed is a function of the importance of the item to safety, design complexity, degree of standardization, the state-of-the-art, and similarity with previously proven designs.

Methods for design verification include evaluation of the applicability of standardized or previously proven designs, alternate calculations, qualification testing and design reviews.

These methods may be used singly or in combination, depending on the needs for the design under consideration.

July, 1987

When design verification is done by evaluating standardized or previously proven designs, the applicabi,lity of such designs is confirmed.

Any differences from the proven design are documented and evaluated for the intended application.

gualification testing of prototypes, components, or features is used when the ability of an item to perform an essential safety function cannot otherwise be adequately substantiated.

This testing is performed before plant equipment installation where possible, but always before reliance upon the item to perform a safety-related function.

gualification testing is performed under conditions that simulate the most adverse design conditions, considering all relevant operating modes.

Test requirements, procedures and results are documented.

Results are evalu-ated to assure that test requirements have been 'satisfied.

Design changes shown to be necessary through testing are made, and any necessary retesting or other verification is performed.

Test configurations are clearly documented.

Design reviews are performed by multi-organizational or interdisciplinary groups, or by single individuals.

Criteria are established to determine when a formal group review is required, and when review by an individual is sufficient.

1.7.3.2.9 Persons representing applicable technical disciplines are assigned to perform design verifications.

These persons are qualified by appropriate education or experience but are not directly responsible for the design.

The designer's immediate supervisor may perform the verification, provided that:

1)

The supervisor is the only technically qualified individual.

or I

1.7-44

July, 1987

2)

The supervisor has not specified a singular design approach, ruled out design considerations, nor established the design inputs.

and 3)

The need is individually documented and approved in advance by the "

supervisor's management.

4)

Regularly scheduled gA audits verify conformance to previous items 1

through 3.

Design verification on safety-related design changes shall be completed

"~

prior to declaring a design

change, or portions thereof operational.

1.7.3.2.10 Plant implementation of the RFC is accomplished by the plant IEC/Planning Department.

Material to perform the design change must meet the specifications established for the original system or as specified by the lead engineer.

For those design changes where testing after completion is required, the testing documentation is reviewed by the organization performing the test and, when specified, by the AEPSC lead engineer or cognizant engineer.

Further, completed RFCs are reviewed by AEPSC gA (Site) following installation and testing.

1.7.3.2.11 Changes to design documents, including field changes, are reviewed, approved and controlled in a manner commensurate with that used for the original design.

Such changes are evaluated for impact.

Information on approved changes is transmitted to all affected organizations.

July, 1987

1.7.3.2.12 Error and deficiencies in, and deviations from approved design documents are identified and dispositioned in accordance with established design control and/or corrective action procedures.

1.7.3.2.13 This mechanism provides for:

1) controlled submission of design

changes,

2) engineering evaluation,

3) review for impact on nuclear safety, 4) review by AEPSC gA, 5) design modification, 6)

AEPSC managerial

review, and 7) approval and record keeping for the implemented design change.

1.7.4 PROCUREMENT DOCUMENT CONTROL

,. 1.7.4.1 SCOPE Procurement documents define the characteristics of item(s) to be procured, identify applicable regulatory and industry codes/standards requirements and specify supplier guality Assurance Program requirements to the extent necessary to assure adequate quality.

, 1.7.4.2 IMPLEMENTATION 1.7.4.2.1 Procurement control is established by instructions and procedures.

These documents require that purchase documents be sufficiently detailed to ensure that purchased materials, components and services associated with safety-related structures or systems are:

1) purchased to specification and code requirements equivalent to those of the original equipment or service (except when the Code of federal Regulations requires upgrading),

2) properly documented to show compliance with the applicable specifica-

tions, codes and standards, and 3) purchased from vendors or contractors who have been evaluated and deemed qualified.

Procedures establish the review of procurement documents to determine that:

quality requirements are correctly stated, inspectable and 1.7-46

July, 1987

controllable; there are adequate acceptance criteria; procurement documents have been prepared, reviewed and approved in accordance with established requirements.

Each involved manager is responsible for assuring that the applicable gA

'equirements are set forth in the procurement documents.

The plant may request assistance of AEPSC cognizant engineers in any procurement activity.

1.7.4.2.2 The N-List/Facility Data Base, in conjunction with other sources, is used to determine equipment classification.

AEPSC Specifications for the Donald C.

Cook Nuclear Plant (DCC Specifications) are used to determine item and documentation requirements, codes or standards that items must fulfill,and define the documentation that must accompany the item to the plant.

Department heads cognizant of the equipment and its quality assurance requirements review procurement documents, as required, to ensure that:

correct classification is made; the appropriate plant specifications which identify quality requirements, are referenced or attached; and that the documentation reouirements are properly stated.

Purchase requisitions for new safety-related equipment are initiated by the AEPSC cognizant engineers who establish the initial equipment quality assurance requirements.

Replacement or spare equipment is procured via the original purchase requirements.

In instances where these requirements have been superseded by a revised specification, and when applicable the

'eplacement/spare part is procured to the revised requirements.

1.7-47

July, 1987

The contents of procurement documents vary according to the item(s) being

'urchased and its function(s) in the plant.

Provisions of this QAPD are considered for application to service contractors also.

As applicable, procurement documents include:

a)

Scope of work to be performed.

b)

Technical requirements, with applicable drawings, specifications, codes and standards identified by title, document number, revision and date, with any required procedures such as special process instructions identified in such a way as to indicate source and need.

c)

Regulatory, administrative and reporting requirements.

d)

Quality requirements appropriate to the complexity and scope of the work, including necessary tests and inspections.

e)

A requirement for a documented QA Program, subject to QA review and written concurrence prior to the start of work.

f)

A requirement for the supplier to invoke appl:icable quality require-ments on subtier suppliers.

g)

Provisions for access to supplier and subtier suppliers'acilities C

and records for inspections, surveillances and audits.

h)

Identification of documentation to be provided by the supplier, the schedule of submittals and documents requiring AEPSC approval.

1.7-48

July, 1987

1.7.4.2.4 The AEPSC gA Department performs off-line reviews of procurement docu-ments to assure that gA Program requirements have been met.

These reviews are conducted in accordance with AEPSC gA Department procedures..

1.7.4.2.5 Changes to procurement documents are controlled in a manner commensurate with that used for the original documents.

1.7.5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS 1.7.5.1 SCOPE Activities affecting the quality of safety-related structures, systems and components are accomplished using instructions, procedures and drawings appropriate to the circumstances, including acceptance criteria for determining if an activity has been satisfactorily completed.

1.7.5.2 IMPLEMENTATION 1.7.5.2.1 Instructions and procedures incorporate:

1) a description of the activity to be accomplished, and 2) appropriate quantitative (such as tolerances and operating limits) and qualitative (such as workmanship and standards) acceptance criteria sufficient to determine that the activity has been satisfactorily accomplished.

Hold points for inspection are established when required.

Instructions and procedures pertaining to the specification of and/or implementation of the gA Program receive multiple reviews for technical adequacy and inclusion of appropriate quality requirements.

Top tier instructions and procedures are reviewed and approved by AEPSC gA.

Lower tier documents are reviewed and approved, as a minimum by management/

1.7-49

July, 1987

supervisory personnel trained to the level necessary to plan, coordinate and administer those day-to-day, verification activities of the gA Program for which they are responsible.

Special procedures may be issued for activities which have short-term applicability.

1.7.5.2.2 AEPSC activities relative to the D.C.

Cook Nuclear Plant are outlined by procedures which provide the controls for the implementation of these activities.

AEPSC has two categories of gA Program implementation procedures:

1)

General Procedures which are applicable to all AEPSC divisions and departments involved with Cook Plant.

2)

Division/department/section procedures which apply to the specific division, department or section involved.

<: 1.7.5.2.3 The Plant Manager Instruc'tions have'been'classifi'ed into the following series:

1000 Organization 2000 Administration 3000 Procurement, Receiving, Shipping and Storage 4000 Operations, Fuel Handling, Surveillance Testing 5000 Maintenance, Repair, Modification, Eg and ISI 6000 Technical - Chemistry, Radiological Controls, Performance/

Engineering Testing, and Instrument and Control Maintenance and Calibration 7000 guality - guality Assurance, guality Control Program, Commitment Control and Condition/Problem Reporting 1.7-50

July, 1987

Instructions and procedures identify the regulatory requirements and commitments which pertain to the subject that it will control and estab-lish responsibilities for implementation.

Instructions and procedures may either provide the guidance necessary for the development of supple-mental instructions and/or procedures to implement their requirements, or provide comprehensive guidance based on the subject matter.

1.7.5.2.4 Plant drawings are produced, controlled and distributed under the control of AEPSC and the plant.

AEPSC design drawings are produced by the AEPSC Design Division under a set of procedures which direct their development and review.

These procedures specify requirements for inclusion of quantitative and qualitative acceptance criteria.

Specific drawings are reviewed and approved by the cognizant engineering divisions/department.

AEPSC has stationed an on-site design staff to provide for the revision of certain types of design drawings to reflect as-built conditions.

1.7.5.2.5 Complex plant procedures are designated as "In Hand" procedures.

Examples of "In Hand" procedures are those developed for extensive or complex jobs where reliance on memory cannot be trusted.

Further, those procedures which describe a sequence which cannot be altered or require the documen-tation of data during the course of the procedure, are considered "In Hand" procedures.

"In Hand" procedures are designated as such by double asterisks

(**) which precede the procedure number on the cover sheet, all pages and attachments of a procedure and the corresponding index.

1.7.6 DOCUMENT CONTROL 1.7.6.1 SCOPE Documents controlling activities within the scope defined in 1.7.2 herein are issued and changed according to established procedu'res.

Documents such as instructions, procedures and drawings, including changes

thereto, 1.7-51

July, 1987

are reviewed for adequacy, approved for release by authorized personnel and are distributed and used at the -location where a prescribed activity is performed.

Changes to controlled documents are reviewed and approved by the same organizations that performed the original review and approval, or by other qualified, responsible organizations specifically designated in accordance with the procedures governing these documents.

Obsolete or superseded documents are controlled to prevent inadvertent use.

1.7.6. 2 If IMPLEMENTATION

" 1.7.6.2.1 Controls are established for approval, issue and change of documents in the following categories:

a)"

Design documents (e.g., calculations, specifications, analyses).

b)

Drawings and related documents.

c)

Procurement documents.

d)

Instructions and procedures.

e)

Final Safety Analysis Report (FSAR).

f)

Plant Technical Specificatioris.

g)

Safeguards documents.

1.7.6.2.2 The review, approval, issuance and change of documents are controlled by:

a)

Establishment of criteria to ensure that adequate technical and quality requirements are incorporated.

b)

Identification of the organization responsible for review, approval, issue and maintenance.

c)

Review of changes to documents by'the 'organization that'erformed the initial review and approval, or by the organization designated 1.7-52

July, 1987

in accordance with the procedure governing the review and approval of specific types of documents.

Maintenance, modification and inspection procedures are reviewed by AEPSC gA for compliance with established inspection requirements.

1.7.6.2.3 Documents are issued and controlled so that:

a)

The documents are available prior to commencing work.

b)

Obsolete documents are replaced by current documents in a timely manner.

1.7.6.2.4 Master lists or equivalent controls are used to identify the current revision of instructions, procedures, specifications and drawings.

These control documents are updated and distributed to designated personnel who are responsible for maintaining current copies of the applicable documents.

The distribution of controlled documents is performed under procedures requiring receipt acknowledgement and in accordance with established distribution lists.

1.7.6.2.5 In the event a drawing is developed on-site to reflect an as-built configuration, the marked-up drawing is maintained in the Master Plant File and all holders of the drawing are issued appropriate notification to inform them the revision they hold is not current, cannot be used and, if required, reference must be made to the Master Plant File drawing.

1.7.6.2.6 Documents prepared for use in training or for interested parties are appropriately marked to indicate that they are for information use only, and cannot be used to operate or maintain the facility, or to conduct 1.7-53

July, 1987

activities affecting the quality of safety-related items.

At Cook Plant,l unless a document is identified as "co'ntrolled" it is automatically assumed the document is for informational use only.

1.7.7 CONTROL OF PURCHASED ITEMS AND SERVICES 1.7.7. 1 SCOPE Activities that implement approved procurement requests for items and services are controlled to assure conformance with procurement document requirements.

Controls include a system of supplier evaluation and selection, source inspection, surveillance, audit and acceptance of items and documentation upon delivery and periodic assessment of supplier performance.

Objective evidence of quality that demonstrates conformance with specified procurement document requirements is available to the nuclear power plant site prior to use of equipment, material, or services.

"= 1.7.7. 2 IMPLEMENTATION 1.7.7.2.1 AEPSC qualifies suppliers by performing a documented evaluation of their capability to provide items or services specified by procurement documents.

Items and services designated as safety-related are purchased from suppliers whose gA programs have been accepted in'"'accordance with AEPSC requirements.

Suppliers of other items/services, such as calibration, fire protection, records storage, etc.,

are evaluated also using different criteria for acceptance.

gualification of such suppliers and maintenance of a gualified Supplier List (gSL), maintained on a data base, is accom-plished by the AEPSC gA Department.

In the discharge of this responsibil-ity, the AEPSC gA Department utilizes information generated by others (such as the CASE Association and ASME) to aid in the supplier qualifica-tion process.

Distinction is made between suppliers, stocking distributors (warehouses) and sales offices.

The supplier or distributor must be approved for inclusion on the

(}SL before procurement can be completed.

1.7-54

July, 1987

AEPSC is a member of CASE and performs audits for submittal to the CASE Register as well as the plant's gualified Supplier List.

T/e CASE Register provides a prescreened list of potential suppliers with gA programs.

An evaluation is made if there is an interest in a CASE listed supplier to consider the scope of the qualification audit and the identity of the auditor which are stated in the Register.

Additional program surveys will be conducted, as necessary, to meet requirements.

Acceptance is not complete until it has been determined that the supplier; can meet the basic gA and technical requirements of the item or service

".~

that is required.

1.7.7.2.2 For items that are not unique to a nuclear power plant ("Commerical Grade" ) where requirements cannot be imposed in a practical manner at time of procurement, programs for dedication and upgrading to safety-related standards are established and accomplished by the AEPSC cognizant engineer prior to the item being accepted for safety-related use.

1.7.7.2.3 In-process surveillance of suppliers'ctivities during fabrication, inspection, testing and shipment of items is performed when deemed necessary, depending upon supplier qualification status, complexity and importance to safety of the item being furnished, and/or previous supplier history.

This surveillance is performed by the cognizant engineering department, responsible plant department, or AEPSC gA, or any combination thereof.

1.7.7.2.4 Spare and replacement parts are procured in such a manner that their performance and quality are at least equivalent to those of the parts that will be replaced.

1.7-55

July, 1987

a)

Specifications and codes referenced in procurement documents for spare or replacement items are at least equivalent to those for the original items or to properly reviewed and approved revisions.

b)

Parts intended as spares or replacement for "off-the-shelf" items, or other items for which quality requirements were not originally specified, are evaluated for performance at least equivalent to the original.

c)

Where quality requirements for the original items cannot be deter-mined, requirements and controls are established by engineering evaluation performed by qualified individuals.

The evaluation assures there is no adverse effect on interfaces; interchangeability, safety, fit, form, function, or compliance with applicable regulatory or code requirements.

Evaluation results are documented.

d)

Any additional or modified design criteria, imposed after previous procurement of the item(s), are identified and incorporated.

'~ 1.7.7.2.5 Instructions and procedures address requirements for supplier selection and control as well as procurement document contro'1.

The PHI on receipt inspection of safety-related items addresses the program for inspection of incoming items including a review of the documentation required under the procurement.

Receipt inspection personnel are qualified and certified in accordance with the requirements of ANSI N45.2.6.

Provisions for receipt inspection apply regardless of where the procurement originates.

Additional inspections may apply if required by the procurement document.

Where items and/or services are safety-related and procurement is accomplished without assistance of AEPSC; supplier selection is limited to those companies identified on the gualified Suppliers List (gSL).:.

1.7-56

July, 1987

1.7.7.2e6 Items received at the site are tagged with a "HOLD" tag and p1aced in a

designated, controlled area until receipt inspected.

During receipt inspection, designated material characteristics and attri.butes are

checked, and documentation is checked against the procurement documents.

If found acceptable, the "HOLD" tag is removed and replaced with an "ACCEPTED" tag and the item is placed in a designated area of the storeroom.

Item traceability to procurement documents and to end use is maintained through recording of "MOLD" and "ACCEPTED" tag number on applicable documents.

Nonconforming items, or missing or questionable documentation results in.

items being placed on "hold" and maintained in a designated, controlled area of the storeroom.

If the nonconformance cannot be cleared, the item is either scrapped, returned to manufacturer, or dispositioned through engineering analysis.

1.7.7.2.7 Contractors providing services (on-site) for safety-related components, are required to have either a formal ouality assurance program and procedures, or they must abide by the plant guality'Assurance Program and procedures.

Prior to their working at the plant,.contractor quality assurance programs must be reviewed and approved by the AEPSC guality Assurance Supervisor.

Contractor procedures must be reviewed and approved by the guality Assurance Supervisor, PNSRC and the Plant Manager.

Further, periodic audits of site contractor activities are conducted under the direction of the AEPSC guality Assurance Supervisor.

1.7.7.2.8 Suppliers are required to furnish the following records:

a)

Applicable drawings and related engineering documentation that identify the purchased item and the specific procurement require-ments (e.g.,

codes, standards and specifications) met by the item.

1.7-57

July, 1987

, b)

Documentation identifying any procurement requirements that have not been met.

c)

A description of those 'nonconformances from the procurement require-ments dispositioned "use-as-is" or "repair".

d) guality records as specified in the procurement requirements.

1.7.7.2.9

, The validity of supplier certificates of conformance is evaluated at the time of supplier resurvey and requalification, and is based on the

• continual'mplementation of the supplier's gA program.

j

,. 1.7.8 IDENTIFICATION AND CONTROL OF ITEMS

. 1.7.8.1 SCOPE Items are identified and controlled to prevent their inadvertent use.

Identification of items is maintained either on the items, their storage areas or containers, or on records traceable to the items.

1.7.8;2 IMPLEMENTATION 1.7.8.2.1 Controls are established that provide for the identification and control of items (including partially fabricated assemblies).

1.7.8.2.2 Items are identified by physically marking the item or its container, and by maintaining records traceable to the item.

The method of identi-fication is such that the quality of the item is not degraded.

1.7-58

July, 1987

1.7.8.2.3 Items are traceable to applicable drawings, specifications or other pertinent documents to ensure that only correct and acceptable items are'sed.

Verification of traceability is performed and documented prior to'-'elease for fabrication, assembly, or installation.

1.7.8.2.4 Requirements for the identification by use of heat number, part number, or serial number are included in the specifications and/or purchase order.

1.7.8.2.5 Separate storage is provided for incorrect or defective items that are on-

hold, and material which has been accepted for use.

All safety-related items are appropriately tagged or identified (stamping, etc.) to provide easy identification as to the items'sage status.

Records are maintained for the issue of items, to provide traceability from storage to end use in the plant.

1.7.8.2.6 When materials are subdivided, appropriate identification numbers are transferred to each section of the material, or traceability is main-tained through documentation.

1.7.9 CONTROL OF SPECIAL PROCESSES 1.7.9.1 SCOPE Special processes are controlled and are accomplished by qualified personnel using approved procedures and equipment in accordance with applicable

codes, standards, specifications, criteria and other special requirements.

1.7-59

July, 1987

1.7.9.2 IMPLEMENTATION 1.7.9.2.1 Processes subject to special process controls are those for which full verification or characterization by direct inspection is impossible or impractical.

Such processes include welding, heat treating, chemical cleaning, application of protective coatings, concrete placement and nondestructive examination.

1.7.9.2.2 I

Special process requirements for chemical cleaning, application of protective coatings and concrete placement are set forth in AEPSC Speci-fications (DCCs) and/or directives prepared by the responsible AEPSC cognizant engineer.

These documents are reviewed and approved by other personnel with the necessary technical competence.

AEPSC Specifications are reviewed by the AEPSC.,(A Department.

Special process requirements for welding, heat treating and nondestruc-tive examination (NDE) are set forth in AEPSC Specifications, the AEP Welding and NDE Manuals and plant procedures.

These specifications and manuals are prepared by or are reviewed and approved by the AEPSC Staff Engineer - Chief Metallurgist (NDE Administrator).

The administrative controls portion of the NDE Manual is reviewed by~the AEPSC Manager of guality Assurance or designee.

Special process procedures, with the exception of welding and heat

treating, are prepared by plant personnel with technical knowledge in the discipline involved.

These procedures are reviewed by other personnel with the necessary technical competence and are qualified by testing.

Welding is performed in accordance with procedures developed to comply with requirements contained in the AEP Welding Manual.

These procedures are qualified in accordance with applicable codes and standards,

and, 1.7-60

July, 1987

Procedure Qualification Records are prepared.

The weld Procedure gualifi-cation Record is reviewed and approved by the AEPSC Staff Engineer-Chief Metallurgist.

Meld qualification documentation is retained in the AEP Melding Manual.

Contractor welding procedures are qualified by the contractor.

These procedures and the qualification documentation are reviewed and approved.":

by the plant and the AEPSC Staff Engineer - Chief Metallurgist.

This documentation is retained by the contractor.

1.7.9.2.3 Nondestructive examination personnel are qualified and certified by either a designated NDE Administrator or by a Cook Plant NDE Level III (NDE Supervisor) who has been qualified and certified by the designated 4

NDE Administrator.

Certification is by examination.

Personnel qualifi-~'ation is kept current by performance of the special process(es) and/or reexamination at time intervals specified by the AEP NDE Manual.

Unsat-'sfactory performance or, where applicable, failure to perform within the designated time intervals, requires recertification.

'I

'lant welders are qualified by the Maintenance Department utilizing the procedures in the AEP fielding Manual.

Examination of specimens is performed by the gC Department in accordance with the AEPSC Specification covering welder qualification.

Plant welder qualification records are maintained for each welder by the Maintenance Department.

Contractor and craft welders are qualified by the contractor utilizing procedures approved by the plant and the AEPSC Staff Engineer - Chief Metallurgist.

Contractor and craft welder qualification records are maintained by the contractor.

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July, 1987

1.?.9.2.4 guality Control Technicians assigned to the guality Control Department perform nondestructive testing for work performed by plant and contractor personnel.

These individuals are qualified to either SNT-TC-1A or ANSI N45.2.6 and records of the qualifications/certifications are maintained at the plant.

1.7.9.2.5 For special processes that require qualified equipment, such equipment is qualified in accordance with applicable codes, standards and specifications.

~ 1.7.9.2.6 Special process qualifications are reviewed during regularly scheduled gA audits.

gualification records are maintained in accordance with 1.7.17 herein.

1.7.9.2.7 The documentation resulting from welding and nondestructive testing is reviewed by appropriate management personnel.

1.7. 10 INSPECTION 1.7.10.1 SCOPE Activities affecting the quality of safety-related structures, systems and components are inspected to verify their conformance with require-ments.

These inspections are performed by personnel other than those who perform the activity.

Inspections are performed by qualified personnel utilizing written procedures which establish prerequisites and provide documentation for evaluating test and inspection results.

Direct inspec-tion, process monitoring, or both, are used as necessary.

When applicable, hold points are used to ensure that inspections are accomplished at the correct points in the sequence of activities.

1.7-62

July, 1987

1.7. 10. 2 IMPLEMENTATION 1.7.10.2.1 Inspections are applied to appropriate activities to assure conformance ;

to specified requirements.

Hold points are provided in the sequence of procedures to allow for the inspection, witnessing, examination, measurement, or review necessary to assure that the critical or irreversible elements of an activity are being performed as required.

Note that hold points may not apply to all procedures but each must be reviewed for this attribute.

Hold points specify exactly what is to be done (e.g.,

type of inspection or examination, etc.),

acceptance criteria, or reference to another procedure, etc., for the satisfactory completion of the hold point.

When included in the sequence of a procedure, the activities required

bye, hold points are completed prior to continuing work beyond that point.

Process monitoring is used in whole or in part where direct inspection alone is impractical or inadequate.

1.7.10.2.2 Training, qualification and certification programs for personnel who perform inspections are established, implemented and documented in accordance with 1.7.2 herein and as described in Appendix B hereto, item 9b, with exceptions as noted therein.

1.7.10.2.3 Inspection requirements are specified in procedures, instructions, drawings, or checklists as applicable.

They provide for the following as appropriate:

1.7-63

July, 1987

t a)

Identification of applicable revisions of required instructions,

'P drawings and specifications.

b)

Identification of characteristics and activities to be inspected.

c)

Inspection methods.

d)

Specification of measuring and test equipment having the necessary accuracy.

e)

Identification of personnel responsible for performing the inspection.

f)

Acceptance and rejection criteria.

g)

Recording of the inspection results and the identification of the inspector.

1.7.10.2.4 Inspections are conducted using the following programs:

a)

Work Activities Performed b

18MECo Personnel Work functions associated with normal operation of the plant, routine maintenance, calibrations, etc.,

are routinely assigned to plant personnel.

18MECo personnel who inspect this work are qualified in accordance with Regulatory. Guide 1.8 and ANSI N18.1, and are periodically trained in their skill area using INPO "accreditable" training.

As a result of the qualifications and training which IIIMECO personnel

receive, a peer inspection system is used.

Peer inspection personnel are independent in that they do not perform or directly supervise the work being inspected, but may be from the same work group.

Cook Plant guality Control Department personnel qualified in

-accordance with Regulatory Guide 1.8 and ANSI N18.1 will ensure (through surveillance) that inspections have been correctly implemented and make routine reports to management.

1.7-64

July, 1987

b)

Work Activities Performed b

Contractors Major modifications, non-routine maintenance, and/or other services on safety-related items are generally performed by contractors, who are required to comply with the applicable requirements of Regulatory Guide 1.58 and ANSI N45.2.

Inspections of these work activities are performed by inspectors qualified and certified in accordance with Regulatory Guide 1.58 and ANSI N45.2.6.

A peer inspection program is not used for work activities performed by these personnel.

Contractor inspection personnel are required to be qualified and certified in accordance with Regulatory Guide 1.58 and ANSI N45.2.6.

18MECo Cook Plant guality Control personnel who are also qualified and certified in accordance with Regulatory Guide 1.58 and ANSI N45.2.6 may perform inspections and/or surveillances of these activities.

'.7.10.2.5 Inspections are performed, documented, and the results evaluated by designated personnel in order to ensure that the results substantiate the acceptability of the item or work.

Evaluation and review results are documented.

1.7. 11 TEST CONTROL 1.7.11.1 SCOPE Testing is performed in accordance with established programs to demon-strate that structures, systems and components will perform satis-factorily in service.

The testing is performed by qualified personnel in accordance with written procedures that incorporate specified require-ments and acceptance criteria.

Types of tests are:

Scheduled Surveillance, preventive maintenance, post-design, qualification.

1.7-65

July, 1987

Unscheduled Pre-and post-maintenance.

Test parameters (including any prerequisites),

instrumentation require-ments and environmental conditions, are specified in test procedures.

Test results are documented and evaluated.

1.7. 11. 2 IMPLfMENTATION

- 1.7.11.2.1 Tests are performed in accordance with programs, procedures and criteria that designate when tests are required and how they are to be performed.

Such testing includes the following:

a) gualification tests, as applicable, to verify design adequacy.

b)

Acceptance tests of equipment and components to assure their opera-tion prior to delivery or installation.

c)

Post-design tests to assure proper and safe operation of systems and equipment prior to unrestricted operation.

d)

Surveillance tests to assure continuing proper and safe operation of systems and equipment.

The PMI on surveillance testing controls the periodic testing of equipment and systems to fulfillthe surveillance requirements established by the Technical Specifications.

Controls have been established to idertify uncompleted surveillance testing to assure it is rescheduled for completion to meet Technical Specifi-cation frequency requirements.

Data taken during surveillance testing is reviewed by appropriate management personnel to assure that acceptance criteria is fulfilled, or corrective action is taken to correct deficiencies.

e)

Maintenance tests after preventive or corrective maintenance.

1.7-66

July, 1987

1.7.11.2.2 Test procedures, as required, provide mandatory hold points for witness, or review.

1.7.11.2.3 Testing is accomplished after installation, maintenance, or repair, by surveillance test procedures or performance tests which must be satisfac-torily completed prior to determining the equipment is in an operable status.

All data resulting from these tests is retained at the plant after review by appropriate management personnel.

1.7.12 CONTROL OF MEASURING AND TEST E(UIPNENT 1.7.12.1 SCOPE Neasuring and testing equipment used in activities affecting the quality of safety-related

systems, components and structures are properly iden-

,~

tified, controlled, calibrated and adjusted at specified intervals to maintain accuracy within necessary limits.

1.7. 12. 2 IMPLEMENTATION 1.7.12.2.1 Each involved plant department has established procedures for calibration and control of measuring and test equipment utilized in the measurement, inspection and monitoring of structures, systems and components.

These procedures describe calibration techniques and frequencies, and mainte-nance and control of the equipment.

AEPSC guality Assurance periodically assesses the effectiveness of the calibration program via the gA audit program.

1.7-67

July, 1987

Measuring and test equipment is uniquely identified and is traceable to its calibration source.

1.7.12.2.3 A system has been established for attaching or affixing labels to measuring and test equipment to display the date calibrated and the next calibration due date or a control system is used that identifies to potential users any equipment beyond the calibration due date.

1.7.12.2.4 Measuring and test equipment is calibrated at specified intervals.

These intervals are based on the frequency of use, stability characteristics and other conditions that could adversely affect the required measurement accuracy.

Calibration standards are traceable to nationally recognized standards, or where such standards do not exist provisions are established to document the basis for calibration.

The primary standards used to calibrate secondary standards

have, except in certain instances, an accuracy of at least four (4) times the required accuracy of the secondary standard.

In those cases where the four (4) times accuracy cannot be achieved, the basis for acceptance is documented and is authorized by the responsible manager.

The secondary standards have an accuracy that assures equipment being calibrated will be within required tolerances.

The basis for acceptance is documented and authorized by the responsible manager.

1.7.12.2.5 Plant procedures define the requirements for the control of standards, test'quipment and process equipment.

1.7-68

July, 1987

1.7.12.2.6 When measuring and testing equipment used for inspection and testing is>>

found to be outside of required accuracy limits at the time of calibration, evaluations are conducted to determine the validity of the results obtained since the most recent calibration.

Retests or reinspections are performed on suspect items.

The results of evaluations are documented.

1.7.13 HANDLING, STORAGE, AND SHIPPING 1.7. 13. 1 SCOPE Activities with the potential for causing contamination or deterioration, by environmental conditions such as temperature or humidity that could adversely affect the ability of an item to perform its safety-related functions and activities necessary to prevent damage or loss are identi-,'ied and controlled.

These activities are cleaning, packaging, preserving, handling, shipping and storing.

Controls are effected through the use of appropriate procedures and instructions.

1.7. 13. 2 IMPLEMENTATION 1.7.13.2.1 Procedures are used to control the cleaning, handling, storing, packaging, preserving and shipping of materials, components and systems in accordance with designated procurement requirements.

These procedures include, but are not limited to, the following functions:

a)

Cleaning - to assure that required cleanliness levels are achieved and maintained.

b)

Packaging and preservation

- to provide adequate protection against damage or deterioration.

When necessary, these procedures provide for special environments such as inert gas atmosphere, specific moisture content levels and temperature levels.

1.7-69

July, 1987

c)

Handling - to preclude damage or safety hazards.

d)

Storing - to minimize the possibility of loss,

damage, or deterio-

'ration of items in storage, including consumables such as chemicals, reagents and lubricants.

1.7.13.2.2 Controls have been established for limited shelf life items such as "0" rings, epoxy, lubricants, solvents and chemicals to assure they are correctly identified, stored and controlled to prevent shelf life expired materials from being used in the plant.

Controls are established in plant procedures.

IA 4 1.7.13.2.3 Packaging and shipping requirements are provided to vendors with the AEPSC Specifications (DCCs) which are a part of the purchase order.

Controls for receipt inspection, damaged items and special handling requirements at the plant are established by plant procedures.

Special controls are provided to assure that stainless steel components and materials are haridled with approved lifting slings.

1.7. 13.2.4 Storage and surveillance requirements have been established to assure segregation of storage.

Special controls have been implemented for critical, high value, or perishable items.

Routine surveillance is conducted on stored material to provide inspection for damage, rotation of stored pumps and motors, inspection for protection of exposed surfaces and cleanliness of the storage area.

1.7-70

July, 1987

1.7.13.2.5 Special handling procedures have been implemented for the processing of.

nuclear fuel during refueling outages.

These procedures minimize the risk of damage to the rew and spent fuel and the possible release of radioactive material when placing the spent fuel into the spent fuel pool.

1.7. 14 INSPECTION, TEST, AND OPERATING STATUS 1.7.14.1 SCOPE Operating status of structures, systems and components is indicated by tagging of valves and switches, or by other specified

means, in such a

manner as to prevent inadvertent operation.

The status of inspections and tests performed on individual items is clearly indicated by markings and/or logging under strict procedural controls to prevent inadvertent I

bypassing of such inspections and tests.

1.7.14. 2 IMPLENENTATION 1.7.14.2.1 For design change (RFC) activities, including item fabrication, instal-lation and test, a program exi'sts which specifies the degree of control required for the identification of inspection and test status of struc-

tures, systems and components.

Physical identification is used to the extent practical to indicate the status of items requiring inspections,

tests, or examinations.

Proce-dures exist which provide for the use of calibration and rejection

stickers, tags, stamps and other forms of identification to indicate test and inspection status.

The Clearance Permit System uses various tags to identify equipment and system operability status.

Another program establishes a tagging system for lifted leads, etc.

For those items requiring calibration, the program provides for physical indication of calibration status by calibration stickers or a control system is used.

'I 1 07 71

July, 1987

Application and removal of inspection and welding stamps, and of such status indicators as tags, marking, labels, etc., is controlled by plant procedures.

The inspection status of materials received at the plant is identified in accordance with established instructions.

The status is identified as Hold, Hold for guality Control Clearance, Reject, or Accept.

The inspection status of work in progress is controlled by the use of hold points in procedures.

Plant guality Control or departmental super-visory personnel inspect ar. activity at various stages and sign off the procedural steps covered by the inspection.

The status of welding is controlled through the use of a weld data block which identifies the inspection and nondestructive examination status of each weld.

1.7.14.2.3 Required surveillance test procedures are defined in PMIs.

These instructions provide for documenting bypassed

tests, and rescheduling of

~

the test.

The status of testing after minor maintenance is recorded as part of the job order.

The status of testing after major maintenance is included as part of the procedure, and includes the performance of functional testing and approval of data by supervisory personnel.

Testing, inspection and other operations important to safety are conducted in accordance with properly reviewed and approved procedures.

The PMI for plant procedures requires that procedures be followed as written.

Alteration to the sequence of a procedure can only be accomplished by a procedure change which is subject to the same controls 1.7-72

July, 1987

as the original review and approval.

When an immediate procedure change is required to continue in-process work or testing and the required complete review and approval process can not be accomplished, an "On The'pot" change is processed in accordance with the PMI on plant procedures.

1.7.14.2.4 Nonconforming, inoperable, or mal functioning str uctures, systems and A

components are clearly identified by tags, stickers, stamps, etc.,

and documented to prevent inadvertent use.

1.7.15 NONCONFORMING ITEMS 1.7.15.2 SCOPE Materials, parts, or components that do not conform to requirements are controlled in order to prevent their inadvertent use.

Nonconforming items are identified, documented, segregated when practical and disposi-.~

tioned.

Affected organizations are notified of nonconformances.

1.7. 15. 2 IMPLEMENTATION 1.7.15.2.1 Items, services, or activities that are deficient in characteristic, documentation, or procedure, which render the quality unacceptable or indeterminate, are identified as nonconforming, and any further use is controlled.

Nonconformances are documented and dispositioned, and notification is made to affected organizations.

Personnel authorized to disposition, conditionally release and close out nonconformances are designated.

The Job Order System and/or the Condition/Problem Reports (refer to 1.7. 16 herein) are used at Cook Plant to identify nonconforming items and initiate correct ve action.

Systems, components, or materials which 1.7-73

July, 1987

require repair or inspection are controlled under the Job Order System.

In addition, the various procedures identified in 1.7.14 herein prov'ide for identification, segregation and documentation of nonconforming items.

1.7.15.2.2 Nonconforming items are identified by marking, tagging, segregating, or by documented administrative controls.

Documentation describes the nonconformance, the disposition of the nonconformance and the inspection requirements.

It also includes signature approval of the disposition.

Completed Job Orders are reviewed by the supervisor responsible for accomplishing the work and the supervisor of the department/section that originated the Job Order.

The gA Department per'i'odically audits the Job Order System, and on a sample basis, Job Orders.

4. 1.7.15.2.3 Items that have been repaired or reworked are inspected and tested in accordance with the original inspection and test requirements or alterna-tives that have been documented.

Items that have the disposition of "repair" or "use-as-is" require documentation justifying acceptability.

The changes are recorded to denote the as-built condition.

When required by established procedures, surveillance or operability tests are conducted on an item after rework, repair or replacement.

~ 1.7.15.2.4 Disposition of conditionally released items are closed out before the.

items are relied upon to perform safety-related functions.

1.7-74

July, 1987

1.7.16 CORRECTIVE ACTION 1.7.16.1 SCOPE Conditions adverse to quality, such as failures, malfunctions, deficien-cies, deviations, defective material and equipment and nonconformances, are identified promptly and corrected as soon as practical.

For significant conditions adverse to quality, the cause of the condition<

is determined, corrective action is taken to correct the immediate

problem, and preventive action is implemented to prevent recurrence.

In these

cases, the condition, cause and corrective action taken is docu-mented and reported to appropriate levels of management.

1.7. 16. 2 t1PL EHENTATION 1.7.16.2.1 Procedures are established that describe the plant and AEPSC corrective action programs.

These procedures are reviewed and concurred with by the AEPSC QA Department.

1.7.16.2.2 Condition/Problem Reports provide the mechanism for plant and AEPSC

"'personnel'o notify management of conditions adverse to quality.

't'y Condition/Problem Reports are also used to report violations to codes, regulations and the Technical Specifications.

Investigations of reported conditions adverse to quality are assigned by management.

The 4

Condition/Problem Report is used to document the investigation of a problem; and to identify the need for a design change to correct system or equipment deficiencies, or to identify the need for the initiation of Job Orders to correct minor deficiencies.

Further, Condition/Problem Reports are used to identify those actions necessary to prevent recurrence of the reported condition.

1.7-75

July, 1987

Significant problems, which are so designated on Condition/Problem

Reports, are reviewed by the Cook Plant Nuclear Safety Review Committee (PNSRC) for evaluation of actions taken or being taken to correct the deficiency and prevent recurrence.

The AEPSC Nuclear Safety and Design Review Committee (NSDRC) is responsible for assuring that independent reviews of violations (as specified in the Technical Specifications) are performed.

These violations are considered significant problems which are documented on Condition/Problem Reports.

The reviews will provide an independent evaluation of the reported problems and corrective actions.

The AEPSC gA Department periodically audits the corrective action systems for compliance and effectiveness.

1.7.17 EQUALITY ASSURANCE RECORDS 1.7.17.1 SCOPE Records that furnish evidence of activities affecting the quality of safety-related structures, systems and components are maintained.

They are accurate, complete, legible and are protected against damage, deteri-oration, or loss.

They are identifiable and retrievable.

1.7. 17. 2 IMPLEMENTATION 1.7.17.2.1 Documents that furnish evidence of activities affecting the quality of safety-related items are generated and controlled in accordance with the procedure that governs those activities.

Upon completion, these documents are considered records.

These records include:

a)

Results of reviews, inspections, surveillances,

tests, audits and material analyses.

b)

~ gualification of personnel, procedures and equipment.

c)

Operation logs.

1.7-76

July, 1987

d) e)

f) g)

h) i)

Maintenance and modification procedures and related inspection results.

Reportable occurrences.

Records required by the plant Technical Specifications.

Condition/Problem Reports.

Corrective action reports.

Other documentation such as drawings, specifications, procurement documents, calibration procedures and reports.

Radiographs (which are also classified as safety-related items).

1.7.17.2.2 Instructions and.procedures establish the requirements for the identi-fication and preparation of records for systems and equipment under the

(}uality Assurance

Program, and provides the controls for retention of these records.

Criteria for the storage location of quality related records and a

retention schedule for these records has been established.

File Indexes have been established to provide direction for filing and to provide for the retrievability of the records.

Controls have been established for limiting access to the Plant Master File to prevent unauthorized entry, unauthorized removal and for use of the records under emergency conditions.

The Accounting Supervisor is responsible for the control and operation of the plant master file room.

1.7.17.2.3 Within AEPSC, each department/division manager is responsible for the identification, collection, maintenance and storage of records generated by their department/division.

Procedures ensure the maintenance of records sufficient to furnish objective evidence that activities affecting quality are in compliance with the established gA Program.

1.7-77

July, 1987

1.7.17.2.4 When a document becomes a record, it is designated as permanent or nonpermanent and then transmitted to file.

Nonpermanent records, have specified retention times.

Permanent records are maintained for the life of the plant or equipment, as applicable.

'; 1.7.17.2.5 Only authorized personnel may issue corrections or supplements to records.

1.7.17.2.6 Traceability between the record and the item or activity to which it applies is provided.

1.7.17.2.7 Except for records that can only be stored as originals, such as radio-graphs and some str ip charts,

records, or micrographs, thereof, are stored in remote, dual facilities to prevent

damage, deterioration, or loss due to natural or unnatural causes.

When only the single original can be

retained, special fire-rated facilities are used;~

1.7.18 AUDITS 1.7.18.1 SCOPE A comprehensive system of audits is carried out to provide independent evaluation of compliance with, and the effectiveness of the guality Assurance

Program, including those elements of the program implemented by suppliers and contractors.

Audits are performed in accordance with written procedures or checklists by qualified personnel not having direct responsibility in the areas audited.

Audit results are documented and are reviewed by management.

Follow-up action is taken where indicated.

1.7-78

July, 1987

1.7. 18. 2 IMPLEMENTATION 1.7.18.2.1 AEPSC A De artment Res onsibilities The basic responsibility for the assessment of the guality Assurance Program is vested in the AEPSC gA Department.

The AEPSC guality Assurance Department is primarily responsible for ensuring that proper gA programs are established and for verification of their implementation.

These responsibilities are discharged in cooperation with the AEPSC and plant management, and their staffs.

1.7.18.2.2 Internal audits are performed in accordance with established schedules that reflect the status and importance of safety to the activities being performed.

All areas where the requirements of 10CFR50, Appendix B apply are audited within a period'f one to two years.

1.7.18.2.3 The AEPSC guality Assurance Department conducts audits to verify the adequacy and implementation of the guality Assurance Program at the plant and within the AEP System.

gA audit reports are distributed to: the Plant Manager and PNSRC (site audits);

and the NSDRC (all audits).

1.7.18.2.4 The independent off-site review and audit organization is the AEPSC Nuclear Safety and Design Review Committee (NSDRC).

This committee is composed of AEPSC, ISMECo and plant management members.

An NSDRC Manual has been developed for this committee which contains the NSDRC Charter and procedures.

The NSDRC conducts periodic audits of plant operations pursuant to established criteria (Technical Specifications, etc.).

1.7-79

July, 1987

NSDRC audit reports are submitted for review to the Chairman of the NSDRC and to the Vice Chairman - Engineering and Construction.

Problem Reports provide for the recording of actions taken to correct deficiencies found during these audits.

1.7.18.2.5 The plant on-site review group is the Plant Nuclear Safety Review Committee (PNSRC).

This committee reviews plant operations as a routine evaluation and serves to advise the Plant Manager on matters related to nuclear safety.

The composition of the committee is defined in the Technical Specifications.

The PNSRC also reviews instructions and procedures, and design changes for safety-related systems prior to approval by the Plant Manager.

In addition, this committee serves to conduct investigations of violations to Technical Specifications, and reviews significant Problem Reports to determine if appropriate action has been taken.

1.7.18.2.6 Audits of suppliers and contractors are scheduled based on the status of safety importance of the activities being performed, and are initiated early enough to assure. effective quality assurance during design, pro-

curement, manufacturing, construction, installation, inspection and testing.

Principal contractors are required to audit their suppliers systematically in accordance with the criteria established within their quality assurance programs.

1.7-80

July, 1987

Regularly scheduled audits are supplemented by "special audits" when significant changes are made in the guality Assurance

Program, when it is suspected that quality is in jeopardy, or when an independent assessment of program effectiveness is considered necessary.

1.7.18.2".8 Audits include an objective evaluation of practices, procedures, instructions, activities and items related to quality; and review of documents and records to confirm that the guality Assurance Program is effective and properly implemented.

1.7.18.2.9 Audit procedures and the scope, plans, checklists and results of indivi-0 dual audits are documented.

1.7.18.2.10 Personnel selected for auditing assignments have experience or are given training commensurate with the needs of the audit and have no direct responsibilities in the areas audited.

1.7.18.2.11 t1anagement of the audited organization identifies and takes appropriate action to correct observed deficiencies and to prevent recurrence.

Follow-up is performed by the auditing organization to ensure that the appropriate actions were taken.

Such follow-up includes reaudits when necessary; 1.7-81

July, 1987

1.7.18.2.12 The adequacy of the Quality Assurance Program is regularly assessed by AEPSC management.

The following activities constitute formal elements of that assessment:

a)

Audit reports, including follow-up on corrective action accomplish-ment and effectiveness, are distributed to appropriate levels of management.

b)

Individuals independent from the Quality Assurance organization, but knowledgeable in auditing and quality assurance, periodically review the effectiveness of the Quality Assurance Programs.

Conclusions and recommendations are reported to the AEPSC Vice President-Nuclear Operations.

.'. 1.7.19 FIRE PROTECTION QA PROGRAM

'.7.19.1 Introduction The Cook Plant Fire Protection QA Program has been developed using the guidance of the NRC Branch Technical Position 9.5-1, Appendix "A" (APSCB).

This Fire Protection QA Program is applicable to:"-')

Fire protection equipment that protects safety-related items which appear in the Fire Protection Technical Specifications;

and, 2)

Other fire protection equipment and/or services considered to be of such importance as to be covered by the Fire Protection QA Program.

Implementation of the Fire Protection QA Program is the responsibility of each involved AEP organization.

1.7-82

July, 1987

The Fire Protection gA Program at Cook Plant applies to the following activities:

design, procurement, fabrication, construction, surveillance, inspection, operation, maintenance, modification and audits.

l.i.19. 0~i The Fire Protection CA Program is under the management control of AEPSC.,i This control consists of:

1)

Formulating and verifying that the Fire Protection gA Program incorporates suitable requirements and is acceptable to the manage-,

ment responsible for fire protection;

and, 2)

'erifying the effectiveness of the Fire Protection gA Program through review, surveillance and audits.

The Fire Protection gA Program is part of the overall plant gA Program.

These gA criteria apply to those items within the scope of the Fire Protection gA

Program, such as fire detection/annunciation systems, fire barrier assemblies/materials, fire suppression

systems, extinguishing equipment, etc.,

and as well as the fire protection requirements of>

applicable safety-related equipment.

AEPSC and plant management have direct functional responsibility for the formulation, implementation and assessment of the Cook Plant Fire Protection gA Program.

Building layout and fire suppression and fire detection systems have been coordinated and designed commensurate with fire areas within the plant.

Operation and maintenance information has been provided to the plant in the form of System Descriptions and equipment supplier instruction material.

1.7-83

July, 1987

The Fire Protection gA Program at Cook Plant provides fot inspection of fire and explosion hazards and training, of fire brigades and responding fire departments.

The Plant Manager has delegated responsibility to various plant departments for the following fire protection activities:

a) b)

c) d)

e) f)

g)

Maintenance of fire protection systems, Testing of fire protection equipment, Fire safety inspections, Fire fighting procedures, Fire drills, Emergency safe shut-down procedures, and Emergency repair procedures (10CFR50, Appendix R).

The Assistant Shift Supervisor on duty, or designee is designated as the Fire Brigade Leader and coordinates the fire fighting efforts of shift personnel and the Fire Brigade.

1.7.19.3 Desi n Control and Procurement Document Control guality standards are specified in the design documents such as appropri-ate fire protection codes and standards, and as necessary deviations and changes from these quality standards are controlled.

The plant design was reviewed by qualified personnel to assure inclusion of appropriate fire protection requirements.

These reviews include items such as:

1)

Peviews to verify adequacy of electrical isolation and cable separation criteria.

2)

Reviews to verify appropriate requirements for room isolation (sealing penetrations, floors and other fire barriers).

3)

Reviews to determine increase in fire loadings.

1.7-84

July, 1987

4)

Reviews to determine the need for additional fire detection and suppression equipment.

A review and concurrence of the adequacy of fire protection requirements.-.

and quality requirements stated in procurement documents is performed.

This review determines that fire protection requirements and quality requirements are correctly stated, verifiable and controllable; there are'dequate acceptance and rejection criteria; and the procurement document has been prepared,-reviewed and approved in accordance with gA Program requirements.

Design and procurement document

changes, including field changes and design deviations are subject to the same level of controls, reviews and

" 'pprovals that were applicable to the original document.

wt 1.7. 19.4 Instructions, Procedures and Drawin s Inspections,

tests, administrative controls, fire drills and training that govern the Fire Protection iiA Program are prescribed by documented instructions, procedures, or drawings, and are accomplished in accordance with these documents.

Indoctrination and training programs for fire prevention and fire

". fighting are implemented in accordance with documented procedures.

Activities associated with the fire protection system are prescribed and accomplished in accordarce with documented instructions, procedures and drawings.

Instructions and procedures for design installation, inspection, test, maintenance, modification and administrative controls are reviewed to assure that proper fire protection requirements are included.

1.7-85

July, 1987

1.7.19e5 Control of Purcha'sed Items and Services Measures are established to assure that purchased items and services conform to the procurement documents.

These measures include provisions, as appropriate, for source evaluation and selection, objective evidence of quality furnished by the contractor, inspections at suppliers, or receiving inspections.

Source or receiving inspection is provided, as a minimum, for those items whose quality cannot be verified after installation.

1.7.19.6

~Ins ection A program for independent inspection of the fire protection activities has been established and implemented.

These inspections are performed by personnel other than those responsible for implementation of the activity.

The inspections include:

a)

Inspection of installation, maintenance and modification of fire protection systems and equipment.

b)

In'spections of penetration seals and fire retardant coating instal-lations to verify the activity is satisfactorily completed.

c)

Inspections of cable routing to verify conformance with design requirements.

d)

Inspections to verify that appropriate requirements for room isola-tion are accomplished following construction or modification activities.

1.7-86

July, 1987

e)

Measures to assure that inspection personnel are independent from the individuals performing the activity being inspected, and are knowledgeable in the design and installation requirements for fire'>

protection.

Inspection procedures, instructions and/or checklists are provided for inspections.

g)

Periodic inspections of fire protection systems, emergency breathing and auxiliary equipment.

h)

Periodic inspections of materials subject to degradation such as fire stops, seals and fire retardant coating.

1.7.19.7 Test and Test Control a)

Installation testing - Following installation, modification, repair; or replacement, sufficient testing is performed to demonstrate that; the fire protection systems and equipment will perform satisfactorily.

lfritten test procedures for installation tests incorporate the requirements and acceptance limits contained in applicable design documents.

b)

Periodic testing - Periodic testing schedules and methods have been implemented and the results documented.

Fire protection equipment is tested periodically to assure that the equipment functions properly.

c)

Programs have been established to verify the testing of fire protec-tion systems and to verify that test personnel are effectively trained.

d)

Test results are documented, evaluated, and their acceptability determined by a qualified responsible individual or group.'.7-87

July, 1987

1.7.19.8 Ins ection, Test and 0 eratin Status The inspection, test and operating status for fire protection systems are performed as described in 1.7.14 herein.

1.7.19.9 Honconformin Items Technical Specification fire protection equipment nonconformances are identified and dispositioned as described in 1.7.15 herein.

1.7.19. 10 Corrective Action The corrective action mechanism described in 1.7.16 herein applies to the Technical Specification fire protection equipment.

1.7.19.11 Records Records generated to support fire protection systems and components are controlled as described in 1.7.17 herein.

1.7.19.12 Audits Audits are conducted and documented to verify compliance with the Fire Protection gA Program as described in 1.7.18 herein.

Audits are periodically performed to verify compliance with the adminis-trative controls and implementation of quality assurance criteria.

The audits are performed in accordance with preestablished written procedures or checklists.

Audit results are documented and reviewed by management having responsibility in the area audited.

Follow-up action is taken by responsible management to correct the deficiencies revealed by the audit.

1.7-88

July, 1987

CHAIRMAN OF THE SOARD VICE CHAIRMAN END IREE RING 4 CONSTRUCTION EX. VICE PREQDENT 4

CHIEF ENGINEER VICE PREQDENT

~

~

~

~

o+

NUCLEAR OPERATIONS QUALITYASSURANCE

~ ~ ~ ~

SST. VICE PREQDEN'I CONSTRUCTION SIL VICE PRESIDENT ELECTRICAL ENGINEERING 4 DEPUTY CHIEF ENGINEER VICE PRESIDENT ENVIRONMENTAL ENOINEERINO VICE PRESIDENT ENGINEERING DESIGN VICE PREQDENT MECHANICAL ENOINEEIUNG ELECTRICAL ENGINEERING DEPARTMENT II)

PLANT MANAGER D.C. COOK PLANT ENVIRONMENTAL ENGINEERINO DIVISION DIVIQON MANAGER CIVIL ENGINEERIHO MECHANICAL ENGINEERINO DIVISION DIVISION MANAGERS FO DEPARTMENT SUPERIN'TENDENTS NUCLEAR OPERATIONS DIVIQOH PLANT CONSTRUCTION DIVIQON SECTION MANAGERS SECTION MANAGERS SECTION MANAGERS SECTION MANAGERS SECTION MANAGERS SECTION MANAGERS SECTION MANAGERS DIVIQON MANAGER DESIGN ADMINISTRATIVEAND FUNCTIONALDIRECTION SECTION IIANAOERS DIVIQDNMANAGER MATEQALS HANDUNO

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ TECHNICALLIAISON

~

~

~

~

~

FUNCTIONALDIRECTION FOR COOK PLANTACTIVITIES AMERICANELECTRIC POWER SERVICE CORPORATION ORGANIZATIONFOR THE SUPPORT OF THE DONALDC. COOK NUCLEARPLANT SECTION MANAGERS NOTES: (1) NOT PART OF AEPSC ORGANIZATION,SHOWN FOR INFORMATIONONLY.

AMERICAN ELECTRIC POWER COMPANY AMERICAN ELECTAIC POWER SERVICE CORPORATION APPALACHIAN POWER COMPANY OHIO POWER COMPANY X

X X

X X

X X

X X

X X

X X

X INDIANA4 MICHIGAN ELECTRIC COMPANY KINGSPORT POWER COMPANY KENTUCKY POWER COMPANY WHEELING ELECTRIC COMPANY MICHIGAN POWER COMPANY COLUMBUS 4 SOUTHERN OHIO ELECTRIC COMPANY I

I CENTAAL I

OPERATING I

X X

X DONALD C.

COOK NUCLEAR PLANT GENERATING SUBSIDIARY L

J (I)

JOINTLYOWNED WITH BUCKEYEPOWER, INC.

XXXXXXXXXX ADMINISTRATIVE,TECHNICAL AND FUNCTIONALDIAECTION r KANAWHA VALLEY L COMPANY~ r I

CARDINAL I

OPEAATING I

AMERICANELECTRIC POWER COMPANY GENERAL ORGANIZATION

CHAIRMANOF THE BOARD ANO CHIEF EXECUTIVEOFFICER AEPSC INDIANA& MICHIGANELECTRIC CO.

ANDOTHER AEP SUBSIDIARIES VICE CHAIRMAN ENGINEERING ANO CONSTRUCTION AEPSC VICE PRESIDENT ANO INDIANA& MICHIGAN ELECTRIC COMPANY

~ ~ 1 ~ 0 ~ 0 ~ 0 ~ 0 ~ ~ 0 ~ 0 ~ 0 ~ 0 ~ ~ 0 ~

0 ~ 0 ~ ~ 0 ~ 0 ~ 10 0

~ ~ 0 ~ 00 EXECUTIVE VICE PRESIDENT ANO CHIEF ENGINEER VICE PRESIDENT VICE PRESIDENT OPERATIONS ANO INDIANA& MICHIGAN NUCLEAR ELECTRIC COMPANY MANAGEROF NUCLEAROPERATIONS MANAGERS ENGINEERING DIVISIONS AEPSC

+1 ~ 0 ~ 00 ~ 0 ~ 0 ~ ~ 0 ~ 0 ~

~ 1 ~ ~ 01 MANAGER QUALITY ASSURANCE AEPSC PLANT MANAGER DONALDC. COOK NUCLEAR PLANT AEPSC QA SUPERVISOR (ONSITE)

SAFETY AND ASSESSMENT SUPERINTENDENT 101 ~ 0 ~ 1 ~ 00000 ~ 00 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 000 ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ 1 ~ 0 ~ 0 ~ 0 ~ 1 ~

ADMINISTRATIVE& FUNCTIONAL SUPERVISION TECHNICALDIRECTION

~ 0 ~ 0 ~ 1 ~ ~ ~ 0 ~ ~ ~

TECHNICALLIAISON

~ ~ ~ ~ ~ ~ ~

FUNCTIONALDIRECTION ORGANI2ATIONALRELATIONSHIPS WITHIN THE AMERICANELECTRIC POWER SYSTEM PERTAININGTO QA &QC ANDSUPPORT OF THE DONALDC. COOK NUCLEARPLANT 1.7.A-91

July, 1987

AEPSC IIANACER OF OUAuTY ASSURANCE OUAUlY ASSURANCE STAFF SPEd AUST(S)

CUAUTY ASSURANCE SUPERVI SCR (SITE)

ENCNEER(S)

AUDITOR, PROXCTS ENCDIEERNC TECHNOLOQSTS ENONEERDIC TECHNdWI(S)

SUPERVISORY AUDITOR SURVOIIANCE/

REVKWS ENONEERNC TECH dAN(S)

AEPSC QUALITY ASSURANCE DEPARTMENT ORGANIZATION

INDIANA 5 MICHIGAN ELECTRIC COMPANY ORGANIZATION FOR THE DONALD C.

COOK NUCLEAR PLANT

ADMINISTRATIVE RESPONSIBILITY fUNCTIONAL RESPONSIBILITY

=

TECHNICAL LIAISON

~car aa Asset QExr JLPOSflQCHC 4>>w

~ awol x s.w

~

L

APPENDIX A REGULATORY AND SAFETY GUIDES ANSI STANDARDS

, 1.

Reg.

Guide 1.8 (9/75)

ANSI N18.1 (1971)

Personnel Selection and Training Selection and Training of Nuclear Power Plant Personnel 2.

Reg.

Guide 1.14 (8/75)

Reactor Coolant Pump Flywheel Integrity

, 3.

Reg.

Guide 1 ~ 16 (8/75)

Reporting of Operating Information, Appendix A - Technical Specifications 4.

Safety Guide 30 (8/72)

ANSI N45.2.4 (1972) guality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment Installation, Inspection, and Testing Requirements for Instrumentation and Electric Equipment During the Construc-tion of Nuclear Power Generating Stations 5.

Safety Guide 33, Appendix A (ll/72)

ANSI N18.7 (1976)

(ANS 3.2 1976)

ANSI N45.2 (1977) guality Assurance Program Requirements (Operation)

Administrative Controls and guality Assurance for the Operational Phase of Nuclear Power Plants guality Assurance Program Requirements for Nuclear Facilities 6.

Reg.

Guide 1.37 (3/73)

ANSI N45.2.1 (1973) equality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants 1.7.A-94

July, 1987

APPENDIX A 7.

Reg.

Guide 1.38 (10/76)

ANSI N45.2.2 (1972) guality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Mater-Cooled

'uclear Power Plants Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants (During the Construction Phase) 8.

Reg.

Guide 1.39 (10/76)

ANSI N45.2.3 (1973)

Housekeeping Requirements for Water-Cooled Nuclear Power Plants Housekeeping During the Construction Phase of Nuclear Power Plants 9.

Reg.

Guide 1.54 (6/73)

ANSI N101.4 (1972) guality Assurance Requirements for Protective Coatings Applied to Mater-Cooled Nuclear Power Plants guality Assurance for Protective Coatings Applied to Nuclear Facilities 10.

Reg.

Guide 1.58 (9/80)

ANSI N45.2.6 (1978) gualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel gualification of Inspection, Exami-nati,on, and Testing Personnel for Nuclear Power Plants 11.

Reg.

Guide 1.63 (7/78)

Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants 12.

Reg.

Guide 1.64 (10/73)

ANSI N45.2. 11 (1974) guality Assurance Requirements for the Design of Nuclear Power Plants guality Assurance Requirements for the Design of Nuclear Power Plants 1.7.A-95

July, 1987

APPENDIX A 13.

Reg.

Guide 1.74 (2/74)

ANSI N45.2.10 (1973)

, guality Assurance Terms and Definitions guality Assurance Terms and Definitions I

A

,~14.

Reg.

Guide 1.88 (10/76)

ANSI N45.2.9 (1974)

Collection, Storage, and Maintenance of Nuclear Power Plant guality Assurance Records Requirements for Collection, Storage, and Maintenance of guality Assurance Records for Nuclear Power Plants 15.

Reg.

Guide 1.94 (4/76)

ANSI N45.2.5 (1974) guality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants Supplementary guality Assurance Require-ments for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants 16.

Reg.

Guide 1.108 (8/77)

Periodic Testing of Diesel Generator Units used as Onsite Electric Power Systems at Nuclear Power Plants 17.

Reg.

Guide 1.123 (7/77)

ANSI N45.2.13 (1976) equality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants guality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 1.7.A-96

July, 1987

APPENDIX A 18.

Reg.

Guide 1.144 (1/79)

ANSI N45.2.12 (1977)

Auditing of Quality Assurance Programs.

for Nuclear Power Plants Requirements for Auditing of Quality Assurance Programs for Nuclear Power

'lants 19.

Reg.

Guide 1.146 (8/80)

ANSI N45.2.23 (1978)

Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants 20.

ANS! N45.2.8 (1975)

Supplementary Quality Assurance Require-ments for Installation, Inspection and" Testing of Mechanical Equipment and Systems for the Construction Phase of "

Nuclear Power Plants 21.

ANSI N45.4 (1972)

Leakage-Rate Testing of Containment Structures for Nuclear Reactors 1.7.A-97

July, 1987

APPENDIX B AEPSC/ISMECO EXCEPTIONS TO OPERATING PHASE STANDARDS AND REGULATORY GUIDES GENERAL

~R Certain Regulatory Guides invoke or imply Regulatory Guides and standards in addition to the standard each primarily endorses.

Certain ANSI Standards invoke or imply additional standards.

Exce tion Inter retation The AEPSC/ISMECo commitment refers to the Regulatory Guides and ANSI Standards specifically identified in Appendix A.

Additional Regulatory

Guides, ANSI Standards and similar documents implied or referenced in those specifically identified are not part of this commitment.

hl18.7 General Exce tion Inter retation AEPSC and 18MECo have established both an on-site and off-site standing committee for independent review activities.

Together they form the independent review body.

The standard numeric and qualification requirement may not be met by each group individually.

Procedures will be established to specify how each group will be involved in review activities.

This exception/interpreta-tion is consistent with the plant s Technical Specifications.

2a.

Sec. 4.3.1 Re uirement "Personnel assigned responsibility for independent reviews shall be specified in both number and technical disciplines, and shall collectively have the experience and competence required to review problems in the following areas:

1.7.B-98

July, 1987

APPENDIX B

Exce tion Inter retation AEPSC Nuclear Safety and Design Review Committee (NSDRC) and Plant Nuclear Safety Review Committee (PNSRC) will not have members specified by number nor by technical disciplines, and its members may not have the experience and competence required to review problems in all areas listed in this section.

This exception/interpretation is consistent with the plant's Technical Specifications.

The NSDRC and PNSRC will not specifically include a member qualified in nondestructive testing but will use'qualified technical consultants to perform this and other functions as determined necessary by the respec-tive committee chairman.

2b.

Sec. 4.3.2.1 Re uirement "When a standing committee is responsible for the independent review program, it shall be composed of no less than five persons of whom no more than a minority are members of the on-site operating organization.

Competent alternatives are permitted if designated in advance.

The use of alternates shall be restricted to legitimate absences of principals.".'i Exce tion Inter retation See Item 2a.

2c.

Sec. 4.3.3.1 Re uirement

. recommendations

. shall be disseminated promptly to appropriate members of management having responsibility in the area reviewed."

Exce tion Inter retation Recommendations made as a result of review will generally be conveyed to; the on-site or off-site standing committee.

Procedures will be maintained specifying how recommendations are to be considered.

1.'7.'-,99

July, 1987

APPENDIX 8 2d.

Sec. 4.3.4

~R ~"

"The following subjects shall be reviewed by the independent review body:

Exce tion Inter retation Subjects requiring review will be as specified in the plant Technical Specifications.

".2e.

Sec. 4.3.4(3)

~lt "Changes in the Technical Specifications or License Amendments relating to nuclear safety are to be reviewed by the independent review body prior to implementation, except in those cases where the change is identical to a previously reviewed proposed change."

Exce tion Inter retation Although the usual practice is to meet this requirement, exceptions are

'4 'ade to NSDRC review and approval prior to implementation in rare cases with the permission of the NSDRC Chairman and Secretary.

PNSRC review and apporval is always done prior to implementation of Technical Specification changes.

2f.

Sec. 4.4 Re uirement "The on-site operating organization shall provide, as part of the normal duties of plant supervisory personnel Exce tion Inter retation Some of the responsibilities of the on-site operating organization described in Section 4.4 may be carried out by the PNSRC and/or NSDRC as described in plant Technical Specifications.

July, 1987

APPENDIX B

2g.

Sec. 5.2.2

~R "Temporary changes, which clearly do not change the intent of the approved procedure, shall as a minimum be approved by two members of the plant staff knowledgeable in the areas affected by the procedures.

At least one of these individuals shall be the supervisor in charge of the shift and hold a senior operator's license on the unit affected."

Exce tion/Inter retation ISNECo considers that this requirement applies only to procedures identi-fied in plant Technical Specifications.

Temporary changes to these procedures shall be approved as described in plant Technical Specifications.

2h.

Sec.

5.2.6 Re uirement "In cases where required documentary evidence is not available, the associated equipment or materials must be considered nonconforming in accordance with Section 5.2.14.

Until suitable documentary evidence is

~

available to show the equipment or material is in conformance, affected q

systems shall be considered to be inoperable and reliance shall not be placed on such systems to fulfilltheir intended safety functions."

Exce tion Inter retation I&HECo initiates appropriate corrective action when it is discovered that documentary evidence does not exist for a test or inspection which is a

requirement to verify equipment acceptability.

This action includes a

technical evaluation of the equipment's operability'tatus.

2i.

Sec. 5.2.8 Re uirement "A surveillance testing and inspection program

. shall include the establishment of a master surveillance schedule reflecting the status of all planned in-plant surveillances tests and inspections."

1.7. B-,101

July, 1987

APPENDIX B Exce tion Inter retation Separate master schedules may exist for different programs such as ISI, pump and valve testing and Technical Specification surveillance testing.

2j.

Sec.

5.2.13.1 "To the extent necessary, procurement documents shall require suppliers to provide a guality Assurance Program consistent with the pertinent requirements of ANSI N45.2 - 1971."

Exce tion Inter retation

-To the extent necessary, procurement documents require that the supplier has a documented guality Assurance Program consistent with the pertinent requirements of 10CFR50, Appendix B; ANSI N45.2; or other nationally recognized codes and standards.

2k.

Sec.

5.2.13.2 Re uirement ANSI N18.7 and N45.2. 13 specify that where required by code, regulation, or contract, documentary evidence that items conform to procurement requirements shall be available at the nuclear power plant site prior to installation or use of such items.

Exce tion Inter retation The required documentary evidence is available at the site prior to use, but not necessarily prior to installation.

This allows installation to proceed while any missing documents are being obtained, but precludes dependence on the item for safety purposes.

. 21.

Sec.

5.2.16 t

Records shall be made and equipment suitably marked to indicate cali-bration status.

1.7. B-102

July, 1987

APPENDIX 8 Exce tion Inter retation See Item 6b.

~

V 4 ~

2m.

Sec. 5.3.5(4)

~R This section requires that where sections of documents such as vendor

manuals, operating and maintenance instructions or drawings are, incor-porated directly or by reference into a maintenance procedure, they shall receive the same level of review and approval as operating procedures.

Exce tion Inter retation I'

'I

'uch documents are reviewed by appropriately qualified personnel, prior to use to ensure that, when used as instructions, they provide proper,and adequate information to ensure the required quality of work.; Mai;ntenance procedures which reference these documents receive the same level of, review and approval as operating procedures.

3.

N45.2. 1, 3a.

Sec.

2 Re uirement N45.2. 1 establishes criteria for classifying items into "cleanness levels",

and requires that items be so classified.

Exce tion Inter retation Instead of using the cleanness level classification system of N45.2.1, the required cleanness for specific items and activities is addressed on a case-by-case basis.

Cleanness is maintained, consistent with the work being performed, so as to prevent the introduction of foreign material.

As a minimum, cleanness'nspections are performed prior to closure of "nuclear " systems and equipment.

Such inspections are documented.

1.7. 8-;103

July, 1987

APPENDIX B

3b.

Sec.

5 "Fitting'nd tack-welded joints (which will not be immediately sealed by welding) shall be wrapped with polyethylene or other nonhalogenated plastic film until the welds can be completed."

Exce tion Inter retation ISHECo sometimes uses other nonhalogenated material, compatible with the parent material, since plastic film is subject to damage and does not always provide adequate protection.

4.

N45.2.2, General N45.2.2=establishes requirements and criteria for classifying safety related items into protection levels.

Exce tion Inter retation I'ns'tead-'of, classifying safety related items into protection levels, controls over the packaging, shipping, handling and storage of such items are established on a case-by-case basis with due regard for the item's complexity, use and sensitivity to damage.

Prior to installation or use, the items are inspected and serviced as necessary to assure that no damage or deterioration exists which could affect their function.

4a.

Sec.

3.9 and Appendix A3.9 "The item and the outside of containers shall be marked."

(Further criteria for marking and tagging are given in the Appendix.)

Exce tion Inter retation These requirements were originally written for items packaged and shipped to construction projects.

Full compliance is not always necessary in the case of'items shipped to operating plants and may, in some cases, increase the probability of damage to the item.

The requirements are implemented to the extent necessary to assure traceability and integrity of the item.

1;7. B-104

July, 1987

APPENDIX B 4b.

Sec. 5.2.2 Re uirement "Receiving inspections level of storage."

shall be performed in an area equivalent<to the Exce tion/Inter retation Receiving inspection area environmental controls may be. less stringent than storage environmental requirements for an item.

However such inspections are performed in a manner and in an environment which do not endanger the required quality of the item.

4c.

Sec. 6.2.4

~R "The use or storage of food, drinks and salt tablet dispensers in:any storage area shall rot be permitted."

Exce tion/Inter retation Packaged food for emergency or extended overtime use may be stored in material stock rooms.

The packaging assures that materials are,not contaminated.

Food will not be "used" in these areas.

4d.

Sec. 6.3.4 Re uirement "All items and their containers shall be plainly marked so that they are easily identified without excessive handling or unnecessary opening of.

crates and boxes."

Exce tion Inter retation See N45.2.2, Section 3.9 (Exception 4b.).

4e.

Sec. 6.4.1 Re uirement "Inspections and examinations shall be performed and documented on a

periodic basis to assure that the integri,ty of the item and its container

. is being maintained."

, 1. 7;B-105

July, 1987

APPENDIX B

Exce tion Inter retation

~ '

.The requirement. implies that all inspections and examinations of items in

.storage are to be performed on the same schedule.

Instead, the inspec-

'tions and.examinations are performed in accordance with material storage procedures which identify the characteristics to be inspected and include the required frequencies.

These procedures are based on technical considerations which recognize that inspections and frequencies needed vary from item to item.

5.

N45.2.8, 5a.

Sec.

2.1 Re uirement Cleanness requirements for housekeeping activities shall be established on the 'basis of five zone designations.

Exce tion I'nter retation Instead of the five-level zone designation system referenced in ANSI N45.2.3, ISNECo bases its controls over housekeeping activities on a consideration of what is necessary and appropriate for the activity involved.

The controls are effected through procedures or instructions.

Factors considered in developing the procedures and instructions include cleanliness control, personnel safety, fire prevention and protection, radiation control and security.

The procedures and instructions make use of standard janitorial and work practices to the extent possible.

However, in preparing these procedures, consideration is also given to the recommendations of Section 2.1 of ANSI N45.2.3.

.,6.

N45.2.4, 6a.

Sec.

2.2 Re uirement Section 2.2 establishes prerequisites which must be met before the installation, inspections and testing of instrumentation and electrical equipment may proceed.

These prerequisites include personnel qualifi-cation, control of design, conforming and protected materials and availability of specified documents.

July, 1987

APPENDIX B Exce tion Inter retation During the operations

phase, this requirement is~ coosMened~to bg'ppli-cable to modifications and initial start-up of.electrical;.equipment.

for routine or periodic inspection and testing, the prerequisite conditions will be achieved as necessary.

6b.

Sec.

6.2.1

'p ~w'.

~

"Items requiring calibration shall be tagged or labeled on completion, indicating date of calibration and identity of person that perforated.;

calibration."

n&i I

~ '~9 Exce tion/Inter retation Frequently, physical size and/or location of installed.plant>i'ns4rumenta-tion precludes attachment of calibration labels or tags.

Instead, each instrument is uniquely identified and is traceable;to;Ms...calibration record.

I W

J

~

~ I

~

xj A scheduled calibration program assures that each instruntenCh calibration is current.

7.

N45.2.5, 7a.

Sec. 2.5.2

~ i "llhen discrepancies, malfunctions nr inaccuracies in inspection and testing equipment are found during calibration, all items inspected with that equipment since the last previous calibration shall be considered unacceptable until an evaluation has been made by the respqnsibl'e author-ity and appropriate action taken.

~,

Exce tion Inter retation ISMECo uses the requirements of N18.7, Section 5.2. 16,aweather than N45.2.5, Section 2.5.2.

The N18.7 requirements.are more applicable to an operating plant.

July, 1987

APPENDIX B

7b.

Sec.

5.4

'"Re uireh'ent

'Hand"torque wrenches used for inspection shall be controlled and must be

'""calibr'ated.at least weekly and more often if deemed necessary.

Impact torque wrenches'used for inspection must be calibrated at least twice daily." '-

Exce tion Inter retation Torque w'renches are controlled as measuring and test equipment in accor-

'dance with ANSI N18.7, Section 5.2.16.

Calibration intervals are based

'n-'use and calibration 'history rather than as per N45.2.5.

=N45;2;6', Sec; 1.2 "The requirements of this standard apply to personnel who perform inspec-

"-"ti'ons, 6xaminations and tests during fabrication prior to or during

~ rec'eipt'f"items at the construction site, during construction, during "preoperational'and start-up testing and during operational phases of nuclear power plants."

Ex'ce 'tion Inter retation Perso'nnel participating in testing who take data or make observations, where special training is not required to perform this function, need not be qualified in accordance with ANSI N45.2.6 but need only be trained to the extent necessary to perform the assigned function.

9.

Re

. Guide 1.58 - General Re uirement gualification of nuclear power plant inspection, examination and testing personnel.

9a.

C.2.a(7)

Regulatory Guide 1.58 endorses the guidelines of SNT-TC-1A as an accep-4'able method of training and certifying personnel conducting leak tests.

'.7.B-108

July, 1987

APPENDIX B

Exce tion Inter retation ISMECo takes the position that the "Level" designation gui,de/jnes<,as recommended in SNT-TC-IA, paragraph 4 do,not qgcessqri]g,assure,,adequate leak test capability.

I8MECo maintains that,depaptmenta1..supqry~sors are best able to judge whether engineers, and other personne],,pre.,qua1i.fied to direct and/or perform leak tests.

Therefore, ISMECo does not,imp],ement the recommended "Level" designation guidelines.

Ig~f f gdht L ~ J 8+/

It is I8MECo's opinion that the training. guidelines, of,.SNT-,,TC;,1$,,-Table I-G, paragraph 5.2 specifically are oriented towards;the,basic. physics involved in leak testing, and further,,towards i,ndi,vidual,s,,who,pre not graduate engineers.

ISMECo maintains that it meets the essence of these training guidelines.

The preparation of leak test procedures aqd,the conduct of leak tests at Cook Plant is under the direct.supp';vision of Performance Engineers who hold engineering degrees, from.accredited engineering schools.

The basic physics.of leak testing,Pave been incor-.,

porated into the applicable test procedures.,

The review:.apd,qpyrqval of~

the data obtained from leak tests is performed by department,,supervisors, who are also oraduate engineers.

IAMECo does recognize the need to assure that individuals inval,.vied in leak tests are fully cognizant of,leak test procedural,,.requirepents and thoroughly familiar with the test equipment involved.

Plant performance engineers receive routine, informal orientation on testing programs, to ensure that these individuals fully understand the requirements of performing a leak test.

9b.

W C5, C6, C7, C8, C10 Exce tion/Inter retation ISMECo takes the position that the classification of inspection, exami-nation and test personnel (inspection personnel) into "Levels" based on the requirements stated in Section 3.0 of ANSI N45.2.6 does;not -neces-,.

sarily assure adequate inspection capability.

I&MECo maiptains that departmental and first line supervisors.

ape, best ab/eto,judge the.

inspection capability of the personnel uqdep.,t)eir, super%i-siorl, pad that "level" classification would require an overly burdensome administrative 1.,7;B-,109

July, 1987

APPENDIX B

.work load, could inhibit insp'ect'ion activities and provides no assurance I

3, AC)

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of inspection capabilities.

Therefore, ISMECo does not implement the "level classificat'ion" concept for'nspection, examination and test personnel.

gw~n ting 4-6$

~

'I

< lq The methodology under which inspections, examinations and tests are conducted at the Donald C.

Cook Nuclear Plant requires the involvement of first line supervisors, engineering personnel, departmental supervisors and plant management.

In essence, the last seven (7) project functions shown in Table 1 to ANSI N45.2.6 are assigned to supervisory-and engineering personnel and not to personnel of the inspector category.

These management supervisory and engineering personnel, as a minimum, meet the 'educational and experience requirements of "Level II and Level III" personnel, as required, to meet the criteria of ANSI 18.1 which exceeds those of ANSI N45.2.6.

In I8MECo's opinion, no useful purpose is served by classification of management, supervisory and engineering personn'el" into."Levels."

Therefore, ISMECo takes the following positions relative to regulatory positions C5, 6, 7, 8 and 10 of Regulatory Guide 1.58.

C-5 Based on the discussion in B. 1 above, this position is not appli-cable to the Donald C.

Cook Nuclear Plant.

$r, r*, ",j'l C-6 Replacement personnel for Donald C.

Cook Nuclear Plant management, supervisory and engineering positions subject to ANSI 18.1 will meet

~

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the educational and'experience requirements of ANSI 18. 1 and there-fore those of ANSI N45.2.6.

Replacement inspection personnel will, as a minimum, meet the educational and experience requirements of ANSI N45.2.6, Section 3.5.1 -.."Level I".

C-7.

IEMECo, as a general

practice, complies with the training recommen-

~

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I dations as set forth in this regulatory position.

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1.7.8-110

July, 1987

APPENDIX B C-8 All I&HECo inspection,,examination and.test personnel are instructed

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in the normal, course of emplojeq ttaining in radiatio'n protection

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<""-163 n-

-ZD&gP'nd the means..to minimize radiation dose exposure.

C-10 I&t1ECo maintains documentation to show that inspection personnel

, meet the minimum requirements of "Level I" and that management, tR ~")t>>

, supervisory and engineering personnel meet the minimum requir'ements.~

of ANSI 18.1.

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-re -n.t 10.

N45.2.8, 3J g qR RIt I;

q~t

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R4.

10a.

Sec.

2.9e I '0'iI, '>>

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":-",.e,. s~~rm "-.g9; Section 2.9e of N45.2.8 lists documents relating to tlie specif'ic stage of I

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installation activity which are to be available at the construction site.

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Exce tion/Inter retation

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All of the documents listed are not necessarily required at the 'construc-tion site for installation and testing.

AEPSC and I&MECo assure that

, they are available to the site as necessary.

10b.

Sec.

2.9e

~

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~R Evidence that engineering or design changes are documented and approved I

shall be available at the construction site prior to installation.

i Exce tion Inter retation Equipment may be installed before final approval of engineering or design changes.

However, the system is not placed into. service until such changes are documented and approved.

R R.

10c. Sec. 4.5.1

~R "Installed systems and components shall be c'leaned, flushed and condi-tioned according to the requirements of ANSI N45.2. 1.

Special considera-tion shall be given to the following requiremen'ts:

(Requirements are given for chemical conditioning, flushing and process controls.)

1.7,.B-111

July, 1987

APPENDIX 8 Exce tion Inter retation

-.,; Systems>hand:components-a'e

<lean'ed, flushed and conditioned as determined

".<ion"a,;,case-by:case basis;

,Ãeasures are taken to help preclude the need for cleaning, flushing and conditioning through good practices during maintenance or modification activities.

11.

N45.2.9 11a.

Sec. 5.4, Item 2

~R i, ggCords.:shall, not be.,stored loosely.:~,"They shall be firmly attached in

~bindery or

placed in'folders.or< envelopes=-for storage on shelving in containers."

Steel file cabinets are preferred.

Exce tion Inter retation

.,Recoy'ds pre.,suitably, stored in steel file cabinets or on shelving in

,':.c". ;~;;containgrq;.-;Hethods"other than binders', folders, or envelopes (for example, dividers) may be used to organize the records for-storage.

11b. Sec.

6.2

,'!A, list;shall;.bg-maintained designating..those personnel who shall have access to the files".

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Exce tion Inter retation

,gules are establishqd-.ggverning access to and control of files as pro-vided for im<ANSI N45.2.9, Section 5.3, Item 5.

These rules do not a'1ways include a requirement'"for a list of personnel who are authorized access.

It should be noted that duplicate files and/or microforms may exist for general use.

11c.

Sec.

5.6

<;,When

.a single records:-storage.facility is maintained, at least the

.followjyg.features. should be, considered 'in its construction:

etc.-

F i.'1.i7!8-112

July, 1987

d>>

4 APPENDIX B Exce tion/Inter retation The Donald C..

Cook nuclear'Plant>Master

-:File:,. Room,;>>and~othee,,o'ff site record; storage, facilities comply, with ~the>requirem'eptsv.oP5UREG-0800 (7/81)

Section ~178,.17.4; '"'

lt.

~R. Gdd 1.144.

12a.

Sec C3a(2)

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Applicable elements of an organization's guality Assurance'j',Pt6gf>$ ) forE "design and construction. phase, activities should be 'audited~at;, Itist annually or at least once, within the life'"of the.activity) wh5Che9er is shorter."

",.<;';~)( )u. p6(t%~$ 'goo

,PF fqo 4

4'14 Exce tion Inter retation v.

'33a7>

.Since most modifications are straight forward,'.they are~not'audited individually.

Instead:'selected

'controls'over modificationsiht;5~huditedh periodically.

12b.

Sec.

C3b(1)

This.'section identifies procurement=.contracts being audited.

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ct j rl~3gt which.'are'exempted <from Exce tion Inter retation

';"(~."

">>i) (r). 1~I y',j'i t ~deqP

'n addition to the exemptions.of'Reg;~Guide'1

144, AEPSC/I>>&MECo.eondsiders that the National Bureau of Standards':or.=other"State";and Feder'a'l..dA'gencies which may provide services to AEPSC/~I&MEGo=are'not re+'ir0d to.be<audited;

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13.

N45.2.13, f,.

5

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Sec. 3.2.2

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N45.2.13 requires that;technical requirements be speci fje'd jj',procurement

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41::.

td

t 14'1 requirement documents"are'to be prepared,'revi'ewed':a'nd-'rel."eall'8 under the requirements established by ANSI N45.2.11.

July, 1987

APPENDIX B Exce tion Inter retation

)

For replacement parts and materials, AEPSC/ICMECo follow ANSI N18.7,

,,,-/ection"5.:2,13",

Subi.t'em f",hich 'sta'tes:

'Where the original item or

,,,;.- peart is;found to'e 'c'omm'er'c'ially 'off'he shelf'r without specifically

,...-,,identified. gA: require'ments,'pare and repl'acement parts may be similarly

procured, but care shall'e exercised'to ensure at least equivalent performance."

13b. Sec.'.3.2

',~R.it' ql

,';,<'rocurement'ocuments

.shall require th'at the supplier have. a. documented equality,Assurance'rogram that implements parts or all of ANSI N45.2 as well as applicable guality Assur'ance'rogram requirements of other nationally recognized codes and standards."

Exce tion Inter retation Refer to Item 2j.

13c.

Se,c 3.,3(a-)...

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~

'.: Reviews of procurement documents shall be performed prior to release for bid and contract award.

I 1

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j Exce ti.on/Inter retation-'Documents may be release'd'or" bad or contract award before completing the necessary reviews.

However, these reviews are completed before the item

".or service is put into service',"- or before work ha's progressed beyond the point where it would be impractical to reverse the action taken.

13d., Sec. 3.,3(b)

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Review of changes to procurement documents shall be performed prior to release for bid and contract award.

~ Zm

July, 1987

APPENDIX 8 Exce tion Inter retation This requirement 'applies -only to, quality related, changes '(~i'.e'!:,.:,ch'anges to the procurement". document,proyvisions,,identified in. ANSIi~N18:."7 Se'ction':

l 5.2.13.1, SUbitems 1.through 5),i '~The~timing of, reviews~!will'~b'e">'the same

's forreview of the original procurement documents.

cf Il L'ia '~>>

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Sec.

10.1

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"Wheeerequired by code, regulation; or contract requi,remend",:.documentary evidence,.that items conform to procurement,documents~shal~l',

bei@v4i!1able

'at the nuclear power plant~site>prior to.,instal.latj'onLor,',use o'f su&'tems",

regardless of'cceptance methods.">

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Exce tion Inter retation.!~';,,"--,,

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Refer.>>to Item 2j..- r+ ~,

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13e.

~R "Post-installation test reouirements and:acceptance do'cumentat'ion -sha'll'-

be mutually established by the purchaser and supplier."

~,',,

Exce tion Inter retation J

~ '.

In exercising its ultimate responsibility for its guality Assurance

Program, AEPSC/ISNECo establishes post-installation test requii ements giving due consideration to supplier, recommendations."

I 14.

Re

. Guide 1.'58 ANSI 945.2.23 and ANSI N45.2.2.12

'4a.

ANSI N45.2.23, Sec.

1.1

'Ir

~R This standard provides requirements and guidance for the qualification of

'udit team leaders, henceforth identified as "lead auditors".

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14b.

ANSI N45.2.12, Sec. 4.2.2 A lead auditor shall be appointed team leader.

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July, 1987

TP(l h>>(

hP APPENDIX".3 V

(

~,

Exce'tion Inter'"retation

a~n~ The;AEPSC"audit~iprogram-.isdirected.',.by,.',the.AEPSG.

Manager(of"equality ',

,~~>~.'"~Assuran'ce".and. is administeredqbyPdesignated;.gA.'Department>section

..'J~

managers/supervis'or who >are>'cey.tified lead auditors. '",- '.

,.g'".~n~ '

>'>h Jns Audits are, in most cases,,',.conducted by individual, auditors, not by "audit teams".

These auditors.are-certified. in-.*accorda'nce.with.

'>'established procedures and are,.assigried=by the responsible /A~ection y~a:l

~ ~manager/supervisor.based~on<<their'idemonstrated audit capabil i'ty6a'nd

,~f I.,igeneral,'now'ledge of"the.'audit subject.

In. cer tain cases, "this results

~l;>in an individual"other.,than;a.,'-.'lead:.auditor'"

conducting 'the actual audit.

'function.

Establi.shed AEPSC audit procedu'res require that,.in'all'ases;.=the'udi.t functions of preparation/organization, reporting of:audit findings and evaluation of corrective actions be reviewed by gA,Department section managers/supervisor',

thereby meeting the requirements of ANSI N45.2.23

~',,<~ relative;;to ~"leadi:auditors",,~.and "auditearn leaders".

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6.$

July,,"'1987