ML20094C430

Rev 6 to QA Manual - Operations

ML20094C430
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/30/1984
From:	ARKANSAS POWER & LIGHT CO.
To:
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ML20094C423	List: 0CAN078406, Forwards Rev 6 to QA Manual - Operations.Return Receipt Requested ML20094C430
References
PROC-840530, NUDOCS 8408070485
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.

Copy No.- [

QUALITY ASSURANCE MANUAL O

OPERATIONS ,

J3 SRKANSAS POWER & LIG H T  :

t i. u HELPING BUILO ARKANSAS lO aar ?8 P a 8?sia P PDR

[

c#""% UNITED STATES y' '

, NUCLEAR REGULATORY COMMISSION

,..s ~h  ;

REGION IV

.[ ) S / $11 RYAN PLAZA DRIVE, SUITE 1000

% M ARLINGTON, TEXAS 79011 E 3 0 IB4 Dockets: 50-313 50-368 l'

Arkansas Power & Light Company ATTN: John M. Griffin, Senior Vice President - Energy Supply P.O. Box 551 Little Rock, Arkansas 72203

-Gentlemen:

By letter dated May 4,1984 (John R. Marshall to Richard P. Denise, "AP&L Quality Assurance Manual - Operations"), Arkansas Power and Light Company submitted Revision 6 to the Quality Assurance Manual which incorporated comments made by the NRC staff.

We have reviewed this submittal and find that it satisfies the requirements of q 10 CFR Part 50, Appendix B, and is therefore acceptable.

If you have any questions concerning the above, please contact this office.

Sincerely, W/ mf E. H. J nson, Acting Chief Reactor Project Branch 2 cc:

J. M. Levine, General Manager Arkansas Nuclear One P.O. Box 608 Russellville, Arkansas 72801 m

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-l l l l 1 1 I I I ARKANSAS POWER & LIGHT COMPANY l l' I I I I I I QUALITY ASSURANCE MANUAL FOR OPERATIONS l l l l TOPICAL REPORT I I I I I I I I l l APPROVED: # . DATE: 5/3c/pr 4 I I ~ QUALIT TA3SURANCE MANAGER / I u l l l l APPROVED: / //)/78u/

~ ENERGY SUPPLY SERVICES DATE: d'/JC /f'/

l l DIRECTOR l l 1 1 I I APPROVED: e-

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%N ENERGY SUPPL P DATE: Jy l

SR. VICE PRESIDE

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5/30/84 i

l l & I APPROVAL SIGNATURES I I I L l l l l l l l

I I

l 1

l l RECORD OF REVISIONS l l

73 l

.O l- l l REVISION l l NUMBER DESCRIPTION DATE l l-l l 0 Initial Issue 6/11/74 l l

l l 1 Response to AEC Questions Submitted 12/13/74 l l 11/21/74. Revisions to Section 2, l l 4, and 7 as indicated.

l l

l l 2 Response to NRC Questions Submitted 3/4/75 l l 2/7/75. Procedure Numbers 1005.xx l l changes to 1004.xx (Number Change Only). l l

l l 3 General revision to change AEC to NRC, 9/8/76 l l update organization, reflect NSP l

'l revisions, minor program implementation l l changes. l 1

l l 4 Eliminate Quality Assurance Committee 9/8/77 l l Changes to Procurement Control - l l Qualification of Vendors. Organizational l

l. Changes. Incorporate Technical l l Specification Changes. l

- l l

.l i l 5 Incorporate Organizational Changes 10/10/80 l l and responses to subsequent NRC l l Questions. Incorporate Regulatory l l Guidas and retype document in its l l entirety in standardized format. l 1 I l 6 Incorporate organizational changes, 5/30/84 l l delete procedural references l l throughout manual, and accurately l l reflect current regulatory commitments l l and QA practices related to the j l . safe operation of AP&L nuclear plants. l l Manual has been reformated and retyped l l in its entirety. I l l l l I I I I 1 l

.I I I I I I I I I I 1 I l r~~x I I I I Cl l A l- . TOPICAL REPORT lREV. 6 l l p l lDATE 5/30/84 l l & l SECTION: RECORD OF REVISIONS lPAGE 1 l l L l l l l l l 1 L

t-l l l l l TABLE OF CONTENTS l

..f ,. l l V- l l l Section Subject Tab h Rev. l I i i 1

-l APPROVAL COVERSHEET l RECORD OF REVISIONS

l. TABLE OF CONTENTS TC-1 6 l TC-2 6

.l TC-3 6 l TC-4 6 l

l TC-5 6 l TC-6 6 l l

-- l POLICY STATEMENT A-1 6 l A-2 6 l INTRODUCTION B-1 6 l I I B-2 6 I I l B-3 6 l B-4 6 l B-5 6 l

~

TERMS AND DEFINITIONS C-1 6 l C-2 6 l l I C-3 6 I I l

C-4 6 l I C-5 6 l

l- C-6 6 l l I C-7 6 I l l

C-8 6 l I

i I , C-9 6 I i 1"

l C-10 G l l 1.0 ORGANIZATION 1 1-1 6 l

1-2 6 l I

l 1-3 6 l- l l

1-4 6 l

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I l 1-5 6 l I l I o' l l A i

l TOPICAL REPORT i

lREV. 6 l

l l P l lDATE 5/30/84 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-1 l l L l l l l l l _I

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i 1-6 6 l 7 l 1-7 6

( l l- 1-8 6 l 1-9 6 l 1-10 6 i  !

1 1-11 6 l 1-12 6 l <

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l 1-14 6 l l

1-15 6

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1-16 6 l

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1-17 6 l

l 1-18 6 l I

' 1-19 6 y j

I 1-20 6 l 1-21 6 l

l 1-22 6 l i- l I

1-23 6 l 2 2-1 6 l

( l 2.0 QUALITY ASSURANCE PROGRAM 2-2 6 1

2-3 6 l 2-4 6 l

l 2-5 6 l l

2-6 6 l

l 2-7 6 l I

1 2-8 6 ,

l 3 3-1 6 l 1 3.0 DESIGN CONTROL 3-2 6 l

.l ,3-3 6 l l

3-4 6 l

l 3-5 6 l l

.4.0 PROCUREMENT DOCUMENT 4 4-1 6 l

l 4-2 6 l l CONTROL 4-3 6 l

l' I l

I A I U i i TOPICAL REPORT I

lREV. 6 l

l l A I P l lDATE 5/30/84 l 1

& l SECTI0ti: TABLE OF CONTENTS IPAGE TC-2 l l l L l 1 l l I I

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I l l 5.0 INSTRUCTIONS, PROCEDURES 5 5-1 6 l I

-^< AND DRAWINGS 5-2 6 I 5-) l 5-3 6  !

l' 5-4 6

6. 0 l

l DOCUMENT CONTROL 6 6-1 6 l 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 l SERVICES 7-3 6 l

l 7-4 6 l 7-5 6 l l l 7-6 6 l l 7-7 6 8.0 l

l IDENTIFICATION AND CONTROL 8 8-1 6 l OF MATERIALS, PARTS AND 8-2 6 l

l COMPONENTS 8-3 6 l 9.0 CONTROL OF SPECIAL 9 9-1 6 l

- m l PROCESSES 9-2 6 l L/ 9-3 6 l 10.0 INSPECTION 10 10-1 6 l 10-2 6

_l l l 10-3 6 l 10-4 6 l 10-5 6 l l I 10-6 6 l 1 l 11.0 TEST CONTROL 11 11-1 6 l 11-2 6 l

l 11-3 6 l 11-4 6 l

l 11-5 6 l 12.0 CONTROL OF MEASURING AND 12 12-1 6 l l l TEST. EQUIPMENT 12-2 6 l I I 12-3 6 l 12-4 6 l O l_ l V .l I

A I

TOPICAL REPORT I

6 I

l lREV. l l P l lDATE 5/30/84 l l & 1 SECTION: TABLE OF CONTENTS lPAGE TC-3 l 1 L l l l l l 1 1

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1 I I l l 13.0 HANDLING, STORAGE AND 13 13-1 6 l

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SHIPPING 13-2 6 I U l l l 13-3 6 l I I 13-4 6 I l l 13-5 6 l 1 1 14.0 INSPECTION, TEST AND I 14 14-1 6 I l l t OPERATING STATUS 14-2 6 l I I 14-3 6 I I l y 14-4 6 i C 14-5 6 15.0 l

.l NONCONFORMING MATERIAL, 15 15-1 6 l r PARTS OR COMPONENTS 15-2 6 l

l - 15-3 6 l gg 15-4 6 l

l 15:5 6 l l 16.0 I CORRECTIVE ACTION 16 16-1 j 6 I ,

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, l . 16-2 6 6 l l I 16-3 6 I '

I f 's l 16-4 6 l l 17.0 QUALITY ASSURANCE RECORDS 17 U-1 6 I l ~

l l 17-2 6 l l I 17-3 6 l l l . 17-4 6 l l I 17-5 6 l' l j' 18.0 AUDITS 18 18-1 6 1 18-2 6 l

l 4 18-3 6 l

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18-4 6 I l '

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I I 1 l

-l FIGURES l

,g l l l_ -Number Title Tab P_ age Rev.

-1 AP&L Corporate 19 F-1 6 l Organization l

'2 _AP&L Corporate Services 19 F-2 6 l 3 AP&L Energy Supply 19 F3 6 l Organization

.l 4 AP&L Quality Assurance 19 F-4 6 l Organization l l l 5 AP&L Nuclear Plant 19 F-5 6 l Organization

-l 6 AP&L Nuclear Plant 19 F-6 6 l Organization (Plant I l  ;

l Operations and Main- I i tenance)

.1 7 AP&L Nuclear Plant 19 F-7 6 l Organization (Plant D'

I Engineering and Technical l Support) l l 8 AP&L Nuclear Plant 19 F-8 6 l Organization (Plant l

_l Administrative Services) l I l

'l I l I I i l I I I I I I I I i i l I- 1 I I I I i 1 1 I I i l i I i O l l A i

l 10PICAL REPORT i

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l l P l 10 ATE 5/30/84 l l & I SECTION: TABLE OF CONTENTS i PAGE TC-5 i

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TABLES l I ',

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. Number

.l-I N Title M.  % Rev. l j -1 AP&L Exc5ptions/ Inter- 19 ' T1-1 6 I I s .

I I pretations of Regulatory T1-2 6 l I + "

Guides and ANSI Standards T1-3 I 6

l . I y l ,,

T1-4 6 l

, ', I I

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.-:T1-5 6 l l

l T1-6 6 I I I

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TI-8 6 I

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,% T1-14 l 6 l I .[$ , '

T1-15 6 I l_ ,

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,q 1 ,

T1-16 ,

6 l

' A ,1 1

~2-

+ Qualit.y' As'surar.ce I 19 T2-1 6-l 7 g- .

, I l , Procedures Matrix . ,

I 3- QualityProframPolicies, -'19 T3-1 6 I l  ;

• l '

Procedures

.r and Instruc- T3-2 6 l

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• tion Manuals List -

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, l &' I SECTION: TABLE OF CONTENTS lPAGE TC-6 l

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l ~ ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT I

l

. QUALITY. ASSURANCE PROGRAM FOR OPERATION

~ ,

. It is the policy of the Arkansas Power & Light Company (AP&L), from the l 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 l

l 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, l repair and modifications, and inservice inspection of AP&L Nuclear j' Plants. The: program shall also meet the requirements of the ASME Boiler l l

'and Pressure. Vessel Codes with respect to items constructed, repaired or

-l~ replaced tolCode requirements.

1 I l I

1 --

l l Under the Program the Energy . Supply Sr.- Vice President, is the final l

. management authority responsible for assuring that this policy statement l and the Quality Assurance Program are implemented within AP&L. The l Nuclear Operations Vice President and each Energy Supply Director is l responsible for the. procedural implementation of the program within his l

l

$ ' assigned area. The plant's General Manager is responsible for the daily

~l -implementation of the Program's procedural requirements at the plant.

.O 1

l i

i i

I 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

l I .the Program. I

.l- l 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. Disputes involving quality, arising from difference of l

opinions between QA personnel and other personnel, which cannot be l- settled interdepartmentally, shall be presented to the Energy Supply l Senior Vice President for resolution. ,I 1

I I

I l

l 1

I l . 1

[') -l- l l Os/ l A l. TOPICAL REPORT l

lREV. 6 l l P l lDATE 5/30/84 l l & l SECTION: STATEMENT OF POLICY c , lPAGE A-1 l I L l l l

1. I I I 9 r=.v .,e,- -e- r- r--r---y----- %,--.--.1% -, - . r-e- - * - - - +, --.e ,r.w--.nm .- - .. - -.--,, , , . - ----rs.-- e-e.--

I I i= l l The Quality Assurance Manager is to provide for annual review of the I

. adequacy and overall effectiveness of the Program. Any defects in the I implementation of either this policy or the Program that are revealed l I during the review are to be reported to appropriate levels of management l together with appropriate recommendations. l l 1 I l Implementation of this policy is necessary in order to achieve the

.l l l reliability and safety required at our Nuclear Plants. Each person l I I l involved in activities concerning our Nuclear Plants is to be responsible l for assuring quality in his own work, and for compliance with the l requirements of the Program. The Quality Assurance Program policies, l manuals, and procedures are mandatory requirements which must be l implemented and enforced by all responsible organizations and l individuals.

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I 1

'l J. Griffin '[b( . l I Energy Supply Sr. Vice President I

.I I f3 l l k' l Date: 6 S /-81 l l

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-1 I I I I I I I I I I I I I I I I I l l l 1

-l l I~ l l I I I I I l- 1 I I J l_ l i l l

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-l A I TOPICAL REPORT lREV. 6 l l P. l lDATE 5/30/84 l

~~l & 1 SECTION: STATEMENT OF POLICY IPAGE A-2 l l .. L l' l l l l l l

q

-l l

1 6

l I INTRODUCTION l

'O I I This TOPICAL report (manual) describes the AP&L quality program applied l

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 I Analysis Reports for Nuclear Power Plants Section 17, published by the l i

lNuclearRegulatoryCommission.

l-l The' objective of this program is to control those phases, as applicable,

! l for the design, procurement, manufacture and fabrication, installation, l operation, testing, refueling, repair, maintenance or modification to I existing safety related (Q-List) structures, systems and components that l

, prevent or mitigate the consequences of a postulated accident which may I cause undue risk to the health and safety of the public. The program is l an outgrowth of the principle that quality assurance emanates from each I individual contributor and that management is responsible for creating an l lawarenessof' quality.

O  !

g The AP&L quality program is designed to comply with the requirements of I 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants l

_landFuelReprocessingPlants,andtocomplywiththequalityassurance l

l requirements of the ASME Boiler and Pressure Vessel Code,Section XI for l l repair, replacement,andinserviceinspectionofitemscoveredbythe I Code and Licensing commitments. l 1

I l- 1 l

l l The AP&L quality program is also designed to comply with the NRC l positions contained in the following regulatory guides, subject to I specific exceptions noted in Table 1 of this manual:

l l

1

> l l

l l

1 I

I l

i l

l l

l l l

[-

l l

i (O

l l

l A

P i

l i

TOPICAL REPORT i

lREV. 6

!DATE 5/30/84 i

l l

l l & 1 SECTION: INTRODUCTION lPAGE B-1 l

! l L l l l l l l l

l I

i 1.8, rev. 1-R I l Personnel Selection and Training (5/77) 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 I

g and Electrical Equipment (8/72) l 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 Cooled Nuclear Power Plants (3/73) l 1.38, rev. 2 l QA Requirements for Packaging, Shipping, l Receiving, Storage and Handling of Items l

l For Water Cooled Nuclear Power Plants l (5/77) l 1.39, rev._2 Housekeeping Requirements For Water Cooled l Nuclear Power Plants (9/77)

-l 1.58, rev. 1 Qualification of Nuclear Power Plant l l' Inspection, Examination and Testing l

l

\gJ' Personnel (9/80) l 1.64, rev. 2 QA Requirements For the Design of Nuclear l

l Power Plants (6/76) l 1.74 QA Terms and Definitions (2/74)

l 1.88, rev. 2 Collection, Storage, and Maintenance of l

l Nuclear Power Plant Quality Assurance l

l Records (10/76) l 1.94, rev. 1 QA Requirements for Installation, l Inspection and Testing of Structured l Concrete and Structural Steel During the I l Construction Phase of Nuclear Power Piints l (4/76) 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

1 I

I I

l l

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("J l l k l l A l TOPICAL REPORT 6 lREV. l l P l lDATE 5/30/84 l l & l SECTION: INTRODUCTION lPAGE B-2 l l L 1 l i I I I I

I

'l l' I l

l 1.123, rev. 1 QA Requirements For Control of Procurement l

[[ -l of Items and Services For Nuclear Power

'l' Plants (7/77) l l 1.144, rev. 1 Auditing of Quality Assurance Programs for l

the Nuclear Power Plant (9/80) 1

-1.146~ Qualification of Quality Assurance Program l

l Audit Personnel For Nuclear Power Plants l (8/80) l 1

I g Based upon compliance to these regulatory guides, the AP&L quality I I

l lprogramalsocomplieswiththefollowingAmericanNationalStanda Institute (ANSI) standards subject to exceptions noted in Table 1 of this 1 manual: I l

l l .

l' N45.2-1977 Quality Assurance Program Requirements for Ncclear l

l

Facilities l

l l

lN45.2.1-1973 Cleaning of Fluid Systems and Associated I l Components During the Construction Phase of I

l Nuclear Power Plants l' l lN45.2.2-1972 Packaging, Shipping, Receiving, Storage and

,l Handling of Items for Nuclear Power Plants (During I the Construction Phase) l I

lN45.2.3-1973 Housekeeping During the Construction Phase of l Nuclear Power Plants l 1

1 I

I I N45.2.4-1972 Supplementary Quality Assurance Requirements for l l Installation, Inspection and Testing of

'l l Instrumentation and Electric Equipment During the l Construction of Nuclear Power Generating Stations l

l l

l l

l l

I l

l I

()# 1 l A I

I TOPICAL REPORT I

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lREV. l l P l lDATE 5/30/84 l l & 1 SECTION: INTRODUCTION lPAGE B-3 l l' L l l l l l I I

I l

~l l

I N45.2.5-1974 Supplementary Quality Assurance Requirements for l p l Installation and Testing of Structural Concrete

?'

l and Structural Steel During the Construction Phase l of Nuclear Power Plants I I

I lN45.2.6-1978 Qualifications of Inspection, Examination and l Testing Personnel for Nuclear Power Plants l 1

I I

I 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 P1, ants l

l N45.2.9-1974 Requirements for Collection, Storage and l Maintenance of Quality Assurance Records for l

l Nuclear Power Plants l

l N45.2.10-1973 Quality Assurance Terms and Definitions r3 I I

Cl N45.2.11-1974 Quality Assurance Requirements for the Design of l Nuclear Power Plants l

l l l l l l N45.2.12-1977 Requirements for Auditing of Quality Assurance l Programs for Nuclear Power Plants l

I l

~

N45.2.13-1976 Quality Assurance Requirements for Control of l

l Procurement of Items and Services for Nuclear l Power Plants ,I I l

. N45.2.23-1978 Qualificatfor of Quality Assurance Program Audit l Personncl for Nuclear Facilities i I I I l l N18.1-1971 Selections and Training of Nuclear Power Plant l Personnel l l l l O l l l kJ ' l l A- l TOPICAL REPORT lREV. 6 l P

l l lDATE 5/30/84 l l & l SECTION: INTRODUCTION lPAGE B-4 l l- L l 1 1 l l I l e-

o l- 1 I

I l N18.7-1976 Administrative Controls and Quality Assurance for i

.(y the Operational Phase of Nuclear Power Plants I

'V I The above requirements are implemented by controlling activities as

[ described in this manual and by procedures referenced in this manual.

l 1

l i I

l l Definitions of terms applicable to the AP&L quality program are found in I

.ltheTermsandDefinitionssectionofthismanual. ,I I

I I

I I

I I

I I

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l l I I I l- 1 I l I I I I I l C l l

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l TOPICAL REPORT i

IREV. 6 l l

l P l lDATE 5/30/84 l 1 & 1 SECTION: INTRODilCTION IPAGE B-5 I I L l I l l l l l l

n.

I l

1 l

l TERMS AND DEFINITIONS l

p I

I l

I l The terms used in this manual follow the definitions provided in l ANSI N45.2.10-1973, supplemented by additional terms and definitions l applicable to this report. l 1

I I

I l Approval - An act of endorsing or adding positive authorization, or both. l 1

I

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

I I

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

l l

l l

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

1 I

Audit - An activity to determine through investigation, the adequacy of l

_ ,q l and adherence to, established procedures, instructions, specifications, l O' I codes, and standards or other applicable contractual and licensing l requirements, and the effectiveness of implementation. l 1 l I I l Bid Evaluation - A formal evaluation of all proposals received in l I

response to an inquiry to determine the vendor to whom the purchase order l will be awarded. l 1 I I l l Certificate of Conformance - A written statement, signed by a qualified l party, certifying that items or services comply with specific requirements. l l I I I l l l Certificate of Compliance - A written statement, signed by a qua~iffied l party, attesting that the items or services are in accordance with l specified requirements and accompanied by additional information to l I

substantiate the statement.

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[d l A l

l TOPICAL REPORT l

(REV. 6 l l

P l l lDATE 5/30/84 l 1 & l SECTION: TERMS AND DEFINITIONS lPAGE C-1 l l L l l l l l l 1

1 '

l I

i --

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_l- Certified Test Report - A written and signed document, approved by a l p

^ ~

lqualifiedparty,thatcontainssufficientdataandinformationtoverify

-l l_the actual properties of items and the actual results of all required l tests. I 1

I iI Certification - The action of determining, verifying and attesting, in I

1 l- writing, to the qualifications of personnel or material. I I

I

l. - l l . Characteristic - Any property or attribute of an item, process, or l

- service that is distinct, describable, and measurable, as conforming or l nonconforming to specified quality requirements. Quality characteristics l l

laregenerallyidentifiedinspecificationsanddrawingswhichdescribe l the . item, p ocess, or service. l l

1 1

I I

l Checks - The tests, measurements, verifcations or controls placed on an I activity by means of investigations, comparisons, or examinations, to

.l - determine satisfactory conditions, accuracy, safety 'or perfo.mance.

l '

l I

l l

l Cleanness - A state of being clean in accordance with predetermined l standards, and usually implies freedom from dirt, scale, heavy rust, .il 1 or other contaminating impurities.

l l

I I I. I

'l Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by I  !

] a legally constituted agency of a Municipality or State of the United l l States, or Canadian Province, or regularly employed by an Authorized l Inspection Agency and having authorized jurisdiction at the site of l msnufacture for installation, repair, modification, and in-service l linspectionofASMEBoilerandPresssureVesselitemsdesignated l safety-related.

I I I I I I I l l 4 '

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.O l l V l A l TOPICAL REPORT l

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! I I I I b _

1 i

)

! I I l I

l Commercial Grade - Those items contained in Q systems and equipment that l ,

L

[') - are: (1) not subject to design or specification requirements unique to I nuclear facilities or activities; (2) used in application other than l lnuclearfacilitiesoractivities;(3)tobeorderedonthebasisof I specifications set forth in manufacturer's published product description; I g and (4) not associated with a loss of safety function.

I I

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

l l

'lComputerCode-Theapplicationsoftwareutilizedwithinadigital l computer to accomplish a specific function or task. Computer codes I requiring Quality Assurance are those whose satisfactory performance is l

l required to prevent accidents which may cause undue risk to the health I and safety of the public or relied upon to mitigate the consequences of l such accidents if they were to occur.

l This involves those computer codes I utilized in design and analyses of Q-list components, and those utilized I as an active portion of Q-list components.

p() l l

l l l l Contaminants - Foreign materials such as mill scale, dirt, oil, chemicals l and any matter than renders a fluid, solid or surface impure and unclean l

l according to preset standards of acceptable cleanness. I I I I I l Contractor - Any organization under contract for furnishing items or l services. It includes the terms Vendor, Supplier, Subcontractor, l Fabricator and sub-tier levels of these where appropriate. l l l l l l Defective Material - A material or component which has one or more l characteristics that do not comply with specified requirements.

l l l l I I I I I I I I I I i

,, I I

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) I l l I I A l TOPICAL REPORT lREV. 6 l l' P l lDATE 5/30/84 l l & l SECTION: TERMS AND DEFINITIONS IPAGE C-3 l l L l l l l l l l

s

~

r1 I

l l

1 Deviation '- A nonconformance or departure of a characteristic from l cp- .g l

specified requirements.

l l

I l

l: . Documentation - My written or pictorial information describing, l

I defining, specifying, reporting or certifying activities, requirements, l

l'. procedures,orresults.

-. I l

l

l. Examination-Anelementofinspectionconsistingofinvestigationof l materials, components, supplies or services to determine conformance to I

_ those specified requirements which can be determined by such l investigation. Examination is usually nondestructive and includes simple l l

physical manipulation, gaging, and measurement.

l l

l

, Handling - An act of physically moving items by hand or mechanical means, l but not including transport modes.

l I

I I

l I

I Inquiry - A document that contcins the necessary information for a vendor 1 to make a proposal. An inquiry may include specifications pertaining to h'O; l

I the equipment, materials, or services proposed to be procured. I

^/ l l

I I

I Inspector (Owner's) - A qualified inspector employed by the Owner whose l ldutiesincludetheverificationofquality-relatedactivitiesor l l installations or both. l I I l~ l l Inspection - A phase of quality control which by means of examination, l lobservationormeasurementdeterminestheconformanceofmaterials, l

l supplies, components, parts, appurtenances, systems, processes or I structures to predetermined quality requirements.

I l l Item-Anylevelofunitassembly,includingstructure, system, l l subsystem, subassembly, component, part or material. l l 1 1 I P l l i i l I I

. I l

O

l l A l

l TOPICAL REPORT i

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l l P l lDATE 5/30/84 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-4 l

. l L l l I l l l l

. . - - . . - - - . . - . - . . ~ . -,- - -. - _ - . . .

3 I

I l

l l Job Order (J.0.) - The Job Order is the document used for identifying and l

(- administrative 1y controlling the work effort on station equipment and V l systems. It identifies applicable procedures and drawings; documents l reviews, approvals and results of inspections and tests; and provides a

[ mechanism for planning, scheduling and authorizing work. l 1

I l

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 l machinery, castings, liquids,formedsteelshapes, aggregates,and l cement.) l l

l 1

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 l safety restrictions. .

n i I

O Nonconformance - A deficiency in characteristic, document, or procedure l which renders the quality of an item unacceptable or indeterminate.

l l

l Examples'ofnonconformanceinclude: physical defects, test failures, l incorrect or inadequate documentation, or deviation from prescribed l processing, inspection or test procedures.

I I

Objective Evidence - Any statement of fact, information, or record, l either quantitative or qualitative, pertaining to the quality of an item l or' service based on observations, measurements, or tests which can be l verified. 1 l

l 1

l l Operation - The total of administrative, maintenance and monitor l activities necessary to sustain the power generating capabilities of the l plant af ter initial start-up. l l

l l

l l

l 1

gS l i  ;

V l A l TOPICAL REPORT lREV. 6 i

l l P l lDATE 5/30/84 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-5 l I L l l I l l l 1

p l

- I l-l l Owner - The person, group, company or corporation who will have or has I y ltitletothefacilityorinstallationunderconstruction.

l l

Package - A wrapping or container including its contents of materials or l equipment. l I

i l

l l

l Packaged Unit - An assembly of items and parts which can be disassembled l lwithoutdestroyingtheintegrityoftheindividualparts.

I l

l Part - An item which has work performed on it and which is attached to l l and becomes part of a component before completion of the component. l 1

l l

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

I l

l Procedure-Adocumentthatspecifiesordescribeshowanactivityisto l l be performed. It may include methods to be employed, equipment or l lmaterialstobeusedandsequenceofoperations.

G I l

I lProcurementDocuments-Contractuallybindingdocumentsthatidentifyand i define the requirements that items or services must meet in order to be l considered acceptable by the purchaser.

I l

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

l l

l l Proposal - A bid, usually written by a vendor in response to an inquiry, l which provides the issuing party with the vendor's proposed compliance to l the inquiry and the cost. l 1

I I

I I

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

l l

1 i

i l I

i l

O I I I l

I l A l TOPICAL REPORT 6 lREV. l l P l l0 ATE 5/30/84 l l & 1 SECTION: TERMS AND DEFINITIONS lPAGE C-6 l 1 L l l l l l l l

r-

.I I

I I

l Purchaser -. The organization or organizations responsible for issuance l

^ I l and administration of a contract, subcontract, or purchase order. I

x. v! I l

g Q-List - A list which wecifically identif ies those st ructures, systems

1. l and components whose tailure could cause an uncontrolled release of l radioactivity, or those essential for the safe shutdown and immediate and I I long-term operation following a Loss of Coolant Accident. l

l. I l .

I

-l Qualification (Personnel) - The characteristics or abilities gained l

,through training or experience or both that enable an individual to I

1. perform a required function.

l l

l l

1 l -Qualified Party - A person or organization competent and recognized as l knowlegeabl.e to perform certain functions. I I

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

n l

l I

id I Qualified Vendor List - A listing of vendors having quality assurance ,I l programs consistent with the requirements of applicable portions of I l10CFR50, Appendix 8.

l-i Quality Assurance - All those planned and systematic actions necessary to l

l provide adequate confidence that an item or a facility will perform l

! satisfactorily in service.

l l

1 Quality Control - Those quality assurance actions which provide a means I to control and measure the characteristics of an item, process, or I lfacilitytoestablishedrequirements.

I l

-l I I

l

.i I o

i l i i

i l

O l i l

'U

'l A l TOPICAL REPORT l

6 l

lREV. l l P l 10 ATE 5/30/84 i l & l SECTION: TERMS AND DEFINI110NS C-7 lPAGE l l L l I l i 1 I I L

3 I

l l l l Receivino - Taking delivery of an item at a designated location. I

,.m i 1

/ l- l Repair - The process of restoring a nonconforming characteristic to a

~

l l condition such that the capability of an item to function reliably and l

l safely is unimpaired, even though that item still may not conform to the I original requirement. ^

l I l Report-Something(document)thatgivesinformatiorforrecordpurposes. l l

l l Review-Anelementofinspectiontodetermineconformancetospecified L l requirements, which can be determined by examination of documents and l activities.

l l l l l Rework-Theprocessbywhichanonconformingitemismadetoconformto I a prior specified requirement by completion, remachining, reassembling or l lothercorrectivemeans. l 1 l Safety-Related - The term " safety-related", as used in this program, l

/3 l refers to those materials, parts, components, systems, structures and i U consumeable ite:ns classified as "Q" and so identified on the Q-list l l applicable to each nuclear plant. l l l 1 l l Source Surveillance - A review, observation, or inspection for the I purpose of verifying that an action has been accomplished as specified at l

l the location of material procurement or manufacture. l I I I l l Specification - A concise statement of a set of requirements to be I satisfied by a product, material or process indicating, whenever I appropriate, the procedure by means of which it may be determined whether I the requirements given are satisfied.

l l l

. l I I l l .

l l l l l l l l 1 I V O I I I I I A l TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l l & 1 SECTION: TERMS AND DEFINITIONS IPAGE C-8 l l L l l l l l l 1 k

i l

I l

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

(] a recognized authority.

Storage - The act of holding items at the construction site or in an area l other than its permanent location in the plant. l 1

1 I

I l Subsystem - A group of assemblies or components or both combined to l performed a single function.

I I

Surveillance - The continuing analysis and evaluation of records, methods l and procedures, including the act of verification, to assure conformance l with technical requirements. I I

I System - A group of subsystems united by some interaction or l interdependence, performing many duties but functioning as a single unit. l 1

l l

I l System Performance Test - A test performed on a completed system l lincludingelectric, instrumentation, controls,fluidandmechanical

( subsystems under normal or simulated normal process conditions such as l

']

l l

temperature, flow, level, and pressure.

I I

Testina - The determination or verification of the capability of an item l to meet specified requirements by subjecting the item to a set of l physical, chemical, environmental or operating conditions.

I I

Titles - Titles of individuals, such as Quality Assurance Manager, when l used in the TOPICAL report assigns the responsibility of performing the l requirement to the noted individual or his appointed designee.

I I

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

l l

l l

l l l l 1 l ,

1 I

,, I

('-) i I I I l A l TOPICAL REPORT 6 lREV. l l P l lDATE 5/30/84 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-9 l l L l l l l 1 1 I I

l l

1 I

.l Transit Carrier (0 pen) - Trucks, trailers, railroad cars, barges, 1 aircraft or ships which do not afford items protection from the l environment. l l

1 l

l l Transit Carrier (Closed) - Trucks, trailers, railroad c.ars, barges, l aircraft or ships which provide protection of items from the environment l by nature of their closed design. I I

l l- l l Use-As-Is - A disposition which may be imposed for a nonconformance when l I

it can be established that the discrepancy will result in no adverse l conditions and that the item under consideration will continue to meet I all engineering functional requirements including performance, l

l maintainability, fit and safety. l -

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

-l l'ebricator and sub-tier levels of these where appropriate. l l 1 I i 7^'s l Verification - An act of confirming, substantiating and assuring that an I activity or condition has been implemented in conformance with the l specified requirements. I l l l l l Work Instructions - Written instructions used to transmit detailed I information on the specific measures necessary to comply with the l requirements of quality assurance procedures or any complex or difficult l l quality-relatedtask. l l l Work Package - A work package is a collection of applicable documents, l such as procedures, cleanliness control forms, inspection and test forms, l hold card forms, Ignition Source Permits, drawings, technical manuals, l

l etc., needed to perform the job. l l l l l l I I l i I I I o l I

(

^

) l I I I l A l TOPICAL REPORT lRLV. 6 l l P l lDATE 5/30/84 l l & l SECTION: TERMS AND DEf!NITIONS lPAGE C-10 l l L l l l

I I I I L. .

e i

I I

I i 1. 0 ORGANIZATION I

o

'd' l

l 1.1 SCOPE l l

l 1

-l l

I This section describes the AP&L organizational structure and i I

responsibilities for establishing and executing the Quality Assurance

^

g l

l Program for AP&L operational nuclear plants in compliance with 10CFR50, 1 Appendix B and applicable Regulatory Guides and ANSI Standards identified I g

l in the Introduction. It also includes a description of the interfaces l lwithotherorganizationswhomaybedelegatedtheworkofestablishing f-' I and executing portions of the Quality Assurance Program. The AP&L l Corporate Organization relevant to the operation of its nuclear plants is l shown in Figure 1. l l

I I

I l

l 1. 2 GENERAL RESPONSIBILITIES l 1

1 l

l l 1.2.1 i i

l 1

m l The ultimate responsibilities for operational nuclear plants within AP&L, I lincludingQualityAssurance,lieswiththeEnergySupplySeniorVice l- President.

l He provides management assessment of the Quality Assurance l Program through review of QA Audit Reports and reports of NRC activities.

l l

1

1. 2. 2 '

l  ;

I l

lTheAdministrativeServicesVicePresidentisresponsibleforthe l

l purchasing functions affecting plant operation as described in Subsection l

1. 3.

l l l 1 I

I I I l

l 1

1 I

I I

I l l l

1

-l l I l

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lREV. l P

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s I

l l

l l 1. 3 CORPORATE SERVICES l

.. ~l l

x

) l I

l 1.3.1 l

l l

l l

l Corporate Services is responsible for the procurement of materials, parts l and components requested by Little Rock General Office (LRGO) personnel l and for supporting the procurement activities at the plant. Procurement l

_ organization is noted in Figure ?.

I I

i 1.3.2 l l 1

1 I

I lTheNuclearBuyerreportstotheSupervisorofPurchasingwhoreportsto l the Manager, Purchasing and Stores and is responsible for the following l I

duties and activities: I I

l i I

1. Prepares purchase orders based upon receipt of reviewed and I l

l approved Purchase Requisitions. l l

l 1

I a

-l 2. Performs the commercial interface functions between AP&L and l J

contractors or vendors.

I I

3. Assures that quality documentation prepared by Energy Supply personnel are included in purchasing documents.

l l l 1 1 I I l 1.4 ENERGY SUPPLY l

1 1 I I l Energy Supply, headed by the Energy Supply Senior Vice President is l l

responsible for all activities related to the operation of AP&L Nuclear I l l l Plants. These activities include as a minimum: design, modification, l maintenance, inservice inspection and test, operation and those l additional activities discussed in Sections 2 through 18 of this manual. l Within Energy Supply, the Nuclear Operations and Energy Supply Service organizations are involved in activities requiring execution of the l

l l Quality Assurance Program (See Figure 3). I l I

(])

k-l 1 A I

l TOPICAL REPORT I

IREV. 6 l l

l P l 10 ATE 5/30/84 I I & l SECTION: 1,0 ORGANIZATION IPAGE 1-2 l l L i I I l l l l l

1

, I I

l l

l 1.4.1 Energy Supply Services I

oM- - l l l

Energy Supply Services is under the direction of the Energy Supply l lServicesDirector,whoreportstotheEnergySupplySeniorVice l President. The Energy Supply Services Director is responsible for l

l l providing support to AP&L nuclear ,

plants in the areas of quality I assurance, administrative services, engineering services and technical I services. His duties include providing technical direction, l administrative guidance and supervision to the: l I

l I

i l

l a. Energy Supply Administrative Services General Manager i

b. ' Engineering Services General Manager l c. Technical Services General Manager l

l

.l d. Quality Assurance Manager I

l 1

1.4.1.'1 Quality Assurance Manager l

l l

lTheAP&LQualityAssuranceOrganization(QAO)asshowninFigure4is e l I under the direction of the Quality Assurance Manager, who reports to the l l

g Energy Supply Services Director. The QA0 performs review, surveillance, I g

l inspection and audit functions during the operational phase of AP&L's l l nuclear plants and is independent of Nuclear Operations, and from cost I and scheduling considerations when opposed to safety and quality- l l considerations. The QA Manager shall have direct access to management 1evels, which assures his ability to:

l l identify quality problems; I l initiate,' recommend or provide solutions through designated channels; and l verify implementation of solutions. l I

I I

I l

l The qualification requirements of the QA Manager are established within I his APSL job descript' ion which includes the following prerequisites:

l l

l

1. Possess a degree from an accredited school in engineering or a l l l related scientific discipline or equivalent; I I

I I

I I

l h- l A l

I TOPICAL REPORT l

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l l P- l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION iPAGE 1-3 l l L i l l l l l l

p i l l- l l 2. Possess a minimum of five years experience in the quality l

-([ l assurance or quality control disciplines with atleast two years in the nuclear field; and l l l l l

, l 3. Exhibit the ability to plan, schedule and direct the activities l 1 of others assigned to or functioning within the QAO. I I I I I The duties and responsibilities of the Quality Assurance Manager include the following:

l l l 1 I l l l 1. Develop Quality Assurance Program requirements for l modification, operation, and maintenance activites related to l

-l the safety related (Q-listed) systems, structures, and l components in AP&L nuclear plants.

l l l

2. Audit of the quality assurance activities as described in l

l Section 18 of this manual. l l l

'I l Review, approval and verification of the quality assurance l 3. l I requirements placed upon contractors or vendors that provide l

equipment, material, or services for AP&L nuclear plants. l

l. I I l

-l 4. Authority to stop work where conditions exist that prohibit l effective quality control inspections, or if faulty materials, l

incorrect workmanship or procedures are detected. l l l l l l

S. Review, approval, distribution and control of QA Manuals and QA l Procedures and revisions thereto.

I I l 6. Review and approval of QA programs for outside organizations l I I

, -l participating in the AP&L QA program. l l 1 1 I I I I I I I I

O i l A i

l TOPICAL REPORT i

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I I P l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-4 l 1 L I I I I I I I

l l I

I l 7. Serve as chairman of the Safety Review Committee. l l

0 i l 8. Provide and maintain a qualified and suitable trained staff to 1

i I

carry out required sta; f f unctions.

I l

9. Formulate progran.s for maintaining the professional competence l of personnel within the QA0 and provide assistance in QA l training and indoctrination programs for division management, i engineering and plant personnel whose activities affect l quality.

l I

I

10. Provide technical direction and guidance to the Quality l

l Engineering Supervisors. I I

I I

I l 1.4.1.1.1 Quality Engineering Supervisor l I

i 1

l l The Quality Engineering Supervisor reports to the Quality Assurance  !

Manager, supervises QA Engineers and Auditors / Inspectors as assigned, l and assists the Quality Assurance Manager in the coordination of O activities within the QA Section. The Quality Engineering Supervisor may I

l l also perform duties normally assigned to Quality Assurance Engineers. l l l l l l 1.4.1.1.2 Quality Assurance Engineers l l l l l l The Quality Assurance Engineers (QAE's) report to a Quality Engineering l Supervisor, as assigned. The Quality Assurance Engineers are to be I l familiar with the Quality Assurance Program and associated procedures, l 10CFR50 Appendix B, regulatory guides, codes, and standards that address l quality assurance. They also possess the necessary functional l independence and authority to: identify quality problems, initiate, l recommend or provide solutions through designated channels, and verify l implementation of solutions. Specitically:

I I l l 1 i i l i I l l l l l A l TOPICAL REPORT lREV. 6 l P

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l l l l s

l 1. The QAE's are to have the authority to inspect, audit or review l j' practices, records, files, instructions, directions or l documents concerned with all areas affecting quality. I l l I I l 2. The QAE's are to schedule and coordinate audits or surveillance l efforts in the areas assigned, document findings, and report l

i results to the Quality Assurance Manager and the Manager of the I audited area.

l l l l1.4.1.1.3 Quality Assurance Auditors / Inspectors l l lTheQualityAssuranceAuditors/InspectorsreporttotheQuality l l Engineering Supervisor and assist him in the implementation of the l lprogrambyperformingauditsandinspectionsasrequiredtoassureproper I application of the Quality Assurance Program. l l l 1 I i 1.4.1.2 Technical Services General Manager l

.I I o l l O l The Technical Services General Manager reports to the Energy Supply l l,ServicesDirectorandisresponsibleforprovidingsupporttoAP&L l l nuclear plants in the areas of plant performance, maintenance and l l availability, chemistry,environmentalmonitoring,metallurgyand l

l nondestructive examination. His duties include the following: I l l I I I 1. Provides technical direction and administrative guidance to: I

-l l l 1 l a. Plant Performance Evaluation Manager l

b. Plant Maintenance Manager l l l c. Availability Engineering Manager l

d. Technical Analysis Manager l l l l

2. Assure conformance to the Quality Assurance Program by l l l instituting the necessary quality-related procedures and I instructions within the Technical Services Department.

l l o i l

A l-I TOPICAL REPORT 1

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l l P l lDATE 5/30/84 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-6 I L I I l I

i 1 l l

1 l

1 l

l 3. Provide for coordination of environmental surveillance programs l q l i

V- 1 I

l 4. Direct development of programs aimed at maximizing efficiency l and availability.

I I

S. Provide for review and analysis of outage data and make I I recommendations for correcting deficiencies which affect l availability or performance. I I

I l 6. Direct the plant maintenance support activities that are

-l assigned to the LRGO.

l l

l l

l l 7. Serve as a member of the Safety Review Committee. l 1

I I

I I 8. Provide and maintain a qualified and suitably trained staff to l-carry out required departmental functions.

l l

l 1.4.1.3 Engineering Services General Manager l

]" l The Engineering Services General Manager reports to the Energy Supply l

l Services Director and is responsible for LRGO design and engineering l lactivitiesrelatedtonuclearplantoperations. His duties include the i following: l l l 1 I l 1. Provide technical direction and administrative guidance to: l 1 1 1 l l a. Mechanical Engineering Manager l

b. Electrical Engineering Manager I y

l c. Civil Engineering Manager l

d. Instrumentation and Controls Engineering Manager l

l l

.l 2. Assure conformance to the Quality Assurance Program by l

l Instituting the necessary quality-related procedures and l instructions within Engineering Services.

l l 1 n i I

( ')

l l A I

TOPICAL REPORT l

6 I

I lREV. l l P l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-7 l l L i l l I i- 1 I

l-l I

I i l 3. Provide for review and approval of LRGO design and engineering i

{]' g activities performed by contractors, vendors, and AP&L

'~'

I personnel.

l l

l 1

I i 4. Provide for review and approval of procurement documents for l equipment, material and services for LRGO engineering projects, I as appropriate.

I I

I l-l l 5. Provide and maintain a qualified and suitable trained staff to l l carry out required departmental functions.

I i

1. 4.1. 4 Energy Supply Administrative Services General Manager I

l l

lTheEnergySupplyAdministrativeServicesGeneralManagerreportstothe l Energy Supply Services Director and is responsible for the development of l ladministrativeprograms,systemsandservicessupportivetomanagement.

I His duties include the following: l l

l l

l

(^3 I 1. Provide technical direction and guidance to:

- (j- l I

l l

l I a. Energy Supply Training Manager l

b. General Services Manager l l l c. Planning, Scheduling & Cost Control Manager l

d. Contract Administration Manager l

l l

2. Maintain overall department fiscal direction and control, and l provides supportive accounting functions. l l

1 l

I l 3. Provice contract administration and administration of I procedures for Energy Supply Little Rock General Office (LRGO) l activities.

l 1

I I

I I

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

l l 1

1 I

l ll V'

l I I I l A I TOPICAL REPORT 6 lREV. l l P I lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-8 l l L l I I l l l l

. .>: n J. +, s iw I '

I I 4%, -

I

• I ,5 . Ancillary support services to Energy Supply operation sections. I p l l

\ / l, I

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

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

l l

l l t i I l Im 8. Assure conformance to the Quality Assurance Program by I f instituting the necessary quality-related procedures and I

l' instructions within Administrative Services. I I .

I I I l\ 1.4.2 Nuclear Operations I

l l I I i Nuclear Operations is under the direction of the Nuclear Operations Vice I i., lPresidentwhoqeportstotheEnergySupplySeniorVicePresidentandis S -

1 responsible for the formulation, licensing, implementation and discharge I 1g4 - of operating policies and procedures relative to nuclear plant operations

'c and for nuclear fuel management. His duties include the following:

l l I I s I 3 1 ' s s I

. ,q ). . I 1. Provide technical direction and administrative guidance to the: 1

(.._ ) s I s l I l I a. Plant's General Manager I

'N '

b' . Nuclear Services Manager l ,

l

.( l c. ANO Project Manager I

( d. Li, censing Manager l

l l I

,, 2. Assure conformance to the Quality Assurance Program by I t I ..y l l instituting the necessary procedures and instructions within I

( the Nuclear Operations Department.

l l 0 1

3. Provide for review and approval of design and engineering performed for,the operating nuclear plants.'

}I, ft ,7 5 I

l

.l l

_ l 4. Provide for review and approval of procurement documents for I

+ equipent, materia,1adtservices.

' l l -

d 1

-s I _

l l ) l 'l_ -

1 I

'# A l i " TOPICAL REPORT IREV. 6 l

',' 1 P I lDATE 5/30/84 1

! & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-9 l l L l l l q .. l 1 I I

,d I'

_]

I I

I I

l l S. Provide for liason between AP&L and applicable regulatocy l

'^') agencies.

l

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

l l

l l 7. Provide for procurement and design review of nuclear fuel. l 1

l 1

l l 8. Overall responsibility for the fire protection program l l implemented at the nuclear plants.

l l

l

'1.4. 2.1 Nuclear Services Manager l l l

l The Nuclear Services Manager reports to the Nuclear Operations Vice l President and is responsible for providing the necessary support services l lrelatedtotheeffectiveoperationandmaintenanceoftheAP&Lnuclear l plants. The duties include the following:

l l

l 1

-l I n l 1. Review, approval and coordination of design changes through the l l Little Rock General Office.

l l

l

2. Review, approval and coordination of purchase requisitions and l contracts generated at the Little Rock General Office. I I

I I

l l 3. Interface with other departments to assure effective l implementation of Regulatory and Company requirements.

l l l

4. Communication interface dealing with all activities at the i nuclear plants. l I l l I I l l l l 1 I I I l l I I I I

n l

l A I TOPICAL REPORT lREV. 6 l l P l 10 ATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-10 l l L l l l l l I l

, t-i ., t 9 & -

1 I

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l l

'a l S. Provide technical dir,ectan and administrative guidance to the l

'( ) ,  ;

Nuclear Fuel Supervisor, who is responsible for the y

l procurerent, design review and performance evaluation of l

.-l nuclear fuel and to provide support. to the plant in the areas l

g l of reactor core ~parformance and assessment of core design l I

analysis.

l

.j l ,

l I

I

/ 6. Serve as a member of thetSafety Review Committee.

vl ,

1.4.2.2 Licensing Manager l

I l l

.i s l l The Licensing Manager reports to the Nuclear Operations Vice President

' l

'/3 i l and is responsible for the coordination of all licensing documents, l

.; lrequirementsandrevisionstheretowhicharerequire'dtobereviewed k , l+ and/or approved by the NRC and for interfacing with the NRC. The l Licensing manager'is also resp sible for the review and approval of l

1 Q-List changes and for the tracking of possible nuclear safety concerns l I

I to assure timely c.loseout. I I

g) l I

( ..

v  ; l 1.4.2.3 Project Manager ,

P --

,g l P lTheProjectManagerreportstotheNuclearOperationsVicePresidentand l l is responsible for providing services at the nuclear plant for field l construction activities and for modifications; to the control room

,, l 7' l simulators usedefor operator's training. .His duties include providing l technicaldire[tionandadministrativeguidance'totheFieldConstruction l

> l Manager and the Simulator Project Coordinator. l l 1 1

l l 1.4.2.3.1 Field Construction Manager l I

I l

l l The Field Construction Manager is responsible for directing the l I

I activities of his staff relating to work associated with plant l a l l ' construction and modifications. His duties include: l l / I l

I s '

• I l .

p ,

l l

() l l TOPICAL REPORT l

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l l A- l 4 l P l lDATE 5/30/84 l

l. & l SECTION: 1.0 ORGANIZATION lPAGE 1-11 l l L l , I l s.

l l

.- l I

. , -s - + - . - - . , - - - . - - - - - , - ,_

, . - = _ -. . . . - - _ . _ .

1 l

l 1

l l 1) Interface with other departments to assure effective l I

implementation of job assignments  !

Q(m l l

I I

2) Provide cost and' schedule controls for departmental activities I I

l

3) Provide technical and administrative guidance to the l- Construction Quality Control (CQC) Supervisor. The CQC l Supervisor is responsible for the surveillance and inspection l of activities performed under the direction of the Field l Construction Manager, and shall have sufficient authority and l organizational freedom to: identify quality problems; l

s

'I ' initiate, recommend or provide solutions through designated I

,; -l- l l channels; and verify implementation of solutions. The CQC l l- Supervisor is also responsible for assuring adequate inspection l , points have been assigned for the work activity, inspectors l have been certified to ANSI N45.2.6, 'irecting the activities l of the inspectors, and interfacing with the Code Inspector for l

l activities involved Code items.

I I

.b _

.I l 1. 5 PLANT ORGANIZATION I I

, I i 1.5.1 General Manager l l I .' 1. 5.1.1 l

l 1 The General Manager reports to the Nuclear Operations Vice President on l the corporate level (see figure 5) and has direct responsibility for l operating the plant in a safe, reliable and efficient manner.

He is

~

.l responsible for operating the plant in accordance with the provisions of l

I the operating licenses, including the on-site quality program.

-I l

~1 I I I I l l 1 i l l 1

' l l l l l 1- A-l l TOPICAL REPORT lREV. 6 l l P l IDATE 5/30/84 l

-l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-12 l

1. L l l l l l l 1

l i

I I

l 1.5.1.2 l

, l

' s I

5 i

I l The General Manager has the authority to shut the plant down if required l and has final approval of plant procedures.

I l

I

1. 5.1. 3 I I

i l

l lTheGeneralManageristoprovidetechnicaldirectionandadministrative ,I l guidance to the:

l l

l l

l l 1) Operations Manager l

2) Maintenance Manager l l y l 3) Administrative Manager l

4) Engineering and Technical Support Manager l 5) Special Projects Manager l

6) Manager, Nuclear Quality Control l l l l 1.5.2 Operations Manager

'h l l

l The Operations Manager (Figure 6) is responsible for directing the actual l . day-to-day operations of the plant. He supervises the operating staff l

l and interfaces with the Maintenance Manager to accomplish l operation-related maintenance activities. The Operations Manager is to l

i provide technical direction and administrative guidance to the:

I . I

1) Operations Superintendents l 2) Operations Technical Staff l 1 1 I I l 1.5.2.1 l l l l 1 l The Operations Superintendents report to and assist the Operations 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 i I 7, I I 1 I iv) - -l A l TOPICAL REPORT I

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IREV. l P

l l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-13 l l L i l l l l l l

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1 I I I l activities. They are to assist the Operations Manager in the supervision l

~} of core refueling, which includes advance planning for the outage, plant l preparation, equipment check-out and the refueling operations. l l l l l l 1.5.2.2 l l l I l l The Shift Supervisors report to the Operations Superintendent and are l I responsible for the actual operation of the unit and for the activities  !

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

be cognizant of operation activities being performed while on duty. The I l I l Shift Supervisor on duty has the authority to shut down the unit if, in l I his judgement, conditions warrant such action. I I I I I I 1.5.3 Maintenance Manager I I I I I l The Maintenance Manager (Figure 6) is responsible for the maintenance of I I I l plant equipment, facilities and planning / scheduling of station work l l

activities as defined by plant maintenance program implementing I I I p l procedures and to assure that maintenance of equipment is conducted in l C' I conformance with applicable standards, codes, specifications and I I I l procedures The Maintenance Manager is also to coordinate l l operation-related maintenance activities with the Operations Manager and I I I l is responsible to make repairs on any structure, system or component l l under his control. The Maintenance Manager is to provide technical I I i l direction and administrative guidance to the: l 1 I I I l 1. Mechanical Maintenance Superintendent l l

l 2. Electrical Maintenance Superintendent I l l l 3. Instrument & Control Superintendent l l 4. Planning and Scheduling Supervisor I r l l l 5. Senior Maintenance Coordinator l l- 6. Shift Maintenance Superintendent I I I I i l l 1 I I I I s l I I A I TOPICAL REPORT IREV. 6 l i l P l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-14 I I L i 1 I I I I I L

\;.

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'l I

i 1~. 5. 4. Engineering and Technical Support Manager i

.N l l

l- The Engineering.and Technical Support Manager (Figure-7) is responsible l for providing plant engineering support services as well as technical and 1 plant analysis and health physics support services to the plant staff.

l l

l-The'EngineeringandTechnicalSupportManageristoprovidetechnical l direction and administrative guidance to the: l I

, 1 1

I I

.l~ 1) Technical Analysis Superintendent l l- 2) Plant Analysis Superintendent I 3) Plant Engineering Superintendent l l

.l 4) Operations Assessment Superintendent l 5) Health Physics Superintendent. l l

l l

, I I

l .1.5.4.1~ Technical Analysis Superintendent l l

l' 1 I

-l The Technical Analysis Superintendent maintains overall responsibility l for radiochemistry, chemistry and environmental programs at the plant.'

l 1 The Technical Analysis Superintendent-is also responsible for maintaining

^ '

l lthe Station Emergency Plan and ensuring the plant staff is capable of l implementing.the requirements delineated in the Plan and its procedures. l l~

l i=. .

I l 1.5.4.1.1 l

.I I

l- .

I l .The Radiochemistry Supervisor reports to the Technical Analysis I

- Superintendent and is' responsible for analyzing the reactor plant water l conditions and providing recommendations to maintain conditions.

l l

l l

'l- .

I l 1.5.4.1.2- l

'l: I The Chemistry and Environmental Supervisor reports to the Technical l lAnalysisSuperintendentandisresponsibleforestablishingwater

-ll : chemistry criteria, analyzing secondary plant water and auxiliary water i I

I l- 1 l- 1 I

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l l A l

l TOPICAL REPORT I

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l-l l conditions and providing recommendations to maintain conditions within l I

acceptable limits. I

. \ c ),

I l

1.5.4.2 Plant Analysis Superintendent I I

I I

l The Plant Analysis Superintendent 'is responsible for the areas of plant l performance, nuclear support and computer support. A supervisor is l I

I_ provided for each of these areas. I I

l i

I 1.5.4.2.1 1

-l l I

l l.ThePlantPerformanceSupervisorreportstothePlantAnalysis l Superintendent and is responsible for: evaluating equipment and system l performance over extended periods, recommending methods of improving and l maintaining good plant efficiency, investigating and evaluating equipment l malfunctions or failures and recommending corrective action to prevent l recurrences, and coordinating the activities of the Inservice Testing l I

Program at the plant. I

.l l

,- l l

V- l I

l~ 1.5.4.2.2 l i I I

I The Nuclear Support Supervisor reports to the Plant Analysis I I

l Superintendent and is re:;ponsible 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 l current accurate information to operations; collection and transmittal of l 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 I

l fuel movements including new fuel receipt and inspection, fuel shuffling I l

l at refueling, inspection of irradiated fuel and shipment of spent fuel. l 1

1 I I I I I

I I I I I

.s' l I

( I I I I l A l TOPICAL REPORT lREV. 6 l l P- l lDATE 5/30/84 l l & 1 SECTION: 1.0 ORGANIZATION [PAGE 1-16 l l~ L i  ! I l l I i

't I

I I

l 1.5.4.2.3 l

- . I I

i ,i l I

il The Computer Support Supervisor reports to the Plant Analysis l lSuperintendentandisresponsibleforthemaintenance,revisionand I development of computer software for the plant monitoring computers and I for providing technical assistance to the Nuclear Support Supervisor and l Nuclear Engineers in development and use of test apparatus for evaluation l

.loffuel,coreandNSSSperformance.

l l

l l1.5.4.3 Plant Engineering Superintendent I

I The Plant Engineering Superintendent is responsible for drawing control, l

l implementation and coordination of the Inservice Inspection Program and I design and plant engineering activities at the plant. The Plant i Engineering Superintendent is to provide technical direction and I administrative guidance to the:

l l

l l 1) Mechanical Engineering Supervisor f~N l

I 2) Electrical Engineering Supervisor l

' i

' l Drafting and Drawing Control Supervisor.

I l

. 3) g l l l1.5.4.4 Operations Assessment Superintendent l

l l The Operations Assessment Superintendent provides the capability to l

l perform engineering evaluations of operating experiences which occur both I at the AP&L nuclear plants and at other nuclear power plants and to l

l recommend corrective actions as a result of these evaluations to help l plant operations personnel-in preventing or dealing with similar I ocurrences. 1 I I I l l l l l l 1 I I l I I I I I

[]'" l l l l A l TOPICAL REPORT lREV. 6 l P

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. l

- l 11 . ..

l ll -1.5.4.5 Health Physics Superintendent l

.,7 y l-l

~;i A"

I . .. - .. -

I l ;The Health _ Physics Superintendent is directly responsible for and has the l

!. authority to implement the Health Physics program at the nuclear plant

'l- and to _ maintain radiation exposure as low as~ reasonably achievable l (ALARA). ;The Health Physics Superintendent has.the authority to stop

,l. worktin radiation treas if he evaluates that a potential for an l

-unanticipated' excessive' exposure to plant personnel or the environment

'l may exist.

l

l 1

l .

l l 1. 5. 5 Administrative Manager l

l-

l. I I

l " The -AdministrativiManager (Figure 8) reports to the General Manager and l

'laidshim'in.theadministrativeaspectsoftheplant'soperation. The l ' Administrative Manager directs.the activities of the administrative staff l

.llandprovidestechnicaldirectionandadministrativeguidancetothe:

e-I 1

-l l

' l- Office Services Supervisor y l) I

p :l -2) Material Management Supervisor g

l M 3) ~ Human Resources. Supervisor

-l- 4) Training Superintendent l

I' Plant Controller

5) I

-l- I

. s l' l I

'1.5.5.1 I

-l l l

1 7 The.0ffice' Services-Supervisor is responsible for administration of the l clerical staff activities ~and the accumulation and disposition of quality l

+-

Il-. assurance _. records related to all phases of the nuclear plant. I 1

1 I

?I "1.5.5.2 I I

i l

l

' jThe. Material Management Supervisor is responsible for plant procurement, I l storage of= materials, parts and equipment, issuance of tools and test 1 equipment and the disposal of-surplus materials.

l l

l

-I l

'l _

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l l 1.5.5.3 l l

(./ ' l I The Human Resources Supervisor is responsible for employment, industrial l lrelationsindustrialsafetyandfirepreventionandsecurity. Reporting I to him are the Safety and Fire Prevention Coordinators, the Security l

l. Coordinator,andtheEmploymentandIndustrialRelationsCoordinator.

I l

l1.5.5.3.1 l l

l

.The Safety and Fire Prevention Coordinators are responsible for l

l conducting periodic checks to examine control of combustables, l housekeeping and other fire prevention / protection efforts as well as to l

l provide a centralization of OSHA and plant safety programs. l 1

l l

l l 1.5.5.3.2 l 1

i l l I The Security Coordinator is responsible for coordination of the efforts l of the security force and to manage the operation of the security system.

l O l l

1.5.5.4 l

I 1 The Training Superintendent is responsible for the training and I retraining of plant personnel and of Little Rock General Office personnel l lasestablishedbyPlantprocedures. l 1 l 1.5.6' Manager, Nuclear Quality Control l l

-l l lTheManager,NuclearQualityControl(Figure 5)isresponsiblefor l l verifying the implementation of the Quality Control Program at the plant l and reports to and receives direction from the General Manager. The l

l' Plant Quality Control department shall have sufficient authority and l l organizational-freedomto: identify quality problems; initiate, l l recommend or provide solutions through designated channels; and verify I implementation of solutions. His duties include the following:

l l l n'

.l

l. A l

l TOPICAL REPORT i

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.I I I I

l_ I I

l l 1) Provide technical direction and administrative assistance to l I

the: I w / l l

l l

g

a. Quality Control Engineering Supervisor I l b. Quality Control Supervisor l

c. Quality Control Engineers l l l d. Quality Control Inspectors l l

l 1 .

l l 2) Interface with the Quality Assurance Manager or his l representative for technical assistance in resolving l significant conditions adverse to quality. l

~l l

I .

l l 3) Authority to place an item in a nonconforming status when such l an item is determined to be in violation of purchase documents, l applicable codes and standards or FSAR requirements.

l l

l l

l l

l 4) Assuring surveillances, inspections and reviews of plant l

. activities and documents are conducted in accordance with plant

/^ l procedures.

'd i

l I

I I

l 1.5.7 Special-Projects Manager l

1 l

1:

l l The Special Projects Manager is responsible for the administration and l I

. control of special' projects pertaining to plant operations, maintenance and administration and is to provide technical direction and l

l l

administra'.ive guidance to a staff of Special Project Coordinators.

l Additional duties include: l l l 1 l l 1) Serving as chairman of the Plant Safety Committee l l l 1 l l 2) Interfacing with onsite regulatory agencies l l l l l l 3) Providing evaluations and recommendations to regulatory l I

requirements and meeting regulatory commitments.

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[3

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l l 1. 6 INDEPENDENT REVIEW ORGANIZATIONS l l

V l l

l l In addition to the responsibilities of key individuals within the AP&L l

. organization who are involved with the overall quality program, AP&L has

! established the following committees as a management tool to I independently review activities occurring during the operational phase of I a nuclear plant.

l I

I I

I i 1.6.1 Safety Review Connittee (SRC) l I

I I

I l The SRC reports to the Nuclear Operations Vice President and is I responsible for providing of f-site independent reviews, and/or audits l

l relating to: the Safety Analysis Report, Technical Specifications, I Procedures and changes thereto; unreviewed safety quer.tions; violations, l

I deviations and reportable events; and any other matter involving safe I operation of the nuclear plant which the committee deems appropriate or  !

g l 1s referred to them by the on-site operating group. The SRC is also to I review the reports and meeting minutes generated from the Plant Safety l

(

A]s l

l Committee. l l

l l

1 1.6.2 Plant Safety Committee (PSC) l ll 1 l

l l The PSC reports to the plants' General Manager and is responsible for l reviewing activities specified in the Administrative Technical l

l Specifications for the purpose of: l l

l l

l l 1) Rendering determinations in writing with regard as to whether i or not an unreviewed safety question (defined by 10CFR50.59) is I involved; and l I I I I I 2) Furnishing written recommendations to the plants' General l Manager for approval of disapproval.

l l 1 1

I l l I I i

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I I

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l These activities include changes to plant procedures and Technical l j l v i Specifications, proposed modifications to plant systems, changes to I I

l plant security and emergency plans, and review of facility l I

I operations to detect potential nuclear safety hazards. I I

I I

I 1. 6. 3 Committee Structure I l

l I

I I

I The organization structure and administrative requirements specific to l i

j each committee are described in the plant's Technical Specifications and l I in internal procedures / documentation. I I

I l

l I

I

1. 7 ORGANIZA'IONAL INTERFACES AND RESPONSIBILITIES I I

l~

l I

I As owner and operator, AP&L assumes full responsibility and authority for  !

I l the plant including action to assure that the plant is operated in l

~l I accordance with sound engineering practices, Licensing requirements and l I

l applicable codes, specifications and procedures.

l 1

1 I

~ (] l Each supplier of equipment, material or services and each maintenance or I l

I I

modification contractor is responsible for administering the applicable I I

l quality control functions as required by AP&L. The Quality Assurance and l l

I Quality Control organizations are responsible for assuring by I I

l surveillance, inspection, audit or review of objective evidence (e.g., l I

I audit reports conducted by others, etc.) that these functions are l I

l accomplished for systems and structures that affect the safety and l I integrity of the plant. I I

I I

I I

I Visits to manufacturer's shops by Quality Assurance organization I I

l personnel are conducted, when deemed necessary, based upon safety l I

l significance, complexity, method of acceptance and past history of the I l

l vendor, to establish product quality and to assure that quality assurance l I and quality control programs function in accordance with AP&L I I

l requireinents. i l

l l

l I

I I

,, I I

('~') i I I I l -- A l TOPICAL REPORT lREv. 6 l l P l 1, &

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.i l

I I

I I The AP&L Energy Supply Organizational Chart (Figure F-3) shows the l I

(~'T- reporting relationships and the lines of communication established I

- g' 1 I

I between the Quality Assurance and Quality Control organizations. These l l lines!of communication are established between the various quality l 1 organizations in order to provide assistance and/or information, when I requested, in verifying satisfactory implementation of the quality I program and in resolving significant conditions adverse to quality. I I

I l

l I

I l

I

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1 I

l l

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I l

l12.0 QUALITY ASSURANCE PROGRAM l j- 1 l

" I

'" l

-l 2.1 ' SCOPE l

l l

I l

l- This quality program is to assure that AP&L nuclear plants are operated l l in a sa'fe, reliable and efficient manner and in accordance with NRC

-l regulations, applicable industrial standards and codes and applicable l l.Companypolicies,. rules,proceduresandlicensingdocuments. A matrix of

,I

-l QA Procedures cross-referenced to each criterion of 10CFR50, App. 8, is l lincludedinTable2.tothismanual.

l- l

- 2.2 GENERAL I I

I

-l-2.2.1' ,I

I I l

g 'This quality program is applie'd 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 fy .

l. cause undue risk to the health and safety of the public or to mitigate l D the-consequences'of such accidents if they were to occur. These l structures, systems, components and consumable items are identified in l

_ltheQ-listwithintheFSARforeachnuclearunit. When structures, l systems and components as a whole are on the Q-list, portions not l associated with'a loss of safety function as determined by Engineering l

l are to be considered Non-Q, unless otherwise dispositioned by l

-Engineering.

l

1 I I

• Expendable and/or consumable items are to include, as a minimum: I nuclear-fuel,weldrods,boricacid,anddieselfuel.

l I I I I l- 1 I I I I l- 1 l l l l l 1 l

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l l

l l 2.2.2 l l

I q j)' l l

l l The quality program for fire protection is addressed in the applicable l section of the FSAR for each operating nuclear unit, and implemented l through appropriate LRGO and plant procedures. lhe effectiveness of the l

fire protection program is verified through scheduled audits conducted by l the QA organization, under the cognizance of the SRC.

l l

l l

l 2.2.3 l l

-l I

l l

l The Q-list is under the control of the Licensing Mar.ager. 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 Q . list and changes thereto are performed in accordance with approved I procedures. Changes to the Q-list require review / approval by the l

. discipline Engineering Manager,, Quality Assurance Manager and Licensing i Manager.

l l

l 1

I o l 2.2.4 L) l l

l The following expendable and/or consumable items are to be controlled in l the following manner to assure service quality:

I i

1. Diesel Fuel - Service quality is assured by applicable l provisions / tests required by the Technical Specification for l

l each operating nuclear unit.

l l

I

2. Welding Rod - Servica quality is assured by procurement from an l evaluated source, requiring material test results, and I controlling the rod on site prior to use, to prevent I degradation. l l

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I I

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3. i

_g

1. Boric Acid - Service quality is assured by procurement from an l

( } evaluated source, requiring a batch analysis to assure I

_, I I ;

I conformance with our specification requirements, and on-site l control prior to use, to prevent degradation. I I

I I

I

2. 3 RESPONSIBILITIES I l

I I

I 2.3.1 I I

I I

1 lAP&Lrecognizesthatqualityassuranceisaninterdisciplinaryfunction l 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 l

I

, workers whose activities may influence quality). This quality program l designates responsibilities and duties of specific individuals, which may I be performed by their appointed designees.

I I

2.3.2 g

l g

This quality program assigns the responsibility for quality to the l

l departments performing the work and includes as a basic requirement that i I

g individuals responsible for verification of conformance are qualified and l 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 I

I I

-l I l 2.3.3 l i

I I

I

_l This quality program also includes provisions that require suppliers, I contractors, subcontractors, consultants, etc. to maintain and use I g

.l quality assurance programs reviewed and approved by the Quality Assurance l Manager. Audits or surveillances by the QA0 provide assurance of I compliance with applicable procedures. I I

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l l A l TOPICAL REPORT IREV. 6 I I P l 10 ATE 5/30/84 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-3 l l L I l l 1 I I I w

I I I l 2.3.4 I 3, I l

! ) l l

'" l l The Nuclear Fuel Supervisor within Nuclear Operations is responsible for l the assurance that nuclear fuel used in AP&L nuclear plants is designed, 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 l

~ administrative procedures. These procedures include the receipt, l inspection, handling, storage, and accountability of Special Nuclear l Material (SNM). The Nuclear Support Supervisor maintains a listing of l those individuals qualified to perform receipt inspections. l l

l l 2.4 PROCEDURES l l

l l

l l

l 2.4.1 l l

1 I

l l

l Activities which affect quality are defined in appropriate procedures, l which are developed to cover AP&L administration and control. The

n. l procedures state the policies and instructions necessary to fulfill the l intent of the program. Procedures provide for standard forms, lists, and l check-offs used in documenting the inspections, certifications, reviews, l I

surveillances and audits. The program and the procedures shall be 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 I l instructions are contained in the documents ~ listed in Table 3. l I

l l

l 2.4.2 I l

l l

l 1

'l Procedures assure that activities affecting quality are performed under l suitably controlled conditions. Controlled conditions include the use of I

-l appropriate equipment; suitable environmental conditions for performing l the activity such as adequate cleanliness; and assurance that required I g

I I

l l

1 1

I I

I

/~T I O l l A l

l TOPICAL REPORT l

lREV. 6 l

l l P 1 lDATE 5/30/84 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-4 l l t i I I I I I I e

.I I

I l

I prerequisites for the given activity have been satisfied. Administrative I v

procedures also assure that the need for special controls, processes, I I

I test, and equipment to attain the required quality and the need for l lverificationofqualitybyinspections,evaluationortestistakeninto I account. I l-l I

I I 2.4.3 I I

I I

I l Other AP&L organizations outside of Energy Supply may establish written l lprocedurestocontrolsupportactivitiesaffectedbytherequirementsof I this quality program. Procedures developed by such organizations are l prepared and reviewed for technical adequacy within the cognizant

'I organization, reviewed by the Quality Assurance Manager and approved by I the cognizant organization's department head.

1 I

2.5 PROGRAM REVISION AND CONTROL I

I g 2.5.1 l

l

(]

I 4 Program revision and control shall be the responsibility of the Quality l Assurance Manager.

l 1

I l

l I

I 2.5.2 l 1

I I

' l l Proposed changes to the Quality Assurance Program for Operations are to l lbesubmittedbytheQualityAssuranceManagertoaffectedLRGOandplant l

l management personnel for review and comment prior to approval and l l transmittal to the Nuclear Regulatory Commission. After resolution of l

I comments, changes are to be approved by the Quality Assurance Manager, I l Energy Supply Services Director, and the Energy Supply Senior Vice l

l President. 1 I

I l

l l

I l i I

I I

I l l hs l A

I TOPICAL REPORT l I l l IREV. 6 l l P I lDATE 5/30/84 l l & I SECTION: 2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-5 l l L l l l i I I I

l I I

'l. 2.5.3 I l l

-\ L l l l

l The Nuclear Regulatory Commission is to be notified of changes to this l l

I quality program annually for those changes that do not reduce the  !

.l I commitments in the program description previously accepted by the Nuclear l Regulatory Commission. Changes to the program description that reduce l

j the commitments are to be submitted and approved by the Nuclear l

Regulatory Commission prior to implementation. The Quality Assurance I l Manager is to determine if changes do or do not reduce the commitments of l I

.this quality program. I l

I i l

l 2.6 PERSONNEL I I

l l

l l

2.6.1 I I

l J l

lEmployeeswhosedutiesandresponsibilitiesarerelatedtothequality l program activities at or in support of the nuclear plant are to l l

participate in appropriate indoctrination and training programs to assure

. ,o l that suitable proficiency-is achieved and maintained in the work they are l l

performing. Such training shall include, as a minimum: plant security; l- discussion of the overall Company policies, procedures and instructions l l

which establish the quality program; an explanation of the AP&L quality l organizations; and a discussion of those procedures which implement the l quality program related to the employee's specific job-related activity.

l l

1 2.6.2 1

l 1

I The education, experience and responsibility requirements of individuals l _ involved in this quality program are documented in job descriptions which l are approved and periodically reviewed by management. Requirements for I l education, experience and proficiency levels are commensurate with the l 1

l l- 1 I

I I

I I

l

-l l l

q -l l ,

g l

kJ l A l TOPICAL REPORT 6 i

p lREV. l l l l0 ATE 5/30/84 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 l l -L l l l l l l 3 m

I-1 I

I i

.l degree of importance of the job assignment. Experience and training l

(] 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 1 in Table 1. Personnel whose qualifications do not meet those specified l in ANSI _N18.1-1971, and who are performing inspection, examination and l testing activities during the operational phase of the plant, are to meet l the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. l l

l l

l 2.6.3 l l

1 I

I l

l Personnel performing inspection and examination activities are to be l lindoctrinatedandtrainedtoassuretheyareawareoftherequirements l which govern their activity. Inspection and examination personnel are to I

~be qualified according to the applicable codes, standards, l specifications, regulatory requirements and LRGO and plant procedures. l Personnel performing inspections on those activities occurring during the l operational phase that are comparable in nature and extent to related l activities occurring during initial plant design and construction are to

. ,m

.i s l ~ meet the provisions of Regulatory Guide 1.58, rev.1 (9/80) and ANSI l V I N45.2.6-1978, in lieu of ANSI N18.1-1971. I I

I I

I 2.6.4 I

I I

l Personnel involved with welding or nondestructive examination of  !

i l materials, systems or components are to meet the appropriate i qualification requirements of the ASME Boiler and Pressure Vessel Code, i Sections III and XI, or for structural welds, the American Welding l

Society (AWS) Structural' Steel Code D1.1, and the American Society l Nondestructive Testing Standard SNT-TC-1A-1975, and certified to perform l these tasks in accordance with these codes and standards.

I I

_l l

I I

I I

I I

I I

l I

nV l , ,

l l A l TOPICAL REPORT lREV. 6 l l P' l lDATE 5/30/84 l I l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-7 l 1 L I I I l 1 l l a.

. I I

I l

l 2.6.5 l

em 'l I L) I l Personnel performing audits of the quality prcgram are to meet the l l

experience, training and qualification / certification requirements of l ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise l noted in Table 1. I l

'* l 2.6.6 l

l Training records are to be maintained in accordance with approved i procedures. For formal training programs, documentation is to include l the objective, content of the program, attendees, and date of attendance.

I I

2.7 PROGRAM REVIEW l

l l

l - 2. 7.1 ,1 1

1 lTheQualityAssuranceManagerisresponsiblef'orareviewofthisprogram

() l on an annual basis to determine the effectiveness and proper l

'd implementation of the quality program.

I I

2.7.2 l 1 Management reviews of the status and adequacy of the quality program are l -accomplished through regular reports and presentations by the QA0 and l through reviews of quality assurance audit reports. Quality Assurance l reports supply data on the status of outstanding audit and corrective l action items and may identify the status of other significant quality

.l program activities as requested by management. l l l l 1 l- l I l

.l l l 1

l. I I l l 1

(')

V l

l A l

l TOPICAL REPORT l

6 l

lREV. l P

l l lDATE 5/30/84 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-8 l l L l l l

l l I l

I I

I I

l 3.0 DESIGN CONTROL i

7 l

1. l

~

1 1 I

-l 3.1 SCOPE l

l-1 I

I l Design activities are to be controlled to assure that proposed plant l changes to the structures, systems, equipment and components conform to

,I l applicable regulatory requirements and that design bases are correctly l ltranslatedintoappropriatedesigndocuments. Design Control activities l are to be in accordance with the requirements of Regulatory Guide 1.64 -

l l

l.Rev.2(6/76)unlessotherwisenotedinTable1.

_I I I

3.2 GENERAL I I

I I

I

,I 3. 2.1 1

1

- Engineering Services and Plant Engineering are to be responsible for the l continued upgrading and modification of plant design. Design documents l (drawings, specifications, procedures and instructions) originating or l

,e l released through these departments are to be based upon the required l O]- lregulatoryrequirements,licensingbaseddocuments, functional l requirements, quality standards and design bases in accordance with NRC l

l

,I 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 inspection criteria. Those design activities performed by individuals l within Engineering Services are controlled by the use of LRGO Energy l Supply Procedures. Those design activities performed by individuals l

within Plant Engineering are controlled by the use of Plant l Administrative and Engineering Administrative Procedures. These l procedures include controls to assure that verified computer codes are

-l certified for use and that their use is specified. l 1

I I

I l i I

l l

I I

I n l , , l l A l TOPICAL REPORT 6 lREV. l P

l l lDATE 5/30/84 l l & I SECTION: 3.0 DESIGN CONTROL IPAGE 3-1 l l L l l l l 1 I I 1

?

l l

l l

l 3.2.2

,Q l l

V l l

l l Design standards and requirements are to be at least equivalent to those l lemployedduringtheconstructionoftheplantandaretobeconsistent I with the technical specifications and license requirements. 1 I

I I

I l 3.3 DESIGN INTERFACE I l

l I

I l Design control activities include measures for the identification and l l control of design interfaces between the various engineering disciplines l l within the department, between LRGO and plant engineering personnel, l lbetweenengineeringpersonnelandotherAP&Lsupportorganizations,and l between engineering personnel and firms / suppliers outside the AP&L l

' l j organization. These measures include the development of procedures among l g

l the participating organizations for the review, approval, release, i distribution and revision of documents involving design interface. I l Coordination of the interface control is the responsibility of the l originating organization's management unless otherwise specified in an j l AP&L procedure applicable to the design activity. Design information I v g g

g between interfacing organizations is to be documented and retained for g

l permament records.

I l l

'l I l 3.4 DESIGN VERIFICATION I I I l l I 3.4.1 I I I I I l To assure the design is adequate and the above requirements and l I

g procedures are implemented, Engineering Services for LRGO design or Plant i Engineering for plant design are to verify the adequacy of the design i through the performance of design reviews, the use of alternate or l

l simplified calculation methods, or the performance of a qualification i l 1

-l 1 I I I I l l l l D l d l l l l

l l A l TOPICAL REPORT IREV. 6 l l P l lDATE 5/30/84 l l & l SECTION: 3.0 DESIGN CONTROL lPAGE 3-2 l l L l l l l l l 1

i l l I I l testing program. The extent and depth of design verification performed I h~ .lbytheresponsibleorganizationisdeterminedbyanassignedengineering I g

i reviewer based upon the importance and complexity of the design, the l I

degree of standardization and its similarity with proven designs. In all g

l l cases, the design verification is to be complete prior to relying upon l the component, system or structure to perform its function.

l l 3.4.2 I l The verification process is to be performed by competent individuals or l groups other than those who performed or supervised the design but who I may be from the same organization. This verification, however, may be I performed by the originator's supervisor in accordance with departmental I procedures if he is the only individual in the organization competent to I g

l perform the verification and provided the need is individually documented l landapprovedinadvancebytheresponsibleManagerorSuperintendent.

l The frequency and effectiveness of use of Supervisors as design verifiers l is to be verified by QA through scheduled audits to guard against abuse.

l (l

V l Where changes to previously verified designs have been made, design i l

g verifications are required for the change, including evaluation of the l g

l effects of the changes on the overall design. I I I I I l 3.4.3 l l l l 1 l When a test program is used to verify the adequacy of a design, it is to I f'includesuitablequalificationtestingofaprototypeorinitial g I

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

l be performed as early as possible prior to installation of plant I equipment, or prior to the point when the installation would become I irreversable. I I I I I I l l l l l l 1

,q l l V l l l l l A I TOPICAL REPORT IREV. 6 l l P l lDATE 5/30/84 l l & I SECTION: 3.0 DESIGN CONTROL lPAGE 3-3 l l L I i l

-l l I I

i l

1 l l l- 3.4.4 l q_ l I

l

• / - l l Design work performed by organizations outside of AP&L is to receive a l I

documented review and approval by engineering personnel in accordance l with LRGO and plant departmental procedures. l l i I

I l 3.5 DESIGN CHANGE l

l l l

l l 3.5.1 l

l 1

l- l l Methods for the preparation, review, approval and implementation of l 4

design changes, including field changes, are documented in departmental l procedures for Engineering Services and Plant Engineering. Design l

l lchangesaresubject'toreviewandverificationbythesameorganization

_, -l which review and verified the original design unless otherwise specified l in departmental procedures for design control. If minor changes to an l approved design are required to meet plant requirements or conditions, l

' Field Change Notices (FCN) may be issued or otherwise documented by a l . cognizant engineer and transmitted with the changes for review and l b'

a'prcval p in accordance with Plant Engineering Administrative Procedurcs.

I I I 3.5.2 I I I I I

-Changes from specified design inputs, such as decign bases, regulatory l

l requirements, codes and standards (including quality standards) are to be l ident1 Tied, approved, documented and controlled through applicable LRGO

.l- and plant departmental procedures. l l l I I l 3.5.3 l l l l l l During preparation of a design change, the responsible engineering l organization is to perform a safety and environmental evaluation per l I l l l 1

-l l o # l , , l l A l TOPICAL REPORT (REV. 6 l l_ P l lDATE 5/30/84 l l & l SECTION: 3.0 DESIGN CONTROL lPAGE 3-4 l

l. L l l l

~l I l l Iz - _. . ..

e I

I i l

l 10CFR50.59 to verify compliance with the Final Safety Analysis Report and l

,7 l to determine if NRC approval of the design change is required. The I i>- _l l

l evaluation is to be documented and then reviewed by the PSC.

l l

l 1

l 3.5.4 l l

l l

l l

l Design changes are also to be submitted to the Manager, Nuclear Quality l l

I Control _ prior to plant implementation to verify the use of appropriate l I

l quality codes, standards and inspection requirements in the design l I documents. I

- 1 l' I I

I 3.6 CORRECTIVE ACTIONS I I

I I

I I

l When design changes are made as a result of design deficiencies or I l

l errors, corrective actions (for significant conditions) are to be taken l l

l in accordance with Section~16.0, to determine the cause and to institute I I

l appropriate changes in the design process and/or Quality program to l prevent recurrence. When a significant design cnange is necessary l because of an incorrect design, the design process and verification l

_\J l I

procedures shall be reviewed and modified as necessary. I I

I I

I

3. 7 DESIGN RECORDS I I

l l

' l I

I The Plant Administrative Manager is responsible for maintaining permanent I I

l records of the design documents for the construction and testing phases. l l

I In addition, he shall be responsible for maintaining records of the  !

I l upgrading or modification of these documents as described in this l I section. The controls for maintaining these records are established by I I

I l specific procedures described in Section 17 of this manual. These l

l I

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

l 1

1 I

I I

I I

I I

I

T I I I

\d i A l TOPICAL REPORT I

IREV. 6 I

l 1 P l 10 ATE 5/30/84 l l & I SECTION: 3.0 DESIGN CONTROL lPAGE 3-5 l l L I l l l l 1 1

f I l

-l l

l 4.0 PROCUREMENT DOCUMENT CONTROL l

n s l l

l 4.1 SCOPE

. I' ' .

l l c .

l

'(l Requirements,for the procurement of items and services are to be clearly l I

, _I stated and, . documented to assure that applicable regulatory requirements, I l

1 design bases', technical requirements and quality assurar,ce criteria are l b 'l r- t j included or referenced in the procurement docurnents, whether procured by l LRGO or'; slant procurement groups. Procurement document control l l

g a'ctivities are to be in accordance with LRGO and plant procurement I y

l procedures and are to meet the provisions set forth in NRC Regulatory l Guide 1.'123, rev.1 (7/77) unless otherwise rioted in 7able 1.

~

s l_ N '

l I' 4.2 Pit 0CUREMENT DOCUMENTS s I l '

l l

l

'4.2.1

+

l l

The_ procurement of materials, parts and components are gene' rated through NNt >

N l t!le prepaiation of a Purchase Requisition (PR) and subsequent issuance of l

.g .%

'd l 6 a,Purchast Order (PO), or when' additional services from the Vendor is  ;

l l req'uired, ?.hrough the preparation and issuance of a Contract. The l proct.rement 'af- services is initiated through the preparation and issuance I of a Contract. The preparation, review, approval and issuance of these l g procurement documents is to be in accordance with applicable procurement l and contract administration procedures. Purchase Orders for items are l I

issued through the AP&L Purchasing group and Contracts for items and/or l . services are issued through'the AP&L Contracts Administration group. l l

l l

l l 4.2.2 l l

l l

l l Procurement documents are to include or reference specific dasign l specifications for the items or services to be procured which define

'l specific codes, standards, tests, inspections, environmental l

' l qualifications, and records to be applied and/or furnished. For standard I

I

, n i I

( I l l

'# l l l A l TOPICAL REPORT 6 lREV.

l

l P l lDATE 5/30/84 l l & 1 SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-1 l l L l l l l l- 1 I 1.

r; I

l 1

l l "off-the-shelf" items, reference to the items catalog number and I

/~' identification number may be included on the procurement document in lieu

l l of a design specification. New or revised specifications for replacement l items are-to be evaluated by the responsible engineering organization l ~against the original specification for the item. The evaluation is to be l

~in accordance with applicable engineering procedures and results in the I g

-l establishment of new baseline and technical quality requirements, which I are to be used for subsequent procurements.

.I l

I I

- 4. 2. 3  !

I i

l I

lProcurementdocumentsarealsotoincludetheidentificationofquality l assurance program requirements applicable to the items or services l

l procured. Procurement documents also establish requirements for source l audits and inspection, extension of the procurement requirements to lower i tier suppliers or subcontractors, and preparation and delivery of I documentation. These requirements may either be in the form of documents I attached to the P0 or Contract or by incorporating them in the specific 7] l design specifications. Quality programs are to be specified by invoking l d the appropriate sections of 10CFR50, App. B, the appropriate ANS1 I g

l standards and/or the appropriate AP&L generated quality requirements for l l items or services. The appropriate sections of the ASME Boiler and i Pressure Vessel Code are to be invoked for items originally designed to l meet ASME requirements.

l l l 4.3 REVIEW OF PROCUREMENT DOCUMENTS g

l l l The responsible Quality Assurance or Quality Control organization, as l

l identified in the LRGO and plant procedures for procurement and contract l administration activities, is to review all procurement documents to l assure that the required quality requirements (including source l surveillance and/or inspection) are imposed on suppliers / contractors.

l 1 I l l I I

!: I l l l A TOPICAL REPORT REV. 6 I P l IDATE 5/30/84 l l & 1 SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l 1 L l , I l l l l l L.

<l;f , . I./ '

T' i

'I r l' . .

l 4.4 I 7';1 1 CHANGES j T0*conctiorMENT DOCUMENTS l

-m l \ ,

I l .?i, i

('3)

' .f l Changes to, procurement documents are/to have the same degree of control I

h'fy and review as imposeo'on the original documents. Changes such as l

W l . inconsequential editorial corrections or changes 'to commercial terms and l

,.. J -  !

l condiffons mai be made by the Nuclear Buyer or Contract Administrator as I l

l appropriate, af ter concurrence f rom the originator.of the document. l

l--

l 1 '

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.p l lDATE 5/30/84 l l & J SECTION: 4.0 PROCUREMENT DOCUMENT CONTF.0L lPAGE 4-3

{4* l pgd. L l

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l l

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-l

' '! I I I

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.--cn TNCTRUCTIONC PRnrFDURE9 ann nRAWINGS l

% l l

) l I l 5.1 SCOPE- l l l

'l- I

~l 5.1.1 l l l l l

.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 minimum: l administrative, ga:eeral plant operations, start-up; shutdown; power

-l operation and load changing, process monitoring, fuel handling; l modification; maintenance and repair; radiation control; calibration and I ~ test; chemical-radiochemical control; plant emergencies; test and

_ l

'i nspection; 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 I I Table 1.

l l 7-)

l l

l I

5.1. 2 I 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 postehted accident. l l 1 l l l 5.2 GENERAL l l 1 1 I l 5. 2.1 1 I I I l l Instructions, procedures and drawings are to include appropriate l quantitative criteria such as dimensions, tolerances and operating limits l and/or qualitative criteria such as comparative workmanship samples to l determine that important activities have been satisfactorily I I I 1 I (m-

) I I I I l A l TOPICAL REPORT IREV. 6 l l P- l lDATE 5/30/84 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-1 l l L l AND DRAWINGS l l l l l 1

o I

i l '

I l accoinpl i sneu. tach procedure is to be sufficiently detailed so that a l I

(~')

x / l qualified individual may perform the required function (s) without direct I

~

l l supervision and is to include measures to document the activity being l performed.

l 1

I

5. 2. 2 I l'

l l

l

. To assure the accomplishment of activities in accordance with approved l instructions, procedures and drawings, each supervisor is responsible for l lqualitycomplianceofhispersonnel. Verification that activities are l . accomplished in accordance with approved instructions, procedures and l drawings is obtained through various levels of surveillance and l inspection by Quality Control personnel and through periodic surveillance l and audits by the QA0.

1 I

l 5.3 REVIEW 0F INSTRUCTIONS, PROCEDURES AND ORAWINGS I l i I

I 5.3.1 l

(')

l l

Instructions, procedures and drawings are prepared, reviewed and approved l in accordance with applicable plant administrative procedures, when l originated at the plant, or in accordance with applicable Energy Supply procedures, when originated from LRGO.

l l l l l

l. l l- 5.3.2 l l 1 1 I l Plant procedures identifiad in the Technical Specifications for each unit I and changes thereto which describe activities required to implement this

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 h

l issuance. Plant Administrative procedures (1000.XX Series) are also I reviewed by the Quality Control staff to verify compliance to AP&L's l l l l l 1 1 1

-n i I

( ) l I

'# i 1 l 'A l TOPICAL REPORT 6 lREV. l l P l . l0 ATE 5/30/84 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l l L l AND DRAWINGS 1 1 1 I l I

7_

i i i i quality program requirements. LNbU Energy supply procedures describing I

l activities. required to implement this quality program are to be reviewed  !

~'

l and approved by a procedures task force committee and Quality Assurance l to assure compliance to AP&L's quality program requirements prior to l submittal of the procedures to the Department Head responsible for l implementation, for approval and subsequent issuance.

I I

I

5. 3. 3 I I

l i I

Plant and LRGO procedures and instructions are to be reviewed no less I l- than every two years to determine if changes are necessary to meet NRC l

. commitments and current AP&L practices. Applicable procedures (i.e.

l those that relate to the incident cause) are to be reviewed following an l lunusualincidentsuchasanaccidentunexpectedtransient,significant l_ operator error or equipment malfunction. Applicable procedures are also I to be reviewed following any modification to a plant system.

I I

I 5.3.4 I I

I f3 -l l

Y- Drawings related to plant changes and modifications are controlled as l . described in Section 3 and 6 to this manual.

l l

1 1

I I

l 5.4 CHANGES TO PROCEDURES l

l 1

l l 5.4.1 I l

l 1

I i

l Changes or revisions to approved instructions, procedures and drawings l are to be reviewed and approved by the same organizations or groups that l performed the original review unless otherwise noted in specific AP&L l I

procedures and controlled in the same manner as the original. I l

I I

l l

I I

I i

1 1

I I

I I

O l l

. (d l A l

I 10PICAL REPORT l l lREV. 6 l 1 P l 10 ATE 5/30/84 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-3 l l L l AND ORAWINGS I I I I I __I

l l

l l 5.4.2 p

As I

l I

I l Temporary changes to approved plant procedures which do not change the 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 docurnented, 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 l plant procedures are to specify the period of time during which they may l be used and made readily available to affected members of the plant I fstaff. In the event of an emergency not covered by an approved I 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 l

l q 1, I

(_) l l l 1

l l l l l 1 l- 1 I I u l l 1 I l I I I l 1 I l l I l l l 1 I l

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.I- A l TOPICAL REPORT lREV. 6 l l P. j IDATE 5/30/84 l l & 1 SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-4 I L '

l l AND DRAWINGS l I I I l

i.

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,, I l

i I 6.1 SCOPE l l-l 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 I l documents, such as calculations, computer codes, analyses, Topical l l Report, FSAR, instructions, procedures, specifications, manuals and I drawings, including changes thereto, which prescribe activities affecting l quality.

l.

I I

l .6.2 RESPONSIBILITIES l

l l

l6.2.1 l l

l lEachorganizationoriginatingdocumentswhichprescribeactivities I af fecting quality is responsible for the establishment of document l l

, g control procedures which identify individuals or groups responsible for

) I preparation, review, approval and maintenance of the document and for the l g issuance of these procedures to the affected individuals or groups.

I I

6. '2. 2 l l Review of these documents for concurrence with quality related I requirements is to be pe-formed by the appropriate Quality Assurance or l Quality Control organization or by the appropriate reviewer as described I in LRGO and plant procedures. l I l l l l 6.2.3 l l l l l l The plant Administrative Manager is responsible for the control and l issuance of plant procedures, and revisions thereto, to assure I distribution in accordance with plant procedures. The plant I Administrative Manager is also responsible for the storage and control of l

-l I

~

l l l l l A I TOPICAL REPORT IREV. 6 l l -P l lDATE 5/30/84 l l & 1 SECTION: 6.0 DOCUMENT CONTROL IPAGE 6-1 1

'l L l l 1 I l I l

I l l I

-appeuveu nistorical plant documents, and the storage of historical l I

7(o, drawing records. The Engineering and Technical Support Manager is  !

1. I

'~ l l responsible for the control and issuance of drawings and revisions l thereto to. assure that they reflect the as-built conditions of the plant.

l l

l 6.3 IDENTIFICATION I I

I I

l Documents are to be identified by a title descriptive of their purpose or

-l applicability and marked or stampad as to their current status (Draft, l

For Information Only, Void, etc.) per departmental procedures. Revision 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.

[

.I I

I I

l 6.4 DISTRIBUTION l

l I

I I

l Distribution lists and/or document registers are to be maintained by the l organization responsible for issuance of the document. These lists are fy l to identify the revision status of the document and are to be reviewed l l

V I- and update'd periodically by the responsible organization to maintain them l in a current status. These lists are available to individuals using the l

document to assure they are in receipt of the current document. These l measures are to preclude the possibility of using outdated or l inappropriate documents.

I, l

l l -6.5 CHANGES I l-1 I

I I 6.5.1 I I

I I

I 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 affected activity.

1 I

I I

I I

I I

C l l l

V l. A l TOPICAL REPORT l

IREV. 6 l

l l -P l lDATE 5/30/84 l l & 1 SECTION: 6.0 DOCUMENT CONTROL IPAGE 6-2 l l- L l l l l l I l

x

~~ n

'I ~ 6.5.2 l l' l C

) I l

i Obsolete or superceded documents are to be destroyed or marked to prevent I

. inadvertent use in'accordance with applicable document control  !

g I procedures.

l I

I I

I I 6.6 STORAGE I

I I

I I

I Documents which affect quality are to be stored and maintained at the I

'l plant in permanent storage facilities and controlled as described in l Section 17 of this manual.

l l

l l

1 l

l 6.7 VERIFICATION I I

I I

I l Quality Control personnel, through their various levels of quality I surveillance and inspection activities, and Quality Assurance personnel, l

l through their audit activities, assure proper documents are being used I

. and made available to those individuals performing the work.  !

y r^N l I V I I I I l l l 1 1 I I l l I I l l l l 1

' 1 I I I I I r

l l I l i l i l l l I I i l I

!- 1 I

I I I I I l I +

l A I TOPICAL REPORT lREV. 6

' I P

I l lDATE 5/30/84 l

& 1 SECTION: 6.0 DOCUMENT CONTROL l IPAGE 6-3 l i l L l I I I I I I I . -. .__ _ _._ _,. ~._ _ . . _ . . _ _ _ _ . _ _ . . _ _ _ _ _ . . _ . _ _ . . _ _ ,

F I

I I

i 1 /. u CONTNUL UF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l

g I l

i l I

l 7.1 SCOPE l

l l

l l

1 The purchase of material, equipment and services is controlled to assure l that, whether purchased directly or through vendors, the material, l equipment and services which affect quality conform to the procurement l

l documents. Procurement control includes provisions for source evaluation I l ~ and selection, objective evidence of quality furnished by the contractor, l

-lsurveillanceandauditatthesource,examinationofproductsupon l delivery and testing of received material for conformance to procurement l criteria. The depth and necessity of procurement controls depend upon I the uniqueness and complexity of the item / service, procurement frequency I 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 the requirements of Regulatory Guide 1.38 Rev. 2 (5/77) and 1.123 Rev.1 l (7/77) unless otherwise noted in Table 1.

l n i I

LJ l7.2.SOURCEEVALUATIONANDSELECTION l 1

l 7.2.1 l l l s l lAQualifiedVendorsList(QVL)istobemaintainedandcontrolledunder l the direction of the Quality Assurance Manc er. The QVL identifies l lthosevendors/contractorsthathavebeenevaluatedandapprovedbythe l QA0 to furnish material, ,eguipment or services, and identifies any l

' restrictions imposed by the QA0 on the vendor / contractor as a result of their evaluation.

l l I I l l l 1 l l I l- I

-l 1

I I I I I I l l

(~3 l l l l Is' A l l TOPICAL REPORT IREV. 6 l p

l l lDATE 5/30/84 l

'l & l SECTION: 7. 0 CONTROL OF PURCHASED lPAGE 7-1 1.

I L l MATERIAL, EQUIPMENT AND SERVICES I l l l l l

4

3ph y & -

3

- I: 1

(.f

~l l

I Vendors / Contractors are_ evaluated and placed on the QVL by any of the l

~

following methods, as approved by the Quality Assurance Manager:

ll~ l (1) Source' survey by AP&L to verify compliance to applicable 10CFR50, ,I gr -l! _ Appendix B requirements or to applicable ASME Section III Quality l Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG I

I components).

l

'l l I

l l (2) . Evaluation and acceptance of source surveys performed by others l (ex. CASE, other utilities, NSSS suppliers, and prime contractors) l indicating a program meeting the appropriate requirements of l 10CFR50, Appendix B. (This method is not applicable for ASME l- procurements.)

l l

l l

1 .

I I (3)- A review of the vendors / contractors current quality records l supported by evidence of documented qualitative and quantitative h I information which can be objectively evaluated. This includes l l review and approval of the veridor's/ contractor's quality assurance program, manual and procedures, when available. (This method is not l

l l applicable for ASME procurements).

~ l l l l-(4)' Evaluation of the vendor's/ contractor's history of providing a l

l . product / service which performs satisfactorily in actual use. l l Evaluation information includes: experience of users of identical l

l or similar products / services of the prospective vendor / contractor; l I

y 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 l l(5) Verification that a vendor is a holder of an ASME Certificate of Authorization issued as a result of an ASME survey may be used in l

.l l lieu of methods 1 and 2 for ASME procurements.

l-I l

.O i l A i

l TOPICAL REPORT i

IREV. 6 i

l l P l lDATE 5/30/84 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-2 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l l l

.I l

l

• 1 l (6)- Verification'that a contractor is a holder of a NRC letter i confirming QA program implementation may be used in lieu of ,I I method 1. I I

l I. I I 7. 2. 3 -

l I

l l

l l Only vendors / contractors listed on the QVL are to be selected for I procurement of material, equipment or services except for items I designated " commercial grade" per plant and LRGO procedures. Standard I catalog items may be procured from a vendor / contractor not listed on the I g

l QVL provided the manufacturer of the item is on the QVL and all AP&L l requested' documentation originates from the manufacturer. The QVL is to

-l be periodically reviewed and updated per quality assurance procedures to l

I ensure the current status of all selected vendors / contractors is l

l Lavailable to personnel involved in the procurement process. I I

l l l l- 7.2.4- 1 I

l l

l p I When contractors are selected to perform work activities at the plant, l V their personnel and work activities are to be controlled in accordance l

l with plant procedures to assure that the contractor conforms to the l

_ procurement documents.

l l 1 l-7.3.SOURCESURVEILLANCE-ANDAUDIT g

I I l'7.3.1 # l 1 1

-The effectiveness of a vendor's/ contractor's quality assurance program is l

l assessed by QA personnel at intervals consistent with the importance, 1 -

l complexity, method of receipt and quantity of the products or services.

l l This assessment may be through source surveillance, source audit, receipt 1 I l

. inspection, independent testing or review of source documentation files. g i 1

1. I

-- l l l l l

O l l-1 l

D A TOPICAL REPORT I

6 1 I lREV. l l p l lDATE 5/30/84 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-3 l l L l MATERIAL, EQUIPMENT AND SERVICES I l l l 1 I

m

.I l LJ

~

.I- -

w, l7 7.3.2 I l

l l

l .

l l ' Requests for source surveillance are mada by the originator of the PR/ l Contract,_and/or tne responsible Quality Control or Quality Assur ece  !

l organization during. their review of the procurement document (reference l I

l- section 4.3) Source surveillance is to be performed by QA personnel or I l

l..their appointed representative in accordance with <.urveillance plans l approved by the _ Quality Assurance Manager and the results documented per l quality assurance procedures. Reports documenting inspections performed l

and discrepancies observed are prepared by the person performing the I

-l - surveillance to _ document compliance to the procurement documents and for i

future use as historical quality perf ormance data.

I I

I 7.3.3 I l-1 I

I I

l Audits of the_ vendor's/ contractor's quality assurance programs are I 1

l periodically performed under the direction of the Quality Assurance l Manager to' verify implementation of a satisf actory quality program on the

- )' l items or services being procured by AP&L. Audits performed by others l I

l (e.g., CASE, other utilities, or prime contractors), as evaluated and I l

l approved by the Quality Assurance Manager, may be used as an alternative l l to audits by AP&L to verify the vendor / contractor is implementing a I I

l satisfactory quality program. Audits are to be conducted in accordance I

l-with Section 18 of this manual. (This alternative method does not apply I I

-l to ASME procurements.)

i I

I I

I l 7.4 RECEIPT INSPECTION I

I I

l l

l 7.4.1 l

1 l

i 1

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 i I

l performed in accordance with plant procedures for receipt inspection. I I

I I

I I

(

v'

'l l  ! I l A l 10PICAL REPORT 1REV. 6 l P

l l lDATE 5/30/84 I l & l SECTION: 7.0 CONTROL Of FURCHASED /-4 IPAGL l l L l MATERIAL, EQUIPMENT AND SERVICLS I i

l i __ l l

1 1

1.

l

, 1 7.4.2 ' 1

'~ l l

L l l

-I.

Receipt inspection activities are to be documented and include, as a i minimum: examination of material or equipment for shipping damage, I proper identification, and quantity; and the review of vendor 1

- documentation, to verify compliance with the procurement document. In l addition,-if material and equipment received at the plant were not l

I inspected at the vendor's facility by AP&L, an inspection is to be l- . performed by a Quality Control Inspector at the point of receiving to I

.l verify that the material or equipment confor:n to the inspection I requirements identified in the procurement documents. I I

I l

l I 7.4.3 I

l- l l

l l- Vendors are to furnish documentation as requ' ired by the procurement I

documents for objective evidence that the material or equipment conforms I to the procurement requirements. Review and acceptance of this I documentation is to be performed by a Quality Control Engineer prior to ey 1 installation or use of such material or equipment and documented unless l

I I

n- otherwise specified in plant procedures. Certificates of Conformance may l

l be required by procurement documents which identify the requirements met I by the vendor. The validity of the vendor's certification program is to l be periodically verified through scheduled source surveillance and audit l lactivitiesorthroughindependenttestingoftheitembyAP&L.

I I

7.4.4 I

I Accepted material and equipment is released, identified as to its l inspection status and forwarded to a controlled storage area or released 1

- for installation per applicable plant procedures.

l l i I I

I I

l l

I I

I I

I o> l l i l l A i TOPICAL REPORT 6 IREV. l l P l lDATE 5/30/84 l

1. & 1 SECTION: 7.0 CONfROL OF PURCHASED lPAGE 7-5 I I L I MATERIAL, EQUIPMENT AND SERVICES I l

.I I I I w

I I

I l

~

j 7.4.5-l

,- l l

) l l

l . Acceptance of services furnished by a contractor is to be identified in l l the procurement documents. Depending upon the service performed, l acceptance may be by technical verification of the data produced, l I

1.

surveillance and/or audit of the activity, or review of objective I l

l evidence for conformance to the procurement document requirements. The l I

acceptance method is to be performed by qualified individuals I l l l knowledgeable in the service provided. l l

l 1

I l 7.4.6 l

l 1

I l

l Independent testing of selected material is to be performed in accordance l with plant procedures / instructions to verify conformance to procurement l criteria and the validity of the vendor's certification documents. l l

l 1

l l 7. 5 NONCONFORMING ITEMS l

l 1

1 I o l 7.5.1 l J l l I I l Nonconformances identified by the vendor / contractor which adversely l affect reliability, performance or interchangeability of the item and l dispositioned repair or use-as-is are to be submitted to and accepted by l I

AP&L prior to closure of the nonconformance by the vendor / contractor.

l These nonconformances are to be documented and become part of the l I

procurement documentation furnished by the vendor / contractor for the l material, equipment or services procored. l l 1 1 I l 7.5.2 l l 1 1 I l Material and equipment found to be deficient or missing procurement l e I documentation during receiving inspection or found to be deficient as a l result of independent testing is to be clearly identified, segregated l l l l l l 1 1

(')

U l

A I I I

I l l TOPICAL REPORT IREV. 6 l l P l 10 ATE 5/30/84 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-6 l l L l MATERIAL, EQUIPMENT AND SERVICES I l l l l 1

d i

I l

2 l T -

i: from acceptable items and dispositioned per plant procedures and as I

.."(] ' g . described in Section 15 of this manual.

~l l

i 17.6- SPARE PARIS ,

I f

I l

~

f Spare parts are to be purchased to the original design requirements or to

,_ l those.specified by a properly reviewed and approved revision to the l n -

-gl design requirements. The applicable quality assurance requirements and

-l- documentation requirements for spare parts are to be included in the l

. ' procurement documents.

1 I

7. 7 I l STORAGE I

I Material and equipment are-to be handled and stored as described in plant

l. proceoures and Section 13 of this manual.

l I

I I

l- '

I

.1 -

1 I

I l~ l Jet i I U-

>l I l I I I i l I I 1 l l I

-l l l l 1 l 1 l

- I l

.I l

'l l l i

'l l I I

'l l

~l I l- l l l l l

, I I

.I I a~

l , , l l A I TOPICAL REPORT IREv. 6 l

-l. P I . lDATE 5/30/84 l l & 1 SECTION: /. 0 CONTROL Of PURCilASLD lPAGE 7-7 I I L I MATERIAL, [QtilPMENI AND SERVICE 5 l 1 1 I I I

h l

I I

l

-l' 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS I q l I

, I

~' l I 8.1 SCOPE l l

l l

l l 8.1.1 1 l

i I

I l . Measures.for the identification and control of materials. (including l lconsumables),partsandcomponents,includingpartiallyfabricated l

l subassemblies,.are_to be established within LRGO and plant procedures. l lTheseproceduresaretorelateanitemofproduction(batch, component, I part, etc.) at any stage, from initial receipt through fabrication, I l installation,repairormodificationtoanapplicabledrawing, l l specification, or other pertinent technical documents. These measures I are to assure that only correct and accepted items are used and I installed. I l

l I

I l 8.1.2 I l

I I

I p, 1 Methods for the traceability of materials, parts and components to l U specific inspection and test records, when required by codes, standards, l

l specifications or procurement documents, are to be established within I I

LRGO and plant procedures and maintained throughout the life or g

l consumption of the item.

l l

I I I

I l 8.2 IDENTIFICATION I I I I I l 8.2.1 l l I l l l Materials, parts and components are to be identified by the vendor in I accordance with the applicable design standards, codes and/or 1 instructions specified in the procurement documents. l I 1 l l l 1 I I l- l l 1 n l l i l l A l TOPICAL REPORT lREV. 6 l l P 1 lDATE 5/30/84 l l & 1 SECTION: 8.0 IDENTIFICATION AND CONTROL IPAGE 8-1 l l L l OF MATERIALS, PARTS AND COMPONENTS I l I i l 1

i l

i I

l 8.2.2 I

^ l l

'C' .I l Materials, parts and components are to be identified and/or tagged at the l

l l

I l

plant in accordance with applicable plant procedures. These tags I I

l identify the status of and provide traceability to the item throughout l I storage and release to installation. I I

i

. I I

I 8.2.3 I I

I I

I I

l Identification of materials, parts and components is accomplished by I l

l either marking or tagging on the item or through records traceable to the l I item. I -

1 I

I I

I 8.2.3.1 1 l

l I

l l

I Physical identification is to be used to the maximum extent possible. I I

l Where physical identification is either impractical or insufficient, l physical separation, procedural controls or other appropriate means are f7 l to be employed in accordance with plant procedures. l Cl -l l l

1 l 8.2.3.2 l

1 1

I I l When identification markings are employed, the markings are to be clear, l I

unambiguous and indelible, and applied in such a manner as not to affect I I I l the integrity or function of the item. Markings are also to be l

transferred to each piece of material (plate, barstock, tubing, etc.)

l when subdivided. Large quantities of small items, may be identified by l I

applying markings or tags to their shipping packages, boxes or other l suitable containers. l l 1 1 I I I I l l I l l l- l l l l l 1 I

/?

\s' l l l l l A l TOPICAL REPORT lREV. 6 l p

l l l0 ATE 5/30/84 l l & 1 SECTION: 8.0 IDENTIFICATION AND CONTROL lPAGE 8-2 l l' L l OF MATERIALS, PARTS AND COMPONENTS l l l l l l

i l

I l

l- 8.2.3.3 l l

g i f I i

s l

l Identification markings are to be recorded on records or as-built l documents if current markings are to be hidden or subject to obliteration l by surface treatment or coatings during fabrication, installation, repair l or modifications.

I I

I 8.3 CONTROL I I

i I

l lPlantorganizationsreceivingmaterials,partsandcomponentsareto l verify that they are properly identified while under their control. l l

lQualityControlpersonnelthroughtheirsurveillanceandinspection l activities assure that compliance to these requirements are being met. l

'lQualityAssurancepersonnelthroughtheirauditactivities,alsoassure I that materials, parts and components are being identified in accordance l with this manual.

I I

l8.4 DEFECTIVE OR INCORRECT ITEMS l

n i I

V I 8.4.1 I I

I I

I Defective or incorrect materials, parts and components identified by l plant personnel or support groups are to be handled in accordance with l

i Section 15 of this manual and plant procedures for nonconformances and

'l corrective action. Defective or incorrect iteins are to be tagged with a l l " hold tag" affixed to the item or otherwise identified per plant l procedures. I l

l 1 I i 8.4.2. I I I l I l Defective or incorrect items are to be stored in segregated areas except l for those items installed or which, due to their size, weight l configuration, etc., are impractical or impossible to store in the I designated controlled storage area.

I I l

f) l l I I I l A l TOPICAL REPORT lREV. 6 l p

l l lDATE 5/30/84 l l & 1 SECTION: 8.0 IDENTIFICATION AND CONTROL IPAGE 8-3 l l L l OF MATERIALS, PARTS AND COMPONENTS l l l l l I

I.

I I

I ..

l tl 9.0 . CONTROL"Or-SPECIAL PROCESSES l

. [D .

V 9.1 SCOPE l l

l l-l I;

1

.l-;Special. processes are to be controlled through the use of qualified I

?

personnel and plant procedures which meet the requirements of applicable l

l ' codes, specifications, standards and other criteria stipulated in AP&L l ll'icensingdocuments.

l l

l l ' 9. 2 GENERAL I I- 1 I

I l:9.2.1' l

I Special processes are those activities which require interim inprocess l controls in addition to final inspection to assure quality and include l such activities as welding, nondestructive examination, heat treating, I coating, plating and chemical cleaning. l 1

l l

W I

J 9.2.2 l

V; l l

l 1

l Technically qualified LRGO or plant personnel are to establish the l

procedural and qualification requirements for those special processes not l

l covered by existing codes or standards or where AP&L quality requirements l s exceed the requirements of established codes or standards.

l l 9.2.3 l

.I l The requirements for welding and nondestructive examination are to comply l

-l' with the: applicable portions of the ASME Boiler and Pressure Vessel Code 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

ll systems are to comply to the requirements of NRC regulatory guide 1.37, l

=

' dated 3/16/73 unless otherwise noted in Table 1.

l

l. I I

O C I l A I

l TOPICAL REPORT I

lREV. 6 I

l l

l P l lDATE 5/30/84 l l & l SECTION: 9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-1 l 1 L i i l l I I I

r "l

l

-l l

l' 9.3 QUALIFICATION l

, l

' l

! l ..

l 9.3.1 l

'l l l

1 l

l Special process procedures for welding and nondestructive examinations l laretobequalifiedpriortousetoassurecompliancetoapplicable l . . codes, standards or specifications. These qualifications are to be l

~ documented and also made available for review to the Code Inspector for I activities on ASME items. l l

l 1 .

l l 9.3.2 l

l l

l- .

l l Personnel responsible for the performance and verification of special l processes are to be qualified and/or certified according to applicable l codes, standards, specifications, regulatory guides and plant procedures. l These qualifications and certifications are to be documented and made I available for review to the Code Inspector for activities on ASME items.

j Personnel qualification and/or certification records for a special l

l q- l process are to be regularly reviewed by the supervisor responsible for l

'J .that special process to assure that the appropriate documents are I l up-to-date and personnel are periodically requalified and/or recertified l In accordance with plant procedures. .

l l

I

9. 4 RECORDS I l i l

I I

.y The results of special processes are to be documented, reviewed, approved l and stored in accordance with appropriate plant procedures and as l addressed in other sections of this manual.

I I

l l l

1 1 I I

I l l l

l l

l l

l l I o'

v l

l A i

l TOPICAL REPORT i

lREV. 6 l

l l P l lDATE 5/30/84 l l & l SECTION: 9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-2 l l L l l l 1 1 I I

l I

_l -

l 31 .J 9.5 VERIFICATION l

n .-- I l

! l Performance of special processes in accordance with applicable codes, strudards, specifications and plant procedures is verified by Quality 1 Control personnel through their surveillance and inspection activities, I and by Quality Assurance personnel through their audit activities.

l

,- I

g-g 1

I l

l I

I l- 1 I

I I

I

-l l

i I

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-I I I

I l

I 1

1 l

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I

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I I

I

-l i I

I I

I I

I I I I

I l i I l l

I I I

.I I I .-

1 1

-3:

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I I

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I I A I TOPICAL REPORT 6 IREV. I I P. l lDATE 5/30/84 1 1 _& 1 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-3 1

'l L I I l 1 1 I I

I I

I I

i~ 10.0 INSPECTION l

^ l l

( ;- 1 l

l 10.1 SCOPE l

l I

l l

l Inspections relating to normal operating activities and inspections l relating to operating activities comparable in nature and extent to those

.l occurring during initial plant design and construction are to be I controlled to assure that inspections are performed in accordance with l applicable design documents, codes, standards, specifications and l procedures. Inspection activities are to be in accordance with l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1. I l l I

I i 10.2 GENERAL l l

l 1 I i 10.2.1 l 1 1 I I l Inspection activities relating to normal operating activities l (Operational Inspections) include:

l l l

1) Work functions associated with normal operation of the plant; l 2) Routine maintenance; I

,I 3) Technical services routinely assigned to the onsite operating l organization; and l

4) Non-routine maintenance activities and minor modifications made l by the onsite operating organization that are not comparable in l nature and extent to related activities accurring during l

l initial plant design and construction. I l I l l l 10.2.2 l l l 1 l l Inspection activities relating to operating activities comparable in l nature and extent to related activities occurring during design and l construction (Construction Inspections) include: l I I l l

, I I 1o) l l l l I

l l l A l TOPICAL REPORT lREV. 6 l

! l P l lDATE 5/30/84 l l & 1 SECTION: 10.0 INSPECTION lPAGE 10-1 l l L l l l l l 1 l L

I I

l 1

.l 1) Non routine maintenance, except as noted in paragraph 10.2.1; l q l and I i

' ' '-i I l 2) Modifications, except as noted in paragraph 10.2.1. l 1

1 I -

l l The following Regulatory Guides are to be applied, as applicable, in l determining the basis for required construction inspections: R.G. 1.30, l Rev. 0 (4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77); l lR.G.1.37,Rev.0(3/73);R.G.1.94,Rev. 1 (4/76); and R.G. 1.116, l Rev. 0-R (7/76). l l

l

'! l l

-l 10.2.3 l

1 -

1 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 performing the inspection are to meet applicable licensing requirements, l codes'and standards appropriate to the discipline involved.

l i

i l

i I

n l 10.3 CONTROL OF INSPECTIONS L) l I

I I

I l 10.3.1 I

I I

I I

l Inspections are to be performed in accordance with approved written l procedures, which set forth the requirements and acceptance limits and l specify the inspection responsibilities. If inspections require detailed l written procedures to perform the task, the procedures are to contain, as l a minimum, the following: I 1

l l

l l 1) Qualitative and/or quantitative acceptance criteria; i

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

l I

i 1

1 I

I I

l l

1 I

I O l l I

C' l A l TOPICAL REPORT l l lREV. 6 l l P l lDATE 5/30/84 l l & l SECTION: 10.0 INSPECTION lPAGE 10-2 l l t l I I i 1 I l

_. = . - -

E I 1

• ~

l-l'  !

3) -Identification of any special equipment and tools required to l

f] ._ perform the inspection (when accuracy = requirements for 1

inspections exceed the accuracy of normally available process l

.l- or_ measuring and test equipment, such additional accuracy l

l requirements are to be specified within those inspection I procedures);

i 14) A step-by-step description of the method of inspection, l examination,. measurement or test to be performed; and  !

.I 5) Identification of those inspection results to be documented. l Inspection forms or checklists are to be used as an aid in l- l documenting ~the inspection activity to assure quality l requirements have been met.

l l

l 10.3,2

~l l

I lOperationalinspectionsaretobeperformedbyqualifiedi.ndividuals l

l other than those who performed or directly supervised the activity being l l inspected. Construction inspections are to'be performed by qualified A l l individuals other than those who performed or directly supervised the Y .lactivitybeinginspectedanddonotreportdirectlytotheimmediate l

l l supervisors who are responsible for the activity being inspected. l

-l l

i I

l 10.3.2.1 l I

I

1. .I I l Operational inspections may be performed by second-line supervisory l lpersonnelorbyotherqualifiedpersonnelnotassignedfirst-line

-l . supervisory responsibility for conduct of the work.

l l

l -

l l

l l 10.3.2.2 l l

l l

I l Construction inspections are to be conducted in a manner similar to that l lassociatedwithconstructionphaseactivitiesinaccordancewith l applicable plant procedures. 1 I

I I

I I

l 1

'O d l l  !

I l

l A l TOPICAL REPORT 6 lREV. l l P l lDATE 5/30/84 l l & l SECTION: 10.0 INSPECTION IPAGE 10-3 l l L 1 l l l l l 1

I i

l10.3.2.3 l l

73 l

\

) l l

l If individuals performing inspections are not part of the Quality l Assurance or Quality Control organizations, the inspection procedures.

l personnel qualification criteria, and independence from undue pressure l such as cost and schedule are to be reviewed and found acceptable by the I l responsible Quality Assurance or Quality Control organization prior to l I

I initiation of the activity. I I

l -

l I

10.3.3 I I

l I

I If an inspection determined to be required is impossible or l disadvantageous, indirect control by monitoring processing methods, l equipment and personnel is to be provided to verify conformance with l applicable documented instructions, procedures and drawings. Both l inspection and process monitoring are to be provided when control is I l inadequate without both.

l l

l 1

I n l 10.4 INSPECTION POINTS l

~

.) l l

l l

l 10.4.1 l

1 I

l- l l Inspection hold points are established for non-routine maintenance l procedures and design change packages (DCPs) by Plant Engineering and l reviewed by the Plant Quality Control group for concurrence and possible l

l assignment of additional inspection hold points to further assure I l conformance with applicable instructions, procedures, drawings and l related documents or to meet appropriate cude and regulatory ,I l requirements. Inspection hold points for work functions associated with I activities other than non-routine maintenance and DCPs, are established l by the originating department, by Quality Control or other responsible l individuals. I I l l I I l l I I I

( l l C]/ l A I TOPICAL REPORT l

lREV. 6 l

l p

l l lDATE 5/30/84 l l & l SECTION: 10.0 INSPECTION lPAGE 10-4 l l L l- I l l l l I

s I

I

'l I

'l :10,4,f

- l l

J, -;)

~

l l

l l Inspection hold points are inserted in procedures based upon safety l

' significance, complexity of the item or activity, degree of

'l standardization of the item or activity, past performance of the item or l lactivitu, procurement frequency, anc' the ability to verify quality by

_ l jobsite testing.

l 1

I i 10.4.3 l l

l l

l l Inspection responsibilities, requirements, information and acceptance l lcriteriafortheworkactivityaretobeidentifiedinappropriate, l

l approved plant documents (e.g. procedures, checklists, ett..) l I

I I -

I i 10.4.4 l l

l 1

l I For work involving the modification, repair, replacement or in-service l linspectionofASMECodematerials,partsandcomponents,thework l

.n l packages are to be made available to the Code Inspector prior to l b commencing work for his review and assignment of inspection hold points.

l

-i.The department responsible for the work activity is responsible for l notifying the Code Inspector when the hold point is reached. Work is not I to proceed past a Code Inspector's inspection hold point until signed or l lwaivedbytheCodeInspector.

l -

l l

l10.5 DOCUMENTATION l c l l l10.5.1 l l 1

' Inspections and process monitoring activities are to be performed and the l

l results documented in accordance with approved procedures or l l instructions. Records are to: provide objective evidence that the

]- 1 I I l l l I 1-l

_] I l A I

I TOPICAL REPORT I

lREV. 6 l

l l P l lDATE 5/30/84 l i

l & 1 SECTION: 10.0 INSPECTION lPAGE 10-5 l

1 L l l l

, I I I l

4 .,

I I

I l

s I inspections and monitoring activities were performed in compliance with l

\ procedures, 4nstructions or drawings to verify design requirements; show p}

l compliance with acceptance criteria or identify the cause of rejected l k items;andidentifhtheappropriateinspectionpersonnelapprovingthe N -1 results.

s l t ,

.1 10.5.2 l

'l l

I I

l Records are to be maintained in accordance with plant procedures and l l'Section17ofthismanual. Inspection results on ASME code items are l available to the Code Inspector for his review. l 1

I I -

1 i 10.5.3 l I I I

I l The results of all inspection and monitoring activities are periodically l levaluatedperplantproceduresandtheresultsdocumentedtodetermine l

l whether the individual inspection programs demon:,trate that the plant can l p lbeoperatedsafelyandasdesigned.

l

,p I s l L'

l10.6NONCONFORMANCES l l '

, l I I g

t Noncomforming items,'found as a result of inspection and monitoring g ei activities are identified, segregated and dispositioned in accordance l l with plant procedur'Ys, and Section 15 of this manual. Rework, repair or l l replacement performed after completion of inspections are to require l l

g reinspection to the extent necessary to determine acceptability to I l established criteria. w -

I l l 1 I l .. I I , I I '

I l l l I l I I I I I I l

-l l l 1 O l l l l

, iJ l A l TOPICAL REPORT lREV. 6 l l p l lDATE 5/30/84 l l & 1 SECTION: 10.0 INSPECTION lPAGE 10-6 l l L l l l

.l I I I

5 I

I I

I i 11.0 TEST CONTROL l

q l i

l tj l l 11.1 SCOPE l

1 l

-l l

l A test program is to be established to assure that testing required to I demonstrate that an item will perform satisfactorily in service is l identified, documented, and performed in accordance with written test l

I procedures. These procedures are to incorporate or reference the I requirements and acceptance criteria contained in applicable codes, I standards and specifications and in the licensing documents. These l activities include testing during the operational phases of the plant and I those tests required as a result of modifications, repairs or l maintenance. These activities are also to comply with the applicable l

I lprovisionsofRegulatoryGuides1.33,Rev.2,unlessotherwisenotedin i Table 1, and with the applicable sections of the ASME Boiler and Pressure l lVesselCodeforASMEdesignateditems.

1 l

l l11.2 PROCEDURES l l

l l11.2.1 l l

l Written procedures / instructions are to be prepared to describe the l

l requirements for conduct of the testing activities. These procedures / I instructions are to contain or reference the information required in l Section 5 of this manual and in the applicable Regulatory Guides l lpertainingtoQualityAssurancerequirementsfortestingactivities.

l l

l l11.2.2 l L. I l

Test procedures / instructions and revisions thereto are to be subject to l the same review and approval process as outlined in Section 5 of this l manual.

l I

I I

I I

l 1 -

I l f") I l A i

I TOPICAL REPORT i

lREV. 6 I

1 l P l 10 ATE 5/30/84 l l & 1 SECTION: 11.0 TEST CONTROL lPAGE 11-1 l i I L l I l j i i i I

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g l 11.3 TEST CONTROLS '

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(3)

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I

'>jl 11.3.1 1

' 1

' ' l I .

' l l Tests relating to plant start up following a unit shut down or fuel l lloadingareiobeconductedperwrittenprocedures/instructionsinorder l

1 to evaluate plant performance as the start-up progresses. Initial l I

y I s'.' art-up' test programs are to be planned to permit safe fuel loading and

., s I

l l start-up, to increase power in safe increments and to perform major l testing at specified power plateaus.

l 3 I l

', 11.3.2.

1 l

I l.Surveillancetestsduringtheoperationalphaseoftheplantaretobe l^ conducted per written procedures / instructions to assure that failures or l

l

,- lsubstandardperformancesdonotremainundetectedandthattherequired l

l operability is maintained to ensure they will continue to operate, I lkeepinsparameterswithinnormalbounds,orwillacttoputtheplantin

. ,,m l a safe condition if they exceed normal bounds.

l I

() l l I

l i 11.3.2.1 l l

l l

l l Mandatory inplant surveillance tests and inspections required to assure l loperationwithinthelimitingconditionsofoperationareidentifiedin the-Technical Specifications applicable to each unit at the plant. To I

l ensure that the required tests are performed as scheduld within the I specified time interval, surveillance procedures are established and l

. maie'ained for mandatory surveillances identified in the Technical l Specifications. These procedures are to specify the component or system, l

.l type of surveillance activity, frequency of activity and the cognizant 1 -individual responsible for completion of the surveillance activity. l I

l l

l 1

1 I

l l

1 l

l O'd l l l l A l TOPICAL REPORT 6 lREV. l l P l l0 ATE 5/30/84 l l & l SECTI('N: 11.0 TEST CONTROL lPAGE 11-2 l l L l l l l l l l

v e

s l

l 1

I i 11.3.2.2 I

I

) l I

I l Inservice inspections reouired to meet the requirements of ASME Boiler i

landPressureVesselCode,SectionXI,aretobeidentifiedinthe i 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

procedures, inspection intervals and type of inspections. Plant l Engineering is to coordinate the implementation of the ISI plans at l

l appropriate scheduled outages. The plans are also to be made available l for review by the Code Inspector. l l

I I

I I

l 11.3.3 I

I I

I I

l Tests following plant modifications, repairs, maintenance, or significant i lchangesinoperatingprocedures,aretobeconductedtoconfirmthatthey l

l are not detrimental to the safe and efficient operation of the plant and l that the components or systems demonstrate satisfactory performance.

.q l l

l

'v'

- l11.3.4 l l

1 Requirements for the given test to be performed are to be identified in I the test procedures / instructions. Evidence is to be available to assure I the following minimum requirements are met:

l l

l l a) test equipment and measuring devices are calibrated in l accordance with the requirements of Section 12 of this manual l

l l and are functioning properly; I b) test personnel have been qualified to perform the test in 1 accordance with the requirements of Section 2 of this manual; l c) appropria'e witness and hold point notifications have been l

I provided; I

I I

l

.l l

l I 1 l

l L!O) l I A l

l TOPICAL REPORT l l lREV. 6 l l P l 10 ATE 5/30/84 l l & 1 SECTION: 11.0 TEST CONTROL lPAGE 11-3 l l L l l l l l I I

i l

i i

i I d) test perequisites completed; and I

[] e) when accuracy requirements for tests exceed the accuracy of l

l normally available process or measuring and test equipment, I l such additional accuracy requirements are to be specified I within those test procedures. I I

I I

I i 11.3.5 l

l i

I I

I Testing activities are to be subject to surveillance / inspections in l laccordancewithSection10ofthismanual. Testing as a result of l

l repair, modifications, replacement or scheduled inservice tests on ASME l lCodeitemsisalsosubjecttoinspectionbytheCodeInspector. The i assignment of inspection hold points is described in Section 10 of this l l manual. l l

1 11.3.6 l

l l

Test results are to be documented in accordance with the applicable

('] l procedures / instructions. Test documents are to contain at least the l l

lfollowing:

1 l

I (1) Identity of item tested.

l l (2) Date of test. l (3) As-found condition.

1 (4) Identification of individuals performing test.

l l

(5) Test results.

l l (6) Corrective actions performed if any. l l (7) As-left condition.

l l

1 I

g 11.3.7 I l

1 I

lTestresultsaretobeevaluatedbyresponsibleplantpersonnelperplant I procedures to assure that test objectives and inspection requirements l 1

1 I

I l

I o l I

V~ I A

I I I l l TOPICAL REPORT lREV. 6 I l p l lDATE 5/30/84 l l & 1 SECTION: 11.0 TEST CONTROL lPAGE 11-4 I I L I I l I i i I L

I I

l .

l l have been satisified. Non-conforming conditions, are to be identified l

-<- I I

u7 landcontrolledinaccordancewithSection15ofthismanual. l l-11.4 RECORDS l

-l i Test results are to provide objective evidence that the testing was I performed in compliance with approved procedures. Test records are to be I maintained and transmitted to the plant Document Control Center for l

l retention in accordance with Section 17 of this manual. I I

I l

l l 11.5 TEST STATUS I l

l l

' 1 I Inspection and test status is to be controlled in accordance with the l lprovisionsofSection14ofthismanual.

1 l

I I; I I

I I

I I

I I

I g i i V  ! I I

I I

I l l i I I

I l I I

I I

I I

I I

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l l

I I

I I

I I I I

l I- 1 I

I I I l

l l l l 1 I I 3 i i (V -l A I TOPICAL REPORT l

IREV. 6 i

j P

l l IDATE 5/30/84 I i & I SECTION: 11.0 TEST CONTROL IPAGE 11-5 I I L I I I 1 I I I

i i I

'l .

I i 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT l fm I I L I l I 12.1 SCOPE I l I I I

! 12.1.1 1 1 1 I i 1 A program is to be established to assure that devices used for I

' measurements, tests and calibrations are identified, controlled and ,I l 1 calibrated against reference standards to assure that accuracy is 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 I measuring and test equipment, unless otherwise noted in Table 1. 1 I I i l l 12.1.2 I I I I I I This section does not apply to rulers, tape measures, levels or other l lsuchdeviceswherenormalcommercialpracticesprovideadequateaccuracy.

n l l l12.2 RESPONSIBILITIES l l 1 12.2.1 I g

I l I

y The cognizant Superintendents / group Supervisors it the plant are I responsible for establishing and maintaining lists of measuring and test i equipment under their control that require periodic calibration and for j the calibration of this equipment, as assigned within plant procedures. I l l I I i 12.2.2 l l l L l I I The cognizant Supervisor is responsible for identifying measuring and l ltestequipmentrequiredfortheactivityandassuresthatthedevicesare l

.I used only by qualified personnel. I I I I I l l L I I i 'I I I I l f\ l A I TOPICAL REPORT IREV. 6 I I P l 10 ATE 5/30/84 l l & I SECTION: 12.0 CONTROL OF MEASURING IPAGE 12-1 I I L I AND TEST EQUIPMENT I l l~ l l I

o

'l I

l l

-l 12.2.3 l

.I D-,' l .

l 1

'l Plant personnel are to be responsible for utilizing only properly 1

- +

fidentifiedandcalibratedmeasuringandtestequipmentwhenperforming l

l ~ inspections and tests for record. I

'l I l

l l 12.2.4' l l

l l

l l .The Manager, Nuclear Quality Control and his staff are responsible for I monitoring test equipment control and use in order to verify compliance I with the program. 1 I

I I

l l' 12.3 GENERAL I I

l l

l

. I 12.3.1 l l

l l

• l

' I -Calibration procedures are to be established for each type of measuring l

,' and test equipment. These prv.edures are to conform to recognized codes l

[ l and standards and to local, state and federal regulations, and are to be I

', lreferencedonthecalibrationreports.

l

.I i

.l12.3.2 l

.I l Measuring and test equipment'is to be properly controlled, calibrated and

.I adjusted at specific intervals or prior to use to assure the necessary 1 accuracy of calibrated. equipment. Calibration intervals are to be based I upon the type of equipment, manufacturer's recommendations, stability and 1

- reliability characteristics, required accuracies, use and other

- 1. conditions affecting calibration. l

, I I

• I I l 12.3.3 I

! I

^

l- ' Reference standards used in the calibration of measuring and test i equipment are to be traceable to the National Bureau of Standards, or if g I I

-l I

(' l l- A i

l TOPICAL REPORT I

lREV. 6 l

l l ~P l lDATE 5/30/84 l 1 & 1 SECTION: 12.0 CONTROL OF MEASURING lPAGE 12-2 l ll L 1 AND TEST EQUIPMENT l l 1 I I l

e.

I I

I l

l nonexistent, to accepted industry or AP&L standards. Reference standards l

(~} are to have an accuracy at least four times that of the measuring and I test equipment. In any instance where the four times criteria is unable l

to be met, standards are to have an accuracy level, acceptable I calibration range, and precision equal to or better than those required l l for the ranges affected by the calibration. Accuracies less than four l times will be acceptable when warranted by statistical analysis or l llimitedbythestate-of-the-artasauthorizedbyresponsiblemanagement.

l l

Reference standards are to be maintained in an environment with l temperature, humidity and cleanliness controls compatible with l maintaining accuracy and operating characteristics of the standards.

l l

l l

l 12,3.4 l l

l I

i 1

l l When measuring and test equipment are found to be out of calibration, an l levaluationofthevalidityofpreviousinspectionortestresultsandthe l acceptability of items previously inspected or tested is to be made and l

l ldocumentedbywrittenreportinaccordancewithplantprocedures. If any i

o i piece of measuring and test equipment is consistently found to be out of I

's I I calibration, it is to be repaired or replaced.

g

,I I

I l12.3.5 l l

1

- R3 calibration per plant procedures is to be performed when the accuracy l of either installed or calibrated equipment is questionable.

l 1

I I

l I

i 12.4 EQUIPMENT IDENTIFICATION I I

I I

I i 12.4.1 I I

I I

I l The measuring and test equipment list is to contain sufficient l information to uniquely identify each iten listed and is to include as a l minimum, calibration intervals, tolerances and storage locations. The l I

l l

l

~l I

()

'V I

l l l

! A l TOPICAL REPLRT 6 lREV. l l P l lDATE 5/30/84 l l & l SECTION: 12.0 CONTROL OF MEASURING IPAGE 12-3 l l L l AND TEST EQUIPMENT l l l l I I

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

1 I

I I

_l list is also to it'entify the group responsible for the control of each l I

N item. I

-$(.] .

12.4.2 l

l l

lEachitemlistedonthemeasuringandtestequipmentlististobe l tagged, labeled or otherwise identified per plant procedures in such a l

l lmannerthatclearlyidentifiestheequipmentanditscalibrationstatus '

I and provides traceability to the calibration records. I 1.

I I

I i 12.4.3 I

I I

I .

l l Measuring and test equipment found to oe out of calibration is to be 1 l tagged'andsegregatedfromacceptableequipmentinaccordancewithplant l procedures until repaired and recalibrated. l I

I I

I .

l l 12.5 RECORDS I

l l

1 I

o l Calibration documentation is to be maintained to verify calibration I status, condition, accuracy and out of tolerance trends of the equipment.

l l

1 1

I I

I I

I I

I I

I I

I l

l I

I I

I I

I I

I I

l l

I l

1 l

l I

I

~l I

.I 1

l-1 I

I l-1 I

O k' I A

I I I

I I l TOPICAL REPORT IREV. 6 l l P l lDATE 5/30/84 l l & I SECTION: 12.0 CONTROL OF MEASURING IPAGE 12-4 1 4

i L i AND TEST EQUIPMENT l l 1 I I i

e I

I I

I 13.0 HANDLING STORAGE AND SHIPPING l m i

' I

) l U I l 13.1 SCOPE I

I I

I I

l Activities for the handling, storage and shipping, including cleaning, l packaging and preservation of materials and equipment are to be performed I in accordance with established instructions, procedures or drawings, to i prevent damage, deterioration or loss of the item. Activities are to 1- comply with the provisions of Regulatory Guide 1.38 rev. 2 unless l otherwise noted in Table 1.

1 l

l l13.2 GENERAL l l

l l13.2.1 ,I I

I Instructions for preservation are to be provided for items subject to I deterioration or damage through exposure to air, moisture, or other l environments during fabrication, processing, assembly, and interim

<, storage periods.

l I Items are to be cleaned, preserved and packaged as I

~l required to preclude deterioration and prevent damage. When maintenance I of specific internal or external environments are necessary, they are to l be included in special packaging instructions and maintenance procedures.

I '

I

.13.2.2 I g

i I

lProcurementdocumentsassurethatanyspecialcleaning, preserving, l; handling, packaging or shipping requirements for purchased material or i equipment are taken into account. I y

i

.I I 13.2.3 l

l 1

fForcritical, sensitive,perishableorhighvaluearticles, I recommendations for their handling, storage, packaging, shipping and I

.preservation are to be requested from the supplier per the procurement i I I I v-) . , ,

' b# l A I TOPICAL REPORT lREV. 6 l

l P i IDATE 5/30/84 i I & 1 SECTION: 13.0 HANbLING, STORAGE AND lPAGE 13-1 l I -L- I SHIPP!NG l l l l I I

d i I l .

l l . documents and furnished to the plant prior to or upon receipt of the item l at the plant.

l I I 13.3 S' HIPPING CONTROLS I

l l 113.3.1-l

'l I

. Shipping requirements are to be specified in the procurement documents.

.l Suppliers compliance to these requirements are to include controls to I

assure.that items are complete and assembled as required; items have been l preserved and packaged in accordance with the procurement documents; I items h' ave been marked and identified in accordans with specifications

_ l. and procurement documents; items have been loadec for shipment in sucn a l

~

• manner as to prevent damage; and required documentation is complete and l fu'rnished in accordance with the procurement documents. l l l

'l l l 13.3.2- l

.I' I

. .. l' I l 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 i documents.' The Health Physics Supervisor is responsible for assuring l lthatradioactivesourcesand'instrumentscontainingradioactivesources l l are' shipped, stored and handled per these requirements and plant l

_ procedures. The Nuclear Support Supervisor is responsible for assuring l- that special nuclear material (SNM), as defined.in plant procedures, are l

. shipped, stored and handled per these requirements and plant procedures.

l

.l l 13.4 RECEIVING l: l v l l 13.'4.1 l

l l Materials and equipment are to be received at the plant per plant l

1 pracedures and subjacted to a receipt inspection in accordance with i Section 7 of this manual. As part of the inspection activity, received l

'l I h l A l

I TOPICAL REPORT l

IREV. 6 i

,l- P. l lDATE 5/30/84 l

_l & l SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-2 l 1 L__ l SHIPPING l l l- 1 I I

i l

l I

I l materials and equipment are to be inspected for damage, deterioration, I

(]. lcleanlinessandproperidentificationandmarkingsperplantprocedures i for receipt inspection.

I I

I I

I l 13.4.2 l l

l l

l l Results of the receiving inspection and disposition of the material or l lequipmentaretobedocumentedonreceivinginspectionrecords.

I Nonconforming items are to be handled in accordance with plant procedures I and Section 15 of this manual.

I I

l13.5STORAGECONTROLS l 1

l l13.5.1 l l l lMaterialsandequipmentwhichhavecompletedthereceivingprocessareto l

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

O V

l l

l I

13.5.2 I l

l I

lStoragecontrolproceduresaretobeestablishedwhichinclude,asa l ' minimum, provisions for the following: controlled access and usage of I lthestoragearea;cleanlinessandgoodhousekeepingcontrols; fire I protection; protection from environmental hazards; segregation of I hazardous materials; and control of those items which have a specified 1 . shelf life. l l l I I I

i 13.5.3 I I I l I l l Only items which have completed the receiving process are to be placed in I il a controlled storage area. Records of the items' location are to be l provided-by the Materials Management Supervisor (see paragraph 13.3.2 for l l control of radioactive sources and SNM) to identify those items currently l

l l i

7s I l 'A I TOPICAL REPORT REV. 6 I l P l lDATE 5/30/84 l I & l SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-3 l l L I SHIPPING I l i I I I

I l

1 I

l .in storage and to facilitate inspection and maintenance planning. l Issuance of iteras from storage for installation or use are to be

' ')

~^

l documented and controlled in accordance with plant procedures. l

-l I l l l 13.5.4 I I

l

.I I I Items identified as. requiring maintenance during storage are to be l maintained in accordance with a documented maintenance program.

I I

13.5.5 l l Storage areas are to be monitored by individuals responsible for the l storage areas so that the integrity and security of stored items is l effectively maintained. Inspections and examinations under the control

-l 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 l

l and their containers are being maintained. Periodic audits under the l control of the Quality Assurance Manager are also performed to assure

,, I compliance to storage requirements. l U/ I I

I .

l l 13.6 HANDLING CONTROLS l l

l l l l 13.6.1 l 1 I I I l Special handling requirem'nts are to be specified in the procurement l ldocumentsandplantprocedurestoprotectthequalityofitems I susceptable to handling damage. Special tools and equipment are to be l provided to handle these items and are to be controlled and maintained I per written procedure to assure safe and adequate handling. I I l l l l 13.6.2 l l l

l. I I Sp cial handling tools and equipment are to be inspected and tested at I specific times in accordance with written procedures to verify that the i l l I I Il V

l I I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l & 1 SECTION: 13.0 HANDLING, STORAGE AND lPAGE 13-4 l l L i SHIPPING l l l l l 1 i -

I I

I I

I handling tools and equipment are adequately maintained. Inspection and I

(~Y .- -test status of these handling tools and equipment are to be controlled in M l accordance with the applicable sections of this manual. I I

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l l l l l A- l TOPICAL REPORT IREV. 6- I l' P' l lDATE 2,5/30/84 I l -& 1 SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-5 I I L I SHIPPING l 1 l l I i

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I i 14.0 INSPECTION, TEST AND OPERATING STATUS I

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l 14.1 SCOPE I

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l The removal from service, inprocess status and return to service of I l equipment,componentsandsystemsformaintenance, modifications, repair, 1

test or inspection is to be controlled per established plant procedures. l These controls are to assure that plant personnel are aware of equipment, l structure or system conditions and to prevert their inadvertent use l

l lunlessclearedbyoperationpersonnel.

1 l

l l14.1.2 l l

1

' Maintenance activities are to be performed in accordance with an l

l established maintenance program to assure that equipment, systems and l lstructuresaremaintainedinaconditionwhichallowsthemtoperform rN l their intended function.

b I I

i 1

I i 14.2 EQUIPMENT CONTROL l l

l I

I l 14.2.1 I I

i l

l l Prior to removal of equipment, components or systems from service for I maintenance, modification, repair, test or inspection activities, i

l j

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 l affecting plant safety. I I

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l A l TOPICAL REPORT 6 lREV. l p

I I IDATE 5/30/84 l l & 1 SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-1 l l L I OPERATING STATUS l l l l I 1 5

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l 14.2.2 l

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l The status of equipment, components and systems during these activities I g is to be identified in accordance with plant procedures / instructions, I which contain, as a minimum, the following: I l

i l

l l 1) methods for control of equipment to maintain personnel and I reactor safety and to avoid unauthorized operation of equipment 1 or systems.

I I

I I

i 1 2) the use of markings or other suitable means to indicate the I status of activities being performed upon individual items.

l l

Suitable means are to include identification numbers which are I traceable to records or the status of these activities.

l l

l I

g 3) provisions for the identification of items which have I satisfactorily passed the required activities. In cases where l l required documentary evidence is not available, the associated eq I l

equipment or system is to be considered nonconforming and I

/

l ' handled in accordance with Section 15 of this manual.

l 1

I

4) , provisions for independent verifications to casure that I

necessary measures (locking or tagging) to secure and identify I equipment or systems in a controlled status, have been I implemented correctly. I l

l l

l

-l_ 14.2.3 I

l l l

l 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 foreign material is removed before the system is reclosed. I I

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'd I I l A I TOPICAL REPORT IREV. 6 I l P I lDATE 5/30/84 l l & 1 SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-2 l l- L l ,

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i 14.2.4 i

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l During maintenance or modification activities, certain portions of I

}I systems, as identified in plant procedures, may be subject to potential l 1 contamination with foreign materials. To prevent such contamination, I control measures, including measures for access control, are to be l established. Immediately prior to closure, an inspection is to be l

I conducted to assure cleanness and the result of such inspection is to be I_ documented. l I

I I

I l .14.2.5 l l

l 1

I I If temporary modifications (such as temporary bypass lines, electrical 1 g jumpers, lifted electrical leads and temporary trip point ' settings) are 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 l

l the Shift Supervisor, identifying the current status of such temporary 1 modifications. Temporary modifications are to be verified by individuals

/~ 3 l independent of the group performing the activity and documented to assure I the required actions are taken to return the equipment or system to its l

l original operating configuration and status. I I

I I

I i 14.2.6 I l

I I I l When equipment or a system is properly identified as being ready to be 1 1

returned to service, the appropriate Shift Supervisor is notified and I I initiates ' the proper operation procedures. Testing of the equipment or l lsystemforfunctionalacceptabilityistobeinaccordancewith l Section 11 of this manual and documented to verify current status of the I item.

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l A l 10PICAL REPORT lREV. 6 i l P I lDATE 5/30/84 l l & l SECTION: 14.0 INSPECTION, TFST AND IPAGE 14-3 l l L l OPERAllNG STA105 l l l 1 I I

l l

l l

l 14.2.7 l n l U l l

l l Equipment, structures and systems found to be nonconforming as a result l of an activity are to be handled in accordance with plant procedures and l Section 15 of this manual. l l

l l

l l 14.3 MAINTENANCE CONTROL l l

l l

1 l 14.3.1 l l

l l

l l 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

l through the Maintenance Manager to assure that the safety of the plant is l not compromised nor the Technical Specifications violated. Maintenance l activities are to be performed per plant procedures and instructions and l I

l conducted in a manner to assure quality at least equivalent to that l specified in the design documents, material specifications and inspection l requirements. As experience is gained in operation of the plant, routine l

. (] - I maintenance may be altered to improve equipment performance and l procedures for repair of equipment are to be improved as directed by the l Maintenance Manager.

l I

I I

I I

l 14.3.2. l I

I I

I l A preventive maintenance program,-including procedures and instructions l for systems, structures and components, is to be established and l

l maintained under the Maintenance Manager which prescribes the frequency l and type of mainteaance to be performed in order to preclude equipment l malfunctions. The program is to be implemented by qualified maintenance l personnel in accordance with written procedures and instructions which l specify the work activities, acceptance requirements and the control l

l

. measures to assure adequate quality. When equipment malfunctions occur, l

l the cause is to be promptly determined, evaluated and recorded per plant l procedures and Section 16 of this manual.

1 l

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• ' 1 l l l l l A I TOPICAL REPORT 6 lREV. l P

l l lDATE 5/30/84 l l & l SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-4 l

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I 14.4 OVERALL PLANT STATUS l 1

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l 14.4.1  !

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I The Shift Supervisor is provided sufficient knowledge of the overall l l plant'statusofequipment,structuresandsystemstocontroloperationof I the plant in a safe manner. The Shift Operators are to maintain a ready l lreferenceofplantsystems,equipmentandcomponentsalignments,aswell l as a status board summary of their conditions. l I

I I

I I

i 14.4.2 I I

I I

I l -The turnover of duties to personnel on succeeding shifts is conducted in 1 accordance with approved plant procedures. These procedures include I

documented turnover action appropriate to the duty station acknowledging I

..the status of the nuclear power plant, its structures, systems and I components (including design changes / modifications which may affect the I

'.g performance of their duties) and transfer of authority.

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l l lDATE 5/30/84 l l & 1 SECTION: 14.0 INSPECTION, TEST AND IPAGE 14-5 l 1 L I OPERATING STATUS l l l- 1 I I

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l 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l

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l 15.1 SCOPE I

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l Nonconforming items are to include materials, parts, components, I l processes,documentsandasapplicable, services (includingcomputer l l ' codes) that do not conform to applicable regulations, codes, standards, I specifications, drawings or licensing documents. Nonconforming items are l

l to be controlled in accordance with approved procedures to prevent their l inadvertant use or installation. These procedures are to contain I measures to assure the prompt identification and notification, I l documentation, segregation,technicalreview,dispositionand I l verification of a nonconforming itea. l I

I I

I l 15.2 GENERAL i

l l

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i 15.2.1 1 I

I I

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/'~') l It is the responsibility of each individual to identify a nonconforming I condition, whether related to a product, process or documentation, and to l report it to their cognizant supervisor for review and concurrence. The I initiator.is to document the nonconformance on a Nonconformance Report I (NCR) unless the nonconformance is determined to be a technical I specification violation and/or reportable to the NRC. See paragraph 15.3 1 for reportable nonconformances.

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l 15.2.2 l 1

I l- I l Nonconforming items are to be tagged with a hold tag, or otherwise l identified per plant procedures, to prevent inadvertant use or 1- installation of the item. Nonconforming items are to be segregated from I acceptable items unless they are currently installed or_ their size, I weight, configuration, etc., makes it impractical to move to a segregated i

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l l lDATE 5/30/84 l l & SECTION: 15.0 NONCONFORMING MATERIAL, 4

IPAGE 15-1 l l L PARTS AND COMPONENTS I l l I I I E

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I l . area. Hold tags are to remain on the item until the disposition is  !

complete per plant procedures.

I I

l15.2.3 l l

l Nonconformance Reports are to identify the group responsible for l l dispositioning the nonconformance. The assigned individual within the l responsible group.is to evaluate the nonconformance and confer, as l appropriate, with interfacing groups to determine its cause and l recommended disposition. The disposition, which may be reject, rework, \,

l repair or use-as-is, and the corrective action taken to prevent l I

recurrence is to be documented on the NCR. g l

I l15.2.4 l I

l The' initiator of the NCR and his department head are to review the i disposition for acceptance prior to implementing corrective action. If l they cannot agree with the assigned individual on the disposition, the l d l plant General Manager is to decide. For a repair or use-as-is l disposition, a cognizant engineer knowledgeable in the design l requireneents for the af fected item is also to review the NCR for l concurrence of the disposition. Written justification for the design l l change, repair or deviation that has been accepted is to be documented to I denote the as-built condition and is to be made a part of the NCR.

I I

l15.2.5 l I

1 I

I The acceptability of rework or repair of materials, parts, components, g g

l l systems and structures are to be verified by reinspecting the item as loriginallyinspectedorbyamethodwhichisatleastequaltothe I original inspection method. The rework and repair inspection records are l to be documented and become part of the permanent records for the item.

l l Upon completion of the corrective action, tte Manager, Nuclear Quality 1

l l l

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tj l I l l I TOPICAL REPORT lREV. 6 l l l A l l P l lDATE 5/30/84 l

I & 1 SECTION

15.0 NONCONFORMING MATERIAL, lPAGE 15-2 l l l L l PARTS AND COMPONENTS l I l

l l

I I i .

l l Control is to verify completion of corrective actions in accordance with I

( lplantproceduresandifacceptable,closetheNCR.

l l l 15.2.6 l

l l lForASMECode,SectionIII, Division 1 materials,partsandcomponents I dispositioned repair or use-as-is, the NCR is to be subject to review and l lconcurrencebytheCodeInspector. I I l l15.3REPORTABLENONCONFORMANCES l l l l15.3.1 l l 1 l_NonconformingitemsorconditionswhicharereportablepertheTechnical l

l Specifications to the NRC are to be documented by the initiator and l

' forwarded to the Special Projects Manager so the appropriate report, per  !

g I plant procedures, can be prepared. l I I

-I l 7" l 15.3.2 I k.1' 1 I I I l Upon disposition of the report by the responsible group the PSC reviews 1 the report for concurrence and possible assignment of additional I corrective actions and forwards the report to the plant General Manager l lforfinalapproval. l l l 15.3.3 l

l 1 The LRGO Licensing section is to be responsible for transmitting approved l

l reports to the NRC within the time period specified in the Technical 1

-Specifications and Licensing procedures.

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l TOPICAL REPORT l

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l P l lDATE 5/30/84 l l & l SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-3 l l L l PARTS AND COMPONENTS l l 1 1 I l

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l l 15.4 SUPPLIER NONCONFORMANCES l fy i l l- 15.4.1 I

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-l l l- Procurement documents are to contain requirements for the i

, .l -vendor / contractor to identify nonconforming conditions to AP&L which

, 1 -violate a technical or material requirement of the procurement document i

.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 acceptance. The vendor / contractor is to document such nonconformances on I their applicable nonconformance report which is to be included in the 1 ljfinaldocumentationpackagesubmittedtoAPAL,inaccordancewiththe l

l procurement documents. I i l 1- I l :15.4.2 I I I I ..

I I .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 i I's ' accepted by AP&L.

l' l l15.5 RECORDS l l' I

-l-15.5.1- l l l l Upon completion of. disposition and verification activities, the completed I g 1 NCR's, reports, and related documents generated to ensure proper l

- disposition and resolution of the nonconformance are to be forwarded to l

I and maintained by the Document Control Center. l l l l l l l r 'l I

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l. I 11 l l l Ln l-1 -A 1

l TOPICAL. REPORT I

IREV. 6 l

l l P. l lDATE 5/30/84 l l & l SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-4 l

I L I PARTS AND COMPONENTS l l l l l l l

I I I I

-l 15.5.2 I

.fi -l- l t,'1 I I I The Manager, Nuclear Quality Control is to maintain and issue a monthly I report to the plant General Manager, identifying the current status of l

l all open NCR's for management review. I i l 1 I I I l l l l 1 I I I l- l l l I I I I I I I I I I l- l 1 l l l 1 l l 1 l I h I l

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-l A l TOPICAL REPORT lREV. 6 l 1 P l IDATE- 5/30/84 l

-ll &- l SECTION: 15.0 NONCONFORMING MATERIAL, lPAGE 15-5 l l L l PARTS AND COMPONENTS I l l l l l i- _.__ _._ _ _ -_

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l I 16.0 CORRECTIVE ACTION l

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l

-l -16.1 SCOPE I I I l l l- A corrective actions system is to be established to assure that I

- conditions adverse to plant safety, such as failure, malfunctions, l

l deficiencies, deviations, defective material and equipment, abnormal l l.occurrencesandnonconformancesarepromptlyidentifiedandcorrected.

l l In the case of significant conditions adverse to safety, this system is l 1

ltoassurethatthecauseoftheconditionisdeterminedandcorrective l action taken documented and reported to appropriate levels of management I

~ for independent review.

l l l

'16.2 GENERAL l

l l 16.2.1 l

l l When deviations, deficiencies, malfunctions or other abnormal occurrences l

p l or conditions are encountered, they are to be reported to responsible l L '\ /l l authorities for review and disposition in accordance with Section 15 of l

g I this manual. I I I I I i 16.2.2 I I I I i l Cognizant supervisors are to review discrepancies discovered during the l lcourseofstationoperations,andinthecaseofsignificantconditions l l adverse to safety, initiate action to identify their cause and take I necessary corrective action to prevent their recurrence. Corrective l

l action measures to resolve the discrepancies and to prevent their I I

recurrence are to be documented in accordance with Section 15 of this g I manual. I I l l l l l l l l l l l l 1 bV .I I I I l A l TOPICAL REPORT lREV. 6 l l P l IDATE 5/30/84 l l & 1 SECTION: 16.0 CORRECTIVE ACTION IPAGE 16-1 l l L l l l l I I I

a I l 1 l l 16.2.3 l

, ; I I y) l l l The appropriate plant department head is to review recorded l l nor.conformances and may specify the need for additional corrective l

l action. The plant's General Manager is to review the monthly status l lreportsconcerning"open"nonconformancereportsandtakesappropriate I g

I 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 technical support groups at the plant and/or LRGO to evaluate the l

nonconformance for final disposition.

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l l l l l' I i 16.2.4 1 l 1

-l l l Adverse quality or safety conditions discovered by QA or QC personnel I during their document review, inspection, audit or surveillance 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 l

O 'I and QC procedures. l V l l l l l 16.2.4.1 l l I I l l The responsible organization to which the corrective action document is l addressed is to evaluate the adverse condition and document the action l

l 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. l I l l 1

-l 16.2.4.2 l 1 I I l l -The response is to be evaluated by the initiating organization (QA or QC) l to determine the adequacy and completeness of the corrective action I l l l l l 1 I I I (m).

l l A I

l TOPICAL REPORT I

lREV. 6 l

l l P l lDATE 5/30/84 l l & l SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-2 l l L I l l l l l 1

I i

. l l l commitments. If the response is acceptable, the initiating organization I is to perform follow-up action to verify implementation of the corrective

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I action commitments, document their findings and when acceptable, close I out the corrective action document.

I I l16.2.4.3 l l 1 If the initiating and responding organizations cannot agree upon a l

l resolution, it is to be referred to the next level of management for l 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 I resolution of QC and QA initiated corrective action documents, I respectively. l l 1 1 I l 16.2.5 l l l l l l When vendors furnish products or services that do not conform to the 1 lrequirementsoftheapplicablepurchasecontractand,intheopinionof J] I the Manager, Nuclear Quality Control, the vendor warrants consideration I for reappraisal, the Manager, Nuclear Quality Control is to submit a l

l vendor reappraisal request to the Manager, Quality Assurance for I determination of action to be taken. Results of the reappraisal, I together with a request for specific corrective actions, are to be I

' transmitted to the vendor. If the vendor does not improve his quality I assurance system and products as requested, the Manager, Quality I Assurance is to remove the vendor from the Qualified Vendor List (QVL) in I accordance with departmental procedures. I I I I I l l I I I I I I l l I I I I I I l l l 1

,o l I I A l TOPICAL REPORT IREV. 6 l P l lDATE 5/30/84 l l & 1 SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-3 I I L l l l l l l l

i i i l l I 16.3 SIGNIFICANT CONDITIONS l LO l l 16.3.1 l

l l l l l l Significant conditions are to include, as a minimum, the following: l l l l l l (1) Conditions that have a direct adverse affect on the safety of I the plant or personnel.

l l (2) Conditions that have caused the uncontrolled release of I radioactive materials (liquid, solid, gaseous or air l

l particulate) to the environs. l (3) Trends indicated by nonconformances which could lead to unsafe l l l plant operations. 1 (4) Any condition the plant's General Manager considers to be of l

l major consequent.9 1 I l l l l 16.3.2 l l l l l l When significant conditions adverse to safety are discovered, the g

responsible supervisor and management personnel are to evaluate the g I condition and determine if it is a repc^ table occurrence. Reportable l loccurrencesaretobehandledasdescribedinSection15ofthismanual l l and are to be submitted to the PSC and SRC for review. l l l l l 1 16.4 VERIFICATION l l 1

-l l l Verification by surveillance or audit of the effective implementation of l I

corrective actions is to be periodically performed and documented by ,

I Quality Assurance personnel. Audits are to be performed in accordance l with Section 18 of this manual.

l l l l l l l l l l l l l l l l l O i l A i

l TOPICAL REPORT i

IREV. 6 i

I l P i lDATE 5/30/84 l l & 1 SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-4 l l L l l 1 l l l l

3 1

l --

i l 17.0 QUALITY ASSURANCE RECORDS l l 1 I O =

i i l 17.1 SCOPE l 3 .

I I I I 9 l 17.1.1 l 1 I -

1 I I Documentation covering design, construction, procurement, fabrication, l inspection, maintenance, nonconformance and corrective action, test and -

l audit activities is to be filed and stored to provide objective evidence l 3^

I I of quality-related activities and to assure the ability to reconstruct -

y  ;

Control of records is to be in accordance with l significant events. l Regulatory Guide 1.88, Rev. 2 (10/76) unless otherwise noted in Table 1.

l l 1 j 17.1.2 I I i-lQualityassurancerecordsaretoincludeoperatinglogs,resultsof Z l

l reviews, inspections, tests, audits, material analyses; monitoring of l 2 =

=

l work performance; qualification of personnel, procedures, and equipment; l

, p:

I historical drawings, specifications, engineering reports, calculations, l procurement documents, calibration procedures and reports, nonconformance -

I reports, corrective action reports, correspondence and related records l 9 -

pertinent to quality as defined in plant procedures for records l management. I $ -

I I 1 I l 17.2 RESPONSIBILITY l =

l l 1 I l 17.2.1 1 1 I I I E l l The Plant Administrative Manager is respor.sible for the establishment, 1

=

implementation and maintenance of the records management program to be i l used throughout the operational life of the plant and for ensuring that l ,,

documentation retention requirements comply with applicable technical _

l specifications, codes and regulations. l 1 =

I 1 1 3

l 1 l l --

1 O i i i i 4 l A l TOPICAL REPORT lREV. 6 l ==

l P l !DATE 5/30/84 1 -

l & l SECTION: 17.0 QUALITY ASSURANCE RECORDS lPAGE 17-1 1 I L i I I e i I i 1 5 a

., 4

i i 1

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.. I 17.2.2 I m f s, l l

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I I I AP&L personnel, other than plant staff, and outside firms that perform I work on the plant in the areas of design, procurement, maintenance, I modification, testing, quality assurance and special nuclear materials I are to provide documentation / certification records to the plant for I I subsequent storage and retention by the Plant Administrative Manager. I I I I I l 17.2.3 l l l l .

l l Quality Assurance personnel are to periodically audit quality-relat d 1

-lrecordsandrecordsfilingandstorageprocedurestoassurethatthe l l records management program is being properly implemented. Audits are to I be performed as outlined in Section 18 of this manual.

l l I l17.3DOCUMENTATIONRETENTION I I Lifetime Quality Assurance Records l17.3.1 l m , ,

l17.3.1.1 l

l l lLifetimerecordsaredefinedasthosewhichmeetoneormoreofthe i following criteria: I l I I I l (1) Those which would be of significant value in demonstrating l capability for safe operation.

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

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

l l (4) Those which provide required baseline data for i. service l

inspection.

l I I I I I l l l n l I

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I I I I l A I TOPICAL REPORT IREV. 6 l l P- 1 IDATE 5/30/84 l l & 1 SECTION: 17.0 QUALITY ASS'JRANCE RECORDS IPAGE 17-2 I I L i I l l l l l

l- l 1 I i 17.3.1.2 1

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I l Lifetime quality-related records are to be maintained for the life of t.he l particular item while it is installed in the plant or stored for fotore l use as prescribed in applicable plant piecedures for document retention 1 an idisposition.

-l l l l

.17.3.2 Non-Permanent Quality Assurance Records l l I

l~17.3.2.I  ;

-l' l l'Nonpermanentrecords'aredefinedasthosewhichmeetallofthe l following criteria: I l- 1 I .

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

-l .(2) Those of no significant value in maintaining, reworking, l l- repairing, replacing or modifying the item.

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

l l (4) Those which do not provide baseline data for inservice l Inspection.

l

-l l

[17.3.2.2 l l l g 'Non permanent records are to provide evidence that an activity was l l- performed in accordance with applicable requirements and be ret.ained for i specified periods as .11rected by the applicable plant procedures for i document retention and disposition. I i l l l l 17.3.3 I I I I I l Categories of permanent and non permanent records to be maintained ano i their appropriate retention periods are described in plan + procedures.

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l. 'A l TOPICAL 3EPORT IFEV. 6 l l P l lDATE 5/30/84 i

'l & 1 SECTION: 11.0 QUALITY ASSURANCE RECORDS lPAGE 17-3 I l' L- 1 I I l l- I i

I I I I l 17.3.4 l nV- l 1

I l

l .Tne Manager, Nuclear Quality Control is responsible for receiving, I inspecting.and authenticating such documents as directed by plant l procedures for turnover of quality assurance documents from suppliers to I AP&L. When approved for receipt by Quality Control, such records are to l

l be transmitted to the Plant Administrative Manager for filing and I

! storage.

I I

-l.17.4STOP. AGE l 1 l l'17.4.1 l

l. l lPermanentrecordsaretobemicrofilmedandstoredwithinacontrolled l l area at the nuclear power plant per plant procedures. A duplicate sct of ,I microfilm is also made and stored at a remote location.

l l l 17.4.1.1 l

7 l l i .)/ -

- l For storage of film and other special processed records, humidity and l 1 . temperature controls are to be provided to maintain an environment as I recommended by the manufacturer and plant procedures.

~

l l l l-17.4.1.2 l

'l

~~

I

.A-list is to be prepared by the Plant Administrative Manager designating l . those personnel who have access to the storage files. I l- 1 I I i 17.4.2 i 1  !

-l l l Plant storage systems are to provide for the accurate retrieval of l

-l l l

information without undue delay and be suf ficient to control and accotml. g I for records removed from the storage facility. I l- 1 1 I l l l- I "M) I . .l. I I

-1. A: 1- TOPICAL REPORT IREV. 6 I

.I P -l IDATE 5/30/84 I l & 1 SECTION: 17.0-QUALITY ASSURANCE RECORDS IPAGE 17-4 l l L l l l

! I I I

l l

l l l .

l l 17.5 RECORDS INDEXING AND RECEIPT CONTROL l

..n i 1 Li I I l 17.5.1~ l l I I I

-- l Indexing methods and systems for quality-related records are delineated l linplantproceduresforplantrecordsmanagement. l l 1

- 17.5.2 l

l l Records submitted for storage in either 1 .*etime or temporary files are l

l to be subject to the following requirements for receipt control: l l l l l l (1) Establishment of a records check list designating the required l quality-related records.

l l (2) Establishment of a system designating criteria for document I inspection to assure that records are accurately completed, l

l legible and received in good condition. l (3)- A file system to indicate which quality related documents have l

(] l been received. I K./ 1 I l I i 17.5.2.1 1 I I l- 1 I Implementation of receipt control requirements for storage is the l

. responsibility of the Plant Administrative Manager.

l l 1 17.6 FINAL DISPOSITION I- l lTheplantAdministrativeManagerisresponsiulefordisposalof l 1 quality-related records in accordance with. plant procedures for document I retention and disposition, which permits periodical purging of records I retained past their required retention date. I l 1 l I

! I l- I l' I I I

, l l

,3 t

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I TOPICAL REPORT I

lREV. 6 1

I l l l P l IDATE 5/30/84 l l & I SECTION: 17.0 QUALITY ASSURANCE RECORDS IPAGE 17-5 I l L I i 1 l l I I

l l l'. I

, ~l 18.0 AUDITS I

/7 l l l 18.1 SCOPE l 1 I i

.l l l 18.1.1 l l l 1 1 I

'l -A comprehensive system of planned and periodic audits are to be provided l i

.to assure and verify compliance with all aspects of the administrative l controls and quality assurance program. Audits are to be planned and l

. performed in accordance with' written procedures, plans and checklists and l

-l are to conform to the applicable portions of Regulatory Guides 1.144, l

- rev. 1 (9/80) and 1.146, rev. 0 (8/80), unless otherwise noted in Table l

l 1. l l l 4

1. .

l l- 18.1.2 l l 1

-l .

=l The audit program is to include provisions to determine the compliance l with and effectiveness of the quality assurance program in controlling l

structuras, systems, components and activities in accordance with the j

-V ;ll rules set forth in the codes, standards and regulations identified in the l l . Introduction of this manual. l

-l l 3;- l 1 -18.2 AUDIT PERSONNEL l

. I l

-l- l l 18.2.1 1 I I

-l l l The Quality Assurance Manager is assigned auditing responsibility within l

-this quality' program and is responsible-for the selection and assignment

/ l of auditors. Auditors are to be independent of any direct responsibility l

. for performance of the. activity which is to be audited and are not to  !

g l = report to a management representative who has direct responsibility for l the activity being audited.

l l 1

-  : l' l

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-l TOPICAL REPORT i

lREV. 6 l

l P. l lDATE 5/30/84 l l & l SECTION: 18.0 AUDITS lPAGE- 18-1 l

.l L l l l 1- 1 I I

l- 1 I I I 18.2.2 I g- l (s~ ~ ~) I l Auditors assigned auditing responsibilities are to have experience and l

i I

. training commensuate with the scope, complexity and/or special nature of l

l the activities to be audited. When audit assignments are made, I considerations are given to special abilities, specialized technical j l training, prior pertinent expertise, personal characteristics, education I and capability. If no one within the QA0 meets these prerequisites I completely, technical specialists are to be used to assist in the 1 lauditingoftheactivity. Technical specialists are to meet the I requirements of paragraph 18.2.1 of this section. I I I I I i 18.2.3 I

.I l l I I Audit personnel are provided appropriate training to assure their I competence for performing the required audits. Proficiency of audit l

l personnel is maintained by one or more of the following methods: 1 I I I I

(~N . l (1) Regular, active participation in the audit process. I

'l (2) Review and study of codes, standards, procedures and l

l instructions. I I

(3) Participation in training or orientation programs.

l l l l18.3AUDITSCHEDULE l l l l 1 18.3.1  ;

I I lAuditsaretobeperformedonaplannedandperiodicbasisinaccordance l

.I with an audit schedule. Audit schedules are to be pr: pared at the I beginning of each year by the QA0 and approved by the Quality Assurance l

l Manager and SRC. l I I I I I I I i l l l l g I l l A I TOPICAL REPORT REV. 6 l l P l 10 ATE 5/30/84 I I & 1 SECTION: 18.0 AUDITS lPAGE 18-2 I I L I I I I I I I

I. l l l l- 18.3.2 l ym, I l q.) l l l Audit scheoules assure that as a minimum, the following areas are l audited,underthecognizanceoftheSRC,attheindicatedfrequencies l

l within AP&L: l I I l >

l l (1) The conformance of facility operation to provisions contain,ed l within the Technical Specifications and applicable license l

l conditions at least once per 12 months. I (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 the entire facility staff at least once per 12 months. l l (3) ,The results of all actions taken to correct deficiencies l

l occurring in facility equipment, structure, systems or methods I of operation that affect nuclear safety at least once per six 1 months. (A portion of this activity is performed as a part of I each internal quality audit.)

l l (N' l (4) The Facility Emergency Plan and implementing procedures at I

' ~'

least once per 12 months.

1 , (5) The Facility Security Plan and implementing procedures at least l once per 12 months.

l l l '(6) Any other area of facility operation considered appropriate by l the SRC or the Nuclear Operations Vice President.

l' l (7) The Facility Fire Protection Program and implementing l procedures at least once per 24 months.

l 1 l l18.3.3 l

l l Audits of vendor / contractor activities are to be scheduled as identified l

l in Section 7, paragraph 7.3.3 of this manual. These audits are to l I, evaluate and verify their quality assurance program, procedures and l l l

I I l l l 1 fy' i I

! J l I I I

-l TOPICAL REPORT 6 l A lREV. l l P l lDATE 5/30/84 l l & 1 SECTION: 18.0 AUDITS lPAGE 18-3 l l L l l l l l 1 i e _

s l l l l l . activities, to assure compliance with the procurement documents, and to I f' .

verify they periodically review and audit their suppliers quality l l assurance program. I I I I l 1 18.3.4 I I l l I l Periodic reviews of the audit programs are to be performed by the SRC or l their appointed management representative at least semi-annually to l

l assure that audits are being accomplished in accordance with the I requirements of the technical specifications, this manual and Regulatory l

l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1. I I I I I

1. 18.3.5 I l l 1 l l- Regularly scheduled audits may be supplemented, as required, to cover I unforeseen events or changed requ.Jements.

l l l18.4AUDITIMPLCMENTATION r~T l l

! I l

18.4.1 1

I I

. Audit plans and checklists are to be prepared by the auditor and approved l

l by the Quality Assurance Manager prior to performing the audit. l Checklists'aretobeusedduringtheaudittoassurethatall l l l requirements of the activities audited are addressed during the audit and I that those procedures and instructions issued to control the audited  ;

I activity are adequate. l l l l l l 18.4.2 I I I I I l Upon completion of an audit, a written report is to be prepared which l lincludesatleastthefollowingitems: l l l l l l l l 1 h~' I

-l A

. I TOPICAL REPORT I

lREV. 6 I

l I

l P. I IDATE 5/30/84 I I & I SECTION: 18.0 AUDITS IPAGE 18-4 l l L I I l i I I I

I I I I l (1) Description of audit scope and date. l I

/

v j

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

l (3) A summary of audit results. l (4)' Details of nonconformances or programmatic deficiencies.

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

l 1 l l18.4.3 I l lDeficienciesidentifiedasaresultofaninternalauditaretobe l l recorded on an Audit Finding Report (AFR) by the auditor and issued to ' l

.the department head responsible for the area audited for corrective I action. The department head a r 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. l Appropriate follow-up including re-audits by the assigned audit grau,n is l

l conducted in the deficient creas to verify proper and timely l implementation of corrective action commitments. Follow-up actions are q to be documented on the AFR.

l l l Y' I I I l l 18.4.4 l l l l l l Audit reports pertaining to plant acthities are to be independently 1 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 plant. Audit reports pertaining to LRGO activities are to be l

l independently reviewed by the SRC. In addition to these reviews, the l audit reports are to be distributed, as a minimum, to the Nuclear l

'l Operations Vice President,' Quality Assurance Manager and appropriate l llevelsofmanagementhavingresponsibilityintheareaauditedtoassure

-l their awareness of the findings. l l l l 1 l l I I l l l 1

-l

! ,l

l l I I

I I A l TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l & l SECTION: 18.0 AUDITS lPAGE 18-5 l l L l l l l l 1 l

m-4 l l l l l '18.4.5 1 l- l

-'4. j _: l l

' ~ ' '

'l. Audit results and findings related to external audits conducted by QA i

.I jersonnel are to be recorded and distributed to the Quality Assurance l

, ll Manager and a designated representative of the audited organization. l

- Deficiencies are to be recorded on an AFR, and the audited organization l

l' is to describe actions taken to correct deficiencies and prevent I recurrence on the AFR. Corrective actions are to be verified by QA

~l personnel and documented on the AFR. l l I I l

.- I 18.5 RECORDS l 1 I l .

l l Written internal audit reports, including checklists, AFR's and related l

_ldocumentationsupportingthefollow-upactivitiesaretobeforwardedto I the Administrative Manager for storage in accordance with Section 17 of l t- this manual. External audit reports are to be maintained / stored in the l

I applicable vendor / contractor. file maintained by the Quality Assurance l l' Manager.

l f '

l l 18.6 NUCLEAR FUEL AUDITS l

1 l lArkansasPower&LightCompanydelegatestoMiddleSouthServices,Inc.,

l- a' wholly owned subsidiary of Middle South Utilities, Inc., the l

-y l responsibility for performing those quality assurance functions necessary l l to assure that its nuclear fuel is designed and fabricated in accordance l lwithregulatoryrequirementsandacceptedcodes,standardsand

. I specifications. The MSS Quality Assurance section monitors the design l and fabrication of the fuel through a program of audits of the fuel l

- l- fabricator, including both design review audits and fuel fabrication l

-audits. MSS a130 conducts audits of component suppliers as deemed 1 necessary by the Manager, Qualtiy Assurance (MSS), to ensure the quality l l~ofthefuel. Formal audit reports are issued by MSS to document their l l

l. I l- 1 l l

-l l

{- . l I A l

l TOPICAL REPORT I

IREV. 6 I

l

.l P l lDATE 5/30/84 l l & l SECTION: 18.0 AUDITS lPAGE 18-6 l l L l l l l l l l

l-1 I I I audit activities and to identify nonconformances or other items requiring I

( action by the fuel-fabricator. Resolution of nonconformances or other items requiring action ~is verified by MSS and documented in follow-up I i reports. The AP&L Quality Assurance Manager is on distribution for all I audit and follow-up reports.

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e 1 I l- l l TABLE 1 l m; I l j i l l ARKANSAS POWER & LIGHT'S EXCEPTIONS / INTERPRETATIONS l OF REGULATORY GUIDES AND ANSI STANDARDS APPLICABLE

' l l TO THIS QUALITY ASSURANCE PROGRAM l l l 1 l

.1 l Regulatory Guide / Exceptions /

g ANSI Standard Requirement Interpretation l g

General Certain Regulatory The AP&L commitment refers l l

.l Guides invoke or to the Regulatory Guides and l imply Regulatory ANSI Standards, specifically l

.I Guides and standards identified in this TOPICAL. l in addition to the Additional Regulatory Guides, l

l standard each ANSI Standards, Guides and l primarily endorses. similiar documents implied l

l Certain ANSI Stan- or referenced in those l dards invoke or specifically identified in l

(] l imply additional this TOPICAL are not part of l standards. this commitment.

l l l General Certain ANSI Our commitment to those l Standards and/or standards applies only to l Regulatory Guides those systems, structures, l

l extend the scope of and components whose satis- l applicability to factory performance is l

l include systems, required to prevent postu- l structures, and lated accidents that could l components whose cause undue risk to the l satisfactory perfor- health and safety of the

.l i mance is required public; or to mitigate l for a plant to the consequences of such l

l operate reliably on accidents. Reliable operation l "high-value of the plant may depend upon l l l l

l l l l A l TOPICAL REPORT lREV. 6 l 1 P l lDATE 5/30/8a l l & l SECTION: TABLE 1 lPAGE T1-1 l l L l l l l l 1 l

I I

l- l l articles." other systems, structures and l components which are not  !

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u. I l covered by this commitment. I I I

.I l l ANSI N18.7 Where changes-are Consistent with the require- l (Section 5.2.13.1) made to procure- ments of ANSI N45.2.11, para-l

.I ments, they shall graph 7.2, minor changes to l l be subject to the (procurement) documents, such l

.1 same degree of as, inconsequential editorial I control as was used corrections, or changes to l

l in the preparation commercial terms and conditions I of the original  !

may not require that the re-y

~l~ documents. vised (procurement) document l receive the same review and I approval as the original l

.. documents.

l l lANSIN45.2.1 Fresh water criteria The turbidity requirement on l

q~ (Section 3.2) l for chlorides, and fresh water is deleted and l Jackson Turbidity the chloride requirement is f

l Units. revised to read "less than l 250 ppm." The turbidity l

l requirement for demineralized I water is deleted.

l l l I

g ANSI N45.2.2 " Preliminary visual Inspection after unloading is I g

l Subsection 5.2.1 inspection or exami- sufficient to determine the l l nation shall be per- condition of many items. In l

l formed prior to special instances, pre-unload- l unloading..." ing examination is performed.

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1 l Ai l TOPICAL REPORT lREV. 6 I

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-l & l SECTION: TABLE 1 lPAGE T1-2 l l L' l l l l l I I

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l l 1

l l ANSI N45.2.2 The (receiving) Receiving inspection is per- l I

(l

(> l Section 5.2.2 inspections shall formed in a manner and in an I l

.l be performed in an environment which does not l area equivalent to endanger the requisite quality I l

l the level of storage of an item. The receiving l requirement for the inspection area environmental l item. controls may be less stringent l than storage environmental l

l requirements for that item, l however, the short time spent l in the less stringent receiv- l ing inspection area shall be l of such duration that will l not adversely affect the item l being received. l l l l l

l. ANSI N45.2.2 ..."The 'Special The "Special Inspection" l Paragraph 5.2.3 Inspection' pro- procedure shall be readily G l cedure, complete available to inspection l with documentation personnel and may be attached l

l instructions shall to the item or container. l be attached to the l

l item or con- l tainer..."

l I ANSI N45.2.2~ The use or storage People working in storage l Subsection 6.2.4 of food, dririks, and areas have a right of access l salt dispensers in to water dispensers per OSHA l

l any storage area is requirements. Additionally, l prohibited. due to the location and l layout of the building, per- l sonnel may temporarily store l lunches in the work place. l l l l l l l 0' l l A i

l TOPICAL REPORT i

lREV. 6 l

l l P l lDATE 5/30/84 l l & l SECTION: TABLE 1 lPAGE T1-3 l l L l l l l l l l

V l l I l l This area is policed for l

(~'i , I sanitation. I U

ANSI N45.2.2 " Container markings Containers are adequately l Appendix (A-3) shall appear on a marked for storage, identifi- l lA.3.9(1)Second minimum of two sides cation, and retrieval.

l l Group of the container, Multiple marking requirements l l preferably on one are imposed, where necessary.

I side and one end." l l l l l l ANSI N45.2.2 " Container markings Container markings are of a l l Appendix (A-3) shall be...no less size which permits easy l

l A.3.9 (4) Second than 3/4" high recognition. l l Group container permit-l ting." l I I I l l ANSI N45.2.2 " Container marking The information required l l Appendix (A-3) shall include the in container inrking is A l A.3.9 following informa- evaluated on a case-by- l tion..." base basis. Marking is l

l adequate in each case. I l l 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 l Section A 3.5.1 (1) brightly colored." I l l I I 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

l Section A 3.5.1 (5) or other means as securing devices or measures I necessary to prevent which will not be detrimental l

l accidental removal. to the item will be used. l l l l l l l l l l l l l O'~ l A l

l TOPICAL REPORT I

IREV. G l l P l lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-4 l l L l l l l l I I

,i '

I I

I .

l

l. ANSI N45.2.2 Marking of items The last paragraph of Section l

^'

Appendix (A-3) not within a con- A.3.9 could be interpreted as

.l Section A 3.9 tainer. prohibiting any direct marking l on bare austenitic stainless

~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 austenitic stainless steels l

l and nickel base alloys subject l l to the following limitations:

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 bt used l l q l on surfaces of corrosion l v/ resistant alioys. Low sulfur, l l l low fluorine and/or low 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 (a) Total inorganic and l

l organic halogen content l shall not exceed one (1) l l percent. l (b) The sulfur content shall l not exceed one (1) l percent.

l l l g) t.

l I I I

l I

l A l TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-5 l l L l l l l l l l

s l '.

I i

1. l

, 'l ANSI N45.2.2 Inert Gc. tilankets There may be cases involving l C large or complex shaped items for which an inert or dry air I l purge is provided, rather

.l I

than a static gas blanket, in l order to provide adequate l protection due to difficulty l of providing a leak proof l barrier. In these cases, a l positive pressure purge flow l

l may be utilized as an alter- l nate to a leak proof barrier.

I I ANSI N45.2.2 Limits halogen and Engineering may allow the use l Appendix A, sulphur content of of tapes containing greater l

-A.3.5.2,(1),(a) tape. amounts of halogans after I

appropriate evaluation, l I

I however, the quantities shall l l

'(o!.

l- not be such that harmful concentrations could be l

l leached or relased by break- l I

down of the compounds under l expected environmental l l

conditions.

i I

General Alternative equivalent

-lRegulatoryGuide l l 1.39 ANSI N45.2.3 requirements may be utilized l to cover those situations not included in the subject l l

Standard; for example, situa-l tions in which shoe covers l I

l.

I I

l l

l l

l' I l

I r l l

I I l l TOPICAL REPORT lREV. 6 l l A l l- p l lDATE 5/30/84 l l '& l SECTION: TABLE 1 lPAGE T1-6 l I I l t i i l

'l I

q ~

.I I I i l and/or coveralls are required l

} but material accountability l

l is not. In addition, zones l might be combined into the l next more restrictive l category in order to reduce l total number of zones. l l l l 1

-l ANSI N45.2.3 Identifies various When this standard is applied, l housekeeping re- its requirements are imple-l- l l quirements, includ- mented in those areas affected l ing cleanliness, by wor'. activities associated

.l 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 l . the progress of l construction.

n; l

l l lRegulatoryGuide Pre-Construction / This section required verifi-l l 1.30/ ANSI N45.2.4 Installation Verifi- cation that items are in l cation satisfactory condition for l l l Regulatory Guide installation and have not l 1.116/ ANSI N45.2.8 suffered since initial l

l receipt inspection. Upon l receipt, items are inspected l and stored in an environment 1 which will not adversely l

l affect the item. Documented l routine inspections and l periodic audits of the storage I I I l l l 1 l- l i I l l n l i i l l A l TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-7 l l L l l l l l 1 1

i OO b

+k

• IMAGE EVALUATION ////p 4)y g + 1ss11AaGercur.3) gy kgf gfs

~

g/ 'k///,4,} *f w?g

+  %

l.0 l# M Ha

i M BH -

m in I

l,l bb l.8 1.25 1.4 1.6 4 150mm >

4 6" >

+j+ L*% b

, /f4% A 4%

• v o 7// u

<>++#+

1

l i

~

1 I I- areas assure that stored items l are maintained in satisfactory

_l conditions. Documentation l

-_v- -

of pre-const ruction veri fica-l tion in addition to documen- l tation of initial receipt

, :l inspection, periodic storage l inspections, and audits of I storage is not required. I I I i 4 l

l -ANSI N45.2.4 Identifies various These tests will be performed l tests to be as determined by " gineering

-I performed. or Nuclear Operations based l I

.; upon the significance of l' change or modif 4ation. l I 1

~l l l R.G. 1.58 In addition... the AP&L takes exception to this I

-(Section C.6) candidate should be requirement. AP&L's education l

J/3'-

1 e l -a high school and experience requirements l

' ' ' .g g

graduate or have are in accordance with ANSI l earned the General N45.2.6-1978. l Education Development l l l (GED) equivalent of I a high school l l

[ diploma. 1 I I l' -

l l .R.G. 1.74/' Definitions of Based upon the guidance of i Certificate of ANSI N45.2.13, 10.2,_the lANSIN45.2.10

'l- Conformance and definitions of these two l Certificate of terms will be exchanged.

l'

• Compliance." l I l

'l- 1 I I l I I I I I q .l l ij l i I I

! 'A .1 TOPICAL REPORT IREV. I

l. P l lDATE 9/30/84 l l & 1 SECfl0N: TABLE 1 lPAGE TI-8 l l L l l 1 1 I I l

a A

^

l l I I l R.G. 1.94/ Section 1.4 defines This requirement for rein- I I I ANSI N45.2.5 inprocess tests and

[v'E l

forcing steel will be l

.1 (Sectior,1.4) states: interpreted to permit taking I the rebar test specimen at i ... samples of these the fabrication shop, prior I tests must be taken to start of fabrication of l from the lot or the rebar from the heat or I batch of ciaterials fraction thereof represented l

l supplied to the site by the test specimen. For l l for use." these tests performed at the I fabrication shop, certifica- l tion shall be available to l ,

l l provide objective evidence l that the test specimens l

I represent the material sup- l plied for use at the site.

l I l Requirement:

lANSIN45.2.5 ' l A '

l (Section 4.5) Section 4.5, Con- l crete Placement, l

I references American l Concrete Institute l l

l (ACI) standards l ACI-305-72, l l l " Recommended Prac- l tice for Hot Weather l

1- Concreting" and ACI- l 306-66, " Recommended l

l Practice for Cold l Weather Concreting."

l l l l l l l l l l l l l 4 l l p l l L 'v I l A I

I TOPICAL REPORT I

IREV. 6 I

l l' P I lDATE 5/30/84 l l & 1 SECTION: TABLE 1 IPAGE TI-9 l l L l l l l l l l t

l 1 1 I I I Interpretation: I I

_( In order to clarify l use of these ACI I standards, we will I apply the following I requirements:

l l PLACING TEMPERATURES OF CONCRETE:

l l l l A. During hot weather concreting:

l l l l Placing temperatures of concrete will be l

l' limited to the following: l ,

I I l l l 1) Concrete members less than 3 feet in least I dimension will not exceed 90 F.

l l l l 2) Concrete members from 3 feet to 6 feet in l

Q_

v l least dimension will not exceed 70*F. I 1 l l l I 3) Concrete members more than 6 feet in least l l dimension will have placing temperature as l

l near 50*F as can be obtained by use of ice l l' as necessary up to 100 percent of adding l

l mixing water; and by shading aggregate and I sprinkling the coarse aggregate the day it l

l is to be used. Care will be taken so that l I

l no unmelted ice remains in the concrete at ,

I the end of the mixing period. I I I i l I I I I I I I l I l l I I I

m. I I t) : 1 A

I I l I I TOPICAL REPORT IREV. 6 l l P i lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-10 l l L i l I l- I l I

I l I l l B. During cold weather concreting: l O

~)

I l

I l

l In heating the water and aggregate, live steam l to heat the fine and coarse aggregate shall not be used. The permissible range for concrete l

l l temperature shall be as follows:

I I

1) Sections less than 3 feet in least l dimensions: 55 to 75*F. l I I I i l 2) Mass concrete 3 feet or more in least l dimension: 45 to 65*F.

I I The mixing water and aggregate will be -

l l purchased as required. The materials will be l free of ice, snow and frozen lumps before they l

l enter the mixer. l l l 1 I O, l ANSI N45.2.5 Requirement: l (Section 4.8) l l Section 4.8, "In process Test on Concrete and - l Reinforcing Steel" states, " Samples for in process l

l test of concrete shall be taken at the sampling

• l point in accordance with ASTM C172. This point may l

l be at the truck mixer discharge if the last piece l of conveying equipment is a chute, bucket, l conveying system, or similar equipment. Pump l concrete must be sampled from the pump line l l l discharge." l I I I I I I l l l l l l l l 1 l l 1 o l i i l l A I TOPICAL REPORT lREV. 6 l l P l lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-11 1 I L l l l l_ l l I

e i l 1 l l Interpretation: l

('i l 1

~~

- C/ - l l l For performance of correlation tests, the l requirements of ANSI N45.2.5-1974 shall be I I followed. I I l l I l ANSI N45.2.5 Requirement: l l(Section4.8) l l Section 4.8, "In process Tests on Concrete and I Reinforcing Steel" contains Table B entitled, i " Required In process Tests." The following l l modifications to this tabla will be applied:

I I Interpretation:

l l l l REINFORCING STEEL l l l I In process testing or reinforcing steel will l l

(') l include the mechanical properties of yield l strength, tensile strength and percent elongation l l I on full size specimens for each bar size for each l l 50 tons or fraction thereof from each mill heat.

l l Bend tests are performed during material l qualification testing only, except as noted below l l 1 for bar sizes #14 through #18. I I I I I l Table A, " Required Qualification Tests" as applied l to reinforcing steel will include bend tests as l

I required by ASTM A615 and summarized below: l l l 1 1 1 l i I I I I I I l i I I l 6 I l b l l A l

l TOPICAL REPORT l

IREV. 6 l

l l P l IDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-12 I I L f I I

-l 6 I I p

1 I I I I l a) For bar sizes #3 through #11, one full size l I

/~ ') specimen from largest bar size rolled from each  !

v l l l mill heat, unless material from one heat l 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 l l l l b) For bar sizes #14 through #18, Supplementary l Requirements S1 of ASTM A615 will be applied.

l I One full size specimen for each bar size for l each mill heat. If supplementary requirements l- are not followed for mill tests, they will be l applied as in process tests.

l l l 1 The above interpretation is consistent with  !

g l Regulatory Guide 1.15, " Testing Reinforcing bars l for Category I Concrete Structures," Revision 1, l

f'y l December 1972. l V l l l l l In process test specimens may be selected at the l rebar fabrication shop, prior to start of l fabrication of the rebar from the heat or fraction l thereof represented by the test specimen.

l 1 I Acceptance criteria for any failed test l

l (qualifications as well as in process) may be the l same as that for tensile tests specified in

l. Subarticle CC-2331.2 of ASME Section is', Div. 2 l

Code (1975). This states that if a test specimen l

l fails to meet the specified strength requirements, l l- l I I l l I I I I I l l I (X) l I I I l A l TOPICAL REPORT lREV. 6 I I P I lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-13 l l L l I l l l I l

n L

1 I I l l two (2) additional specimens from the same heat and I

~'l I' of the same bar size would be tested, and if either I v I I I of the two additional specimens fails to meet the I specified strength requirements, the material l

l represented by the tests would be rejected for the i specified use. Alternative use of rejected I material under strict control may be subject to l l evaluation by the Project Engineer.

l l l Requirement:

lANSIN45.2.5 1 (Section 4.9) l l Section 4.9, Mechanical (Cadweld) Splice Testing l

l states in paragraph 4.9.4 " Separate test cycles I shall be established for mechanical splices in l

l horizontal, vertical and diagonal bars, for each l l bar size and for each splicing crew..."

l l l Interpretation:

l l

/7 l l The terms " horizontal, vertical and diagonal bars" l

l will be interpreted to apply respectively to the l following types of splice positions:

l l l l

a. Hozizontal, including 10 to horizontal l l l b. Vertical, including 10* to vertical l

c. 45* angle, including 10 to 80* angle l l l l The words " splicing crew" will be interpreted to I refer to all members on the project that are I activitely engaged in preparing and assembling l

1 - cadweld mechanical splices at the final splice l location. Separate test cycles will be established l l 1 I for each bar size and each splice position. l l l l l l l i I n)

(.~

I l I l l A l TOPICAL REPORT IREV. 6 l l P I IDATE 5/30/84 l l & 1 SECTION: TARLE 1 IPAGE T1-14 l l L l l l l l l l L. _

.I l l

l l ANSI N45.2.12 An individual audit For those routine audits l (O

v I

l (Para 0raph 4.2.1) plan describing conducted during operations, I l

l the audit to be a written procedure (s) l performed shall be covering each audit may be l developed and utilized. Procedure (s) will l documented by the identify the audit scope, l auditing organiza- a requirement that individual l tion. This p'lan checklists be utilized list-l l shall identify the ing requirements which are to l audit scope, the be audited and notification l

l requirements, the of the audited group. l l activities to be l

l audited, organiza- l tions to be notified, l the applicable l documents, the l

l schedule, and written l procedures or check-l lists.

(]J C

l l

l l

l l l ANSI N45.2.13 The certificate The person attesting to a l (Section 10.2.d) should be attested certificate shall be an l

l to by a person who authorized and responsible l is responsible for employee of the supplier, l

l this quality assur- and shall be identified by l ance function and the Supplier.

l l l whose function and l position are

l described in the l Purchaser's/

fl Supplier's quality l

l assurance program.

l l l l 1 l I I I b"' l l A l

l TOPICAL REPORT l

lREV. 6 1

l l .P l l0 ATE 5/30/84 l l & l SECTION: TABLE 1 lPAGE T1-15 l l L l l l l l l 1

I I I I I 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

-I couraged, it should the originator's supervisor, l not be construed if the supervisor is the only l

l that such verifi- individual in the organization I cation constitutes competent to perform the l

l the required inde- verification. I pendent design l l l verification, ..." l

-l l I I I I l l l l l

l' l I I l l l l l l 1

-p v

I 1,

I I

I I l' I I I I I I I I .

I I I I I I I l I I I I I I I I I I I I I I I l l l I I I I I I I I I em i I

(') l I A l

l TOPICAL REPORT l

IREV. 6 l

l l P I lDATE 5/30/84 l l & 1 SECTION: TABLE 1 lPAGE T1-16 l l L I I I l l l l k

J

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i i l I l l TABLE 3 l cs l l sj- I QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION l l MANUALS LIST l l l 1 l l 1. Quality Assurance Program for Operations l l l l l l The Quality Assurance Program'for Operations establishes the l

.l policies and guidelines of the AP&L quality assurance program for l

l its operating nuclear plants. This program is to be followed by all l l organizations involved in safety-related work applicable to l ..

I operating nuclear plants. I I I I i l 2. Energy Supply Procedures Manual l I I I l l The Energy Supply Department - Little Rock General Of fice (LRGO) l l employes a system of procedures designated as Energy Supply l

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

(] l licensing, training and procurement activities in support of the l

~#

operating plant.

l l l l The ESP's and revision thereto are prepared by Energy Supply LRGO l l l personnel, reviewed and approved by the Quality Assurance Manager, I the Energy Supply (LRGO) Procedures Task Force and the responsible l l I department head. I I I I I l 3. Quality Assurance Procedures Manual i 1

I l l The Quality Assurance Organization employes a system of procedures l designated as Quality Assurance Procedures (QAP) in order to assure l l l proper implementation of the program. The QAP's and revisions l l l

'l I I I I I I I I I o I l V I A

I TOPICAL REPORT I

6 i

l I IREV. l l P l lDATE 5/30/84 l I & 1 SECTION: TABLE 3 IPAGE T3-1 l l L I I I I I I l

i l l I l theritto are prepared by the Quality Assurance Organization, reviewed l I I and approved by the Quality Assurance Manager and approved by the

v. l I l Energy Supply Services Director and the Sr. Vice President, Energy I Supply l l l l

~.

4 Quality Assurance Administrative Procedures Manual l

l l The Quality Assurance Organization also employes a system of l l 1 procedures designated as Quality Assurance Administrative Procedures l (QAA). These procedures provide technical and administrative l l l instructions to the Quality Assurance staff to aid in implementing l their responsibilities within the quality program.

l l l l l5. Overall Plant Adminstrative Procedures Manual l

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

^\

l control on site activities. Overall Plant Administrative Procedures I and changes thereto are prepared by the plant staff, reviewed by the l l l Plant Safety Committee and approved by the plant's General Manager. l The procedures and revisions are also raviewed by the Manager, l l l Nuclear Quality Control to assure that Quality Assurance Program l commitments are met.

l l l 1 l6. Departmental Plant Administrative Procedures l I Each department (operations, maintenance, engineering and technical l l l support, training, quality control, etc.) at the plant has developed I procedures in support of the Overall Plant Aoministrative Procedures l

l and this Quality Assurance Program. These procedures provide l technical and administrative instructions to the various departments l l l l l l l l l l

()

e l I

' l I I I I A I TOPICAL REPORT IREV. 6 l l P l 10 ATE 5/30/84 I l & l SECTION: TABLE 3 lPAGE T3-2 I I L I I I I I I l

l l I l I to aid in implementing their responsibilities within the quality l l program. Each department head is responsible to perform a QA review

'] ~

l l of their procedures to assure conformance with the Quality Assurance l I

l Program. These procedures are reviewed by the Plant Safety g l Committee and approved by the Plant's General Manager. I I l I I I l l I I I I I I I I I I I I I I l l I I I I l I I I I I I I I I l 1 I n i I L _J l l I I I I I I I I I I I I I I l i I I I I I I I I I l I 'l i I

. 1 I 1' I 1 I 1 1 1 I 4

I I l l I I U

o l l l I I

I l A l TOPICAL REPORT IREV. 6 I I P l IDATE 5/30/84 l l .& 1 SECTION: TA8LE 3 lPAGE T3-3 l l L l l I l I I I

-