ML19326B507

QA Manual for Operations

ML19326B507
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/27/1974
From:	ARKANSAS POWER & LIGHT CO.
To:
References
APL-TOP-1, NUDOCS 8004160304
Download: ML19326B507 (89)

Text

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M,Zi TABLE OF C0hTENTS

• A ARKANSAS POWER S ~IGifT COMPANY Section Subject Tab Page POLICY STATEMENT FOREWORD TERMS AND DEFINITIONS RECORD OF REVISIONS 1.

ORGANIZATION 1

1.1 SCOPE 1

1.2 ARKANSAS POWER 6 LIGHT COMPANY I

1.3 ADMINI5TRATIVE SERVICES 1

1.3.1

!!ANAGER OF SAFETY 1

1.3.2 SUPERVISOR OF PURCilASING 1

1.4 PRODUCTION DEPAR'DIENT 2

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1.4.1 QUALITY ASSURANCE ORGANIZATION 2

1.4.2 NUCLEAR SERVICES ORGANIZATION 6

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1.4.3 OPERATION AND MAIhTENANCE COORDINATOR 8

1.4.4 CllIEF CHEMIST 9

1.4.5

!!ANAGER, DESIGN AND CONSTRUCTION 9

1.4.6 ASSISTANT CHIEF ENGINEER 9

1.5 ARKANSAS NUCLEAR ONE ORGANIZATION 10 1.5.1 ADf!INISTRATIVE 10 1.5.2 NUCLEAR 10 1.5.3 QUALITY CONTROL 11 1.5.4 OPERATIONS GROUP 11 1.5.5

!!AIhTENANCE GROUP 11 1.5.6 TEClfNICAL SUPPORT GROUP 12 1.6 QUALITY PROGRAM C0bHITTEES 12 1.6.1 QUALITY ASSUR.%CE C0tNITTEE 12 1.6.2 SAFETY REVIEW C0hBIITTEE 13 1.6.3 PLANT SAFETY C0hBIITTEE 17 1.6.4 ENV'.RONMENTAL RESPONSIBILITIES 19 1.7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES 20 2.

QUALITY ASSURANCE PROGRAM 2

i 2.1 SCOPE 1

2.2 PURPOSE 1

2.3 APPLICABILITY 1

2.4 PROCEDURES 2

DATE 7'

REV. O

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QUALITY ASSURANCE MANUAL 6/11/74 TITLE: TABLE OF CONTENTS A

0F PAGE 1 of 5 CONTENTS o

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Section Subj ect Tab Page 2.

QUALITY ASSURANCE PROGRAM (CONTINUED) 2 2.5 PROGRAM REVISION AND CONTROL 3

2.6 SYSTEM STRUCTURE AND COMP 0NEhT 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 DESICN PROCESS / VERIFICATION 1

3.4 DESIGN RECORDS 3

4 PROCUREMENT DOCINENT CONTROL 4

4.1 SCOPE 1

4.2 GENERAL 1

4.3 REQUISITIONS 2

4.4 SPECIFICATIONS 2

4.5 PURCHASE ORDERS 2

5.

INSTRUCTIONS, PROCEDURES AND DRAWINGS 5

5.1 SCOPE 1

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g 5.2 GENERAL 1

5.3 TEMPORARY CHANGES 1

5.4 E!!ERGENCIES 2

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 DOCUMENT IDEhTIFICATION 2

6.4 STORAGE AND FILING REQUIREMEhTS 2

7.

CONTROL OF PURCHASED MATERIAL, EQUIPMENT 7

a u scavn.e3 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

m DATE V-0 6/11/74 QUALITY ASSURANCE !!ANUAL TITLE: TABLE OF-C0hTENTS PAGE 2 of 5

TABLE OF COSTENTS

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Section Subject Tab Page (J

8.

IDENTIFICATION AND CONTROL OF MATERIALS.

8 PARTS AND COMPONENTS 8.1 SCOPE 1

8.2 IDENTIFICATION AND MARKING 1

8.3 TAGGING 1

8.4 DOCUMENTATION 2

8.S DEFECTIVE OR INCORRECT ITEMS 2

9.

CONTROL OF SPECIAL PROCESSES 9

9.1 SCOPE 1

9.2 RESPONSIBILITY 1

9.3 GENERAL 1

9.4 QUALIFICATION 2

10.

INSPECTIOff 10 10.1 SCOPE 1

10.2 RESPONSIBILITY l

10.3 INSPECTION PROCEDURES 2

10.4 INSPECTOR QUALIFICATION 2

10.S DOCUMENTATION 3

11.

TEST CONTROL 11

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%d 11.1 SCOPE 1

11.2 GENERAL 1

11.3 PROCEDURE APPROVAL 2

11.4 DOCUME.VTATION AND REVIEW OF TEST RESULTS 2

12.

CONTROL AND MEASUREMENT OF TEST EOUIPMENT 12 12.1 SCOPE 1

12.2 GENERAL 1

12.3 RESPONSIBILITIES 1

12.4 EQUIPMENT IDENTIFICATION 2

12.S DOCUMENTATION 2

13.

IIANDLING. STORAGE AND SHIPPING 13 13.1 SCOPE 1

13.2 SPECIAL REQUIREMENTS 1

13.3 RECEIVING INSPECTION 1

13.4 STORAGE AND PRESERVATION 1

13.5 RADIOACTIVE MATERIALS 2

13.6 RECORDS 2

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DATE REV.

QUALITY ASSURANCE MANUAL 0

6/11/74 p

TITLE: TABLE OF CONTENTS TABLE OF PAGE 3 of S CONTENTS)

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.

NONCONFORMING 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

17.4 PRODUCTION DEPARTMENT 2

17.5 STORAGE 3

17.6 RECORDS INDEXING AND RECEIPT CONTROL 4

17.7 FINAL DISPOSITION 4

18.

AUDITS 18 l

18.1 SCOPE 1

18.2 GENERAL 1

l 18.3 IN-PLANT REVIEW AND SURVEILIANCE 1

18.4 AUDIT PERSONNEL 2

1 18.5 DOCUMENTATION 2

19.

RESPONSE TO NRC QUESTIONS 19 1

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QUALITY ASSURANCE MANUAL REV.

2 3/4 TITLE: TABLE OF CONTENTS TABLE OF l

PAGE 4 of 5 CONTENTS l

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FIGURES AND TABLES xv Figures Number Title Tab 1-1 Arkansas Power 6 Light Company 1

Corporate Organization 1-2 Arkansa. Power 6 Light Company 1

Administrative Services - Purchasing 1-3 Arkansas Power G Light Company 1

Production, Transmission and Engineering 1-4 Arkansas Power 6 Light Company 1

ANO Organization Tables Number Title Tab Page 2-1 Quality Assurance Procedures 2

6 2-2 Plant Quality Procedures 2

8 2-3 Nuclear Services Procedures 2

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I REV. 0 QUALITY ASSURANCE MANUAL 6/11/74 i'/

TABLE OF l

TITLE: TABLE OF CONTENTS PAGE 5 of 5 CONTENTS l

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O)

ARKANSAS POWER 4 LIGHT COMPANY POLICY STATEMENT

.tV QUALITY ASSURANCE PROGRAM FOR OPERATION It is the policy of the Arkansas Power 6 Light Company (AP6L), from the high-

• 1 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 AP6L 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 AP6L. The Plant Superintendent and the Plant Quality Control Engineer are responsible for the daily implementation of the Program's procedural require-ments at the plant. The Manager of Nuclear Services is responsible for the procedural implementation of the program within the Production Department.

The Manager of Quality Assurance shall be responsible for establishing the Program. The Quality Assurance Committee shall be responsible for review

• 1 and approval of the program established by the Manager of Quality Assurance.

410.1 Cg'hThe Quality Assurance Engineers reporting to the Manager of Quality Assurance shall be responsible for auditing the Program as necessary. and monitoring all activities required by the Program to assu e compliance with its require-ments. The Plant Quality Control Engineer shall have the authority and organi:stional freedom necessary to meet the requirements of 10 CFR 50, Appendix 3.

The Quality Assurance Committee shall periodically require the Manager of Quality Assurance to review the adequacy and overall effectiveness of the Program. Any defects in the implementation of either this policy or the Pro-gram that are revealed during the review, and that require corporate action for correction, will be reported to me together with appropriate recommenda-tions.

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 quality in his own work, and for compliance with the requirements of the Program. 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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1-FM J. D. Phillips

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5enior Vice President

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Production, Transmission 6 Engineering Dated:

3/4/75

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FOREWORD 4

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V 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 quality 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 practices. To meet this objective, a Quality Assurance Program for Operation applicable 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 made 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 cnd 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 assurance emanates from each individual contributor, and that management is responsible for creating an awareness of quality and reliability.

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

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 and/or the Quality Assurance Committee to implement additional or changed requirements.

The Quality Program 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 3/4/75 TITLE: FOREWORD L

PAGE 1 of 1 FOREWORD

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TERl!S AND DEFINITIONS Approval - An act of endorsing or adding msitive authorization, or both.

Approved Bidders List - A listing of approved vendors considered acceptable to APSL 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 detemin through investigation, the adequacy of, and adherence to, established proudures, instructions, specifications, codes, and standards or other applicable contractual and licensing requirements, and the effectiveness of implementation.

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

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Certificate of Conformance - A written statement, signed by a qualified party, certifying that items or services comp Ay with specific requirements.

Certificate of Compliance - A written statement, signed by a qualified party, attesting that the items or services are in accordance with specified require-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 specified quality requirements. Quality characteristics are generally iden-tified in specifications and drawings which describe the item, process, or service.

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

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REV. O 6/11/74 07 QUALITY ASSURANCE MANUAL I

TITLE: TER!!S AND DEFINITIONS PAGE 1 of 6 TERMS

Cleanness - A state of being clean in accordance with predetermined standards, and usually implie. ireedom 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 assembly.

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 organi::ation under contract for furnishing items or services.

It includes the Nrms Vendor, Supplier, Subcontractor, Fabricator and sub-tier levels of the s where appropriate.

Defective Material - A material or compon tnt which has one or more character-istics that do not comply with specified L quirements.

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

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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 measurement.

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" denotes a mandatory requirement.

Handling - 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.

DATE 4: f--

REV. 0 6/1'* / 74 w:8 QUALITY ASSURANCE MANUAL TITLE: TERMS AND DEFINIUONS PaGE 2 of 6 TERIS

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

Inspector (0wner'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 detemines 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.

Master 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.

Material - A substa-ce er combination of substances forming components, parts, pieces, and equipment items.

(Intended to include such as machinery, castings, d

i liquids, fomed steel shapes, aggregates, and cement.)

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

Nonconformance - A deficiency in characteristic, documentation, or procedure which renders the quality of an item unacceptable or indeterminate. 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 power 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, m

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QUALITY ASSURANCE MANUAL 6/11/74 TITLE: TERMS AND DEFINITIONS PAGE 3 of 6 TERMS

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.

P ncurement D)cuments - 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 compliance to the inquiry and the cost.

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

' Purchaser - The organization or organizations responsible for 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 rs.dioactivity, or those essential for the safe shutdown and immediate and long-term operation following a Loss of Coolant Accident.

Qualification (Personnel) - he characteristics or abilities gained through training or experience or both that enable an individual to perfom a required function.

Qualified Party - A person or organization competent and recognized as knowledge-able to perform certain functions.

Qualified Procedure - A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose.

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E[P REV. 0 6/11/7.1 QUALITY ASSURANCE MANUAL TITLE: TERMS AND DEFINITIONS PAGE 4 of 6 TERMS

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

Quality Control - Rose quality assurance actions which provide a means to 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 - De process of restoring a nonconfoming characteristic to a condition such that the capability of an item to function reliably and safely is unim-paired, even though that item still may not confom to the original requirement.

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

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

Source Surveillance -

review, observation, or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture.

Specification - A concise statement of a set of requirements to be satisfied by a product, a material or process indicating, whenever appropriate, the procedure e

by means of which it may be detemined whether the requirements given are satis fied.

Standard - The result of a particular standardization effort approved by a i

recognized authority.

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

Testi.

- The detemination or verification of the capability of an item to meet specit.ed requirements by subjecting the item to a set of physical, chemical, environmental or operating conditions.

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REV. 0 EI QUALITY ASSURANCE FfANUAL 6/11/74 TITLE: TER>lS AND DEFINITIONS PAGE S of 6 TERl!S

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Transit

'Ihe state of being conveyed or transported from one place to another.

Transit Carrier (0 pen) - Trucks, trailers, railroad cars, barges, aircraft or ships which do not afford items protection from the environment.

Transit Carrier (Closed) - Trucks, trailers, railroad cars, barges, aircraft cr ships 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 i'c 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.

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

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

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

O 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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QUALITY ASSURANCE MANUAL 6/11/74 TITLE: TERMS AND DEFINITIONS PAGE 6 of 6 TEPJtS

RECORD OF REVISIONS A

NUMBER DESCRIPTION DATE O

Initial Issue 6/11/74 1

Response to AEC Questions Submitted 12/13/74 11/21/74. Revisions to Sections 2, 4, and 7 as indicated.

2 wsponse to NRC Questions Submitted 3/4/7S

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Procedure Numbers 1005.xx i to 1004.xx (Number Change Only)

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2 3/4/75 TITLE: RECORD OF REVISION RECORD OF' PAGE 1 of 1 REVISIONS.

1.

ORGANIZATION g

g 1.1 SCOPE l

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 AP&L Nuclear Plants.

1.2 ARKAUSAS POWER & LIGHT COMPANY (AP&L)

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

The ultimate responsibility for all power production facilities within AP&L, including Quality Assurance, lies with the Senior Vice President, Production, Transmission and Engineering. He provides management assessment of the Qua-

• 1 lity cogram through review of minutes of Quality Assurance Committee meet-

• h10.2 in6s, quality reports and reports of AEC activities. Functioning under the Senior Vice President, Production, Transmission and Engineering and providing line control over power plant operation is the General Office-Production De-partment headed by the Director of Power Production.

The Senior Vice President, Administrative Services, shall be responsible for the purchasing functions affecting Plant operation as described in Subsection 1.3.2.

1.3 ADMINISTRATIVE SERVICES The Administrative Services Organization (Figure 1-2), prerides purchasing ser-vices and overall personnel safety control requirements l'. support of the oper-ation of AP&L Nuclear Plants. The duties of individuals performing key functions related to the quality of 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 re-sponsible 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 h) Is responsible for AP&L implementation of OSHA requirements

5) Inspects AP&L facilities for compliance with the Corporate Safety Manual.

1 3.2 Supervisor of Purchasing The Supervisor of Purchasing reports to the Manager, Purchasing and Stores, l

and shall be_ responsible for the following quality-related duties and activities:

DATE QUALITY ASSURANCE MANUAL REV. 1 12/13/Th TITLE: ORGANIZATION PAGE 1 of 20 SE ION

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1) Prepares purchase orders based upon receipt of reviewed and approved purchase requisitions.

2) Performs the commercial interface functions between AP6L aed contractors or vendors.

3) Assures that quality documen;ation 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 AP6L Nuclear Pl ants.

These activities include design, procurement, modificatien, maintenance, and operation. Within the Power Production Department, implementation and coordina-tion of the Quality Assurance Program shall be accomplished by the Manager of Quality Assurance under the technical direction of the Quality Assurance Committee.

1.4.1 Quality Assurance Organization (QAO)

The AP6L Quality Assurance Orgard :ation as shown in Figure 1-3 is under the direction of the Manager of Quality Assurance, who reports administrative 1y to the Director of Power Production.

The Quality Assurance Organization performs review, surveillance, inspection and audit functicns during design, construction and operational phases of AP6L's Nuclear Plants.

The duties and responsibilities of the Quality Assurance Organization during the design and construction phases are described in the AP6L Quality Asst: ance Manual for Design and Construction. QA0 auties and responsibil-ities in support of the operational phase are described below. The Quality Assurance Organization is independent of existing design, construction, and operation organizations, and reports directly to the Director of Power Production on administrative matters, and receives technical direction from the Quality Assurance Committee.

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 Organization.

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QUALITY ASSURANCE MANUAL 6/11/74 SECTION TITLE: ORGANIZATION PAGE 2 of 20 1

The Manager of Quality Assmance acts as Chairman of the Quality Assurance

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I Committee and is responsible for developing Quality Assurance Program re-quirements for design, procurement, manufacture, construction, mcdification, operation, and maintenance related to the Q-Listed systems, structures, and components in AP&L Nuclear Plants. The Manager of Quality Assurance shall be responsible for the audit of all quality assurance activities conducted with-in the AP&L organization and for the review, approval and verification of the quelity assurance requirements placed upon contractors or vendors that pro-vide equipment, material, or services for AP&L Nuclear Plants. The Manager of Quality Assurance has the authority to stop work where conditions exist that prohibit effective quality control inspections, or if faulty materials, incor-rect workmanship or procedures are detected. He is also responsible for the

• 1 control and distribution of QA Manuals and QA Manual Revisions.

• h10.6 For plant operations the stop work authority is directed through the Plant Superintendent.

1.4.1.2 Quality Assurance Engineers The Quality Assurance Engineers report to the Manager of Quality Assurance.

They verify by audit the effetive implementation of the Quality Assurance Program for Operations. The Quality Assurance Engineers are thoroughly know-ledgeable of the Quality Assurance Program and associated procedures, Safety Analysis Reports, and 10 CFR 50, Appendix B.

They are fmniliar with the re-gulatorf guides, codes, and standards that address quality assurance. They confer with the-Manager of Quality Assurance in regard to technical issues, periodic audits, reviews, noncenformances, corrective actions and external l

l relations including inplant contractor and vendor representatives. The Qua-lit; Assurance Engineers shall possess the following qualifications:

1) Be a graduate of a four-year accredited engineering or science school or equivalent with two years of experience in quality assurance, including testing or inspection of equivalent manufa turing, construction sad in-stallation 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 Assurance requirements of a nucleSr facility, or

2) Be a high school graduate with at least five years experience in general 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 ot.a 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 provide effective leadership.

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TITLE: ORGANIZATION 0 Cf 0 PAGE 3 of 20

9 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 1

job through previous performance or satisfactory completion of proficiency testing.

1.4.1.2.1 Tc assure adequate control of plant operational activities a Quality Assurance Engineer (Operations) position has been designated.

He possesses the necessary functional independence and authority to investigate, identify and effect solutions to quality problems.

Specifically:

1) The Quality Assurance Engineer (Operations) shall have the authority to audit or review records, files, instructions, directives or documents concerned with plant operation.

2) The Quality Assurance Engineer (Operations) shell have the authority to enter all areas of the Plant for inspection, sur-veillance or audi;t purposes consistent with plant established procedures.

3) He Quality Assurance Engineer (Operations) shall not perform any activity concerned with operations except in the areas of review or audit. He shall have no in-line productior, respon-sibilities.

(7 a) The signcture of the Quality Assurance Engineer (Operations)

(,

shall not appear on any document which directs, authorizes or in any way implements an operational a. tivity. This provision does not preclude review signatures on procedures, design or procurement documents or verification sig stures on inspection, surveillance or audit documentation.

S) He Quality Assurance Engineer (Operations) shall document his audit and surveillance efforts and report his findings to the Plant Superintendent and to the Manager of Quality Assurance, at the frequency directed by the audit or surveillance plan.

%e Quality Assurance Engineer (Operations) interfaces with onsite QuJity Control personnel by routinely conferring with the Quality Control Engineer to evaluate plant procedures and practices regarding quality assurance.

1.4.1.2.2 To provide adequate control of engineering activities performed within the Production Department, a Quality Assurance Engineer (Engineering) position has been designated. He possesses the necessary functional independence and authority to investigate, identify and effect solutions to quality problems. Specifically:

1) The Quality Assurance Engineer (Engineering) shall have the authority to audit or review records, files, instructions,

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6,11/74 QUALITY ASSURANCE MANUAL TITLE: ORGANIZATION PAGE 4 of 20

i directives or documents concerned with the design and pro-curement activitie" performed by the Production Department.

2) The Quality Assurance Engineer (Engineering) is responsible for the audit of Prc. duction Department originated documents (e.g.,

purchase requisitions, specifications and drawings) used in activities that affect the quality of Q-listed systems, struc-tures and components.

3) The Quality Assurance Engineer (Engineering) shall verify review of architect-engineer or NSSS manufacturer orginated specifications and purchase orders for the inclusion of quality assurance requirements.

4) The Quality Assurance Engineer (Engineering) shall not perform any activity concerned with design or procurement except in the areas of review or audit. He shall have no in-line production responsibilities.

5)

"he signature of the Quality Assurance Engineer (Engineering) shall not appear on any document which directs, authorizes or in any way implements design or procurement activity. This provision does not preclude review signatures oa procedures, design or procurement documents or verifistion signatures on inspection, surveillance or audit documentation.

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6) The Quality Assurance Engineer (Engineering) shall document his V

audit and surveillance efforts and report his findings to the Manager cf Nucleat Services and to the Manager of Quality Assurance at the frequency directed by the audit or surveillance plan.

1.4.1.2.3 To assure that the AP6L audit program is effectively implemented by the Quality Assurance Organization, a Quality Assurance Engineer (Audits) position has been designated. His audit responsibilities are as follows:

1) The Quality Assurance Engineer (Audits) shall coerdinate within the Quality Assurance Organization, the planning, scheduling and perfomance of APSL internal audits of construction, engin. 3 ring and operations.

2) The Quality Assurance Engineet (Audits) shall conduct audits of the NSSS manufacture and architect-engineer organizations and principal vendors.

3) The Quality Assurance Engineer (Audits) shall perform special audits that include witnessing architect-engineer audits, observation of AEC audits, performance of investigative audits and surveillance audits.

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QUALITY ASSURANCE !!ANUAL SECTION u

TITLE: ORGANIZATION PAGE 5 of 20 f

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4) ne Quality Assurance Engineer (Audits) shall perform vendor shop inspections related to the procurament of spare parts for the operating nuclear plants.

5) The Quality Assurance Engineer (Audits) shall document his audit and surveillance efforts and report his findings to the Manager of Quality Assurance at the frequency directed by the audit or surveillance plan.

1.4.1.3 Ouality Assurance Inspectors The Quality Assurance Inspectors report to the Manager of Quality Assurance and assist him bf performing audits and inspections as required to assure proper application of the Quality Assurance Program. Quality Assurance Inspectors are assigned specific responsibility by discipline and are required to have specialized training and at least three years experience (or equivalent education) in this area of responsibility.

1.4.2 Nuclear Services Organization The Nuclear Services Organization is headed by the Manager of Nuclear Services, who reports to the Director of Power Production. He Manager of Nuclear Services shall be responsible for all activities performed by APSL in support of the operr. tion of APSL Nuclear Plants.

In executing this responsibility he directs a staff of supervisors including the ANO Plant Superintendent.

1.4.2.1 ANO Plant Superintendent g

The Plant Superintendent reports directly to the Manager of Nuclear Services and shall be responsible for assuring 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 alsa be respon-sible for the overall direction and administration of the training, safety and onsite quality programs.

The Plant Superintendent has the authority to make repairs on any plant system, component or structure and to make design changes and modifications to those items which are not Q-List items. He has the authority to make changes in the plant staff, to shut the plant down if required, and has final approval of all plant procedures.

1.4.2.2 Fuel Management Supervisor The Fuel Management Supervisor reports to the Manager of Nuclear Services and shall be responsible for all AP6L activities affecting utilization of nuclear fuel within AP6L Nuclear Plants. His duties include the following:

1)

Providas technical direction and ridministrative guidance to er.gineers and technicians as assigned.

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DATE sk QUALITY ASSURANCE MANUAL 6/11/74 TITLE: ORGANIZATION PAGE 6 of 20 SECTION

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2) Ensures confomance to the quality-related procedures and instructions which apply to design, engineering, procurement and utili::ation of nuclear fuel by APSL and its Prime Contractors and vendors.

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

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

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

6) Reconcends "stop work" for cause for the engineering, design and fabri-cation of nuclear fuel to the Manager of Nuclear Services.

7) Coordinates fuel perfomance analyses with Middle South Services.

8) Maintains accountability for all nucicar fuel within the possession of APSL.

9)

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

10) Establishes reload fuel enrichment requirements and core configurations,

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

q 1.4.2.3 Licensing Supervisor

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'Ihe Licensing Supervisor reports to the Manager of Nuclear Services and shall be responsible for all Federal, State and local licensing requirements for APSL Nuclear Plants. His duties include the following:

1) Provides technical direction and administrative guidance to engineers i

and technicians as assigned.

2)

Is designated as the lead APSL representative for the Atomic Energy Commission licensing activities.

3) Coordinates with the Production Project Supervisor all licensing inter-face activities between APSL, the NSSS supplier, and the architect-engineer for all nuclear power plant projects.

4) Reviews and recommends approval for all licensing work perfomed by APSL, the NSSS supplier, and the architect-engineer.

S) Reviews and recommends approval for all permit and licensing applications (Federal, State, and local) necessary for each nuclear power plant proj ect.

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-i QUALITY ASSURANCE MANUAL SECTION TITLE: ORGANIZATION PAGE 7 of 20

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6) Reviews the plant licensing status on a routine basis with the Manager of Nuclear Services.

7)

Reviews or initiates all applicable incoming and outgoing correspondence regarding licensing of the nuclear power plant project.

8) Coordinates all licensing hearings and meetings with the AEC regarding the Preliminary Safety Analysis Report (PSAR), Final Safety Analysis Report (FSAR), and Environmental Report (ER).

9)

Provides a critical path licensing schedule for the Manager of Nuclear Services.

10) Coordinates the environmental impact reporting requirements related to changes in nuclear plant design.

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

1.4.2.4 Production Project Supervisor The Production Project Supervisor reports to the Manager of Nuclear Services and shall be responsible for design and engineering activities related to a specific nuclear plant project. His duties include the following:

1)

Provides technical direction and administrative guidance to:

a) Assistant Production Project Supervisor - Mechanical b) Assistant Production Project Supervisor - Electrical 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 recommends approval of design, engineering and fabrication performed by APGL Prime Contractors or vendors.

4)

Reviews and recommends approvaI of procurement documents that purchase equipment, material, and services for the nuclear power plant proj ects.

S)

Recommends "stop work" for cause in the engineering and design for nuclear power plant projects.

1.4.3 Operation and Maintenance Coordinator The Operation and Maintenance Coordinator reports to the Director of Power Production and has the following quality-related duties and responsibilities:

DATE QUALITY ASSURANCE MANUAL II SE TITLE: ORGANIZATION PAGE 8 of 20

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1) Serves as a member of the Quality Assurance Committee and he Safety Review Committee.

2)

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

1.4.4 Chief Chemist The Chief Chemist reports to the Director of Power Production and has the following quality-related duties und responsibilities:

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

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

1.4.5 Manager, Design and Constniction The Manager, Design and Construction, reports to the Director af Power Produc-tion, and has the following quality-related duties and responsibilities:

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

2) Coordinates the design and construction activities for all non-nuclear power generating projects, n

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1.4.6 Assistant Chief Engineer LJ The Assistant Chief Engineer reports to the Senior Vice President, Production, Transmission and Engineering, and shall be responsible for engineering support of APGL Nuclear Plants. He is assisted by the following management personnel:

1.4.6.1 Manager of Transmission System Operations The Manager of Transmission. System Operations performs the following quality-related duties and responsil)ilities:

1)

Serves as a member of the Quality Assurance Committee.

2)

Is responsible f ar the calibration and maintenance of major switchboard relays and switchboard equipment.

3)

Is responsible for communication associated with the Industrial Security Plan and the Emergency Plan.

4)

Is responsible for the design and procurement of switchboard and substation components.

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QUALITY ASSURANCE MANUAL SECTION TITLE: ORGANIZATION PAGE 9 of 20

l 1.4.6.2 Manager of Installation and Testing

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The Manager of Installation and Testing serves as.a member of the Quality Assurance Committee as the representative of the staff of the Assistant Chief Engineer.

1.5 ARKANSAS NUCLEAR ONE ORGANIZATION All activities which affect quality shall be performed by individuals.kose scope of authority and duties are clearly established and delineated in writing.

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

1 Fcr descriptive purposes the ANO organi:ation may be divided into six groups, as follows:

1) Adninistrative

4) Operation

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

/N Section 1.4.

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1.5.1.2 The Assista.

Plant Superintendent assists the Suparintendent in all phases of plant management. He assumes all the responsibilities and authorities of the Superintendent in his absence. He is also respon-sible for coordinating the efforts of the Operation, Maintenance, Technical Support, Nuclear, and Quality Control Groups.

1.5.2 Nuclear 1.5.2.1 The Nuclear Engineer monitors and evaluates core physics and core performance for both nuclear and thermal hydraulic activities. He assists in developing fuel shuffling patterns and actively partici-pates in other phases of fuel management.

The Nuclear Engineer is authorized to conduct measurements of the core output in conjunction with the Plant Superintendent, and supervises the Reactor Technician.

1.5.2.2 The Reactor Technician monitors and evaluates the daily nuclear, thermal, and hydraulic performance of the reactor to obtain optimum fuel utili:ation. He recommends to the Nuclear Engineer the safest way of operating the reactor under all operating conditions. He is also responsible for the performance of all nuclear instrumen-tation, control and protection systems, including their testing and repair.

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y QUALITY ASSURANCE MXalAL 6/1 /74 v

TITLE: ORGANIZATION PAGE 10 of 20 1

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1.5.3 Quality Control v

1.5.3.1 The Quality Control Engineer shall be responsible for implementation of the Quality Assurance Program for Operations at the plant. He reports to, and receives direction from, the Assistant Plant Super-intendent. The Quality Control Engineer has authority to communicate with the Manager of Quality Assurance or his representative for tech-nical 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.

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

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to shut the plant down if conditions warrant such action.

%J 1.5.4.2 The Shift Supervisor shall be responsible for the actual operation of the unit during his assigned shift. He directs activities of the unit during his assigned shift. He directs activities of the oper-ators on his shift and is cognizant of all operation-related main-tenance activities being performed while he is on duty.

In the absence of health physics personnel, he shall be responsible for having health physics activities performed as the need arises.

The Shift Supervisor on duty has the authority to shut down the unit if, in his judgment, conditions warrant such action.

1.5.5 Maintenance Group 1.5.5.1 The Maintenance Supervisor shall be responsible for organizing and conducting a preventive maintenance program and for directing repairs of electrical and mechanical equipment. He shall be responsible 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 Operations Super-visor. The Maintenance Supervisor shall have the authority to make repairs on any structure, system, or component under his control.

DATE

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1.S.6 Technical Support Group v

1.5.6.1 The Technical Support Engineer directs the plant's technical activ-ities including maintenance and operation of instrumentation, control systems, non-nuclear systems, radiation and health physics work, station chemistry, water control, and test activities in conjunction with the Operations Supervisor. The Technical Support Engineer shall have the authority to make repairs on any item or system under his control.

1.5.6.2 The Results Engineer monitors and evaluates daily plant thermal per-formance to obtain maximum efficiency in the plant steam cycle. He recommenos equipment maintenance or modifications necessary to improve steam cycle efficiency. He is also responsible for the performance of ( 1 non-nuclear instrumentation, control systems and plant computer systems, including their testing and repair.

1.5.6.3 Two Chemical and Radiation Protection Engineers are responsibic for overall chemistry and radiochemistry requirements including primary and secondary water chemistry. They direct the health physics pro-gram which includes training of personnel in the use of equipment, control of radiation exposures, continuous determination of the radiological status of the plant, surveillance of all radioactive waste disposal operations and implementation of the Environmental Blonitoring Program. The Chemical and Radiation Protection Engineers shall have the authority to set up ra/

tion barriers and to restrict (O

access of plant personnel into contaminated areas.

1.6 QUALITY PROGRA!.! COM?!ITTEES 1.6.1 Quality Assurance Committee (QAC) 1.6.1.1 Flembership Director of Power Production llanager of Transmission System Operations

!!anager 7f Installation and Testing Plant Superintendent (s)

Operations and Staintenance Coordinator Production Engineer

!!anager of Quality Assurance (Chairman) 1.6.1.2 Hectings The committee shall meet at least quarterir during plant operation. A mcfority of the QAC members is required for a quoruu.

Each committee member shall have a designated alternate. Not more than two alternate members are to be counted in the quorum.

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DAE a c-REV* 0 QUALITY ASSURANCE !!ANUAL 6/11/74 TITLE: ORGANIZATION SECTION PAGE 12of 20

1.6.1.3 Authority l

I The Manager of Quality Assurance shall report technically to the QAC which, in turn, shall report directly to the Senior Vice President, Production, Trans-mission and Engineering.

1.6.1.h ResponsibC

.es Responsibilities of the QAC for plant operation are as follows:

1)

Provide technical direction to the Manager of Quality Assurance in devising and implementing the AP&L Quality Assurance Program.

2) Review and approve the AP&L Quality Assurance Program and revisiens.

3).'ipprove QA programs of the major organizations participating in the AP&L Quality Assurance programs based upon the review and recommendation of the Manager of Quality Assurance.

4) Approve significant changes to construction and A-E quality programs (QAP-7).

5) Review significant deficiencies reported to the AEC under the requirements of 10 CFR 50 55 (e) for concurrence that appropriate measures have been taken to resolve the deficiency.

6) Resolve Quality Assurance related disputes arising from differences of opinion between the QA section and other groups (Administrative Services,

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Purchasing, Nuclear Services, Plant Staff, etc.).

If either party is not

• h10 5 satisfied with the QAC decision he may appeal to the Senior Vice President

• of Production, Transmission and Engineering.

1.6.1.5 General Specialists in mechanical, concrete, structural, and electrical construction shall be made available from AP&L Engineering Department to assist the com-mittee members in their review activities, as required.

1.6.2 Safety Review Committee (SRC) 1.6.2.1 Membership Director Power Production (Chairman)

Manager of Nuclear Services Maintenance and Operations Coordinator Arkansas Power & Light Company Manager of Safety Arkansas Nuclear One Superintendent Chief Chemist Arkansas Nuclear One Chemical and Radiation Protection Engineer Arkansas Nuclear One Nuclear Engineer Radiation and Health Physics Consultant Ruelear Safety Consultant Design and Construction Project Engineer DATE QUALITY ASSURANCE MANUAL V-12/13/7h TITLE: ORGANIZATION PAGE 13 of 20 1

a

'"y The Director of Power Production shall appoint an acting chairman in the

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absence of the Chairman. The plant staff members shall be non-voting members.

Alternates:

1) Each permanent voting member shall appoint an alternate to serve in his absence. Committee records shall be maintained showing each such cur-rent designation.

2) No more than two alternates shall serve on the committee at any one time.

3) Alternate members shall be non-voting.

1.6.2.2 Qualifications

1) At least four voting members including participating alternates shall have a minimum of a Bachelor's Degree in Engineering or the Physical Sciences or equivalent and have a minimum of three years of professional level experience, nr the equivalent, in nue; ear services, nuclear plant operation, or nuclear engineering, and the necessary overall nuclear bac!cground to determine when to call consultants and contractors for d mling with complex problems beyond the scope of the Company organi-

ation.

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2) Members and alternates shall collectively have the capability required

(

)

to review the areas of:

v a) Reactor Operations b) Nuclear Engineering c) Chemistry and Radiochemistry d) Metallurgy e)

Instrumentation and Control f) Radiological Safety g) Mechanical and Electrical Engineering h)

Environmental Considerations i) Other Appropriate Fields Required by the Unique Characteristics of the Nuclear Unit (s) Involved When the nature of a particular situation dictates, special consultants will be utilized to provide expert advice to board members upon request of any two board members.

3)

If sufficient expertise in the specialty in 6.1.2.2(2) abo've is not available from within the board, staff specialists and/or outside con-sultants shall be used to supplement review and audit functions of the board.

Personnel in this category shall be competent in technical matters related to nuclear unit safety and other engineering and scien-tific support aspects, q

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1.6.2.3 Meeting Frequency i

q; The Safety Review Committee shall meet on call by the Chairman but not less frequently than twice a year.

During the period of initial operation, Safety Review Committee shall meet no less frequently than once per calendar quarter.

1.6.2.4 Quorum

1) No less than a majority of the committee voting membership shall con-stitute a quorum.

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.

1.6.2.5 Purpose

1) The Safety Review Committee shall conduct a critical examination of design, construction and those aspects of monitoring nuclear unit operation necessary to formulate an independent evaluation of contem-plated actions, and after-the-fact investigations of anomalies.

2) The Safety Review Committee shall be constituted by a written charter stating:

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i a) Subjects within purview of the board

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b) Responsibility and authority c) Mechanisms for convening meetings d) Provisions for use of subgroups e) Authority for access to unit records f) Reporting requirements 1.6.2.6 Authority and Responsibility The Safety Review Committee shall be advisory to the Senior Vice President, Production, Transmission and Engineering (PTSE) and AP6L corporate manage-ment.

1.6.2.7 Review and Audit The board will verify that: nuclear unit operation is consistent with Company policy, rules, approved operating procedures and license provisions; unusual events are promptly investigated and corrected in a manner which reduces he probability of recurrence of such events; trends are detected which ay not be apparent to a day-to-day observer.

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The operation of the nuclear unit (s) shall be formally a'idited on a periodic

('-'j bas es. These audits shall be performed no less frequently than semiannually.

Periodic review of the activity shall be performed by the board to assure that such audits are being accomplished in accordance with requirements of Technical Specifications. Such audits shall include verification of confor-mance with normal, off normal, maintenance and emergency surveillance, test and radiation control procedures and the Emergency and Security Plans.

These audits shall be performed in accordance with appropriate written instructions or procedures and shall include verification.of compliance with internal rules, procedures and regulations and license provisions, performance of the operating staff, and corrective actions following anom-alles. Written reports of such audits shall be incorporated in the records of the board and disseminated to appropriate members of management, including those having respcnsibility in the area audited. Followup action, including re-audit of deficient areas, shall be taken where indicated and the results reported to responsible management levels on a formal basis.

Subjects for review shall include:

1)

Proposed tests and experiments, and results thereof, when these consti-tute an unreviewed safety question defined in 10 CFR 50.59.

2)

Proposed changes in procedures, equipment, or systems which may involve an unreviewed safety question as defined in 10 CFR 50.59 (c) or changes which are referred by the Plant Superintendent. Also, new procedures which may affect nuclear safety.

/N (v)

3) Proposed Technical Specification or license changes.

4) Violations of statutes, regulations, orders, Technical Specifications, license requirements, or internal procedures or instructions having safety significance.

5) Significant operating abnormalities or deviations from normal performance of unit equipment whose failure would affect safe shutdown of the plant.

6) Abnormal occurrences as defined in Section in the Technical Specifica-tions.

7) The Emergency Plans and procedures.

8) The Industrial Security Plan and Procedures.

9) Envircimental monitoring.

10) Nuclear safety matters deemed essential to the safe operation of the facility by the Superintendent, the Plant Safety Committee, the Manager of Nuclear Services, the Director of Power Production, o' the Senior Vice President (PTSE).

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11) Reports and meeting minutes of the Plant Safety Committee.

L.J

12) Reports submitted to the Atomic Energy Commission and associated responses.

1.6.2.8 Minutes

!!eeting minutes shall be prepared, formally approved, retained and promptly distributed to board members and other appropriate members of management having responsibility in the areas reviewed.

1.6.3 Plant Safety Committee (PSC) 1.6.3.1 Membership Assistant Superintendent (Chairman)

Technical Support Engineer Chemical and Radiation Protection Engineer Operations Supervisor 1

?!aintenance Supervisor Nuclear Engineer lhe Superintendent shall appoint an acting chairman in the absence of the Assistant Superintendent.

1.6.3.2 Qualifications

(_)

The qualifications of the regular members of the Plant Safety Committee with regard to experience and technical specialties of the individual members shall be maintained at a level at least equal to those described in ANSI N16.1 - 1971.

1Property "ANSI code" (as page type) with input value "ANSI N16.1 - 1971.</br></br>1" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..6.3.3 Consultants Additional personnel with expertise in specific areas such as radiochemistry, reactor engineering, and health physics may serve as consultants to the Plant Safety Committee.

1.6.3.4 Meeting Frequency

?!onthly, and as required, on call of the Chairman.

1.6.3.S Quorum i

Chairman plus three members or their designated alternates.

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1.6.3.6 Alternates Designated alternates shall be from other plant personnel in the appropriate disciplines; however, there shall be no more than two (2) alternate members serving on the committee at any one time.

1.6.3.7 Responsibilities

1) The committee shall review proposed normal, off nomal and emergency operating procedures; proposed maintenance procedures and proposed changes thereto and any other proposed procedures or changes which affect nuclear safety.

2) The committee shall review proposed tests and experiments which affect nuclear safety.

3) The committee shall review proposed changes to the Technical Specifi-cations which affect nuclear safety.

4) The committee shall review proposed changes or modifications to plant systems or equipment which affect nuclear safety.

5) The committee shall review nuclear unit operations to detect any poten-tial safety hazards.

6) The committee shall investigate reported instances of violations of the p

Technical Specifications, such investigations to include reporting, Q

evaluation and recommendations to prevent recurrence, to the Super-intendent.

7) The committee shall perform special reviews and investigations and render reports thereon as requested by the Superintendent.

8) The committee shall review the periodic drills to be conducted on emergency procedures, including evt.cuation (partial or complete) of the site and check adequacy of communications with off-site support groups.

9) The committee shall review the Industrial Security Plan and implemen-ting procedures and shall submit recommended changes to the Super-intendent.

10) The committee shall review the Emergency Plan and implementing proce-dures and shall submit recommended changes to the Superintendent.

1.6.3.8 Authority

1) The Plant Safety Committee shall be advisory, p

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aEy* o DATE f7 QUALITY ASSURANCE MANUAL 6/11/74 I

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ON PAGE IS of 20 1

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2) 'Ihe Plant Safety Committee shall recommend to the Superintendent approval

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or disapproval of proposals under items 1.6.3.7(1) through 1.6.3.7(4).

above.

a)

In the event of a disagreement between the recommendations of the Plant Safety Committee and the actions contemplated by the Super-intendent, the course determined by the Superintendent to be more conservative will be followed.

Records of the disagreement will be sent for review to the Manager of Nuclear Services, the Director of Power Production and the Safety Review Committee by the Superinten-dent.

3), The P', ant Safety Committee shall make tentative determinations as to whether or not proposals considered by the Committee involve unreviewed safety questions. This determination shall be subject to review and approval by the Safety Review Committee.

1.6.3.9 Records Minutes shall be kept at the plant of all meetings of the Plant Safety Committee and copies shall be sent to the Manager of Nuclear Services, the Director of Power Production and the Chairman of the Safety Review Committee by the Superintendent.

1.6.3.10 Procedures (n

Written administrative procedures for committee function shall be prepared

')

and maintained describing:

the method of submission and the content of presentations to the committee; provisions for the use of subcommittees; review and approval by members of written committee evaluations and recom-mendations; *he distribution of minutes; and, such other matters as may be appropriate.

1.6.4 Environmental Responsibilities The Plant Safety Committee and the Safety Review Committee shall review and audit the following:

1) Preparation of proposed Environmental Technical Specifications.

2) Ceordination 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.

4) Proposed written procedures, as described in Sepcification S.5, and proposed changes thereto which affect the plant's environmental impact.

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5) Proposed changes or modifications to plant systems or equipment which would affect the plant's environmental impact and the evaluation of the j

g impact of these changes.

6) Results of the Environmental Monitoring Pregrams 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 reco==endations for=ulated to prevent recurrence.

1.7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES As owner and operator, AP&L 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 Manager of Nuclear Services is responsible for establishing technical and management interfaces between the constructor, architect-engineer (A/E),

• nuclear steam supply system (NSSS) vendor, and AP&L. These interfaces may

• 1 be utilized as needed during operation of a nuclear unit for technical con-

• h10.10 sultation and services. These interfaces are established prior to the com-plete phasecut 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 modification contractor is responsible for administering the applicable quality control functions as required by AP&L. The Quality Assurance Organization is responsible for ensuring 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 assur-ance and quality control programs function in accordance with AP&L requirements.

The Manager, Quality Assurance, is responsible for communications with the AEC Regional Office regarding AEC quality assurance requirements related to the quality assurance activities described in the Quality Assurance Program for Operations and the implementation of the procedures within AP&L-support organizations.

The Plant Superintendent is responsible for com=unications with the AEC Regional Office regarding the adequacy, tsplementation and use of the Qua-lity Assurance Program for Operations at the Plant.

QUALITY ASSURANCE MANUAL REV. 1 DATE 1pf13/7h TITLE: ORGANIZATION SECTION PAGE 20 og 20

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President Arkansas Power 6 Light Company 1

Senior Vice President Senior Vice President g Senior Vice President Customer Services Production, Transmission Administrative Services and Engineering Assistant Director of Manager of Director of Director Chief Power Long Range Corporate

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-Engineer Production Planning Services Personnel 4

ARKANSAS POWER 4 LIQlT COMPANY CORPO, RATE ORGANIZATION Figure 1-1 i

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1 SENIOR VICE PRESIDENT AININIS'IRATIVE SERVICES e

l l-1 DIRECTOR DIRECTOR 0F 0F PERSONNEL CORPORATE SERVICES s

k MANAGER MANAGER OF PURCilASING AND' OF i

SAFETY STORES j

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4 SUPERVISOR l

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ARKANSAS POWER 6 LIGirr COMPANY Sr. Vice President Prod. Transmis.

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PRODUCTION, TRANSMISSION G ENGINEERING G Engineering Safety Review Quality Assurance Committec Committee l

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Direct r Assistant Manager P wer Chief Engineer Long Range Produci.on l

Building Planning l Superintendent I

l Technical Manager Manager Manager Manager Manager Direction Substation Transmi s sion Transmission Land and Installation Design Eng. G Constr.

System Operations Right of Way G Testing l

1 Manager Operation and Manager Chief Manager

_ __ J Design G Maintenance Nuclear G Construction Coordinator Services Chemist Quality Assurance I

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Production Fue1 ANO Quality Licensing P roj ect Management Plant Assurance Supervisor Supervisor Sup ervi sor Superin tendent l Staff 1

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I Ass't. Production Ass',t. Productio" Plant Sa fet y I

Ass:stant Plant Project Supervisor Project Supe rvi sor I.' **'ll""

flechanical filec t ri ca l Superintendent Figu 3

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ger Plani /

v' Quelity Superins.endent Assurance Administrative l

Assistant l

Plant Safety l

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Committee i Assistant Plant Superint endent Clerks Security Force Comunication i

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Secret ary l

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Quality liaintenance Operations Nuclear Technical Control Supervisor I

Supervisor Engineer l

Support i

Engineer I

i Quality Training Shift Reactor Con 1

Coordinator Supervisor Technicians l

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. _. _ _ Chemical and t

Results Plant Repairman Pl. fint. Elec.

Asgts Rad. Prot.

Engineer I

Pl. Repr. IIelper Pl. 51. E. IIelper Engineers s

Supervisor

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Instrument Repr.

Plant Cherf st Production Operator i Instrument Repr.

Ilealth Physics Storekeeper llelper Assistant A

" I PlantOperator!

j Plant Operatorg Storekeep er I

i~ Waste Control !

Laborers and Operator l

Arkansas Power G Light Company llelpe rs

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ANO Organization - Units 1 4 2 Figure 1-4

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2., QUALITY ASSURANCE PROGRAM a)

(V 2.1 SCOPE 2.1.1 he APSL Corporate Quality Assucince 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 n e 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 AEC regulations, applicable indus-trial 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 applied, but not limited to the structures, systems and components defined ir. *.he Plant Q-List.

2.3.2 ne Program functions in addition to the Corporate Quality Assurance Program for Design and Construction. The Quality Assurance Committee (v;

shall review and approve the Program and determine its adequacy and effectiveness during its scheduled meetings by review of audit reports, nonconformances, and significant problems.

2.3.3 AP6L shall be responsible for the assurance that nuclear fuel used in APGL Nuclear Plants is designed, procured, manufactured, and utili::ed in accordance with regulatory requirements, and related industrial codes and standards. APGL delegates to Middle South Services the actual perfomance of quality assurance functions related to the design, procurement and manufacture of nuclear fuel. He Middle South Services Quality Assurance Program for the performance of this activity is reviewed by the Manager of Quality Assurance and approved for use by the Quality Assurance Committee. He technical interface with Middle South Services is the responsibility of the Fuel Management Supervisor.

ne interface and its attendant duties and responsibilities are con-trolled by the procedure for fuel management centrol (NSP-11). Onsite quality control for nuclear fuel is implemented through the use of procedures in the Master Plant Manual.

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i 2.3.4 The Program defines responsibilities and duties to specific positions.

Q 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, ne procedures shall state the policies and instructions necessary to fulfill the intent of the Program. ney shall include the standard forms, lists and checkoffs used in documenting the inspec-tions, certifications, reviews und audits. he Program and the proce-dures shall be modified or supplemented from time to time as tho need for change arires during the life of the Plant.

2.4.2 The procedu_res ensure that activities affecting quality are performed under suitably 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. %e procedures also specify the need for special controls, processes, and test equipment to attain the required quality, and the need for verifi-cation of quality by inspection and test.

2.4.3 Program Procedures

1) Quality Assurance Procedures The Quality Assurance Organization employs a system of procedures designated as Quality Assurance Procedures (QAP) in order to 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. These procedures are listed by the title in Table 2-1.

2) Quality Control Procedures ne plant operation organization employs a system of procedures 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, nese procedures are listed by title in Table 2-2.

3) Nuc1 car Services Procedures s

The Nuclear Services Organization within the Production Department employs a system of procedures designated as Nuclear Services

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Procedures (NSP) in order to implement Prcgram requirements for (q!

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 Manager of Quality Assurance, and approved by the Manager of Nuclear Services. These procedures 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 cogni: ant organization, reviewed by the Manager of Quality Assurance and approved by the cognizant organization's department head.

2.4.5 Any procedure used at the operating plant will be reviewed and approved in accordance with the master plant manual.

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

Proposed changes to the AP6L Quality Assurance Program shall be reviewed and approved by the Quality Assurance Committee.

2.5.2 Quality Assurance Programs of Others 2.5.2.1 Re Program includes provisions that require suppliers, contractors, (g

subcontractors, consultants, etc., to maintain and use adequate

'- 'j quality assurance programs.

2.5.2.2 Contractor quality assurance programs shall be reviewed and approved by the Manager, Quality Assurance. The review and approval of such documents by AP5L in no way relieves the contractor of his respon-sibility to APSL to meet the applicable quality requirements of the licensing agency as outlined in 10 CFR 50, Appendix B.

Audits by the Quality Assurance Organization provide assurance of compliance with applicable procedures.

2.6 SYSTEM, STRUCBJRE, AND COMPONENT CLASSIFICATION 2.6.1 ne systems, structures and components that perform safety-related functions are designated as Q-List items. The Q-List specifically identifies those systems, structures and components whose failure could cause an uncontrolled release of radioactivity, or those essential for safe shutdown and the immediate and long-term operation following a Loss of Coolant Accident. hhen 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.

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s fg 2.6.2 ne Q-List is initially generated by the architect-engineer during'

(")

the design phase of the project. He Q-List is considered a design document and is reviewed and approved in accordance with the procedure for design verification (NSP-4). The approved Q-List is retained as functional document throughout the life of the plant to provide for the application of Program requirements to a specific system, stzucture 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 ruanagement to arrange for the quality assurance indoctrination program. The Plant Superintendent has responsibility for Plant Staff personnel indoctrination regarding the Quality Assurance Program.

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

2.7.2 The quality assurance indoctrination for the management of AP6L support organizations shall be conducted by the Manager of Quality Assurance or his designated representative. The management of the support organi-m(v) zation in turn is responsible for conductinF an indoctrination of employees in their respective groups. The inacctrinations they con-duct cover the areas in which the group or employee has particular responsibilities. The Quality Assurance Program indoctrination is coordinated at the plant by the Plant Training Coordinator or his 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 contents as applicable with specific emphasis placed on those sections which most directly affect the employee's position.

4) Discussion of interfaces with the AEC and contracted organizations.

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

He Plant Training Coordinator maintains the record of attendance for plant 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 Plant Operations to deter-mine the effectiveness and proper implementation of the Program (ANO-14).

2.8.2 3e Quality Assurance Engineer (Operations or Engineering) regularly reviews the status, adequacy, and effectiveness of the implementing procedures as part of his daily work (ANO-17 and ANO-18).

2.8.3 In addition, the Quality Assurance Committee shall assess the scope, implementation, and effectiveness of the Program through review of audit reports to assure its effective compliance with corporate policy and with 10 CFR 50, Appendix B.

He assessments are undertaken during the regularly scheduled meetings of the Committee, or on a case basis if so requested by any member, o

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Table 2-1 Quality Assurance Procedures ANO-3 Surveillance Audits This procedure establishes methods for perforhing quality assurance surveil-lance audits for Arkansas Power & Light Company at the manufacturing, design, or engineering facilities of companies supplying syctems, 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.

ANO h Field Weld Audits This procedure establishes methods for performing quality assurance audits of field velds on Q-List items and Q-List field weld records at the site.

Pro-visions are made for auditing veld identifications, velder qualifications, velding procedures, procedure qualifications, and welding tests and test records.

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 3 and ANSI Nh5.2, and pro-l I vides a method of reporting findings and identifying deficiencies.

ANO-7 Review of Handline of Nonconformance This procedure establishes methods for performing quality assurance audits on nonconforming items.

It incorporates methods for auditing documentation of Q-List items as well as rework and repair of nonconforming items.

ANO-8 Field Electrical Surveillance Audits This procedure establishes methods for performing quality assurance audits of the various types of electrical systems and components, including motors, raceway, transformers, switchgear, motor control centers, instrumentation, and cable installation.

It incorporates methods of auditing both documenta-tion and physical aspects of Q-List items.

ANO-9 Job Site Receiving, Handling and Storace This procedure establishes methods for performing audits of receiving, hand-ling, and storage activities.

It incorporates methods for auditing docu-mentation of Q-List items as well as the physical handling and storage of Q-List items.

DATE QUALITY ASSURANCE MANUAL 12/13M3 TITLE: QUALITY ASSURANCE PROGRAM PAGE 6 of 13

I ANO-10 Calibration of Measurine and Test Equipment This procedure establishes methods for perfor=ing audits of the calibration and testing of tools, instruments, and equipnent. It incorporates methods for auditing both documentation and physical aspects of Q-List items.

ANO-11 Document Control Audits This procedure establishes methods for the audit of dccument controls to as-sure that specifications, drawings, procedures and instructions are properly recorded and filed.

ANO-lh Operatine Plant General Audit This procedure establishes methods for the audit of general plant operations to assure that plant quality programs conform to the requirements of 10 CFR 50, Appendix B.

ANO-16 Review of Audits This procedure establishes methods for the review of audit reports submitted by other organizauions associated with AP&L nuclear plant projects.

ANO-lT Operatine Plant Surveillance Audit This procedure establishes a method for frequent surveillance audits of plant

(

) quality activities to assure compliance with the AP&L Quality Assurance Pro-It provides methods to identify areas of deficiency (or potential de-gram.

ficiency) for necessary corrective action.

ANO-18 Engineering Surveillance Audit This procedure establishes a method for frequent surveillance audits of engi-neering activities ans activities of other production support activities to assure compliance with the AP&L Quality Assurance program.

It provides methods to identify areas of deficiency (or potential deficiency) for necessary cor-rective action.

ANO-19 " Shelf Item" Vendor rudit This procedure establishes methods for performing quality assurance 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.

O DATE QUALITY ASSURANCE MANUAL EV.

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Table 2-2

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ARKANSAS NUCLEAR ONE PLANT (UALITY CONTROL PROCEDURES

• 2 1004.01 DesignControl 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 Production Department for design work are established.

1004.02 Initiation And Processing of Trouble Tickets This procedure provides direction for initiation and processing of trouble tickets to document the nonconformance of systems, structures, materials,

• 1 parts or components. Troable tickets are used as a means of identifying nonconformances which do not require immediate corrective action.

1004.03 Training and Indoctrination This procedure delineates the requirements for, and the contents of, the QC training and indoctrination program for personnel at Arkansas Nuclear One.

Persons involved in operations affecting quality are familiarized with the p

quality requirements imposed by regulatory agencies, recognized industrial Q

codes and standards and the APSL Quality Assurance Program.

1004.04 Turnover of Q. A. Docn%ats from Construction to AP6L This procedure describes the methodology for Review of Quality Assurance Records associated with system turnover.

It assures that documents are com-plete and adequate, that specified inspections and tests have been satisfac-torily accomplished, and that systems, structures, items or components are acceptable to APSL.

1004.0! Purchase Requisition Preparation and Processing This procedure establishes the 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 necessary to verify that the item is in conformance with the applicable

. specifications.

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1004.06 Material Receivine and Inspection 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.

100h.07 Control of Special Processes This procedure covers the establishement of process controls and requirements for qualifications of personnel, procedures and equipment.

100h.08 Q.C. Inspections This procedure provides guidance for inspection planning (including inspec-tion hold points), performance of inspection, and reporting for all activi-ties affecting quality. These inspections are mandatory for Q-List items and are optional for BOP items.

100h.09 Plan for Preoperational Testing (Deleted)

After the preoperational testing of Arkansas Nuclear One Unit 1 a startup or

• ganization was established reporting directly to the Manager of Nuclear Ser-

• 1 vices.

• L10.8 1004.10 Calibration Control l

I This procedure provides requirements for the calibration program, and detailed guidance for QC surveillance of inspection, measuring and test equipment to assure that the equipment is in calibration at the time of use.

100h.11 Handling, Storage and Shippine 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.

100h.12 Operational Test Control 1his procedure defines testing and requirements, frequencies, documentation, coordination and administrative controls associated with ongoing testing during the commercial operation of the plant.

100h.13 Nonconformance and Corrective Action This procedure provides the methodology for reporting, analyzing, disposi-tioning (including approvals) nonconforming material, parts and components DATE I

QUALITY ASSURANCE MANUAL V. 1 12/13/7h TITLE: QUALITY ASSURANCE PROGRAM PAGE 9 of 13 SE ION

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e-and further provides for inspection of resubmitted material.

It also addresses a

f x

the assessment of cause, recommended corrective action, follow-up and reporting

( (v) to responsible management.

1004.14 Initiation and Processing of Job Orders This procedure provides direction for initiating and processing of job orders for corrective or preventive maintenance activities within the plant.

A job

• 1 order applies to Q-List items and shows proper review, approval and documenta

• tion.

1004.15 This Number Not Assigned-1004.16 This Number Not Assigned

• 1 Procecure 1004.16, " Review and Verification of Documents", was deleted after a

• review determined that the procedure is not necessary.

i 1004.17 Onsite Fabrication and Modification Control This procedure establishes a set of controls for the fabrication and modifica-tion activities performed by non-APSL personnel such as contractors or v.endors.

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 assures that all material associated with Q-List items can be identified and

<s

(

)

matched with their applicable quality assurance documentation.

v 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 requirecents for Quality Assurance and Quality Control personnel engaged in inspection or testing.

1004.21 Procedure Handling

• 2 This procedure covers the handling of procedures not specifically related to the test program. These procedures will cover details necessary for b

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7-~g operating the ANO facility in a safe, reliable and efficient manner. Specific areas by this plan are Quality Contre,o1 Procedures, Administrative Procedures, i,

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 speci-fications, 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, and reten-tion.

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.

(Oj 1004.25 Document Retention

• 2 s/

This procedure identifies the specific records which must be retained for the Arkansas Nuclear One and specifies the method of retention and the required retention periods for such records.

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NUCLEAR SERVICES PROCEDURES 1.

Design Interface Control This procedure establishes the internal and external interface control by which the Manager of Nuclear Services controls each discipline contributing to the design process within APGL. This Production Project Supervisor is established as the focal point for all external design work accomplished for AP6L by NSSS supplier, architect-engineer or engineering consultants.

2.

Design Criteria ne procedure formalizes the establishment of the design bases and criteria for safety-related systems, structures and components.

3.

Design Process his procedure establishes the methods for the preparation of drawings, speci-fications and analyses incluaing calculations. Standardized formats for design disclosure documents are established and specific quality levels of acceptance standards as guidelines are provided.

4 Design Verification A

(#)

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.

S.

Design Change Control 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.

6.

Design Defic _iency/ Corrective Action This procurement formalizes the reporting of design deficiencies and provides a method of positive feedback to assure that appzopriate corrective action is taken to prevent recurrence of the deficiencies.

7.

Design Document Control This procedure establishes those design documents that are controlled within the Production Department by providing a standardized file and distribution system compatible with the AN0 Records System and future projects, f3

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Drawing Control his procedure establishes the responsibility of the Production Department staff and the method by which engineering drawings, either in paper form or on aperture cards, are controlled, including receipt, filing, disposition of superseded drawings and retention.

9.

Licensing /SAR/ER Control This procedure establishes the methods by which the safety analyses reports, environmental reports and changes thereto are prepared, reviewed and approved for submittal to Federal, State and local authorities.

10.

Engineering Reports and Evaluations This procedure provides the methods by which the design procedures are used to formally control engineering investigations, evaluations and reports per-formed by Production Department personnel in support of the operating nuclear plant.

11.

Fuel Management Control This procedure establishes the methods by which +.he Fuel Management Supervisor controls the interf ace for fuel management between Middle South Services, the operating nuclear plant and the Production Department.

12.

Procurement Control i

i His procedure establishes the responsibilities and methods by which procure-ment of safety-related parts, material or services is reviewed and approved by APSL.

It includes the required QA review and technical review of contractor-prepared purchase specifications and documents.

13.

Purchase Requisition Preparation and Processing This procedure establishes the methods used for the procurement of safety-related parts, materials and equipment by APGL when the item or service is procured solely by APSL in accordance with a reviewed and approved specifi-cation. His procedure provides detailed control for the actual preparation, review and approval of a purchase requisition and for the distribution con-trol and follow-up of the actual purchase order released to the vendor by the Supervisor of Purchasing.

14 Administrative Control This procedure establishes filing systems, file indexes and methods for processing incoming, outgoing, and internal correspondence. This procedure includes the instructions for processing and filing the Admini'strative/

General Technical and Project Technical Correspondence.

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TITLE: QUALITY ASSURANCE PROGRAM PAGE 13 of 13

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DESIGN CONTROL p)

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3.1 SCOPE 3.1.1 Design activities s'n11 be controlled to assure that proposed plant changes to the stle.-tures, systems, equipment and components conform to applicable regulatory requirements and that design bases are cor-rectly translated into appropriate design documents.

3.2 GENERAL 3.2.1 The AP4L Production Department shall be responsible for the continued upgrading and modification of plant design. Design documents (drawings, 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 in accordance with AEC licensing requirements. Design activities 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-fomed by individuals within the AP6L Production Department are controlled by the use of QAP's for the design process (NSP's 1-8).

The plant staff uses QCP 1004.01 for the contro!. of design activities.

3.2.2 Design standards and r2quirements shall be at least equivalent to those employed during the construction of the station and shall be consistent (d

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 estnblishment of a suitable test program.

Where 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 Peviews of design documents generated within APSL are accomplished teing applicable design verification and design control procedures (NSP-4).

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3.3.3 During the above reviews, particular attention shall be given to La v

following areas:

1) Assurance that all appropriate standards are clearly delineated in the documents. Where it is considered necessary to deviate from these standards, separate written approval shall be required from the Manager of Nuclear Services and shall be appended to the 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 utili:ed; the compatibility of design for in-service inspection, maintenance and repair; and the acceptance criteria for inspections and tests.

Performance history and failure data o. 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 AEC approval

, w) prior to the final approval of the design document has been iden-(.V tified.

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

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

A feedback system of corrective action by distribution of th 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. Changes that are strictly of an editorial nature may be made in ink with the approval of the cognizant Plant Supervisor, or the Plant Superintendent.

In every case, copies of editorial changes are routed to the participating design organi:ation and the plant Administrative Assistant.

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TITLE: DESIGN CONTROL PAGE 2 of 3

3.4 DESIGN RECORDS 3.4.1 ne Administrative Assistant shall be responsible for maintaining per-manent 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 described in this section. The controls for maintaining these records are established by specific procedures described in Section 17.

Rese records provide the historic reference necessary for the safe and reliable operation of the plant.

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TITLE: DESIGN CONTROL PAGE 3 of 3 3

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PROCUREMENT DOCUMENT CONTROL l

h h.1 SCOPE h.l.1 Control of the procurement activities shall provide assurance that applicable regulatory requirements, design bases, technical requirements and quality assurance criteria are suitably included or referenced in the documents for procurement of material, equipment, and services, whether purchased by AP&L or by its contractors and/or subcontractors. Pro-curement documents are the drawings, specifications and purchase requi-sitions that result in a purchase order.

k.2 GENERAL k.2.1 Vendors shall be selected from the Qualified Vendor List (QVL).

h.2.2 Vendors may be added to the QVL as approved by the Manager of Quality Assurance.

Such approval is based upon the vendor's past performance.

ability to supply a quality product and recommendations by other parties.

Vendors may be placed on the QVL pursuant to information rr eived from

• 1 the architect-engineer, NSSS supplier or consultants. To qualify to be placed on the QVL, a vendor must have a quality assurance program consist

• ent with the requirements of applicabic portions of 10 CFR 50, Appendix 3 and ANSI NkS.2 which apply to the specific goods or services supplied by that vendor.

4.2.3 Purchase documents for spare or replacement parts or parts of safety-i {

)

related structures, systems or components, including "off the shelf"

• 1

)

items, shall be reviewed by the Plant Quality Control Engineer for k10.11 adequacy of quality requirements. The review determines similarity,

)

compatibility, current regulatory applicability and inclusion of, at a minimum, the quality assurance requirements and acceptance criteria of the original part. As part of the review, a document control form shall be included which specifies the documents to be supplied by the vender to verify that engineering quality, inspections, and tests have been completed.

4.2.4 The preparation, review, and control of procurement documents are established in the procedures for purchase requisition and processing (NSP-13; QCP 100k. 05 ).

h.2 5 The Manager of Quality Assurance shall verify the compliance with pro-curement 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-1k; ANO-17; ANO-18).

DATE QUALITY ASSURANCE MANUAL REV. 1 12/13/7L TITLE: PROCUREMENT DOCUMENT CONTROL SC ON PAGE 1 of 3

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4.2.6 Where multiple procurement is involved, the Pu?..hasing Department shall (V

apply identical quality assurance requirements to each vendor.

4.2.7 AP6L purchase documents shall require prime vendors to apply the appli-cable 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 cog-nizant supervisor, Plant Quality Control Engineer and by the Plant Superintendent or Assistant Plant Superintendent before issue of a purchase order.

4.3.2 When a Q-List design change is involved.equisitions are initiated by the Production Department as described in the procedure for purchase requisition preparation and processing (NSP-13).

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 equivalent to the applicable portions of specifications under which the equipment

[]

was originally furnished.

In situations where a part is being replaced V

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 prepared and reviewed by the Production Department to assure that applicable codes, standards and other design bases are included or referenced and that appropriate and sufficient requirements for quality assurance documentation are incorporated therein. Applicable codes, standards and other design bases are deter-mined from a review of the FSAR, Q-List, material control list, drawings i

and other design disclosure documents which apply to the "as-built" plant. This review requirements are specified in the quality assurance procedure for design verification (NSP-4).

4.4.3 It is the responsibility of the cognizant plant supervisor to assure that both the originator and the reviewer of a Q-List specification are qualified to perform their assigned tasks.

4.S PURCllASE ORDERS 4.S.1 Purchase orders shall be issued by AP6L Purchasing Department and shall affirm those requirements set forth in the specifications.

REV. 0 QUALITY ASSURANCE MANUAL 6/11 74 n

TITLE: PROCUREMENT DOCUMENT CONTROL SECTION PAGE 2 of 3 4

h.5.2 Purchase orders for

• ist items shall require that vendors and their subvendors posa,s a Quality Assurance Program consistent l

l vith the applicable requirements of 10 CFR 50, Appendix B, or ANSI Nh5 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.

h.5.3 Changes to purchase orders and reference documents for Q-List items

• 1 are to be subject to review equivalent to that of the original do-

• kl0.13 cuments.

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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.

5.1.2 Additional procedures may be required as determined by the Plant Superintendent.

5.2 GENERAL 5.2.1 Instructions, tests, calibration, specifications, procedures, main-

• 1 tenance, modification and repair processes are developed, reviewed

• 410.15 and approved according to the administratiite procedure on handling of procedures (QCP 1004.21). Drawings are controlled by the admini-

• 2 strative procedure for drawing control (QCP 1004.23). Drawings and

• 2 specifications related to plant modifications are reviewed according

• 1 to the procedures for design change control (QCP 1004.01 and NSP-5)

• 410.15 for QA concurrence of the quality designation of the design change package. QA review of drawings and specifications related to modi-fications involving Q-List systems or equipment is provided by the

}

Plant Safety Committee.

G 5.2.2 I structions, 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 the activity being performed.

5.2.4 To assure accomplishment of the activities in accordance with approved 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 for Nuclear Power Plants".

5.3 TEMPORARY CHANGES n

(v) y om QUALITY ASSURANCE MANUAL 3/4/75 TITLE:

INSTRUCTIONS, PROCEDURES AND DRAWINGS SECTION g

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5.3.1 Temporary changes to procedures in the Master Plant Manual which do

(, s) not change the intent may be made provided such changes are approved L'

by two members of the plant staff at least one of whom shall be a Shift Supervisor.

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 approved by the Plant Superintendent.

5.3.3 A temporary change in effect for more than one year will be reviewed at the earliest possible date by the Plant Safety Committee, and either rescinded or added to the procedure as a revision, as provided for in the administrative procedure for document control (QCP 1004.22).

• 2 5.4 EMERGENCIES In cases of emergency whero the safety of personnel, the public, or the re-actor or other equipment are in immediate jeopardy and approval by normal channels is not possible because of time restraints, temporary deviations from established instructions, procedures or drawings may be made with the approval of the Shift Supervisor and one other individual holding a Senior Operctor's License. These changes shall be approved by the Duty Emergency j

Coordinator and by the Plant Superintendent at the earliest possible time.

5.5 CHANGES TO PROCEDURES Changes or revisions to approved instructions, procedures or drawings which O

affect quality. are controlled by the procedure on handling of procedurcs V

(QCP 1004.21).

• 2 5.6 REVIEW OF PROCEDURES, INSTRUCTIONS AND DRAWINGS 5.6.1 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 incidents.

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

5.6.3 Applicable instructions and procedures shall be reviewed, and revised as necessary, following major changes to the Quality Assurance Pro-gram.

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DOCUMENT CONTROL i

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6.1 SCOPE 6.1.1 The 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-7)

2) Drawing control (NSP-8)

3) Plant records management (QCP 1004.24)

• 2

4) Document retention (QCP 1004.25)

• 2

5) Document Control (QCP 1004.22)

• 2 6.2 GENERAL 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.

p, 6.2.2 The Administrative Assistant shall supervise the issuance of the (j

Master Plant Manual 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 ; rocedures (QCP 1004.21), and document control

• 2 (QCP 1004.22).

• 2 O

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3) Changes to docua 4s such as operating procedures, maintenance (3'j procedures an6 w ouilt drawings shall be reviewed and approved by the same or p i:ctions which perform the original review and approval.

If such is not possible, the Plant Superintendent shall a: _re that the review is delegated to appropriate qualified re-sponsibir

.aps.

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

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6.2.S Permanent plant dc "ments are stored at the plant site by the plant staff under the supervision of the Administrative Assistant.

Records *

(or copies, as appropriate) generated by Nuclear Services, Quality

• 1 Assurance, or others are provided to the plant staff for storage.

• 410.16 These records include:

1) Procurement documents for Nuclear Services' purchased items.

2) Design Specifications, Drawings, and Design Criteria originated or revised by Nuclear Services.

3) Design Change Request packages and supporting documents.

6.3 DOCUMENT IDENTIFICATION 6.3.1 Documents shall contain a title descriptive of their purpose or appli-p cability 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 a revision record page or other appropriate means.

6.4 STORAGE AND FILING REQUIRCMENTS 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-mi:e damage and pro. rve the integrity of the documents.

Storage con-trols ate set forth in procedures for plant records management, and document retention (QCP 1004.24; QCP 1004.2S).

• 2

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7 CONTROL OF PURCHASED MATERIAL, EQUIPME'iT AND SERVICES I

I 7.1 SCOPE 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. Precurement control shall include provisions, as appropriate, for the evaluation and selection of vendors, objective evidence of quality, furnished surveillance of the vendors and exam-ination of products upon delivery.

7.2 S0tJRCE EVALUATION 7.2.1 Vendors shall be selected on the basis of demonstrated capability during the design and construction phase to provide a quality product, process or service in accordance with the procurement documents for the operational phase.

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 before the purchase order is released. Such review shall be based on:

7 2.2.1 The current ability of the contractor to comply with those elements of 10 CFR 50, Appendix B which pertain to the type of material, equipment or services being procured.

l l 7.2.2.2 A survey and evaluation of the vendor's facilities and quality as-surance program, when no previous records are available.

73 DOCUMENTATION 0.-

QUALITY 731 Verifiable evidence of quality shall be furnished by vendors as pre-scribed in the procedure for procurement control. (NSP-12) 7.3.2 Documentary evidence that material and equipment conform to the pro-curement requirements shall be available at the site prior to instal-lation or use of such material and equipment. As necessary, vendors are to be requested to maintain documentation. A certificate of con

• 1 formance is to be maintained at the plant site to reference any docu

• h10.12 mentation by the vendor. Such documentary evidence shall be retained

• at the site and shall be sufficient to identify the specific require-ments, such as codec, 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-conform-ance report is filed in such a case.

7.h SOURCE INSPECTION DATE QUALITY ASSURANCE MANUAL REV. 1 12/13/Th TITLE: CONTROL OF PURCHASED MATERIAL, SECT 105 EQUIPMENT AND SERVICES PAGE 1 of 2

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7.h.1 The effectiveness of quality control by vendors shall be assessed by the Manager of Quality Assurance at intervals consistent with the im-portance, 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.

7.h.2 Source ir.spection 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 Nh5.2 (applicable to the product or service provided).

3) Design and quality classification, codes and standards which ap-ply to the product or service provided.

b) The procurement document requirements.

75 RECEIPT INSPECTION 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 100h.06). This procedure assures that:

1) The material, equipment or component is properly identified and corres-l I

ponds with the receiving documentation, as required by h.2.3

• 1 h10.17A 2)

Inspection of the material, component or equipment and acceptance records is performed in accordance with predetermined inspection instruments, prior to installation or use.

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

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

5) Supplier non-conformances which have been accepted by AP&L prior to shipment of the item shall be documented in the procurement records fur

• 1 nished by the supplier at the time of receipt or the item shall be con *h10.17B sidered non-conforming as required by procedure 100h.06 and 100h.13 7.6 STORAGE 7.61 Q-List materials shall be handled and stored as prescribed in the pro-cedure for handling, storage, and shipping of Q-List materials (QCP 100h.11).

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

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IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS j

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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 suall be su:'ficient to prevent the use of incorrect, defective or illegibly marked materials, parts and components.

8.2 IDENTIFICATIM AND MARKING 8.2.1 Materials, parts and c ompenents shall be identified and marked by suppliers in accordasce with requirements set forth in applicable codes and in the procurement documents. The requirements shall absure that :

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

2)

Identification of parts and corresponding documents vill accompany all partially fabricated assemblies shipped as one unit. Such documentation slhll include, as applicable, heat numbers, part numbers, serial numbers, material certifications and veld quali-fications to provide sufficient bases for determining the accepta-

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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.

• h10.18 8.3 TAGGING 8.33 In addition to being marked, Q-List materials, parts and components shall be tagged with a "Q Tag".

The tag shall identify the item and the permanent filed records which document the item.

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

DATE QUALITY ASSURANCE MANUAL Y* 1 12/13/7h TITLE: IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND CO?@O;myrg PAGE 1 of 2 8

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[^N, 8.3.3 Tagging shall be performed in accordance with th'e procedure for material

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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-dure for nonconformances and corrective action (QCP 1004.13).

8.5.2 Defective or inceirect items shall be clearly identified on the "Q" tag.

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

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CONTROL OF SPECIAL PROCESSES 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 Re 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 Maintenance Supervisor, Technical Support Engineer and Quality Control Engineer shall develop procedures and provide qualified person-nel for current special processes as delineated in the procedure for l

control of special processes (QCP 1004.07).

9.2.3 The Qualit" Assurance Engineer (Operations) shall periodicially audit special process procedures and personnel qualification to assure compli-ance with applicable codes and specifications.

1 9.3 GENERAL

()

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

1) Special maintenance and cleaning.

2) Metal joining, such as welding, soldering and bra::ing.

3) hermal cutting.

4) Hot and cold working and bcnding.

5) Coating and plating.

6) Nondestructive examination.

7) Radiological analyses and contamination control.

8) Chemical analyses.

9) Heat treating.

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9.4 QUALIFICATION 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).

9.4.2 The 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.

INSPECTION 10.1 SCOPE 10.1.1 On and effsite 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 100h.08) which specifies inspection requirements,

• h10.1 9 techniques, documentation and responsibility as described in Section 3, h, and 7 of the Program.

10.1 3 Quality-related activities subject 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.

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

5) operation of safety-related items.

6) Special maintenance activities.

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T) Inservice Inspection 10.2 RESPONSIBILITY 10.2.1 The Plant Superintendent shall be responsible for assuring that plant personnel cemply 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. Sour-surveillance /

inspection shall be the responsibility of the Manage: 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 The Quality Assurance Engineer (Operations) shall review inspection records prepared by the Quality Control Engineer and inspection personnel, and shall periodically audit inspection procedures and i

personnel qualifications to assure that inspection requirements are i

being fulfilled.

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10.3.1 To accomplish inspections, written procedures, instructions, diagrams, foms and checklists shall be provided which as a minimum contain the following:

1) Qualitative and quantitative acceptance criteria.

2)

Identification of those individuals responsible for perfoming the innpection operation.

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.

4)

Identification of any special tools, equipment or skills required.

S) A signoff by signature or a controlled stamp showing evidence of completing and verifying the inspection, j

6) The results of the inspection operation.

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 process monitoring shall be provided when control is adequate without (3) both.

x.s 10.3.3 Inspection personnel shall verify that inspection equipment utili::ed is within calibration prior to perfoming 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 IS and 16 of the Program and the procedure for nonconformance an/ corrective action (QCP 1004.13)c 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 ir.spections shall meet the following requirements:

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1)

Be independent from the individual or group performing the activity being inspected.

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

3)

Be currently qualified and so designated on a list of qualified 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).

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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 centained 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

• 1 410.8 11.2.1 Testing of Q-List structures, systems and components shall be perform-ed by qualified personnel in accordance with approved written test procedures. The supervisor responsible for performing the test shall verify that all test equipment 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 sumreillance tests, tests shall be performed following significant plant modification or significant changes in operating procedures to confirm that the modification or l

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O changes are not detrimental to the safe and efficient operation of the plant.

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

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

11.2.S 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:

ps,

1) Identify of part or material, system, stnicture, or component

{

(j under test.

2) Date of test.

3) Data taken.

4) Name and signature of individual performing test.

S) Test results and conclusions.

6) Identify of portable test equipment.

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

8) Review signatures of cognizant supervisors, and final review signature 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).

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.a 11 5 PREOPERATIONAL TESTING 1151 A manual describing the provisions that control the transfer of safe

• l ty related equipment and records from the principal contractors to AP&L during the preoperational testing phase up to fu,el loading, shall be prepared and shall include the identification of those sig-

• 1 nificant QA-related activities, provisions established to assure

• 410.8 proper inspection and verification of equipment; the means of tag-ging 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.

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11

12..CCNTROL OF MEASUREMENT AND TEST EQUIPMENT 12.1 SCOPE 12.1.1 A control progrea snall be established to assure that tools, gages, instrunents 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 specified by the inspection or test requirements. This activity is referenced in the procedure for calibration control (QCP 100h.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 ad-justed at specified intervals to maintain accuracy within the neces-sary limits.

12.2.2 Calivration 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.

12.2.3 Calibration procedures shall conform to recognized standards and lo-cal, State and Federal regulations.

12.2.h The procedure shall be clearly noted on a calibration report, and the comparison standards utilized in the calibration method shall be traceable to the National Bureau of Standards, and supported by cer-tification reports and data sheets when applicable.

12.2.5 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

• 410.21

" state of the art".

12.2.6 When inspection, examination, meas,urement and test equipment is found to be out of 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, examinec,

• 1 or tested shall be made and documented by written report on a case

• h10.2C basis.

The Plant Superintendent or his designee has final approval of such evaluation, and at his discretion may require repetition of the inspection, examination, er test.

12.3 RESPONSIBILITIES 12.3.1 The Results Engineer and Maintenance Supervisor shall be responsible for compiling a list of all measuring and testing devices under their control that require periodic calibration.

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TITLE: CONTROL OF MEASUREMENT AND TEST EQUIPMENT PAGE 1 of 2 SECTION 12

12.3 2 The control of measuring and testing devices used in the calibra-tion of Q-List equipment shall be the responsibility of the cogni-zant supervisor, whc shall ensure that the devices are used only by qualified personnel and are properly segregated from other devices.

12.3.3 Plsnt personnel shall be responsible for utili:ing only properly identified and calibrated equipment.

12 3.h The Quality Control Engineer sLs11 be responsible for monitoring test equipment control and use in order to verify compliance with the program.

12.h EQUIPMENT IDENTIFICATION 12.h.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.h.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:

1, Equipment identification

2) Calibration reports and test data (until recalibrated)

3) Manufacturer's data sheets h) C-libration procedures DAIE V.

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13.

HANDLING, STORAGE, AND SHIPPING ss/

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, parts or components after their arrival at the station.

13.3 RECEIVING INSPECTION 13.3.1 Upon arrival of material at the station, the Maintenance Supervisor shall be responsible for assuring that the items are inventoried, and inspected for damage, deterioration and cleanliness as described in the procedure for material receiving and inspection (QCP 1004.06).

['V)

The QC inspector is responsible for inspecting and classifying Q-List materials.

13.3.2 Results of the receiving inspection and disposition of the material shall be noted in the material received inspection report.

13.4 STORAGE AND PRESERVATION The Production Storekeeper shall be responsible for assuring that:

13.4.1 Khen possible and practicable materit'.s are stored indoors, and in all instances in a manner that provides adequate protection against damage or misuse.

1 13.4.2 Designated items receive special protection such as controlled environ-ment, locked storage, special coverings and segregation to prevent

)

contamit.ation.

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

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13.5 RADI0 ACTIVE MATERIALS 13.5.1 The Chemical and Radiation Protect.;n Engineer shall be responsible for ensuring that radioactive materials are handled, stored and shipped in accordance with applicable regulatory requirements.

13.6 RECORDS The Quality Control EnE neer shall be responsible for assuring that 13.6.1 i

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 I'

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-.p 14.

INSPECTION, TEST, AND OPERATING STATU_S, l

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14.1 SCOPE 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 OPERATIONAL 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 re=ain undetected, and that the required relic 71-lity of safety systems is maintained.

The procedure for operational test control (QCP 100h.12) identifica the surveillance tests and in-spections to be performed.

N nconformances discovered r'all be docu-o mented and resolved as pr escribed in the procedure for nonconformances and corrective action (QCP 100h.13). Controls for assuring'that tests are scheduled as required and that test results are obtained are pro-vided by a ecmputerized program or a master test control chart.

If a

• test or inspection is not performed within its required surveillance

• 1 interval, the Plant Superintendent is informed. He vill take action

• h10.02 as necessary.

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glb.2.2 The adequacy of initially installed components is ensured by manu-facturer's testing as required by the procurement contractor, and by procedures controlling material receipt and inspection, and hand-ling (QCP 100h< 06; QCP 100h.07). Startup testing. and performance tests following modifications verify the adequacy of newly installed items.

14.3 IDENTIFICATION OF OPERATIONAL STATUS lk.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.

Ih.3.2 overall Plant Status 14.3.2.1 The Shift Supervisor shall maintain sufficient knowledge of overall plant status tests and inspections to control overall plant opera-tions. The shift operators will maintain a ready reference of plant systems, structures and components alignments as well as a status board sumnary of abnormal conditions. The St.ft Supervisor shall ensure that personnel performing tests and inspections keep the shift operators informed of the current status of tests and inseections.

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15.

NONCONFORMING MATERIAL, PARTS, OR CCMPONENTS 15.1 SC0pE 15.1.1 Nonconforming items include materials, parts, components, processes and documents that do not conform to applicable regulations, codes, standards, specifications or contractual documents.

15.1.2 Nonconforming items shall be controlled to pravent 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 100h.05; 100h.06; 100h.08; 100h.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, in-stallation, or operation).

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

)

duals authorized to approve dispositions and corrective action.

These reports shall clearly and positively identify the item, describe the nature of nonconformance and give no recommendation for disposition and for corrective action.

15.2.2.1 The procedure for material receiving and inspection (QCP 100h.06) defines the action to be taken when defective items are received.

Source inspection nonconformances shall be reported on the Vendor Inspection Report in accordance with the procedure for quality con-trol inspection (QCP 1004.08).

15.2.3 Recommended dispositions shall be approved by the Plant Superinten

• tendent prior to implementation.

All dispositions involving deci-

• 1 sions to "uce-as-is" or " repair" shall be reviewed by the Manager

• h10.23 of Nuclear Services.

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 AP&L as required by the applicable purch. se order or contract.

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15.2.5 ne acceptability of rework or repair of materials, parts, components, 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. B e rework and repair inspection records shall be documented and chall 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 DOCUP!ENTATION 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.

LORRECTIVE ACTION I\\s) 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 authorities 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, detemine their cause, and take necessary corrective action to prevent their recurrence.

16.2.3 The cognizant 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 Manager of Nuclear Services evaluate the non-(]

conformance for final disposition.

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16.2.4 When vendors furnish products or services that do not conform to the requirements of the applicable purchase contract, the APSL 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 supplie r.

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 bidders list.

16.3 SIGNIFICANT NONCONFORMANCES 16.3.1 hhen discrepancies involve violations of the Technic ' Specifications or conditions which adversely affect, or could adversely affect, the safe operation of the station, a written abnormal occurrence report of the discrepancy shall be prepared by the plant safety committee and reviewed and approved by the plant Superintendent, the Manager of Nuclear Services, the Director of Power Production, the Senior Vice President (PTSE) and the chairman of the Safety Review Committee.

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16.3.1.1 Nonconformances of "significant consequence" include those noted U/

below:

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

2) Conditions that have caused the uncontrolled relense 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 maj or con-sequence.

Conditions adverse to quality other than 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 the Quality Assurance Engineer (Operations), where appropriate.

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QUALITY ASSURANCE RECORDS I

17.1 SCOPE 17.1.1 Qualfty-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 Administrative Assistant shall be responsible for the establish-ment, implementation and maintenance of the records management program to be used throughout the operational life of the plant.

17.2.2 The Administrative Assistant, under the technical guidance and review of the Quality Control Engineer, shall be responsible for ensuring that document retention requirements comply with applicable codes and regulations.

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17.2.3 The Quality Assurance Engineer (Operations) shall periodically audit quality assurance records and records filing and storage procedures to assure that the records management program is being properly implemented.

17.3 DOCUMENT RETENTION 17.3.1 Lifetime Quality Assurance Records 17.3.1.1 Lifetime records are defited as those which meet one or more of the following criteria (QCP 1004.25).

• 2 I ', Those which would be of significant value in demonstrating capa-bility for safe operation.

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

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

4) Those 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 (V) of the particular item while it is installed in the plant or stored for future use, as prescribed in the procedure for document reten-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 following 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 inspaction.

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 perieds 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 periods are described in the procedure for document retention and disposition (QCP 1004.25).

• 2 17.4 PRODUCTION DEPARTMENT 17.4.1 Production Department personnel that perform work on the plant in the areas of design, procurement, maintenance, modification, testing and provision of special nuclear materials shall document such work and forward the records to the Administrative Asristant.

17.4.2 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 APSL (QCP 1004.04).

17.4.3 When approved for receipt by the Quality Control Engineer, such records shall be transmitted to the Administrative Assistant for filing and storage.

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17.5 STORAGE

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

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

2) Made safe and secure from theft, vandalism and unauthorized use.

3) Adequately protected against environmental deterioration.

4) Adequately protected against fire.

17.5.1.1 The following features or suitable alternatives shall be incorporated in the design 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).

4) Sealant applied over walls as a moisture or condensation

/7 barrier.

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

6) Foundation sealant and provision for drainage.

7) Forced-air circulation with filter system.

8) Dry chemical or gas fire protect ion system.

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 filic and other special processed records, humidity and tempert.ture controls shall be provided to maintain an environ-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.

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2 17.5.2 Plant storage systems shall provide for the accurate retrieval of

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information within undue delay and shall be sufficient to control

V and account for records removed from the storage facility.

17.6 RECORDS INLEXING AND RECEIPT CONTROL 17.6.1 Indexing methods and systems for quality-related records are deline-ated in the procedure for plant records management (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 enforcement of receipt control requirements shall be the responsibility of the Administrative Assistant.

17.7 FINAL DISPOSITION O

17.7.1 Final disposition of quality-related records is controlled by the C/

procedure for document retention and disposition (QCP 1004.25) which

• 2 requires that the Administrative Assistant periodically purge the non-permanent files of records retained past their authorized reten-tion date.

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18. AUDITS 18.1 SCOPE

(

) 18.1.1 Audits shall be performed to determine the complia effectiveness of, applicable quality assurance program nce with, and shall be performed on a planned and periodic basis in a s.

The audits with the audit schedule.

ccordance Supplementary audits shall be performed as required.

18.2 GENERAL 18.2.1 Reviews and audits of records, station operation procurement, construction, maintenance, modification, design activities, for conformance to the eighteen criteria of 10 CFR 50

, examination

• 1 and other quality-related activities shall be perform d b

, Appendix B,

• h10.1h lity Assurance Organization to assess the adequacy e

y the Qua-Assurance Program and to verify compliance with est bli of the Quality program requirements.

shed quality a

lity Assurance Procedures for audits (ANO-14; ANO 17These activ

ANO-18).

18.2.2 Results of these reviews and audits shall be rec distributed to responsible management as outlined iorded, reported, and 18.6.

n the Subsection 18.2.3 The Manager of Quality Assurance shall perform sch d l vendors and service contractors a e u ed audits of their quality assurance programs,s required to verify and evaluate the Quality Assurance Program and procurementassure tha G

all aspects of Manager of Quality Assurance also verifies that requirements. The ors review and audit the quality assurance programsvendors and contract-ers.

This activity is referenced in the procedure foof their suppli-audits.

(ANO-3).

r surveillance 18.3 IN-PLANT REVIEW AND CURVEILLANCE 18.3.1 In addition to Quality Assurance audits ed by the Quality Control Engineer. view and surveillance of qua shall be conduct-18.3.2 The program shall include:

1)

Document and record review.

2)

Surveillance and evaluation of compliance with cedures, instructions, methods, and other requireme t established pro-n s.

3)

Investigation of nonconformance and other unusual events.

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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 Manager of Nuclear Services.

18.4 AUDIT PERSONNEL 18.4.1 The Quality Assurance Section, including the Quality Assurance Engineer (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 capabili ty.

13.4.2 Audit personnel are provided appropriate training to assure their com-potence for performing the required audits. Proficiency of audit per-sonnel 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 instructions.

3) Participation in training or orientation programs.

18.5 DOCUMENTATION 18.5.1 Audit Reports 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) Description of audit scope and date.

2)

Identification of the auditor (s).

3) A summary of audit results.

4) Details of nonconformances or programmatic deficiencies.

5) Recommendations for correcting nonconformances or improving the Quality Assurance Program as appropriate.

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The findings of audits shall be reported to the Manager of Quality Assurance, the Manager of the area concerned and to the Senior Vice President, Production, Transmission and Engineering if officer level action is required. APSL requires written reports from each organization on the measures taken to correct deficiencies and prevent recurrence. Appropriate follow-up including re-audits is made to determine that nonconformances are effectively corrected and that the corrective action precludes repetitive occurrences.

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.

3) Reports of re-audit activities, f3

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g-S RESPONSES TO NRC QUESTIONS N)

Listed below are NRC questions that have been responded to by Revision to APL-TOP-1, Quality Assurance Manual for Operations.

Question Pajg,e Section Revision 410.1 Policy Statement 1

410.2 1

1.2 1

410.3 1

Foreword - Policy Statement 1

410.4 1

Foreword - 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

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