Text

QA Manual for Operations,Revision 4
	ML19326B553
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/08/1977
From:	; ARKANSAS POWER & LIGHT CO.
To:	;
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ML19326B548	List: ML19326B553;
References
	APL-TOP-1-A, NUDOCS 8004160340
	Download: ML19326B553 (111)
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LIST OF EFFECTIVE PAGES PAGE NIAfBER REVISION DATE

[ Title Page Rev. 4

/ NRC Acceptance Letter Rev. 4 9/8/77

[ List of Effective Pages Rev. 4 9/8/77

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[PolicyStatement Foreword Pg. 1 of 1 Rev. 4 9/8/77 Terms- Pg. 1 of 6 Rev. 0 7 6/11/74 Pg. 2 of 6 Rev. 0 6/11/74 Pg. 3 of 6 Rev. 0 6/11/74 Pg. 4 of 6 Rev. 0 6/11/74 Pg. 5 of 6 Rev. 0 6/11/74-Pg. 6 of 6 Rev. 0 6/11/74 Record of Revisions Pg. 1 of 1 Rev. 4 9/8/77 4

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TABLE OF CONTENTS ARKANSAS POWER 6 LIGHT COMPANY SECTION SUBJECT TAB PAGE POLICY STATEMENT FOREWORD TERMS AND DEFINITIONS

1. ORGANIZATION 1 1.1 SCOPE 1 1.2 ARKANSAS POWER I, LIGHT COMPANY 1 1.3 ADMINISTRATIVE SERVICES 1 1.3.1 MANAGER OF SAFETY 1 1.3.2 SUPERVISOR OF PURCHASING 1 1.4 PRODUCTIO.' DEPARTMENT 2 1.4.1 QUALITY ASS;'%NCE ORGANIZATION 2 1.4.2 NUCLEAR SERVI 2 S ORGANIZATION 5 1.4.3 SUPERINTENDENT OF POWER PLANT 7 1.4.4 OPERATION AND MAINTENANCE COORDINATOR 7 1.4.5 MANAGER, CHEMISTRY AND TECHNICAL SERVICES 7 1.4.6 MANAGER, DESIGN AND CONSTRUCTION 8 '

1.4.7 DIRECTOR OF G. O. ENGINEERING 8 1.5 ARKANSAS NUCLEAR ONE ORGANIZATION 8 !

1.5.1 ADMINISTRATIVE I 8

1.S.2 NUCLEAR -

9 1.S.3 QUALITY CONTROL 9 1.5.4 OPERATIONS GROUP 10 1.5.S MAINTENANCE GROUP 10 1.5.6 TECHNICAL SUPPORT GROUP 10 1.5.7 INSTRUMENTATION 6 CONTROLS GROUP 11 1.6 QUALITY PROGRAM C0hNITTEES 12

1. 6.1 SAFETY REVIEW CONNI1 TEE 12 1.6.2 PLANT SAFETY C0hMITTEE 14 1.6.3 ENVIRONMENTAL RESPONSIBILITIES 16 1.7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES 17

2. QUALITY ASSURANCE PROGRAM 2 2.1 SCOPE 1

2.2 PURPOSE 1

2.3 APPLICABILITY 1 2.4 PROCEDURES 2

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" QUALITY ASSURANCE MANUAL Y* 4 DATE 9/8/77 TITLE: TABLE OF CONTENTS TABLE OF

. ___ PAGE 1 of 5 CONTENTS

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l t t C SEC? ION SUBJECT TAB }GE

2. QUALITY ASSURANCE PROGRAM (CONTINUED) 2 2.6 PP0 GRAM REVISION AND CONTROL 3 2.6 SYSTEM STRIICTURE AND COMPONENT CLASSIFICATION 3 2.7 TRAINING AND PERSONNEL 4 2.8 PROGRAM REVIEW 5

3. DESIGN CONTROL 3 3.1 SCOPE 1 3.2 GENERAL 1 3.3 DESIGN PROCESS / VERIFICATION 1 3.4 DESIGN RECORDS 3

4. PROCUREMENT DOCUMENT CONTROL 4 4.1 SCOPE 1 4.2 GENERAL 1 4.3 REQUISITIONS 2 4.4 SPECIFICATIONS 2 4.5 PURCIMSE ORDERS 3

5. INSTRUCTIONS, PROCEDURES AND DRAWINGS 5 5.1 SCOPE 1 5.2 GENERAL 1 5.3 TEMPORARY CHANGES 1 5.4 ESERGENCIES 1 5.5 CHANGES TO PROCEDURES 2 5.6 REVIEW OF PROCEDURES, INSTRUCTIONS AND DRAWINGS 2

6. DOCUMENT CONTROL 6 6.1 SCOPE 1 6.2 GENERAL 1 6.3 DOCUSENT IDENTIFICATION 2 6.4 STORAGE AND FILING REQUIREMENTS 2

7. CONTROL OF PURCHASED MATERIAL, EQUIPhENT 7 AND SERVICES 7.1 SCOPE 1 7.2 SOURCE EVALUATION 1 7.3 DOCUMENTATION OF QUALITY l '

7.4 SOURCE INSPECTION 1 7.5 RECEIPT INSPECTION 2 7.6 STORAGE 2

.~ DATE )

9/8/77

[ QUALITY ASSURANCE MANUAL )

e TITLE: TABLE OF CONTENTS TABLE OF PAGE 2 of 5 CONTENTS I

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SELTION SUBJECT TAB PACE

8. IDENTIFICATION AND CONTROL OF MATERIALS. 8 PARTS AND COMPONENTS ,

f 8.1 SCOPE 1 8.2 IDENTIFICATION AND MARKING 1

8. 's TAGGING 1 P.4 DOCUMENTATION 2 8.S DEFECTIVE OR INCORRECT ITEMS 2 j

9. CONTROL OF SPECIAL PROCESSES 9 9.1 SCOPE 1 9.2 RESPONSIBILITY 1 9.3 GENERAL 1 9.4 QUALIFICATION 2

10. INSPECTION 10 l 10.1 SCOPE 1 10.2 RESPONSIBILITY 1 I' 10.3 INSPECTION PROCEDURES 2 l

~.4 v INSPECTOR QUALIFICATION 2 10.S DOCUhENTATION 3

11. TEST CONTROL 11 l 11.1 SCOPE 1 I 11.2 GENERAL l 1

11.3 PROCEDURE APPROVAL 2

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11.4 DOCUMENTATION AND REVIEW OF TEST RESULTS 2 !

11.S PREOPERATIONAL TESTING 3

12. CONTROL AND FEASUREhENT OF TEST EQUIPMENT 12 1

12.1 SCOPE 1 12.2 GENERAL 1 t 12.3 RESPONSIBILITIES 1 12.4 EQUIPMENT IDENTIFICATION 2 l 12.5 DOCUFENTATION 2

13. g gING, STORAGE AND SHIPPING 13 13.1 SCOPE 1 13.2 SPECIAL REQUIREMENTS 1 13.5 RECEIVING INSPECTION 1 13.4 STORAGE AND PRESERVATION 1 13.S RADI0 ACTIVE MATERIALS 2 913.6 RECORDS 2 ;

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PAGE 3 of a TABLE OF CONTENTS

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, SECTION SUBJECT TAB PAGE

14. INSPECTION, TEST AND OPERATING STATUS 14 14.1 SCOPE 1 14.2 DETERMINING OPERATIONAL STATUS 1 14.3 IDENTIFICATION OF OPERATIONAL STATUS 1

15. NONCO!$ FORMING MATERIAL, PARTS OR COMPONENTS 15 .

15.1 SCOPE 1 15.2 GENERAL 1

15. 3 TAGGING AND STORAGE 2 15.4 DOCUMENTATION 2

16. CORRECTIVE ACTION 16 16.1 SCOPE 1 16.2 GENERAL 1 16.3 SIGNIFICANT NONCONFORMANCES 1

17. QUALITY ASSURANCE RECORDS 17 17.1 SCOPE 1

./ ' 17.2 RESPONSIBILITY 1

\ 17.3 DOCUMENT RETENTION 1 l 17.4 PRODUCTION DEPARTMENT 2 17.5 STORAGE 2 l

i 17.6 RECORLS INDEXING AND RECEIPT CONTROL 3 !

17.7 FINAL DISPOSITION 4 '

18. AUDITS 18 18.1 SCOPE 1 18.2 GENERAL 1 18.3 .

IN-PLANT REVIEW AND SURVEILLANCE 1 18.4 AUDIT PERSONNEL 2 18.5 DOCUMENTATION 2

19. _ RESPONSE TO NRC QUESTIONS 19 1 *2

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QUALITY ASSURANCE MANUAL REV. 4 gfgjy TITLE: TABLE OF CONTENTS PAGE 4g S TABLE OF CONTENTS 1

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FIGURES AND TABLES FIGURES NUMBER TITLE TAB 1-1 Arkansas Power G Light Company 1 Corporate Organization 1-2 Arkansas Power t. Light Company 1 Administrative Services - Purchasing 1-3 Arkansas Power G Li,'ht Company 1 Production, Transmission and Engineering 1-4 Arkansas Power G Light Company 1 ANO Organization TABLES '

-. NUMBER TITLE TAB PAGE 2-1 Quality Assurance Procedures 2 6 l

2-2 Plant Quality Procedures 2 8 2-3 Nuclear Services Procedures 2 11 l

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QUALITY ASSURANCE MANUAL REV. 4 9/S/77 TITLE: TABLE OF CONTENTS TABLE OF PAGE5 of 5

_ . . . CONTFNTS

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ARKANSAS POWER 6 LIGHT COMPANY POLICY STATEMENT QUALI*IY ASSURANCE PROGRAM FOR OPERATION It is the policy of the Arkansas Power 6 Light Company (APSL), from the high-

est level of corporate management, that its Quality Assurance Program for *410.3 Operation shall meet the requirements of the Code of Federal Regulations,10 410.4 CFR 50, Appendix B, with respect to operation, maintenance, refueling, repair and modifications, and inservice inspection of APSL Nuclear Plants. The Program shall, in addition, comply with WASH 1283, 5/24/74; WASH 1284, *1 10/26/73; and WASH 1309, 5/10/74; and be responsive to Industrial Standards *410.9 and Codes which pertain to the structure of the Program and the implementa- 6 tion of its procedures. 2 410.25 Under the Program, the Senior Vice President, Production. Transmission and Engineering, is the final management authority responsible for assuring that this policy statement and the Quality Assurance Program are implemented with-in APGL. The Plant Superintendent and the Plant Quality Control Engineer are responsibic for the daily implementation of the Program's procedural require-ments at the plant. Each Production Department Manager (Manager, Nuclear

f3 Projects, Manager, Licensing, Manager, Nuclear Fuel, etc.) is responsible for *3 the procedural implementation of the program within his assigned area.

The Manager of Quality Assurance shall be responsible for establishing the

Program. The Manager of Quality Assurance and the Assistant Director of

4 Power Production shall also be responsible for approval of the program. *410.1 Quality Assurance personnel reporting to the Manager of Quality Assurance *4 I shall be responsible for auditing the Program as necessary and monitoring all !

activities required by the Program to assure compliance with its require-ments. !

'the Plant Quality Control Engineer shall have the authority and !

organizational freedom necessary to meet the requirements of 10 CFR 50, Appendix B.

The Manager of Quality Assurance shall provide for annual review of the *4 adequacy and overall effectiveness of the Program. Any defects in the implementation of either this policy or the Program that are revealed during the review, and that require action for correction, will be reported to *4 appropriate levels of management 'together with appropriate recommendations. *4 Implementation of this policy is necessary in order to achieve the reliabi-lity and safety required at our Nuclear Plants. Each person involved in ac-tivities concerning our Nuclear Plants shall be responsible for assuring i

quality Program.

in his own work, and for compliance with the requirements of the j The Quality Assurance Program policies, manuals, and procedures *1 are mandatory requirements which must be implemented and enforced by all *410.7 responsible organizations and individuals. *

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c J.!D'. Phillips /

Senior Vice President l Production, Transmission 6 Engineering l

FOREWORD Quality assurance requirements have been established for the design and construction of AP6L Nuclear Plants to assure that regulatory require-ments and licensing commitments, codes and standards are correctly translated into the as-built plant. It is the objective of this pro- *1 gram to establish quali ty assurance requirements to ensure that acti- *410.3 vities such as operating, testing, refueling, repairing, maintaining *410.4 and modifying the Plant are conducted in accordance with good engineering p'actices.

r To meet this objective, a Quality Assurance Program for Operation anplicable to APSL Nuclear Plants has been established by Arkansas Power 6 Light Company. The Program, identified as the Quality Assurance Program for Operations, provides quality criteria to be ap- 2 plied to the operational phase of the plant. It has been written to *410.25 comply with Title 10, Code of Federal Regulations, Part 50, Appendix B *1 (10 CFR 50, Appendix B), WASH 1283, 5/24/74; WASH 1284,10/26/73; and

WASH 1309, 5/10/74. The Program controls those phases, as applicable, *410.9 for the design, procurement, manufacturing and fabrication, installation, repair, maintenance or changes mcde to existing plant structures, com-ponents and systems that prevent or mitigate the consequences of a postulated accident which may cause undue risk to the health and safety of the public. It assures that the necessary operational safeguards are applied in accordance with the criteria for safe, efficient, and reliable operation. The Program is an outgrowth of the principle that quality i assurance emanates from each individual contributor, and that management G is responsible for creating an awareness of quality and reliability.

AP6L's initial Quality Assurance Program was formalized on March 10, 1971,

with the initial issue of AP6L's Quality Assurance Manual. The program

was revised and upgraded seven times (12/17/71, 4/5/72, 8/22/72, 2/6/73,

6/5/73, 12/4/73, 3/26/74), and on 6/11/74, the Quality Assurance Program *1 for Operations was described in a manual separate from the construction *410.3 program. *410.4 Quality Assurance Program changes are made as required by the Manager of Quality Assurance to implement additional or changed requirements. *4 The Quality Prtgram is implemented through quality assurance procedures

contained in the following manuals. *

Quality Assurance Procedures Manual *

Quality Assurance Administrative Procedures Manual *

Nuclear Services Procedures Manual *

ANO Master Plant Manual - Quality Control Procedures

All procedures contained in these manuals which are identified in this

program are reviewed and approved as described in paragraph 2.4.3. The "

procedures are developed and revised as necessary by the cognizant group. *2 The procedures and revisions are examined by the Manager of Quality As- *410.24 surance to assure that Quality Assurance Program commitments are met. *

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QUALITY ASSURANCE MANUAL 9/8/77 TITLE: FOREWORD PAGE 1 of 1 FOREWORD

l TER!!S AND DEFINITIONS Approval - An act of endorsing or adding positive authorization, or both.

Approved Bidders List - A listing of approved vendors considered acceptable to AP6L and eligible to make proposals in response to the issuance of an inquiry.

Appurtenance - A part that is attached to a component which has been completed.

As-Built Data - Documented data that describes the condition actually achieved in a product.

Assembly - A combination of subassemblies or components, or both, fitted together to form a unit.

Audit - An activity to determine through investigation, the cdequacy of, and adherence to, established procedures , instructions, specifications, codes , and standards or other applicable contractual and licensing requirements, and the effectiveness of impicmentation. -

Bid Evaluation - A formal evaluation of all proposals received in response to an inquiry to detemine the vendor to whom the purchase order will be awarded.

l I Certificate of Conformance - A written statement, signed by a qualified party, certifying that items or services comply with specific requirements. l 1

Certificate of Compliance - A written statement, signed by a qualified party, attesting that the items or services are in accordance with specified require- I ments and accompanied by additional information to substantiate the statement.

Certified Test Report - A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual prop-erties of items and the actual results of all required tests.

Certification - The action of determining, verifying and attesting, in writing, to the qualifications of personnel or material.

Characteristic - Any property or attribute of an item, process, or service that is distinct, describable, and measurable, as conforming or nonconforming to l specified quality requirements. Quality characteristics are generally iden-tified in specifications and drawings which describe the item, process, or l service.

Checks 'Ihe tests, measurements, verifications or controls placed on an activ-ity by means of investigations, comparisons, or examinations, to determine satisfactory condition, accuracy, safety or performance.

l I DAE I~ REV. O 6/11/74 F QUALITY ASSURANCE MANUAL 0 TITLE: TERMS AND DEFINITIONS PAGE 1 of 6 TElBIS

Cleanness - A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other contam-inating impurities.

Component - A piece of equipment such as a vessel, piping, pump, valve or core support structure, which will be combined with other components to form an asserably .

Construction Phase - A period which commences with receipt of items at the construction site and ends when the components and systems are ready for turn-over to operations personnel.

Contaminants - Foreign materials such as mill scale, dirt, oil, chemicals and any matter that renders a fluid, solid or surface impure and unclean according to preset standards of acceptable cleanness.

Contractor - Any organization under contract for furnishing items or services.

It includes the terms Vendor, Supplier, Subcontractor, Fabricator and sub-tier levels of these where anpropriate.

Defective Material - A material or component which has one or more character-istics that do not comply with specified requirement:,.

Deviation - A nonconformance or departure of a characteristic from specified requirements.

Documentation - Any written or pictorial information describing, defining, speci-fying, reporting or certifying activities, requirements, procedures , or results.

Examination - An element of inspection consisting of investigation of materials, components, supplies or services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gaging, and measureme nt .

Generating Station - A utility company complex, constructed and operated for the purpose of producing electric power.

Guidelines - Particular provisions which are considered good practice but which are not mandatory. The term "should" denotes a guideline; the term "shall" denot es a mandatory requirement, llandling - An act of physically moving items by hand or mechanical means, but not including transport modes.

Inquiry - A document that contains the necessary information for a vendor to make a proposal. An inquiry may include specifications pertaining to the equip-ment , materials, or services proposed to be procured.

l l DATE REV. 0 6/11/74 QUALITY ASSURANCE MANUAL TITLE: TLRMS AND DEFINITIONS PAGE 2 of 6 TEIU1S

G Inspector (State or Code) - A qualified inspector employed by a 1cgally con-stituted agency of a Municipality o state of the United States, or Canadian Province, or regularly employed by an Authorized Inspection Agency and having authorized jurisdiction at the site of manufacture or installation. .

Inspector (owner's or Insta11er's) - A qualified inspector employed by the Owner or Installer whose duties include the verification of quality-related activities or installations or both.

Inspection - A phase of quality control which by means of examination, observa-tion or measurement determines the conformance of materials, supplies, compon-ents, parts, appurtenances, systems, processes or structures to predetermined quality requirements.

Item - Any level of unit assembly, including structure, system, subsystem, subassembly, component, part or material.

Manufacturer - One who constructs any class of component, part, or appurtenance to meet precribed design requirements.

?! aster Plant Manual - A manual consisting of various subsets of procedures, such as operating procedures , emergency procures, test and maintenance procedures, used by Plant operations staff, and maintained for the life of the Plant.

taterial - A substance or combination of substances foming components, parts,

( pieces, and equipment items. (Intended to include such as machinery, castings, U liquids, fomed steel shapes, aggregates, and cement.)

lodification - A planned change in plant design or operation and accomplished in accordance with the requirements and limitations of applicable codes, stan-dards, specifications , licenses and predetemined safety restrictions.

onconformance A Jeficiency in characteristic, documentation, or procedure which renders t e quality of an item unacceptable or indeteminate. Examples of nonconfomance include: physical defects, test failures, incorrect or inadequate documentation, or deviation from prescribed processing, inspection or test procedures.

Objective Evidence - Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements, or tests which can be verified.

Operation - The total of administrative, maintenance and monitor activities necessary to sustain the pNer generating capabilities of the plant after initial start-up.

Owner - The person, group, company or corporation who will have or has title to the facility or installation under construction.

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TITLE: TERMS AND DEFINITIONS PAGE a of e TERMS j

t Package - A wrapping or container including its contents of material or equipment .

Packaged Unit - An assembly of items and parts which can be disassembled with-out destroying the integrity of the individual parts.

Part - An item which has work performed on it and which is attached to and becoues part of a component before completion of the component.

Plant - The equipment, piping, structures, buildings and property that comprise an installation or facility.

Procedure - A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used and sequence of operations.

Procurement Documents - Contractually binding documents that identify and define the requirements which items or services must meet in order to be con-sidered acceptable by the purchaser.

Project - A planned series of activities including all actions necessary to pro-vide, utilize, and maintain a facility or portion thereof.

Proposal - A bid, usually written by a vendor in response to an inquiry, which provides the issuing party with the vendor's prcposed coupliance to the inquiry and tl.e cost.

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Purchase Order (or Contract) - A document authorizing a vendor to provide equip-ment, material or services in accordwice with stated terms and conditions.

Purchaser, - 1he organi:ation or organizations responsible tar issuance and administration of a contract, subcontract, or purchase order.

Q-List - A list which specifically identified those structures, systems and components whose failure could cause an uncontrolled release of rr.dioactivity, or those essential for the safe shutdown and immediate and long-term operation following a Loss of Coolant Accident.

Qualification (Personnel) - The characteristics or abilities gained through i training or experience or both that enable an individual to perform a required fun ction .

Qualified Party - A person or organi:ation competent and recognized as knowledge-abic to perform certain functions. l Qualified Procedure - A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has bet.n proven adequate for its intended purpose.

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--J REV. O g-- yg QUALIT( ASSURANCE MANUAL TITLE: TERMS AND DEFINITIONS PAGE 4 of 6 TERMS

l I Quality Assurance - All those planned and systematic actions necessary to pro-vide adequate confidence that an item or a facility will perform satisfactorily i in service.

Quality Control - Those quality assurance actions which provide a means to l

control and measure the characteristics of an item, process, or facility to established requirements.

Receiving - Taking delivery of an item at a designated location.

Repair - ne process of restoring a nonconfoming characteristic to a condition such that the capability of an item to function reliably and safely is unim-i paired, even though that item still may not conform to the original requirement.

Report - Something (document) that gives information for record purposes.

Rework - The process by which a nonconfoming item is made to confom to a prior specified requirement by completion, remachining, reassembling or other corrective means.

Source Surveillance - A review, observation, or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufactute.

Specification - A concise statement of a set of requirements to be satisfied by I '

a product, a material or process indicating, whenever appropriate, the procedure i by means of which it may be determined whether the requirements given are satisfied.

Standard - The result of a particular standardization effort approved by a recognized authority.

Storage - The act of holding items at the construction site or in an area other than its pemanent location in the plant.

Subsystem- A group of assembies or components or both combined to perform a single function.

System - A group of subsystems united by some interaction or interdependence, performing many duties but functioning as a single unit.

System Performance Test - A test performed on a completed system including electric, instrumentation, controls, fluid and mechanical subsystems under nor-mal or simulated normal process conditions such as temperature, flow, level, and pressure.

Testing - %e determination or verification of the capability of an item to meet specitied requirements by subjecting the item to a 3et of physical, chemical, environmental or operating conditions.

O I i REV. 0 6/11/74 QUALIIY ASSURANCE !!ANUAL TITLE: TERMS AND DFFINITIONS PAGE 5 of 6 TER!!S

l l Transit - The state of being conveyed or transported from one place to another.

Transit Carrier (Open) - Trucks, trailers, railroad cars, barges, aircraft or ships which do not afford items protection from the environment.

Transit r.arrier (Closed) - Trucks, trailers, railroad cars, barges, aircraft or uhips which provide protection of items from the environment by nature of their closed design.

Set-Point A* predetermined critical level at which a bistable device changes state to indicate that the quantity under surveillance has reached the selected value.

Use-as-is - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering func-tional requirements including performance, maintainability, fit and safety. 1 It Vendor - Any organization under contract for furnishing items or services.

includes the terms Contractor, Subcontractor, Supplier, Fabricator and sub-tier levels where appropriate.

Verification - An act of confirming, substantiating and assuring that an activ- l ity or condition has been implemented in conformance with the specified require- l l

ments. l l l Work Instructions - Written instructions used to transmit detailed information on the specific measures necessary to comply with the requirements of quality assurance procedure or any complex or difficult quality-related task.

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i e DAE REV. O 6/11/74 l

QUALITY ASSURANCE MANUAL TITLE: TERMS AND DEFINITIONS PAGE 6 of 6 TERMS

a RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE 0 Initial Issue 6/11/74 1 Response to AEC Questions Submitted 12/13/74 11/21/74. Revisions to Section 2, 4, and 7 as indicated.

2 Response to NRC Questions Submit:ed 3/4/7S 2/7/75. Procedure Numbers 1005.xx '

changes to 1004.xx (Number Change Only) 3 General revision to change AEC to NRC, 9/8/76 update organization, reflect NSP revisions, minor program implementation I I changes.

4 Eliminate Quality Assurance Committee Changes to Procurement Control - Qualifi-cation of Vendors. Organizational Changes.

Incorporate Technical Specification Changes, l

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1. ORGANIZATION 1.1 SCOPE This section defines lines of responsibility and describes the organizational structure for the quality assurance functions required for the safe and reli-able operation, maintenance, and modification of AP6L Nuclear Plants.

1.2 ARKANSAS POWER 6 LIGHT COMPANY (AP6L)

The AP6L Corporate Organization relevant to the operation of nuclear plants is depicted in Figure 1.1.

The ultimate responsibility for all power production facilities within APSL, including Quality Assurance, lies with the Senior Vice Pr.sident, Production, Transmission and Engineering. He provides management assessment of the Qua *410.2 lity Program through review of Quality Assurance General Audit (ANO-14) *4 reports and reports of NRC activities. Functioning under the Senior Vice *4 President, Production, Transmission and Engineering and providing line con-trol over power plant operation is the General Office-Production Department headed by the Director of Power Production.

The Vice President, Financial Services, shall be respmible .or the purchas *3 ing functions affecting Plant operation as described in Subsection 1.3.2.

p V 1.3 ADMINISTRATIVE SERVICES The Administrative Services Organization (Figure 1-2), provides purchasing ser-vices and overall personnel safety control requirements in support of the oper-ation of AP6L Nuclear Plants. The duties of individuals performing key func-tions related to the quality ef the activities involved are as follows:

1.3.1 Manager of Safety The Manager of Safety reports to the Director of Personnel and shall be responsible for the following quality-related duties and activities:

1) Serves as a member of the Safety Review Committee

2) Establishes the corporate safety policies

3) Publishes the Corporate Safety Manual

4) Is responsible for.AP6L imp)? mentation of OSHA requirements

5) Inspects AP6L facilities for compliance with the Corporate Safety Manual.

1. 3. 2 Supervisor of Purchasing '

l I

(qThe Supervisor of Purchasing reports to the Manager, Purchasing and Stores, and

, 'shall be responsible for the following quality-related duties and activities:

DATE

[ QUALIT( ASSURANCE MANUAL EV. 4 9/8/77 TITLE: ORGANIZATION PAGE 1 of 17 SECTION 1

s lh1) Prepares purchase orders based upon receipt of reviewed and approved, purchase requisitions.

2) Performs the commercial interface functions between APGL and contractors or vendors.

3) Assures that quality documentation prepared by Plant or Production Depart-ment personnel are included in purchasing documents.

1.4 PRODUCTION DEPARTMENT The Production Department, headed by the Director of Power Production, shall be responsible for all activities related to the operation of APGL Nuclear Plants.

These activities include design, procurement, modification, maintenance, and operation. Within the Power Production Department, coordination of the Quality *4 Assurance Program shall be accomplished by the Manager of Quality Assurance. *4 1.4.1 Quality Assurance Organization (QAO)

The AP6L Quality Assurance Organization as shown in Figure 1-3 is under the direction of the hhnager of Quality Assurance, who reports to the Assistant *4 Director of Power Production. The Quality Assurance Organization performs *3 review, surveillance, inspection and audit functions during design, construc-tion and operational phases of APGL's Nuclear blants. The duties and

- 3 responsibilities of the Quality Assurance Organization during the design and

'"# ; construction phases are described in the APSL Quality Assurance Manual -

Nuclear Construction. QA0 duties and responsibilities in support of the *4 operational phase are described below. The Quality Assurance Organization is independent of existing design, construction, and operation organizations , and *3 reports directly to the Assistant Director of Power Production. _

4 l

1.4.1.1 Manager of Quality Assurance The Manager of Quality Assurance shall possess the following qualifications:

1) He shall possess a degree from an accredited school in engineering or a related scientific discipline or equivalent.

2) He shall possess a minimum of five years experience in the quality assur-ance or quality control disciplines with at least two years in the nuclear

~

field.

3) He shall exhibit the ability to plan, schedule and direct the activities of others assigned to or functioning within the Quality Assurance Organi:ation.

1.4.1.1.1 Responsibilities *

4

1) The Manager of Quality Assurance is responsible for developing Quality

7-~s Assurance Program requirements for design, procurement, manufacture,

' ) construction, modification, operation, and maintenance related to the Q-Listed system, structures, and components in APSL Nuclear Plants.

4 DATE REV.

QUALITY ASSURANCE MANUAL 9 / 8 /,' ,'

TITLE: _0RGANIZATION SECTION

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[] 2) he Manager of Quality Assurance shall be responsible for the audit of *4

(/ all quality assurance activities conducted within the AP6L orgaai:ation.

i

3) The Manager of Quality Assurance is responsible for the review, approval *4 and verification of the quality assurance requirements placed upon contractors or vendors that provide equipment, material. or services for 8 AP6L Nuclear Plants.

4) The Manager of Quality Assurance has the authority to stop work where *4 conditions exist that prohibit effective quality control inspections, or if faulty materials, incorrect workmanship or procedures are detected.

(For plant operations the stop work authority is directed through the

Plant Superintendent.) *

5) The Manager of Quality Assurance is also responsible for the control, and

distribution of QA Manuals and QA Manual Revisions. *

6) The Manager of Quality Asst.rance is responsible for review and approval

of QA programs for outside organizations participating in the AP6L QA

program. *

7) ne Manager of Quality Assurance establishes provisions for the resolution * ;

of disputes involving quality, arising from a difference of opinion between

QA personnel and other department (engineering, procurement, manufacturing,

etc.) personnel.

1.4.1.2 Quality Assurance Engineers and Supervisors

1.4.1.2.1 QUALITY ASSURANCE SUPERVISOR

i The Quality Assurance Supervisor reports to the Manager of Quality Assurance. *4 He shall supervise QA Engineers and Inspectors, as assigned, and assist the

Manager of Quality Assurance in the coordination of activities of the QA

i Section. The Quality Assurance Supervisor may also perform duties normally

i assigned to Quality Assurance Engineers.

1.4.1.2.2 QUALITY ASSURANCE ENGINEER The Quality Assurance Engineer (QAE) report, to the Manager of Quality Assur-

ance or QA Supervisor, as assigned. Quality Assurance Engineers assure

adequate control of quality activities in the areas of Construction, Opera-

tions, Engineering and Audits. They possess the necessary functional

independence and authority to investigate, identify and effect solutions to

quality problems. Specifically: *

1) The QAE shall have the authori*.y to audit or review practices, records,

files, instructions, directions or documents concerned with all areas

affecting quality. *

/N) !The QAE shall schedule and coordinate audits or surveillance efforts in

, the areas assigned, document findings, and report to the Manager of

Quality Assurance and the Manager of the audited area.

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' QUALITY ASSURANCE MANUAL REV. 4 TITLE: ORGANIZATION SECTION PAGE 3 of 17 3

9) 3 The QAE shall not perform any activity concerned with design, procure-ment, or construction except in the areas of observation, review or

audit. He shall have no in-line production or construction responsi-

bilities. *4 1.4.1.2.3 QUALIFICATIONS

R e Quality Assurance Engineer and Supervisor report to the Manager of

Quality Assura' ice. They verify by audit the effective implementation of the Quality Assurance Program for Operations. They are thoroughly knowledgeable *4 of the Quality Assurance Program and associated procedures, Safety Analysis Reports, and 10 CFR 50, Appendix B. They are familiar with the regulatory guides, codes, and standards that address quality assurance. They confer with the Manager of Quality Assurance in regard to technical issues, periodic audits, reviews, nonconformances, corrective actions and external. relations 1 including inplant contractor and vendor representatives. He Quality Assurance Engineers and Supervisors shall possess the following qualifications: *4

1) Be a graduate of a four-year accredited engineering or science school or I equivalent with two years of experience in quality assurance, including testing or inspection of equivalent manufacturing, construction and in-sta11ation activities. At least one year of this experience should be associated with nuclear facilities; or, if not, the individual shall have completed training sufficient to acquaint him thoroughly with the Quality 9 Assurance requirements of a nuclear facility, or l

2) Be a high school graduate with at least five years experience in general l quality assurance or engineering of equivalent manufacturing, construction '

and installation activities. At least two years of this experience shall be in quality assurance, including testing or inspection of equivalent manufacturing, construction and installation activities. At least one year of this experience shall be associated with nuclear facilities; or, if not, the individual shall have training sufficient to acquaint him thoroughly with the Quality Assurance requirements of a nuclear facility, and

3) Possess an understanding of management principles necessary to organize and direct the activities of the assigned personnel. He shall have the ability to communicate clearly and p . vide effective leadership.

These education and experience requirements shall not be treated as absolute when other factors provide reasonable assurance that a person can competently perform a particular task. Other factors may demonstrate capability in a given job through previous performance or satisfactory completion of proficiency testing.

1.4.1.3 QUALITY ASSURANCE INSPECTORS *4 The Quality Assurance Inspectors report to the MrQA or designated QAE or *4 QA Supervisor and assist him in the implementation of the program by performing

audits and inspections as required to assure proper application of the Quality Assurance Program.

DATE t' -QUALITY ASSURANCE MANUAL REV. 4 9/8/77 TITLE: ORGANIZATION SECTION PAGE 4 cW 17

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' QA Inspectors are assigned by discipline or specific responsibility and are )

r: quired to have specialized training and at least three years experience (or equivalent) in his area of responsibility.

1.4.2 Nuclear Services Organization The Nuclear Services Organization (NS0) is a quasi-organization reporting to *3 the Assistant Director of Power Production. The NSO is made up of the Nuclear

Proj ects, Nuclear Fuels, and Licensing Sections of the Production Department.

These sections share the common use of procedures, drawings, and administrative

l controls. '

1.4.2.1 Manager, Nuclear Fuel *

3

'Ihe Manager, Nuclear Fuel reports to the Assistant Director of Power

Production and shall be responsible for all APSL activities affecting utili-

zation of nucicar fuel within AP6L Nuclear Plants. His duti~es include the following:

1) Provide technical direction and administrative guidance to engineers and technicians as assigned.

2) Ensures conformance to the quality-related procedures and instructions f3 which apply to design, engineering, procurement and utilization of nuclear

,vl fuel by APGL and its Prime Contractors and vendors.

3) Reviews all design, engineering and fabrication of nuclear fuel by APGL and its Prime Contractors and vendors.

4) Prepares specifications and requisitions for the purchase of nuclear fuel.

5) Reviews or initiates all correspondence, specifications and drawings relating to nuclear fuel.

6) Recommends "stop work" for cause for the engineering, design and fabri-cation of nuclear fuel to the Assistant Director of Power Production. *3

7) Coordinates fuel performance analyses with Middle South Services.

8) Maintains accountability for all nuclear fuel within the possession of AP6L.

9) Interfaces with the onsite Nuclear Engineer regarding nuclear fuel receipt, fuel performance, spent fuel shipping and refueling of the nuclear plants.

10) Establishes reload fuel enrichment requirements and core configurations.

- 11) Serves as a membe7 of the Safety Review Committee.

J DATE 7 QUALITY ASSURANCE MANUAL REV. s 9/8/7-'

TITLE: ORGANIZATION PAGE 5 of 17 SECTION

1.4.2.2 Manager, Licensing *

3 The Manager, Licensing reports to the Assistant Director of Power Production

and shall be responsible for all Federal, State and local licensing require-ments for AP6L Nuclear Plants. His duties include the following:

1) Provides technics 1 direction and administrative guidance to engineers and technicians as assigned.

2) Is designated as the lead'APSL representative for the Nuclear Regulatory *3 j Commission licensing activities. j

3) Coordinates with the Manager, Nuclear Projects, MrQA Plant Superintendent, *4 and Manager, Nuclear Fuel all licensing interface activivies between APGL, the NSSS supplier, and the architect-engineer for all AP6 nuclear power *4 ;

plants. *4

4) Reviews and recommends approval for or approves all licensing work perform- *3 ed by APSL, the NSSS supplier, and the architect-engineer. 3 l

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5) Reviews and recommends approval for or approves all permit and licensing *3 '

applications (Federal, State, and local) necessary for each AP6L nuclear *4 l power plant. *4

) Reviews the plant licensing status on a routine basis with the Assistant *3 l 4

Director of Power Production. l

7) Initiates, reviews or approves all Reportable Occurrence and Significant

Deficiency 10CFR50.55(e) reports for each AP6L nuclear power plant.

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4 ,

8) Reviews or initiates all applicable incoming and outgoing correspondence

regarding licensing of APSL nuclear power plants. *

9) Coordinates all licensing hearings and meetings with the NRC regarding *4 l the Preliminary Safety Analysis Report (PSAR), Final Safety Analysis !

Report (FSAR), and Environmental Report (ER) . l

10) Provides a licensing schedule for the Assistant Director of Power Produc- *4 tion.

3

11) Serves as a member of the Safety Review Committee. *4

12) Coordinates the environmental impact reporting requirements related to *4 changes in nuclear plant design.

13. Verifies the. deletions from or additions to the Q-List are based on the "4 safety-related functions of the component, system or structure as docu-mented in the Safety Analysis Report.

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~ I DATE ej! QUALITY ASSURANCE MANUAL REV. 4 9/8/77 i TITLE: ORGANIZATION SECTION t

PAGE 6 of 17

1.4.2.3 hianager, Nuclear Projects

The hfanager, Nuclear Projects reports to the Assistant Director of Power *3 Production and shall be responsible for design, engineering, construction

and startup activities related to nuclear plant projects. His duties include the following:

1) Provides technical direction and administrative guidance to:

a) Production h!echanical Supervisor

b) Production Electrical Supervisor *3 c) Production Startup Supervisor *

2) Ensures conformance to the Quality Assurance Program by instituting the necessary quality-related procedures and instructions within the Produc-tion Department.

3) Reviews and approves design, engineering and fabrication performed by APSL Prime Contractors or vendors.

4) Reviews and approves procurement documents that purchase equipment, material, and services fer the nuclear power plant projects.

1.4.3 ANO Plant Superintendent The Plant Superintendent (Superintendent of Power Plant) reports directly to *3 the Assistant Director of Power Production and shall be responsible for assur-

ing that the plant is operated in a safe, reliable, and efficient manner, in accordance with Technical Specifications and in compliance with all regulatory requirements. He shall also be responsible for the overall direction and administration of the training, safety and onsite quality programs.

The Plant Superintendent has the r.uthority to shut the plant down if required,

and has final approval of all pl.mt procedures. *4 1.4.4 Operation and blaintenance Coordinator h Operation and blaintenance Coordinator reports to the Assistant Director *3 of Power Production and has the following quality-relate i duties and

responsibilities:

1) Servea as a member of the Safety Review Committee.

2) Is responsible for non-nuclear related plant maintenance and operation.

1.4.5 blanager, Chemistry and Technical Services *4 The blanager, Chemistry and Technical Services reports to the Assistant Director

of Power Production and has the following quality-related duties and responsi-O bilities:

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DATE

[ QUALITY ASSURANCE btANUAL REV. 4 973777 l TITLE: ORGAF'.ZATION SECTION 7 PAGE / of 17 7 l

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l hl) Serves as a member of the Safety Review Committee.

2) Performs sampling and analyses support activities for nuclear r'wer plant operation and the Environmental Monitoring Program.

1.4.6 Manager, Design and Construction The Manager, Design and Construction, reports to the Assistant Director of *3 Power Prr duction, and he.s the following quality-related duties and responsi-bilities.

1) Performs initial site selection and siting surveys for all APGL power generating stations.

2) Coordinates the design and construction activities for all non-nuclear !

power generating projects.

1.4.7 Director of General Office Engineering *3 The Director of General Office Engineering reports to the Senior Vice.

1 President, Production, Transmission and Engineering, and is responsible for

construction of transmission lines and substation and t:ansmission system )

operat, ions. *4 1.5 ARKANSAS NUCLEAR ONE ORGANIZATION All activities which affect qua ity shall be performed by individuals whose scope of authority and duties are clearly established and delineated in writing. .

l The structure of authority and lines of communication for Arkansas Nuclear One organization is shown in Figure 1-4.

For descriptive purposes the ANO organization may be divided into deven groups, *3 as follows:

1) Administrative 4) Operations 7) Instrumentation and *3 Controls (ISC) *

2) Nuclear 5) Maintenance

3) Quality Control 6) Technical Support

1. 5.1 Administrative 1.5.1.1 The Plant Superintendent's responsibilities are described in Section 1.4.

1.5.1.2 The Assistant Plant Superintendent assists the Superintendent in all phases of plant management. He assumes all the responsibilities and authorities of the Superintendent in his absence. He is also respon-fy sible for coordinating the efforts of the Opeiation, Maintenance,

) Technical Support, Nuclear, Quality Control, and ISC Groups. *3 5 REV. 4 ^

t QUALITY ASSURANCE hDNUAL t 0/9/77 TITLE: ORGANIZATION PAGE 8 mg 17 SECTION

r)1.5.1.3 The Nuclear Plant Administrator reports to and assists the Plant *3

( ,j Superintendent in the plant administration. In addition, he administers the activities of the clerical staff and the accumulation and disposition of records related to all phases of the nuclear power plant. The clerical staff consists of the Records Supervisor and *3 clerks. The Nuclear Plant Administrator also has the responsibility for the security of the plant. *3 1.5.2 Nuclear 1.5.2.1 The Nuclear Engineer is responsible for monitoring reactor core and

Nuclear Steam Supply System (NSSS) performance for conducting reactor

performance and physics testing as required to assure safe and reliable

operation and to provide current accurate information to operations.

He is responsible for collection and transmittal of nuclear fuel manage

ment data to the Nuclear Fuel Section in Little Rock, Middle South

Services in New Orleans, and the reactor vendors as required. The

Nuclear Engineer is responsible for on-site safeguards and accounta-

bility of the nuclear fuel and assists in planning of all fuel move- *3 ments including new fuel receipt, fuel shuffling at refueling, and

shipment of spent fuel.

1.5.2.2 Two Reactor Engineers assist the Nuclear Engineer in performing the

tasks of reactor and NSSS performance monitoring and evaluation in

collection and transmittal of nuclear fuel management data and in

7"'SI maintaining the safeguards and accountability program for nuclear fuel.*

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1.5.2.3 The Reactor Technician is responsible for procurement and preparation

of test equipment required for reactor core performance and core

physics monitoring and testing. He is further responsible for main-

tenance of computer software related to the monitoring of reactor or

NSSS performance. He assists in the conduct of testing as required.

1.5.3 Quality Control 1.s.3.1 The Quality Control Engineer shall be responsible for implementation of the Quality Assurance Program for Operations at the plant. He reports to, an' receives directions from, the Assistant Plant Super-intendent. .'te Quality Control Engineer has authority to communicate wit' the Manager of Quality Assurance or his representative for tech-nien1 assistance and coordination in resolving significant conditions adverse to quality.

The duties of the Quality Control Engineer include surveillance, checks, inspections, reviews of quality-related activities and docu-ments, and maintenance of the Quality Control files. The Quality Control Engineer shall have the authority to place any item in a nonconforming status when he determines such item to be in violation of purchase documents, applicable codes and standards, or FSAR requirements.

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'n DATE 5

QUALITY ASSURANCE MANUAL REV. 4 9fgf'-

TITLE: ORGANIZATION PAGE 9 of 17 SECTION

1.5.4 Operations Group 1.5.4.1 The Supervisor of Plant Operations shall be responsible for directing *3 the actual day-to-day operations of the plant. He supervises the operating staff and is responsible for operator training and qualifi-cations. He coordinates operation-related maintenance activities with the Supervisor of Plant Maintenance, Technical Support Engineer, *3 and Nuclear Engineer. The Supervisor of Plant Operations shall have

authority to shut the plant down if conditions warrant such action.

1.5.4.2 The Assistant Supervisor of Plant Operations reports to and assists the Supervisor of Plant Operations in directing the day-to-day operation of *3 the power plant. He is responsible for coordination and daily review of operating surveillance tests and coordination of operation related *3 maintenance activities. He will assist the Supervisor of Plant Opera- *3 tions in the supervision of core refueling, which includes advance planning for the outage, plant preparation, equipment check-out, and the refueling operation.

1.5.4.3 The Shift Operating Supervisor shall be responsible for the actual *3 operation of the unit during his assigned shift. He directs activities of the unit during his assigned shift. He directs activities of the operators on his shift and is cognizant of all operation-related -

maintenance activities being performed while he is on duty. In the S absence of health physics personnel, he shall be responsible for having health physics activities performed as th'e need arises. The Shift Operating Supervisor on duty has the authority to shut down the unit

3 if, in his j udgment, conditions warrant such action.

1. 5. 5 Maintenance Group

4 1.5.5.1 The Supervisor of Plant Maintenance shall be responsible for organiz- *3 ing and conducting a preventive maintenance program and for directing repairs of electrical and mechanical equipment. He shall be responsi-ble for the training and qualification of the maintenance staff. He oversees the operation of the warehouse and assures maintenance of an adequate inventory of spare parts and consumables. He coordinates.

operation-related maintenance activities with the Supervisor of Plant *3 Operations. The Supervisor of Plant Maintenance shall have.the authority to make repairs on any structure, system, or component under his control.

1.5.6 Technical Support Group 1.5.6.1 The Technical Support Engineer reports directly to the Assistant Plant

Superintendent and supervises the Technical Support Group. Technical

Support for the plant is divided into four distinct functional sub- *3 groups with a supervisor for each group, as follow in paragraphs

1.5.6.2 through 1.5.6.5.

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DATE EV. 4 QUALITY ASSURANCE SMNUAL 9/8/77 TITLE: ORGANIZATION PAGE 10 of 17 SECTION

=_

91.5.6.2 The Plant Performance Engineer reports to the Technical Support

Engineer. His responsibilities include: 1) Evaluating equipment and

4 system performance over extended periods and recommending methods of

l improving and maintaining good plant efficiency, 2) investigating and *3 evaluating equipment malfunctions or failures and recommending corrective * '

action to prevent excessive recurrences, and 3) provide assistance in

completing records and reports that require special knowledge and/or j skill. '

1.5.6.3 The Health Physics Supervisor reports to the Technical Support Engineer.*

He is directly responsible for and has the authority to implement the

Health Physics program at Arkansas Nuclear One and maintains exposures *3 as low as practical. His daily duties include supervision of Health

Physics Technicians and he is essentially free from operating pressure

to implement the ALARA program because he reports to the Technical

Support Engineer who is on the level of maintenance and operations.

1.5.6.4 The Radiochemistry Supervisor reports to the Technical Support

Engineer. He has the responsibility for assuring that reactor *3 plant water conditions are maintained within acceptable limits and

for management of liquid and gaseous radwaste.

1.5.6.5 The Chemistry 6 Environmental Supervisor reports to the Technical

Support Engineer. He has responsibility for assuring that secondary

O plant water conditions are maintained within acceptable limits.

The scope of his responsibility includes surveillance and mainten-

ance of water quality conditions in the condensate and feedwater *3 cycle, startup boiler, heating boiler, nuclear and non-nuclear loops

of the intermediate cooling water system, evaluation of circulating

water chlorination system, evaluation of plant makeup and condensate

demineralizer equipment.

1.5.7 Instrumentation and Controls Group

1.5.7.1 The Instrument 6 Control group is responsible for the calibration,

maintenance, checking, adjustment, testing and surveillance of all

instrument and controls systems inherent to the power plant . This

includes the plant computer and the maintenance of a test equipment

1ab to assure the most accurate test equipment possible. The force is

under the supervision of the Instrument 6 Controls Supervisor, who

reports directly to the Assistant Plant Superintendent. The Instrument *3 and Controls Supervisor is also responsible for keeping the plant

computer operational for data collection, fuel management, and equip-

ment status; maintain inventory of spare parts for ISC reliability

and performance, as necessary. Three Assistant Instrument 6 Controls

Supervisors report directly to the Instrument and :ontrols Supervisor. *

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[ QUALITY ASSURANCE MANUAL V* 4 9/8'77 TITLE: ORGANIZATION PAGE 11 of 17 SECTION

1. 6 QUALITY PROGRAM C0bNITTEES 1.6.1 Safety Review Committee (SRC) *4 1.6.1.1 Membership *4 Ditactor Power Production (Chairman)

Assistant Director of Power Production *3 Maintenance and Operations Coordinator Arkansas Power 5 Light Company Manager of Safety Arkansas Nuclear One Superintendent Manager, Chemistry and Technical Services *4 Arkansas Nuclear One Nuclear Engineer Radiation and Health Physics Consultant Nuclear Safety Consultant Manager, Nuclear Fuel *3 Manager, Licensing

In his absence, the Chairman shall appoint an Acting Chairman. *3 Alternates:

1) Each permanent voting member shall have an alternate to serve in his *3 absence. Alternates shall be appointed in writing by the SRC Chairman. *

2) No more than two alternates shall serve on the committee at any one time as voting members. *3 1.6.1.2 Function *4 Members and alternates shall collectively review and audit the areas of: *4

1) Reactor Operations *

2) Nuclear Engineering *

3) Chemistry and Radiochemistry *

4) Metallurgy *3

5) Instrumentation and Control *

6) Radiological Safety *

7) Mechanical and Electrical Engineering *

8) Environmental Considerations *

9) Other appropriate Fields Required by the Unique Characteristics

of the Nuclear Power Plant.

When the nature of a particular situation dictates, special consultants will be utilized to provide expert advice to the SRC upon request of *3 the SRC Chairman.

DATE

'Y QUALITY ASSURANCE MANUAL REV. 4 afgf

TITLE: ORGANIZATION SECTION PAGE 12 of 17

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1. 6.1. 3 Heeting Frequency *4 The Safety Review Committee shall meet on call by the Chairman but not less I frequently than once per 6 months. During the period of initial operation, *4 Safety Review Committee shall meet no less frequently than once per calen- {'

dar quarter.

1.6.1.4 Quorum *4

1) A quorum shall consist of the Chairman or his designated alternate and *3 five members including alternates. *

2) Either the Chairman or Acting Chairman shall be present.

3) No more than a minority of the quorum shall have line responsibility for nuclear unit operation.

1.6.1.5 Authority and Responsibility

The Safety Review Committee shall report to and be advisory to the Senior Vice *4 President, Transmission and Engineering (PTSE) in those areas of responsibility

specified in 1.6.1.6 and 1.6.1.7.

a 1.6.1.6 Review

The SRC shall review:

1) The safety evaluations for 1) changes to procedures, equipment or I systems and 2) tests or experiments completed under the provisions of *3 10CFR50.59, to verify that such actions did not constitute an unreview-

j 3

ed safety question. -

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2) Proposed changes to procedures, equipment or systems which involve an l unreviewed safety question as defined in 10CFR50.59. *3

3) Proposed tests or experiments which involve an unreviewed safety '

question as defined in 10CFR50.59. *3 l

4) Proposed changes in Technical Specifications or licenses.

5) Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having neclear safety significance.

6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

I

7) Reportable occurrences requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission. *

3

8) Reports and minutes of Plant Safety Committee meetings. *

r. . r -

W QUALITY ASSURANCE MANUAL REV. 4 DATE 9/8/77 TITLE: ORGANIZATION SECTION PAGE 13 of 17 p

G1.6.1.7 Audits

4 Audits of fac?lity activities shall be performed under the cogni::ance of the SRC. These audits shall encompass: *3

1) The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.

2) The performance and retraining of all members of the facility manage-

ment and operations staff, and the performance, training, and qualifi- *3 cations of new members of the entire facility staff at least once per year.

3) The results of all actions taken to correct deficiencies occurring in facility equipment, structure, systems or methods of operation that affect nuclear safety at least once per six months.

4) The Facility Emergency Plan and implementing procedures at least once *3 per two years. l

5) The Facility Security Plan and implementing procedures at least once *4 per two years.

'^ 5 V) Any other area of facility operation considered appropriate by the *3 SRC or the Senior Vice President (PTSE).

1.6.1.8 Records

4 Racords of SRC activities shall be prepared, approved and distributed as

indicated below: *

3

1) Minutes of each (SRC) meeting shall be prepared, approved and forwarded

to the Senior Vice President (PTSE) within 30 days following each

meeting.

2) Reports of reviews encompassed by Section 1. 6.1. 6. 5) , 6) , 7) , and 8) * --

above, shall be prepared, approved and forwarded to the Senior Vice

President (PTSE) within 30 days following completion of the review. *3

3) Audit reports encompassed by Section 1.6.1.7 above, shall be forwarded * -

to the Senior Vice President (PTSE) and to the management positions

responsible for the areas audited within 30 days after completion of the audit.

1.6.2 Plant Safety Committee (PSC) *4 1.6.2.1 Membership

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i Assistant Plant Superintendent (Chairman) *3 I

, Technical Support Engineer l Instrumentation and Controls Supervisor *3 '

Supervisor of Plant Operations

Supervisor of Plant Maintenance

Nuclear Engineer Health Physics Supervisor *3 The Plant Superintendent shall appoint an acting chairman in the absence of

the Assistant Plant Superintendent.

1.6.2.2 Meeting Frequency *4 Monthly, and as required, on call of the Chairman or his designated alter- *3 nate.

1.6.2.3 Quorum *4 Chairman plus three members including alternates. *3 1.6.2.4 Alternates *4 '

Designated alternates shall be appointed by the Chairman in writing and

shall serve only on a temporary basis; however, there shall be no more than *3 I two (2) alternate members serving on the committee as voti :g members at any

9 onetime.

1.6.2.S Responsibilities * '

The Committee shall be responsible for: *

4

1) Review of all procedures required by Appendix A of the Technical

Specifications and revisions and any other proposed procedures or * -

revisions as determined by the Superintendent to affect nuclear safety. *

2) Review of proposed tests and experiments which affect nuclear safety. j

3) Review of proposed changes to the Appendix A Technical Specifications. *3

4) Review of proposed changes or modifications to plant systems or equipment which affect nuclear safety.

S) Review of nuclear unit operations to detect any potential nuclear safety *3 ha:ards.

6) Investigation of reported instances of violations of the Technical Specifications, such investigations to include reporting evaluation and *3 {

recommendations to prevent recurrence to the Superintendent. * '

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/ ~'} 7) Performance of special reviews and investigations and render reports *3 3 \s_) thereon as requested by the Plant Superintendent.

8) Review of the Plant Security Plan and implementing procedures and shall *3 submit recommended changes to the Plant Superintendent. *

4) Review of the Emergency Plan and implementing procedures and shall submit *

recommended changes to the Plant Superintendent. *

3

10) Review of those reportable occurrences requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to

the NRC.

1.6.2.6 Authority *4 The Plant Safety Committee shall: *3

1) Recommend to the Plant Superintendent written approval or disapproval *3 of proposals under items 1.6.2.5(1) through 1.6.2.S(4) above.

a) In the event of a disagreement between the recommendations of the i Plant Safety Committee and the actions contemplated by the Super- i intendent, the course determined by the Plant Superintendent to be *3 more conservative will be followed. Records of the disagreerant will be sent for review to the Assistant Director of Power *

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Production and the Safety Review Committee by the Plant Superin- *3 tendent on the next working day. *

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2) Render tentative determinations, in writing, as to whether or nr t *3 items considered under 1.6.2.5(1-4) and 1.6.2.5(6) above involve *4 !

unreviewed safety questions. l l

1.6.2.7 Records

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Minutes shall be kept by the committee of all meetings of the Plant Safety

Committee and copies shall be sent to the Chairman of the Safety Review *3 j Committee by the Superintendent.

f 1.6.3 Environmental Responsibilities *4 l The Plant Safety Committee and the Safety Review Committee shall review and l audit the following: l l

1) Preparation of proposed Environmental Technical Specifications.

2) Coordination of Environmental Technical Specification development with the Safety Technical Specification.

3) Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes. '

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97g777 g TITLE: ORGANI2ATION SECTION PAGE 16 of 17 1

4) Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's environmental impact.

5) Proposed changes or modifications to plant systems or equipment which

would affect the plant's environmental impact and the evaluation of the impact of these changes.

6) Results of the Environmental Monitoring Programs prior to their submit-tal in each semiannual Environmental Monitoring Report.

7) Investigation of all reported instances of violations of Environmental Technical Specifications. Where investigation warrants instances shall be evaluated and recommendations formulated to prevent recurrence.

1.7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES As owner and operator, APGL assumes full responsibility and authority for the Plant and shall take all appropriate action to assure that the Plant is operated in accordance with sound engineering practices, including appli-cable codes, specifications and procedures.

The Assistant Director of Power Production is responsible for establishing *3 technical and management interfaces between the constructor, architect-

engineer (A/E), nuclear steam supply system (NSSS) vendor, and AP5L. These *1 i

Dnterfaces may be utilized cchnical consultation as needed and services. Theseduring operation interfaces of a nuclear**410.10 are established unit for prior to the complete phaseout of the design and construction forces to

assure an orderly transition within the contractor firms.

Each supplier of equipment, material or services and each maintenance or 1 modification contractor is responsible for administering the applicable !

quality control functions as required by AP6L. The Quality Assurance l

Organi:ation is responsible for assuring by surveillance and audit that '

these functions are accomplished for all systems and structures that affect the safety and integrity of the plant.

Visits to manufacturer's shops by Quality Assurance Organization personnel are conducted to establish product quality and to ensure that quality l assurance and quality control programs function in accordance with APGL requirements.

The Manager, Quality Assurance is responsible for communications with the l NRC Regional Office regarding NRC quality assurance requirements related *3 to the quality assurance activities described in the Quality Assurance Program for Operations and the implementation of the procedures within APSL support organizations.

'Ihe Plant Superintendent is responsible for communications with the NRC *3 Rtgional Office regarding the adequacy, implementation and use of the Quality Assurance Program for Operations at the Plant.

G l DATE i QUALITY ASSURANCE MANUAL

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O O O t 3 OIAIRMAN OF 111E BOARD AND Cl!IEF EXEClTflVE OFFICER PRESIDENT 6 O!IEF OPERATING OFFICER SENIOR VICE PRESIDENT SENIOR VICE PRESIDENT PRODUCTION, TRANSMISSION PERSONNEL VICE PRESIDENT CUSTOMER SERVICES 4 ENGINEERING DIRECTOR FINANCIAL SERVICES DIRECTOR OF GENERAL DIRECTOR OF DIRECTOR OF DIRECTOR OF OFFICE ENGINEERING POWER PRODUCTION SYSTEM PLANNING CORPORATE SERVICES Arkansas Power S Light Company Figure 1-1 Corporate Organization Rev. 3 9/8/76

O O O .

r PRESIDENT 6 CillEF OPERATING OFFICER VICE PRESIDENT PERSONNEL FINANCIAL SERVICES DIRECTOR i

DIRECTOR OF CORPORATE SERVICES MANAGER OF SAFETY MANAGER OF PURCilASING AND STORES 1

SUPERVISOR OF PURCilASING Figure 1-2 Rev. 3 9/8/76 Arkansas Power G Light Company Administrative Services Organization

A /

Arkansas Po Production, Light Company ransmission 6 Engineering

()h SR. VICE PRESIDENT PROD. TRANS. ENGR.

SAFE 1Y REVIEW COMMITTEE I I DIRECTOR OF DIRECTOR OF DIRECTOR OF GENERAL SYSTEM PLANNING POWER PRODUCTION OFFICE ENGINEERING I

ASSISTANT DIRECTOR OF POWER PRODUCTION I E E I E MANAGER MANAGER OPERATION 5 0111ER PROD. MANAGER DESIGN AND CllEMISTRY AND MAINTENANCE DEPARTMENT QUALITY CONSTRUCTION TEGINICAL SERVICES COORDINATOR SECTIONS ASSURANCE

.. ___ _ _ . _ _ _ . _ _ _ . ~

_3 ANAGER MANAGER l ANO QUALITY UCLEAR NUCLEAR MANAGER I PLANT ASSURANCE FUEL PROJECTS LICENSING l SUPERINTENDENT STAFF

, ; ______________a , ,

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PRODUCTION PRODUCTION t PRODUCTION PLANT ASSISTANT ELECTRICAL MECilANICAL I STARTUP SAFETY PLANT SUPERVISOR SUPERVISOR SUPERVISOR COMMITTEE EUPERINTENDENT l

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g [_,[_) - NUCLEAR SERVICES ORGANIZATION '

Figure I-3 Rev. 4 9/8/77

MANAGER OF PLANT QUALITY ASSURANCE SUPERINTENDENT PLANT SAFETY NUCLEAR PLANT C0hNITTEE ADMINISTRATOR ASSISTANT PLANT SUPERINTENDENT COMMUNICATION QUALITY CONTROL SUPERVISOR OF TECHNICAL SUPPORT ENGINEER PLANT OPERATIONS ENGINEER INSTRUMENTATION SUPERVISOR OF NUCLEAR AND CONTROLS PLANT MAINTENANCE ENGINEER SUPERVISOR QUALITY CONTROL PLANT MAINTENANCE REACTOR INSPECTORS STOREKEEPER CREW ENGINEERS Arkansas Power S Light Company ANO Organization - Units 1 6 2 Figure 1-4 Rev. 3 9/8/76

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O 2. QUALITY ASSURANCE PROGRAM 2.1 SCOPE 2.1.1 The AP6L Corporate Quality Assurance Program for Operations (Program) addresses those requirements, responsibilities, and actions that pro-vide managerial and administrative controls to assure safe plant operation.

2.2 PURPOSE 2.2.1 The purpose of the Program is to ensure that Arkansas Power 6 Light Company nuclear power plants are operated in a safe, reliable and efficient manner in compliance with NRC regulations, applicable *3 industrial standards and codes and all applicable Company policies, rules, approved operating procedures and license provisions.

2. 3 APPLICABILITY 2.3.1 The Program is applied to systems, equipment and components to the extent consistent with their importance in preventing or mitigating the consequences of postulated accidents that could cause undue risk to the health and safety of the public. The Program is therefore

<~'s applied, but not limited to the structures, systems and components x ) defined in the Plant Q-List.

2.3.2 The Program functions in addition to the Quality Assurance Manual - I Nuclear Construction. The Manager of Quality Assurance and the

Assistant Director of Power Production shall approve the Program. *4 l Program adequacy and effectiveness is determined by performance cf *

audits.

l 2.3.3 AP6L shall be responsible for the assurance that nuclear fuel used in AP6L Nuclear Plants is designed, procured, manufactured, and utilized in accordance with regulatory requirements, and related industrial codes and standards. AP6L delegates to Middle South Services the actual performance of quality assurance functions related to the design, procurement and manufacture of. nuclear fuel. The Middle South Services Quality Assurance Program for the performance of 'this activity is reviewed and approved by the Manager of Quality As' surance. The *3 technical interface with Middle South Services is the responsibility of the Manager, Nuclear Fuel. The interface and its attendant *3 duties and responsibilities are controlled by the procedure for fuel management control (NSP-IV-1). Onsite quality control for nuclear *3 fuel is implemented through the use of procedures in the Master Plant l Manual.

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2.3.4 The Program defines responsibilities and duties to specific positions.

These responsibilities and duties may be performed by other qualified persons if the specified individual is not available.

2.4 PROCEDURES 2.4.1 Activities which affect quality shall be defined in appropriate proce-dures. Procedures shall be developed to cover APGL administration and control. The procedures shall state the policies and instructions necessary to fulfill the intent of the Program. Procedures shall *3 provide for standard forms, lists and checkoffs used in documenting the

l inspections, certifications, reviews and audits. The Program and the procedures shall be modified or supplemented from time to time as the i need for change arises during the life of the Plant.

2.4.2 The procedures ensure that activities affecting quality are perfonned under suitaely controlled conditions. Controlled conditions include the use of appropriate equipment; suitable environmental conditions for performing the activity such as adequate cleanness and assurance that required prerequisites for the given activity have been satisfied.

The procedures also specify the need for special controls, processes, and test equipment to attain the required quality, and the need for verification of quality by inspection and test.

2.4.3 Program Procedures

1) Quality Assurance Procedures l

The Quality Assurance Organization employs a system uf procedures designated as Quality Assurance Procedures (QAP) in order to I implement the requirements of the Program. The QAP's and revisions thereto are prepared by the Quality Assurance Organization, reviewed and approved by the Manager of Quality Assurance and approved by the Director of Power Production. QAP's referenced in this *3 document are listed by title in Table 2-1. *

2) Quality Control Procedures l

The plant operation organization employs a system of procedures i designated as Quality Control Procedures (QCP) in order to implement '

Program requirements that control onsite activities. The QCP's and revisions thereto are prepared by the plant staff, reviewed by the Plant Safety Committee and the Manager of Quality Assurance, and !

approved by the Plant Superintendent. QCP's referenced in this *3 document are listed by title in Table 2-2. *

3) Nuclear Services Procedures The Nuclear Services Organization within the Production Department employs a system of procedures designated as Nuclear Services DATE QUALITY ASSURANCE MANUAL 9/8/77 TITLE: QUALITY ASSURANCE PROGRAM SECTION PAGE 2 of 12

a O Procedures (NSP) in order to implement Program requirements for i

U' the control of design, engineering and procurement activities in support of the operating plant. The NSP's and revisions thereto are prepared by the Nuclear Services Organization, reviewed by the blanager of Quality Assurance, and approved by the cognizant manager

and the Assistant Director of Power Production. NSP's referenced *3 in this document are listed by title in Table 2-3.

2.4.4 Other organizations within AP6L may establish written procedures to control support activities affected by the requirements of this Pro-gram. Procedures developed by such organizations shall be prepared and reviewed for technical adequacy within the cognizant organization, reviewed by the Manager of Quality Assurance and approved by the cognizant organization's supervisor. *3 2.4.5 Any procedure used at the operating plant in the master plant manual

will be reviewed and approved in accordance with the Procedure *3 QCP 1004.21.

2.5 PROGRAM REVISION AND CONTROL 2.5.1 Program revision and control shall be the responsibility of the Manager of Quality Assurance.

2.5.2 Proposed changes to the Program shall be submitted to cognizant *

/] 'nanagers for review and comment prior to approval.

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2.5.3 Changes to the AP6L Quality Assurance Program shall be approved by the *4 l l Manager of Quality Assurance c..d the Assistant Director of Power

Production. j !

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, Quality Assurance Programs of Others * '

2.5.4.1 The Program includes provisions that require suppliers, contractors,

subcontractors, consultants, etc. , to maintain and use adequate quality assurance programs.

2.5.4.2 Contractor quality assurance programs shall be reviewed and approved *4 by the Manager, Quality Assurance. The review and approval of such documents by AP6L in no way relieves the contractor of his respon-sibility to AP6L to meet the applicable quality requirements of the licensing agracy as outlined in 10 CFR 50, Appendix B. Audits by the Quality Assurance Organization provide assurance of con.pliance with applicable procedures 2.6 SYSTEM, STRUCTURE, AND COMPONENT CLASSIFICATION 2.6.1 The system, structures and components that perform safety-related functions are designated as Q-List items. The Q-List specifically ,

l identifies those systems, structures and components whose failure

/'] could cause an uncontrolled release of radioactivity, or those j

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( essential for safe shutdown and the immediate and long-term operation i

(]/ following a Loss of Coolant Accident. When structures, systems or equipment as a whole are on the list, portions not associated with a loss of safety function are not meant to be included. l 2.6.2 The Q-List is initially generated by the architect-engineer during the design phase of the project. The Q-List is considered a design document and is reviewed and approved in accordance with the proce-dure for design verification (NSP-II-4). The approved Q-List is *3 retained as a functional document throughout the life of the plant to provide for the application of Program requirements to a specific system, structure or component.

2.7 TRAINING AND PERSONNEL Employees whose duties and responsibilities are related to the quality assur-ance activities at the Plant shall participate in appropriate indoctrination and training programs. It shall be the responsibility of the employee's immediate management to arrange for the quality assurance indoctrination program. The Plant Superintendent has responsibility for Plant Staff parsonnel indoctrination regarding the Quality Assurance Program.

2.7.1 Quality Assurance Indoctrination The purpose of quality assurance indoctrination is to familiarize O the employee with the Quality Assurance Program. Emphasis is placed j \.j on the importance and meaning of quality assurance as it applies to the employee's particular position and function.

I 2.7.2 The quality assurance indoctrination for the management of AP5L support '

organi:ations shall be conducted by the Manager .of Quality Assurance or his designated representative. The management of the support organization in turn is responsible for conducting an indoctrination of employees in their respective groups. The indoctrinations they conduct shall cover the areas in which the group or employee has particular responsibilities. The Quality Assurance Program indoctri-natHn is coordinated at the plant by the Training Coordinator or his *3 i

designated representative. Quality assurance indoctrination includes the following items:

1) Discussion of the philosophy and objectives of the Quality Assurance Program.

2) Explanation of the Company's quality assurance organization and demonstration of how it affects the duties and responsibilities of the employee.

3) Summary of the QAP's and QCP's content as applicable with specific emphasis placed on those sections which most directly affect the employee's position.

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f A record of attendance at quality assurance indoctrination sessions shall be maintained by the Manager of Quality Assurance, for members of the Quality Assurance Organization and APSL support organizations.

1he Training Coordinator maintains the record of attendance for plant *3 staff.

2.8 PROGRAM REVIEW 2.8.1 The Manager of Quality Assurance shall be responsible for an annual review of the Quality Assurance Program for Operations to determine *3 the effectiveness and proper implementation of the Program (ANO-14). ;

2.8.2 Assigned Quality Assurance personnel regularly review the status,

adequacy, and effectiveness of the implementing procedures as part of *4 daily work (ANO-13, ANO-17 and ANO-18) .

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O Table 2-1 Quality Assurance Procedures ANO-3 Surveillance Audits This procedure establishes methods for performing quality assurance surveil-lance audits for Arkansas Power 6 Light Company at the manufacturing, design, or engineering facilities of companies supplying systems, materials, and/or components. It is specifically designed to verify the quality programs of suppliers and provides a method of reporting findings and identifying defi-ciencies.

4 ANO-6 Supplier Quality Assurance System Evaluation This procedure establishes methods for performing quality assurance audits

at the supplier's facility. It is specifically designed to verify the qua- *1 lity programs of suppliers to 10 CFR 50, Appendix B and ANSI N45.2, and pro-

vide a method of reporting findings and identifying deficiencies.

ANO-13 Central Chemistry Laboratory Surveillance Audit *

' GThi s procedure establishes a method for frequent surveillance audits of the *4 Central Chemistry Laboratory to assure compliance with the AP6L Quality Assurance

Program. It provides methods to identify areas of deficiency (or potential

deficiency) for necessary corrective action.

ANO-14 APSL Quality Assurance General Audit *3 This procedure establishes methods for general audit of the operating plant (s),

l Nuclear Services Organization, Quality Assurance Section and others to assure *3 ,

that quality activities conform to the requirements of 10 CFR 50, Appendix B. * '

ANO-15 Review of Supplier Documentation, Evaluation and Qualification

This procedure is designed to establish a method for documentation of reviews

and evaluations performed in-house by AP6L QA personnel to qualify suppliers for *4 providing Q-list materials or services. This includes the review and evaluation

of the Supplier's Quality Assurance Program, Manual, procedures and/or other

supporting documentation, as appropriate.

ANO-17 Operating Plant Surveillance Audit l

l This procedure establishes a method for frequent surveillance audits of plant quality activities to assure compliance with the AP6L Quality Assurance Program. It provides methods to identify areas of deficiency (or potential oficiency) for necessary corrective action.

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/30-18 Engineering Surveillance Audit

'Ihis procedure establishes a nethod for frequent surveillance audits of engineering activities and activities of other production support activities to assure compliance with the AP6L Quality Assurance Program. It provides m:thods to identify areas of deficiency (or potential deficiency) for necessary corrective action.

ANO-19 " Shelf Item" Vendor Audit

This procedure establishes methods for performing quality assu. 2nce audits

at the facilities of the " shelf item" vendor. It is specifically designed *1 to verify that items supplied are identifiable by means acceptable to indus-

try by recognized manufacturers and proven in service or tested by nationally -

accepted codes and standards. It also provides a method of reporting find-

ings and identifying deficiencies.

ANO-20 Preoperational and Startup Program Surveillance Audit *4 The purpose of this procedure is to examine the preoperational program to

10 CFR 50, Appendix B, and identify areas of deficiency and potential *3 deficiency for corrective action. *

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Table 2-2 ARKANSAS NUCLEAR ONE PLANT QUALITY CONTROL PROCEDURES *2 1004.01 Design Control This procedure establishes the methods for control and design measures for the modification of those plant systems and plant equipment identified on the plant Q-List. The interface control and responsibilities between ANO and the Nuclear Projects Section for design work are established.

4 1004.04 Turnover of Q. A. Documents from Construction to APSL This procedure describes the methodology for Review of Quality Assurance Records associated with plant turnover. It assures that documents are *3 i

complete and adequate, and that structures, items or components are accept- *3 able to AP6L.

1004.05 Purchase Requisition Preparation and Processiirs

( I This procedure establishes it e methods and responsibilities for preparation, !

review and approval of purchase requisitions for safety-related items to assure that the procurement documents contain the quality requirements l necessary to verify that the item is in conformance with the applicable i specifications.

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1004.06 Material Receiving and Inspection 4

This procedure establishes the methods by which material is received at ANO and inspected to assure that it is the correct material, conforms to require-ments and has the proper identification and documentation. ;

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1004.07 Control of Special Processes i

This procedure covers the establishment of process controls and requirements for qualifications of personnel, procedures and equipment. {

j 1004.08 Q.C. Inspection This procedure provides control for inspection planning (including inspec- *3 tion hold points), performance of inspection, and reporting for all activi- {

ties affecting quality. *3 !

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1004.10 Calibration Control This procedure provides requirements for the calibration program, and *3 guidance for QC surveillance of inspection, measuring and test equipment to assure that the equirment is in calibration at the time of use.

1004.11 Handling, Storage and Shipping of Q-List Materials This procedure establishes the measures and methods for the handling and storage of Q-List materials at ANO to preclude degradation or damage to such material. Also this procedure covers the basic requirements for acceptable material shipping both to and from the plant to prevent damage and maintain the quality of the item being shipped.

1004.12 Operational Test Control This procedure defines testing and requirements, frequencies, documentation, coordination and administrative controls associated with ongoing testing during the commercial operation of the plant.

1004.13 Nonconformance and Corrective Action This procedure provides the methodology for reporting, analyzing, disposi-h7"')s tioning (including approvals) nonconforming material, parts and components

and further provides for inspection of resubmitted material. It also addresses the assessment of cause, recommended corrective action, follow-up and reportin' to responsible management.

1004.18 Material Identification This procedure establishes the methods by which materials, parts and compon-ents that will be used at ANO for operation and maintenance can be identified.

It addresses identification of material associated with Q-List items and *3 traceability to applicable quality assurance documentation. *3 1004.19 Hold, Caution and QC Tagging This procedure establishes the administrative controls and the methods for status identification of systems, structures and components. It provides guidelines on the use of stamps, tags and labels during inspections, tests and operations. It also covers use of the QC Hold Tag for Identifying Non-conforming Items.

1004.20 Qualification and Certification of Quality Control Personnel This procedure establishes the educational and work experience requirements for Quality Control personnel engaged in inspection or testing. *3

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s 1004.21 Handling of Procedures *3

'this procedure covers the handling of procedures used in the operating *3 plant. These procedurer ill cover details necessary for operating the *3 ANO facility in a safe, t., liable and efficient manner. Specific areas covered by this plan are Quality Control Procedures, Administrative *3 Procedures, Operating Procedures, Emergency Procedures, Maintenance Procedures, Chemistry and Radiation Protection Procedures, Test and Inspection Procedures and Refueling Procedures.

1004.22 Document Control *2 This procedure establishes the methods by which changes and revisions to specifications, drawings and engineering documents that describe the "as-built" condition of ANO are controlled, distributed and dispositioned.

This procedure also establishes the distribution lists for procedures and documents used in the quality-related activities at ANO.

1004.23 Drawing Control *2 This procedure establishes responsibility of the Arkansas Nuclear One (ANO) staff and method by which engineering drawings are controlled including receipt, filing, indexing, distribution, disposition of superseded drawings,

,m and retention.

<V) 1004.24 Plant Records Management *2 This procedure establishes the methods of documenting handling and storing records generated during operation, maintenance, modification and repair of the Plant.

1004.25 Document Retention and Disposition *3 This procedure identifies the specific records which must be retained for *3 Arkansas Nuclear One and specifies the method of retention and the required retention periods for such records.

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TABLE 2-3 NUCLEAR SERVICES PROCEDURES NSP-II-1 Design Interface Control *3 This procedure establishes the internal and external interface control by

' which the Nuclear Services Organization controls each discipline contri-

buting to the design process within AP6L. The Manager, Nuclear Projects *3 is established as the focal point for all extemal design work accomplished *3 for APGL by NSSS supplier, architect-engineer or engineering consultants.

NSP-II-2 Design Criteria *3 The procedure formalizes the establishment of the design bases and criteria for safety-related systems, structures and components.

NSP-II-3 Design Process *3 This procedure establishes the methods for the preparation of drawings, O

V specifications and analyses including calculations. Standardized formats for design disclosure documents are established and specific quality levels of acceptance standards as guidelines are provided.

NSP-I '-4 Design Verification

3 This procedure establishes the methods used within APGL for the independent checking of design documents through a formalized design review or alternate calculation or qualification testing.

NSP-II-5 Design Change Control *3 This procedure establishes the methods used to maintain control of design changes during design, fabrication and construction phases of a nuclear project and for control of modifications to operating nuclear plants.

NSP-II-6 Design Deficiency / Corrective Action *3 This procedure forma 11:es the reporting of design deficiencies and provides *3 a method of positive feedback to assure that appropriate corrective action is taken to prevent recurrence of the deficiencies.

NSP-II-7 Design Document Control *3 This procedure establishes those design documents that are controlled within

[^')

v the Production Department by providing a standardized file and distribution system compatible with the ANO Records System and future projects.

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i 9 NSP-II-8 Drawing Control \

This procedure establishes the responsibility of the Nuclear Services *3 Organization and the method by which engineering drawings, either in paper form or on aperture cards, are controlled, including receipt, filing, disposition of nuperseded drawings and retention.

NSP-II-9 Procurement Control *3 This procedure establishes the responsibilities and methods by which I procurement of safety-related parts, material or services is reviewed and approved by APGL. It includes the required QA review and technical review i

of contractor-prepared purchase specifications and documents.

NSP-II-10 Purchase Requisition Preparation and Precessing *3 This procedure establishes the methods used for the procurement of safety-related parts, materials and equipment by AP6L when the item or service is procured solely by APSL in accordance with a reviewed and approved specifi-cation. This procedure provides detailed control for the actual preparation, ,

review and approval of a purchase requisition and for the distrit'ation c:n- l trol and follow-up of the actual purchase order released to the vendor by the Supervisor of Purchasing.

O NSP-IV-1 Fuel Management Control *

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, { l 3. DESIGN CONTROL 3.1 SCOPE 3.1.1 Design activities shall be controlled to assure that proposed plant 1 changes to the structures, systems, equipment and components conform to applicable regulatory requirements and that design bases are cor- ,

rectly translated into appropriate design documents. l 1

3.2 GENERAL l

3.2.1 The APGL Production Department shall be responsible for the continued-upgrading and modification of plant design. Design documents (drawings, l i

specifications, procedures and instructions) originating or released '

for review through these departments shall be based upon the required regulatory requirements, quality standards and design bases i in accordance with NRC licensing requirements. Design activities *3 !

may include calculations, analyses, materials, selection, equipment arrangement and layouts, and specifications of test and inspection criteria that are essential to the safety-related functions of the structures, systems and components. Those design activities per-formed by individuals within the APSL Production Department are controlled by the use of QAP's for the design process (NSP's -II-1-8). *3 The plant staff uses QCP 1004.01 for the control of design activities.

{ } 3.2.2 Design standards and requirements shall be at least equivalent to those employed during the construction of the station and shall be consistent with the Technical Specifications and license provisions.

3. 3 DESIGN PROCESS / VERIFICATION 3.3.1 To assure that the design is adequate and that the above requirements and procedures are satisfied, each design document related to design change shall be internally reviewed by the organization initiating the design. The internal review may be accomplished using alternate calcu-lation methods or by the establishme:tt of a suitable test program.

hhere a test program is used to verify the adequacy of a specific design feature in lieu of other verifying or checking processes, it shall include suitable qualification testing of a prototype unit under the most adverse conditions.

3.3.2 Reviews of design documents generated within APSL are accomplished using applicable design verification and design control procedures (NSP- II-4) . *3 I l A

REV* 3 QUALITY ASSURANCE MANUAL 9/8/76 TITLE: DESIGN CONTROL ON PAGE 1 of 3 3

3.3.3 During the above reviews, particular attention shall be given to the following areas:

1) Assurance that all appropriate standards are clearly delir. 'ated in the documents, h'her it is considered necessary to deviate from these standards, sep. ate written approval shall be required from the Manager, Nuclear Projects and shall be appended to the *3 approval sheet releasing the document (s) for implementation.

2) Assurance that the qualifying information for the materials, com-ponents, equipment and processes is contained in the documents and is suitable for the intended applications. This information shall include, as applicable, the physics, hydraulics, thermal, strength and accident analysis utilized; the compatibility of design for in-service inspection, maintenance and repair; and the acceptance criteria for inspections and tests. Performance history t and failure data on installed components is considered when similar components are intended for installation as part of a system or structure modification.

3) Assurance that design interfaces are compatible and consistent with the overall design bases and existing systems where more than one activity has participated in the designs.

4) Assurance that the design document is consistent with the Safety Analysis Reports and, if required, that the need for NRC approval *3 prior to the final approval of the design document has been iden-tified.

5) Assurance that the inspection requirements of Section 10 are included and adequate.

6) Assurance that errors and deficiencies discovered in the design as a result of the reviews are documented and disposition assigned.

A feedback system of corrective action by distribution of the review comments to the originating activity shall be used to prevent repetitive errors or deficiencies in the design process.

3.3.4 Additional changes to the basic document (s) (including field changes as a result of modifications which in any way affect the technical adequacy of the design) shall be subject to the same review criteria as the basic documents.

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{ } 3.4 DESIGN RECORDS 3.4.1 The Nuclear Plant Administrator shall be responsible for maintaining *3 permanent records of the design documents for the construction and testing phases. In addition, he shall be responsible for maintaining records of the upgrading or modification of these documents as des-cribed in this section. The controls for maintaining these records are established by specific procedures described in Section 17. These records provide the historic reference necessary for the safe and reliable operation of the plant.

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! 4. PROCUREMENT DOCUMENT CONTROL 4.1 SCOPE 4.1.1 Control of the procurement activities shall provide assurance that applicable regulatory requirements, design bases, technical require-ments and quality assurance criteria are suitably included or referenced in the documents for procurement of material, equipment, and services, whether purchased by APGL or by its contractors and/or s ubcontractors . Procurement documents are the drawings, specifica-tions and purchase requisitions that result in a purchase order.

4.2 GENERAL 4.2.1 Vendors shall be selected from the Qualified Vendor List (QVL).

4.2.2 Vendors may be placed on the QVL as approved by th MrQA by any of

the following methods: *

1. By satisfactorily meeting 10CFR50, Appendix B requirements by

facility survey by APGL. (ANO-6) *

2. Pursuant to appropriate documented information received from *

,s others, i.e., Architect-Engineer, NSSS Supplier, other utilities, *

,(\~-} NRC, AShE, etc. , indicating a program meeting appropriate require-

ments of 10CFR50, Appendix B. *4

3. A review of the Supplier's current quality records supported by

evidence of documented qualitative and qm.ntitative information

which can be evaluated. This includes review and evaluation of the

Supplier's Quality Assurance Program, Manual, and Procedures, as

appropriate. (ANO-15 ) *

4. Survey of the vendor or contractor to assess his capability to

document and execute controls that meet the requirements of the

purchase order, including verification that his technical capa-

bility, organization, facilities and inspection measures are

commensurate with P.O. requirements (ANO-19) . Vendors qualified

l by this method are limited to those supplying in-kind or off the

shelf replacement parts that do not alter the design intent of

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the original component specification.

4.2.3 Purchase documents for spare or replacement parts or parts of safety-related structures systems or components, including "off the shelf" *1 items, procured by the plant staff shall be reviewed by the Plant *4 Quality Control Engineer for adequacy of quality requirements. The review determines similarity, compatibility, current regulatory applicability and inclusion of, at a minimum, the quality assurance requit 'ments and acceptance criteria of the original part. As part of the .? view, a document control form shall be included which IG specifies the documents to be supplied by the vendor to verify that engineering quality, inspections, and tests have been completed.

,' DATE QUALITY ASSURANCE MANUAL REV. 4 9/8/77 t

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.2.4 The preparation, review and control of procurement documents are established in the procedures for purchase res :isition preparation *3 and processing (NSP-II-10; QCP 1004.05). ,

4.2.5 The Manager of Quality Assurance shall verify the compliance with procurement procedures and shall evaluate the effectiveness of these procedures. Methods of verification and evaluation are delineated in quality assurance procedures for surveillance audits and general audits (ANO-3; ANO-6; ANO-14; ANO-17; ANO-18; ANO-19; *3 and ANO-20) .

4.2.6 When multiple procurement is involved, the Purchasing Department shall apply identical quality assurance requirements to each vendor.

4.2.7 APSL purchase documents shall require prime vendors to apply the applicable quality assurance requirements to each sub-tier vendor where such requirements apply to the goods or services being purchased by AP6L from the prime vendor.

4.3 REQUISITIONS 4.3.1 Requisitions for Q-List material, equipment or services may be initiated by any plant employee, but shall be reviewed and approved by the cognizant supervisor, Plant Quality Control Engineer and by a the Plant Superintendent or Assistant Plant Superintendent or designee

before issue of a purchase order. (1004.05)

l 4.3.2 When a Q-List design change is involved, requisitions are initiated *4 by the Nuclear Projects Section as described in the procedure for

purchase requisition preparation and processing (NSP-II-10) or by

the plant staff as described in 4.3.1.

4.3.3 Requisitions for Q-List items shall be clearly identified as Q-List.

4.4 SPECIFICATIONS 4.4.1 Specifications for Q-List replacement parts shall be at least equiva-lent to the applicable portions of specifications under which the equipment was originally furnished. In situations where a part is being replaced for inadequate service or because its operational requirements were modified, its specification must reflect the new requirements imposed.

4.4.2 Q-List specifications shall be reviewed by the Nuclear Services *3 Organization to assure that applicable cc-les, standards and other

design bases are included or referenced and that appropriate and sufficient requirements for quality assuranae documentation are incorporated therein. Applicable codes, stacdards and other design bases are determined from a review of the FSAP, Q-List, material control list, drawings and other design disclosure documents which

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_} apply to the "as-built" plant. These review requirements are specified in the quality assurance procedure for design verification (NSP-II-4) .

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QUALITY ASSURANCE MANUAL TITLE:

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4.5 PURCHASE ORDERS 4.5.1 Purchase orders shall be issued by APSL Purchasing Department and shall affirm those requirements set forth in the specifications.

4.5.2 Purchase orders for Q-List items shall require that vendors and their subvendors possess a Quality Assurance Program consistent with the applicable requirements of 10 CFR 50, Appendix B, or ANSI N45.2 which apply to the specific goods or services provided by that vendor. . The Purchase Order shall include provisions for source surveillance and inspection, as required.

4.5.3 Changes to purchase orders and reference documents for Q-List *1 items are to be subject to review equivalent to that of the *410.13 original documents.

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5. _ INSTRUCTIONS, PROCEDURES AND DRAWINGS 5.1 SCOPE 5.1.1 Instructions, procedures and drawings shall be provided as necessary for the control of those activities which affect quality. Activities controlled by procedures include: Administration, normal operations, maintenance, security, inspection, testing, health physics, chemistry, refueling, surveillance, emergency operations and quality assurance and quality control programs and procedures. I 5.1.2 Additional procedures may be required as determined by the Plant Superintendent. j 5.2 GENERAL 5.2.1 Instructions, tests, calibration, specifications, procedures, main- *1 i

j tenance, modification and repair processes are developed, reviewed *410.1S

-and approved according to the administrative procedure on handling

of procedures (QCP 1004.21). Drawings are controlled by the admini- *2 i

strative procedure for drawing control (QCP 1004.23). Drawings and *2 j specifications related to plant modifications are reviewed according *1 l to the procedures for design change control (QCP 1004.01 and NSP-II-5)*410.15 !

for QA concurrence of the quality designation of the design change *3 packagc. QA review of drawings and specifications related to modi-

fications involving Q-List systems or equipment is provided by the

Plant Safety Committee.

5.2.2 Instructions, procedures and drawings which prescribe activities which affect quality shall include appropriate quantitative or qua-litative criteria for determining that important activities have been satisfactorily accomplished.

5.2.3 Procedures which affect quality shall include measures to document I t

the activity being performed.

5.2.4 To assure accomplishment of the activities in accordance with approved I

instructions, procedures and drawings, each supervisor shall be re-sponsible for quality compliance of personnel under his supervision.

Surveillance by the Plant Quality Control Engineer and periodic sur-veillance by the Manager, Quality Assurance ensures compliance with approved instructions, procedures and drawings. Additionally, audits by the Quality Assurance Engineer (Operations) verify compliance with approved instructions, procedures and drawings.

5.2.5 The format, content and philosophy of instructions and procedures shall comply with the guidelines provided in ANSI N18.7-1972, "Administra-tive Controls of Nuclear Power Plants".

5.3 TEMPORARY CHANGES l I Ji QUALITY ASSURANCE MANUAL REV. 3 DAR ar m TITLE: INSTRUCTIONS, PROCEDURES AND DRAWINGS PAGE 1 of 2 SECTION 5

5.3.1 Temporary changes to procedures in the Master Plant Manual which do 9 not change the intent may be made provided such changes are approved by two members of the plant staff at least one of whom holds a *4 senior reactors operators license on the unit affected. *4

5. 3. 2 Temporary changes to the procedures in the Master Plant Manual which involve an intent change may be made provided such changes are reviewed by the PSC, approved by the Plant Superintendent or his *4 representative prior to implementation. *4 5.4 CHANGES TO PROCEDURES 5.4.1 Changes or revisions to approved Plant instructions, procedures or *3 drawings which affect quality are controlled by the procedure on handling of procedures (QCP 1004.21). *2 5.4.2 Changes or revisions to Quality Assurance and Nuclear Services

procedures require the same review and approval as specified by *3 paragraph 2.4.3.

5.5 REVIEW 0F PROCEDURES, INSTRUCTIONS AND DRAWINGS 5.5.1 Applicable procedures, instructions and drawings shall be reviewed following any unusual incident (e.g., abnormal equipment malfunction or accident) and revised, as necessary to prevent recurrence of such q incidents.

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5. 5. 2 Applicable instructions, procedures and drawings shall be reviewed, and revised as necessary, following any modifications to the plant.

5. 5. 3 Applicable instructions and procedures shall be reviewed, and revised as necessary, following major changes to the Quality Assurance Program.

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6. DOCUMENT CONTROL 6.1 SCOPE 6.1.1 'Ihe issue, receipt, use, and storage, and changes thereto, of documents which affect quality shall be controlled. Documents which shall be controlled include drawings, specifications, instructions and proce-dures.

6.1. 2 Documents are controlled by the following procedures:

1) Design document control (NSP-II-7). *3

2) Drawing control (NSP-II-8). *3

3) Plant records management (QCP 1004.24) *2

4) Document retention (QCP 1004.2S) *2

5) Document Control (QCP 1004.22) *2

6) Drawing control (QCP 1004.23) *3 6.2 GENERAL l l 6.2.1 Documents pertaining to quality-related activities such as specifica-tions, procedures and drawings shall be used only after proper review and approval.

6.2.2 The Nuclear Plant Administrator shall supervise the issuance of the *3 Master Plant Mnnual and shall assure that the approved revisions are distributed to the location where the subject activity is being performed.

6.2.3 An issue sheet or facsimile shall be employed to maintain a record of persons to whom documents have been issued.

6.2.4 Changes in documents shall be subject to the following:

1) Prior to implementation, documents affecting quality such as instructions, procedures and drawings shall be reviewed to assure that they are adequate and timely, and that appropriate quality requirements are clearly and accurately stated.

2) Individuals and groups responsible for reviewing, approving and issuing documents and revisions thereto are identified in procedures for handling of procedures (QCP 1004.21), and document control *2 (QCP 1004.22). *2 l l gy~

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QUALITY ASSURANCE MANUAL REV. 3 DATE 9/8/76 TITLE: DOCUMENT CONTROL PAGE 1 of 2 SECTION

f' 3) Changes to documents such as operating procedures, maintenance procedures and as-built drawings shall be reviewed and approved by the same organizations which perform the original review and approval. If such is not possible, the Plant Superintendent shall assure that the review is delegated to appropriate qt;alified responsible groups.

4) Obsolete and superseded documents shall be destroyed (except for *3 one file copy) or stamped to prevent inadvertent use.

6.2.5 Permanent plant documents are stored at the plant site by the plant

staff under the supervision of the Nuclear Plant Administrator. *3 Records (or copies, as appropriata) generated by the Nuclear Services *1 Organization, Quality Assurance, or others are provided to the plant *410.10 staff for storage. These records include: *

1) Procurement documents for items purchased by the Nuclear Services *3 Organization.

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2) Design Specifications, Drawings, and Design Criteria originated

or revised by the Nuclear Services Organization. *3 1

3) Design Change Request packages and supporting documents, j i

6.3 DOCUMENT IDENTIFICATION 6.3.1 Documents shall contain a title descriptive of their purpose or '

applicability and shall be conspicuously labeled as to current status (Draft, Preliminary, Approved, Void, etc.) '

6.3.2 An indication of current revisions to specifications, procedures and drawings shall be maintained in a document control register or within I

I a revision record page or other appropriate means.

6.4 STORAGE AND FILING REQUIREMENTS I 6.4.1 Documents which affect quality shall be stored at the plant in per-manent storage facilities in a manner which allows ready and positive identification and retrievability. The storage technique shall mini-mize damage and preserve the integrity of the documents. Storage con-trols are set forth in procedures for plant records management, and document retention (QCP 1004.24; QCP 1004.25). *2 I

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7.1.1 The purchase of material, equipment and services shall be controlled !

to assure that, whether purchased directly or through vendors, the material, equipment and services which affect quality conform to the )

procurement documents. Procurement control shall include provisions, I

as appropriate, for the evaluation and selection of vendors, objective l evidence of quality, furnished surveillance of the vendors and exam-

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ination of products upon delivery.

7.2 SOURCE EVALUATION 7.2.1 Vendors shall be selected on the basis of demonstrated capability j during the design and construction phase to provide a quality product, process or service in accordance with the procurement documents for j the operational phase. 1 7.2.2 When the vendor is not on the Qualified Vendors List (QVL), the Mana- *1 ger of Quality Assurance shall review and approve the vendor's quali-fications as described in paragraph 4.2.2 *4 7.3 DOCUMENTATION OF QUALITY A 7.3.1 Verifiable evidence of quality shall be furnished by vendors as h prescribed in the procedure for procurement control. (NSP-II-9) *3 7.3.2 Documentary evidence that material and equipment conform to the pro-curement requirements shall be available at the site prior to installation or use of such material and equipment. As necessary,

vendors are to be requested to maintain documentation. A certificate *1 of conformance is to be maintained at the plant site to reference *410.12 any documentation by the vendor. Such documentary evidence shall be

retained at the site and shall be sufficient to identify the specific requirements, such as codes, standards or specifications, met by the purchased material and equipment. On a case basis the QCE may release certain equipment for installation without proper documentation, but before the equipment is used all documents shall be received. A non-conformance report is filed in such a case.

7.4 SOURCE INSPECTION 7.4.1 The effectiveness of quality control by vendors shall be assessed by the Manager of Quality Assurance at intervals consistent with the importance, complexity, and quantity of the product or service.

Requests for source inspection by the Manager of Quality Assurance are made by the plant Quality Control Engineer or the Quality Assurance Engineer (Engineering) during their reviews of purchase requisitions.

O DATE QUALITY ASSURANCE MANUAL REV. 4 9/8/77 TITLE: CONTROL OF PURCHASED MATERIAL, SECTION EQUIPMENT AND SERVICES PAGE 1 of 2 7

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. ( ) 7.4.2 Source inspection shall be documented and shall provide a record !

of compliance by the vendor with regard to:

1) The vendor's quality assurance program.

2) 10 CFR 50, Appendix B, or ANSI N45.2 (applicable to the product or service provided). !

3) Design and quality classification, codes and standards which l apply to the product or service provided. i

4) The procurement document requirements.

7.S RECEIPT INSPECTION

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Upon receipt of Q-List materials at the plant, a receiving inspection shall be performed and the condition of the material clearly and completely record-ed in a receiving report as prescribed in the procedure for material receiv-ing and inspection (QCP 1004.06).

1 This procedure assures that.

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1) The material,. equipment or component is properly identified and corres-ponds with the receiving documentation, as required by 4.2.3. *1 410.17A

2) Inspection of the material, component or equipment and acceptance q records is performed in accordance with predetermined inspection

'ij instructions, prior to installation or use. *4

3) Items accepted and released are identified as to their inspection status and forwarded to a controlled storage area or released for installatior.. I i

4) Nonconforming items are held in a segregated, controlled area when *4 practical and are clearly identified until proper disposition is made *4 l in accordance with the procedure for nonconformance and corrective l action.

5) Supplier non-confomances which have been accepted by APGL prior to

shipment of the item shall be documented in the procurement records *1 furnished by the supplier at the time of receipt or the item shall *410.17B be considered non-conforming as required by procedure 1004.06 and

1004.13.

7.6 STORAGE 7.6.1 Q-List materials shall be handled and stored as prescribed in the procedure for handling, storage, and shipping of Q-List materials (QCP 1004.11).

l 7.6.2 Q-List material shall be clearly identified as such and stored in a controlled area.

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{ } 8. gEpFICATION AND CONTROL OF MAT 1! RIALS, PARTS AND COMPONENTS 8.1 SCOPE 8.1.1 Identification and control measures shall be established to assure that all quality-related materials, parts, components and partially fabri-cated assemblies are directly traceable to the documentation which verifies their acceptance as required throughout fabrication, receipt, storage, installation and use of each item.

8.1. 2 The measures shall be sufficient to prevent the use of incorrect, defective or illegibly marked materials, parts and components.

8.2 IDENTIFICATION AND MARKING 8.2.1 Materials, parts and components shall be identified and marked by suppliers in accordance with requirements set forth in applicable codes and in the procurement documents. The requirements shall assure that:

1) Marking of shipping containers or packages is sufficient to allow *3 proper handling of the container or package and positive identi-fication of received items at the plant. *3

2) Identification of parts and corresponding documents will accompany all partially fabricated assemblies shipped as one unit. Such

{ } documentation shall include, as applicable, heat numbers, part numbers, serial numbers, material certifications and weld quali-fications to provide sufficient bases for determining the accepta-bility of the assembly and its component parts.

8.2.2 Markings of items or material shall be done using methods not deleteri-ous to the integrity of the material.

8.2.3 When specified by purchasing document, individual items shall be per-manently marked.

8.2.4 Group or bundle marking and temporary marking may be authorized by the Quality Control Engineer as conditions warrant, and provided that posi-tive identification and traceability of the items or material can be maintained.

8.2.5 All Q-List materials, parts and components are identified as required *1 by 1004.18. *410.18

8. 3 TAGGING 8.3.1 In addition to being marked, Q-List materials, parts and components shall 'ie tagged with a "Q Tag". The tag shall identify the item and the permanent filed records which document the item.

g 8.3.2 Nonconforming items shall be identified by affixing a "Q" Tag and shall be segregated where possible.

$52" QUALITY ASSURANCE MANUAL REV. 3 DATE Bf TITLE: IDENTIFICATION AND CONTROL OF 9/8/76 MATERIALS, PARTS AND COMPONENTS PAGE 1 of 2- SECTION g

s 8.3.3 Tagging shall be performed in accordance with the procedure for material

/ identification (QCP 1004.06).

8.4 DOCUMENTATION 8.4.1 Documentation for parts and materials received from vendors shall be stored in the Quality Control File as described in the procedure for plant records management (QCP 1004.24). *2 8.4.2 'the removal of Q-List items from storage and their subsequent disposi-tion shall be documented and controlled by the Release to Maintenance form described in the procedure for material identification (QCP 1004.18).

8.5 DEFECTIVE OR INCORRECT ITEMS 8.5.1 Defective or incorrect materials, parts and components which cannot be reworked or repaired for their intended use by acceptable methods shall be handled in accordance with Section 15 of the Program and the proce-i dure for nonconformances and corrective action (QCP 1004.13).

l 8.5.2 Defective or incorrect items shall be clearly identified on the "Q" tag, i

8.5.3 Defective or incorrect items shall be stored in segregated areas when-

! ever feasible.

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9. CONTR0i 0F SPECIAL PROCESSES G 9.1 SCOPE 9.1.1. Special processes performed in the course of operations at the Plant are controlled by the procedures on special processes (QCP 1004.07) to assure that they are properly and safely accomplished.

9.2 RESPONSIBILITY 9.2.1 The Plant Superintendent shall be responsible for assuring compliance with the requirements for control of special processes, and for developing adequate staff training and procedures for special processes identified in the future.

9.2.2 The Supervisor of Plant Maintenance, Technical Support Engineer and *3 Quality Control Engineer shall develop procedures and provide qualified personnel for current special processes as delineated in the procedure for control of special precesses (QCP 1004.07).

9.2.3 Quality Assurance personnel shall periodically audit special process *4 procedures and personnel qualification to assure compliance with applicable codes and specifications.

9.3 GENERAL 9.3.1 Special processes include, but are not necessarily limited to:

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1) Special maintenance and cleaning.

2) Metal joining, such as welding, and brazing.

3) Thermal cutting.

4) Hot and cold working and bonding.

5) Coating and plating.

6) Nondestructive examination. l

7) Heat treating. *4 l

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9.4 -QUALIFICATION 1 9.4.1 Personnel shall be qualified and/or certified for each special process according to applicable regulations, industrial standards and other requirements as described in the procedure for control of special

processes (QCP 1004.07).

i 9.4.2 1he Training Coordinator maintains records of personnel qualification appropriate to each special process. On request, he shall provide lists of qualified personnel and their particular qualifications to the cognizant supervisor of the special process to be performed.

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10.1 SCOPE 10.1.1 On and offsite activities affecting quality are inspected to verify conformance with applicable procedures, design documents, codes and specifications for accomplishing the activity.

10.1.2 Inspection of quality-related activities is controlled by the process *1 for inspection (QCP 1004.08) which specifies inspection requirements,*410.19 techniques, documentation and responsibility as described in Section 3, 4, and 7 of the Program.

10.1.3 Quality-related activities subj ect to inspection include, but are not limited to:

1) Special processes as identified in Section 9 of the Program.

2) Modifications to the plant.

3) Repairs or replacement of equipment.

4) Receipt of Q-List materials, parts or components.

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5) Operation of safety-related items. !

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6) Special maintenance activities, t

7) Inservice Inspection.

10.2 RESPONSIBILITY l

10.2.1 The Plant Superintendent shall be responsible for assuring that plant personnel comply with the regulations, codes and procedures controlling inspection.

10.2.2 The Quality Control Engineer or his designated representative shall perform required inspections within the plant. Source surveillance /

inspection shall be the responsibility of the Manager of Quality Assurance. The Quality Control Engineer is responsible for reviewing and approving inspection records and for assuring that inspection hold points were properly documented.

10.2.3 Quality Assurance personnel shall periodically audit inspection *4 procedures, inspection records and personnel qualifications to assure that inspection requirements are being fulfilled. l l

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h 10.3 INSPECTION PROCEDURES 10.3.1 To accomplish inspections, written procedures, instructions, diagrams, I forms and checklists shall be provided which as a minimum contain

! the following:

I

1) Qualitative and quantitative acceptance criteria.

2) Identification of those individuals. responsible for performing the inspection operation.

i 3) A description of the method of inspection examination, measure-ment or test of material or product process necessary to be performed to assure quality.

I 4) Identification of any special tools, equipment or skills required.

5) A signoff by signature or a controlled stamp showing evidence of completing and verifying the inspection. 1 l

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6) The results of the inspection operation. l 10.3.2 If inspection of processed material or products is impossible or dis-advantageous, indirect control by monitoring processing methods, equipment, and personnel shall be provided. Both inspection and g process monitoring shall be provided when control is adequate without both.

10.3.3 Inspection personnel shall verify that inspection equipment utilized is within calibration prior to performing any inspection operation.

If improper or out-of-calibration equipment is found, the inspector has the authority to suspend the inspection activities.

10.3.4 If an inspection of a quality-related activity reveals that a noncon-formance has occurred, the inspector has the authority to suspend further activity until the nonconformance is rectified.

10.3.4.1 Nonconformances are reported and corrective action is implemented in accordance with Sections 15 and 16 of the Program and the procedure for nonconformance and corrective action (QCP 1004.13).

10.4 INSPECTOR QUALIFICATION 10.4.1 Personnel qualified to perform inspections are normally the Quality Control Engineer, the onsite quality control staff and the quality assurance inspectors. Personnel qualified to perform inspections shall meet the following requirements:

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1) Be independent from the individual or group performing the activity being inspected, *4

2) Have satisfactorily completed the qualification requirements as specified in the procedure for qualification and certification of quality control personnel (QCP 1004.20), or *4

3) Be currently qualified and so designated on a list of qua2ified inspectors approved by the Quality Control Engineer or the Manager of Quality Assurance.

10.5 DOCUMENTATION 10.5.1 Records of inspections shall be maintained by the Quality Control Engineer in accordance with the procedures governing document control, and document retention (QCP 1004.22; QCP 1004.25). *2 O

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p 11. TEST CONTROL 11.1 SCOPE 11.1.1 Necessary testing requirements to determine whether Q-List structures, systems and components perform satisfactorily in service shall be established in written test procedures. The test procedures shall incorporate the requirements and acceptance limits contained in the Technical Specifications, codes and regulations, and applicable design, operating, maintenance and manufacturer's documents. Testing within the scope of this section includes both periodic testing and those tests required as a result of modification, maintenance, or repair of safety-related items.

11.2 SURVEILLANCE TESTING "l

h10.8 11.2.1 Testing of Q-List structures, systems and components shall be perform-ed by qualified personnel in accorda*,ce with approved written test procedures.

The supervisor responsiale for performing the test shall verify that all test equipnent is properly calibrated.

11.2.2 The test procedures shall include the following (as applicable):

1) ' Test procedure approval sheet.

2) Test objective or applicability.

3) Prerequisites for testing.

b) Acceptance criteria.

5) References.

6) Special test equipment.

7) Limits and precautions.

8) Step-by-step instructions.

9) System lineup checklists for test and return to normal.

10)

Data sheets providing sufficient parameter checks and data gathering.

11) Test results review and approval signature sheet.

11.2 3 In addition to regularly scheduled surveillance tests, tests shall be performed following significant plant modification or significant changes in operating procedures to confirm that the modification or l l DATE QUALITY ASSURANCE MANUAL

1 12/13/7h TITLE: TEST CONTROL SE C ON PAGE 1 of 3

,1

changes are nnt i3trimental to the safe and efficient operation of IO the plant.

11.2.4 All surveillance calibration, checks and inspections required by Section 4 of the Technical Specifications shall be specified on an

" Operational Test Control List." This list shall state the title, type of surveillance activity, frequency and cognizant individual *3 responsible for completion of the surveillance activity.

11.2.5 To ensure that the required tests are performed as scheduled within each time interval, a computer program has been devised to indicate when tests are required.

11.3 PROCEDURE APPROVAL 11.3.1 Test procedures shall be subject to the same review and approval pro-cess as outlined in Section 6 of the program.

11.4 DOCUMENTATION AND REVIEW OF TEST RESULTS 11.4.1 Test results shall be documented and reviewed to assure that the test objective has been met and that action called for by the test is taken.

11.4.2 Records of test results shall include at least the following:

1) Identity of part of material, system, structure, or component *3 under test.

2) Date of test.

3) Data taken.

4) Name and signature of individual performing test.

5) Test results and conclusions.

6) Identity of portable test equipment. *3

7) Recommendations for corrective action or retesting resulting from the test.

8) R<c.:ew signatures of cognizant supervisors, and final review

ugnature of Plant Superintendent when required.

11.4.3 Testing records shall provide objective evidence that the test was performed in compliance with approved procedures. Testing records shall be maintained in the plant files in accordance with the pro-cedures for document retention (QCP 1004.25). *2 F&'

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11.5 PREOPERATIONAL TESTING 11.5.1 A manual describing the provisions that control the transfer of

safety related equipment and records from the principal contractors

to AP6L during the preoperational testing phase up to fuel loading,

shall be prepared and shall include the identification of those *1 significant QA-related activities, provisions established to assure *410.8 proper inspection and verification of equipment; the means of

tagging and identifying structure systems and components in a

manner that denotes the inspection and test status; and provisions

to assure the effective transfer, storage, and control of records.

11.5.2 Beginning with issuance of an operating license, additional

administrative controls governing testing activities must be

implemented.

The administrative controls utilized during previous *4 testing activities must, in some cases, be modified. The ANO Plant

Procedures provide for administrative controls to assure the safe

operation of the plant.

11.5.3 ' The Manager of Quality Assurance is responsible for establishing *3 audits of the preoperational testing program (ANO-20).

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( 12. CONTROL OF MEASUREMENT AND TEST EQUIPMENT 12.1 SCOPE 12.1.1 A control program shall be established to assure that tools, gages, instruments and other measuring and testing devices used in activi-ties affecting quality are controlled and calibrated with sufficient scheduled frequency to assure that accuracy is maintained within the limits spccified by the inspection or test requirements. This activity is referenced in the procedure for calibration control (QCP 1004.10).

12.2 GENERAL 12.2.1 All measuring and testing devices used in conjunction with Q-List items or systems shall be properly controlled, calibrated, and adjusted at specified intervals to maintain accuracy within the necessary limits.

12.2.2 Calibration of these devices shall normally be in accordance with manufacturer's recommendations, when available, and in all instances shall be in a manner that maintains the tolerance for accuracy of the equipment.

j 12.2.3 Calibration procedures shall conform to recognized standards and

)

local, State and Federal regulations.

1 12.2.4 The procedure shal1 be clearly noted on a calibration report, and the comparison standards utilized in the calibration method shall be traceable to the National Bureau ot 6tandards, and supported by certification reports and data sheets when applicable.

12.2.S Comparison standards utilized to calibrate other test equipment shall be more accurate than the instrument being calibrated by a factor of at least two (2). A considerable amount of test equipment calibra- *1 tions allow a factor of 10 to be used and are dependent upon the *4 2h

" state of the art".

12.2.6 Nhen inspection, examination, measurement and test equipment is

found to be out af calibration through use or damage, an evaluation

of the validity of previous inspection, examination, or test re-

sults and the acceptability of items previously inspected, examined, *1 or tested shall be made and documented by written report on a case *410.20 basis. The Plant Superintendent or his designee has final approval

of such evaluation, and at his discretion may require repetition of

the inspection, examination, or test.

12.3 RESPONSIBILITIES 12.3.1 The Instrumentation and Controls Supervisor and Supervisor of Plant *3

{ } Maintenance shall be responsible for compiling a list of all measur-( ing and testing devices under their control that require periodic calibrathm ff7'~

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12 3.2 The control of measuring and testing devices used in the calibra-O tion of Q-List equipment shall be the responsibility of the cogni-zant supervisor, who shall ensure that the devices are used only by qualified personnel and are properly segregated from other devices.

12 3.3 Plant ersonnel shall be responsible for utilizing only properly identific d and calibrated equipment.

12 3.h The Quali.y Control Engineer shall be responsible for monitoring test equipnent control and use in order to verify compilance with the program.

12.h EQUIPMENT IDENTIFICATION 12.4.1 The equipment identification list identifying equipment requiring calibration shall contain sufficient information to uniquely iden-tify each item listed and shall include calibration intervals and tolerances for accuracy.

12.k.2 Each item listed on the equipment identification list shall be label-ed in such a manner that clearly identifies the equipment and shows date of last calibration and date recalibration is due.

12 5 DOCUMENTATION 12 5.1 The following records shall be maintained in a permanent plant file:

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1) Equipment identification

2) Calibration reports and test data (until recalibrated)

3) Manufacturer's data sheets k) Cd ibration procedures l I cr -

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(( ) 13. RNiDLING, STORAGE, AND SHIPPING 13.1 SCOPE 13.1.1 Appropriate controls shall be applied to Q-List material, parts, com-ponents and assemblies to ensure that they are handled, stored and shipped in a manner which will prevent damage and deterioration of the item. These activities are referenced in the procedure for handling, storage and shipping of Q-List materials (QCP 1004.11).

13.2 SPECIAL REQUIREMENTS 13.2.1 When special cleaning, preserving, handling, packaging or shipping of purchased material is required, such requirements shall be deline-ated in appropriate purchase order documents.

13.2.2 Additionally, vendors shall be required to recommend special procedures required for handling, storage or preservation of supplied materials, l parts or components after their arrival at the station.

13.3 RECEIVING INSPECTION 13.3.1 Upon arrival of material at the station, the Supervisor of Plant *3 Maintenance shall be responsible for assuring that the items are *3 inventoried, and inspected for damage, deterioration and cleanliness as described in the procedure for material receiving and inspection

t. (QCP 1004.06) . The QC inspector is responsible for inspecting and !

classifying Q-List materials. i 13.3.2 Results of the receiving inspection and disposition of the material shall be nated in the material received inspection report.

13.4 STORAGE AND PRESERVATION 1

The Production Storekeeper shall be responsible for assuring that:

13.4.1 When possible and practicable materials are stored indoors, ana in all instances in a manner that provides adequate protection against damage or misuse.

13.4.2 Designated items receive special protection such as controlled environ-ment, locked storage, special coverings and segregation to prevent t contamination. '

13.4.3 Storage areas are monitored by the Production Storekeeper so that the security and integrity of stored item is effectively maintained.

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/ 13.S RADIOACTIVE MATERIALS 13.5.1 The Health Physics Supervisor shall be responsible for ensuring *3 that radioactive materials are handled, stored and shipped in accordance with applicable regulatory requirements.

13.6 RECORDS 13.6.1 The Quality Control Engineer shall be responsible for assuring that the following permanent records are maintained to demonstrate proper control over the handling, storage, shipping, cleaning, and preser-vation of Q-List materials:

1) Material Received Reports

2) Quality Control Receiving Inspection Reports l

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14. INSPECTION, TEST, AND OPERATING STATUS 14.1 SCOPE

( l I This section describes the measures to be employed in determining the inspec-tion, test, and operational status of systems, structures, and components re-quired to prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public (Q-List items).

It describes the means used to identify status levels to the operator, and for documenting and correcting substantial conditions.

14.2 DETERMINING OPERAT IONAL , STATUS.

14.2.1 Q-List items shall be subjected to a controlled program of surveil-lance testing and inspections to ensure that failures or substandard performances do not remain undetected, and that the required reliabi-lity of safety systems is maintained. The procedure for operational test control (QCP 1004.12) identifies the surveillance tests and in-

-spections to be performed. Nonconformances discovered shall be docu-mented and resolved as prescribed in the procedure for nonconformances and corrective action (QCP 1004.13). Controls for assuring that tests are scheduled as required and that test results are obtained are pro-vided by a computerized program or a master test centrol chart. If a

test or inspection is not performed within its required surveillance *1 interval, the Plant Superintendent is informed. He will take action *41G 22 as necessary.

14 .2.2 The adequacy of initially installed components is ensured by manu-G facturer's testing as required by the procurement contractor, and by procedures controlling material receipt and inspection, and hand-ling (QCP 1004.06; QCP 1004.07). Startup testing and performance tests following modifications verify the adequacy of newly installed l items. '

14.3 IDENTIFICATION OF OPERATIONAL STATUS 14.3.1 The quality conformance and safe operational status of Q-List mater-ials, systems, structures, and components shall be indicated to the operator through systems of tagging, as described in the procedure for hold, caution and QC tagging (QCP 1004.19). The tagging process clearly identifies materials, systems, structures, and components containing nonconforming items, and provides administrative control of their use.

14.3.2 Overall Plant Scatus 1

14.3.2.1 The Shift Operating Supervisor shall maintain sufficient knowledge of *3 overall plant status tests and inspections to control overall plant operations. The shift operators will maintain a ready reference of plant systems, structures and components alignments as well is a status board summary of abnormal conditions. The Shift Opci g *3 Supervisor shall ensure that personnel performing tests an d in sr. - e tions keep the shift operators informed of the current statua of tests and inspections. l s

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15. NONCONFOPJIING MATERIAL, PARTS, OR COMPONENTS y

15.1 SCOPE 15.1.1 Nonconforming items include materials, parts, components, processes 1 and documents that do not conform to applicable regulations, codes, standards, specifications or contractual documents.

15.1.2 Nonconforming items shall be controlled to prevent their inadvertent use or installation. Appropriate' procedures shall be established to assure the prompt detection, recording, segregation, verification, technical review and disposition, including records of disposition, -

of nonconforming items. These activities are referenced in proce-dures for purchase requisition preparation and processing, material receipt and inspection, inspections, and nonconformance and correct-ive action (QCP's 1004.05; 1004.06; 1004.08; 1004.13).

15.2 GENERAL 15.2.1 All nonconforming materials, parts, components, processes or docu-ments shall be identified as such and reported to the cognizant super-visor (s) for disposition and corrective action. This rule shall apply no matter where or when the discrepant item is discovered (e.g. during vendor surveillance, receiving inspection, storage surveillance installation, or operation).

p)15.2.2

( Reports of nonconformance shall be prepared and circulated to the U Quality Control Engineer, cognizant supervisors, and/or other indivi- !

duals authorized to approve dispositions and corrective action. These reports shall clearly and positively identify the item, describe the l nature of nonconformance and give recommendation for disposition *3 ;

and for corrective action. 1 15.2.2.1 The procedure for material receiving and inspection (QCP 1004.06) {

defines the action to be taken when defective items are received. j 15.2.2.2 Source inspection nonconformances shall be identified to the vendor *4 l and reported in inspection reports in accordance with the procedure *4 !

for quality control inspection MCP 1004.08).

15.2.3 Recommended disposition of nonconformance reports prepared in accord- *4 ance with the procedure for Nonconformance and Corrective Action *4 (1004.13) shall be approved by the Plant Superintendent prior to *4 implementation. All dispositions involving decisions to."use-as-is" *1 or " repair" shall be reviewed by the Manager, Nuclear Projects. *410.23 15.2.4 The specifications for quality assurance in each procurement docu-ment or contract require the vendor or contractor to identify all material or parts that do not conform to the procurement require-ments. All such vendor nonconformances shall be reported to APSL as required by the applicable purchase order or contract.

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') 15.2.5 Re' acceptability of rework or repair of materials, parts, components,

,I V systems and structures, or of remanufactured items shall be verified by reinspecting the item as originally inspected or by a method which is at least equal to the original inspection method. W e rework and repair inspection records shall be documented and shall become part of the quality assurance records for the item.

15.3 TAGGING AND STORAGE 15.3.1 Nonconforming materials, parts and components shall be tagged with a "Q" Tag, or otherwise identified, to prevent inadvertent use; and when possible and practicable, segregated storage shall be provided. Use of the "Q" Tag is described in the procedure for material receiving and inspection (QCP 1004.06).

15.4 DOCUMENTATION 15.4.1 Reports of nonconformances and documentary evidence of their proper resolution shall be maintained in the Quality Control files. The Quality Control Engineer shall issue a monthly report to the Plant Superintendent listing all open nonconformance reports.

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( 16. CORRECTIVE ACTION 16.1 SCOPE 16.1.1 A corrective action system shall be established to assure that condi-tions adverse to quality are promptly identified and corrected. The corrective action system shall provide for determination that the specified corrective measures have been implemented and an assessment of the effectiveness of the corrective measures.

16.2 GENERAL 16.2.1 When deviations, deficiencies, malfunctions or other abnormal occur-rences or conditions are encountered, they shall be reported to respon-sible oathorities for review and disposition in accordance with Section 15 of the Program.

16.2.2 Cognizant supervisors shall review discrepancies discovered during the course of station operations, determine their cause, and take necessary corrective action to prevent their recurrence.

l 16.2.3 The cogni: ant plant supervisor shall propose corrective action to the Plant Superintendent. The Plant Superintendent reviews the nonconfor-mance and approves corrective action. Corrective action shall be prompt and shall prevent recurrence of the nonconformance. If the condition is of "significant consequence," the Plant Superintendent shall request that the Assistant Director of Power Production evaluate *3 the nonconformance for final disposition.

16.2.4 Khen vendors furnish products or services that do not conform to the requirements of the applicable purchase contract, the AP6L Quality Assurance Organization shall conduct a reappraisal of the vendor's quality assurance system when appropriate. Special emphasis shall be directed to those system elements that could contribute directly to produce deficiencies. Results of the reappraisal, together with a request for specific corrective actions, shall be transmitted to the supplier. If the vendor does not improve his quality assurance system and products as requested, the Manager of Quality Assurance may remove the vendor from the Qualified Vendor List (QVL). *3 16.3 SIGNIFICANT NONCONFORMANCES 16.3.1 The following actions shall be taken for reportable occurrences: *

1) The NRC shall be notified and/or a report submitted pursuant to

Technical Specification requirements. *

3

2) Each reportable occurrence requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months netification to the

NRC shall be reviewed by the Plant Safety Committee and submitted

to the Safety Review Committee, Assistant Director of Power Produc

b tion and the Manager, Licensing by the Plant Superintendent.

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16.3.1.1 Nonconformances of "significant consequence" include those noted below:

1) Conditions that have directly affected the safety of the Plant or personnel.

2) Conditions that have caused the uncontrolled release of radio-active contaminants (liquid, solid, gaseous or air particulate).

3) Conditions where a number of nonconformances indicate a trend which could lead to unsafe plant operation.

4) Any condition the ~ Superintendent considers to be of major con-sequence.

Conditions adverse to quality othei chan violations of Technical Specifications shall be documented as required by the procedure for nonconformance and corrective action (1004.13).

16.3.2 Verification by surveillance or audit of the effective implementation of corrective action shall be documented by Quality Assurance 1 personnel, where appropriate. *4 l

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g 17. QUALITY ASSURANCE RECORDS 17.1 SCOPE 17.1.1 Quality-related documentation covering design, construction, procure-ment, fabrication, inspection, maintenance, nonconformance and correc-tive action, test and audit activities shall be filed and safely stored to provide a written evidentiary record of quality-related activities.

17.1.2 Documents made part of quality assurance records shall include oper-ating logs, results of reviews, inspections, tests, audits, materials analyses,' qualifications of personnel, procedures, drawings, specifi-cations, correspondence and related records pertinent to quality as defined in the procedure for records management.

17.2 RESPONSIBILITY 17.2.1 The Nuclear Plant Administrator shall be responsible for the establish *3 ment, implementation and maintenance of the records management program to be used throughout the operational life of the plant.

17.2.2 The Nuclear Plant Administrator, under the technical guidance and *3 review of the Quality Control Engineer, shall be responsible for ensuring that documentation retention requirements comply with 9 applicable codes and regulations.

l 17.2.3 Quality Assurance personnel shall periodically audit quality assurance *4 records and records filirg and storage procedures to assure that the records management program is being properly implemented.

17.3 DOCUMENTATION RETENTION 17.3.1 Lifetime Quality Assurance Records l

17.3.1.1 Lifetime records are defined as those which meet one or more of the following criteria (QCP 1004.25). *2

1) Those which would be of significant value in demonstrating capability for safe operation. ~

2) Those which would be of significant value in maintaining, reworking, repairing, replacing, or modifying the item.

3) Those which would be of significant value ir determining the cause of an accident or malfunction of an item.

4) These which provide required baseline data for in-service inspection.

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< )17.3.1.2 Lifetime quality assurance records shall be maintained for the life

- U of the particular item while it is installed in the plant or stored for future use, as prescribed in the procedure for document roten-tion and disposition (QCP 1004.25). *2 17.3.2 Non-permanent Quality Assurance Records 17.3.2.1 Non-permanent records are defined as those which meet all of the fo* lowing criteria:

1) Those of no significant value in demonstrating capability for safe operation.

2) Those of no significant value in maintaining, reworking, repair-ing, replacing, or modifying the item.

3) Those of no significant value in determining the cause of an accident or malfunction of an item.

4) Those which do not provide baseline data for in-service inspection.

17.3.2.2 Non-permanent records shall provide evidence that an activity was performed in accordance with applicable requirements, and shall be retained for specified periods as directed by the procedure for document retention and disposition (QCP 1004.25). *2 17.3.3 Categories of records to be maintained and their appropriate retention l periods are described in the procedure for document retention and disposition (QCP 1004.25). *2 17.3.4 The Quality Control Engineer shall be responsible for receiving, inspecting and authenticating such documents as directed by the procedure for turnover of quality assurance documents from construc-tion to APGL (QCP 1004.04).

17.3.5 When approved for receipt by the Quality Control Engineer, such records shall be transmitted to the Nuclear Plant Administrator *3 for filing and storage.

17.4 PRODUCTION DEPARTMENT l

17.4.1 Productien Department personnel, other than Plant Staff, that perform *4 work on the plant in the areas of design, pracurement, maintenance, modification, testing, Quality Assurance and special nuclear materials *4 shall document such work and forward the records to the Nuclear Plant *3 Administrator.

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QUALITY ASSURANCE MANUAL TITLE: QUALITY ASSURANCE RECORDS I

9/8/77 PAGE 2 of 4 17

17.5 STORAGE g~

)17.5.1 Permanent records shall be stored in the records vault and shall be: n

1) Adequately protected from earthquake, flood and similar hazardous natural phenomena.

2) Made safe and secure from theft, vandalism and unauthori:ed use.

3) Adequately protected against environmental deterioration.

4) Adequately protected against fire.

17.5.1.1 The following features or suitable altematives shall be incorporated in the desip of the storage facility:

1) Reinforced concrete, concrete block, masonry, or equal construc-tion.

2) Concrete floor and roof with sufficient slope for drainage; if a floor drain is provided, a non-return check valve (or equal) shall be included.

3) Fire retardant door (two-hour Underwriters' rating minimum). I

4) Sealant applied over walls as a moisture or condensation

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5) Surface sealant on floor providing a hard-wear surface to minimize concrete dusting. 3 l

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6) Foundation sealant and provision for drainage.

7) Forced-air circulation with filter system.

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8) Dry chemical or gas fire protection system. I

9) No pipe other than those providing fire protection to the storage facility is to be located within the facility.

17.5.1.2 For storage of film and other special processed records, humidity l and temperature controls shall be provided to maintain an environ- l ment as recommended by the manufacturer.

17.5.1.3 A list shall be prepared designating those personnel who shall have access to the files.

17.5.2 Plant storage systems shall provide for the accurate retrieval of information without undue delay and shall be sufficient to control *4 and account for records removed from the storage facility. ,

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QUALITY ASSURANCE MANUAL 9 4

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\- 17.6.1 Indexing methods and systems for quality-related records are deline-ated in the procedure for plant records r anagement (QCP 1004.24) *2 17.6.2 Records submitted for filing in either lifetime or temporary files shall be subject to the following requirements for receipt control:

1) Establishment of a records check list designating the required quality-related records.

2) Establishment of a system designating criteria for document inspection to assure that records are accurately completed, legible, and received in good condition.

3) A file system to indicate which quality-related documents have been received.

17.6.2.1 Implementation and enforcenent of receipt control requirements shall be the responsibility of the Nuclear Plant Administrator. *3 17.7 FINAL DISPOSITION 17.7.1 Final disposit on of quality-related records is controlled by the ,

procedure for d..:ument retention and disposition (QCP 1004.2S) which *2 requires that the Nuclear Plant Administrator periodically purge the *3

't j non-permanent files of records retained past their authorized V retention date.

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18. AUDITS i l l 18.1 SCOPE 18.1.1 Audits shall be performed to determine the compliance with, and effectiveness of, applicable quality assurance programs. The audits shall be performed on a planned and periodic basis in accordance with the audit schedule. Supplementary audits shall be performed as required.

18.2 GENERAL 18.2.1 Reviews and audits of records, station operation, design activities, procurement, construction, maintenance, modification, examination *1 for conformance to the eighteen criteria of 10 CFR 50, Appendix B, *410.14 and other quality-related activities shall be performed by the Qua-lity Assurance Organization to assess the adequacy of the Quality Assurance Program and to verify compliance with established quality program requirements. These activities are performed using the Qua-lity Assurance Procedures for audits (ANO-14, ANO-17; ANO-18, ANO-20) . *3 18.2.2 Results of these reviews and audits shall be recorded, reported, and distributed to responsible management as outlined in the Subsection 18.6.

18.2.3 The hbnager of Quality Assurance shall perform scheduled audits of

{ ) vendors and service contractors as required to verify and evaluate t

their gaality assurance programs, procedures, and activities, and to assure that suppliers are effectively complying with all aspects of the Quality Assurance Program and procurement requirements. The Manager of Quality Assurance also verifies that vendors and contract-ors review and audit the quality assurance programs of their suppli-ers. This activity is referenced in the procedures for vendor audits *3 (ANO-3, ANO-6, ANO-19). *3 18.3 IN-PLANT REVIEW AND SURVEILLANCE 18.3.1 In addition to Quality Assurance audits, an in-plant program for re-view and surveillance of quality-related activities shall be conduct-ed by the Quality Control Engineer.

18.3.2 The program shall include:

1) Document and record review.

2) Surveillance and evaluation of compliance with established pro-cedures, instructions, methods, and other requirements.

3) Investigation of nonconformance and other unusual events.

l I DATE QUALITY ASSURANCE MANUAL REV. 3 97gj TITLE: AUDITS PAGE 1 of 3 SECTION 1R

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7 { } 4) Verification of required corrective action implementation.

18.3.3 The Quality Control Engineer shall submit reports to the Plant Superintendent. If the Plant Superintendent feels further action is required he may refer the deficiency to the Assistant Director of *3 Power Production.

18.4 AUDIT PERSONNEL 18.4.1 The Quality Assurance Section, ine.luding the Quality Assurance Engi-neer (Operations), shall be assigned auditing responsibilities based on experience or training which establish that their qualifications are commensurate with the complexity or special nature of the activities to be audited. When audit assignments are specified, considerations are given to special abilities, specialized technical training, prior pertinent expertise, personal characteristics, education and physical capability. l 1

18.4.2 Audit personnel are provided appropriate training to assure their l l

competence for performing the required audits. Proficiency of audit I personnel is maintained by one or more of the following methods:

1) Regular, active participation in the audit process.

2) Review and study of codes, standards, procedures, and instruc-l l tions. 1

3) Participation in training or orientation programs. ,

1 18.5 DOCUMENTATION l 1

18.5.1 Audit Reports I i

18.5.1.1 Upon completion of any audit, a signed written report shall be pre-pared which includes at least the following items. 1 l

1) Description of audit scope and date. 1

2) Identification of the auditor (s). I i

3) A summary of audit results.

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4) Details of nonconformances or programraatic deficiencies. I j

5) Recommendations for correcting nonconformances or improving .

the Quality Assurance Program as appropriate. '

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FJF DATE gf QUALITY ASSURANCE MANUAL REV. 3 9/8/76 9 TITLE: AUDITS SECTION PAGE 2 of 3 8

'y[ '318.5.1.2 The findings of audits shall be reported to the Manager of Quality 4 N ,,/ Assurance, the Manager of the area concerned and to the Senior Vice President, Production, Transmission and Engineering if officer level action is required. When audits are conducted within organizations other than AP6L, written responses are required to *3 describe measures taken to correct deficiencies and prevent recurrence. For audits conducted within AP6L, written responses *4 may be required depending upon the nature of findings. When a written response is requested, the audited organization is respon- *4 sible for providing the written response in a timely manner.

Appropriate follow-up including re-audits is made to determine that nonconformances are effectively corrected and that the corrective action precludes repetitive occurrences. Follow-up action for each *4 finding is required.

18.5.2 Records 18.5.2.1 The following records shall be maintained to represent the status of the plant's activities in complying with all aspects of the Quality Assurance Program:

1) Audit reports.

2) Reports from affected organizations indicating completion and effectiveness of action taken to correct deficiencies.

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(_,) 3) Reports of re-audit activities.

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DATE REV. 4

QUALITY ASSURANCE MANUAL 9/8/77 TITLE: AUDITS PAGE 3 of 1 SECTION

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7 RESPONSES TO NRC QUESTIONS

( s '1y Listed below are NRC questions that have been responded to by Revision to APL-TOP-1, Quality Assurance Manual for Operations.

Question Page Section Revision 410.1 Policy Statement 1 410.2 1 1.2 1 410.3 1 Foreword - Policy Statement 1 410.4 1 Fore'.mrd - Policy Statement 1 410.5 13 1.6.1.4 1 410.6 2 1.4.1.1 410.7 Policy Statement 1 410.8 9 Table 2-2 1 1 11.2 1 3 11.5 1 410.9 Foreword - Policy Statement 1 410.10 20 1.7 1 410.11 1 4.2.3 1 410.12 1 7.3.2 1 410.13 3 4.5.3 1 410.14 1 18.2.1 1 410.15 1 5.2.1 1

( 410.16 1 6.2.5 1 410.17 2 7.5 1 410.18 1 8.2.5 1 410.19 1 10.1.2 1 410.20 1 12.2.6 1 410.21 1 12.2.5 1 410.22 1 14.2.1 1 410.23 1 15.2.3 1 410.24 1 Foreword 2 410.25 1 Foreword - Policy Statement 2 t_ >

l QUALITY ASSURANCE MANUAL REV. 2 l t TITLE: RESPONSES TO NRC QUESTIONS 3fffh5 3gg71g3 PAGE 1 of 1 19 L_

ML19326B553

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