ML20077A409

Rev 6 to QA Manual Operations

ML20077A409
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/10/1983
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20077A397	List: 0CAN068313, Forwards Rev 6 to QA Program Topical Rept, QA Manual Operations. Rev Deletes Procedural Refs Throughout Text & Changes Organization of Energy Supply Dept ML20077A409
References
NUDOCS 8307220314
Download: ML20077A409 (148)

Text

- .

s .

s, f g

l .. .. -

~- r .

Copy No.

O . . .

u-

~

,, e

\. q XGUALITY ASSURANCE

,s

• N

s. #

e m.

MANUAL l

O=

OPERATIONS

~

s' M

o 6

o 4

Y" 1 . Annansas P.OWER & LIGHT HELPING BUILD ARKANSAS .

O

' 1307220314 830610

,. 'PDR ADOCK 05000 l ,+ P l

___..________.1_____..__.-_.____. . . _ _ , _ , , _ _ . - - _ _ _ _ , _ _ . , _ _ _ . . . , _ _ _ . - - . _ _ _ , . . , _ _ , _ , - _ _ . . _ _ _ _ _ _ .

.g ,

4 I

I 4 , I I

f l j -

l I

Q 'I 1

I I

j>,

i >

I l

• 4 l .

I <

j

1 l  ;

b ~"

s.

L*~

.

3 I I e

' ' l I .

' l

, I e s .

I I

,'a l l

l ,.

l 1-iQ-1 A 4,' il '

(

TOPICAL REPORT l

IREV. 6 I

I y I

1 "t ; IDATE 6/10/83 1 , p,, ,l ..I APPP,0 VAL SIGNATURES &) o I l '+ r I ' ' le^ l I I C 'l l l I N . . , . _ _ _ , _ . , - - - - _ . - - _ L;-__._.-,-..-.---.-- - - - l ' l l 1 l TABLE OF CONTENTS l l O .I i Section Subject l i , l Tab h Rev. l. , 1- -l  : l l APPROVAL COVERSHEET l ' _l TABLE OF CONTENTS TC-1 6 l  ! l TC-2 6- l l TC-3 6 ] l TC-4 6 l ,

l TC-5 6 l

l .TC-6 6 l . { l POLICY STATEMENT A-1 6 l l l A-2 6 l i INTRODUCTION B-1 6 l l B-2 6 l ) B-3 6 i l l B-4 6 l~ I B-5 6 l TERMS AND DEFINITIONS l C-1 6 l I C-2 6 I l 1 l C-3 6 l I l-l C-4 6 l l C-5 6 l ' l C-6 6 l l C-7 6 l C-8 6 l C-9 6 l l C-10 6 l 1. 0 ORGANIZATION 1 1-1 6 l l 1-2 6 l l 1-3 6 l l 1-4 6 l l 1-5 6 l- 'l ' I l l l l l 1 A l TOPICAL REPORT 6 lREV. l P ] lDATE 6/10/83 l l & 1 SECTION: TABLE OF CONTENTS lPAGE TC-1 l ! I L i i I

I I I l

l i i I i 1-6 6 l l 1-7 6 l . I 1-8 6 l l 1-9 6 l 1 1-10 6 l l l-11 6 l 1 1-12 6 l l 1-13 6 l l 1-14 6 l l 1-15 6 l l 1-16 6 l l 1-17 6 l l 1-18 6 l 1-19 6 l l 1-20 6 l l 1-21 6 l l 1-22 6 l l 2.0 QUALITY ASSURANCE PROGRAM 2 2-1 6 l l 2-2 6 l l 2-3 6 l l 2-4 6 l l 2-5 6 l l 2-6 6 l l 2-7 6 l l 3.0 DESIGN CONTROL 3 3-1 6 l l 3-2 6 l~ l 3-3 6 l l 3-4 6 l l 3-5 6 I l 4.0 PROCUREMENT DOCUMENT 4 4-1 6 I CONTROL f 4-2 6 l l 4-3 6 l l ' l l I I I 'i I G ,V ' 1 I I l A I TOPICAL REPORT IREV. 6 l l P 1 IDATE 6/10/83 I I & 1 SECTION: TABLE OF CONTENTS IPAGE TC-2 l l L I i l l l I I .I I I l l 5.0 INSTRUCTIONS, PROCEDURES 5 5-1 6 l - I AND DRAWINGS 5-2 6 I 5-3 6 l 5-4 6 l l 6.0 DOCUMENT CONTROL 6 6-1 6 l I i l 6-2 6 l l 6-3 6 l

7. 0 l CONTROL OF PURCHASED 7 7-1 6 l

l MATERIAL, EQUIPMENT AND 7-2 6 l SERVICES 7-3 6 I l 7-4 6 l ! l 7-5 , 6 l

l 7-6 6 l 8.0 l IDENTIFICATION AND CONTROL 8 8-1 6 l

l OF MATERIALS, PARTS AND 8-2 6 l COMPONENTS 8-3 6 l 9. 0 CONTROL OF SPECIAL l 9 9-1 6 l l PROCESSES 9-2 6' l l 9-3 6 l 10.0 INSPECTION . 10 10-1 6 l l 10-2 6 l l 10-3 6 l l l 10-4 6 l l 10-5 6 l l 11.0 TEST CONTROL 11 11-1 6 l l 11-2 6 l~ l 11-3 6 l 11-4 6 l

l 11-5 6 l 12.0 l CONTROL 0F MEASURING AND 12 12-1 6 l

l TEST EQUIPMENT 12-2 6 l l 12-3 6 l l 12-4 ' 6 l l I I I -l l l 1 Q V l l I I l A  ! TOPICAL REPORT 6 lREV. l l P ' l lDATE 6/10/83 l l & l SECTION: TABLE OF CONTENTS IPAGE TC-3 l l L l ' l l l l I I l l I I l 13.0 HANDLING, STORAGE AND 13 13-1 6 l I cs SHIPPING 13-2 6 I 13-3 6 l l 13-4 6 l l 13-5 6 l 14.0 INSPECTION, TEST AND l 14 14-1 6 l l OPERATING STATUS 14-2 6 l l 14-3 6 l l 14-4 6 l 14-5 6 l 15.0 NONCONFORMING MATERIAL, l 15 15-1 6 l l PARTS OR COMPONENTS 15-2 , 6 l l 15-3 6 l l 15-4 6 l l 16.0 CORRECTIVE ACTION 16 16-1 6 l 16-2 6 l l 16-3 6 l l 16-4 6 l c l 17.0 QUALITY ASSURANCE RECORDS 17 17-1 6 l (.) 17-2 6 l l 17-3 6 l l 17-4 6 l 17-5 6 l 17-6 6 l 18.0 AUDITS l 18 18-1 6 l l 18-2 6 l l 18-3 6 l l 18-4 6 l 18-5 6 l l 18-6 6 l l l l I l 1 l ~ l l l l l l 1 l l I I (O) l A l TOPICAL REPORT I lREV. 6 I l l P I lDATE 6/10/83 l l & 1 SECTION: TABLE OF CONTENTS lPAGE TC-4 I I L l l 1 I I I I l I l l l FIGURES l Number Title Tab Page Rev. 1 AP&L Corporate l 19 F-1 6 l l Organization l 2 AP&L Corporate Services l 19 F-2 6 l l 3 AP&L Energy Supply 19 F-3 6 l l Organization 4 AP&L Quality Assurance l l 19 F-4 6 l l Organization 5 AP&L Nuclear Plant l l 19 F-5 6 l l Organization 6 AP&L Nuclear Plant l l 19 F-6 6 l l Organization (Plant l Operations and Main- l l l tenance) l 7 AP&L Nuclear Plant 19 F-7 6 l l Organization (Plant f3 l Engineering and Technical l l 'd Support) l l l 8 AP&L Nuclear Plant 19 F-8 6 l Organization (Plant l l l Administrative Services) l l I l l l I I I-1 I I I I I I I l I I I I I I I I I I I I . I I I I I I I I I ('S 'v' I l l l l A I TOPICAL REPORT 6 lREV. l P l I lDATE 6/10/83 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-5 I I L l l l l 1 I l I I I I l Ti.al.ES l l O -I i Number l i Title Tab. M Rev. l 1 AP&L Exceptions / Inter-l 19 T1-1 6 l l pretations of Regulatory T1-2 6 l l Guides and ANSI Standards T1-3 6 I T1-4 ] 6 I l T1-5 6 l l T1-6. 6 l l T1-7 6 l l T1-8 6 I l T1-9 . 6 l l T1-10 6 l l T1-11 6 l l T1-12 6 I l T1-13 6 l l T1-14 6 I l T1-15 6 l l 2 Quality Assurance 19 T2-1 6 l l Procedures Matrix l 3 Quality Program Policies, l 19 T3-1 6 l l Procedures and Instruc- T3-2 6 , l tion Manuals List l t I i l l 1 1 I I I-1 I I ' I l I ' I I I l 1 I I I I I I ~ .I I l I I . l . I I I I l l I I I l I Q l l .A l I TOPICAL REPORT I IREV. 6 I I l i P I lDATE 6/10/83 I i & I l SECTION: TABLE OF CONTENTS IPAGE TC-6 l l L I l l l 1 I I t l l I I l ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l I QUALITY ASSURANCE PROGRAM FOR OPERATION I l It is the policy of the Arkansas Power & Light Company (AP&L), from the l highest level of corporate management, that its Quality Assurance Program l l for Operation meet the requirements of the Code of Federal Regulations, l 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, l repair and modifications, and inservice inspection of AP&L Nuclear l Plants. The program shall also meet the requirements of the.ASME Boiler l and Pressure Vessel Codes with respect to items constructed, repaired or l replaced to Code requirements. l l l 1 - l l Under the Program the Energy Supply Sr. Vice President, is the final l lmanagementauthorityresponsibleforassuringthatthispolicystatement l and the Quality Assurance Program are implemented within AP&L. l The l Nuclear Operations Vice President and each Energy Supply Director is l responsible for the procedural implementation of the program within his j assigned area. The plant's General Manager is responsible for the daily l implementation of the Program's procedural requirements at the plant. O i l l i l l The Quality Assurance Manager is responsible for establishing the l Program. The Quality Assurance Manager, Energy Supply Services Director l and the Energy Supply Sr. Vice President are responsible for approval of l the Program. I I ~ Quality Assurance personnel reporting to the Quality Assurance Manager l are responsible for auditing the Program as necessary and monitoring l activities required by the Program to assure compliance with its , l requirements. l l l l l l l The Quality Assurance Manager is to provide for annual review of the l adequacy and overall effectiveness of the Program. Any defects in the i 1 l I l l l 1 ! l I l I l Q l A I l TOPICAL REPORT I I lREV. 6 l l P  ! l0 ATE 6/10/83 l l & l SECTION: STATEMENT OF POLICY lPAGE A-1 l l L i l l l 1 _ _ _ . - 1 1 1 I I I I l implementation of either this policy or the Program that are revealed l ' during the review are to be reported to appropriate levels of management 3 _ l together with appropriate recommendations. l I I i 1 - 1 I Implementation of this policy is necessary in order to achieve the l lreliabilityandsafetyrequiredatourNuclearPlants. Each person I involved in activities concerning our Nuclear Plants is to be responsible l l for assuring quality in his own work, and for compliance with the i requirements of the Program. The Quality Assurance Program policies, I l manuals,andproceduresaremandatoryrequirementswhichmustbe i implemented and enforced by all responsible organizations and l I ' individuals. l l l 1 I I I I W. Cavanaugh, III. I Energy Supply Sr. Vice President I g l l Date: I O i l I i l I I I I I .I I I I I I I I I I l-1 I I I I l l I l l I I I I l I I I l I l . I I I I I I I I l -O d I i A I I I I TOPICAL REPORT (REV. 6 l l P l lDATE 6/10/83 l l & 1 SECTION: STATEMENT OF POLICY lPAGE A-2 l I L i I I l l l 1 I I I l I INTRODUCTION ' ! l (ys I . I l l This TOPICAL report (manual) describes the AP&L quality program applied l lbyAP&Ltoitsoperatingnuclearplants. This manual is intended to l serve as a standard reference for final safety analysis reports to l , l fulfill the requirements of the Standard Format and Contents of Safety l Analysis Reports for Nuclear. Power Plants, Section 17, published by the l Nuclear Regulatory Commission. l l The objective of this program is to control those phases, as applicable, I l for the design, procurement, manufacture and fabrication, installation, l operation, testing, refueling, repair, maintenance or modification to l existing safety related (Q-List) structures, systems and components that l l prevent or mitigate the consequences of a postulated accident which may -l cause undue risk to the health and safety of the public. The program is l l an outgrowth of the principle that quality assurance emanates from each l individual contributor and that management is responsible for creating an l awareness of quality. l o i , The AP&L quality program is designed to comply with the requirements of  ! l 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants l I , and Fuel Reprocessing Plants, and to comply with the quality assurance l requirements of the ASME Boiler and Pressure Vessel Code,Section XI for l i repair, replacement, and inservice inspection of items covered by the l Code and Licensing commitments. l l l-I l l In general, the AP&L quality program complies with NRC positions l contained in the following regulatory guides, subject to specific l exceptions noted in the body of this manual, Table 1 of this manual or in l the final safety analysis reports: I I I l l l l l I -l-I l I l 1 l l (~' l l l I l A l TOPICAL REPORT 6 lREV. l l P l lDATE 6/10/83 l l & l SECTION: INTRODUCTION lPAGE B-1 l l L l l l l l l 1 l l l l l 1.8, rev. 1-R Personnel Selection and Training (5/77) l q# l 1.28, rev. 1 QA Program Requirements-Design and . l Construction (3/78) l 1.30 QA Requirements for Installation, l l Inspection and Testing of Instrumentation l and Electrical Equipment (8/72) i 1.33, rev. 2 QA Program Requirements-Operations (2/78) l 1.37 QA Requirements For Cleaning of Fluid l Systems and Associated Components of Water l l Cooled Nuclear Power Plants (3/73) 1.38, rev. 2 l l QA Requirements for Packaging, Shipping, l l Receiving, Storage and Handling of Items l l For Water Cooled Nuclear Power Plants l l (5/77) l 1.39, rev. 2 Housekeeping Requirements For Water Cooled l l Nuclear Ppwer Plants (9/77) l 1.58, rev. 1 Qualification of Nuclear Power Plant l Inspection, Examination and Testing l IsI V l I Personnel (9/80) l g 1.64, rev. 2 QA Requirements For the Design of Nuclear l g l Power Plants (6/76) l 1.74 QA Terms and Definitions (2/74) c l 1.88, rev. 2 Collection, Storage, and Maintenance of l l Nuclear Power Plant Quality Assurance l Records (10/76) l 1.94, rev. 1 QA Requirements for Installation, l l Inspection and Testing of Structured l Concrete and Structural Steel During the l l Construction Phase of Nuclear Power Plants l I l (4/76) I ' I l 1.116, rev. 0-R QA Requirements For Installation, l Inspection and Testing of Mechanical l Equipment and Services (5/77) l . l i l l l I I I ^ (  : l l '" I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l & l SECTION: INTRODUCTION lPAGE B-2 l i I L 1 l l l l I I _ ._ I 1 l 1- . 1.123, rev. 1 l l QA Requirements For Control.of Procurement 1 p of Items and Services For Nuclear Power i l ~ Plants (7/77) _ l 4 1.146 Qualification of Quality Assurance Program

l l

Audit Personnel For Nuclear Power Plants I

(8/80)

! l-I [ l-Baseduponcompliancetothese.regulatoryguides,theAP&Lquality l program also complies with the following American National Standard l I j l Institute (ANSI)standardssubjecttoexceptionsnotedinthebodyof l l this manual, Table 1 of this manual or in the final safety analysis l reports: l , l 1 l l'N45.2-1977 Quality Assurance Program Requirements for Nuclear j l Facilities l -l i 1 I , 4 l l N45.2.1-1973 _l Cleaning of Fluid Systems and Associated I l Components During the Construction Phase of I ~ l Nuclear Power Plants

O l i

l i l

-l -N45.2.2-1972 Packaging, Shipping, Receiving, Storage and l l

Handling of Items for Nuclear Power Plants (During - - l the Construction Phase) l 1 1 ' l I l l ! l N45.2.3-1973 Housekeeping During the Construction Phase'of l ~ Nuclear Power Plants I l N45.2.4-1972 Supplementary Quality Assurance Requirements for i Installation, Inspection and Testing of I Instrumentation and Electric Equipment During the l l Construction of Nuclear Power Generating Stations l , I l -l ' I =l . I I , I I I I ' I I O V l i I I l I A I TOPICAL REPORT IREV. 6 l -l P l lDATE 6/10/83 1 I & 1 SECTION: INTRODUCTION , l IPAGE B-3 l l L l l l i 'l i I ___l I I I I l N45.2.5-1974 Supplementary Quality Assurance Requirements for l q Installation and Testing of Structural Concrete l V . l and Structural Steel During the Construction Phase l l of Nuclear Power Plants . l l l N45.2.6-1978 Qualifications of Inspection, Examination and l Testing Personnel for Nuclear Power Plants l l l l l l l N45.2.8-1975 Supplementary Quality Assurance Requirements for l l Installation, Inspection and Testing of Mechanical l Equipment and System for the Construction Phase of l l Nuclear Power Plants l l 1 N45.2.9-1974 Requirements for Collection, Storage and l Maintenance of Quality Assurance Records for l Nuclear Power Plants l l l N45.2.10-1973 Quality Assurance Terms and Definitions l 0> lN45.2.11-1974 , Quality Assurance Requirements for the Design of l y l Nuclear Power Plants l 1 1 I I l N45.2.li.-1977 Requirements for Auditing of Quality Assurance l 'I Programs for Nuclear Power Plants l l N45.2.13-1976 Quality Assurance Requirements for Control of I i Procurement of Items and Services for Nuclear i Power Plants l l 1 lN45.2.23-1978 Qualification of Quality Assurance Program Audit l Personnel for Nuclear Facilities l l l l t i I l N18.1-1971 Selections and Training of Nuclear Power Plant l Personnel I g i l i l I 'N (O l l A l l TOPICAL REPORT I 6 I lREV. l P l l lDATE 6/10/83 l l & 1 SECTION: INTRODUCTION lPAGE B-4 l l L l l l l  ! I I l t . . - . . .- _~ . . . . . . . _ - . . . - _ . _ _ _ _ _ ..

I

' I ' I I i N18.7-1976 Administrative Controls and Quality Assurance for 1 I the Operational Phase of Nuclear Power Plants O I l . I i , l-The above requirements are implemented by controlling activities as. l described in'this manual and by prdcedures referenced in this manual. l I I I I I Definitions of terms applicable to the AP&L quality program are found in I I

the Terms and Definitions section of this manual.

l l l 1 I 1 1 'l I I ! I I - 1 I I I ! l .I l l l 1

1 I

1 . I I I l-l- 1 I !o l I l l I ^ l 1 l - 1 -l i I l I ! l- ' I I I i l I ! I -

1. L I

I I I I I I I I I I , I I I I I I I I I I . I I I l - 1 I I I C I d i I /, I i TOPICAL REPORT l IREV. 6 1 I l P l IDATE 6/10/83 l l & 1 SECTION: INTRODUCTION lPAGE B-5 l I L I I I -l 1 I I I l 1 l l TERMS AND DEFINITIONS l i n I y l l l The terms used in this manual follow the definitions provided in l lANSIN45.2.10-1973..supplementedbyadditionaltermsanddefinitions l applicable to this report. I I I I I I Approval - An act of endorsing or adding positive authorization, or both. I l l l l l Appurtenance - A part that is attached to a component which h.as been I completed. t I i lAs-BuiltData-Documenteddatathatdescribestheconditionactually l achieved in a product. l l l l 1 I l Asseinbly - A combination of subassemblies or components, or both, fitted l together to form a unit. I I ,I Audit - An activity to determine through investigation, the adequacy of g> I and adherence to, established procedures, instructions, specifications, I ( l codes, and standards or other applicable contractual and licensing l requirements, and the effectiveness of implementation. j i l I l Bid Evaluation - A formal evaluation of all proposals received in i response to an inquiry to determine the vendor to whoni the purchase order l will be awarded. l l l l.- 1 I l Certificate of Conformance - A written statement, signed by a qualified l party, certifying that items or services comply with specific l requirements. l I I I l l Certificate of Compliance - A written statement, signed by a qualified l party, attesting that the items or services are in accordance with [ specified requirements and accompanied by additional information to l substantiate the statement. I g I I I I O i l A i I TOPICAL REPORT i IREV. 6 i I P I l IDATE 6/10/83 l l & I SECTION: TERMS AND DEFINITIONS lPAGE C-1 l l L l l I l __ i . I l I I I I l Certified Test Report - A written and signed document, approved by a l I m qualified party, that contains sufficient data and information to verify I Q . l I the actual properties of items and the actual results of all required I l tests. ,I I ,I l Certification-Theactionofdetermining,verifyingandattesting,in I writing, to the qualifications of personnel or material. l 'l i I i l Characteristic - Any property or attribute of an item, proces.s, or l service that is distinct, describable, and measurable, as conforming or l nonconforming to specified quality requirements. Quality characteristics l are generally identified in specifications and drawings which describe l l the item, process, or service. l 1 l-I . l l Checks - The tests, measurements, verifcations or controls placed on an l activity by means of investigations, comparisons, or examinations, to l determine satisfactory conditions, accuracy, safety or performance. l -l l l 1 I l Cleanness - A state of being clean in accordance with predetermined b standards, and usually implies free' dom from dirt, scale, heavy rust, oil l or other contaminating impurities. l l ' I I I l Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by l l a legally constituted agency of a Municipality or State of the United l States, or Canadian Province, or regularly employed by an Authorized l lInspectionAgencyandhavingauthorizedjurisdictionatthesiteof l manufacture for installation, repair, modification, and in service l inspection of ASME Boiler and Presssure Vessel items designated l safety-related. I I I I I l Commercial Grade - Those items contained in Q systems and equipment that l lare: (1) not subject to design or specification requirements unique to 'l nuclear facilities or activities; (2) used in application other than l l l 1 I I I I I I O i l A i l TOPICAL REPORT lREV. 6 l P l l lDATE 6/10/83 l l & 1 SECTION: TERMS AND DEFINITIONS lPAGE C-2 l l L l l l l l l 1 .I I -l C I l' nuclear facilities.or activities; (3) to be ordered on the basis of l specifications set forth in manufacturer's published product description; I and (4) not associated with a loss of safety function. I I I I I l- l Component - A piece of equipment such as a vessel, piping, pump, valve or l l core support structure, which will be combined with other components to ' l form an assembly. l

I I

i I . I I Contaminants - Foreign materials such as mill scale, dirt, 01.1, chemicals ). l landanymatterthanrendersafluid,solidorsurfaceimpureandunclean I .I according to preset standards of acceptable cleanness. l l I I l - I ! l Contractor - Any organization under contract .for furnishing items or I . services. It includes 'the terms Vendor, Supplier, Subcontractor, l Fabricator and sub-tier levels.of these where appropriate. .l l 1 l , I I j l Defective Material - A material or component which has one or more l l

g characteristics that do not comply with specified requirements, l g

LO ! l Deviation-Anonconformanceordeparture.ofacharacteristicfrom l I specified requirements. I 1 l' l I I I Documentation - Any written or pictorial information describing, I defining, specifying, reporting or certifying activities, requirements,

I procedures, or results.

1 - I l- - 1 I I Examination - An element of inspection consisting of investigation of I l materials,-components,suppliesorservicestodetermineconformanceto -l those specified requirements which can be determined by such I investigation. Examination is usually nondestructive and includes simple

'- I . physical manipulation, gaging, and measurement.

l I 1 1 4 'l I l Dndling - An act of physically moving items by hand or mec'ianical means, I

z. lbutnutincluding-transportmodes.

l l 1 I I Q- l l A I l TOPICAL REPORT ~ l lREV. 6 I l

I P I lDATE 6/10/83 l l & 1 SECTION

TERMS AND DEFINITIONS (PAGE C-3 1 2

i L l l l 1 I I l l-1 I . I 4 l Inquiry - A document that contains the necessary information for a vendor l I to make a proposal. ~ An inquiry may include specifications pertaining to O - i l the equipment, materials, or services proposed to be procured. I i l I l l Inspector (Owner's) - A qualified inspector employed by the Owner whose l I 1 1 duties'. include the verification of quality related activities or I I i l ' installations or.both. l l l l . l l Inspection - A phase of quality control which by means of examination, l 1 observation or measurement determines the conformance of materials, -

-l supplies, components, parts, appurtenances, systems, processes or l

. structures to predetermined quality requirements. - 1 I l Item - Any level of unit assembly, including structure, system, l subsystem, subassembly, component, part or material. l l I I  ! 1 I ' I l . Job Order (J.O.) The Job Order is the document used for identifying and l

I I

administratively controlling the work effort on station equipment and I ! systems. It identifies applicable procedures.and drawings; documents .I - l l I 1 l reviews, approvals and results of inspections and tests; and provides a I l l mechanism for planning, scheduling and authorizing work. l 1 l' l I t . l l Manufacturer - One who constructs any class of component, part, or l

appurtenance to meet prescribed design requirements.

I I ~ Material - A substance or combination of substances forming-components,

l parts, pieces and equipment items. (Intended to include such as l machinery, castings, liquids, formed steel shapes, aggregates, and i

l cement.) l i i ' l l l Modification - A planned change in plant design or operation and l accomplished-in accordance with the requirements and limitations of l ; applicable codes, standards, specifications, licenses and predetermined l I safety restrictions. . I I l i I l 'Q- l-

l. A 1

l TOPICAL REPORT I lREV. 6 l l r l P ' l lDATE 6/10/83 l i l & l.SECTION: TERMS AND DEFINITIONS I lPAGE C-4 I -l L I I I I i 1 I t - , - .--.y-= .w,,, . . , ,.v.,w,-w,-3.-c,,,,,,,r,-,,m-, ee4-,,,,,,.,4,,-, -w-w,-=w,,-w,,w-,,,,#-=,...m,,-,~.,,..-.ww._,,.me-+,-t-ef.,-ww----wy,w-----m-,,e--* l l I I I Nonconformance - A deficiency in characteristic, document, or procedure l p which renders the quality of an item unacceptable or indeterminate. V _ l Examples of nonconformance include: physical defects, test failures, l incorrect or inadequate documentation, or deviation from prescribed I processing, inspection or test procedures. l l l l l 1 Ob.iective Evidence - Any statement of fact, information, or record, I either quantitative or qualitative, pertaining to the quality of an item l or service based on observations, measurements, or tests which can be l l l verified. I ' I l Operation - The' total of administrative, maintenance and monitor l activities necessary to sustain the power generating capabilities of the I plant after initial start-up. l l l Owner - The person, group, company or corporation who will have or has l title to the facility or installation under construction. I I I I I l Package - A wrapping or container including its contents of materials or l equipment. 1 I Packaged Unit - An assembly of items and parts which can be disassembled I without destroying the integrity of the individual parts. I I I I I I Part - An item which has work performed on it and which is attached to I ~ and becomes part of a component before completion of the component. l l Plant - The equiment, piping, structures, buildings and property that I comprise an installation or facility. I I I I I l Procedure - A document that specifies or describes how an activity is to I be performed. It may include methods to be employed, equipment or l materials to be used and sequence of operations. , l l l l 1 I l l I O' i l A i l TOPICAL REPORT i 6 i IREV. l l P l lDATE 6/10/83 l l & 1 SECTION: TERMS AND DEFINITIONS lPAGE C-5 l l L I l l l 1 , I l I I I I l Procurement Documents - Contractually binding documents that identify and l m define the requirements that items or services must meet in order to be I . I considered acceptable by f.he purchaser. l. I I I l l Project - A planned series of activities including all actions necessary l ltoprovide, utilize,andmaintainafacilityorportionthereof. 1 l I Proposal - A bid, usually written by a vendor in response to an inquiry, I which provides the issuing party with the vendor's proposed c.ompliance to l !theinquiryandthecost. I I I I Purchase Order (or Contract) - A document authorizing a vendor to provide l equipment, material or services in accordance with stated terms and l conditions. l l Purchaser - The organization or organizations responsible for issuance l and administration of a contract, subcontract, or purchase order. l l I l I l l Q-List - A list which specifically identifies those structures, systems O i g and components whose failure could cause an uncontrolled release of l i g l radioactivity, or those essential for the safe shutdown and immediate and l llong-termoperationfollowingaLossofCoolantAccident. 1 l I Qualification (Personnel) - The characteristics or abilities gained l through training or experience or both that enable an individual to i perform a required function. ' ~ l I Qualified Party - A person or organization competent and recognized as l knowlegeable to perform certain functions. l l l 1 I l Qualified Procedure - A procedure which incorporates all applicable codes l and standards, manufacturer's parameters, and engineering specifications l and has been proven adequate for its intended purpose. , l I I I I I I I I f~N I O l A l' l TOPICAL REPORT-I 6 I lREV. l l P l lDATE 6/10/83 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-6 l l L l l l 1 I I I I I I l l Qualified Vendor List - A listing of vendors having quality assurance l I r l programs consistent with the requirements of applicable portions ~of h .l 10CFR50, Appendix 8. l l I l 1 I I l Quality Assurance - All those planned and systematic actions necessary to l lprovideadequateconfidencethatanitemorafacilitywillperform l satisfactorily in service. l l 1 1 l l Quality Control - Those quality assurance actions which provide a means l to control and measure the characteristics of an item, process, or i facility to established requirements. l l l 1 - l l Receiving - Taking delivery of an item at a designated location. l l l l l l Repair - The process of restoring a nonconforming characteristic to a l lconditionsuchthatthecapabilityofanitemtofunctionreliablyand l safely is unimpaired, even though that item still may not conform to the l loriginalrequirement. Report - Something (document) that gives information for record purposes. I I Review - An element of inspection to determine conformance to specified l requirements, which can be determined by examination of documents and l activities. 1 I l ~ Rework - The process by which a nonconforming item is made to conform to l l a prior specified requirement by completion, remachining, reassembling or l other corrective means. ,1 1 I I Safety-Related - The term " safety-related", as used in this program, l refers to those materials, parts, components, systems, structures and l consumeable items classified as "Q" and so identified on the Q-list , l applicable to each nuclear plant. , l l 1 I I l I l l l Q l A i TOPICAL REPORT I 6 I l lREV. l P l l lDATE 6/10/83 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-7 l l L l l l l l _. I I I I l l l Source Surveillance - A review, observation, or inspection for the i p_ lpurposeofverifyingthatanactionhasbeenaccomplishedasspecifiedat l the location of material procurement or manufacture. l-1 I I I l Specification - A concise staterrent of a set of requirements to be l satisfied by a product, material or process indicating, whenever l appropriate, the procedure by means of which it may be determined whether l the requirements given are satisfied. I I Standard - The result of a particular standardization effort approved by l a recognized authority. l l l l 1 l Storage - The act of holding items at the construction site or in an area l other than its permanent location in the plant. I l l Subsystem - A group of assemblies or components or both combined to l performed a single function. l 1 I i l l q l Surveillance - The continuing analysis and evaluation of records, methods I U and procedures, including the act of verification, to assure conformance l with technical requirements. l 1 I l l I l System - A group of subsystems united by some interaction or I interdependence, performing many duties but functioning as a single unit. I g l I 1 System Performance Test - A test performed on a completed system I including electric, instrumentation, controls, fluid and mechanical I subsystems under normal or simulated normal process conditions such as l temperature, flow, level, and pressure. I I I I I l Testing - The determination or verification of the capability of an item l to meet specified requirements by subjecting the item to a set of I physical, chemical, environmental or operating conditions. . l l l l l l l l l ! 1 I I O I 1 I l l l A l TOPICAL REPORT IREV. 6 l l P l l & lDATE 6/10/83 l l 1 SECTION: TERMS AND DEFINITIONS l IPAGE C-8  ! l L I I I l l l 1._ - I I I I . I I Titles - Titles of individuals, such as Quality Assurance Manager, when I used in the~ TOPICAL report assigns the responsibility of' performing the I requirement to the noted individual or his appointed designee. I I I I I l Ransit - The state of being conveyed or transported from one place to l' I another. I I l 'Trans'it Carrier '(Open) - Trucks, trailers, railroa'd cars, barges,

1. aircraft or ships which do not afford items protection from the l l-environment.

l lTransitCarrier(Closed)-Trucks, trailers,railroadcars, barges,. I aircraft or. ships which provide protection of items from the environment I by nature of their closed design. I I lUse-As-Is-Adispositionwhichmaybeimposedforanonconformancewhen I it can be established that the discrepancy will result in no adverse I conditions and that the item under consideration will continue to meet-l all engineering functional requirements including performance, l I maintainability, fit and safety. l l l 'I

Vendor'- Any organization under contract for furnishing items or l services. It includes the terms Contractor, Subcontractor, Supplier, l I

fFabricatorand.sub-tierlevelsofthesewhereappropriate. l . l ~ l Verification - An act of confirming, substantiating and assuring that 'an - t I activity or condition has been implemented in conformance with the i specifled requirements. I I ( Work Instructions - Written instructions used to transmit detailed I I infomation on the specific measures necessary to comply with the 1 [ requirements,of quality assurance procedures or any complex or difficult l '- quality-related task. ! , I I I j< l' I l l l 1 O i- i i ' l A I TOPICAL REPORT 6 lREV. l l P l lDATE 6/10/83 1

i. 1 & 1 SECTION: TERMS AND DEFINITIONS lPAGE C-9 l I L l l l

t l l- , I i ___ ,. _ _ _ , . . - . _ . . . ~ . _ _ - - - - I I l - 1 l Work Package - A work package is a collection of applicable documents, I such as procedures, cleanliness control forms, inspection and test forms, ,I hold card forms, Ignition Source Permits, drawings, technical manuals, I letc.,neededtoperformthejob. I I I I I I I I I I I I I I I I l I l l I - l 1 I I I I I I I I I I I I I I I I I I I O I l l l l 1 1 I i 1 I I I I I I I I I I-1 I I I I I I I I I I I l l l l 1 I I I I . I I I I I I I I O I l A i I TOPICAL REPORT i IREV. 6 I i l 1 P l lDATE 6/10/83 I I & 1 SECTION: TERMS AND DEFINITIONS IPAGE C-10 l i L 1 I I I I I l I I I l l 1.0 ORGANIZATION I l I _ 1.1 SCOPE I I l-  ! l This section describes the AP&L organizational structure and l lresponsibilitiesforestablishingandexecutingtheQualityAssurance l Program for AP&L operational nuclear plants in compliance with 10CFR50, l Appendix B and applicable Regulatory Guides and ANSI Standards identified l in the Introduction. It also includes a description of the interfaces l l l with other organizations who may be delegated the work of establishing l- and executing portions of the Quality Assurance Program. The AP&L l lCorporateOrganizationrelevanttotheoperationofitsnuclearplantsis l shown in Figure 1. l l l l l l 1 1. 2 GENERAL RESPONSIBILITIES l l 1 1 I l The ultimate responsibilities for operational nuclear plants within AP&L, l l including Quality Assurance, lies with the Energy Supply Sen'ior Vice l President. He provides management assessment of the Quality Assurance l Program through review of QA Audit Reports and reports of NRC activities. I I ,I 1.2.2 l .l l lTheAdministrativeServicesVicePresidentisresponsibleforthe l l purchasing functions affecting plant operation as described in Subsection l ~ l1.3. ' ! I l I I I I I I l l I_ l l i l l l l r i I [ l . I I i l l I 1 l l O N/ l l l l l A l TOPICAL REPORT IREV. 6 l I P l lDATE 6/10/83 I I & I SECTION: 1.0 ORGANIZATION IPAGE 1-1 l l L l l l l l _ l I i i l 1 I l

I ~1.3i CORPORATE SERVICES I

I i-O i I

1. 3.1 I

i l' i i I l-j i Corporate Services is responsible for the procurement of materials, parts l l and components requested by Little-Rock General Office .(LRGO) personnelj- !. I and.for supporting the procurement activities at the plant. Procurement l , organization is noted in Figure 2. I l ' -l 4 1.3.2 l l l 'i

. The Nuclear Buyer reports to the Supervisor of Purchasing who reports to i

l ~ the Manager, Purchasing and Stores and is responsible.for the following l ldutiesandactivities: l 4 -l I ] l 1. Prepares purchase orders based upon receipt o'f reviewed and , I approved Purchase Requisitions. 1-

l L i l 1

l l 2. Performs the commercial interface functions between AP&L and l l contractors or vendors. l l

3. Assures that quality documentation prepared by Energy supply

'. I personnel are included in purchasing documents. l .; l , i I i I I

1 1. 4 ENERGY SUPPLY l

l } 1-I , I I l Energy Supply, headed by the Energy Supply Senior Vice President is l I l l responsible for all activities related to the operation of AP&L Nuclear l l Plants. These activities include as a minimum: design, modification, .l I [ l maintenance,inserviceinspectionandtest,operationandthose i additional activities discussed in Sections 2 through 18 of this manual. l l

Within Energy Supply, the Nuclear Operations and Energy Supply Service

. I organizations are involved in activities requiring execution of the l

i Quality Assurance Program (See Figure 3). l l l ! l l O " i l A i I TOPICAL REPORT i lREV. 6 I l l l l P l lDATE 6/10/83 I i l &_ l SECTION: 1.0 ORGANIZATION (PAGE 1-2 l ! l L i ' i l I I I l -,g ve-*'-WV t "*se War g-yne t w w-y-+w-w" --va'w-~+v-we m y-vw 6 re ' = ,- w wr wrmw mw w w "* w*wwm = vr-vNm wrv "w-* w=-mt w w - -- ww w& We-'P -e-wm'e'tSt'm*'**-'w=&w ,- c I < - l 1 - l i 1.4.1 Energy Supply Services l 4 . x ,. l O- _l I Energy Supply Services is under the direction of the_Fnergy Supply . ..' 'l ' l l Services Director, who reports to the Energy Supply Senior Vice -' l President. The Energy Supply Services Director is responsible for l lprovidingsupporttoAP&Lnuclearplantsintheareasofquality l l assurance, administrative services, engineering service.s and technical le I r g services. His duties include providing technical direction, ' l I administrative guidance and supervision to the: , , I l I l -  ; l l a. Energy Supply Administrative Services General Manager F . b. EngineeringServicesGen[eialManager - - , l l c. Technical Services General. Manager ' , I

d. Quality Assurance Managei-l -

l l . < l l1.4.1.1 Quality Assurance Manager l ' ' ' ~ I

The AP&L Quality Assurance Organization (QAO) as shown in Figure 4 is l y

I under the direction of the Quality- Assurance Manager, who reports to the 1 ON I g Energy Supply Services Director. The QA0 performs review, surveillance, I g l inspection and audit functions during the operational phase of AP&L8 s l l nuclear plants and is independent of Nuclear Operations, and from cost I g I and scheduling considerations when opposed to safety and quality l l considerations. e l ~ I l

ThedutiesandresponsibilitiesoftheluslityAssuranceManagerinclude

~ l- ' g I the following: - l 1 - I ~ g. , i 1. Develop Quality Assurance Program requirements for ' l-l modification, operation, and maintenance activites related to l the safety-related (Q-listed) systems, structures, and I components in AP&L nuclear plants. l l l . I l I ~ l i 1 - l l l s i I t I 1 -C1 I i 1 l A .I TOPICAL REPORT lREV. 6 l l p- l lDATE 6/10/83 l l & l SECTION: 1.0 ORGANIZATION ' lPAGE 1-3 l l L l l l l 1 - l _ I I. _ ._. _ _ _ _ . = _ _ _ _ _ . , , . . _ . - _ _ . - . , _ _ , - - _ . - - . - . . - - - . - - - .. . . s d g g

V l l

~ l 2. Audit of the quality assurance activities as described in l V '_ Section 18 of this manual. I O. .- l l ~ g l ' g 3. Review, . approval and verification of the quality assurance l h 4 , I requirements placed upon contractors or vendors that provide 1 l g ', g equipment, material, or services for AP&L nuclear plants. l '; I l

4. Authority to stop work where conditions exist that prohibit l

l effectiv,e quality control. inspections, or if faulty materials, l g g e in. correct workmanship or procedures are detected. g g . _ ls; . . -

v.  ;

l - ~5. g

Control and distribution of QA Manuals and QA Procedures and

• ' I

- I .rev,isions thereto.' l 1 I i l l '6: - Review and approval of QA programs for outside organizations l -g ^ participating in the AP&L QA program. u I . ~ g l

g. '7. ~ Serve as a member of the Safety Review Committee. g g

I - I i ~'

. 8. Provide,and maintain a qualified and suitable trained staff to i I carry out required staff' functions.

l 'l y 1 l 3 s ~, 'I 9. Formulate prograr.s for maintaining.the professional competence 1 ' l .' I of pdrsonnel within the QA0 and provide assistance in QA I l

I, training and indoctrination programs for division management,-

.I f - engineering and plant personnel whose activities affect ~

1. quality.

" I l { l l m .I > I l l 10. Provide technical direction and guidance to the Quality l. ? Engineering Supervisors. I l ~ l l l' l i l- l l

• I l

l I ' 1 l N - I g g / I I i i f] I A l TOPICAL REPORT I 6 I lREV. l P I -. " ~ 1 l,. - .lDATE 6/10/83 l L,1 l- & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-4 l -. I L %l _ , , I l r.- l ,I l-N 9....g , , , . - , ----w- w+m-v -**Twv** ***'d" **Y"' k l , l i  ; 1 4 1 1.4.1.1.1 Quality Engineering Supervisor I , (. 3  ;< , I l .A 4- l 3 g

• . \d ' '_ i TheQualityEnkineeringSupervisorreportstotheQualityAssurance l lHanager, supervises QA Engineers and Auditors / Inspectors as assigned, l and assists the Quality Assurance Manager in the coordination of l

I I

activities within the QA Section. The Quality Engineering Supervisor may l I also perform duties normally assigned to Quality Assurance Engineers. 1 I

l l ' l l 1.4.1.1.2 Quality Assurance Engineers I

y i

' I l l l The Quality Assurance Ensineers (QAE's) report to a Quality Engineering i g Su' pervisor, as assigned. The Quality Assurance Engineers are to be ^ l l j familiar with the Quality Assurance Program and associated procedures, I I , l 10CFR50 Appendix B, regulatory guides, codes, and standards that address l " I l u q>uality assurance. They also possess the necessary functional l l' independence and authority to: l identify quality problems, initia'te, I g j l recommeyd,orprovidesolutionsthrough;designatedchannels,and, verify i A' ,\ f l implementation,of solutions. Specifically: l I ^ '  ; ff% g- x / ll 4 i I ~ g 1. <The QAE's[are to have the authority to inspect, audit or review l g l practices, records, files, instructions, directions or l g documents concerned with all areas affecting quality. I I

2. The QAE's are to schedule and coordinate audits or surveillance i efforts in the areas assigned, document findings, and report I l#

~ j ') results to the Quality Assurance Manager and the Manager of the ~ l f audited area. I I ' I I l l 1.4.1.1.3 Quality Assurance Auditors / Inspectors l l l t l l 1 i l The Quality Assurance Auditors / Inspectors report to the Quality I l-EngineeringSupervisorandassisthimintheimplementationofthe g I l l program by performing audits and inspections as required to assure proper l lapplicationoftheQualityAssuranceProgram. i i ' I 1 I < O l l i O I A I TOPICAL REPORT l lREV. 6 1 l l P, I IDATE 6/10/83 I I I '& r;l SECi] ION: 1.0 ORGANIZATION IPAGE 1-5 l l L, l , I I l l_ _l . I l 4 , _ , _g , , . c - - - ' * ~ - - - "' " - ' " - -' I I I I I 1. 4.1. 2 Technical Services General Manager l I O l I l I The Technical Services General Manager reports to the Energy Supply l lServicesDirectorandisresponsibleforprovidingsupporttoAP&L 1 nuclear plants in the areas of plant performance, maintenance and l l l availability, chemistry, environmental monitori.ig, metallurgy and l nondestructive examination. His duties include the following: l l l l 1 l l 1. Provides technical direction and administrative guidance to: l I I I i l a. Plant Performance Evaluation Manager l l b. Plant Maintenance Manager l c. Availability Engineerir.g Manager l l l d. Technical Analysis Manager 1 l 1

2. Assure conformance to the Quality Assurance Program by l instituting the necessary quality-related procedures and l

I instructions within the Technical Services Department. l n V - l 3. l g Provide for coordination of environmental surveillance programs g i I l 4. Direct development of programs aimed at maximizing efficiency l and availability. l I I I I I l 5. Provide for review and analysis of outage data and make l I g recommendations for correct'ng deficiencies which affect I-g I availability or performance. 1 I I I I l 6. Direct the plant maintenance tupport activities that are l assigned to the LRGO. l 'l l

7. Serve as a member of the Safety Review Committee.

l l I . I I I I I I I I O i l A i I TOPICAL REPORT i lREV. 6 I l l P I lDATE 6/10/83 I l & I SECTION: 1.0 ORGANIZATION lPAGE l-6 l l l L l l I I I I I I I I I l 8. Provide and maintain a qualified and suitably trained staff to l I carry out required departmental functions. O ~l I l 4 ,l 1.4.1.3 Engineering Services General Manager ,I i I The Engineering Services General Manager reports to the Energy Supply l Services Director and is responsible for LRGO design and engineering l lactivitiesrelatedtonuclearplantoperations. His duties include the l following: l l l l l l 1. Provide technical direction and administrative guidance to: l l l l l l a. Mechanical Engineering Manager i

b. Electrical Engineering Manager l c. Civil Engineering Manager l l

d. Iitstrumentation and Controls Engineering Manager l l l

l

2. Assure conformance to the Quality Assurance Program by g l instituting the necessary quality-related procedures and l

l V instructions within Engineering Services. I I

3. Provide for review and approval of LRGO design and engineering

I activities performed by contractors, vendors, and AP&L l

l ! personnel. I 1 ' I l ,I 4. Provide for review and approval of procurement documents for ~ l equipment, a;aterial and services for LRGO engineering projects, l as appropriate. I I l S. Provide and maintain a qualified and suitable trained staff to l carry out required departmental functions. l l 1 I I I . I i i i l l i i l l I (^' I I I I l A l TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-7 l 1 L i i l l I I I I I l' I l 1.4.1.4 Energy Supply Adr.inistrative Services General Manager i l-l l l The Energy Supply Administrative Services General Manager reports to the I l l Energy Supply Services Director and is responsible for the development of l l administrative progt-ams, systems and services supportive to management. l l.His'dutiesincludethefollowing: 1 l l l 1. Provide technical direction and guidance to: I l l a. Energy Supply Training Manager l b. General Services Manager l l l c. Planning, Scheduling & Cost Control Manager l d. Contract Administration Manager i I I I I l 2. Maintain overall department fiscal direction and control, and l l provides supportive accounting functions. I I

3. Provide contract administration and administration of p l procedures for Energy Supply Little Rock General Office (LRGO) I d

l activities. I l

4. Administration of the training and development effort for l Energy Supply.LRGO personnel.

l l I I I I l 5. Ancillary support services to Energy Supply operation sections. I I l l'~ l I 6. Provida and maintain a qualified and suitable staff to carry I out required departmental functions. ' l 7. Serve as a member of the Safety Review Committee. I I 1 I I i 1.4.2 Nuclear Operations l l I I I l Nuclear Operations is under the direction of the Nuclear Operations Vice I ! President who reports to the Energy Supply Senior Vice President and is i l I I ,O i i l .A i i I I I TOPICAL REPORT IREV. 6 l !- l P l lDATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-8 l l L l l 1 l_ l l I 1- r- ~l I I - 1 I responsible for the formulation, licensing, implementation and discharge 1 of operating policies and procedures relative to nuclear plant operations  ; _ l and for nuclear fuel management. His duties include the following: I l' l l l -l 1. Provide technical direction and administrative guidance to the: 1 I 1. i , I a. Plant's General Manager I i

b. Nuclear Services Manager l l I c. ANO Project Manager

.I

d. Licensing Manager l

. .1 l '2. Assure conformance to the Quality Assurance Program by I instituting the necessary procedures and instructions within l -l the Nuclear Operations Department. I I

3. Provide for review and approval of design and engineering

I performed for the operating nuclear plants. l I

I

I I

I I- 4. . Provide for review and approval of procurement documents for 1 equipment, material and services. I I

5. Provide for liason between AP&L and applicable regdlatory -

l l ' - 1. agencies. I I I

I I

i  ! 6. Provide and maintain a qualified and suitable staff to carry l l out required departmental functions. ' I I

7. Provide for procurement and' design review of nuclear fuel.

l l l ' 1-I I I i I l i I I I I l . I I i I l

• I

' l l 1 I 'l i Qb ' I I l A l TOPICAL REPORT 6 lREV. l l P l i' IDATE 6/10/83 I -l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-9 l l L l l l l -I I J . I c rw - g-- g- , -e -, e- m p-e-w&-w,-<,e- -,-w.--6,w-%e-%-------ey- - - - u,-r<- e m, m&-.,- - , , ---w--r,,--.,.--e~,n----e*,-e-ew,, w--w- --w-e-, r i I I i l 1.4.2.1 Nuclear Services Manager I. I I eG V l i l The Nuclear Services Manager reports to the Nuclear Operations Vice l-President and is responsible for providing the necessary support services I related to the effective operation and maintenance of the AP&L nuclear l l plants. The duties include the following: l l l

1. Review, approval and coordination of design changes through the l

l Little Rock General Office. l l l l l l 2. Review, approval and coordination of purchase requisitions and I I g contracts generated at the Little Rock General Office. l l l l 3. Interface with other departments to assure effective l implementation of Regulatory and Company requirements. I I I I I l 4. Communication interface dealing with all activities at the l l nuclear plants. l 0 l g 5. Provide. technical direction and administrative guidance to the l g I Nuclear Fuel Supervisor, who is responsible for the I procurement, design review and performance evaluation of l l nuclear fuel and to provide support to the plant in the areas l l of reactor core performance and assessment of core design I analysis. 1 I l-1 I l 6. Serve as a member of the Safety Review Committee. I I I I I l 1.4.2.2 Licensing Manager l I I I I l The Licensing-Manager reports to the Nuclear Operations Vice President l landisresponsibleforthecoordinationofalllicensingdocuments, I requirements and revisions thereto which are required to be reviewed l I I l l l l l O 1 i i i i l A l TOPICAL REPORT IREV. 6 l P l l IDATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-10 l l L l l l 1 I I _ _I I I I I l and/or approved by the NRC and for interfacing with the NRC. The l ~ Licensing manager is also responsible for the review and approval of l Q-List changes and for the tracking of possible nuclear safety concerns l ltoassuretimelyclosecut. I i 1.4.2.3 Project Manager l l l The Project Manager reports to the Nuclear Operations Vice President and I is responsible for providing services at the nuclear plant for field l lconstructionactivitiesandformodifications'tothecontrolroom ,I simulators used for operator's training. His duties include providing i technical direction and administrative guidance to the Field Construction l Manager and the Simulator Project Coordinator. I I I I I l 1.4.2.3.1 Field Construction Manager 1 I i i l l The Field Construction Manager is responsible for directing the l lactivitiesofhisstaffrelatingtoworkassociatedwithplant q construction and modifications. l l His duties include: l V I I I l l 1)- Interface with other departments to assure effective l l implementation of job assignments 1 I

2) Provide cost and schedule controls for departmental activities l

l 1

3) Provide technical and administrative guidance to the i

! Con e.uction Quality Control (CQC) Supervisor. The CQC I Supervisor is responsible for the surveillance and inspection l of activities performed under the direction of the Field l l Construction Manager. The CQC Supervisor is also responsible l-l I for assuring adequate inspection points have been assigned for I the work activity, inspectors have been certified to ANSI I l i . I l l l 1 I l i I O i l A i I TOPICAL REPORT i lREV. 6 I i l l P 1 IDATE 6/10/83 I l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-11 l l L l l l l 1 I I L I I I l l N45.2.6, directing the activities of the inspectors, and i I interfacing with the Code Inspector for activities involved  ! .I Code items. l I I I I l 1. 5 PLANT ORGANIZATION I I l I I 1.5.1 General Manager i l I I l i 1.5.1.1 I l l l l l l The General Manager reports to the Nuclear. Operations Vice President on I the corporate level (see figure 5) and has direct responsibility for I operating the plant in a safe, reliable and efficient manner. He is l I , responsible for operating the plant in accordance with the provisions of I the operating licenses, including the on-site quality program. I I I I i 1.5.1.2 I I I I I l l The General Manager has the authority to shut the plant down if required l landhasfinalapprovalofplantprocedures. l l l 1.5.1.3 l l l lTheGeneralManageristoprovidetechnicaldirectionandadministrative l guidance to the: l I 1 I-I l 1) Operations Manager l l 2) Maintenance Manager I l 3) Administrative Manager 1

4) Engineering and Technical Support Manager 1 5) Special Projects Manager I

6) Manager, Nuclear Quality Control l

l . I I I i , I l l l I l l Q-- l A l I I TOPICAL REPORT IREV. 6 I I P l IDATE 6/10/83 I I I SECTION: 1.0 ORGANIZATION IPAGE 1-12 l l L I l l 1 i i i { l l I I l 1.5.2 Operations Nanager l 1 Q ~ l l The Operations Manager (Figure 6) is responsible for directing the actual l l I ' day-to-day operations of the plant. He supervises the operating staff l and interfaces with the Maintenance Manager to accomplish l operation related maintenance activities. The Operations Manager is to l provide technical direction and administrative guidance to the: l l l 1 l l 1) Operations Superintendents l

2) Operations Technical Staff l

l l l1.5.2.1 l l l lTheOperationsSuperintendentsreporttoandassisttheOperations l Manager in directing the day-to-day operation of the power plants. They l-are responsible for coordination of the daily review of operating l surveillance tests and coordination of operation-related maintenance l I activities. They are to assist the Operations Manager in the supervision q l of core refueling, which includes advance planning for the outage, plant i J  ! g preparation, equipment check-out and the refueling operations.

I I

l1.5.2.2 l l 1 i The Shift Supervisors report to the Operations Superintendent and are l responsible for the actual operation of the unit and for the activities l ' l I i

of the operators during their assigned shift. The Shift Supervisor is to l~

g l be cognizant of operation activities being performed while on duty. The i Shift Supervisor on duty has the authority to shut down the unit if, in I his judgement, conditions warrant such action. I I I I I l 1.5.3 Maintenance Manager l l l l l l l The Maintenance Manager (Figure 6) is responsible for the maintenance of I I , plant equipment, facilities and planning / scheduling of station work 1 1 I l ' l' ' 'O d I l A I l TOPICAL REPORT I 6 I I lREV. l l P l l IDATE 6/10/83 1 i l & 1 SECTION: 1.0 ORGANIZATION l IPAGE 1-13 l l L l l l l l l l l -l l l l l activities as defined by plant maintenance program implementing I procedures and to assure that maintenance of equipment is conducted in V l conformance with applicable standards, codes, specifications and l l-procedures The Maintenance Manager is also to coordinate ~ l operation-related maintenance activities with the Operations Manager and l I g is responsible to make repairs on any structure, system or component l g l under his control. The Maintenance Manager is to provide technical l ldirectionandadministrativeguidancetothe: I I l 1. Mechanical Maintenance Superintendent i 2. Electrical Maintenance Superintendent l l 3. Instrument & Control Superintendent l 4. Planning and Scheduling Supervisor l

5. Senior Maintenance Coordinator l 6. Shift Maintenance Superintendent l I

I I I l 1.5.4 Engineering and Technical Support Manager l I I I I l The Engineering and Technical Support Manager (Figure-7) is responsible O i l for providing pla.it engineering support services as well as technical and 1 i g I plant analysis and health physics support services to the plant staff. l The Engineering and Technical Support Manager is.to provide technical I direction and administrative guidance to the: l l 1 I I I I 1) Technical Analysis Superintendent l l 2) Plant Analysis Superintendent ~ l 3) Plant Engineering Superintendent l l 4) Operations Assessment Superintendent ! 5) Health Physics Superintendent. l I I I l . I 1.5.4.1 Technical Analysis Superintendent l I I I I l The Technical Analysis Superintendent maintains overall responsibility l I l for radiochemistry, chemistry and environmental programs at the plant. I g l l l O V I I I 1 I l A l TOPICAL REPORT 6 lREV. l P l l IDATE 6/10/83 I I & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-14 l l L l l l l l 1 1 ._ m _. _ _ _ . .- -- _ _ . . _ . . _ . . _ ._ _ ._. 4 I i l 1 l-1 The -Technical Analysis Superintendent is also responsible for maintaining l I ' ( . the Station Emergency. Plan and' ensuring the-plant staff.is capable of I l implementing the. requirements delineated in the Plan and its procedures. l-1 I 4 I I i 1.5.4.1.1 l l l 1 I l' The Radiochemistry Supervisor reports to the Technical Analysis l' l Superintendent and is responsible for analyzing the reactor plant water z I conditions and providing recommendations to maintain conditions. I i 1. l 'l -1.5.4.1.2 'l 4 1 I I l . I -l The Chemistry and Environmental Supervisor reports to the-Technical l lAnalysisSuperintendentandisresponsibleforestablishingwater ~ l_ l ' chemistry criteria, analyzing secondary plant water and auxiliary water l lconditionsandprovidingrecommendationstomaintainconditionswithin l' acceptable limits. l. I i i i + l-l X 1.5.4.2 Plant Analysis Superintendent -l l U l i I I l l .The Plant Analysis Superintendent is responsible for.the areas of plant 1 performance, nuclear support and computer support. A supervisor is-1 provided for each of these areas. l l l __I ! I -l

I 1.5.4.2.1 l l

I~ L I I i  !- The Plant Performance Supervisor reports to the Plant Analysis I - Superintendent and'is responsible for: evaluating equipment and system l l performance over extended periods, recommending methods of improving and I ( maintaining good plant efficiency, investigating and evaluating equipment l l malfunctions or failures and recommending corrective action to prevent I recurrences, and coordinating the activities of the Inservice Testing l- l Program at the plant. l . I l- I 1 I l .I l-1 iO I i i i i i l A I TOPICAL REPORT 6 lREV. l P I l lDATE 6/10/83 I l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-15 l i- .1 L i l l l l i l I , -.r., . . . . . . , . _.,-._,._.,-,_,........,__.-_...,,,.,_,m--- ,,,-w__ 1 1 1 l l l 1.5.4.2.2 l I O -l i The Nuclear Support Supervisor reports to the Plant Analysis l i l-Superintendent and is responsible for monitoring reactor core and Nuclear l Steam Supply System (NSSS) performance; conducting reactor performance l and physics testing to assure safe and reliable operation and to provide 1 -current accurate information to operations; collection and transmittal of I g nuclear fuel management data to the Nuclear Fuel Supervisor in Little l Rock and the reactor vendors as required; on site safeguards and l accountability of the nuclear fuel; and assisting in the planning of all l_ l fuel movements including new fuel receipt and inspection, fuel shuffling I at refueling, inspection of irradiated fuel and shipment of spent fuel. l l l 1.5.4.2.3 I l 1 The Computer Support Supervisor reports to the Plant Analysis l Superintendent and is responsible for the maintenance, revision and l I development of computer software for the plant monitoring computers and I for providing technical assistance to the Nuclear Support Supervisor and l 4 lNuclearEngineersindevelopmentanduseoftestapparatusforevaluation l of fuel, core and NSSS performance. l l I I I I l 1.5.4.3 Plant Engineering Superintendent i I I I I I The Plant Engineering Superintendent is responsible for drawing control, I I ' f implementation and coordination of the Inservice Inspection Program and I i design and plant engineering activities at the plant. The Plant l lEngineeringSuperintendentistoprovidetechnicaldirectionand j l administrative guidance to the: l l l l l l l 1) Mechanical Engineering Supervisor l l 2) Electrical Engineering Supervisor , I 3) Drafting and Drawing Control Supervisor. l . I l 1 I I I I I O i 1 A i I TOPICAL REPORT i 6 I i lREV. i l P ' l lDATE 6/10/83 1 I & I SECTION: 1.0 ORGANIZATION lPAGE 1-16 l l L l l l l l  ! I - ._ _, . -- - -- - - ---- - - - - - - - -- - - ~ ~ - - ' - - I I l 1.5.4.4 l l Operations Assessment Superintendent i I I (i U l l l The Operations Assessment Superintendent provides the capability to I perform engineering evaluations of operating experiences which occur both I at the AP&L nuclear plants and at other nuclear power plants and to I recommend corrective actions as a result of these evaluations to help i plant operations personnel in preventing or dealing with similar I ocurrences. I I l1.5.4.5 Health Physics Superintendent l l 1 l The Health Physics Superintendent is directly responsible for and has the I authority to implement the Health Physics program at the nuclear plant I and to maintain radiation exposure as low as reasonably achievable I (ALARA). The Health Physics Superintendent has the authority to stop I work in radiation areas if he evaluates that a potential for an , I unanticipated excessive exposure to plant personnel or the environment l l may exist. I y O U I I 1.5.5 Administrative Manager I I y y i I The Administrative Manager (Figure 8) reports to the General Manager and l aids him in the administrative aspects of the plant's operation. The l I Administrative Manager directs the activities of the administrative staff I and provides technical direction and administrative guidance to the: I i 1 l-I i 1) Office Services Supervisor l l 2) Material Management Supervisor I y l l 3) Human Resources Supervisor l ! I

4) Training Superintendent l

I 5) Plant Controller I l I I I

l

. l l 1 1 I I I l i I I A I TOPICAL REPORT IREV. 6 l l P l 10 ATE 6/10/83 I I & l SECTION: 1.0 ORGANIZATION lPAGE 1-17 l l L i l I i l__ l I i ._ 1 l 'l l l 1.5.5.1 1-I I O ' - 'l The Office Services Supervisor is responsible for administration of the I i

l '

l - clerical staff activities and the accumulation and disposition of quality

• l' assurance records related to all phases of the nuclear plant. l l '

I l 1 -1.5.5.2 I l l l I l l The Material Management Supervisor is responsible for plant procurement, -I storage of materials, parts and equipment, issuance of tools and test I equipment ~and the disposal of surplus materials. l ! l l l i 1.5.5.3 I

l 1 l

l. .I - l The Human Resources Supervisor is responsible for employment, industrial l l relations,industrialsafetyandfirepreventionandsecurity. Reporting y I to him are the Safety and Fire Prevention Coordinators, the Security l Coordinator, and the Employment and Industrial Relations Coordinator.  ! y l , O l 1. 5. 5. 3.1 I ! I-l I The Safety and Fire o revention Coordinators are responsible for l l conducting periodic checks to examine control of combustables, I l housekeeping and other fire prevention / protection efforts as well as to l provide a centralization of OSHA and plant safety programs. - l l j.. I I i 1.5.5.3.2 I I I 'l l l The Security Coordinator is responsible for coordination of the efforts I of the security force-and to manage the operation of the security system. I I I I I I l . I I I I I V I ' l 1 DU I I I I I l A I TOPICAL REPORT IREV. 6 1 ! I- P I lDATE 6/10/83 l l & l l'SECTION: 1.0 ORGANIZATION IPAGE 1-18 I L I L i I l I I 1 I I l ,, . . , . . - - - - . . - - _ . . . - _ - - - - - _ _ _ . - ~ - . - _ . - , . . . _ _ . ~ . _ _ _ _ _ - - - _ _ - . . I l l l l 1.5.5.4 l 1 O - I l The Training Superintendent is responsible for the training and i i l retraining of plant personnel and of Little Rock General Office personnel I l as' established by Plant procedures. l l l l l l 1.5.6 Manager, Nuclear Quality Control l 1 I l-l l The Manager, Nuclear Quality Control (Figyre 5) is responsibl.e for l l verifying the implementation of the Quality Control Program at the plant l and reports to and receives direction from the General Manager. His l duties include the following: , I i l 1) Provide technical direction and administrative assistance to l the: l l i i_ I l a. Quality Control Supervisor l

b. Quality Control Engineers

c. Quality Control Inspectors l

g l i N,.; I I I I l 2) Interface with the Quality Assurance Manager or his l representative for technical assistance in resolving j significant conditions adverse to quality. l l I I I l 3) Authority to place an item in a nonconforming status when such l I ~ an item is determined to be in violation of purchase documents, l applicable codes and standards or FSAR requirements. l l ' 1 I I

l 4) Assuring surveillances, inspections and reviews of plant l activities and documents are conducted in accordance with l plant procedures. l I

I I I I . I I I I I I I l l O 'd I I I I , l A l TOPICAL REPORT 6 lREV. l P l l lDATE 6/10/83 l l 6 l SECTION: 1.0 ORGANIZATION IPAGE 1-19 l l L- l l l l _ l i I I I I I -l 1.5.7 Special Projects Manager l 1 O l I v l l The Special Projects Manager is responsible for the administration and l control of special projects pertaining to plant operations, maintenance I and administration and is to provide technical direction and  ! administrative guidance to a staff of Special Project Coordinators. l Additional duties include: l 1 l l l i 1) Serving as chairman of the Plant Safety Committee l l - I l l 2) Interfacing with onsite regulatory agencies l' l 1 I i - I l 3) Providing evaluations and recommendations to regulatory l l requirements and meeting regulatory commitments. l l l l1.6 INDEPENDENT REVIEW ORGANIZATIONS ,I I i lInadditiontotheresponsibilitiesofkeyindividualswithintheAP&L q l organization who are involved with the overall quality. program, AP&L has l V lestablishedthefollowingcommitteesasamanagementtoolto l l independently review activities occurring during the operational phase of l a nuclear plant. I i 1.6.1 Safety Review Committee (SRC) 1 I ~ The SRC reports to the Nuclear Operations Vice President and is l responsible for providing off-site independent reviews, and/or audits l relating to: the Safety Analysis Report, Technical Spacifications, l Procedures and changes thereto; unreviewed safety questions; violations, l deviations and reportable events; and any other matter involving safe l operation of the nuclear plant which the committee deems appropriate or l I , is referred to them by the on site operating group. The SRC is also to l l review the reports and meeting minutes generated from the Plant Safety l Committee. l l l 1 fr 1 A i l I l l TOPICAL REPORT lREV. 6 l l P l l0 ATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-20 l l L l l 1 I I I l I I l . -- l l 1.6.2 Plant Safety Committee (PSC) -l .l g- -l l The PSC reports to the plants' General Manager and is responsible for I l l l-reviewingactivities_specifiedintheAdministrativeTechnical 1 - Specifications for the purpose of: l l 1 l l l 1) Rendering determinations in writing with regard as to whether ,l or not an unreviewed safety question (defined by_10CFR50.59) is l involved; and l i I ? l-l I

i. 2)

-I Furnishing written recommendations to the plants' General I i Manager for approval of disapproval. , I I l These activities include changes-to plant procedures and Technical l l Specifications, proposed modifications to plant systems, changes to l [ plant security and emergency plans, and review of facility - l l operations to detect potential nuclear safety hazards. !l I i l l' ' l-l .1.6.3 Committee Structure t j O a l i I

• l l- The organization structure and administrative requirements specific-to l i

each committee'are' described in the plant's Technical Specifications and i l in internal-procedures / documentation. l i l l I 1 - l ! l 1. 7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES i I l l-l l l As owner and operator, AP&L assumes full responsibility and authority for I. ,I the plant including-action to assure that the plant is operated in l accordance with sound engineering practices, Licensing requirements and I applicable codes, specifications and procedures. I g l l lEachsupplierofequipment,materialorservicesandeachmaintenanceor l l modification contractor is responsible for administering the applicable I . quality control functions as requiret by AP&L. The Quality Assurance and l l l l 1 Q l l A i l TOPICAL REPORT I lREV. 6 I l l P l lDATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-21 l l- L I l l l 1 I I I l l I-

1. Quality Control organizations are responsible.for assuring by I surveillance, inspection, audit or review of objective evidence (e.g.,

.I audit reports conducted by others, etc.) that these. functions are ~ l accomplished for systems and structures that affect the safety and I integrity of the plant. l I I I I I Visits to manufacturer's shops.by Quality Assurance organization l lpersonnelareconducted,whendeemednecessary,baseduponsafety - l significance,. complexity, method of acceptance'and past history of the I vendor,.to establish product quality and to assure that quality assurance ~ ' I and quality control programs function in accordance with AP&L l requirements. . 1 I I I i ' I I I I l l I I I l l l-1 I .O l I 1 i l l 1 I I I I I 4 I ! l I I ! l I g l.- I I I I i 1 I l I I 1 1 I i i l l I ' I l l l l . I I I , I I

I I 4 -

l l A TOPICAL REPORT lREV. 6 l p l l lDATE 6/10/83 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-22 l I L l l I I I I __ l 3 - - - . - - - - - - - - - - ~ - - - - - - ---- - ~~ ~ ~~~" - ~~~~~" I l 1 l l 2.0 QUALITY ASSURANCE PROGRAM l l () _l l 2.1 SCOPE l l l 1 I l- > I l This quality program is to assure that AP&L nuclear plants are operated l in a safe, reliable and efficient manner and in accordance with NRC' l regulations, applicable industrial standards and codes and applicable l Company policies, rules, procedures and licensing documents. A matrix of l QA Procedures cross-referenced to each criterion of 10CFR50,. App. B, is l lincludedinTable2tothismanual. I I ' 1 I 2.2 GENERAL I i 1 l 1 2.2.1 l l l l ,I This quality program is applied to those safety-related structures, l systems and components and to those expendable and/or consumable items

• l whose satisfactory performance is required to prevent accidents which may

, l cause undue risk to the health and safety of the public or to mitigate l the consequences of such accidents if they were to occur. These l structures, systems, components and consumable items are identified in l the Q-list for each nuclear plant. When structures, systems and _ l components as a whole are on the Q-list, portions not associated with a l loss of safety function as determined by Engineering are to be considered l Non-Q, unless otherwise dispositioned by Engineering. l l l l-1 I l

• Expendable and/or consumable items are to include, as a minimum: l

, l nuclear fuel, weld rods, boric acid, and diesel fuel. I ' I I I i l 2.2.2 l l 1 I I l The Q-list is under the control of the Licensing Manager. The Licensing l Section maintains an up-to-date list of personnel issued a copy of the l Q-list and assures that reviews, approvals and distributions of the l l l 1 1 I I O I l A I l TOPICAL REPORT I lREV. 6 I l P l l lDATE 6/10/83 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-1 l l L I i 1 l 1 I i 1 l l 1 l ' l I t I l Q-list and changes thereto are performed in accordance with approved l l ,f3 procedures. Changes to the Q-list require review / approval by the J , l discipline Engineering Manager, Quality Assurance Manager and Licensing i Manager. - 1 I l2.3 RESPONSIBILITIES l l l l2.3.1 l l l l AP&L recognizes that quality assurance is an interdisciplinary function I involving many organizational groups, encompasses many functions and l I , activities and extends to various levels in all participating l organizations (from the Energy Supply Senior Vice President to all I workers whose activities may influence quality). This quality program l l designates responsibilities and duties of specific individuals, which may l be performed by their. appointed designees. l l 1 2.3.2 l n l This quality program assigns the responsibility for quality to the l departments performing the work and includes as a basic requirement that l individuals responsible for verification of conformance are qualified and I do not perform or directly supervise the work. Additionally, independent I reviews, audits and surveillances are provided by individuals not l reporting to the groups responsible for performing the work. l l l l-1 I l 2.3.3 l l 1 1 I ~ l This quality program also includes provisions that require suppliers, l contractors, subcontractors, consultants, etc. to maintain and use l l quality assurance programs reviewed and approved by the Quality Assurance l Manager. Audits or surveillances by the QA0 provide assurance of l compliance with applicable procedures. , l i 1 l l I I ' i I l O ' l A i I TOPICAL REPORT i lREV. 6 I l l l P l lDATE 6/10/83 i I & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-2 l l L l l 1 i i l i l l l l I l l 2.3.4 l l- . 1 ' O- .l The' Nuclear Fuel Supervisor within Nuclear Operations is responsible for l_ I 1 the assurance that nuclear fuel used in AP&L nuclear plants is designed, I I l procured, manufactured, and utilized in accordance with regulatory l requirements, and related industrial codes and standards. On-site ' l quality control of nuclear fuel is implemented through the use of plant d l s ladministrativeprocedures. These procedures include the receipt, l inspection, handling, storage, and accountability of Special Nuclear l Material (SNM). The Nuclear Support Supervisor maintains a 1isting of l l those individuals qualified to perform receipt inspections. l ' l l l l - l l 2.4 PROCEDURES l l - I I l l 2.4.1 l 1 l l l l l Activities which affect quality are defined in appropriate procedures, l which are developed to cover AP&L administration and control. The l procedures state the policies and instructions necessary to fulfill the , O i intent of the program. Procedures provide for standard forms, lists, and l i I check-offs used in documenting the inspections, certifications, reviews, l surveillances and audits. The program and the procedures shall be' l l modified or supplemented from time to time as the need for change arises l ! during the life of the plant. Quality program policies, procedures and l l instructions are contained in the documents listed in Table 3. l l l-1 l -l 2.4.2 l , I l l l , l Procedures assure that activities affecting quality are performed under i suitably controlled conditions. Controlled conditions include the use of l appropriate equipment; suitable environmental conditions for performing l the activity such as adequate cleanliness; and assurance that required I prerequisites for the given activity have been satisfied. Administrative l ' procedures also assure that the need for special controls, processes, l 1 I l -Q l l A l l TOPICAL REPORT l lREV. 6 l l l P l lDATE 6/10/83 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-3 l l L l l l ~ 1._ l I I I I I I l commitments in the program description previously accepted by the Nuclear I S g Regulatory Commission. Changes to the program description that reduce V _ l the commitments are to be submitted and approved by the Nuclear l Regulatory Commission prior to implementation. The Quality Assurance  ! y l Manager is to determine if changes do or do not reduce the commitments of 'l this quality program. l l 2.6 PERSONNEL ,I I I l 2.6.1 1 l 1 lEmployeeswhosedutiesandresponsibilitiesarerelatedtothe, quality I program activities at or in support of the nuclear plant are to l participate in appropriate indoctrination and training programs to assure I that suitable proficiency is achieved and maintained in the work they are l performing. Such training shall include, as a minimum: plant security; I discussion of the overall Company policies, procedures and instructions I I g which establish the quality program; an explanation of the AP&L quality I organizations; and a discussion of those procedures which implement the l O- I g quality program related to the employee's specific job-related activity. I I l l2.6.2 l 1 l l The education, experience and responsibility requirements of individuals l l involved in this quality program are documented in job descriptions which I l g are approved and periodically reviewed by management. Requirements for l-I education, experience and proficiency levels are commensurate with the l degree of importance of the job assignment. Experience and training I requirements for plant staff personnel are to meet the requirements of l ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted I in Table 1. Personnel whose qualifications do not meet those specified I in ANSI N18.1-1971, and who are performing inspection, examination and

I testing activities during the operational phase of the plant,,are to meet I the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. I l l I

I I ! (3 V I I I I i l A l TOPICAL REPORT lREV. 6 l l P 1 lDATE 6/10/83 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-5 I I L i I I I I I l l l l 1 l 2.6.3 l 1 O V I i I _ l Personnel performing inspection and examination activities are to be l indoctrinated and trained to assure they are aware of the requirements I which govern their activity. Inspection and examination personnel are to I be qualified according to the applicable codes, standards, I specifications, regulatory requirements and LRGO and plant procedures. I Personnel performing inspections on those activities occurring during the 1 operational phase that are comparable in nature and extent to related I activities occurring during initial plant design and construction are to I meet the provisions of Regulatory Guide 1.58, rev. 1 (9/80) and ANSI l N45.2.6-1978, in lieu of ANSI N18.1-1971. l l l l2.6.4 I l-Personnel involved with welding or nondestructive examination of I materials, systems or components are to meet the appropriate I qualification requirements of the ASME Boiler and Pressure Vessel Code, 1 Sections III and XI, or for structural welds, the American Welding i Society (AWS) Structural Steel Code 01.1, and the American Society l l Nondestructive Testing Standard SNT-TC-1A-1975, and certified to perform I lthesetasksinaccordancewiththesecodesandstandards. I I 2.6.5 l l l . lPersonnelperformingauditsofthequalityprogramaretomeetthe ~ l experience, training and qualification / certification requirements of I I

ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise I noted in Table 1. I I

I I I 1 I I I l l I . I I I I I I l I l l k]- I A l I TOPICAL REPORT l 6 1 lREV. I l P I lDATE 6/10/83 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 I I L I l l ,  ! l' _ - 1 I -- =. . . . ..= . . . . . I I 1~ l 1 2.7 -PROGRAM REVIEW l t 'l I g .g. .I 2.7.1 I i~ l I l I I The Quality Assurance Manager is responsible for'a review of-this program I on an annual basis to determine the effectiveness and proper. I implementation of the quality program. ' l , I I l' l. I I 2.7.2 ~ 1 ! I l i i- I Management reviews of the status and adequacy of the quality program are I I accomplished through regular reports and presentations by the QA0 and i l through' reviews of quality assurance audit reports. -Quality Assurance l ! reports supply data on the status of outstanding audit and corrective _ I action items and may identify the status of other significant quality l'

• I program activities as requested by management.

.I j I l- . I i I l I l' O i 1 i l ' i l 4 l l l I -l I I l' I i i

l I

I ! I l-1 I I i -l i I I I I , I I i l l ! I ! I l I l l ' 1 I . I I I l l I I I I i Q-l l A i I TOPICAL REPORT I IREV. 6 I I t l P I lDATE 6/10/83 l 1 & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-7 l 1 L l l l 1- 1 I _ !. I I l 1 I l l -l 3.0 DESIGN CONTROL. l l- g 3.1 SCOPE-l - l, . l l l Design activities are to be controlled to assure that proposed plant I 1 g changes to the structures, systems, equipment and components conform to I 1 g l' applicable-regulatory requirements and that design bases are correctly l l j g tran' slated into appropriate design. documents. Design-Control activities l l! I are to be in accordance with the requirements of Regulatory Guide 1.64 -' I Rev. 2'(6/76) unless otherwise noted in Table 1. 1 l l l I 3.2 ~ GENERAL I 1 - l 1 1-

3. 2.1 '

Il- l 3 I I l Engineering Services and Plant Engineering are to be responsible for the I continued upgrading and modification of plant design. Design' documents l I (drawings, specifications, procedures and instructions) originating or n . l released through these departments are to be based upon the required l regulatory requirements, licensing based documents, functional l requirements, quality standards and design bases in accordance with NRC -l l licensing requirements. Design activities may include calculations, ! l l analyses, materials selection, equipment arrangement and layouts, ~ -l accessability for inservice inspection, and the specification of test and l; . l l inspection criteria. Those design activities performed by individuals 1-1 l g within Engineering Services are controlled by the use of LRGO-Energy l Supply Procedures. Those design activities performed by individuals [I-I within Plant Engine'e ring are controlled by the use of Plant 2 l Administrative and Engineering Administrative Procedures. l I 4 I I l l l l 1 I I 1 i I . I I I f I l l 4 1 .g i A l TOPICAL REPORT 6 lREV. l l ~P ' l lDATE 6/10/83 l -l & 1 SECTION: 3.0 DESIGN CONTROL IPAGE 3-1 l 1 L 'l l l l l i I l gp ww ey a-r w-p g- e g = y gr e wy e y--=re---'Wiw,W41--y'+-Fr- 1e p g

• 14 Mag p-5 *-hN1-y-P-*-E'----r--o-----f-yemygyf-yvyw'1-'F'y*qw-"w---

I I I I i 3.2.2 i O D l I Design standards and requirements are to be at least equivalent to those I employed during the construction of the plant and are to be consistent I with the technical specifications and license requirements. I I l l l l 3.3 DESIGN INTERFACE I l I l l l Design control activities include measures for the identification and I control of design interfaces between the various engineering disciplines I within the department, between LRGO and plant engineering personnel, I g between engineering personnel and other AP&L support organizations, and l between engineering personnel and firms / suppliers outside the AP&L l I l organization. These measures include the development of procedures among I the participating organizations for the review, approval, release, I distribution and revision of documents involving design interface. I Coordination of the interface control is the responsibility of the I originating organization's management unless otherwise specified in an AP&L procedure applicable to the design activity. Design information l g l l V between interfacing organizations is to be documented and retained for i permament records. l I I I I I 3.4 DESIGN VERIFICATION l l I I I l 3.4.1 l l l l 1 J To assure the design is adequate and the above requirements and I procedures are implemented, Engineering Services for LRGO design or Plant l Engineering for plant design are to verify the adequacy of the design l I g through the performance of design reviews, the use of alternate or - I g I simplified calculation methods, or the performance of a qualification I testing program. The extent and depth of design verification performed 1 - . I I I I I I I I O I I I I I l A l TOPICAL REPORT 6 lREV. l P l l lDATE 6/10/83 l l & 1 SECTION: 3.0 DESIGN CONTROL IPAGE 3-2 l l L l l l l l I l ~ I 1 I I I by the responsible organization ,is determined by.an assigned engineering l reviewer based upon the importance and complexity of the design, the d . I degree of standardization and"its similarity with proven designs. I I I l .s l l 3.4.2 I I I 'l I l The verification process is to be performed by competent individuals or i groups other than those who performed or supervised the design but who I g I may be from the same organization. This' verification, however, may be I performed by the originator's supervisor "in~ accordance with departmentall l Procedures if he is the only individual in the organization competent to i perform the verification. Where changes to previously verified designs l have been made, design verifications are required for the change, I including evaluation of the effects of the changes on the overall design. I I 3.4.3 1 l-I l When a test program is used to verify the adequacy of a design, it is to I include suitable qualification testing of a prdtotype or initial I I

production unit under the most adverse conditions and' carried out in l accordance with documented procedures and/or instructions.

l l I I l 5 l 3.4.4 I l-1 - 1 I . l l Design work performed by organizations outside.of[ AP&L is to receive a i ~ documented review and approval by engineering personnel in accordance I with LRGO and plant departmental procedures; - l i i l I I l 3.5 DESIGN CHANGE I I ' l l l l 3.5.1 l , I I I I I Methods for the preparation, review, approval and impl.ementation of I design changes, including field changes, are documented in departmental l ' i I l A' l ' U l A l TOPICAL REPORT l .  ! I IREV. J6 l l P 1 ~ IDATE 6/10/83 l l & 1 SECTION: 3.0 DESIGN CONTROL , IPAGE 3-3 -l I L i 'l I I I I I l l l < 1 l - procedures for Engineering Services and Plant Engineering. Design l I o _g changes are subject to review and verification by the same organization 1 j I which review and verified the original design unless otherwise specified I in departmental procedures for design control. If minor changes to an l l approved design are required to meet plant requirements or conditions, 1 Field Change Notices (FCN).may be issued or otherwise documented by a l l' cognizant' engineer and transmitted with the changes for review and I approval in accordance with Plant Engineering Administrative Procedures. ' I I 3.5.2 l l I Changes from specified design inputs, such as design bases, regulatory l l requirements, codes and standards (including quality standards) are to be l identified, approved, documented and controlled through applicable LRGO l and plant departmental procedures. I I I I I I 3.5.3 I I I I I e l During preparation of a design change, the responsible engineering l lorganizationistoperformasafetyandenvironmentalevaluationper l l 10CFR50.59 to verify compliance with the Final' Safety Analysis Report and l ltodetermineifNRCapprovalofthedesignchangeisrequired. The 1 evaluation is to be documented and then reviewed by the PSC. I I I I I I 3.5.4 I I l-1 I l Design changes are also to be submitted to the Manager, Nuclear Quality l Control prior to plant implementation to verify the use of appropriate l l l quality codes, standards and inspection requirements in the design l I g documents. I g I l l' I I I I . I I ' I I I I I i I O ' l A I TOPICAL REPORT lREV. 6 l P l I lDATE 6/10/83 I i l & 1 SECTION: 3.0 DESIGN CONTROL lPAGE 3-4 l l L l l l L i I I I 5 ~ ,. ,- - k i l ' - - l_, ,! ' '. I I el j 3.6 - i'ESIGN RECORDS '~' '/ ' I l (V; I s , i x . l The Pidnt Administrative Manager is responsible for mainta1Mng permanent I lrecorosofthedesigndocumentsfortheconstructionandtestingphases. 1 In addition, he shall be responsible for maintaining records of the i upgrading or modification of these documents as described in this l section. The controls for maintaining these records are established by l I lspecificproceduresdescribedinSection17ofthismanual. These l records provide the historic reference necessary for the safe and l , I lreliableoperationoftheplant. 1 I . l I I l l l s I l i I I . I I I I .I I I I I I I I I (V~'i l l l l l 1 I I I I I I I I I

I i

l I 1 l-I I N , I l- ' ' l t ' l l - I 1 I I l i l W ~ l e l I l I I . I I I l I I l I l rs 1 I l 'd i A l TOPICAL REPORT IREV. 6 l I p I l lDAiE 6/10/83 l l l & I SECTION: 3.0 DESIGN CONTROL l IPAGE 3-5 I I L I l l l l l I L I I I I l 4.0 PROCUREMENT DOCUMENT CONTROL i l I I (Vl . I 4.1 SCOPE I I I I I I l Requirements for the procurement of items and services are to be clearly l lstatedanddocumentedtoassurethatapplicableregulatoryrequirements, l l design bases, technical requirements and quality assurance criteria are l lincludedorreferencedintheprocurementdocuments,whetherprocuredby l LRGO or plant procurement groups. l Procurement document control l lactivitiesaretobeinaccordancewithLRG0andplantprocurement l l procedures and are to meet the provisions set forth in NRC Regulatory l Guide 1.123, rev. 1 (7/77) unless otherwise noted in Table 1. l l l l4.2 PROCUREMENT DOCUMENTS l l l l 4.2.1 1 l l lTheprocurementofmaterials,partsandcomponentsaregeneratedthrough l ,, I the preparation of a Purchase Requisition (PR) and subsequent issuance of l U laPurchaseOrder(P0),orwhenadditionalservicesfromtheVendoris l required, through the preparation and issuance of a Contract. l The l lprocurementofservicesisinitiatedthroughthepreparationandissuance of a Contract. l l The preparation, review, approval and issuance of these l lprocurementdocumentsistobeinaccordancewithapplicableprocurement l and contract administration procedures. l Purchase Orders for items are l lissuedthroughtheAP&LPurchasinggroupandContractsforitemsand/or l~ l services are issued through the AP&L Contracts Administration group. l l l ' l 1 l l 4.2.2 l l l l l 1 l l Procurement documents are to include or reference specific design I lspecificationsfortheitemsorservicestobeprocuredwhichdefine I specific codes, standards, tests, inspections, 2nvironmental , l I I I I I I I I I r3 l l l V l A l TOPICAL REPORT lREV. 6 l l P l l lDATE 6/10/83 1 1 & I SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL IPAGE 4-1 l l L l l l l l _I I l l I i l l qualifications, and records to be applied and/or furnished. For standard l ,3 "of f-the-shelf" items, reference to the items catalog number and O _ l identification number may be included on the procurement document in lieu l l lofadesignspecification. New or revised specifications for replacement l items are to be evaluated by the responsible engineering organization l l lagainsttheoriginalspecificationfortheitem. The evaluation is to be l in accordance with applicable engineering procedures and results in the l l lestablishmentofnewbaselineandtechnicalqualityrequirements,which l are to be used for subsequent procurements. l 1 l l 1 l 4.2.3 l - 1 l l l 1 1 Procurement documents are also to include the identification of quality I assurance program requirements applicable to the items or services l procured. Procurement documents also establish requirements for source l lauditsandinspection,extensionoftheprocurementrequirementstolower l tier suppliers or subcontractors, and preparation and delivery of l I documentation. These requirements may either be in the form of documents _ l attached to the P0 or Contract or by incorporating them in the specific l design specifications. Quality programs are to be specified by invoking i the appropriate sections of 10CFR50, App. B, the appropriate ANS1 l lstandardsand/ortheappropriateAP&Lgeneratedqualityrequirementsfor l items or services. The appropriate sections of the ASME Boiler and l l l Pressure Vessel Code are to be invoked for items originally designed to l meet ASME requirements. l I I I I I l 4.3 REVIEW 0F PROCUREMENT DOCUMENTS 1 I I I i l The responsible Quality Assurance or Quality Control organization, as  ! identified in the LRGO and plant procedures for procurement and contract l administration activities, is to review all procurement documents to l l lassurethattherequiredqualityrequirements(includingsource l surveilla'ce and/or inspection) are imposed on suppliers / contractors. l

• I I

I I I I I I p V I A I. i _I I l l TOPICAL REPORT lREV. 6 l l P I lDATE 6/10/83 l l 1 SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l l L I I i l l I  ! I I I I l 4.4' CHANGES TO PROCUREMENT DOCUMENTS I (] l l l Changes to procurement documents are to have the same degree of control l landreviewasimposedontheoriginaldocuments. Changes such as l inconsequential editorial corrections or changes to commercial terms and l l l conditions may be made by the Nuclear Buyer or Contract Administrator as l appropriate, after concurrence from the originator of the document. l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I o l l l l l 1 I I I I I I I I I l-1 I l 1 1-I I I I I I I l l l 1 I I I I l i I . I I ' I I I I I I I I I I I (v3 I A I TOPICAL REPORT I I IREV. 6 I I P l IDATE 6/10/83 I I & I SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL IPAGE 4-3 l l L I I I I I I I l I l 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS l l l i n l i V . l 5.1 SCOPE l l l l 1 . I l 5.1.1 j l I I I l Instructions, procedures and drawings are provided for the control of l those activities which affect quality and safety at the nuclear plant. l Activities covered by written procedures include, as a minimu.m: - l administrative, general plant operations, start-up; shutdown; power l operation and load changing, process monitoring, fuel handling; l l modification;maintenanceandrepair;radiationcontrol;calibrationand l test; chemical radiochemical control; plant emergencies; test and l inspection; and quality assurance, quality control and LRGO activities in l support of plant activities. The format, content and philosophy of l instructions and procedures are to comply with the guidelines in ANSI l N18.7-1976 and Regulatory Guide 1.33 (2/78) unless otherwise noted in l l Table 1. I l l -, I U 5.1. 2 I I I Instructions and procedures are also provided for the control of l activities relating to the repair, replacement or modifications to ASME l l Code,Section III, Class 1, 2 or 3 components required to be operable to l mitigate the consequences of a postulated accident. l l l l l l 5.2 GENERAL l l 1 l l l 5.2.1 1 I I I I l Instructions, procedures and drawings are to include appropriate l l quantitative criteria such as dimensions, tolerances and operating limits l and/or qualitative criteria such as comparative workmanship samples to l I I determine that important activities have been satisfactorily I I I I I I n i I V I A l TOPICAL REf'GRT I lREV. 6 I l l P l 10 ATE 6/10/83 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-1 l I L l AND DRAWINGS l l l 1 I _. _ l I l l I l accomplished. Each procedure is to be sufficiently detailed so that a l q lqualifiedindividualmayperformtherequiredfuaction(s)withoutdirect I supervision and is to include measures to document the activity being l performed. l I l l l5.2.2 I l l To assure the accomplishment of activities in accordance with approved I instructions, procedures and drawings, each supervisor is responsible for l lqualitycomplianceofhispersonnel. Verification that activities are l accomplished in accordance with approved instructions, procedures and I drawings is obtained through ve.rious levels of surveillance and l inspection by Quality Control personnel and through periodic surveillance l landauditsbytheQAO. l l I g 5.3 REVIEW OF INSTRUCTIONS, PROCEDURES AND DRAWINGS I l 1 5.3.1 l l l Instructions, procedures and drawings are prepared, reviewed and approved l in accordance with applicable plant administrative procedures, when I originated at the plant, or in accordance with applicable Ener5y Supply l procedures, when originated from LRGO. l l l l l 1 l 5.3.2 l l l. I I l Plant procedures identified in the Technical Specifications for each unit l ,I and changes thereto which describe activities required to implement this l l quality program are to be reviewed by the PSC prior to submittal of the l procedures to the Plants' General Manager for approval and subsequent l issuance. Plant Administrative procedures (1000.XX Series) are also l reviewed by the Quality Control staff to verify compliance to AP&L's l l- . I l 1 1 I I I I I O l l V l A l TOPICAL REPORT l 6 l lREV. l l P l lDATE 6/10/83 l 1 & 1 SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l l L l AND DRAWINGS l l l l l I I l I l quality program requirements. LRGO Energy Supply procedures describing I l activities required to implement this quality program are to be reviewed .I and approved by a procedures task force committee and Quality Assurance I to assure compliance to AP&L's quality program requirements prior to I submittal of the procedures to the Department Head responsible for l l implementation,forapprovalandsubsequentissuance. I I l5.3.3 l 1 I lPlantandLRGOproceduresandinstructionsaretobereviewednoless I than every two years to determine if changes are necessary to meet NRC l commitments and current AP&L practices. Applicable procedures,(i.e. I those that relate to the incident cause) are to be reviewed following an l lunusualincidentsuchasanaccident,unexpectedtransient,significant l operator error or equipment malfunction. Applicable procedures are also l l to be reviewed following any modification to a plant system. I i l5.3.4 l o lDrawingsrelatedtoplantchangesandmodificationsarecontrolle g l g i described in Section 3 and 6 to this manual. l l l l 1 I 5.4 CHANGES' TO PROCEDURES I l i I I l 5.4.1 1 I l I~ l l Changes or revisions to approved instructions, procedures and drawings 1 are to be reviewed and approved by the same organizations or groups that I performed the original review unless otherwise noted in specific AP&L i lproceduresandcontrolledinthesamemannerastheoriginal. I I I I I I I . I I I l l 1 1 I O i I A l TOPICAL REPORT i lREV. 6 I l l P l IDATE 6/10/83 l l & 1 SECTION: 5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-3 l .I L i AND DRAWINGS I l 1._ __ _ l - - - - I l l l l l 5.4.2 l l l l ~ ~') (V , l l Temporary changes to approved plant procedures which do not change the l l intent of the procedure may be made provided such changes are approved by l two members of the plant staff, at least one of whom holds a senior l reactors operators license on the unit affected and the change is-l documented, reviewed by the PSC, and approved by the plant's General l Manager within 14 days of implementation. Temporary changes to approved l plant procedures which change the intent of the procedure may, be made l provided such changes are reviewed by the PSC and approved by the Plants' l General Manager prior to implementation. Temporary changes to approved l l plant procedures are to specify the period of time during which they may ,1 be used and made readily available to affected members of the plant l l staff. In the event of an emergency not covered by an approved l procedure, operations personnel may take action, without obtaining l approvals, so as to minimize personnel injury and damage to the facility l and to protect health and safety. l 1 I I I o 1 l l I l l I l l I l l I l l I I I I l~ l l I i l 1 I I I I I I I I I I I I I I I . 1 I I I I I I I I ('~) l l A I I I l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l & 1 SECTION: 5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-4 l l L l AND ORAWINGS I l t i I l . _ _ . _ l l ~ l l l l 6.0 DOCUMENT CONTROL l i l' I / ' . , l 6.1 SCOPE l l l 1 1 l l The various quality program documents identified in Table 3 provide means I to control the review, approval, issuance, use and retrievability of l documents, such as instructions, procedures, specifications, manuals and l l drawings,includingchangesthereto,whichprescribeactivitiesaffecting l quality. l l l l l l 6.2 RESPONSIBILITIES l l l l l l 6.2.1 1 I I I I l Each organization originating documents which prescribe activities l I

affecting quality is responsible for the establishment of document I control procedures which identify individuals or groups responsible for l preparation, review, approval and maintenance of the document and for the l issuance of these procedures to the affected individuals or groups.

O i i l i I l 6.2.2 l l l 1 I I The plant Administrative Manager is responsible for the control and l y issuance of plant procedures, and revisions thereto, to assure t l distribution in accordance with plant procedures. The plant l Administrative Manager is also responsible for the storage arid control of ~ l l approved historical plant documents, and the storage of historical I drawing records. The Engineering and Technical Support Manager is I responsible for the control and issuance of drawings and revisions l thereto to assure that they reflect the as-built conditions of the plant. I I l I I I I . I I I I I l l l O l i I 'd l A l TOPICAL REPORT I I lREV. 6 l l P l lDATE 6/10/83 l l & l SECTION: 6.0 DOCUMENT CONTROL IPAGE 6-1 l l L -1 1 I 1 I I I l L- _ . . 'l l l l l 6.3 IDENTIFICATION l l ] . l I Documents are to be identified by a title descriptive of their purpose or l l l l applicability and marked or stamped as to their current status (Draft, l For Information Only, Void, etc.) per departmental procedures. Revisfors l status of documents are to be identified in document registers, l distribution lists and/or within the revision record page/ block of the l document. l l l6.4 DISTRIBUTION l l l lDistributionlistsand/ordocumentregistersaretobemaintainedbythe l organization responsible for issuance of the document. These lists are l l to identify the revision status of the document and are to be reviewed l and updated periodically by the responsible organization to maintain them l linacurrentstatus. These lists are available to individuals using the l l document to assure they are in receipt of the current document. These j measures are to preclude the possibility of using outdated or l inappropriate documents. O i i l i I l 6.5 CHANGES I I I I I l 6.5.1 l l I I I l Changes to controlled documents are to be reviewed and approved by the l same organizations which performed the original review and approval l unless otherwise specified in departmental procedures applicable to the l I g affected activity. I 1 I 6.5.2 l l 1 lObsoleteorsupercededdocumentsaretobedestroyedormarkedtoprevent t l inadvertent use in accordance with applicable document control I procedures.

. l I

l t l I I l (VT l A l TOPICAL REPORT I 6 I lREV. l P l l lDATE 6/10/83 l l l & l SECTION: 6.0 DOCUMENT CONTROL lPAGE 6-2 l l L l l l l l_ l - - - _ l -I l I I l l l 6.6 STORAGE l 1 'd _l i Documents which affect quality are to be stored and maintained at the I i 1. l.plantinpermanentstoragefacilitiesandcontrolledasdescribedin. l Section 17 of this manual. l I I i i I 6.7 VERlFICATION- l I I I I l Quality Control personnel, through their various levels of quality i I , surveillance and inspection activities, and Quality Assurance personnel, l l through their audit activities, assure proper documents are being used -l and made available to those individuals performing the work. I l l 1 I l l l 1-I l l I I I I I I O l l l 1 1 I I I l l I I I I I I I I I l~ l l I I J-1 I i i l j I ' I I I I l i I I I I I i I . I I I

I l

I I

1 I

O i l A i l TOPICAL REPORT i lREV. 6 i I , l 'P I lDATE 6/10/83 l , I & I SECTION: 6.0 DOCUMENT CONTROL IPAGE 6-3 I i I L I l l I l- 1 I I l l l l 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l l Q .l l 7.1 SCOPE l l l l 1 l I l The purchase of material, equipment and services is controlled to assure l l that, whether purchased directly or through vendors, the material, l equipment and services which affect quality conform to the procurement l documents. Procurement control includes provisions for source evaluation l and selection, objective evidence of quality furnished by the contractor, l l surveillance and audit at the source, and examination of products upon I delivery. The depth and necessity of procurement controls depend upon l the uniqueness and complexity of the item / service, procurement frequency l with the same supplier and past supplier performance for the specific l items or services covered by the procurement document. The control of l purchased material, equipment and services is to be in accordance with l l the requirements of Regulatory Guide 1.38 Rev. 2 (5/77) and 1.123 Rev. 1 l (7/77) unless otherwise noted ii. Table 1. l l l I l l 7.2 SOURCE EVALUATION AND SELECTION O l i l i l l 7.2.1 l l l 1 l l A Qualified Vendors List (QVL) is to be maintained and controlled under l the direction of the Quality Assurance Manager. The QVL identifies l those vendors / contractors that have been evaluated and approved by the l QA0 to furnish material, equipment or services. l l~ I 7.2.2 i l l I l l Vendors /ContractorsareevaluatedandplacedontheQVLbyanyofthe l following methods, as approved by the Quality Assurance Manager: l l l l 1 l ! . I l l l l l 1 1 I O V I I l I i A l TOPICAL REPORT 6 IREV. l l p l lDATE G/10/83 l l & l SECTION: 7. 0 CONTROL OF PURCHASED (PAGE 7-1 l l L l MATERIAL, EQUIPMENT AND SERVICES l l j i l I I l I l l l l (1). Source survey by AP&L to verify compliance to applicable 10CFR50, l I i Appendix B requirements or to applicable ASME Section III Quality I l Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG l components). I I l(2) Evaluation and acceptance of source surveys performed by others l (ex. NRC, ASME, other utilities, NSSS suppliers, and prime l contractors) indicating a program meeting the appropriate l requirements of 10CFR50, Appendix B or ASME Section III. I I I l l l (3) A review of the vendors / contractors current quality records l supported by evidence of documented qualitative and quantitative l information which can be objectively evaluated. This includes l l review and approval of the vendor's/ contractor's quality assurance i program, manual and procedures, when available. (This method is not l y applicable for ASME procurements). l l 1 (4) Evaluation of the vendor's/ contractor's history of providing a l product / service which performs satisfactorily in actual use. l l Evaluation information includes: experience of users of identical l or similar products / services of the prospective vendor / contractor; l l and/or procurement records that have been accumulated in connection l with previous procurement activities and operating experiences. l (This method is not applicable to ASME procurements). l l- ~ (5) Verification that a vendor is a holder of an ASME Certificate of l Authorization may be used in lieu of methods 1 and 2 for ASME l procurements. I I l 7.2.3 I I . l l l Only vendors / contractors listed on the QVL are to be selected for l procurement of material, equipment or services except for items l designated " commercial grade" per plant and LRGO procedures. Standard l l l 1 l i O)

k. l A l TOPICAL REPORT I

6 I lREV. l l P l l0 ATE 6/10/83 l l l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-2 l 1 L l MATERIAL, EQUIPMENT AND SERVICES l l l L I __. I L l l l l 1 l l catalog items may be procured from a vendor / contractor not listed on the .l QVL provided the manufacturer of the . item is on the QVL and all AP&L . I requested documentation originates-from the manufacturer. The QVL is to l l. lbeperiodicallyreviewedandupdated'perqualityassuranceproceduresto  ! l ensure the current status of all selected vendors / contractors is l t lavailabletopersonnelinvolvedintheprocurementprocess. I -l 7.2.4 I I ' l lWhencontractorsareselectedtoperformworkactivitiesattheplant, I their personnel and work activities are to be controlled in accordance l-with plant procedures to assure that the contractor conforms to the l procurement documents. l l -l I I I l 7. 3 SOURCE ~ SURVEILLANCE AND AUDIT l 1 I I l l 7.3.1 l 1 1 I I l The effectiveness of a vendor's/ contractor's quality assurance program is l assessed by QA personnel at intervals consistent with the importance, l complexity, method of receipt and quantity of the products or services.- l I This assessment may be through source surveillance, source audit, receipt l inspection or review of source documentation files. ' l l I I I l 7.3.2 l 1 l 1-l l Requests for source surveillance are made by the originator of the PR/. l Contract,'and/or the responsible Quality Control or Quality Assurance l organization during their review of the procurement document (reference l section 4.3) Source surveillance is to be performed by QA personnel or l l their appointed representative in accordance with surveillance plans l  ; lapprovedbytheQualityAssuranceManagerandtheresultsdocumentedper l quality assurance procedures. Reports documenting inspections performed l I I I l 1 1 I I pJ -l i A l l TOPICAL REPORT i l lREV. 6 l P l I lDATE 6/10/83 l l & l SECTION: . 7. 0 CONTROL OF PURCHASED IPAGE 7-3 l l L :l MATERIAL, EQUIPMENT AND SERVICES I l .l l l l I l 1 l l and discrepancies observed are prepared by the person performing the l surveillance to document compliance to the procurement documents and for J . l future use as historical quality performance data. l 1 l l l 7.3.3 l l l l l 'l l Audits of the vendor's/ contractor's quality assurance programs are l periodically performed under the direction of the Quality Assurance l Manager to verify implementation of a satisfactory quality pr.ogram on the l l items or services being procured by AP&L. Audits performed by others l (e.g., NRC, ASME, or prime contractors), as evaluated and approved by the l lQualityAssuranceManager,maybeusedasanalternativetoauditsby l AP&L to verify the vendor / contractor is implementing a satisfactory l lqualityprogram. Audits are to be conducted in accordance with l Section 18 of this manual. l l l l l l l 7. 4 RECEIPT INSPECTION ' l l l l q l 7.4.1 l l V I I I I l Materials and equipment, including ASME Code materials and equipment, are l subject to inspection upon receipt at the plant. The degree of l inspection is specified in the procurement documents and is to be l performed in accordance with plant procedures for receipt inspection. I l 7.4.2 I I I Receipt inspection activities are to be documented and irwlude, as a j minimum: examination of material or equipment for shipping damage, l proper identification, and quantity; and the review of vendor l documentation, to verify compliance with the procurement document. In l addition, if material and equipment received at the plant were not l inspected at the vendor's facility by AP&L, an inspection is t.o be l l l 1 l l l l l A l I V l A l TOPICAL REPORT l l l lREV. 6 l P l l lDATE 6/10/83 l l & l SECTION: 7. 0 CONTROL OF PURCHASED lPAGE 7-4 l l L l MATERIAL, EQUIPMENT AND SERVICES l l , I l I l l I I l performed by a Quality Control Inspector at the point of receiving to l g- verify that the material or equipment conform to the inspection . I requirements identified in the procurement documents. I I I I I l 7.4.3 I I I I I I Vendors are to furnish documentation as required by the procurement I documents for objective evidence that the material or equipment conforms l to the procurement requirements. Review and acceptance of th.is l I documentation is to be performed by a Quality Control Engineer prior to l l installation or use of such material.or equipment and documented unless l l otherwise specified in plant procedures. Certificates of Conformance may I be required by procurement documents which identify the requirements met i by the vendor. The validity of the vendor's certification program is to I be periodically verified through scheduled source surveillance and audit l , lactivitiesorthroughindependenttestingoftheitembyAP&L. I I l7.4.4 l 1 l' O i l Accepted material and equipment is released, identified as to its i l inspection status and forwarded to a controlled storage area or released l I l for installation per applicable plant procedures. I g i I l7.4.5 l l I l Acceptence of services furnished by a contractor is to be identified in I-g I the procurement documents. Depending upon the service performed, I acceptance may be by technical verification of the data produced, I surveillance and/or audit of the activity, or review of objective i evidence for conformance to the procurement document requirements. The I acceptance method is to be performed by qualified individuals I knowledgeable in the service provided. l I . 'l I I I l I I I ] I l A I l TOPICAL REPORT I IREV. 6 l l l P l lDATE 6/10/83 l l & 1 SECTION: 7. 0 CONTROL OF PURCHASED [PAGE 7-5 l l L I MATERIAL, EQUIPMENT AND SERVICES I l l l 1 _l l.- 1 I I - 7.5 PONCONFORMING ITEMS I 1 I D _l l 7.5.1 I 1 l l l 1 I . I l Nonconformances identified by the vendor / contractor which adversely l l _ affect reliability, performance or interchangeability of the item and i dispositioned repair or use-as-is are to be-submitted to and accepted by I > AP&L prior to closure of the nonconformance by the vendor / contractor. l l 'These nonconformances are to be documented and become part of.the l procurement documentation furnished by the vendor / contractor for the l material, equipment or services procured. -1 I I I - l l 7.5.2 l I I I - l-1 Material and equipment found to be deficient or missing. procurement l documentation during receiving inspection is to be clearly. identified, I segregated from acceptable items and dispositioned per plant procedur'es l and as described in Section 15 of this manual.

7. 6 SPARE PARTS I

' I lSparepartsaretobepurchasedtotheoriginaldesignrequirementsorto l those specified by a properly reviewed and approved revision to the. l I design requirements. The applicable quality assurance requirements and l documentation requirements for spare parts are to be included in the l lprocurementdocuments. l l

7. 7 STORAGE 1

l l Material and equipment are to be handled and stored as described in plant l procedures and Section 13 of this manual. l l l 1 l l I . l l 1 l l 1 1 I Q I l i I l l A l TOPICAL REPORT IREV. 6 l l P l 10 ATE 6/10/83 l l & 1 SECTION: 7. 0 CONTROL OF PURCHASED lPAGE 7-6 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l 1 I l I I I I l 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS l l'3 ' l 8.1 SCOPE l 1 I I I i 8.1.1 l l l 1 1 I Measures for the identification and control of materials, parts and l components, including partially fabricated subassemblies, are to be i established within LRGO and plant procedures. These procedures are to l lrelateanitemofproduction(batch, component,part,etc.)atanystage, I from initial receipt through fabrication, installation, repair or l l modification to an applicable drawing, specification, or other, pertinent I technical documents. These measures are to assure that only correct and l laccepteditemsareusedandinstalled. l l l 8.1.2 l l l l lMethodsfcrthetraceabilityofmaterials,partsandcomponentsto l l specific inspection and test records, when required by codes, standards, l specifications or procurement documents, are to be established within l LRGO and plant procedures and maintained throughout the life or l l consumption of the item. l 1 l8.2 IDENTIFICATION l l l l8.2.1 l~ l l l Materials,partsandcomponentsaretobeidentifiedbythevendorin l accordance with the applicable design standards, codes and/or l instructions specified in the procurement documents. l l l l I I I I I I I I I I I I I O U-I I I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l & l SECTION: 8.0 IDENTIFICATION AND CONTROL lPAGE 8-1 l l L l OF MATERIALS, PAP,TS AND COMPONENTS l l l l l l , _-..-- -, - - - - - - - - ~c ' ' ^ ~ ~ ' ' ~ '

• I I

I I l 8.2;2 I I I r ^'i i i V - l Materials, parts and components are to be identified and/or tagged at the l lplantinaccordancewithapplicableplantprocedures. These tags l l identify the status of and provide traceability to tne item throughout l lstorageandreleasetoinstallation. l l l l8.2.3 l l l l Identification of materials, parts and components is accomplished by l l either marking or tagging on the item or through records traceable to the I item. I I l8.2.3.1 l l l lPhysicalidentificationistobeusedtothemaximumextentpossible. l l Where physical identification is either impractical or insufficient, I lphysicalseparation,proceduralcontrolsorotherappropriatemeansare l I to be employed in accordance with plant procedures. c) im i I I I I l 8.2.3.2 I I I I I l When identification markings are employed, the markings are to be clear, I lunambiguousandindelible,andappliedinsuchamannerasnottoaffect the integrity or function of the item. Markings are also to be l l I ~ transferred to each piece of material (plate, barstock, tubing, etc.) l when subdivided. Large quantities of small items, may be identified by l l applying markings or tags to their shipping packages, boxes or other l l suitable containers. I i i l i l I I I I I I I l l I I I I I I I l l ^', (V I l A l l TOPICAL REPORT l [REV. 6 l l I P l lDATE 6/10/83 l I & l SECTION: 8.0 IDENTIFICATION AND CONTROL IPAGE 8-2 l l L I 0F MATERIALS, PARTS AND COMPONENTS l l l I I I t I I I I I 8.2.3.3 l l l /l D' l l . l Identification markings are to be recorded on records or as-built I documents if current markings are to be hidden or subject to obliteration l l by surface treatment or coatings during fabrication, installation, repair l lormodifications. l l l l8.3 CONTROL l l l lPlantorganizationsreceivingmaterials,partsandcomponentsareto l l Verify that they are properly identified while under their control. l lQualityControlpersonnelthroughtheirsurveillanceandinspection l l activities assure that compliance to these requirements are being met. I lQualityAssurancepersonnelthroughtheirauditactivities,alsoassure l that materials, parts and components are being identified in accordance l i fwiththismanual. l l l l8.4 DEFECTIVE OR INCORRECT ITEMS l n I O l 8.4/1 l 1 I l Defective or incorrect materials, parts and components identified by l l plant personnel or support groups are to be handled in accordance with l lSection15ofthismanualandplantproceduresfornonconformancesand l corrective action. Defective or incorrect items are to be tagged with a l i " hold tag" affixed to the item or otherwise identified per plant l procedures. l~ I I l l I l 8.4.2. I I I l l l Defective or incorrect items are to be stored in segregated areas except I for those items installed or which, due to their size, weight I configuration, etc. , are impractical or impossible to store in the I designated controlled storage acea. I I I I O O I I A I I TOPICAL REPORT I lREV. 6 I l l P 1 lDATE 6/10/83 l l & 1 SECTION: 8.0 IDENTIFICATION AND CONTROL lPAGE 8-3 l l L I 0F MATERIALS, PARTS AND COMPONENTS l l l I - - . - .I I I I I I l 9. 0 CONTROL OF SPECIAL PROCESSES l l O - i l 9.1 SCOPE i l l l l l l l SP ecial processes are to be controlled through the use of qualified l personnel and plant procedures which meet the requirements of applicable l codes, specifications, standards and other criteria stipulated in AP&L l llicensingdocuments. I I l9.2 GENERAL l l l9.2.1 , I I lSpecialprocessesarethoseactivitieswhichrequireinteriminprocess l controls in addition to final inspection to assure quality and include l lsuchactivitiesaswelding,nondestructiveexamination,heattreating, l coating, plating and chemical cleaning. l 1 1 I l 9.2.2 I O i l l i l l Technically qualified LRGO or plant personnel are to establish the l procedural and qualification requirements for those special processes not l covered by existing codes' or standards or where AP&L quality requirements l exceed the requirements of established codes or standards. I I l9.2.3 l I , The requirements for welding and nondestructive examination are to comply l with the applicable portions of the ASME Boiler and Pressure Vessel Code l l or for structural welds, the AWS Structural Steel Code D1.1, and the l American Society of Nondestructive Testing (ASNT-TC-1A-1975 and l supplements). The requirements for cleaning and flushing of fluid l systems. are to comply to the requirements of NRC regulatory guide 1.37, l I g dated 3/16/73 unless otherwise noted in Table 1. I I I O V I A I I I I l l TOPICAL REPORT lREV. 6 l I P l 10 ATE 6/10/83 l l & 1 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-1 l l L l l l l l l _ _ _ l .. . . _- . ~ - - . . . - - - . - - - . A i. l l I . l l 9.3 -QUALIFICATION l l i O . .I i 9.3.1 1 . I I I I i 1. Special process procedures for welding and nondestructive examinations l l are to be qualified prior to use to assure compliance to applicable I codes, standards or specifications. These qualifications are to be I j ldocumentedandalsomadeavailableforreviewtotheCodeInspectorfor 4 l activities on ASME items. l l l l l , l 9.3.2- . l I I I I ~ i Personnel responsible for the performance and verification of special I lprocessesaretobequalifiedand/orcertifiedaccordingtoapplicable I codes, standards, specifications, regulatory guides and plant procedures. ~ l lThesequalificationsandcertificationsaretobedocumentedandmade 1 I available for review to the Code Inspector for activities on ASME items. l I ! Personnel qualification and/or certification records for a special' l l process are to be regularly reviewed by the supervisor responsible for O lthatspecialprocesstoassurethattheappropriatedocumentsare l i i up-to-date and pe'rsonnel are periodically requalified and/or recertified l in accordance with plant procedures. l l I 9.4 RECORDS I I ~~ lTheresultsofspecialprocessesaretobedocumented, reviewed, approved l and stored in accordance with appropriate plant procedures and as l l'addressedinothersectionsofthismanual. l' l I I I I I I I 1 l l- l 1 , . I I I I I I I n i 1 - y i I I I l A l TOPICAL REPORT 6 IREV. 1 P 1 l lDATE 6/10/83 I l & 1 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-2 l l L I l 'I I I I i l I .l I I 10.0 INSPECTION-I 1 i Q v , l 1 10.1 SCOPE I l I 'l ' 'l I I Inspections relating to normal operating activities and inspections l lrelatingtooperatingactivitiescomparableinnatureandextenttothose l occurring during initial plant _ design and construction are to be l l l controlled to assure that inspections ;are performed. in accordance with l l applicable design documents, codes, standards, specifications and l l procedures.' Inspection activities are to be in accordance with l l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1. ~ 1 I I l I l 10.2 GENERAL 1 I i l l l 10.2.1 I I I I ~ l l Inspection activities relating to normal operating activities 1 I l (Operational Inspections) include: I I I l 1) Work functions associated with normal operation of the plant; l 2) Routine maintenance; l l-

3) . Technical services routinely assigned to the onsite operating ~

l organization; and -l

4) .Non-routine maintenance activities and minor modifications made I

by the onsite operating organization that are not comparable in 1 nature and extent to related activities occurring during ~ !r I initial plant design and construction. I I I I i { l 10.2.2 l 1 I I I 1 Inspection activities relating to operating activities comparable in  !

l. nature and extent to rslated activities occurring during design and I l construction (Construction Inspections) include: ,

I l l ' l l I I I I I I A l TOPICAL REPORT 6 IREV. l p l IDATE 6/10/83 l l & -l'5ECTION: 10.0 INSPECTION IPAGE 10-1 s  ! l L 1 I I I I I l 1 I I I , l .1) Non-routine maintenance, except as noted in paragraph 10.2.1; ' I and 1 2) Modifications, except as noted in paragraph 10.2.1. I I I l ~ . l l The following Regulatory Guides are to be applied, as applicable, in l l determining the basis for required construction inspections: R.G. 1.30, l l Rev. 0 (4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77); I lR.G.1.37,Rev.0(3/73);R.G.1.94,Rev.1(4/76);andR.G.1.116, l Rev. 0-R (7/76). l' I I I I I l 10.2.3 I I I I l l Personnel performing inspection activities to verify quality are to be l lqualifiedasstatedinSection2ofthismanual. When inspection I techniques require specialized qualifications or skills, personnel l lperformingtheinspectionaretomeetapplicablelicensingrequirements, l codes and standards appropriate to the discipline involved. l I I I I l i 10.3 CONTROL OF INSPECTIONS 0 l l l 1 10.3.1 1 I I I I I Inspections are to be performed in accordance with approved written i procedures, which set forth the requirements and acceptance limits and I specify the inspection responsibilities. If inspecitions require detailed l l written procedures to perform the task, the procedures are to contain, as ~ l a minimum, the following: I I I I I -l 1) ' Qualitative and/or quantitative acceptance criteria; I

2) Prerequisites for performing the inspection and any limiting l conditions; l

I

3) Identification of any special equipment and tools required to I perform the inspection; I

~ I l l I I I l- l A l TOPICAL REPORT lREV. 6 l P 1 I lDATE 6/10/83 l l & 1 SECTION: 10.0 INSPECTION lPAGE 10-2 I I L i l i I i l l I I I l l 4) A step-by-step description of the method of inspection, I

n. l examination, measurement or test to be performed; and I l

l 5) Identification of those inspection results to be documented. l. l Inspection forms or checklists are to be used as an aid in l l documenting the inspection activity to assure quality I requirements have been met.  ! g I I l10.3.2 l l l lOperationalandconstructioninspectionsaretobeperformedbyqualified .I individuals other than those who performed or directly supervised the I activity being inspected. I y I I l10.3.2.1 l l l g Operational inspections may be performed by second-line supervisory l , I personnel or by other qualified personnel not assigned.first-line l supervisory responsibility for conduct of the work. l w l I g 10.3.2.2 I l lConstructioninspectionsaretobeconductedinamannersimilartothat I associated with construction phase activities in accordance with I applicable plant procedures. I i l 10.3.3 l' l If al inspection determined to be required is impossible or g l l disadvantageous, indirect control by monitoring processing methods, i equipment and personnel is to be provided to verify conformance with l l applicable documented instructions, procedures and drawings. Both l inspection and process monitoring are to be provided when control is l l l inadequate without both. , I l 1 l i I I I I /l D l I I I l A l TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l t l & 1 SECTION: 10.0 INSPECTION lPAGE 10-3 l l L l l l l _ l l I .. .= . - . . I I l I l 10.4 INSPECTION POINTS l l- I . l 10.4.1 l 1 I I I l Inspection hold points are established for non routine maintenance l lproceduresa/iddesignchangepackages'(DCPs)byPlantEngineeringand l reviewed by the Plant Quality Control group for concurrence and possible l l assignment of additional inspection hold points to further assure l conformance with applicable instructions, procedures, drawings and l lrelateddocumentsortomeetappropriatecodeandregulatory l requirements. Inspection hold points for work functions associated with l l activities other than non-routine maintenance and DCPs, may be l established by the originating department or by Quality Control. l 1 1 I I l 10.4.2 l I I I I l Inspection responsibilities, requirements, information and acceptance l ,I criteria for the work activity are to be identified in appropriate, l approved plant documents (e.g. procedures, checklists, etc.) O i l l i l l 10.4.3 l l 1 I I l For work involving the modification, repair, replacement or in-service l inspectu ' _' ASME Code materials, parts and components, the work l packages are to be made available to the Code Inspector prior to l commencing work for his review and assignment of inspection hold p'oints. l The department responsible for the work activity is responsible for l notifying the Code Inspector when the hold point is reached. Work is not l to proceed past a Code Inspector's inspection hold point until signed or l waived by the Code Inspector. I I I I I I I . I I ' I I I I I I I b* l l A l I TOPICAL REPORT l lREV. 6 l l l P J IDATE 6/10/83 I l & 1 SECTION: 10.0 INSPECTION JPAGE 10-4 l l L I I I I I I I , 1 ~ l I 'l l l 10.5 DOCUMENTATION 1 l g- g U ,I , , l 10.5.1 l l l l l 1 Inspections and process monitoring activities are to ce performed and the l results documented in accordance with approved proceddres or l instructions. Records are to: provide objective evidence that the l inspections'and monitoring activities were performed in compliance with _. I procedures, instructions or ' drawings to verify design requirements; show l compliance with acceptance criteria or identify the cause of rejected I items; and identify the eppropriate inspection personnel approving the l lresults. l l 1 l10.5.2 l l ' l Records are to be maintained in accordance with plant procedures and l Section 17 of this manual. Inspection results on ASME code' items are l I

available to the Code Inspector for his review. .

,, 1 1 b 10.5.3 l l l l The results of the inspection and monitoring activities are periodically l evaluated per plant procedures and the results documented to determine l l whether the individual inspection programs demonstrate that the plant can l be operated safely and as designed. l l I I l 1 l 10.6 NONCONFORMANCES l l l  ! l l l Noncomforming items found as a result of inspection and monitoring l activities are identified, segregated and dispositioned in accordance l with plant procedures and.Section 15 of this manual. Rework, repair or l replacement performed after completion of inspections are to require l l l reinspection to the extent necessary to determine acceptiabili,ty to l lestablishedcriteria. I I l - l (3 l l l l l C/ l A l TOPICAL REPORT 6 lREV. _ l l P l lDATE 6/10/83 l l & 1 SECTION: 10.0 INSPECTION l i lPAGE 10-5 l l L l l l l l ! 1 l i I, I .l 11.0 TEST CONTROL l l l (J3 l' l

l. 11.1 SCOPE I I l l 1 l

l A test program is to be established to assure that testing required to l I ~-. l demonstrate that an item will perform satisfactorily in service is I l [ identified, documented, and performed in accordance with written test l l procedures. 'These procedures are to incorporate or reference the I l l ,l requirements and acceptance criteria contained in applicable codes, l standards and specifications and in the licensing documents. These l activities include testing during the operational phases of the plant and l those tests required as a result of modifications, repairs or I maintenance. These activities are also to comply with the applicable l f provisions of Regulatory Guides 1.33, Rev. 2, unless otherwise noted in l Table 1, and with the applicable sections of the ASME Boiler and Pressure l I Vessel Code for ASME designated items. I I I I I I 11.2 PROCEDURES I I w I I I 11.2.1 1 I Written procedures / instructions are to be prepared to describe the l requirements for conduct of the testing activities. These procedures / l ~ instructions are to contain or reference the information required in l Section 5 of this manual and in the applicable Regulatory Guides l I pertaining to Quality Assurance requirements for testing activities. I I i 11.2.2 I I I I I I I Test procedures / instructions and revisions thereto are to be subject to I I .l the same review and approval process as outlined in Section 5 of this l ! 'I ' manual. I -1 I , .l . l l: ~ .I i I l i l l l - l ' I m. (d I I A I l TOPICAL REPORT I IREV. 6 I l l l P l l lDATE 6/10/83 I I & 1 SECTION: 11. G TEST CONTROL IPAGE 11-1 l l L I l 1 1 I I _I . , . ,,y.,,. _.--.m ,- ( c. I - l l l I; 11.3 TEST CONTROLS l l O V . I I 11.3.1 l I l l e I l~ l l Tests relating to plant start-up following a unit shut down or fuel l loading are to be conducted per written procedures / instructions in order l to evaluate plant performance as .the start-up progresses. Initial , j start-up test programs are to be planned to permit safe fuel loading and l start-up, to increase power in safe increments and to perform major l I . I testing at specified power plateaus. l 1 l l I 11.3.2. , ', I I I , I  ; I f Surveillance tests during the operational phase of the plant are to be I l conducted per written procedures / instructions td assure,that failures or l substandard performances do not remain undetected and that the required l operability is maintained to ensure they will continue to operate, l keeping parameters within normal bounds, or will' act to put the plant in I l a safe condition if they exceed normal bounds. O i i l i l i 11.3.2.1 l 1 1 1 1 I Mandatory inplant surveillance tests and inspections required to assure l. I I operation within the limiting conditions of operation are identified in I I l the Technical Specifications applicable to each unit at the plant. To

• l ens /rethattherequiredtestsareperformedasscheduledwithinthe l'

~ l j l l specified time interval, surveillance procedures are established and l I l maintained for.manc'r .!,/ turveillances identified in the Technical s I I

l Specifications T w 7.rocedures are to specify the component or system, l

. type of surve t!au wivity, frequency of activity and the cognizant I l individual responsible for completion of the surveillance activity. l l ', I I I I , . I l 4 i sr I - I 1 I , I I .p'j i A l I I l l TOPICAL REPORT lREV. 6 l l P l l GATE 6/10/83 l l' &. I SECTION: 11.0 TEST CONTROL lPAGE 11-2 l l L l l l l  ! I I I I I .I , l -11.3.2.2 l l 4 l- ~ v' Di l l l Inservice inspections required to meet the requirements of ASME Boil'er i . landPressureVesselCode,SectionXI',aretobeidentifiedinthe -

1. In-Service Inspection (ISI) Programs applicable to each unit at the l l plant. Plant Engineering is to establish and maintain an ISI plan for l each unit. The plan specifies the inspection items, inspection l l

f procedures, inspection intervals and type of inspections. Plant l Engineering is to coordinate the implementation of the ISI pl.ans at l l lappropriatescheduledoutages. The plans are also to be made available l for review by the Code Inspector. ' l l l . I l 11.3.3 I l 1 I I I ' I l Tests following plant modifications, repairs,-maintenance, or significant l lchangesinoperatingprocedures,aretobeconductedtoconfirmthatthey l are not detrimental to the safe and efficient operation of the plant and l l < f that the componer.ts or systems demonstrate satisfactory performance. I I I 11.3.4 I I I I > I Requirements for the given test to be performed are to be identified in 'l the test-procedures / instructions. Evidence is to be available to assure l the following minimum requirements are met: I 1 I I ' a) ' test equipment and measuring devices are calibrated in. ~ j l accordance with the requirements of Section 12 of this manual l and are functioning properly; , l b) test personnel have been qualified to perform the test in l accordance with the requirements of Section 2 of this manual;

I and

' l I g c) appropriate witness and hold point notifications have been [ l provided. , I i 'l I

1 I

I I l I I I l O-' . l A. l TOPICAL REPORT i 6 l lREV. l l P l lDATE 6/10/83 l l l' & 1 SECTION: 11.0 TEST CONTROL lPAGE 11-3 l i I L i I I I I I I ..- -- ,, ,,y,, - , ..w. . . . . . , ,-,.-,,----,--,,...,-,.,,,~,.-,,.,.,,,..-..-,..,m ,. ,, - ,-. - , -m m ,,.~.. _ - i l.

'l l

? l l 11.3.5 l 1 O .l . i l

l. Testing activities.are to be subject to surveillance / inspections in l-accordance with Section 10 of this manual. Testing as a result of

! I repair, modifications, replacement or scheduled inservice tests on ASME l I f l Code'itemsisalsosubjecttoinspectionbytheCodeInspector. The l . assignment of inspection hold points is described in Section 10.of this -l ' ~ l manual. i 1. 11.3.6 l l lTestresultsaretobedocumentedinaccordancewiththeappligable l procedures / instructions. l Test documents are to contain at least the l , lfollowing: ~l l I f (1) Identity of item tested. l (2) Date of test. l (3) As-found condition. l (4). Identification.of individuals performing test. ' 0 , i (5) Test results. l i g-l (6) Corrective actions performed if any. 1 j . (7) As-left condition. ! l ' .I l 11.3.7 ' l 1 l lTestresultsaretobeevaluatedbyresponsibleplantpersonnelperplant l l l procedures to assure that test objectives and inspection requirements l -have been satisified. Non-conforming conditions, are to be identified l and controlled in accordance with Section 15 of this manual. l l -l -l l

.~ l . I l l 4

g l l . I l l , l l l I !- 1 I l' N i ~ d l l A P l l TOPICAL REPORT 1 lREV. 6 I l l l lDATE 6/10/83 l & l SECTION: 11.0 TEST CONTROL IPAGE 11-4 i l L l l l [ t I . __ _ I ..-+,wr e.,-r.,-..,,--,-o-,4y, ,,,,,or ,,,.m...,-.-.--mw, ye-,.i% w..-,w w.w ,,wv.,w w n. ,,w,w,.~,.g..wy I I I-1 I 11.4 RECORDS I I l Q . I l Test results are to provide objective evidence.that'the testing was -l l lperformedincompliancewithapprovedprocedures. Test records are to be 'I maintained and transmitted to the plant Document Control Center for i . retention in accordance with Section 17 of this manual. l l l-l11.5TESTSTATUS l l I l'Inspectionandteststatusistobe'controllhdinaccordancewiththe .1 provisions of Section 14 of this manual. l I l' I I - 1 I I I I I I I 1. I l I l l I l l l-I o l l l I I I l l l l-1 I I l I I I I I l- -I I I l , ~l I

1 ' 1

I I I I

-l I l l i i l i l . I i . l . I' I I i , I I I I 1 I ! 'O- - l A TOPICAL REPORT I I l lREV. 6 l l P l 10 ATE 6/10/83 l l & 1 SECTION: 11.0 TEST CONTROL IPAGE 11-5 I I L l l l I I I I l I I l i 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT l l O _l 12.1 SCOPE 1 i I l I l i 12.1.1 i I I I I i l A program is to be established to assure that devices used for I measurements, tests and calibrations are identified, controlled and i l calibrated against reference standards to assure that accuracy is l I maintained within the limits specified by the inspection or test I requirements. Control of measuring and test equipment is to comply with I the applicable provisions of Regulatory Guide 1.33, rev. 2, pertaining to l measuring and test equipment, unless otherwise noted in Table 1. l I l. I I I i 12.1.2 I 1 l l l l This section does not apply to rulers, tape measures, levels or other l lsuchdeviceswherenormalcommercialpracticesprovideadequateaccuracy. l l l I g 12.2 RESPONSIBILITIES l l I 12.2.1 l l The cognizant Superintendents / group Supervisors at the plant are l I responsible for establishing and maintaining lists of measuring and test I

equipment under their control that require periodic calibration and for l the calibration of this equipment, as assigned within plant procedures. I I

l i l l 12.2.2 I I I I I I The cognizant Supervisor is responsible for identifying measuring and I test equipment required for the activity and assures that the devices are l used only by qualified personnel. , I

j. I I

l l l [ l I

1

(') l l A I l TOPICAL REPORT I I I lREV. 6 I .I P l IDATE 6/10/83 l l & I SECTION: 12.0 CONTROL OF MEASURING IPAGE 12-1 1 I L i AND TEST EQUIPMENT l l l l l l l l l - _ ,_ . . _ , _ _ _ _ . - _ - _ _ _ _ . - ._ _ l l . -1 i 12.2.3 I l l ' (} I l Plant personnel are to be responsible for utilizing only properly l 1 l l identified and calibrated-measuring and test equipment when performing I l inspections and tests for record. .) l I I 12.2.4 I l l l 1 I i l The Manager, Nuclear Quality Control and his staff are responsible for l monitoring test equipment control and use in order to verify compliance l with the program. l 1 I l 1 l 12.3 GENERAL l l l 1 12.3.1 I l l 1 I I I l Calibration procedures are to be established for each type of measuring l and test equipment. These procedures are to conform to recognized codes l and standards and to local, state and federal regulations, and are to be l I referenced on the calibration reports. I I I 12.3.2 I l i 1. I Measuring and test equipment is to be properly controlled, calibrated and l adjusted at specific intervals or prior to use to assure the necessary l ]accuracyofcalibratedequipment. Calibration intervals are to be based l upon the type of equipment, manufacturer's recommendations, stability and l~ l ! reliability characi. eristics, required accuracies, use and other l conditions affecting calibration. l l l l l .I I l l 12.3.3 l l l 1 l -I l l l Reference standards used in the calibration of measuring and test l equipment are to be traceable to the National Bureau of Standards, or if l 1 I l l ! I I I b'N / l A l TOPICAL REPORT I lREV. 6 I l l l P l lDATE 6/10/e; I l l & 1 SECTION: 12.0 CONTROL OF MEASURING ' IPAGE 12 2 l l L l AND TEST EQUIPMENT l l l 1 I I i I I i .I I nonexistent, to accepted industry or AP&L standards. Reference standards I are to have an accuracy at least four times that of the measuring and V- _ l test equipment. In any instance where the four times criteria is unable I to be met, standards.are to have an accuracy level, acceptable l l calibration range, and precision equal to or better than those required i g for the ranges.affected by the calibration. Reference standards are to I be maintained in an environment with temperature, humidity and I lcleanlinesscontrolscompatiblewithmaintainingaccuracyandoperating I characteristics of the standards. I I I I -12.3.4 I l l ) I I I l When measuring and test equipment are found to be out of calibration, an I evaluation of the validity of previous inspection or test results and the I acceptability of items previously inspected or tested is to be made and I documented by written report in accordance with plant procedures. If any I piece of measuring and test equipment is consistently found to be out of I calibration, it is to be repaired or replaced. I O- 1 I U  ; 12.3.5 I I I Recalibration per plant procedures is to be performed when the accuracy 1 of either installed or calibrated equipment is questionable. l l I I I I i 12.4 EQUIPMENT IDENTIFICATION l 1 1 l-I i 12.4.1 l l l l l l I The measuring and test equipment list is to contain sufficient I information to uniquely identify each item listed and is to include as a l minimum, calibration intervals, tolerances and storage locations. The 1 l list is also to identify the group responsible for the control of each I item. . I i l I I I I I I A l TOPICAL REPORT 6 IREV. l P I lDATE 6/10/83 l ! l & 1 SECTION: 12.0 CONTROL OF MEASURING

lPAGE 12-3 l I L I AND TEST EQUIPMENT l

l l l _ i I I I l' l-. . I l . 12.4.2 ~l ~l ~A 1

l I

V l Each item: listed on the~ measuring'and test equipment list is to be l- . tagged,. labeled or otherwise identified per plant procedures in such a l manner that clearly identifies the equipme.nt and its calibration status .l I

and provides traceability to the calibration-records.

I i 12.4.3 I I Measuring and test equipment found to be ~out of calibration is to be l . tagged and segregated from acceptable equipment in accordance with plant. I' procedures until repaired and recalibrated. l l l 12.5 RECORDS I -g i-I Calibration documentation is to be maintained to verify calibration ' -l

l. . status, condition, accuracy and out of tolerance trends of the equipment. l I

I l l 1 -l O. i l i i I 1 l-I I I -l I l-1 I I I I I l-l .I .I ! I I ! I I I I I I , I I j- 1 I i l 1 I I l l l . I I I l i I I l I l Ov I I I l l- A l TOPICAL REPORT IREV. 6 l l P l IDATE 6/10/83 l l & I SECTION: 12.0 CONTROL OF MEASURING IPAGE 12-4 I I L i AND TEST EQUIPMENT l l 1 1 I . I I I I I i 13.0 HANDLING STORAGE AND SHIPPING I I I ("~) - l l 12.1 SCOPE I I I I I I I Activities for the handling, storage and shipping, including cleaning, I packaginr d preservation of materials and equipment are to be performed I in accore with established instructions, procedures or drawings, to i prevent ' damage, deterioration or loss of the item. Activities are to I comply with the provisions of Regulatory Guide 1.38 rev. 2 unless l lotherwisenoted.inTable1. l l 1 13.2 GENERAL I i 13.2.1 1 I lInstructionsforpreservationaretobeprovidedforitemssubjectto I deterioration or damage through exposure to air, moisture,' or other l environments during fabrication, processing, assembly, and interim s I storage periods. . Items are to be cleaned, preserved and packaged as I required to preclude deterioration and prevent damage. When maintenance I of specific internal or external environments are necessary, they are to I be included in special packaging instructions and maintenance procedures. I i 13.2.2 l l l g Procurement documents assure that any special cleaning, preserving, l-y I handling, packaging or shipping requirements for purchased material or i equipment are taken into account. I i 13.2.3 l l l For critical, sensitive, perishable or high value articles, l l recommendations for their handling, storage, packaging, shipping and I I i ! I I I l () l l I A I l TOPICAL REPORT I lREV. 6 I I l l P i l I lDATE 6/10/83 I I & 1 SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-1 l l L i SHIPPING l 1 l_ l _ i I 4 I I I . l i nreservation are to be requested from the supplier per the procurement I ' documents and furnished to the plant prior to or upon receipt of the ' item r _ l- at the plant. l' I I I . 'l ~l ~ -l 13.3 SHIPPING CONTROLS I l-1 -l l .. I 13.3.1 1 I I I I l Shipping requirements are to be specified in the procurement documents. l. 1 lSupplierscompliancetotheserequirementsaretoincludecontrolsto l assure that items are complete and assembled as required; items have been l_ l preserved and packaged in accordance with the procurement c'ocuments; ~ ~, l items have been marked and identified in accordance with specifications l and procurement documents; items have been loaded for shipment in such a' I manner as to prevent damage; and required documentation is complete and l, l furnished in accordance with the procurement documents. I i 13.3.2 I I Special nuclear material and sources are to be shipped and stored as l specified in the AP&L operating license and other appropriate regulatory l documents. The Health Physics Supervisor is responsible for assuring , I that radioactive sources and instruments containing radioactive-sources l are shipped, stored and handled per these requirements and plant

l procedures. The Nuclear Support Supervisor is responsible for assuring I

that special nuclear material (SNM), as defined in plant procedures, are I shipped, stored and handled per these requirements-and plant procedures. l I ' I I I l 13.4 RECEIVING l l l I I l 13.4.1 1 I I I i 1 l Materials and equipment are to be received at the plant per plant .l procedures and subjected to a receipt inspection in accordance with I , 1 1 I l l~ O. l A I TOPICAL REPORT l lREV. 6 I l i P l 4 10 ATE 6/10/83 l l & l SECTION: 13.0 HANDLING, STORAGE AND lPAGE 13-2 l 3 i L l SHIPPING l l t i I I I l I .I l 1 Section 7. of-this manual. As part of the inspection activity, received l materials and' equipment are to be' inspected for damage, deterioration,-- 4 .I cleanliness and proper identification and markings per plant procedures I g for-receipt inspection. i l

l_13.4.2 i I I

l-j g Results of the receiving inspection and disposition.of the material or l g i equipment are to be documented on receiving inspection records.- ) Nonconforming items are to be handled in accordance with plant procedures ' I and Section 15 of this ma sal. [ l I -l

'~ -

I l 13.5 STORAGE CONTROLS l I I i i 13.5.1 I i I I i i .1, I Materials-and equipment which have completed the receiving process _are to' l

i. be stored based on the classification level of storage specified on the i l procurement documents or related design documents.

.$ l l l l l { .I 13.5.2 1 l-i I I l Storage control procedures are to be established which include, as a

• i I

g minimum, provisions for~the following: controlled access and usage of ,i , [ l the storage area; cleanliness and good housekeeping controls; fire I I g protection; protection from environmental hazards; and segregation of I'- g l l hazardous materials. I I I I 1 1 13.5.3 l 1 1 I I l Only items which have completed the receiving process are to be placed in I a controlled storage area. Records of the items' location are to be l 8 provided by the Materials Management Supervisor (see paragraph 13.3.2 for i l l I I I I I I

(]

I I l I -l A l TOPICAL REPORT IREV. 6 l l P. 1 IDATE 6/10/83 l l- & 1 SECTION: _13.0 HANDLING, STORAGE AND IPAGE 13-3 i I L. I SHIPPING i i i i i i 1 I I I l control of radioactive sources and SNM) to identify those items currently l 'I 'I 'in' storage and to facilitate inspection and maintenance planning. O l Issuance of items from storage for installation or use are to be 1 ldocumentedandcontrolledinaccordancewithplantprocedures. l-l l-13.5.4 l 1 I Items identified as requiring maintenance during storage are 'to be i maintained in accordance with a documented maintenance program. I I I I I i 13.5.5 l l l I - I l Storage areas are to be monitored by individuals responsible for the , I storage areas so that the integrity and security of stored items is i effectively maintained. Inspections and examinations under the control I of the Manager, Nuclear Quality Control are to be performed and I documented on a periodic basis to_ assure that the integrity of the items I and their containers are being maintained. Periodic audits under the-l control of the Quality Assurance Manager are also performed to assure l I . compliance to storage requirements. ~ l 1 13.6 HANDLING CONTROLS ! I l i 13.6.1 1 l l lSpecialhandlingrequirementsaretobespecifiedintheprocurement t I documents and plant procedures to protect the quality of items I susceptable to handling damage. Special tools and equipment are to be I provided to handle these items and are to be controlled and maintained l [ per written procedure to assure safe and adequate handling. I I i l I l I . I I I I I l I i i i ~ O- i I A i l TOPICAL REPORT i ' IREV. 6 l l P l lDATE 6/10/83 I 1 & 1 SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-4 ' 1 l L I SHIPPING I I l I I I I .- - . . _ - . , = _ _ . - - _ . - . . - . ~ , . - , . - . . . - _ - . - - . - - - - - _ . . - . . - . . ... . . - _- .- - . - - - . . ~ - . . l I 1 - 1 I -~ l 13.6.2. -l - 1 o.

I i .

i -l Special handling tools and equipment are to be inspected and tested at~ I-specific times in accordance'with written procedures to verify that the I handling tools and equipment are adequately maintained. Inspection and I -test status of these handling tools and equipment are to be controlled in _ I g l l accordance with the applicable sections of this manual. I I 4 l I

l. l' l

l ll l l

I I

l i I 2 I l-1 1 l-

l 1

I l l I '- I 1 I I i- I . I I I I O -l l l i I l , I I I I I 1 I l-l !. I I I r I l

I l-

l' l'

! I I I ! .I I 4 l l l l l l I l-1 I I < 'l l-I I I i- I l I l 1 I -O l l -A l I TOPICAL REPORT l 6 l lREV. I ^ .l .P I lDATE 6/10/83 1 l & 1 SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-5 I a 1 L l SHIPPING a l l - - i l l 1 9 ee- .*,-w-..e----e----.---.~.,-+-.,,....,- , .-.-,-.,4se,-.--ywr, .-.,www-. , ,, ,e.--, c.+--,---+--r *,-ea--ww.- -,w-,-,.e-,.=>m-. I I I I l 14.0 INSPECTION, TEST AND OPERATING STATUS I I I (~') l l L' l 14.1 SCOPE I I I I I I 14.1.1 l l l 1 1 I The removal from service, inprocess status and return to service of l 1 g equipment, components and systems for maintenance, modifications, repair, I g I test or inspection is to be controlled per established plant. procedures. l I g These controls are to assure that plant personnel are aware of equipment, g I I structure or system conditions and to prevent their inadvertent use l lunlessclearedbyoperationpersonnel. l l l l l 14.1.2 l I I I l Maintenance activities are to be performed in accordance with an I g i established maintenance program to assure that equipment, systems and I structures are maintained in a condition which allows them to perform '3 ., l their intended function. l v! I g I I 14.2 EQUIPMENT CONTROL I I I I I I 14.2.1 I I I I I l Prior to removal of equipment, components or systems from service for I I g maintenance, modification, repair, test or inspection activities, l-I permission is to be received and documented from the Shift Supervisor. l The Shift Supervisor is to assure that the item can be released without I affecting plant safety. 1 I l l l l l l l 1 I i . 1 I I I I I I I I fl L l I l I l A I TOPICAL REPORT 6 lREV. l l P l lDATE 6/10/83 l l & 1 SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-1 l l L I OPERATING STATUS I l l I I I I l -l l 14.2.2 l -l l l The status of equipment, components and systems during these activities-I l , is to be identified-in accordance with plant procedures / instructions, l which contain, as a minimum, the' following: l l I 1 l l 1) l methods for control of equipment to maintain personnel and I reactor safety and to avoid unauthorized operation of equipment l or: systems. I l -I I -l l 2) the use of. markings a.other suitable means to indicate the l status of-activities being performed upon individual items. l l Suitable means are to include identification numbers which are l -l traceable to records of the status of these activities. _ l i 'l 3) provisions for the identification of items which have l' ~ satisfactorily passed the required activities. In cases where. l l required' documentary evidence is not available, the associated I equipment or system is to be considered nonconforming and l handled in accordance with Section 15 of this manual. 1 l ~ l 4)- provisions'for independent verifications, where appropriate,'to l l ensure that necessary measures such as locking or tagging to l secure and' identify equipment or systems in a controlled l status, have been_ implemented correctly. l l l l' l l 14.2.3 I I I I I l When entry into a closed system is required, control measures are to be i established to prevent entry of extraneous material and to assure that I g l foreign material is removed before the system is reclosed. I I I I I I . I I I I I I l l 1 -1 A TOPICAL REPORT REV. 6 l

l. Ps l lDATE 6/10/83 I I & I SECTION: 14.0 INSPECTION, TEST AND IPAGE 14 2 l l L l OPERATING STATUS l l l l l l

I I I l l 14.2.4 I I I C) L . l . l During maintenance or modification activities, certain portions of I I l systems,asidentifiedinplantprocedures,maybe~subjecttopotential I contamination with foreign materials. To prevent such contamination, I control measures, including measures for access control, are to be i established. Immediately prior to closure, an inspection is to be l lconductedtoassurecleannessandtheresultofsuchinspectionistobe I documented. I I I I I i 14.2.5 l I I I I l If temporary modifications (such as temporary bypass lines, electrical I l l

jumpers, lifted electrical leads and temporary trip point settings) are l I required for a system or piece of equipment, they are to be performed in I accordance with plant procedures. A status log is to be maintained by I g

l the Shift Supervisor, identifying the current status of such temporary I modifications. Temporary modifications are to be verified by individuals l l independent of the group performing the activity and documented to assure l l V the required actions are taken to return the equipment or system to its I original operating configuration and status. I I I I I i 14.2.6 l l l 1 l I l When equipment or a system is properly identified as being ready to be l l returned to service, the appropriate Shift Supervisor is notified and ~ l initiates the proper operation procedures. Testing of the equipment or i I system for functional acceptability is to be in accordance with l Section 11 of this manual and documented to verify current status of the 1 item. I I I I I I I I . I l l l I I l I. I pd I l A I TOPICAL REPORT I I I lREV. 6 l l P l lDATE 6/10/83 l l & 1 SECTION: 14.0 INSPECTION, TEST AND IPAGE 14-3 l l L l OPERATING STATUS I l l l l l 1 i r __ _ . . _ . _ . __ _ _ . - - _ _ - -- --- - -- -l I l i 14.2.7 I l 1. /"3 I I V , l Equipment, structures and systems found to be nonconforming as a result I l of an activity are to be handled in accordance with plant procedures and l Section 15 of this manual. l l l 1 l l 14.3 MAINTENANCE CONTROL I I l 1 i 14.3.1 I l l l 1 I I In addition to the requirements and controls identified in paragraph 14.2 l of this section, a maintenance program is to be planned and scheduled l through the Maintenance Manager to assure that the safety of the plant is l l not compromised nor the Technical Specifications violated. Maintenance I activities are to be performed per plant procedures and instructions and l conducted in a manner to assure quality at least equivalent to that l specified in the design documents, material specifications and inspection I requirements. As experience is gained in operation of the plant, routine . I maintenance may be altered to improve equipment performance and b V l procedures for repair of equipment are to be improved as directed by the I l y 1 Maintenance Manager. I I I l i I 14.3.2 l l l l l l A preventive maintenance program, including procedures and instructions l for systems, structures and components, is to be established and ~ l maintained under the Maintenance Manager which prescribes the frequency I and type of maintenance to be performea in order to preclude equipment I malfunctions. The program is to be implemented by qualified maintenance I personnel in accordance with written procedures and instructions which l specify the work activities, acceptance requi,rements and the control l measures to assure adequate quality. When equipment malfunctions occur, I the cause is to be promptly determined, evaluated and recorde,d per plant I procedures and Section 16 of this manual.  ! g I I I I O I d I A I l TOPICAL REPORT I lREV. 6 I I l P l 10 ATE 6/10/83 l l & l SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-4 l l L I OPERATING STATUS l l l 1 I l I I I I l -14.4 '0VERALL PLANT' STATUS l 1-A i I

V .

l 'The Shift Supervisor'is to maintain sufficient knowledge of the overall 1 -l l g plant status'of equipment, structures and systems to control operation of I g l the plant in a safe manner. .The Shift Operators are to maintain a ready l I J g reference of plant systems, equipment and components alignments, as well- g I I as a status' board summary of their conditions. I l I l-1 l-I I l I I I I I I I I I 1 I I i l i l' l I I I I I I I I I I 'l O i l l i i I .I I - .I .I I I

I I

I l l I I 'l 1-1 I I I i l I i I l ' 1 I I l l i I I l l

I

. I I I 1 I l l I l 4 l I t Q\ - l A I TOPICAL REPORT i 6 I ' lREV. 1 l p l lDATE 6/10/83 1 4 1 & 1 SECTION: 14.0 INSPECTION, TEST AND IPAGE 14-5 I I L l OPERATING STATUS l ' l I  ! l I / I l' I-l l: 15.0 NONCONFORMING MATERIAL', PARTS AND COMPONENTS l l l I N'd - 1 .15.1 SCOPE I l l 1 l l l - Nonconforming items are to -include materials, parts, . components, - l processes and documents that do not conform to app 1'icable regulations,- l codes, standards, specifications, drawings or licensing documents. I Nonconforming items are to be controlled in accordance with approved- I l . procedures to prevent their inadvertant use or installation. These l procedures are to contain measures to assure the prompt identification l and notification, documentation, segregation, technical review, l l ldispositionandverificationofanonconformingitem.' I I I-15.2 GENERAL I ' I I I I I 15.2.1 I l l I l .It_is the responsibility of ecch individual-to identify a nonconforming 4 l condition, whether related to a product, process or documentation, and to l I l report it to their cognizant supervisor for review and concurrence. The I l l initiator is to document the nonconformance on a Nonconformance Report -l ) I (NCR) unless the nonconformance is determined to be a technical I 4 I I l specification violation and/or reportable to the NRC. See paragraph 15.3 l I for reportable nonconformances. I i . .I 1 [ . l l 15.2.2 I~~ . I l l l [ ' Nonconforming items are to be tagged with a hold tag, or otherwise ' l identified per plant procedures, to prevent inadvertant use or l

. I installation of the item. Nonconforming items are to be segregated from I I

I l acceptable items unless they are currently installed or their size, l  ; weight, configuration, etc., makes it impractical to move to a segregated l area. Hold tags.are to remain on the item until the disposition is l I complete per plant procedures. I g I I I I ] l l A 1 l TOPICAL REPORT I lREV. 6 l l l P l lDATE 6/10/83 l l &. I SECTION: 15.0 NONCONFORMING MATERIAL, lPAGE 15-1 l 1 L l PARTS AND COMPONENTS l l l _l l I l I l l 15.2.3 l I l (m l I V _ l Nonconformance Reports are to identify the group responsible for l l ldispositioningthenonconformance. The assigned individual within the I responsible group is to evaluate the nonconformance and confer, as l l appropriate, with interfacing groups to determine its cause and I recommended disposition. The disposition, which may be reject, rework, I l repair or use as-is, and the corrective action taken to prevent I recurrence is to be documented on the NCR. I I I I i 15.2.4 I l l l l l l The initiator of the NCR and his department head are to review the l ldispositionforacceptancepriortoimplementingcorrectiveaction. If I they cannot agree with the assigned individual on the disposition, the l lplantGeneralManageristodecide. For a repair or use-as-is l disposition, a cognizant engineer knowledgeable in the design l l requirements for the affected item is also to review the NCR for l l concurrence of the disposition. Written justification for the_ design D g change, repair or deviation that has been accepted is to be documented to g i denote the as-built condition and is to be made a part of the NCR. I I I I I i 15.2.5 l 1 1 I I l The acceptability of rework or repair of materials, parts, components, I lsystemsandstructuresaretobeverifiedbyreinspectingtheitemas I originally inspected or by a method which is at least equal to the l' l loriginalinspectionmethod. The rework and repair inspection records are l to be documented and become part of the permanent records for the item. l I Upon completion of the corrective action, the Manager, Nuclear Quality l Control is to verify completion of corrective actions in accordance with l I plant procedures and if acceptable, close the NCR. l . I I I I i I i l i I l ]b l I A l l TOPICAL REPORT l lREV. 6 I l l P l IDATE 6/10/83 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-2 l l L l PARTS AND COMPONENTS l l l l l I l l- - I l '15.2.6 1 1 l -Q ~l - l For ASME Code,Section III, Division 1 materials, parts and components 1 I -[ l 'dispositioned repair or use-as-is, the NCR is to be subject to review and-l concurrence by the Code Inspector.- l l l l l .1-15.3 REPORTABLE'NONCONFORMANCES l I 1 ~l-i 15.3.1 I l l

l

-l I Honconforming items or. conditions which are reportable per the Technical l Specifications to the NRC are to be docunanted by the initiator and . l forwarded to the Special. Projects Manager.so thel appropriate report, per I plant procedures, can be prepared. 1 -l 15.3.2 l l l Upon disposition'of the report by the responsible group the PSC reviews l the report for concurrence and possible assignment of additional I corrective actions and forwards the report to.the plant General Manager l for final approval. l I l I i l 15.3.3 I l l l-I . l l The LRGO Licensing section is to be responsible for transmitting approved l I reports to the NRC within the time period specified in the Technical ~ y -l Specifications and Licensing procedures. l l l l 1 -l 15.4 SUPPLIER NONCONFORMANCES l l 1 1 I l ~ 15.4.1 l 1 I l- l -- l Procurement documents are to contain requirements for the , l . vendor / contractor to identify nonconforming conditions to AP&L which l I l l O l l A I l TOPICAL REPORT i IREV. 6 1 l l P -l lDATE 6/10/83 l l l SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-3 l l L l PARTS AND COMPONENTS l l ~l i I I f I ( l I l I violate a technical or material requirement of the procurement document ~ l p and which results in a disposition of repair or use-as-is. All such . I nonconformances are to be reported to AP&L for evaluations and l I I acceptance. g The vendor / contractor is to document such nonconformances on l their applicable nonconformance report which is to be included in the l final documentation package submitted to AP&L, in accordance with the l procurement documents. l l l l l l 15.4.2 l l l l 1 l l Upon receipt of items at the plant, a Quality Control Engineer is to i review any nonconformance reports in the documentation package to assure l the nonconforming conditions have been properly dispositioned and l accepted by AP&L. I I i 15.5 RECORDS I I I 15.5.1 l l l Upon completion of disposition and verification activities, the completed l NCR's, reports, and related documents generated to ensure proper l disposition and resolution of the nonconformance are to be forwarded to I g l and maiatained by the Document Control Jenter. l I I I I l '15.5.2 1 1 1 I-I l The Manager, Nuclear Quality Control is to maintain and issue a monthly l report to the plant General Manager, identifying the current status of I l all open NCR's for management review. I l l I I l l l l l 1 I . l l l l' I I I l I I A I TOPICAL REPORT IREV. 6 l l P l ! lDATE 6/10/83 l l & l SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-4 l l L l PARTS AND COMPONENTS l l

1 I I I

l I l 16.0 CORRECTIVE ACTION l 1 I pd i 16.1 SCOPE i .l j. I I I I l A corrective actions system is to be established to assure that l conditions adverse to plant safety, such as failure, malfunctions, 1 deficiencies, deviations, defective material and equipment, abnormal l ,I occurrences and nonconformances are promptly identified and corrected. l In the case of significant conditions adverse to safety, this. system is l l to' assure that the cause of the condition is determined and corrective I l action taken documented and reported to appropriate levels of management i for independent review. I I I 16.2 GENERAL I I I I I I 16.2.1 I I I l l I When deviations, deficiencies, malfunctions- or other abnormal occurrences l or conditions are encountered, they are to be reported to responsible l l I authorities for review and disposition in accordance with Section 15 of l this manual. l l l l l 1 l 16.2.2 l 1 I l- l l Cognizant supervisors are to review discrepancies discovered during the l course of station operations, and in the case of significant conditions ~ l adverse to safety, initiate action to identify their cause and take l necessary corrective action to prevent their recurrence. Corrective l action measures to resolve the discrepancies and to prevent their l I I recurrence are to be documented in accordance with Section 15 of this I

• I l manual. , l i l l I 1 . I I

I I I I l I i l A l TOPICAL REPORT 6 IREV. l P l 10 ATE 6/10/83 l 1 & I SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-1 l l L l l l 1., I I I l l I l l .16.2.3 l 1 I (v~) _ l l The appropriate plant department head is to review recorded l I nonconformances and .nay specify the need for additional corrective l action. The plant's General Manager is to review the monthly status l reports concerning "open" nonconformance reports and takes appropriate l l action to ensure corrective action is both prompt and prevents I recurrence. If the nonconformance is of a significant condition adverse l l to safety, the plant's General Manager may request assistance.from l ltechnicalsupportgroupsattheplantand/orLRGOtoevaluatethe I nonconformance for final disposition. I l l I I I 16.2.4 l l l l l l Adverse quality or safety conditions discovered by QA or QC personnel l lduringtheirdocumentreview, inspection,auditorsurveillance l l activities, which appear to be of a repetitive nature, are to be i documented on an appropriate report form in accordance with applicable QA I and QC procedures. l I (n) l I l I l 16.2.4.1 l l l l l l The responsible organization to which the corrective action document is I g addressed is to evaluate the adverse condition and document the action I taken to resolve the condition. In the case of significant conditions I adverse to safety, documentation is to include action initiated to ~ l determine cause and to prevent recurrence. I I I I I i 16.2.4.2 I l I I I l The response is to be evaluated by the initiating organization (QA or QC) I to determine the adequacy and completeness of the corrective action l l I I I I i I I ' I I ' (G 'd l l l l I A I TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l l & I SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-2 l l L l l l l l l 1 I I I l l commitments. If the response-is acceptable, the initiating organization .I is 'to perform follow-up action to verify implementation of. the corrective O I i } .. 1 action commitments, document their findings and when acceptable, close , l. out the corrective action document. I 'l l16.2.4.3 l l l-j If the initiating and responding organizatio'ns cannot agree upon a l I ' resolution, it is to be referred to :the next level of management for l- , resolution. The General Manager at the plant and the Senior Vice l President, Energy Supply at LRGO are to have the final decision regarding_ l lresolutionofQCandQAinitiatedcorrectiveaction' documents., ' 1 respectively. l-l !' l l-l l l 16.2.5 I l l~

I l

When vendors furnish products or services that do not conform to the l l _ requirements of the applicable purchase contract and,-in the opinion of-I the Manager,- Nuclear Quality Control, the vendor warrants consideration l 'I ~O i , for reappraisal, the Manager, Nuclear Quality Control is to submit a i .I vendor reappraisal request to the Manager, Quality Assurance for I , determination of action to be taken. Results of the reappraisal, 7 l together with a request for specific corrective actions, are to be. l I' j ' . ltransmittedto-thevendor.If the vendor does not improve his quality l l . assurance system and products as requested,'the Manager, Quality l lAssuranceistoremovethevendorfromtheQualifiedVendorList(QVL)in  ! g'* I accordance with departmental procedures. I I l-I l-I .I I I . I-t I 1 I ! I

- l-I

' I I

• I l

l l

l l

l l l 'l 'Q l l A i l TOPICAL REPORT I lREV. 6 l l l P l lDATE 6/10/83 1 , 1. & l SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-3 l L l L I I l l' 'l I __I - ,+,e -.r7,,,i,.,-- .--..,-.m,.,..e,b.-,.U..,:~-,,,.%.___._ , ,,, ,.- .-,.,.,_,.,-.,,,..-w,-c.,...-m, ,~,m. .,,..,w..,_r. w,_, ..m,,.- 1-4- 1 1 1: l l' 16.3 SIGNIFICANT CONDITIONS I - . I ' l i ~O _ .I 16.3.1 ' 1 I I I I l I Significant conditions are to include, as a minimum, the following: 1 I 4 I I i 1 (1) Conditions that have a direct adverse affect on the safety of I

the plant or personnel.

1 l (2) Conditions that have caused the uncontrolled release of 1 radioactive materials (liquid, solid, gaseous ~or air I g. I particulate) to the environs. l-(3) Trends indicated by nonconformances which could lead to unsafe I plant operations. 'I h (4) :Any condition the plant's General Manager considers to be of~ ~ l major consequence. 1 I l -l 16,3.2 l -1 t l i I l' ' I I When significant condt ions adverse to safety are discovered, the O I g responsible supervisor ahd management personnel are to evaluate the I 1 g l ~ condition and determine if it is a reportable occurrence. Reportable {

occurrences are to be handled as described in Section 15 of this manual-i I and are to be submitted to the PSC and SRC for review. I I

l I

1 16.4 VERIFICATION

'l 1 l 1 l- ' I I Verification by surveillance or audit of the effective implementation of I f corrective actions is to be periodically performed and documented by 1 Quality-Assurance personnel. Audits are to be performed in accordance l L -with Section 18 of this manual. . l l l l l l , I I l' I . I !- .I l 1 I I i 1 ' I O- F l A i l TOPICAL REPORT lREV. 6 l l l P l. IDATE 6/10/83 l I & 1 SECTION: 16.0 CORRECTIVE ACTION IPAGE 16-4 i 1- L I l 1 ! I I , _ __ _ l I ~ a ' .n I l l- ' l l 17.0 QUALITY ASSURANCE RECORDS l 1

• l I

[9 v' l _ l 17.1 SCOPE I I I I I l 17.1.1 ' l 1 g _ I l Documentation covering design, construction, procurement, fabrication, I inspection, mainienance, nonconformance and' corrective action, test and I audit activities is to be filed and stored 'to provide objective evidence I of quality-related activities and to assure the ability to reconstruct I significant events, Control'of records is to be in accordance with l' } lRegulatoryGuide1.88,Rev.2(10/76)unlessotherwisenotedinTable1. g _ - -l g 17.1.2 -l l l Quality assurance records'are to include operating l'ogs, results of l reviews, inspections, tests, audits, matbrial-analyses' qualifications of l I g personnel, procedures, historical drawings, specifications, engineering- l g I reports, calculations, correspondence and related records, pertinent to LO 'I

quality as defined in plant procedures for records management.

l I g i I l17.2 RESPONSIBILITY ,I I i 17.2.1 I, l l l ,I ~ The Plant Administrative Manager is responsible for the establishment, I implementation and maintenance of the records, management program to be i I , used throughout.the operational life of the plant and for ensuring that l l documentation retention requirements comply with applicable technical l specifications, codes and regulations. - l 1 s I 1 I I l-I . I' I I , I l I l .I l T l_ (d l l A l I TOPICAL REPORT 1 lREV. 6 l I P i j l lDATE 6/10/83 l l & 1 SECTION: 17.0 QUALITY ASSURANCE RECORDS lPAGE 17-1 l L l l l l 1-I I l 1 i l . - .~ . . . - . - - l-I e l. I l .17.2.2-l 4 I ' l .I - .f] -- --l AP&L personnel,. other than plant staff, and outside firms that perform I l { work on.the plant'in.the areas of design, procurement, maintenance,

I modification, testing, quality assurance and special nuclear materials i U

laretoprovidedocumentation/certificationrecordstotheplantfor l ~ l 1 subsequent storage and retention by the Plant Administrative Manager. l l l s l i: ^ l -17.2.3.. I ' l I i I I . l- . I Quality Assur?nce personnel are to periodically audit quality-related l l records and' records filing and storage procedures to assure that the -I l N- I records management program is being properly implemented. Audits are to l lbeperformedasoutlinedinSection18ofthis' manual. j l l l

, 17.3 DOCUMENTATION RETENTION-

$ I l l l17.3.1' Lifetime Quality Assu.ance Records 1 -l l17.3.1.1

I

_l I fl< l Lifetime-recordsaredefinedasthosewhichmeetoneormoreofthe t I following criteria: . I l ' l

I I

..- l (1) Those which would be of significant value in demonstrating l l l capability for safe operation. 1- { l q. 1 1 ~ (2) Those which would be of significant value in maintaining, I reworking, . repairing, replacing or modifying the item.

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

l (4) Those which provide required baseline data for inservice l - , g 1 g inspection.  ;

..s 1 I

g. . 1 1

- g

n. l I

l r {.. l .I l d l l A l TOPICAL REPORT 6 i lREV. l l P l lDATE 6/10/83 l

I & 1 SECTION

17.0 QUALITY ASSURANCE RECORDS lPAGE 17-2 l 1 L l l l

l l 1 I , .- m w .~y,.m.---g3.,,w...,,.,--,.7.,, , - , . ,.,,,,_-e , ., , _ . . , - - .. -3,m..,--,,,y,_,_my,3 ,, vwy m_, , _ ,,,,mm,_,.,, w.,%, .., . , . , -,. , _ . . . . . I l l l l 17.3.1.2 I ,l 1 U l Lifetime quality-related records are,to be maintained for the life of the l l particular item while it is installed in the plant or stored for future l use as prescribed in applicable plant procedures for document retention l I and disposition. I I l17.3.2 Non-Permanent Quality Assurance Records l l f l17.3.2.1 l l l l Hon permanent records are defined as those which meet all of the l following criteria: l ' I l l I l I (1) Those of no signiff,7 ant value in demonstrating capability for ' l safe operation. i l , l l (2) Those of no significant value in maintaining, reworking, ' l l repairing, replacing or modifying the item. i 7, I (3) Those of no signifiednt value in determining the cause of an I b l accfdent or malfbnction of an item. - I (4) Those which do not provide baseline data for inservice I inspection. I I ,I 17.3.2.2 l l l Non permanent records are to provide evidence that an activity was l performed in accordance with applicable requirements and be retained for l~ i specified periods as directed by the applicable plant procedures for i document retention and disposition. I I I I I l_ 17.3.3 i !f I I I l Categories of permanent and non permanent records to be maintained and I their. appropriate retention periods are described in plant procedures. I I I I l I (d^'s l A I TOPICAL REPORT I 6 I IREV. l l P l lDATE 6/10/83 I I & 1 SECTION: 17.0 QUALITY ASSURANCE RECORDS lPAGE 17-3 l 1 L I I I I I  : _I r l I l l 17.3.4 I l , I l i b' 1' l l The Manager, Nuclear Quality Control is responsible for receiving, l linspectingandauthenticatingsuchdocumentsasdirectedbyplant l procedures for turnover of quality assurance documents from suppliers to l l AP&L. When approved for receipt by Quality Control, such records are to I be transmitted to the Plant Administrative Manager for filing and l g storage. l l l 17.4 STORAGE I I I I I l17.4.1 l l l Permancnt records are to be stored in a fire rated vault and be: l l (1) Adequately protected from earthquake, flood and similar l hazardous natural phenomena. l (2) Made safe and secure from theft, vandalism and unauthorized m i use. l (3) Adequately protected against environmental deterioration. l (4) Adequately protected against fire. I l I l l l 17.4.1.1 1 1 I I I l The following features or suitable alternatives are to be incorporated in l l the design of the storage facility:  ! g I I (1) Reinforced concrete, concrete block, or masonry construction. l l (2) Coiicrete floor and roof with sufficient slope for drainage; if l a floor drain is provided, a non-return eneck valve shall be l included. I (3) Firo retardant door (two-hour Underwriter's rating minimum). l (4) Sealant applied over walls as a moisture or condensation l barrier. I, I I l_ l l l {#') l A l TOPICAL REPORT l l lREV. 6 l l P l 10 ATE 6/10/83 l l & 1 SECTION: 17.0 QUALITY ASSURANCE FECORDS lPAGE 17-4 l l L l l l l l I I m i I I I I (5) Surface sealant on floor providing a hard-wear surface to l g l minimize concrete dusting. V l (6) Foundation sealant and provision for drainage. l l (7) Forced-air circulation with filter system. l (8) Ory chemical or gas fire protection system. l l (9) No pipe other than those providing fire protection to the l storage facility is to be located within the facility. l 1 l l l 17.4.1.2 l l l l l l l For storage of film and other special processed records, humidity and l ltemperaturecontrolsaretobeprovidedtomaintainanenvironmentas l recommended by the manufacturer and plant procedures. l l l l l l 17.4.1.3 l I I I I i l A list is to be prepared by the Plant Administrative Manager designating l lthosepersonnelwhohaveaccesstothestoragefiles.

o. I l

U 17.4.2 I I i l Plant storage systems are to provide for the accurate retrieval of I information without undue delay and be sufficient to control and account I for records removed from the storage facility. 1 l I l17.5RECORDSINDEXINGANDRECEIPTCONTROL l I l17.5.1 l l l Indexing methods and systems for quality-related records are delineated I in plant procedures for plant records management. I I l l 1 I . I I I I I I I I I (~1 1 I V l A I I I TOPICAL REPORT lREV. 6 l l P i lDATE 6/10/83 I I & 1 SECTION: 17.0 QUALITY ASSURANCE RECORDS lPAGE 17-5 l l L i I I I L. - 1 I I I I I i 17.5.2 I I Q _ l i Records submitted for storage in either lifetime or temporary files are I l l ltobesubjecttothefollowingrequirementsforreceiptcontrol: l l 1 (1) Establishment of a records check list designating the required l quality-related records. l l l (2) Establishment of a system designating criteria for document I inspection to assure that records are accurately completed, I l legible and received in good condition. I (3) A file system to indicate which quality-related documents have l been received. I l l17.5.2.1 l l l lImplementationofreceiptcontrolrequirementsforstorageisthe l responsibility of the Plant Administrative Manager. l I I I I I i 17.6 FINAL DISPOSITION O i l l i l l The plant Administrative Manager is responsible for disposal of l quality related records in accordance with plant procedures for document I retention ar;d disposition, which permits periodical purging of records I retained past their required retention date. I I I I-I ! l l l I I I I I I I ' l I I I I I I . I I ! l L . I l l l l l l l l l O %/ I I I I 1 A I TOPICAL REPORT lREV. 6 l l p l _l lDATE 6/10/83 I I & 1 SECTION: 17.0 QUALITY ASSURANCE RECORDS IPAGE 17-6 l l l L l l l l l l I i , _ _ _ _ _ _ _ _ . . . - _ . - - . - - - - ~ r I I I l 18.0 AUDITS l l l (] . l I 18.1 SCOPE l l l l 1 1 l 18.1.1 I l l l l l l A comprehensive system of planned and periodic audits are to be provided l to assure and verify compliance with all aspects of the administrative l controls and quality assurance program. Audits are to be planned and l l performed in acccrdance with written procedures, plans and checklists and i are to conform to the applicable portions of Regulatory Guides 1.144, l lrev.1(9/80)and1.146,rev.0(8/80),unlessotherwisenoted,inTable i 1. l l l l l l 18.1.2 l 1 1 I I I The audit program is to include provisions to determine the compliance l lwithandeffectivenessofthequalityassuranceprogramincontrolling , l Structures, systems, components and activities in accordance with the l l lrulessetforthinthecodes,standardsandregulationsidentifiedinthe l Introduction of this manual. l l l l l l l 18.2 AUDIT PERSONNEL l l l 1 I l 18.2.1 ' l I l~ l I l The Quality Assurance Manager is assigned auditing responsibility within l this quality program and is responsible for the selection and assignment I of auditors. Auditors are to be independent of any direct responsibility i ,I for performance of the activity which is to be audited and are not to l report to a management representative who has direct responsibility for l the activity being audited. I . I l l l 1 1 I

I I

pd l A l l 1 l l TOPICAL REPORT IREV. 6 l l P l l0 ATE 6/10/83 l l & l SECTION: 18.0 AUDITS lPAGE 18-1 l l L l l l l l I I I 1 I I I i 18.2.2 l l l (l U I l l Auditors assigned auditing responsibilities are to have experience and l-l training commensuate with the scope, complexity and/or special nature of l l the activities to be audited. When audit assignments are made, I lconsiderationsaregiventospecialabilities,specializedtechnical l training, prior pertinent expertise, personal characteristics, education l I and capability. If no one within the QA0 meets these prerequisites

l. completely, technical specialists are to be used to assist in the l lauditingoftheactivity. Technical specialists are to meet the I requirements of paragraph 18.2.1 of this section. I I

I I l l 18.2.3 1 I I I l l Audit personnel are provided appropriate training to assure their I competence for performing the required audits. Proficiency of audit l personnel is maintained by one or more of the following methods: l l I l l l I (1) Regular, active participation in the audit process. I l l (2) Review and study of codes, standards, procedures and I instructions. l l (3) Participation in training or orientation programs. I l l18.3AUDITSCHEDULE l l l 18.3.1 1 I I , Audits are to be performed on a planned and periodic basis in accordance I with an audit schedule. Audit schedules are to be prepared at the I beginning of each year by the QA0 and approved by the Quality Assurance I g l Manager and SRC. I I I I i 1 . I I I I I I I I O i l A i J TOPICAL REPORT i IREV. 6 I i ! P l IDATE 6/10/83 l 1 & 1 SECTION: 18.0 AUDITS lPAGE 18-2 l I L I l l l _ __ l I _ --- I I I i l .l 18. , I l I l (V'1 l Au Jit schedules assure that as a minimum, the following areas are audited l l ' the indicated frequencies within AP&L: l l 1 l (1) The conformance of facility operation to provisions contained I within the Technical Specifications and applicable license l l conditions at least once per year. l l (2) The performance training, qualifications, and retraining of all l l members of the facility management and operations staff, and l the performance, training, and qualifications of new members of l I l the entire facility staff at least once per year. l (3) The results of all actions taken to correct deficiencies l occurring in facility equipment, structure, systems or methods I of operation that affect nuclear safety at least once per six l months. l (4) The Facility Emergency Plan and implementing procedures at l l least once per year. l (5) The Facility Security Plan and implementing procedures at least l n l U l once per two years. l l (6) Any other area of facility operation considered appropriate by l the SRC or the Energy Supply Senior Vice President. l l (7) The Facility Fire Protection Program and implementing l I

procedures at least once per two years.

l l l l18.3.3 [ l I Audits of vendor / contractor activities are to be scheduled as identified I in Section 7, paragraph 7.3.3 of this manual. These audits are to i levaluateandverifytheirqualityassuranceprogram,proceduresand I activities, to assure compliance with the procurement documents, and to l verify they periodically review and audit their suppliers quality l assurance program. l , I l I I I I I I O l l l I l l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 I l & 1 SECTION: 18.0 AUDITS IPAGE 18-3 l l L l l l l_ l l I r l l l l l 18.3.4 g . l l l Q\ ' . l Periodic reviews of the audit programs are to be performed by the SRC or l l their appointed management representative at least semi-annually to l assure that audits are being accomplished.in accordance with the l .I l requirements of the technical specifications, this manual and Regulatory l l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1. l 1 1 I I I i 18.3.5 , 1 I I I i l Regularly scheduled audits may be supplemented, as required, to cover .l lunforeseeneventsorchangedrequirements. I l l18.4AUDITIMPLEMENTATION l 1 l 18.4.1 I l I

Audit plans and checklists are to be prepared by the auditor and approved l by the Quality Assurance Manager prior to performing the audit.

l l lChecklistsaretobeusedduringtheaudittoassurethatall l requirements of the activities audited are addressed during the audit and l l that those procedures and instructions issued to control the audited I activity are adequate. l l l l l l 18.4.2 l 1 ' l-I l l l Upon completion of an audit, a written report is to be prepared whict l l includes at least the following items: i l l I l (1) Description of audit scope and date. l (2) Identification of the auditor (s). l (3) A summary of audit results. I l (4) Details of nonconformances or programmatic deficiencies. l l l 1 I 1 ' I l I O l i A i l TOPICAL REPORT i lREV. 6 l P l l lDATE 6/10/83 l l & 1 SECTION: 18.0 AUDITS lPAGE 18-4 l l L l l l l- 1 I I I I I I l (5) Recommendations for correcting nonconformances or improving the I l Quality Assurance Program, as appropriate. I Os i l l18.4.3 I I Deficiencies identified as a result of an internal audit are to be l recorded on an Audit Finding Report (AFR) by the auditor and issued to l lthedepartmentheadresponsiblefortheareaauditedforcorrective l action. The department head or their assigned designee is to provide l prompt corrective action to the deficiencies identified and document on l the AFR the action taken or to be taken to prevent recurrence. I lAppropriatefollow-upincludingre-auditsbytheassignedauditgroupis l l conducted in the deficient areas to verify proper and timely I implementation of corrective action commitments. Follow-up actions are l to be documented on the AFR. l l 1 1 I I I 18.4.4 l l , 1 I l Audit reports pertaining to plant activities are to be independently l reviewed by the PSC and the SRC to determine if additional corrective l l actions need to be initiated to assure continued safe operation of the l l plant. Audit reports pertaining to LRGO activities are to be l independently reviewed by the SRC. In addition to these reviews, the l audit reports are to be distributed, as a minimum, to the Quality l l Assurance Manager and appropriate levels of management having l lresponsibilityintheareaauditedtoassuretheirawarenessofthe L l findings. l-l l l l 1 l 18.4.5 l l l l l l l Audit results and findings related to external audits conducted by QA l personnel are to be recorded and distributed to the Quality Assurance l l Manager and a designated representative of the audited organization. ~ l l l I l l 1 I I l Q' l A i l TOPICAL REPORT I lREV. 6 I l l P l lDATE 6/10/83 I l & l SECTION: 18.0 AUDITS IPAGE 18-5 I I L l l l 1 I I I I O O O . m 9' PRESIDENT AND CHIEF r EXECUTIVE OFFICER ____m_ f n e.-e o C = m W CORPORATE COMMUNICATIONS SR.VICE PRESIDENT S > VICE PRESIDENT ASSIST. TO THE PRESIDENT o. ! F --t O o i O m eme % o 7 > b I H m m m

m O O ENERGY SUPPLY ENERGY DELIVERY 8 FINAME REGULATION ADMINISTRATIVE CONSERVATION 8

= SR. VICE PRESIDENT SERVICES 8 LEGAL SERVICES S ERVICES ~ RENEWABLE SR.VICE PRESIDENT SR.VICE PRESIDENT VICE PRESIDENT $ ASSIST. SEC. 8 RESOURCES VICE PRESIDENT t d O ASSIST. TREASURER = me= iE;E Q . ARKANSAS POWER 8 LIGHT CO. , CORPORATE ORGANIZATION s H OO ) O N CO W e=mme === - s--- - - mm amme e=== - mm== - a==-> - am-m emme a--- e--s - eas. e _ smo - _ esso _ mamm _ - _ enum ---s _ a--a _ _ _ _ - _ _ _ _ _ _ _ _ _ _ .a ae r-l l , I I I 1 i O .I l 1 i I l PRES / DENT AND CHIEF l l EXECUTIVE OFFICER l l 1 l I 1 I I ADMINISTRATIVE SERVICES I I VICE PRESIDENT I I I I I I I I I l I I CORPORATE PERSONNEL CORPORATE I I SERVICES DIRECTOR SECURITY l DIRECTOR

• l MANAGER l

l l l l-1 1 l PuRCHASiNo a l 1 wSEER I I l l l l O l RURC AS,R. l SUPERVISOR l I l l l 1 NUCLEAR  ! I BUYER ,I I I I I I - l 1 I I I I I I l ll I 1 I I ARKANSAS POWER 8 LIGHT CO. I l CORPORATE SERVICES 1 l I 1 I ~ I i l I I I I I O l A P l TOPICAL REPORT IREV. 6 I I l I & lDATE 6/10/83 I I FIGURE 2. AP&L CORPORATE SERVICES IPAGE F-2 I I L i I I I- 1 I I O O O m Re t~ ENERGY SUPPLY _ _ _ _ _ _ SR. VICE PRESIDENT _ ,,,, l I i i m I l 1 l 5 C I i NUCLEAR OPERATIONS FOSSIL & HYDRO ENERGY SUPPLY m" VICE PRESIDENT OPERATIONS l SERVICES O! RECTOR DIRECTOR D QUALITY p q  :- ASSURANCE O y 1 MANAGER

z H m o I g , ,

g m ANO NUCLEAR LICENSING  ! ANO ENERGY SUPPLY TECHNICAL ENGINEERING $o $ O SES SERVICES MANAGER PROJECT l ADMINISTRATIVE SERVICES SERVICES GENERAL MANAGER MANAGER SERVICES GENERAL GENERAL r-M MANAGER l GENERAL MANAGER MANAGER l MANAGER o I E l. ' E ' C MANAG ER, NUCLEAR ANO FIELD ENERGY SUPPLY DISCIPLINE NUCLEAR OUALITY FUEL SUPERVISOR CONSTRUCTION ! MANAGER TRAINING - ENGINEERING l MANAGER MANAGERS @ CONTROL l rd mam >>m i M M ,<

• CONSTRUCTION l CONTRACT GUALITY CONTROL T_ - a ADMINISTRATION -

,sm m SUPERVISOR MANAGER .--- LINES OF COMMUNICATION Lg LINES OF REPORTABILITY A " ARKANSAS POWER 8 LIGHT CO. ENERGY SUPPLY ORGANIZATION - --_-_____________________ _= _ _______________._ ,___.__________ 4 O o v O T r- '__ ENERGY SUPPLY ______ SR. VICE PRESIDENT l a o I I l m @ ENERGY SUPPLY

l SERVICES l DIRECTOR

.A i i > l I o " I " I 004 '.lTY o L--- ASSCRANCE QQ o> 3 n MANAGER > r- > < z- r-I t wH I i N -< :n I j > m t dM om 3

o QUALITY QUALITY ENGINEERING

} ZE>

• SUPERVISOR ENGINEERING SUPERVISOR (LRGO)

R (PLANT) .; m I i i I QUALITY QUAllTY .' ASSURANCE QUALITY ASSURANCE ASSURANCE ENGINEERS / lNSPECTORS ENGINEERS / AUDITORS l l~~535~ $M2 - AUDITORS mm- , ' LINES OF REPORTABILITY m ?D* --- LINES OF Ao ARKANSAS POWER 8 LIGHT CO. COMMUNICATION y OUALITY ASSURANCE ORGANIZATION w ggggggg----____________M_ , . . E O O O -MMM-M--MM-MMMMM____M_.________.___. ________________________ f T t-- NUCLEAR OPERAT10NS n VICE PRESIDENT m o C l x m us GENERAL MANAGER 3 r-SPECIAL PROJECTS MANAGER N R NUCLEAR , o QUALITY CONTROL E o H D r- 0 m > l . > r- I I " :o m y y 0 QUALITY CONTROL QUALITY CONTROL > ENGINEERS 2 _ SUPERVIS OR A H ! o l o a g QUALITY CONTROL 1 4 N INSPECTORS i -4 M o i i 1 I z ENGINEERING AND ' M AINTENANCE ADMINISTR ATIVE OPERATIONS .-M __ _ TECHNICAL SUPPORT 'CA MANAGER MANAGER MANAGER >>m MANAGER o -4 <:l* - mma m ,sm e H me ARKANSAS POWER S LIGHT CO. 8 NUCLEAR PLANT ORGANIZATION MNM-_MMMM-M M M-MM_M-___M_M_MM___M_M_MM M_______________g__ggg l l 1 I I I I I O l  !! I GENERAL MANAGER f i l l 1 l i i l l c ,,,,7, o ,3 MANAGER uniurguases MANAGER ;j I I il l 'l l ELECTRICAL  ! M AINTEN ANCE - l l OPER ATIONS OPE ATI NS  ! l SUPERIN T EN DENT SUPERIN TE N DENT I I ' I I I l ELECTRICAL

l l UNIT I UNIT 2 SHIFT SHIFT SUPERV SORS  !

l SUPE RVIS O RS SUPE RVISOR S l g I l l 1 . I MECHANICAL  ! l - M AINTEN ANCE O PLANT - PLANT l

0 ER* TORS SUPERINTENDENT l OPERATORS l i

l l , 1 MECHANICAL l OPERATIONS MAINTENANCE -  ! l TECHNICAL SUPERVISORS I l ENG INE ERS I I I. I l l l 18C ~ I8C PLANNING & I ~ SUPERVISORS SUPERINTENDENT suP S0R I I SHIFT S R. l M AIN TE N ANCE ~ M AINTEN ANCE ' l SUPERINTENDENT COOR DIN ATO R  ! I I I I I I ARKANSAS POWER 8 LIGHT COMPANY l l NUCLEAR PLANT ORGANIZATION

• I I

l ' I I I I I I l4 I O P i ToercAL ReeoaT iRev. 6 i i l lDATE 6/10/83 I l & I FIGURE 6. l L AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-6 l 1 l I I I (PLANT OPERATIONS & MAINTENANCE l ~ f l I l I I I o I I j ,i I I II l !I l l ! 1 GENERAL I l MANAGER I I l I I l I I I I l I ENGINEERING S l TECHNICAL l SUPPORT g I MANAGER  ! I I I i i I l , i i TECHNICAL l l PLANT ANALYSIS - PLANT CPERATIONS I g ANALYSIS - , ENGINEERING ASSESSMENT SUPERLNTENDENT SUPERINTENDENT l SUPERINTDEENT SUPERINTENENT g i EMERGENCY i .I I PLANT MECHANICAL HEALTH PLAN - PERFORMANCE - ENGINEERING PHYSICS -  ! I Co0Ron4 tor O i l SUPERVISOR SU=ERvis0R SUPERINTENDENT I i I l RAD NUCLEAR ELECTRICAL HEATH I l CHEMISTRY - SUPPORT - ENGINEERNG PHYSICS - g SUPERVISOR SUPERVISOR l SUPERVISOR SUPERVISOR j i l l CHEMISTRY & I COMPUTER DRAFTING & HEATH ENVIRONMENTAL - SUPPORT l I SUPERVISOR -DRAWING CONTROL PHYSICS SUPERVISOR SUPERVISOR SPECIALISTS I l - 1 1 I I I I I I I I I I I I I I I I I I I l ARKANSAS POWER S LIGHT COMPANY l l I NUCLEAR PLANT ORGANIZATION I I I I I I O lA l P i I top 1 cat ReeoRT iaev. s i l & FIGURE 7. IDATE 6/10/83 l I F-7 AP&L NUCLEAR PLANT ORGANIZATION IPAGE l l L I (PLANT ENGINEERING & TECHNICAL SUPPORT) I I i i I I i I .I I l I l I O l l 1 l .I l !I I I I I I I I l I I II l 4 I I I l GENERAL g MANAGER i l I I I - 1 I I ^ NENN"" l I I I I I I , I I I I O i TRAiNiNo eu Ee>N T -OFFICE sEaviCE. supEnvisOn HUMAN EsOu CE. supEnvisOs MATERIALS MANAeEMENT PLANT CONT oLLe-i sueEnvisOn i l l I I I I I l . 1 I I I ! SECURITY EMPLOYMENT & SAFETY & _ COORDINATOR INDUSTRIAL FIRE I RELATIONS PREVENTION i l COORDINATOR COORDINATORS I l 1 I I I I I I I I I I I I I I I I ARKANSAS POWER 8 LIGHT CO. . I I NUCLEAR PLANT ORGANIZATION I I I I I I O lA l P l l T0eICAL aseoar inev- 6 l IDATE 6/10/82 I l & i FIGURE 8. AP&L NUCLEAR PLANT ORGANIZATION lPAGE F-8 l l L I l I t I I (PLANT ADMINISTRATIVE' SERVICES)I I r- , I I I l l TABLE 1 l . l . I O ' l ARKANSAS POWER & LIGHT'S EXCEPTIONS / INTERPRETATIONS ( i 0F REGULATORY' GUIDES AND ANSI STANDARDS APPLICABLE l- -TO THIS QUALITY ASSURANCE PROGRAM l l l 1 I I I I Regulatory Guide / Exceptions /- ANSI Standard. Requirement Interpretation l General Certain Regulatory The AP&L commitment refers l Guides invoke or 'to the Regulatory Guides and l imply Regulatory ANSI Standards, specifically l Guides and standards identified in this TOPICAL. l l 'in addition to the Additional Regulatory Guides, i standard each ANSI Standards, Guides and I primarily endorses, similiar documents implied or l Certain ANSI Stan-l' or referenced in those l dards invoke or - specifically identified in I imply additional this TOPICAL are not part of l standards. this commitment. l l 1 General Certain ANSI Dur commitment to those l Standards and/or standards applies only to l Regulatory Guides those systems, structures, i extend the scope of and components whose satis- l l applicability to factory performance is l include systems, required to prevent postu- l structures, and lated accidents that could l components whose cause undue risk to undue l satisfactory perfor- risk to the_ health and safety l mance-is required of the public; or to mitigate l for a plant to the consequences of such 'l operate reliably on accidents. Reliable ~ operation l I; I I I l l I I l A l TOPICAL REPORT lREV. 6 l P l lDATE 6/10/83 l l & l SECTION: TABLE 1 lPAGE T1-1 I I L I I I ,l l l _ I L I I l l l "high-value- of the plant may depend upon 1 articles." other systems, structures and  ! g g D . I components which are not I covered by this commitment. l l l lANSIN18.7 Where changes are Consistent with the require-l (Section 5.2.13.1) made to procure- ments of ANSI N45.2.11, para- I ments, they shall graph 7.2, minor changes to l l . be subject to the (procurement) documents, such I same degree of as, inconsequential editorial I control as was used corrections, or changes to I in the preparation commercial terms and conditions I of the original may not require that the re- I documents, vised (procurement) document l l receive the same review and I l approval as the original 1 documents. I I I I l l ANSI N45.2.1 Fresh water criteria The turbidity requirement on I g (Section 3.2) for chlorides, and fresh water is deleted and l Jackson Turbidity the c.hloride requirement is i Units. revised to read "less than l 250 ppm." The turbidity I g requirement for demineralized I water is deleted. I I l' I I I ANSI N45.2.2 " Preliminary visual Inspection after unloading is l Subsection 5.2.1 inspection or exami- sufficient to determine the l nation shall be per- condition of many items. In I g formed prior to special instances, pre-unload-I unloading..." ing examination is performed. I I I l i I I I I I I I I I I O I 1 O I A l TOPICAL REPORT I lREV. 6 I l l P l lDATE 6/10/83 l l & I SECTION: TABLE 1 IPAGE T1-2 I I L I l l l l 1 I l l l- . l l ANSI N45.2.2 The (receiving) Receiving inspection ~is per- l l'Section5.2.2 inspections shall formed in a manner and in an l be performed in an environment which does not . l. area equivalent to endanger the requisite quality .l the level of~ storage: of an item. The. receiving l. [' , l~ requirement for the inspection area environmental l item. controls may b'e less stringent l 4 I 1 1 than storage environmental _ l . requirements for ,that item, l  : however, the short time spent I in the less. stringent receiv- l l ing inspection area shall be l l of such duration that will l not adversely affect ~'the item j l' l being received. l ~l l l l l- l ANSI N45.2.2 ... The 'Special The "Special Inspection" -l !' Paragraph 5.2.3 l Inspection' pro- procedure shall be readily l cedure, complete available t i inspection l with documentation personnel and'may be attached. L 'l- instructions shall to the item or container. l be attached to the l ' item or con- l tainer..." I l l -ANSI N45.2.2 ~ The use or storage ' People working in storage l ' Subsection 6.2.4 of food, drinks, and areas have a right of access l salt dispensers in to water dispensers per OSHA l any storage area is requirements. Additionally, l l prohibited. due to the location and l layout of the building, per-- l I

sonnel may temporarily store l

[ l . I ' l l l l l 1 I h I l I l l l A l TOPICAL REPORT 6 lREV. l l P l lDATE 6/10/83 l l '& l SECTION: TABLE 1 lPAGE T1-3 l

l L l l l

-l i I I

l l l l l lunches in the work place. l l This area is policed'for -l ~ sanitation. l l l l l l ANSI N45.2.2 " Container markings Containers are adequately l l Appendix (A-3') shall appear on a marked for storage, identifi-l A.3.9 (1) Secc:td minimum of two sides cation, and retrieval. l g Group of the container, Multiple marking requirements I l preferably on one are imposed, where necessary. I side and one end." l I ANSI N45.2.2 " Container markings Container markings are of a l Appendix (A-3) shall be...no less sizo which permits easy l lA.3.9(4)Second than 3/4" high recognition.  ! y l Group container permit- l ting." l l l ANSI N45.2.2 " Container marking The information required I l Appendix (A-3)- shall include the in container marking is l A.3.9 following informa- -evaluated on a case-by-l tion..." . base basis. Marking is l adequate in each case. l l l ANSI N45.2.2 "Non-metallic plugs Non-metal plugs and caps are l Appendix (A-3) and caps shall be of a suitably visible color. l brightly colored." lSectionA3.5.1(1) l l ANSI N45.2.2 Plugs or caps shall In cases where plugs or caps l Appendix (A-3) be secured with tape do not snugly fit, additional l I

Section A 3.5.1 (5) or other means as securing devices or measures l necessary to prev'ent which will not be detrimental l accidental removal. to the item will be used.

l l . I l l l 1 I I I O i l A i l TOPICAL REPORT i lREV. 6 l i l P l l lDATE 6/10/83 l l & l SECTION: TABLE 1 IPAGE T1-4 l 1 L l l l l l  ! I , __ = _ - _ . _ E 4 I I l . I l' ANSI N45.2.2 Marking of' items The last paragraph of Section l l Appendix (A-3) not withi,n a con- A.3.9 could be interpreted as _l- Section A~3.9 tainer. prohibiting any direct marking l. on bare austenitic stainless

j. '

-l l steel and nickel alloy metal l surfaces. In lieu thereof, l paragraphs A.3.9. (1) and (2) l

will be used to control l marking on the' surface.of-l

{ l l austenitic stainless steels l l and nickel base alloys subject l to the following limitations: j l l " Marking materials containing l l sulfur, lead, zinc, mercury, l l copper and low melting alloys l l as a basic chemical consti-l l tuent shall not be brought in l contact,'or shall not be'used l on surfaces of corrosion O. ,i resistant alloys. Low sulfur, l-i g l low fluorine and/or low l l l chlorine compounds may'be l used on austenitic stainless l steels." The maximum limits l -l for the above mentioned mark- l- ~ ing materials will be as l l follows: l I . (a) Total inorganic and l l- l organic halogen content l shall not exceed one (1) l l percent. l (b) The sulfur content shall l l not exceed one (1) l percent. I - l l !O l A l TOPICAL REPORT lREV. 6 l l l P l lDATE 6/10/83 l l & l SECTION: TABLE 1 lPAGE T1-5 l l L l l l 1 I I I 9 . _ - - - _ _ _ _ _ _ _ _ _ ~ - _ . - _ . _ . _ l l l l l ANSI N45.2.2 -Inert Gas Blankets There may be cases involving l 1arge 'or complex shaped items I l g [ . .I for which an inert or dry air l. ! purge'is provided, rather l l l than a static gas blanket, in l l order to provide adequate l l protection due.to difficulty l l of providing a leak proof  ! g 'l barrier. In these cases, a i positive pressure purge flow l l may be utilized as an alter- 1 nate to a leak proof barrier.' l I ANSI N45.2.2 Limits halogen and Engineering may allow the use I l Appendix A, sulphur content of of tapes containing greater l A.3.5J2, (1), (a) tape. amounts of halogens after l l appropriate evaluation,  !

however, the quantities shall l

- l not be such that harmful 1 .O i g concentrations could be i ' g I leached or relased by break- I down of the compounds under l expected environmental I conditions. l l l I lRegulatoryGuide General Alternative equivalent l 1.39 ANSI N45.2.3 requirements may be utilized I to cover those situations not I l included in the subject' -l Standard, for example, situa- I g I tions in which shoe covers l and/or coveralls are required - l but material accountability I I is not. In addition, zones I l i I - Q l l A l l TOPICAL REPORT I lREV. 6 I l l P l lDATE 6/10/83 -l l & l SECTION: TABLE 1 - 1PAGE T1-6 l l L l l I l l I l-e ...._.........-.._,,....,.._,.._,-.__....~,_.-...___,_,_..,,._,c._._ _ _ . . _ , , . _ . . . , _ . _ , , _ , , _ _ , _ . _ I I l l l might be combined into the l I ',) l next more restrictive I I l category in order to reduce 1 total number of zones. l l lANSIN45.2.3 Identifies various When this standard is applied, l housekeeping re- its requirements are imple- l quirements, includ- mented in those areas affected l ing cleanliness, by work activities associated l l fire prevention, with modifications, opera-l and fire protection tions, or maintenance as l l which must be determined necessary by Plant l accomplished during Staff. l the progress of I construction. l l l l l l Regulatory Guide Pre-Construction / This section required verifi- l 1.30/ ANSI N45.2.4 Installation Verifi- cation that items.are in I cation satisfactory condition for l Regulatory Guide installation and have not l l 1.116/ ANSI N45.2.8 suffered since initial l receipt inspection. Upon l receipt, items are inspected l l and stored in an environment l which will not adversely l affect the item. Documented l routine inspections and l periodic audits of the storage l areas assure that stored items l l are maintained in satisfactory l conditions. Documentation l of pre-construction verifica-l- tion in addition to documen- l l tation of initial receipt I l l l 1 1 I (~ \-} l l A l l TOPICAL REPORT l lREV. 6 1 l l P l lDATE 6/10/83 l l & 1 SECTION: TABLE 1 IPAGE T1-7 l l L l l l l 1 I I [ _ . - - l i I l l inspection, periodic storage l inspections, and audits of - l storage is not required. l-1 I I I l ANSI N45.2.4 Identifies various These tests will be performed l I g tests to be as determined by Engineering performed. l l or Nuclear Operations based l l upon the significance of I change or modification. l l l l l R.G. 1.58 In addition.. . the AP&L takes exception to this l (Section C.6) candidate should be requirement. AP&L'_s education a high school l l and experience requirements l graduate or have are in accordance with ANSI l l l earned the General N45.2.6-1978. l l Education Development l (GED) equivalent of I a high school

r. l diploma. l

\ l l l l

. l R.G. 1.74/ Definitions of Based upon the guidance of l ANSI N45.2.10 Certificate of ANSI N45.2.13, 10.2, the l Conformance and definitions of these two l Certificate of terms will be exchanged.

l Compliance." l l l l~ i I l R.G. 1.94/ Section 1.4 defines This requirement for rein- l y ANSI N45.2.5 inprocess tests and forcing steel will be l (Section 1.4) states: interpreted to permit taking l the rebar test specimen at l "... samples of these the fabrication shop, prior l tests must be taken to start of fabrication of i l from the lot or the rebar from the heat or l I l l l l l l 1 i fl U l 1 I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l & l SECTION: TABLE 1 lPAGE TI-8 l l L l l l l l l l r I I I I I batch of materials fraction thereof represented l p 'l supplied to the site by the test specimen.~ For ~ l . l for use." these tests performed at the l l fabrication shop, certifica-l tion.shall be available to l l' provideobjectiveevideEce -l l that.the test specimens l represent the material sup-l l plied for use at.the site. I i 1 l . l l ANSI N45.2.5 Requirement: 1 (Section 4.5) Section 4.5, Con-l crete Placement, l l references American l Concrete Institute I (ACI) standards l ACI-305-72, i " Recommended Prac-l tice for Hot Weather l [ I Concreting" and ACI-l 306-66, "Reccamended i Practice for Cold' ' l Weather Concreting." l 1 i i l j l Interpretation: l 1 In order to clarify l use of these ACI 1 standards, we will l l apply the following l I requirements: I I I I I I l . I I I I I l I I I -(] ' I l A l I TOPICAL REPORT I lREV. 6 I l p l l lDATE 6/10/83 l l & l SECTION: TABLE 1 lPAGE T1-9 l l- L l l l l J . I I L 1 I l l 'l L PLACING TEMPERATURES OF CONCRETE: 1 I o l i , -l A. During hot weather concreting: ~ 1 I l 1 -l l Placing temperatu'res.of concrete will be l limited to the following: I i l ' 1. l 1) ' Concrete membirs'less than 3 feet in least , f 4 l - dimension will not exceed 90?F. l~ , l ,_ l

I I

! l .. 2) Concrete members from'3 feet to 6 feet in ~ l l g leastdimensionwillNotexceed70*F. I ' l i

3) Concrete members n: ore than 6 feet in least' l

l l , dimension will have placing temperature as. l l near 50*F'as can be.obtained by use of ice l I as necessary up. to 100 percent of adding l mixing water; and by shading aggregate and l l sprinkling the coarse aggregate the day it- l I g is to be used. Care will be taken so that ! l , no unmelted ice remains in the concrete at 1 l th'e end of the, mixing period. l I i l' l , . B. Duringcoldw$ather1 concreting: l g

I x ,

I ~~ I ~ l In heating.the water and aggregate, live steam l to heat the fine and coarse aggregate shall not' I be used. Thepermissiblerangeforconcrete l l , temperature shall; be as follows: l l l ~ - l ' l l 1) Sections less than 3 feet in least I ~ dimensions: 55 to 75 F. l 1 - . I l ' l l l l  : I 1 I Q :1 l A -1 l TOPICAL. REPORT 1 [REV. 6 I l l P l .. IDATE 6/10/83 l ! l & 1 SECTION: TABLE 1 IPAGE T1-10 1 l L l l l

l__ ~l i I

. - , . - , - - . . , . ~ . . - . . _ . - . . . . . - . . . - - . . - . . . . . _ . - . - - . . . . - . - - . - . . - - 1 " I l l l 2) Mass concrete 3 feet or more in least l I dimension: 45 to 65*F. I .l. l l-l The mixing water and aggregate will be l purchased as required. The materials will be -l j' free of ice, snow and frozen lumps before they ' I enter the mixer. l l- . g. l . l l ANSI N45.2.5 Requirement: l_ I I (Section 4.8) l I l Section 4.8, "In process Test on Concrete and l

Reinforcing _ Steel" states, " Samples for in process l

J l test of concrete shall be taken at the sampling l point in accordance with ASTM C172. This point may I l be at the truck mixer discharge if the last piece l ) l of conveying equipment is a chute, bucket, - - l conveying system, or similar equipment. Pump l l concrete must be sampled from the pump line l discharge." l [ O. I I  ; I I l Interpretation: l 1 l I l-j l For performance of correlation tests, the l l l I requirements of ANSI N45.2.5-1974 shall be I 1 I l followed. l l l'~ ) l l l l ANSI N45.2.5 Requirement: l  ; l, (Section 4.8) I (- l Section 4.8, "In process Tests on Concrete and l I [

1 Reinforcing Steel" contains Table 8 entitled, I I

l " Required In process Tests." The following l I r l modifications to this table will be applied: I 5 1 l . I o 1 I l l l l l .i ! ~l ' I l f] l l A l l TOPICAL REPORT l lREV. 6 1 l

i. l P l lDATE 6/10/83 l 1

I. & 1 SECTION: TABLE 1 lPAGE T1-11 l ! -l L l l l 1 ___ l . I l ..--......,-,r-- m---.=-.-, +..-,...c., - , - - . . , , . ,- -,,. ,-- - -.. ~ ,,m -. ---r-,,,... -m, .~,.-~.,,.-y,.,.,,.,-,..we i 0 ~ t\ r l '( ' - ' l 'l ' a _ _ ij l b l Interpratation: ' a l ]\,3 % I l ( l l . I REINFORCING, STEEL l l l l l l In process testing or reinforcing steel will l l include the mechanical properties of yield I strength, tensile strength and percent elongation l l on full size specimens for each bar size for each I g l 50 tons or fraction thereof from each m.ill heat. l Bend tests are performed during material l l qualification testing only, except as noted below l for bar sizes #14 through #18. I J Q l l /. Table A, " Required Qualification Tests" as applied l to reinforcing steel will include bend tests as l l required by ASTM A615' and summarized below: 1- , l I l, ,,- a) For bar sizes #3 through #11, one full size specimen from largest bar size rolled from each l l

mill heat, unless material from one heat I e differs by three or more disignation numbers. l

,When this occurs, one bend test shall be made l- from both the highest and lowest designation l number of.the deformed bars rolled. l l f b) For bar sizss #14 through #18, Supplementary l l 1 Requirements S1 of ASTM A615 will be applied. l I One full size specimen for each bar size for ,,# f; l l  ; each mill heat. If supplementary requirements I , g are not followed for mill tests, they will be ',' l applied as in process tests. l l ~l l l l l 8 l l l l l l I l O- I l A i l TOPICAL REPORT i i lREV. 6 l l P l lDATE 6/10/83 l l &. l SECTION: TABLE 1 lPAGE T1-12 l l L l l l' l I I .-l y . . - ~ , , ,,,..,,--c.e.-.e

• I I

I I l The above interpretation is' consistent with l Regulatory Guide 1.15, " Testing Reinforcing bars .I for Category I Concrete Structures," Revision 1, l. l December 1972. 1 l l l In process test specimens may be selected at the I rebar fabrication shop, prior to start of I l fabrication of the rebar from the heat or fraction l thereof represented by the test specime.n. l l l l 1 l Acceptance criteria for any failed test l l (qualifications as well as in process) may be the l l same as that for tensile tests specified in l Subarticle CC-2331.2 of ASME Section III, Div. 2 l l Code (1975). This states that' if a test specimen i fails to meet the specified strength requirements, _l l two (2) additional specimens from the same heat and l l of the same bar size would be tested, and if either l l of the two additional specimens fails to meet the O i g , specified strength requirements, the material l i g l represented by the tests would be rejected for the I specified use. Alternative use of rejected l l material under strict control may be subject to l_ evaluation by the Project Engineer. I l 1 ANSI N45.2.5 Requirement: l (Section 4.9) I Section 4.9, Mechanical (Cadweld) Splice Testing i states in paragraph 4.9.4 " Separate test cycles I shall be established for mechanical splices in l horizontal, vertical and diagonal bars, for each I bar size and for each splicing crew. . ." l l . I I I I I I l l l l O- i l A i l TOPICAL REPORT 6 i lREV. l P l l lDATE 6/10/83 l l & 1 SECTION: TABLE 1 lPAGE T1-13 l 1 L l l l 1 I I I I I l I

1. i

=l l l Interpretation: l l 2 O -

1. The terms " horizontal, vertical and diagonal bars" l

i l l will be interpreted to apply respectively to the ^ I following types of splice positions: 1 l l I _ l I a. Hozizontal, including 10* to horizontal l I -

b. Vertical, including 10* to vertical l c. 45 angle, including 10* to 80* angle

] l , I l l l l The words " splicing crew" will be interpreted to l l refer to all members on the project that.are-l- l activitely engaged in preparing and assembling l l cadweld mechanical splices at the final splice I location. Separate test cycles will be established I for each bar size and each splice position. l l l I

ANSI N45.2.12 An individual audit For those routine audits I (Paragraph 4.2.1) plan describing conducted during operations, I the audit to be - a written procedure (s) l l performed shall be covering each audit may be l l developed and utilized. Procedure (s) will l

l documented by the identify the audit scope,- I auditing organiza- -a requirement that individual I tion. This plan checklists be utilized list- l l shall identify the ing requirements which are to I audit scope, the be audited and notification I requirements, the of the audited group. I activities to be - l audited, organiza-I tions to be notified, I the applicable i . I I I I I I I I i > O r l A i l TOPICAL REPORT i lREV. 6 i l l P l IDATE 6/10/83 l l & 1 SECTION; TABLE 1 IPAGE T1-14 I I L l l l l  ! I I "Y l i I I l documents, the I ^ I schedule, and written I (j l l I procedures or check- 1 lists. I I lANSIN45.2.13 The certificate The person attesting to a 1 (Section 10.2.d) should be attested certificate shall be an I to by a person who authorized and responsible l is responsible for employee of the s.upplier, I this quality assur- and shall be identified by I ance function ard the Supplier. I whose function and , I position are I described in the l l Purchaser's/ l Supplier's quality l l assurance program. l I I l l l R.G. 1.64 (Section "While design Consistent with the require- l C.2)/ ANSI N45.2.11 verification by the ment of ANSI N45.2.11, l l designer's immediate paragraph 6.1, design verifi- I supervisor is en- cation may be performed by-l l couraged, it should the originator's supervisor, I not be construed if the supervisor is 'the only l -I tnat such verifi- individual in the organization I ' ~ cation constitutes competent to perform the l the required inde- verification. I pendent design i veri fication, . . . " l l I I I I I I I 1 1 I . I I I I I I I I I P' I I I I l A I TOPICAL REPORT lREV. 6 I p I I lDATE 6/10/83 l l & 1 SECTION: TABLE 1 (PAGE T1-15 l l L l l l l _. I I I m a _ ,w _ ]y,II T - ~ 1 j i d }-_. .y;_' 5_ x - , e m ' ]- ~ ' . _ m mm _ x = \) mMa x x x a_ _ g 2 ~~ _ ,\ is9WnEP A* _ gdq%$ . " ~ &4 _ e m m a n;x- ~ x x x ?5a _ r aec8'caH"'. "?g. ' x. . f _ r - = x _ _ - sM9 c x _ _ _ _ um.wa "mnE _ g *G . ~~ 4 4 _ _ g . sni%g$ 9N 3# =~ . 1- _ an~ x x x = x _ gwu.m =9 sS _ r srN8.Fpp x x x x x x x x x = _ e m u 0 k5r x x

• x _ _. a a

.m _ g=v n9t0" _ a x x _ _ . _ y . _ eer;2s o 2 _ x x x x u.. .. _ x = x _ _ ll _ ~.. _ ". m m m m a X I R h T A M S w n E _ o _ R e m a g U _ D _ e s s. e E _ C _ e m a _ O - l 2 R m. u a P _ _ E - u _ L E B C A N _ _. L- . _ T A _ _R R S T_ _ U S T E W T N E _ )N ( S Y N I E C N , .(_ ,- T l V M A S - M E F M N Q - G- 6 _ - A 1 6 R5DN 5 D R N T [U l R O F N N C ~' 'O T^ T~ .M N s. e . TN O f A ~E' O OA ~- _.j 0 AI L N S- T - _. D' d P S OT DC A O R T S R ~l Tl NG A M $ l LCJ ONTC o? P T TM LR e em L f f'M (N A DA TN R O A V-E EI N O EMA T T N (I m m IE f, N R M ir O T fLsi L IT .M a _ T i O TiDNC M Q D N A R G iO ti oD C E TA NR C TJ T fAC T T-TU~, l P A MR 'A t AETNAMR C6 UE MR f D N O f_ C f. m. == t I iN T O R TN N G A ETL M5 E l N t0N TfO H 5 Go 6C H'h N S Od NAAE C( A ! 3N) e e m m N P 6 (! K E06 'M M NkTNT ALG R M!s t N( _ T D GG TA C0 C R UCl ' T AL# RD)T TFATA TOT TN AI P T A s l~C RU DT[ N N TRUiNL NCBi T D AJ[ . T H N NTT P CfN GRt LioR E I[ I6 7l I NI~ i!bA T ESRIC SOTd OTfO RhiRkTPTFRAH TRANCErD ICf LEGsN0IAN!M O T d A~A i F GICG R llA ITE T f A[ ?. 5 nit OR A G Ai6-Ils5 GEDSF P 0PT i N'R S LIFD fNC-NC G TbNiO tDTAM IFERMf Rf f NCAA f l Py 0D IA2NRWlT T&ilTTfV AO FNNL H R 6 O E } A f' t h6C)Nf[ filBD iNifFA tlI~ s ~CSiFTAS NREVMDS D N i ff R EC0'UFUTRIEPFWO6 CtKNt T T6(FI ~TI FC A OoAtlNCDCD l AeNs CP Ml4RR ZDAI I~ hAOAlO NI i-hC NN6 L RA6DD L T 'BN!P o'TL'N lib f 0 OA DI~$D RT P. L I U$ NTRk!iifR R DA UUD T6RA i R IffT GGl Il't O~U TCTCCCi R f f ETT! O MM 5T O'T tfRk V Tf T f D I~ AhGfREU F LH A GAN~0 T'A W i N S$s ND Nd'0 O A A'CCCeFsW AhtNNt IR V~C3 R'OR-AP'C C (. _ O'ttAAfflO EfBORDkRRNn0Ori DhCCPCP PPDD6Dhv(CC P 6C iurO06ERfOE'AA t ) MN 0p tg . m fs$CCHDNDCRQQJff e _ P7dsCbC __ s e-m. a e m m e m S C E P _. - - S ~ _ = S.~ I 5 I O2 6 1 27 39 44477i i 7 4 21

=

' 1 d'4 3 H D.

C 3 3 ~d -61 ' 2 -no b. 3,1. ~2 2. b. ~0 U1

_ E '0 TU 62 DT 012ODf?60d1D0T

.~ . -

Td 006.'0064 T-6

?.

0 O0 m

e m

u

~

Id 6j00)i 6 6 d d- 6g a

- DT20l 4 0 0 06 O 0 dD 6 6 4 01o 0M'85 26 O 5 U: 0 O0

)66d0d29d1601IO0l e

O 1 -

NPAA 1~

! l'A~P TA~-

1

$ A 7 2. 2b6Tl0cIl2MF1~

P F l- T V ~-

SSF~Ps$PFS$$AsPAAVF PTfT!rF P !fA~ TT1 B TRTTT1 ~

i E7A-'l- 3AT - *

=

m.

a

- fpPFF'PPFF$AP4AvP&

TFPVT I ADhDVl07

' - - - - [lP)IlP

~

~

~~

~

~ -~~ -FT7~177PMD~P7

~.~:

,i PP^'7Pl7~~P]'O_'Lj

[7'

~

f L . ..

9l -

_ > _ 4OTN>r mmmOy M2. m a m

m m

_ Chm mNWO c,.W

- " e

_ V5H>O T- t>f- mN T$m 4N

- r _

- e

~ l-l I

l F l -

TABLE 3 1.

l .

I QUALITY PROGRAM POLICIES, PROCEDURES'AND INSTRUCTION

'O~-

.l I

MANUALS LIST

-l

' l I

I I

-1.

l - 1. -Quality Assurance Program for Operations j-l- I l

I l The' Quality Assurance Program for Operations establishes the l policies and guidelines of the AP&L quality assurance program for

~

its operating nuclear plants.- This prograra is to be followed by all l

.I I j- . organizations' involved in safety related work applicable to l operating nuclear plants.

l

' Ll l

l l

l 2. Energy Supply Procedures Manual l.

l

!' l' l I

1 i l 'The Energy Supply Department - Little Rock General Office -(LRGO) l l employes a system of procedures designated as Energy Supply l'

l ' Department Procedures (ESP) in order to implement Program 'l requirements for the control of design, engineering, nuclear fuel,.

, I licensing, training and procurement activities in support of the l

i. operating plant.

l l

l The ESP's and revision thereto are prepared by Energy Supply'LRGO l'

l personnel, reviewed and approved by the Quality Assurance Manager,. l l the Energy Supply (LRG0) Procedures Task Force and the responsible l' '

department head.

l 1

i l 1-l' l

3. Quality Assurance Procedures Manual

'l l

i' l l  ;

i l i

1 The Quality Assurance Organization employes a system of precedures. l designated as Quality Assurance Procedures'(QAP) in order to assure l- proper implementation of the program. The QAP's and revisions l-thereto are prepared by the Quality Assurance' Organization, reviewed l- l

.I I I I I

I I I Cs l l A l

l TOPICAL REPORT l

lREV. 6 1

l l P l lDATE 6/10/83 l l & l SECTION: TABLE 3 lPAGE T3-1 l l L l l l

l. I I I

I l

l l

l and approved by the Quality Assurance Manager and approved by the l l Energy Supply Services Director and the Sr. Vice President, Energy

_ l Supply.

I I

l 1

I l 4. Quality Assurance Administrative Procedures Manual I l

i I

I l The Quality Nsmrra Organization also employas a system of l procederes designated as Quality Assurance Administrative Procedures 1 (QAA). These procedures provide technical and administrative -l l instructions to the Quality Assurance staff to aid in implementing I g

l their responsibilities within the quality program. I I

l 1

I I 5. Overall Plant Adminstrative Procedures Manual l l

l 1

l l The plant operation organization employes a system of procedures l l designated as Overall Plant Administrative Procedures. These l procedures implement Quality Assurance Program requirements and l l control on site activities. Overall Plant Administrative Procedures l

l and changes thereto are prepared by the plant staff, reviewed by the O

V l i

Plant Safety Committee and approved,by the plant's General Manager. l l The procedures and revisions are also reviewed by the Manager, I i

Nuclear Quality Control to assure that Quality Assurance Program I commitments are met. I I

I i i l i

I 6. Departmental Plant Administrative Procedures i I

I I

I l Each deprtment (operations, maintenance, engineering and technical I suppm t, training, quality control, etc.) at the plant has developed I procedures in support of the Overall Plant Administrative Procedures I j and this Quality Assurance Program. These procedures provide i technical and administrative instructions to the various departments I to aid in implementing their responsibilities within the quality

! l program.

l l l l

1 I

i l

I I

fy' i

A I I I

l I I TOPICAL REPORT lREV. 6 l l P l IDATE 6/10/83 l l & 1 SECTION: TABLE 3 IPAGE T3-2 l l L l l l l I 1 i