0CAN078504, Rev 7 to QA Manual Operations
| ML20129J581 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/31/1985 |
| From: | Enos J ARKANSAS POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 0CAN078504, CAN78504, NUDOCS 8507230149 | |
| Download: ML20129J581 (200) | |
Text
{{#Wiki_filter:e -_ [ I, I I, I l- 1 I I I l QUALITY ASSURANCE MANUAL OPERATIONS l l l l REVISION 7 APPROVALS l If I I I I: 1 I l l . I I: 1 1: 1 1: I l' I I I I I I I I I l I I,i I I I l l l l l l 1 l l Attached are the revised pages to the subject manual for your review and l l approval. Please sign and date in the applicable space below to signify O. l your approval. Upon approval, these revisions are to be issued to the NRC l l l per the provisions of 10CFR50.54(a) and to all manual holders. l APPROVED: 5/23/g' l UALTTP ASSURANCE MANAGER' ] APPROVED: I -/ O /7% a /s l l
~ DIRECTOR, ENERGY SUPPLY ERV. l l APPROVED: N- l l SR. VICE PRESIDENT, g PLY l l 1 1 I I I l l I I I I I I l 8507230149 850531 I
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33;; z - _ l - l I RECORD OF REVISIONS l l l
-l REVISION l l NUpWER DESCRIPTION DATE l s l l Initial Issue ~
l 'O 6/11/74 l 1 - 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 l 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 5 Incorporate Organizational Changes 10/10/80 l l and responses to subsequent NRC l l Questions. Incorporate Regulatory l Guides and retype document in its O l l entirety in standardized format.
l l l 1 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 l l safe operation of AP&L nuclear plants. l l Manual has been reformated and retyped l l in its entirety. l l l l 7 Changes given below are identified 05/31/85 l l on the pages by a bar in the left l l margin, placed next to the affected l l area. l l 1 I I l l l 1 l 1 l l l 1 l l l I nV l l A I l TOPICAL REPORT i lREV. 7 l l , l P l lDATE 5/31/85 l
.l & l SECTION: RECORD OF REVISIONS lPAGE 1 l l L. I l l l l l l
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l l l 7 (cont.) Corrected by errata (includes misspelled l l words) on the following pages: l I . l l A-1 2-5 10-6 T1-9 l 1 l A-2 3-2 11-5 T1-13 l l 1-10 3-3 13-2 T3-1 l l 1-12 3-4 13-4 T3-2 l l 1-18 4-2 15-2 T3-3 l l 1-19 5-2 3 l l 1-20 5-3 15-5 l l 1-22 5-4 15-4 l l 1-23 6-2 16-1 l l 7-2 T1-6 l l 9-1 l l l l Page C-7: revised definition l l Page C-8: revised definition l i Page 1-9: revised paragraph 1.4.2(1) l l Page 1-10: revised paragraph 1.4.2.1 l l Page 1-11:added paragraph 1.4.2.1.1 l l : paragraph 1.4.2.2 redesignated l l 1.4.2.1.2 l l :added paragraph 1.4.2.1.3 l l : paragraph 1.4.2.3 redesignated l l 1.4.2.2 and revised l
\ l Page 1-12: paragraph 1.4.2.3.1 redesig- l-I nated'1.4.2.2.1 l l Page 1-13:added 7) to paragraph 1.5.1.3 l l Page 1-14 & 15: revised paragraph 1.5.3 l l to delete Planning / Scheduling Supervisor l l Page 1-21:added paragraph 1.5.8 l l Pages 1-1 to 1-23: paragraph locations l l changed l l Page 2-2: paragraph 2.2.2 redesignated l l 2.2.3 and revised [
l Page 2-2: paragraph 2.2.3 redesignated l l 2.2.4 l l Page 2-2: paragraph 2.2.4 redesignated l l 2.2.5 l l Page 2-2: new paragraph 2.2.2 added l l l l Page2-3: revised paragraph 2.2.5(2) l l Page 2-7 and 2-8: revised paragraph 2.6.4 l l Pages 2-3 to 2-9: paragraph locations l
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I I l RECORD OF REVISIONS l l l l REVISION l p l NUMBER DESCRIPTION DATE l V I I l 7 (cont.) Page 7-3: revised paragraphs 7.2.3 and l l 7.2.4 l l Pages 7-3 to 7-7: paragraph locations l
.' I changes l l Page 15-1: revised paragraph 15.2.1 l l Page 18-3: revised paragraph 18.3.2 l l Pages 18-3 to 18-6: paragraph locations l l changes l l Page F-1: revised Figure 1 l l Page F-2: revised Figure 2 l l Page F-3: revised Figure 3 l l Page F-5: revised Figure 5 l l Page F-6: revised Figure 6 l l Page T2-1: revised titles l l Page AA-1 to AA-3: new Appendix A added l l Page AB-1 to AB-8: new Appendix B added l l l l l l l l l l l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I I i l l I I I I I i i l l I I I I I I I
- I I 4 I I l I I I (v] I A l TOPICAL REPORT IREV. 7 l l l P I IDATE 5/31/85 I
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+, , . , I l l l l TABLE OF CONTENTS l l l l Section Subject Tab Pg Rev. l 1 I l l l APPROVAL COVERSHEET l RECORD OF REVISIONS l l TABLE OF CONTENTS TC-1 7 l TC-2 7 l l l TC-3 7 l TC-4 7 l l l TC-5 7 l TC-6 7 l l TC-7 7 l TC-8 7 l l POLICY STATEMENT A-1 7 l A-2 7 l l l INTRODUCTION B-1 6 l B-2 6 l l l B-3 6 l O ' I B-4 e i l l B-5 6 l TERMS AND DEFINITIONS C-1 6 l l C-2 6 l C-3 6 l l C-4 6 l C-5 6 l l C-6 6 l C-7 7 l l C-8 7 l C-9 6 l l C-10 6 l l l l 1 l l l 1 1 I I I I I A l TOPICAL REPORT lREV. 7 l l P l lDATE 05/31/85 l l & 1 SECTION: TABLE OF CONTENTS lPAGE TC-1 l l L l l l l l l l
-l l I l l 1. 0 ORGANIZATION 1 1-1 7 l I
1-2 7 I O l 1-3 7 i l 1-4 7 l
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l 1-7 7 l l 1-8 7 l l 1-9 7 l l 1-10 7 l l 1-11 7 l 1-12 l 7 l l 1-13 7 l
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1 1-15 7 l 1-16 7 l l l 1-17 7 l 1-18 7 l l l 1-19 7 l O l 1-20 7 l l 1-21 7 l 1-22 7 l l l 1-23 7 l 2.0 QUALITY ASSURANCE PROGRAM 2 2-1 6 l l . 2-2 7 l 2-3 7 l 2-4 7 l 2-5 7 l l l 2-6 7 l 2-7 7 l l l 2-8 7 l 2-9 7 l l l l l l l l l l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 05/31/85 l l & I SECTION: TABLE OF CONTENTS lPAGE .TC-2 l l L l l l l l l l
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! l l 3.0 DESIGN CONTROL 3 3-1 6 I I
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l 3-5 6 l 4.0 PROCUREMENT C0CUMENT 4 4-1 l 6 l l CONTROL 4-2 7 l 4-3 6 5.0 INSTRUCTIONS, PROCEDURES l l 5 5-1 6 l AND DRAWINGS 5-2 l 7 l l 5-3 7 l l 5-4 7 6.0 l l DOCUMENT CONTROL 6 6-1 6 l l 6-2 7 l l 6-3 6 l 7.0 CONTROL OF PURCHASED 7-1 l 7 6 l l MATERIAL, EQUIPMENT AND 7-2 7 l SERVICES 7-3 l 7 l l 7-4 7 () I 1 7-5 7 I I l l 7-6 7 l q l 7-7 7 8.0 l l IDENTIFICATION AND CONTROL 8 8-1 6 l OF MATERIALS, PARTS AND 8-2 l 6 l l COMP 0NENTS 8-3 6 l 9.0 CONTROL OF SPECIAL 9 9-1 l 7 l l PROCESSES 9-2 6 l 9-3 6 l l l l l l 1 1 I I I 4 l l l l l l l l l l 1 I j l A l TOPICAL REPORT lREV. 7 l l P l lDATE 05/31/85 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-3 l l L l l l l 1 I I
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.l -l l 1 l 10.0 INSPECTION 10 10-1 6 l l
10-2 6 I O l 10-3 e l 10-4 6 . l 10-5 6 l , 10-6 .7 11.0 l l TEST CONTROL 11 11-1 6 l l 11-2 6 l l 11-3 6 l l 11-4 6 l l 11-5 7 l 12.0 CONTROL OF MEASURING AND 12 12-1
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l TEST EQUIPMENT 12-2 6 l l 12-3 6 l l 12-4 6 l 13.0 HANDLING, STORAGE AND 13 13-1 l 6 l l SHIPPING 13-2 7 l l 13-3 6 l l 13-4 7 l O l 13-5 6 l l 14.0 INSPECTION, TEST AND 14 14-1 6 l l OPERATING STATUS 14-2 6 l l 14-3 6 l 14-4 6 l l 14-5 6 l 15.0 NONCONFORMING MATERIAL, 15 15-1 l 7 l l PARTS OR COMPONENTS 15-2 7 l 15-3 l 7 l l 15-4 7 l l 15-5 7 l 1 1 I I I l l 1 l l l 1 1 I l l O lA l P l l TOPICAL REPORT lREV. lDATE 05/31/85 7 l l
- l. & l SECTION: TABLE OF CONTENTS lPAGE TC-4 l l L l l l
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1_ _ _ _ _ . - _- - . ~ - ~ - ~ - ~ - - - - -- - - - ~- - - 1 I I I i 16.0 CORRECTIVE ACTION 16 16-1 7 I I I 16-2 6
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l 16-3 6 l 16-4 6 17.0 l l QUALITY ASSURANCE RECORDS 17 1 6 l l 17-2 6 l l 17-3 6 l l 17-4 6 l l 17-5 6 l 18.O AUDITS 18 18-1 _l 6
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l 18-6 7 l 1 1 I l I I I I I I I I O j l l l l l l l l l l 1 I I l I I I I I I I I I I I l- 1 I I I I I I I ' I I I l l I I I i l I i I O lA l P l l 10,1 CAL RE,0R1 lREv. 7 lDATE 05/31/85 l l l & 1 SECTION: TABLE OF CONTENTS IPAGE TC-5 I I L l l l l l l l
l l I l l FIGURES l 1 I (T (,) l Number l l Title Tab M Rev. l 1 AP&L Corporate F-1 7 I l Organization l 2 AP&L Corporate Services F-2 7 3 AP&L Energy Supply l l F-3 7 l Organization l l 4 AP&L Quality Assurance F-4 6 l Organization l l l 5 AP&L Nuclear Plant F-5 7 l Organization l l l 6 AP&L Nuclear Plant F-6 7 l Organization (Plant l l l Operations and Main- l tenance) l 7 AP&L Nuclear Plant F-7 6 l 1 Organization (Plant Engineering and Technical l l l ') ( Support) 8 AP&L Nuclear Plant l l 19 F-8 6 l 1 Organization (Plant l l Administrative Services) l l l l 1 I I I I l l l l l l l 1 I I I I l l l l l l l l l l l l l 1 l A l TOPICAL REPORT lREV. 7 l l P I lDATE 05/31/85 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-6 l l L l l l l l l l
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- I I I TABLES I ,
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1 Number Title Tab Pm Rev. I I l' AP&L Exceptions / Inter- T1-1 6 pretations of Regulatory l 1 I T1-2 6 I Guides and ANSI Standards T1-3 l 6 l 1- T1-4 6 l T1-5 l 6 l !- l T1-6 7 l l T1-7 l 6 l l TI-8 6 I I ! T1-9 7 I
! l l j l T1-10 6 I 4
T1-11 6 l l I T1-12 6 I . T1-13 7 l l l T1-14 6 l i I I T1-15 6 I I l T1-16 6 l 2 Quality Assurance T2-1 7 l l l Procedures Matrix I 3 Quality Program Policies, T3-1 7 l l i l Procedures and Instruc- T3-2 7 I I ., tion Manuals List T3-3 7 I I i 4 I l
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! I l i l 1 1 I i l i 1 I I l l i l l
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I TOPICAL REPORT I IREV. 7 I I . l I P l IDATE 05/31/85 1 i ! & 1 SECTION: TABLE OF CONTENTS lPAGE TC-7 l 1 L l l l
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I I I I l APPENDICES I I I O' i l Nu 8er 14 tie a Rev. i l 1 1 I A Quality Program For AA-1 7 l Transport Packages l AA-2 7 l l AA-3 7 I l l l I I B Quality Program For AB-1 7 I i l Fire Protection AB-2 7 l l AB-3 7 1 4 l AB-4 7 l l AB-5 7 l l AB-6 7 l l AB-7 7 l l AB-8 7 l l i I I I I I I O l l l I L I I I I I I a I i l I r i I l l , I l l I
- I I I I I I I I I I I l I l l 1 I I I I I I
, I I I I A I TOPICAL REPORT IREV. 7 i P l IDATE 05/31/85 l l & I SECTION: TABLE OF CONTENTS IPAGE TC-8 l l L I l l 1 I I I
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1 I I I l ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l I QUALITY ASSURANCE PROGRAM FOR OPERATION I O l l l 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 lforOperationmeettherequirementsoftheCodeofFederalRegulations, l l 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, I l repair and modifications, and inservice inspection of AP&L nuclear l l The program shall also meet the requirements of the ASME Boiler l l plants. and Pressure Vessel Codes with respect to items constructed, repaired or l replaced to Code requirements. l I l l I I I Under the Program the Energy Supply Sr. Vice President, is the final l lmanagementauthorityresponsibleforassuringthatthispolicystatement l and the Quality Assurance Program are implemented within AP&L. l The l lNuclearOperationsVicepresidentandeachEnergySupplyDirectoris l l responsible for the procedural implementation of the program within his l lassignedarea. The plant's General Manager is responsible for the daily l l implementation of the Program's procedural requirements at the plant. I O l l l The Quality Assurance Manager is responsible for establishing the l Program. The Quality Assurance Manager, Energy Supply Services Director l l l and the Energy Supply Sr. Vice President are responsible for approval of I ltheProgram. l l l lQualityAssurancepersonnelreportingtotheQualityAssuranceManager l l are responsible for auditing the Program as necessary and monitoring l lactivitiesrequiredbythe"rogramtoassurecompliancewithits requirements. l l Disputes involving quality, arising from difference of I lopinionsbetweenQApersonnelandotherpersonnel,whichcannotbe l l settled interdepartmentally, shall be presented to the Energy Supply l lSeniorVicePresidentforresolution. l l l l l l l l l l l O l l A I l TOPICAL REPORT l lREV. 7 I l l P l lDATE 5/31/85 I I & I SECTION: STATEMENT OF POLICY IPAGE A-1 I I L l l l l l l l
I s I I I l The Quality Assurance Manager is to provide for annual review of the 1 ladequacyandoveralleffectivenessoftheProgram. Any defects in the V l l implementation of either this policy or the' Program that are revealed I during the review are to be reported to appropriate levels of management l together with appropriate recommendations. l
, I l
- I l s l
I Implementation of this policy is necessary in orde'r to achieve the l l reliability and safety required at our nuclear plants. Each person l l involved in activities concerning our nuclear plants is to be responsible l lforassuringqualityinhiscwnwork,andforcompliancewiththe requirements of the Program. l l The Quality Assurance Program policies, I l manuals,andproceduresaremandatoryrequirementswhichmustbe l l implemented and enforced by all responsible organizations and l l individuals. l l l
, xjnk?:}7'(' * /,-
l l ' l l J. Griffin (Nb' I
' 3 Energy Supply Sr. Vice President l l l I O l oete: 4/.1wAw l l s ~.
1 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 I I I I I I I s I l I I l l l 1 I I O lA l p I I TOPICAL REPORT lREV. 7 lDATE 5/31/85 l l & I SECTION: STATEMENT OF POLICY IPAGE A-2 I I L I I I l l l l
1 I l l l Purchaser - The organization or organizations responsible for issuance l landadministrationofacontract, subcontract,orpurchaseorder. l l l lQ-List-Alistofsafetyrelatedstructures, systems,andcomponents-l that is, those structures, systems, and components that are relied upon l ltoremainfunctionalduringandfollowingdesignbasiseventsto I ensure: (1) the integrity of the reactor coolant boundary, (2) the l lcapabilitytoshutdownthereactorandmaintainitinasafeshutdown
' l I condition, and (3) the capability to prevent or mitigate the l lconsequencesofaccidentsthatcouldresultinpotentialoffsite l exposure comparable to the guidelines of 10 CFR Part 100.
l I i l i i I Qualification (Personnel) - The characteristics or abilities gained l l through training or experience or both that enable an individual to l l perform a required function, l i i 1 l l Qualified Party - A person or organization competent and recognized as l lknowlegeabletoperformcertainfunctions. l l l Qualified Procedure - A procedure which incorporates all applicable codes I and standards, manufacturer's parameters, and engineering specifications l landhasbeenprovenadequateforitsintendedpurpose. l 1 l lQualifiedVendorList-Alistingofvendorshavingqualityassurance l l programs consistent with the requirements of applicable portions of l 10CFR50, Appendix B. l l l l Quality Assurance - All those planned and systematic actions necessary to l l provide adequate confidence that an item or a facility will perform l lsatisfactorilyinservice. l l l
, lQualityControl-Thosequalityassuranceactionswhichprovideameans l l to control and measure the characteristics of an item, process, or l lfacilitytoestablishedrequirements. l l l l I A I TOPICAL REPORT REV. 7 p
l l lDATE 05/31/85 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-7 l l L l l l l l l I
l l I I l Receiving - Taking delivery of an item at a designated location. l 1 1 Repair - The process of restoring a nonconforming characteristic to a l condition such that the capability of an item to function reliably and
'l safely is unimpaired, even thoug;) that item still may not conform to the l
l < loriginalrequirement. l l 1 l Report-Something(document)thatgivesinformationforrecordpurposes. l I l l Review-Anelementofinspectiontodetermineconformancetospecified l l requirements, which can be determined by examination of documents and l l activities. l l l l Rework-Theprocessbywhichanonconformingitemismadetoconformto l l a prior specified requirement by completion, remachining, reassembling or l lothercorrectivemeans. l l l Safety-Related (Q) - Safety related structures, systems, and components l l are those that are relied upon to remain functional during and following l design basis events to ensure: (1) the integrity of the reactor coolant l boundary, (2) the capability to shut down the reactor and maintain it in l lasafeshutdowncondition,and(3)thecapabilitytopreventormitigate l l the consequences of accidents that could result in potential offshe l lexposurescomparabletotheguidelinesof10CFRPart100. l 1 l lSourceSurveillance-Areview, observation,orinspectionforthe l l purpose of verifying that an action has been accomplished as specified at l lthelocationofmaterialprocurementormanufacture. l l 1 Specification-Aconcisestatementofasetofrequirementstobe l l l satisfied by a product, material or process indicating, whenever l l appropriate,theprocedurebymeansofwhichitmaybedeterminedwhether l the requirements given are satisfied. 1 I l i I I I I l l A l TOPICAL REPORT lREV. 7 l l P l IDATE 05/31/85 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-8 l l L l l l l l l I
l i I I l 1.0 ORGANIZATION l o V l l ; l 1.1 SCOPE l l l l l l This section describes the AP&L organizational structure and l l responsibilities for establishing and executing the Quality Assurance l l Program for AP&L operational nuclear plants in compliance with 10CFR50, l lAppendixBandapplicableRegulatoryGuidesandANSIStandardsidentified I in the Introduction. It also includes a description of the interfaces l lwithotherorganizationswhomaybedelegatedtheworkofestablishing l l and executing portions of the Quality Assurance Program. The AP&L l lCorporateOrganizationrelevanttotheoperationofitsnuclearplantsis l l shown in Figure 1. l 1 I I I i 1.2 GENERAL RESPONSIBILITIES I I I I I I 1.2.1 l l l l 1 p I The ultimate responsibilities for operational nuclear plants within AP&L, I lincludingQualityAssurance,lieswiththeEnergySupplySeniorVice l l President. He provides management assessment of the Quality Assurance l lProgramthroughreviewofQAAuditReportsandreportsofNRCactivities. l l l 1.2.2 l l l The Administrative Services Vice President is responsible for the I purchasing functions affecting plant operation as described in Subsection I 1.3. I I l1.3 CORPORATE SERVICES l l l
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.O I l A I l TOPICAL REPORT I IREV. 7 I l l P I IDATE 5/31/85 1 l & l SECTION: 1.0 ORGANIZATION lPAGE 1-1 I I L l l l l l I l
I I I I I Corporate Services is responsible for the procurement of materials, parts l l and components requested by Little Rock General Of fice (LRGO) personnel l l and for supporting the procurement activities at the plant. Procurement I organization is noted in Figure 2. l l 1 1.3.2 I I lTheNuclearBuyerreportstotheSupervisorofPurchasingwhoreportsto l l the Manager, Purchasing and Stores and is responsible for the following l ldutiesandactivities: l l 1 l 1. Prepares purchase orders based upon receipt of reviewed and l approved Purchase Requisitions. l 1 I I I I l 2. Performs the commercial interface functions between AP&L and l l contractors or vendors. l l l
- 3. Assures that quality documentation prepared by Energy Supply l l l personnel are included in purchasing documents. l I I l 1.4 ENERGY SUPPLY l l l l l l Energy Supply, headed by the Energy Supply Senior Vice President is l lresponsibleforallactivitiesrelatedtotheoperationofAP&LNuclear l l Plants. These activities include as a minimum: design, modification, I maintenance, inservice inspection and test, operation and those l
l additional activities discussed in Sections 2 through 18 of this manual. l lWithinEnergySupply,theNuclearOperationsandEnergySupplyService l 1 organizations are involved in activities requiring execution of the I. lQualityAssuranceProgram (See Figure 3). l l 1 1.4.1 Energy Supply Services l l I I I l 1 I I I I O i I A i l TOPICAL REPORT l lREV. 7 l I I P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-2 l l L I l l l l l I
l I I I l Energy Supply Services is under the direction of the Energy Supply l n I Services Director, who reports to the Energy Supply Senior Vice I I') l l President. The Energy Supply Services Director is responsible for 1 l providing support to AP&L nuclear plants in the areas of quality l l assurance, administrative services, engineering services and technical l I j services. His duties include providing technical direction, i administrative guidance and supervision to the: l l l l l
; a. Energy Supply Administrative Services General Manager l
- b. Engineering Services General Manager l l l c. Technical Services General Manager l
- d. Quality Assurance Manager I l Quality Assurance Manager l1.4.1.1 I I lTheAP&LQualityAssuranceOrganization(QAO)asshowninFigure4is l l under the direction of the Quality Assurance Manager, who reports to the l Energy Supply Services Director. The QA0 performs review, surveillance, l
fJ l inspection and audit functions during the operational phase of AP&L's l nuclear plants and is independent of Nuclear Operations, and from cost l and scheduling considerations when opposed to safety and quality l considerations. The QA Manager shall have direct access to management l l levels, which assures his ability to: identify quality problems; l initiate, recommend or provide solutions through designated channels; and l verify implementation of solutions. l l l 1 I l The qualification requirements of the QA Manager are established within l his AP&L job description which includes the following prerequisites: l l 1
- 1. Possess a degree from an accredited school in engineering or a l related scientific discipline or equivalent; l l l l l l l l l l l l I I I
(] I I A l l TOPICAL REPORT l lREV. 7 1 l l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE l-3 I I L l l l l l I 1
I I I I I 2. Possess a minimum of five years experience in the quality l (] l assurance or quality control disciplines with atleast two years U l in the nuclear field; and l l 1 I I I 3. Exhibit the ability to plan, schedule and direct the activities l of others assigned to or functioning within the QA0. l l 1 l The duties and responsibilities of the Quality Assurance Manager include l l the following: l l l l I i 1. Develop Quality Assurance Program requirements for I 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 l Section 18 of this manual. l l l l 1 p l 3. Review, approval and verification of the quality assurance l requirements placed upon contractors or vendors that provide l l l equipment, material, or services for AP&L nuclear plants. I I I I I l 4. Authority to stop work where conditions exist that prohibit l effective quality control inspections, or if faulty materials, l
l incorrect workmanship or procedures are detected. l I I I I l S. Review, approval, distribution and control of QA Manuals and QA l Procedures and revisions thereto. I I
- 6. Review and approval of QA programs for outside organizations l participating in the AP&L QA program. I I I I I l 7. Serve as chairman of the Safety Review Committee. l I I I I I l i I I I I I (d3 l A l TOPICAL REPORT lREV. 7 l
; l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-4 l 1 L l l l l l l 1 L
l l l l l 8. Provide and maintain a qualified and suitable trained staff to l {') v ; carry out required stati functions. l
- 9. Formulate programs for maintaining the professional competence l
l of personnel within the QA0 and provide assistance in QA l training and indoctrination programs for division management, l engineering and plant personnel whose activities affect l quality. l l l l l 10. Provide technical direction and guidance to the Quality l l Engineering Supervisors. l l l 1 I l 1.4.1.1.1 Quality Engineering Supervisor l 1 I I I l The Quality Engineering Supervisor reports to the Quality Assurance l Manager, supervises QA Engineers and Auditors / Inspectors as assigned, l I and assists the Quality Assurance Manager in the coordination of I activities within the QA Section. The Quality Engineering Supervisor may l O l also perform duties normally assigned to Quality Assurance Engineers. I V I I f I I l 1.4.1.1.2 Quality Assurance Engineers l 1 l l l l l The Quality Assurance Engineers (QAE's) report to a Quality Engineering l Supervisor,asassigned. The Quality Assurance Engineers are to be l l l familiar with the Quality Assurance Program and associated procedures, l 10CFR50 Appendix B, regulatory guides, codes, and standards that address l l 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. Specifically: I i
- 1. The QAE's are to have the authority to inspect, audit or review l practices, records, files, instructions, directions or l I
documents concerned with all areas affecting quality. ; I I m i I ()
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l l A I l TOPICAL REPORT I lREV. 7 I l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-5 l l L l l l l l 1 I l
I I I I l 2. The QAE's are to schedule and coordinate audits or surveillance i efforts in the areas assigned, document findings, and report l l results to the Quality Assurance Manager and the Manager of the I audited area. l l 1 l1.4.1.1.3 Quality Assurance Auditors / Inspectors l l 1 lTheQualityAssuranceAuditors/InspectorsreporttotheQuality l l Engineering Supervisor and assist him in the implementation of the l lprogrambyperformingauditsandinspectionsasrequiredtoassureproper l l application of the Quality Assurance Program. I I I I I l 1.4.1.2 Technical Services General Manager I i l I I l The Technical Services General Manager reports to the Energy Supply I lServicesDirectorandisresponsibleforprovidingsupporttoAP&L l l nuclear plants in the areas of plant performance, maintenance and I l availability, chemistry,environmentalmonitoring,metallurgyand l
, I nondestructive examination. His duties include the following: I b/'s I I
.I I I 1. Provides technical direction and administrative guidance to: l l l l l 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 1
- 3. Provide for coordination of environmental surveillance programs l l l l l l l l l I I I I O i l A i
I TOPICAL REPORT i lREV. 7 i I I P l lDATE 5/31/85 I l & I SECTION: 1.0 ORGANIZATION IPAGE 1-6 I l L I I l l l l 1 l
I I I I l 4. Direct development of programs aimed at maximizing efficiency l l and availability.
- I O l l I 5. Provide for review and analysis of outage data and make l
l recommendations for correcting deficiencies which affect l I availability or performance. l l l I 6. Direct the plant maintenance support activities that are l assigned to the LRGO. l l l l l 4 l 7. Serve as a member of the Safety Review Committee. l l l l l l 8. Provide and maintain a qualified and suitably trained staff to l l carry out required departmental functions. l l l l1.4.1.3 Engineering Services General Manager l 1 I l lTheEngineeringServicesGeneralManagerreportstotheEnergySupply l l Services Director and is responsible for LRGO design and engineering l l.activitiesrelatedtonuclearplantoperations. His duties include the l l following: l l l l l l 1. Provide technical direction and administrative guidance to: l
-1 1 I i l a. Mechanical Engineering Manager l
- b. Electrical Engineering Manager l
l c. Civil Engineering Manager l
- d. Instrumentation and Controls Engineering Manager l
l l
- 2. Assure conformance to the Quality Assurance Program by l instituting the necessary quality-related procedures and l instructions within Engineering Services.
l l 1 I I I I l l l I A l TOPICAL REPORT lREV. 7 I P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-7 l l L l 1 l l l l l
l l I I l 3. Provide for review and approval of LRGO design and engineering l l activities performed by contractors, vendors, and AP&L l l personnel. l I I I I I 4. Provide for review and approval of procurement documents for l l equipment, material and services for LRGO engineering projects, l l as appropriate. I I I I I l S. Provide and maintain a qualified and suitable trained staff to l l carry out required departmental functions. l l l l1.4.1.4 Energy Supply Administrative Services General Manager l l l lTheEnergySupplyAdministrativeServicesGeneralManagerreportstothe l Energy Supply Services Director and is responsible for the development of I ladministrativeprograms,systemsandservicessupportivetomanagement. l l His duties include the following: l I I I I g l 1. Provide technical direction and guidance to: I s I l l I l a. Energy Supply Training Manager l
- b. General Services Manager l l l c. Planning, Scheduling & Cost Control Manager l l d. Contract Administration Manager l
l l l 2. Maintain overall department fiscal direction and control, and l l provides supportive accounting functions. I I I I I l 3. Provide contract administration and administration of I procedures for Energy Supply Little Rock General Office (LRGO) I activities. I I I I I I 4. Administration of the training and development effort for l Energy Supply LRGO personnel. l l l l l O ' l A I TOPICAL REPORT i IREV. 7 i l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-8 l l L I l l l l l l
I I I i l 5. Ancillary support services to Energy Supply operation sections. [ ,q i l I V l l l 6. Provide and maintain a qualified and suitable staff to carry l l out required departmental functions. I I I l 7. Serve as a member of the Safety Review Committee. l l l l 1 l 8. Assure conformance to the Quality Assurance Program by l l instituting the necessary quality-related procedures and I I I l instructions within Administrative Services. l l l l l l 1.4.2 Nuclear Operations l l l l l l Nuclear Operations is under the direction of the Nuclear Operations Vice l l President who reports to the Energy Supply Senior Vice President and is l I I l responsible for the formulation, licensing, implementation and discharge l of operating policies and procedures relative to nuclear plant operations l l and for nuclear fuel management. His duties include the following: l l 1 I I p l 1. Provide technical direction and administrative guidance to the: l (.), I i l I l a. Plant's General Manager l l b. Nuclear Services General Manager l l l l c. AND Projects Manager l 1 I I I l 2. Assure conformance to the Quality Assurance Program by l instituting the necessary procedures and instructions within l the Nuclear Operation' Department. l l l l 1 l 3. Provide for review and approval of design and engineering l I performed for the operating nuclear plants. I I I I I
- 4. Provide for review and approval of procurement documents for l equipment, material and services. l l 1 l I I
I O I I I l
\J l A l TOPICAL REPORT IREV. 7 l l P I lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE l-9 l l L I l l l l l l
c l l l l l S. Provide for liaison between AP&L and applicable regulatory l I agencies. I Oe l l f 6. Provide and maintain a qualified and suitable staff to carry I out required departmental functions. I I I I I l 7. Provide for procurement and design review of nuclear fuel. I I I I I l 8. Overall responsibility for the fire protection program l implemented at the nuclear plants. l l l l Nuclear Services General Manager l1.4.2.1 l l l lTheNuclearServicesGeneralManagerreportstotheNuclearOperations l l Vice President and is responsible for providing the necessary support l lservicesrelatedtotheeffectiveoperationandmaintenanceoftheAP&L l l nuclear plants. The duties include the following: l l l 1 I g l 1. Provide technical direction and administrative guidance to the: I v I I I I l a. Licensing Manager l
- b. Nuclear Programs Manager l
I c. Nuclear Fuel Supervisor I I i l l I 2. Interface with other departments to assure effective I implementation of Regulatory and Company requirements. l 1 I
- 3. Communication interface dealing with all activities at the l
I nuclear plants. I I I I I I 4. Serve as a member of and provide administrative support to the l Safety Review Committee. l l l l l l l l l l i l l I I I I l Pd I A I TOPICAL REPORT IREV. 7 I , I P I IDATE 5/31/85 I I & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-10 l l L I l l i l i l I i
'l l l
l l 3.4.4 I I I (] V l l l Design work performed by organizations outside of AP&L is to receive a l I l documented review and approval by engineering personnel in accordance l l I with LRGO and plant departmental procedures. l I I I I I 3. 5 DESIGN CHANGE l I I I I I 3.5.1 I I I I I I Methods for the preparation, review, approval and implementation of I I l l aesign changes, including field changes, are documented in departmental l l procedures for Engineering Services and Plant Engineering. Design l I l changes are subject to review and verification by the same organization I l I which reviewed and verified the original design unless otherwise l I l specified in departmental procedures for design control. If minor I l l changes to an approved design are required to meet plant requirements or l I l conditions, Field Change Notices (FCN) may be issued or otherwise l l l documented by a cognizant engineer and transmitted with the changes for s) l review and approval in accordance with Plant Engineering Administrative l l Procedures. I I I I I I 3.5.2 l l l l l l Changes from specified design inputs, such as design bases, regulatory i I l requirements, codes and standards (including quality standards) are to be I g I identified, approved, documented and controlled through applicable LRGO I I l and plant departmental procedures. I I I 1 l 3.5.3 l l 1 I I I l During preparation of a design change, the responsible engineering l I organization is to perform a safety and environmental evaluation per l I I l I I I I I O I I I I l A I TOPICAL REPORT lREV. 7 l P '. I I lDATE 5/31/85 l l & I SECTION: 3.0 DESIGN CONTROL IPAGE 3-4 l l L I I I I I I i
l l l l l "off-the-shelf" items, reference to the items catalog number and l lidentificationnumbermaybeincludedontheprocurementdocumentinlieu l ~> l of a design specification. New or revised specifications for replacement l litemsaretobeevaluatedbytheresponsibleengineeringorganization l l against the original specification for the item. The evaluation is to be 1 linaccordancewithapplicableengineeringproceduresandresultsinthe l l establishment of new baseline and technical quality requirements, which l laretobeusedforsubsequentprocurements. l l l l4.2.3 l l l lProcurementdocumentsarealsotoincludetheidentificationofquality l l assurance program requirements applicable to the items or services l l procured. Procurement documents also establish requirements for source l l audits and inspection, extension of the procurement requirements to lower l tier suppliers or subcontractors, and preparation and delivery of l documentation. These requirements may either be in the form of documents l lattachedtotheP0orContractorbyincorporatingtheminthespecific l l design specifications. Quality programs are to be specified by invoking l ltheappropriatesectionsof10CFR50, App.8,theappropriateANSI l standards and/or the appropriate AP&L generated quality requirements for l litemsorservices. The appropriate sections of the ASME Boiler and l l Pressure Vessel Code are to be invoked for items originally designed to l lmeetASMErequirements. l l l l4.3 REVIEW 0F PROCUREMENT DOCUMENTS l l l lTheresponsibleQualityAssuranceorQualityControlorganization,as l l l -identified in the LRGO and plant procedures for procurement and contract l ! ladm'nistrationactivities,istoreviewallprocurementdocumentsto l l assure that the required quality requirements (including source l lsurveillanceand/orinspection)tireimposedonsuppliers/ contractors. l l l l l l l l l l l /~') V l l l 1 l A l TOPICAL REPORT lREV. 7 l l P l IDATE 5/31/85 l l & l SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l l L l l l l l l l
I I I I I 1.4.2.1.1 Nuclear Fuel Supervisor l 1 i O i l The Nuclear Fuel Supervisor reports to the Nuclear Services General i l lManagerandisresponsiblefortheprocurement,designreviewand l l performance evaluation of nuclear fuel. The Nuclear Fuel Supervisor also l provides support to the plant in the areas of reactor core performance I and assessment of core design analysis. I I l l i l l l1.4.2.1.2LicensingManager l l l lTheLicensingManagerreportstotheNuclearServicesGeneralManagerand l is responsible for the coordination of all licensing documents, l I lrequirementsandrevisionstheretowhicharerequiredtobereviewed l and/or approved by the NRC and for interfacing with the NRC. l The l lLicensingmanagerisalsoresponsibleforthereviewandapprovalof l l Q-List changes and for the tracking of possible nuclear safety concerns l to assure timely closecut. l O I l O 1.4.2.1.3 Nuclear Programs Manager l l l The Nuclear Programs Manager reports to the Nuclear S-rvices General l l Manager and is responsible for providing support to the nuclear plants in I the areas of fire protection, emergency planning, radioactive waste and I health physics / radiation protection. l l l l l l 1.4.2.2 Projects Manager l I l l l l The Projects Manager reports to the Nuclear Operations Vice President and I is responsible for providing services to the nuclear plants in the areas I l of construction activities, control room simulator modifications used for i operator training, and review, approval and coordination of design l changes through the Little Rock General Office. His duties include l lprovidingtechnicaldirectionandadministrativeguidancetothe: 1 I I (] I l l 1 I l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-11 l l L I l l l l 1 I
I I I I l a. Field Construction Manager I (\ l b. Project Services Supervisor l l c. Special Projects Coordinators i I I l l l 1.4.2.2.1 Field Construction Manager I I I I I l The Field Construction Manager is responsible for directing the I activities of his staff relating to work associated with plant I construction and modifications. His duties include: l I I I I l 1) Interface with other departments to assure effective I implementation of job assignments l l l l 2) Provide cost and schedule controls for departmental activities l l l l 3) Provide technical and administrative guidance to the l l Construction Quality Control (CQC) Supervisor. The CQC I l Supervisor is responsible for the surveillance and inspection l p I of activities performed under the direction of the Field I
^
Construction Manager, and shall have sufficient authority and l l organizational freedom to: identify quality problems; I initiate, recommend or provide solutions through desi rated l l channels; and verify implementation of solutions. The CQC l Supervisor is also responsible for assuring adequate inspection l l points have been assigned for the work activity, inspectors I have been certified to ANSI N45.2.6, directing the activities l l of the inspectors, and interfacing with the Code Inspector for I activities involving Code items. l l 1
- 1. 5 PLANT ORGANIZATION l
l l General Manager l1.5.1 l l l l l l 1 I I l l O i l A i I TOPICAL REPORT i [REV. 7 i l l P I lDATE 5/31/85 I l & I SECTION: 1.0 ORGANIZATION IPAGE 1-12 I I L I I l l I I I
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I l l I l 1.5.1.1 l l l O' i l The General Manager reports to the Nuclear Operations Vice President on l i the corporate level (see figure 5) and has direct responsibility for operating the plant in a safe, reliable and efficient manner. l l He is l lresponsibleforoperatingtheplantinaccordancewiththeprovisionsof l l the operating licenses, including the on-site quality program. l l l l l l 1.5.1.2 l l l l 1 l The General Manager has the authority to shut the plant down if required I and has final approval of plant procedures. I I l1.5.1.3 l l l lTheGeneralManageristoprovidetechnicaldirectionandadministrative l guidance to the: l l l 1 I g l 1) Operations Manager i V 2) Maintenance Manager Administrative Manager l l 3) I
- 4) Engineering and Technical Support Manager l
l 5) Special Projects Manager l
- 6) Manager, Nuclear Quality Control l
l 7) Work Control Center Manager l l i I I l 1.5.2 Operations Manager l
- l l l l l The Operations Manager (Figure 6) is responsible for directing the actual 1 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 l provide technical direction and administrative guidance to the: l l l 1 I I I I I
/3 l l l 1 'd I A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-13 l l L l l l l l I l
I I I l l 1) Operations Superintendents ' l p 2) Operations Technical Staff V I l l1.5.2.1 l l l The Operations Superintendents report to and assist the Operations l l Manager in directing the day-to-day operation of the power plants. They I lareresponsibleforcoordinationofthedailyreviewofoperating i surveillance tests and coordination of operation-related maintenance I I activities. They are to assist the Operations Manager in the supervision l l of core refueling, which includes advance planning for the outage, plant l l preparation,equipmentcheck-outandtherefuelingoperations. l l l 1.5.2.2 l 1 i The Shift Supervisors report to the Operations Superintendent and are I responsible for the actual operation of the unit and for the activities l i loftheoperatorsduringtheirassignedshift. The Shift Supervisor is to g I be cognizant of operation activities being performed while on duty. The l \- Shift Supervisor on duty has the authority to shut down the unit if, in l l his judgement, conditions warrant such action. l l l l l l 1.5.3 Maintenance Manager l I l l l l The Maintenance Manager (Figure 6) is responsible for the maintenance of l plant equipment and facilities as dofined by plant maintenance program l l implementing procedures and to assure that maintenance of equipment is l conducted in conformance with applicable standards, codes, specifications l l and procedures. The Maintenance Manager is also to coordinate 1 operation-related maintenance activities with the Operations Manager and I is responsible to make repairs on any structure, system or component I under his control. The Maintenance Manager is to provide technical l direction and administrative guidance to the: l I I I I I I I l O i l A i l TOPICAL REPORT i IREV. 7 i I l P I lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-14 l l L I l l 1 I I I
1 I I I l 1. Mechanical Maintenance Superintendent l
- 2. Electrical Maintenance Superintendent l
l 3. Instrument & Control Superintendent l
- 4. Senior Maintenance Coordinator l S. Shift Maintenance Superintendent l l l l
1 l 1.5.4 Engineering and Technical Support Manager l l l 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 l l plant analysis and health physics support services to the plant staff. l The Engineering and Technical Support Manager is to provide technical [ direction and administrative guidance to the: l l 1 l 1 - l l 1) Technical Analysis Superintendent l
- 2) Plant Analysis Superintendent l
l 3) Plant Engineering Superintendent l
- 4) Operations Assessment Superintendent l 5) Health Physics Superintendent.
O l i l i l l 1.5.4.1 Technical Analysis Superintendent l l l l l l The Technical Analysis Superintendent maintains overall responsibility l for radiochemistry, chemistry and environmental programs at the plant. l l The Technical Analysis Superintendent is also responsible for maintaining l ltheStationEmergencyPlanandensuringtheplantstaffiscapableof l implementing the requirements delineated in the Plan and its procedures. l l l I I l 1.5.4.1.1 l l l l l l The Radiochemistry Supervisor reports to the Technical Analysis l lSuperintendentandisresponsibleforanalyzingthereactorplantwater I conditions and providing recommendations to maintain conditions. l l l l 1 1 I I I Q V l l A l TOPICAL REPORT l 7 1 l lREV. l l P l lDATE 5/31/85 I I & i SECTION: 1.0 ORGANIZATION lPAGE 1-15 I I L l l l l l I I
I l l l l 1.5.4.1.2 I o l l The Chemistry and Environmental Supervisor reports to the Technical l l lAnalysisSuperintendentandisresponsibleforestablishingwater l l chemistry criteria, analyzing secondary plant water and auxiliary water I lconditionsandprovidingrecommendationstomaintainconditionswithin l l acceptable limits. l l l l l l 1.5.4.2 Plant Analysis Superintendent l l 1 1 I l The Plant Analysis Superintendent is responsible for the areas of plant l performance,nuclearsupportandcomputersupport. A supervisor is l l l provided for each of these areas. l I l l l l 1.5.4.2.1 l l l l l l The Plant Performance Supervisor reports to the Plant Analysis l Superintendent and is responsible for: evaluating equipment and system l l l performance over extended periods, recommending methods of improving and I maintaining good plant efficiency, investigating and evaluating equipment l I malfunctions or failures and recommending corrective action to prevent l recurrences,andcoordinatingtheactivitiesoftheInserviceTesting l l l Program at the plant. l l l l 1 l 1.5.4.2.2 l l 1 l 1 l The Nuclear Support Supervisor reports to the Plant Analysis l lSuperintendentandisresponsibleformonitoringreactorcoreandNuclear l l Steam Supply System (NSSS) performance; conducting reactor performance l landphysicstestingtoassuresafeandreliableoperationandtoprovide l l current accurate information to operations; collection and transmittal of I lnuclearfuelmanagementdatatotheNuclearFuelSupervisorinLittle l l Rock and the reactor vendors as required; on-site safeguards and l laccountabilityofthenuclearfuel;andassistingintheplanningofall l I I I l O i l A i l TOPICAL REPORT i lREV. 7 i I l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION IPAGE 1-16 I l L l l l l l l _I
I I l l l fuel movements including new fuel receipt and inspection, fuel shuffling l C,e latrefueling,inspectionofirradiatedfuelandshipmentofspentfuel. I i I l 1.5.4.2.3 I I I I I The Computer Support Supervisor reports to the Plant Analysis l Superintendent and is responsible for the maintenance, revision and l l development of computer software for the plant monitoring computers and l for providing technical assistance to the Nuclear Support Supervisor and. l lNuclearEngineersindevelopmentanduseoftestapparatusforevaluation of fuel, core and NSSS performance. l l l l l l l l 1.5.4.3 Plant Engineering Superintendent l l l l l l The Plant Engineering Superintendent is responsible for drawing control, l implementation and coordination of the Inservice Inspection Program and design and plant engineering activities at the plant. The Plant l l l Engineering Superintendent is to provide technical direction and administrative guidance to the: l l O i i l i I l 1) Mechanical Engineering Supervisor l
- 2) Electrical Engineering Supervisor l
l 3) Drafting and Drawing Control Supervisor. l l l l l l 1.5.4.4 Operations Assessment Superintendent l l l l 1 l The Operations Assessment Superintendent provides the capability to l perform engineering evaluations of operating experiences which occur both l at the AP&L nuclear plants and at other nuclear power plants and to l recommend corrective actions as a result of these evaluations to help l plant operations personnel in preventing or dealing with similar l ocurrences. I I I I I I I I I I l A l TOPICAL REPORT IREV. 7 l l P l 10 ATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-17 l l L l l l l 1 I I
I I I . I i 1.5.4.5 Health Physics Superintendent l /~~T U l 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 l and to maintain radiation exposure as low as reasonably achievable l I (ALARA). The Health Physics Superintendent has the authority to stop l work in radiation areas if he determines that a potential for an l unanticipated excessive exposure to plant personnel or the environment ; I l may exist. l l l l l l 1.5.5 Administrative Manager l l l l l l The Administrative Manager (Figure 8) reports to the General Manager and l aids him in the administrative aspects of the plant's operation. The l l Administrative Manager directs the activities of the administrative staff I and provides technical direction and administrative guidance to the: I I
- 1) Office Services Supervisor l
q l 2) Material Management Supervisor l V 3) Human Resources Supervisor l l 4) Training Superintendent l
- 5) Plant Controller l
1 I l1.5.5.1 l l l The Office Services Supervisor is responsible for administration of the l clerical staff activities and the accumulation and disposition of quality l assurance records related to all phases of the nuclear plant. I I i 1.5.5.2 l l l The Material Management Supervisor is responsible for plant procurement, l l storage of materials, parts and equipment, issuance of tools and test l equipment and the disposal of surplus materials. l l l l l C) l l A l l TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-18 I I L l l l l l l 1
I I l I
.I 1.5.5.3 l l l C.- l I
The Human Resources Supervisor is responsible for employment, industrial 1 l I
; relations, industrial safety and fire prevention and security. Reporting I l to him are the Safety and Fire Prevention Coordinators, the Security l Coordinator, and the Employment and Industrial Relations Coordinator.
I I i 1.5.5.3.1 I I I I l lTheSafetyandFirePreventionCoordinatorsareresponsiblefor l conducting periodic checks to examine control of combustables, l housekeeping and other fire prevention / protection efforts as well as to I l provide a centralization of OSHA and plant safety programs. l l l l l l 1.5.5.3.2 l l l l I l- The Security Coordinator is responsible for coordination of the efforts I of the security force and to manage the operation of the security system. l O 1.5.5.4 I I lTheTrainingSuperintendentisresponsibleforthetrainingand l retraining of plant personnel and of Little Rock General Office personnel l as established by Plant procedures. l l l Manager, Nuclear Quality Control l1.5.6 I I The Managar, Nuclear Quality Control (Figure 5)'is responsible for l l verifying the implementation of the Quality Control Program at the plant l and reports to and receives direction from the General Manager. The l l Plant Quality Control department shall have sufficient authority and l organizational freedom to: identi y .luality problems; initiate, l recommend or provide solutions through designated channels; and verify l implementation of solutions. His duties include the following: I I I I I Q' l l A l I TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/21/85., l 9 l & 1 SECTIGN: 1.0 ORGANIZATION lPAGE 1-19 l j l L l l l 6 l l l l
1 I I I l 1) Provide technical direction and administrative assistance to 1 p I the: I y i I l l
- a. Quality Control Engineering Supervisor
- b. Quality Control Supervisor l
l l
- c. Quality Control Engineers l l l d. Quality Control Inspectors l l l l l l 2) Interface with the Quality Assurance Manager or his l representative for technical assistance in resolving l
l significant conditions adverse to quality. I I I I I l 3) Authority to place an item in a nonconforming status when such I l an item is determined to be in violation of purchase documents, l l applicable codes and standards or FSAR requirements. l l l l- l l 4) Assuring surveillances, inspections and reviews of plant l' ( activities and documents are conducted in accordance with plant procedures. l l \p. l l I l 1 l 1.5.7 Special Projects Manager l l l l l l The Special' Projects Manager is responsible for the administration and l control of special projects pertaining to plant operations, maintenance l l 'and administration and is to provide technical direction and l administrative guidance to a staff of Special Project Coordinators. I Additional duties include: I I l l l l 1) Serving as chairman of the Plant Safety Committee i I l l l l 2) Interfacing with on-site regulatory agencies l 1 l 1 l l 3) Providing evaluations and recommendations to regulatory l requirements and meeting regulatory corrmitments. l l l l l > O i I A i I TOPICAL REPORT lREV. 7 l l ~P l IDATE 5/31/85 I l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-20 I I L I l l l l l l
l l l l l 1.5.8 Wcrk Control Center Man g l
- l l U l l The Work Control Center Manager is responsible for the I
l ' I planning / scheduling of station work activities and the maintenance of the ! I I l equipent history and associated reports. He supervises the Work Control l I Center staff and interfaces with the Operation Manager and Maintenance I I I l Manager to accomplish the scheduling of the outage /non-outage work l l activities. The Work Control Center Manager is to provide technical l I I l direction and administrative guidance to the: l 1 l l l l 1) Scheduling Supervisor l
- 2) Planning Supervisor Maintenance History Supervisor l
l 3) l l l l l l 1.6 INDEPENDENT REVIEW ORGANIZATIONS l l l 1 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 ( l established the following committees as a management tool to l
' '- independently review activities occurring during the operational phase of l
[ a nuclear plant. l l l l l l 1.6.1 Safety Review Committee (SRC) l l l l 1 l The SRC reports to the Nuclear Operations Vice President and is l l responsible for providing off-site independent reviews, and/or audits l I I l relating to: the Safety Analysis Report, Technical Specifications, l Procedures and changes thereto; unreviewed safety questions; violations, l deviations and reportable events; and any other matter involving safe l operation of the nuclear plant which the committee deems appropriate or l is referred to them by the on-site operating group. The SRC is also to l review the reports and meeting minutes generated from the Plant Safety l Committee. l l l I I I I O i l A i l TOPICAL REPORT i lREV. 7 i l l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-21 l 1 L l l l l l I I
I l l I l 1.6.2 Plant Safety Committee (PSC) l I O I I I l The PSC reports to the plants' General Manager and is responsible for l lreviewingactivitiesspecifiedintheAdministrativeTechnical l l Specifications for the purpose of: I I I I I i 1) Rendering determinations in writing with regard to whether or i not an unreviewed safety question (defined by 10CFR50.59) is l l involved; and I I I I I I 2) Furnishing written recommendations to the plants' General i Manager for approval of disapproval. l l l l These activities include changes to plant procedures and Technical l l Specifications, proposed modifications to plant systems, changes to l l plant security and emergency plans, and review of facility I operations to detect potential nuclear safety hazards, l I ' I I I 1.6.3 Committee Structure l I l The organization structure and administrative requirements specific to l each committee are described in the plants' Technical Specifications and l l in internal procedures / documentation. 1 I I I I I 1.7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES l l l
; I I l As owner and operator, AP&L assumes full responsibility and authority for l ltheplantincludingactiontoassurethattheplantisoperatedin l l accordance with sound engineering practices, Licensing requirements and I applicable codes, specifications and procedures.
l l l lEachsupplierofequipment,materialorservicesandeachmaintenanceor l l modification contractor is responsible for administering the applicable l lqualitycontrolfunctionsasrequiredbyAP&L. The Quality Assurance and l l l 1 I O' i l A i l TOPICAL REPORT i 1REV. 7 i l l P l lDATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION lPAGE 1-22 l l L l l I I I I I
1 I I i l Quality Control organizations are responsible for assuring by l .w l surveillance, inspection,auditorreviewofobjectiveevidence(e.g., I l review audit reports conducted by others, etc.) that these functions are l laccomplishedforsystemsandstructuresthataffectthesafetyand I integrity of the plant. l l l l l l Visits to manufacturer's shops by Quality Assurance organization I personnel are conducted, when deemed necessary, based upon safety I significance, complexity, method of acceptance and past history of the I vendor, to establish product quality and to assure that quality assurance l and quality control programs function in accordance with AP&L I requirements. l l l l lTheAP&LEnergySupplyOrganizationalChart(FigureF-3)showsthe I reporting relationships and the lines of communication established l lbetweentheQualityAssuranceandQualityControlorganizations. These I lines of communication are established between the various quality l l organizations in order to provide assistance and/or information, when I requested, in verifying satisfactory implementation of the quality l lprogramandinresolvingsignificantconditionsadversetoquality. I I ' I I I I I
' I I
I I l I , I I I I I I I I I l l l l 1 I I l 1 I I I I I I I I I l l I I I I I A I TOPICAL REPORT IREV. 7 P l l 10 ATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION IPAGE l-23 I I L I l l 1 I I I
,, _ _ - - - _ _ _ _ , __m-- v.-- -, .-- , - -
I I I l l 2.2.2 l l l l
=Q- l The quality program for transport packages is addressed in Appendix A of l l
lthismanual,andimplementedthroughapp{opriateLRGOandplant l procedures. Theeffectivenessofthisprograq.isverifiedthrough l scheduled audits conducted by the QAO, under the cognizance of the SRC. l 1 l I 2.2.3 I l l I I The quality program for fire protection is addressed in Appendix B of l this manual and in the applicable sectiori of the FSAR for each operating l nuclear unit, and implemented through appropriate LRGO and plant procedures. The effectiveness of the fire protection program is verified l l l through scheduled audits conducted by the QA organization, under the cognizance of the SRC. l l l l 1 l i l l 2.2.4 l l . I I l l The Q-list is under the control of the Licensing Manager. The Licensing l O l Section maintains an up-to-date list of personnel issued a copy of the i , l Q-list and assures that reviews, approvals and distributions of the l Q-list and changes thereto are performed in accordance with approved procedures. Changes to the Q-list require review / approval by the l l l discipline Engineering Manager, Quality Assurance Manager and Licensing l l Manager. l l l l l l 2.2.5 l l 1 1 I l The following expendable and/or consumable items are to be controlled in l the following manner to assure service quality:
~
l l I I 1. Diesel Fuel - Service quality is assured by applicable l l provisions / tests required by the Technical Specification for l each operating nuclear unit. l 1 l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-2 l ! l L. l l l l l l l I
I I I I l 2. Welding Rod - Service quality is assured by procurement from an l l evaluated source, requiring material test results when b l specified by the ASME Code or applicable design document, and l l controlling the rod on-site prior to use, to prevent l degradation. l 1 I I I l 3. Boric Acid - Service quality is assured by procurement from an l l evaluated source, requiring a batch analysis to assure conformance with our specification requirements, and on-site l l l l control prior to use, to prevent degradation. I I I 2.3 RESPONSIBILITIES I I I I I l'2.3.1 l l l lAP&Lrecognizesthatqualityassuranceisaninterdisciplinaryfunction involving many organizational groups, encompasses many functions and l l l lactivitiesandextendstovariouslevelsinallparticipating l organizations (from the Energy Supply Senior Vice President to all O l L./ I y workers whose activities may influence quality). This quality program I g l designates responsibilities and duties of specific individuals, which may l lbeperformedbytheirappointeddesignees. I I l23.2 l l l This quality program assigns the responsibility for quality to the l l departments performing the work and includes as a basic requirement that l , individuals responsible for verification of conformance are qualified and j do not perform or directly supervise the work. Additionally, independent l reviews, audits and surveillances are provided by individuals not l l reporting to the groups responsible for performing the work. l l l l 1 I I I I 1 l l I I I (l v l A I TOPICAL REPORT I I I I lREV. 7 l l P l lDATE 5/31/85 l l & I SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-3 l l L l l l l l l l
I I I I l 2.3.3 l 1 I l Q- l This quality program also includes provisions that require suppliers, 1 l contractors, subcontractors, consultants,etc.tomaintainanduse l l
- l quality assurance programs reviewed and approved by the Quality Assurance l Manager. Audits or surveillances by the QA0 provide assurance of l compliance with applicable procedures. l l l l l l 2.3.4 l 1 1 I I l The Nuclear Fuel Supervisor within Nuclear Operations is responsible for l ltheassurancethatnuclearfuelusedinAP&Lnuclearplantsisdesigned, l l procured, manufactured, and utilized in accordance with regulatory l requirements, and related industrial codes and standards. On-site l
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 l l those individuals qualified to perform receipt inspections. O i I l i I l 2.4 PROCEDURES l l l l I l 2.4.1 I I 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 l procedures state the policies and instructions necessary ta fulfill the l intent of the program. Procedures provide for standard forms, lists, and l l check-offs used in documenting the inspections, certifications, reviews, l 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 l l instructions are contained in the documents listed in Table 3. l l l l l l l l l l I I i (] l A l TOPICAL REPORT lREV. 7 l l F l lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-4 l l L l l l l l l _l
r l l 1 I I 2.4.2 l 1 I Q l l Procedures. assure that activities affecting quality are performed under l l suitably controlled' conditions. Controlled conditions include the use of l l appropriate equipment; suitable environmental conditions for performing l ltheactivitysuchasadequatecleanness;andassurancethatrequired l l prerequisites for the given activity have been satisfied. Administrative l lproceduresalsoassurethattheneedforspecialcontrols, processes, l l test, and equipment to attain the required quality and the need for l lverificationofqualitybyinspections,evaluationortestistakeninto l l account. l 1 1 I I I 2.4.3 l 1 1 I l l Other AP&L organizations outside of Energy Supply may establish written l procedures to control support activities affected by the requirements of l l this quality program. Procedures developed by such organizations are l l_preparedandreviewedfortechnicaladequacywithinthecognizant l I organization, reviewed by the Quality Assurance Manager and approved by l lthecognizantorganization'sdepartmenthead. l l l l2.5 PROGRAM REVISION AND CONTROL l l l l2.5.1 l l l lProgramrevisionandcontrolshallbetheresponsibilityofthe' Quality l l Assurance Manager. l I I l l l 2.5.2 l l 1 I I l Proposed changes to the Quality Assurance Program for Operations are to l lbe'subiaittedbytheQualityAssuranceManagertoaffectedLRGOandplant l l I r I l l l l l A l TOPICAL REPORT lREV. 7 l p l lDATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-5 l l L l l l l l I I
I I I I l management personnel for review and comment prior to approval and l I transmittal to the Nuclear Regulatory Commission. After resolution of I l comments, changes are to be approved by the Quality Assurance Manager, lEnergySupplyServicesDirector,andtheEnergySupplySeniorVice l President. l l l l l l l 2.5.3 l l 1 l l l The Nuclear Regulatory Commission is to be notified of changes to this l lqualityprogramannuallyforthosechangesthatdonotreducethe l commitments in the program description previously accepted by the Nuclear l l Regulatory Commission. Changes to the program description that reduce l the commitments are to be submitted and approved by the Nuclear l l Regulatory Commission prior to implementation. The Quality Assurance l Manager is to determine if changes do or do not reduce the commitments of l l lthisqualityprogram. I I I " 2.6 PERSONNEL I l l I O () l 2.6.1 l g l l lEmployeeswhosedutiesandresponsibilitiesarerelatedtothequality l l program activities at or in support of the nuclear plant are to l participate in appropriate indoctrination and training programs to assure l l that suitable proficiency is achieved and maintained in the work they are l performing. Such training shall include, as a minimum: plant security; l l discussion of the overall Company policies, procedures and instructions l which establish the quality program; an explanation of the AP&L quality l l organizations; and a discussion of those procedur2s which implement the l quality program related to the employee's specific job-related activity. I I l l 1 1 I I l 1 1 I I I l_ l A l TOPICAL REPORT REV. 7 l l P l 10 ATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 l l L 1 l l l l l 1
l I. I I I 2.6.2 I I I Q l l The education, experience and responsibility requirements of individuals l l linvolvedinthisqualityprogramaredocumentedinjobdescriptionswhich l l are caproved and periodically reviewed by management. Requirements for I education, experience and proficiency levels are commensurate with the l l degree of importance of the job assignment. Experience and training l lrequirementsforplantstaffpersonnelaretomeettherequirementsof l l ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted I
.linTable1. Personne'l whose qualifications do not meet those specified l l in ANSI N18.1-1971, and who are performing inspection, examination and l ltestingactivitiesduringtheoperationalphaseoftheplant,aretomeet l l the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. I I I I I I 2.6.3 I I I I l l Personnel performing inspection and examination activities are to be l l indoctrinated and trained to assure they are aware of the requirements I which govern their activity. Inspection and examination personnel are to l lbequalifiedaccordingtotheapplicablecodes, standards, l l specifications, regulatory requirements and LRGO and plant procedures. l lPersonnelperforminginspectionsonthoseactivitiesoccurringduringthe l l operational phase that are comparable in nature and extent to related l lactivitiesoccurringduringinitialplantdesignandconstructionareto l l meet the provisions of Regulatory Guide 1.58, rev. 1 (9/80) and ANSI I lN45.2.6-1978, in lieu of ANSI N18.1-1971. l l 1 l2.6.4 l l 1 lPersonnelinvolvedwithweldingofmaterials,systemsorcomponentsare l l to meet the appropriate qualification requirements of the ASME Boiler and l lPressureVesselCode,SectionsIIIandXI,orforstructuralwelds,the l l l l l l l l l l l
'O I I A I
l TOPICAL REPORT I IREV. 7 l l l P I lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-7 I I L I l l l l l l
I i I l l American Welding Society (AWS) Structural Steel Code D. 1. Personnel l g involved with nondestructive examination of materials, components'or l systems are to meet the qualification requirements of the American l lSocietyNondestructiveTestingStandardSNT-TC-1A,orASMESectionIII l and XI for ASME Code materials, components or systems. Personnel are to l be certified to perform these tasks in accordance with these codes and l standards. l l 1 l l l 2.6.5 l 1 1 1 I l Personnel performing audits of the quality program are to meet the l experience, training and qualification / certification requirements of l ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), i cw otherwise l l I lnotedinTable1. I I 2.6.6 1 l l lTrainingrecordsaretobemaintainedinaccordancewithapproved procedures. For formal training programs, documentation is to include l l O j the o83ective, centent of the progrem, attendees, end date of attendance. l l l l 2.7 PROGRAM REVIEW l l l l2.7.1 l l l lTheQualityAssuranceManagerisresponsibleforareviewofthisprogram l l on an annual basis to determine the effectiveness and proper l implementation of the quality program. l l l I 2.7.2 l 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 I I
- 1. I I A l TOPICAL REPORT IREV. 7 l p
l l lDATE 5/31/85 l
! & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-8 I I L I I I I I I I
1 I I 1 I -through reviews of quality assurance audit reports. Quality Assurance ! freportssupplydataonthestatusofoutstandingauditandcorrective O, I action items and may identify the status of other significant quality I fprogramactivitiesasrequestedbymanagement. I I I I I I I I I I I I I I I I I I I I I I
, I I I I I I
-l l I I I I I I i i l l I I I I I
I I I I I I I I I I I I I I I I I I I I I I I I I ! I I . I I I I i I i I 1 l I I I I I I i I I l' I I [ A TOPICAL REPORT E 5/31/85 l i l & I SECTION: 2.0 QUALITY ASSURANCE PROGRAM iPAGE 2-9 l L l l I l l 4 _ . _ _ _ _ . . . . _ _ . . . . _ . _ . _ . _ . _ _ . _ . _ . _ . _ . _ _ . _ . . . . _ . - _ _ _ _--
I I I- I l 3.2.2 s l I l O ' l Design standards and requirements are to be at least equivalent to those i l lemployedduringtheconstructionoftheplantandaretobeconsistent l l with the technical specifications and license requirements. l I I I I I 3.3 DESIGN INTERFACE l l 1 I I l Design control activities include measures for the identification and l lcontrolofdesigninterfacesbetweenthevariousengineeringdisciplines l
- l. within the department, between LRGO and plant engineering personnel, I l between engineering personnel and other AP&L support organizations, and l I
l between engineering personnel and firms / suppliers outside the AP&L l I I I organization. These measures include the development of procedures among ;
'l the participating organizations for the review, approval, release, I ldistributionandrevisionofdocumentsinvolvingdesigninterface.
I Coordination of the interface control is the responsibility of the I originating organization's management unless otherwise specified in an l l AP&L procedure applicable to the design activity. Design information 1 O i l between interfacing organizations is to be documented and retained for ; i I permanent records. 1 I I l l I 3.4 DESIGN VERIFICATION l , I I I I i l 3.4.1 1 1 I i l I L I To assure the design is adequate and the above requirements and l
. procedures are implemented, Engineering Services for LRG0 design or Plant l
l Engineering for plant design are to verify the adequacy of the design I i f lthroughtheperformanceofdesignreviews,theuseofalternateor l
'l simplified calculation methods, or the performance of a qualification l l l l l I l
i I . I l
- 1 I I l l
- .I I i O i l A I
I TOPICAL REPORT IREV. 7 l i- 1 p I IDATE 5/31/85 l
- & 3.0 DESIGN CONTROL IPAGE 3-2 I
-l 1 SECTION:
I L l l I I I I I
I l l I I testing program. The extent and depth of design verification performed l g by the responsible organization is determined by an assigned engineering I reviewer based upon the importance and complexity of the design, the l degree of standardization and its similarity with proven designs. In all l l cases, the design verification is to be complete prior to relying upon I the component, system or structure to perform its function. l l l l3.4.2 l l I lTheverificationprocessistobeperformedbycompetentindividualsor l l groups other than those who performed or supervised the design but who l lmaybefromthesameorganization. This verification, however, may be l performed by the originator's supervisor in accordance with departmental l l lproceduresifheistheonlyindividualintheorganizationcompetentto l perform the verification and provided the need is individually documented l l landapprovedinadvancebytheresponsibleManagerorSuperintendent. l The frequency and effectiveness of use of Supervisors as design verifiers l l listobeverifiedbyQAthroughscheduledauditstoguardagainstabuse. l l 'dhere changes to previously verified designs have been made, design l lverificationsarerequiredforthechange,includingevaluationofthe l effects of the changes on the overall design. l I I I I I l 3.4.3 l l l l 1 I When a test program is used to verify the adequacy of a design, it is to l l include suitable qualification testing of a prototype or initial l
; I production unit under the most adverse conditions and carried out in l laccordancewithdocumentedproceduresand/orinstructions. Testing is to l be performed as early as possible prior to installation of plant l
i equipment, or prior to the point when the installation would become l irreversible. l 1 I I I ' f I I I I I I I I I I O V I I I I i A l TOPICAL REPORT 7 lREV. l l P I lDATE 5/31/85 l l & l SECTION: 3.0 DESIGN CONTROL IPAGE 3-3 I I L I l l l 1 1 I
l l l l l accomplished. Each procedure is to be sufficiently detailed so that a l I qualified individual may perform the required function (s) without direct I supervision and is to include measures to document the activity being performed. l I I 5.2.2 l l l lToassuretheaccomplishmentofactivitiesinaccordancewithapproved l instructions, procedures and drawings, each supervisor is responsible for l l quality compliance of his personnel. Verification that activities are l accomplished in accordance with approved instructions, procedures and l l drawings is obtained through various levels of surveillance and l l l inspection by Quality Control personnel and through periodic surveillance l landauditsbytheQA0. I l 1 5.3 REVIEW 0F INSTRUCTIONS, PROCEDURES AND DRAWINGS l l l
- 5. 3.1 l
l 1 O l Instructions,preceduresenddrewingsereprepered,reviewedeedepproved j l in accordance with applicable plant administrative procedures, when l lorigina'.edattheplant,orinaccordancewithapplicableEnergySupply l l procedures, when originated from LRGO. I I I I I l 5.3.2 l
' l l I I l Plant procedures identified in the Technical Specifications for each unit l landchangestheretowhichdescribeactivitiesrequiredtoimplementthis l quality program are to be reviewed by the PSC prior to submittal of the i I
procedures to the plant General Manager for approval and subsequent l l issuance. Plant Administrative procedures (1000.XX Series) are also l reviewed by the Quality Control staff to verify compliance to AP&L's l l 1 I I l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l l L l AND DRAWINGS l l l l l 1
I I I l c l quality program requirements. .LRGO Energy Supply procedures describing l lactivitiesrequiredtoimplementthisqualityprogramaretobereviewed l
~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
l submittal of the procedures to the Department Head responsible for l-l implementation,forapprovalandsubsequentissuance. l l l l5.3.3 l l l lPlantandLRGOproceduresandinstructionsaretobereviewednoless l l than every two years to determine if changes are necessary to r.aet NRC l lcommitmentsandcurrentAP&Lpractices. Applicable procedures (i.e. l those that relate to the incident cause) are to be reviewed following an l lunusualincidentsuchasanaccident,unexpectedtransient,significant l l operator error or equipment malfunction. Applicable procedures are also l ltobereviewedfollowinganymodificationtoaplantsystem. l l 1 l-5.3.4 l Drawings related to plant changes and modifications are controlled as l described in Section 3 and 6 of this manual. l l l 1 I
! 5.4 CHANGES TO PROCEDURES l l 1 l l l 5.4.1 1 I I I I l Changes or revisions to approved instructions, procedures and drawings l laretobereviewedandapprovedbythesameorganizationsorgroupsthat l l performed the original review unless otherwise noted in specific AP&L l lproceduresandcontrolledinthesamemannerastheoriginal. l
-l I n
i I l l t i I ^ l I l l l l i l l I O I l A I l TOPICAL REPORT I lREV. 7 I l j l P. - l lDATE 5/31/85 l l & l.SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-3 l l L l AND DRAWINGS l l
! l l l l i
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I I I I l 5.4.2 I I I
'T l (V I Temporary changes to approved plant procedures which do not change the l
I 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 I reactors operators license on the unit affected and the change is documented, reviewed by the PSC, and approved by the plant's General l l l lManagerwithin14daysofimplementation. Temporary changes to approved plant procedures which change the intent of the procedure may be made l l I provided such changes are reviewed by the PSC and approved by the plant's General Manager prior to implementation. Temporary changes to approved l l I lplantproceduresaretospecifytheperiodoftimeduringwhichtheymay l l be used and made readily available to affected members of the plant l l staff. In the event of an emergency not covered by an approved I procedure, operations personnel may take action, without obtaining I l approvals,soastominimizepersonnelinjuryanddamagetothefacility l l and to protect health and safety. I I I I I I I O i I i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 1 I I I I I I l l l 1 (~)
's-I I A I
I TOPICAL REPORT I IREV. 7 I I l P 1 IDATE 5/31/85 I l & 1 SECTION: 5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-4 I I L I AND DRAWINGS I l l l l I
I I I I I approved historical plant documents, and the storage of historical l g ldrawingrecords. The Engineering and Technical Support Manager is O l responsible for the control and issuance of drawings and revisions l l ltheretotoassurethattheyreflecttheas-builtconditionsoftheplant. l l l l6.3 IDENTIFICATION I I lDocumentsaretobeidentifiedbyatitledescriptiveoftheirpurposeor l applicability and marked or stamped as to their current status (Draft, l l l For Information Only, Void, etc.) per departmental procedures. Revision l status of document is to be identified in document registers, l l distribution lists and/or within the revision record page/ block of the l document. l l l l l l l 6.4 DISTRIBUTION I I I I I l Distribution lists and/or document registers are to be maintained by the l lorganizationresponsibleforissuanceofthedocument. These lists are , I to identify the revision status of the document and are to be reviewed l l landupdatedperiodicallybytheresponsibleorganizationtomaintainthem l in a current status. These lists are available to indi"iduals using the l l ldocumenttoassuretheyareinreceiptofthecurrentdocument. These l measures are.to preclude the possibility of using outdated or l I inappropriate documents. I I l6.5 CHANGES l 1 l l6.5.1 I I lChangestocentrolleddocumentsaretobereviewedandapprovedbythe l l same organizations which performed the original review and approval l lunlessotherwisespecifiedindepartmentalproceduresapplicabletothe l affected activity. l l l 1 1 I I l l I A l TOPICAL REPORT IREV. 7 l P l l IDATE 5/31/85 l l & l SECTION: 6.0 DOCUMENT CONTROL IPAGE 6-2 l l L l l l l l l l
I I I I I 7.2.2 l l l l b^ l Vendors / Contractors are evaluated and placed on the QVL by any of the I l l following methods, as approved by the Quality Assurance Manager: l l l l(1) Source survey by AP&L to verify compliance to applicable 10CFR50, l l Appendix B requirements or to applicable ASME Section III Quality I l Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG l components). l l 1 I I l l (2) Evaluation and acceptance of source surveys performed by others l l (ex. CASE, other utilities, NSSS suppliers, and prime contractors) l indicating a program meeting the appropriate requirements of l l 10CFR50, Appendix 8. (This method is not applicable for ASME l procurements.) l l I I I I l (3) A review of the vendors / contractors current quality records l l supported by evidence of documented qualitative and quantitative l information which can be objectively evaluated. This includes l O l l review end epprove, of the veeder's/ceetrector's neeisty essurance l program, manual and procedures, when available. (This method is not l l I applicable for ASME procurements). l 1
, (4) Evaluation of the vendor's/ contractor's history of providing a l product / service which performs satisfactorily in actual use.
l l l Evaluation information includes: experience of users of identical l l or similar products / services of the prospective vendor / contractor; l and/or procurement records that have been accumulated in connection l with previous procurement activities and operating experiences. l l l (This method is not applicable to ASME procurements). l l l l(5) Verification that a vendor is a holder of an ASME Certificatelof l Authorization issued as a result of an ASME survey may be used in l lieu of method (1) for ASME procurements. l l l l l pV I I I l I l A l TOPICAL REPLRT 7 lREV. l l P l lDATE 5/31/85 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-2 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l I l l
I I I I I (6) Verification that a contractor is a holder of a NRC letter l l confirming QA program implementation may be used in lieu of I method 1. l l l 1 I l 7.2.3 I I I I I I Vendors / contractors listed on the QVL are to be selected for procurement I of material, equipment or services except for items designated l " commercial grade" per plant and LRGO procedures and as noted in l l paragraph 7.2.4. Standard catalog items may be procured from a l l l vendor / contractor not listed on the QVL provided the manufacturer of the l litemisontheQVLandallAP&Lrequesteddocumentationoriginatesfrom the manufacturer. l l The QVL is to be periodically reviewed and updated per l lqualityassuranceprocedurestoensurethecurrentstatusofqualified I vendors / contractors is available to personnel involved in the procurement l process. l l l l 1 7.2.4 l l 1 Tl V l lServicesbycontractorswhichprovideonlytechnicalguidance/supportor g l which require work activities to be performed under the scope of the AP&L l l QA Program may be furnished by contractors not listed on the QVL. The l l contractors work activities and personnel are to be controlled in l laccordancewithLRG0/plantprocedurestoassurethatthecontractor I conforms to the procurement documents. l I I I I l 7.3 SOURCE SURVEILLANCE AND AUDIT l l l l 1 l 7.3.1 l l l l l l The effectiveness of a vendor's/ contractor's quality assurance program is l lassessedbyQApersonnelatintervalsconsistentwiththeimportance, l l l l l l l l l l l i I I CQ l A l TOPICAL REPORT lREV. 7 l l P I lDATE 5/31/85 l l & 1 SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-3 I I L I MATERIAL, EQUIPMENT AND SERVICES l l l l 1 I
I I I I
% l complexity, method of receipt and quantity of the products or services. I g This assessment may be through source surveillance, source audit, receipt C l inspection, independent testing or review of source documentation files.
l l l l l l l 7.3.2 l l l l l l Requests for source surveillance are made by the originator of the PR/ l l Contract,and/ortheresponsibleQualityControlorQualityAssurance l l organization during their review of the procurement document (reference l lsection4.3) Source surveillance is to be performed by QA personnel or l l their appointed representative in accordance with surveillance plans l lapprovedbytheQualityAssuranceManagerandtheresultsdocumentedper i quality assurance procedures. Reports documenting inspections performed .' landdiscrepanciesobservedarepreparedbythepersonperformingthe l l surveillance to document compliance to the procurement documents and for I future use as historical quality performance data. l l l l7.3.3 l l l l Audits of the vendor's/ contractor's quality assurance programs are l l periodically performed under the direction of the Quality Assurance l lManagertoverifyimplementationofasatisfactoryqualityprogramonthe l l items or services being procured by AP&L. Audits performed by others l l(e.g., CASE,otherutilities,orprimecontractors),asevaluatedand l l approved by the Quality Assurance Manager, may be used as an alternative l
;N ltoauditsbyAP&Ltoverifythevendor/contractorisimplementinga l l satisfactory quality program. Audits are to be conducted in accordance I with Section 18 of this manual. (This alternative method does not apply l
l' to ASME procurements.) l I I i i l I . l l l l l l l l l l 1 I I I I l A I TOPICAL REPORT lREV. 7 l P l lDATE 5/31/85 l l & l SECTION: 7. 0 CONTROL OF PURCHASED IPAGE 7-4 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l l l
l l 1 I I 7.4 RECEIPT INSPECTION l l 1 7.4.1 l l l l l l Materials and equipment, including ASME Code materials and equipment, are l lsubjecttoinspectionuponreceiptattheplant. The degree of l inspection is specified in the procurement documents and is to be l lperformedinaccordancewithplantproceduresforreceiptinspection. l l l l7.4.2 l l l
'lReceiptinspectionactivitiesaretobedocumentedandinclude,asa l minimum:
l examination of material or equipment for shipping damage, l l proper identification, and quantity; and the review of vendor documentation, to verify compliance with the procurement document. l l In l l addition,ifmaterialandequipmentreceivedattheplantwerenot l l inspected at the vendor's facility by AP&L, an inspection is to be l lperformedbyaQualityControlInspectoratthepointofreceivingto l l l verify that the material or equipment conform to the inspection l O lrequirementsidentifiedintheprocurementdocuments. l l l l7.4.3 l l l Vendors are to furnish documentation as required by the procurement l l documents for objective evidence that the material or equipment conforms l l.totheprocurementrequirements. Review and acceptance of this l l documentation is to be performed by a Quality Control Engineer prior to l linstallationoruseofsuchmaterialorequipmentanddocumentedunless l l otherwise specified in plant procedures. Certificates of Conformance may l lberequiredbyprocurementdocumentswhichidentifytherequirementsmet l l by the vendor. The validity of the vendor's certification program is to l lbeperiodicallyverifiedthroughscheduledsourcesurveillanceandaudit l l activities or through independent testing of the item by AP&L. l l l l l l l l l O I l A I l TOPICAL REPORT I lREV. 7 I l l P l lDATE 5/31/85 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-5 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l l l
I I I I l 7.4.4 l l l l i (Va l Accepted material and equipment is released, identified as to its l linspectionstatusandforwardedtoacontrolledstorageareaorreleased l l for installation per applicable plant procedures. l l l l l l 7.4.5 l l l l l l Acceptance of services furnished by a contractor is to be identified in l ltheprocurementdocuments. Depending upon the service performed, l l acceptance may be by technical verification of the data produced, I lsurveillanceand/orauditoftheactivity,orreviewofobjective l l evidence for conformance to the procurement document requirements. The l lacceptancemethodistobeperformedbyqualifiedindividuals l l knowledgeable in the service provided. I I I l l l 7.4.6 l l l l l l Independent testing of selected material is to be performed in accordance l with plant procedures / instructions to verify conformance to procurement l l criteria and the validity of the vendor's certification documents. l 1 l l l l 7.5 NONCONFORMING ITEMS I I I l l 1 7.5.1 I i i l I l l Nonconformances identified by the vendor / contractor which adversely l laffectreliability,performanceorinterchangeabilityoftheitemand l dispositioned repair or use-as-is are to be submitted to and accepted by l lAP&Lpriortoclosureofthenonconformancebythevendor/ contractor. l l These nonconformances are to be documented and become part of the l lprocurementdocumentationfurnishedbythevendor/contractorforthe l l material, equipment or services procured. l l l l l l 1 l l l A I TOPICAL REPORT IREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-6 l l L l MATERIAL, EQUIPMENT AND SERVICES l l 1 I I I
s l I I I l 7.5.2 l l l l Material and equipment found to be deficient or missing procurement l ldocumentationduringreceivinginspectionorfoundtobedeficientasa l result of independent testing is to be clearly identified, segregated l from acceptable items and dispositioned per plant procedures and as l described in Section 15 of this manual. l l l l l l 8 7.6 SPARE PARTS l l l l 1 l Spare parts are to be purchased to the original design requirements or to l lthosespecifiedbyaproperlyreviewedandapprovedrevisiontothe l design requirements. The applicable quality assurance requirements and l l ldocumentationrequirementsforsparepartsaretobeincludedinthe l w urement documents. l l I I I I l 't . / STORAGE l l l l 1 l Material and equipment are to be handled and stored as described in plant l O lproceduresandSection13oftnismenuei. l l l l 1 I I I I l l 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 I I I I l l r3 1 1 1 I V l A l TOPICAL REPORT IREV. 7 l P l l IDATE 5/31/85 l I & 1 SECTION: 7. 0 CONTROL OF PURCHASED [PAGE 7-7 l l L I MATERIAL, EQUIPMENT AND SERVICES I l l l l l
I I I l l 9.0 CONTROL OF SPECIAL PROCESSES l l l G l U l 9.1 SCOPE i I i l 1 l l Special processes are to be controlled through the use of qualified l lpersonnelandplantprocedureswhichmeettherequirementsofapplicable l l codes, specifications, standards and other criteria stipulated in AP&L l llicensingdocuments. l l l l9.2 GENERAL l l l 9.2.1 l l l lSpecialprocessesarethoseactivitieswhichrequireinteriminprocess l l controls in addition to final inspection to assure quality and include l lsuchactivitiesaswelding,nondestructiveexamination,heattreating, l l coating, plating and chemical cleaning. l l l l l l 9.2.2 O l I l l ' l 3 I Technically qualified LRGO or plant personnel are to establish the l lproceduralandqualificationrequirementsforthosespecialprocessesnot l l cov? red by existing codes or standards or where AP&L quality requirements l exceed the requirements of established codes or standards. l l l l9.2.3 l l l lTherequirementsforweldingandnondestructiveexaminationaretocomply l l with the applicable portions of the ASME Boiler and Pressure Vessel Code l lorforstructuralwelds,theAWSStructuralSteelCodeD1.1,andthe l l American Society of Nondestructive Testing (SNT-TC-1A and supplements). l lTherequirementsforcleaningandflushingoffluidsystems'aretocomply l l to the requirements of NRC regulatory guide 1.37, dated 3/16/73 unless l I lotherwisenotedinTable1. g i i 1 _I A I TOPICAL REPORT lREV. 7 l l P l IDATE 5/31/85 l l & l SECTION: 9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-1 l l L l l l l l l I
I I l I l inspections and monitoring activities were performed in compliance with I procedures, instructions or drawings to verify design requirements; show l l compliance with acceptance criteria or identify the cause of rejected i l items;andidentifytheappropriateinspectionpersonnelapprovingthe l l results. I I l l I i 10.5.2 I I I I I l Records are to be maintained in accordance with plant procedures and l lSection17ofthismanual. Inspection results on ASME Code items are l l available to the Code Inspector for his review. I I I I I l 10.5.3 I I l l l I The results of all inspection and monitoring activities are periodically l levaluatedperplantproceduresandtheresultsdocumentedtodetermine l l whether the individual inspection programs demonstrate that the plant can I be operated safely and as designed. 1 l l l10.6NONCONFORMANCES l l l l Noncomforming items found as a result of inspection and monitoring l l activities are identified, segregated and dispositioned in accordance l lwithplantproceduresandSection15ofthismanual. Rework, repair or l l replacement performed after completion of inspections are to require l lreinspectiontotheextentnecessarytodetermineacceptabilityto l l established criteria. 1 I I I I I l 1 1 I I I I I I I I I l i I I I I I I I n i I I I V l A l TOPICAL REPORT IREV. 7 I l p I IDATE 5/31/85 l I & 1 SECTION: 10.0 INSPECTION IPAGE 10-6 I l L I l l l I I I
I I I I l have been satisified. Nonconforming conditions, are to be identified l l and controlled in accordance with Section 15 of this manual. l l I l11.4 RECORDS l 4 l lTestresultsaretoprovideobjectiveevidencethatthetestingwas l performed in compliance with approved procedures. Test records are to be l lmaintainedandtransmittedtotheplantDocumentControlCenterfor l l retention in accordance with Section 17 of this manual. l I I I I l 11.5 TEST STATUS l l l l l l Inspection and test status is to be controlled in accordance with the l lprovisionsofSection14ofthismanual. l l l l l l l l 1 I I I l i () I I l I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I l l l l l l I A I TOPICAL REPORT IREV. 7 l P l IDATE 5/31/85 I
- I & I SECTION
- 11.0 TEST CONTROL IPAGE 11-5 l l L l l l l l l l il
I I I I l documents and furnished to the plant prior to or upon receipt of the item l I I O lattheplant. l l13.3SHIPPINGCONTROLS l l l l13.3.1 l l l lShippingrequirementsaretobespecifiedintheprocurementdocuments. l l Suppliers compliance to these requirements are to include controls to l lassurethatitemsarecompleteandassembledasrequired;itemshavebeen l l preserved and packaged in accordance with the procurenent documents; I l items have been marked and identified in accordance with specifications l l and procurement documents; items have been loaded for shipment in such a l lmannerastopreventdamage;andrequireddocumentationiscompleteand l l furnished in accordance with the procurement documents. l I I I I l 13.3.2 I I I I I l Special nuclear material and sources are to be shipped and stored as l lspecifiedintheAP&Loperatinglicenseandotherappropriateregulatory l l documents. The Health Physics Supervisor is responsible for assuring l lthatradioactivesourcesandinstrumentscontainingradioactivesources l l are shipped, stored and handled per these requirements and plant l procedures. The Nuclear Support Supervisor is responsible for assuring l l l that special nuclear material (SNM), as defined in plant procedures, is l l shipped,storedandhandledpertheserequirementsandplantprocedures. l l l l13.4 RECEIVING I I l13.4.1 l l l lMaterialsandequipmentaretobereceivedattheplantperplant l l l lproceduresandsubjectedtoareceiptinspectioninaccordanc Section 7 of this manual. As part of the inspection activity, received l l 1 I l - pJ l A' l TOPICAL REPORT l 7 l l l IREV. l l P I lDATE 5/31/85 l l & 1 SECTION: 13.0 HANDLING, STORAGE AND IPAGE 13-2 l l L i SHIPPING l l l l l 1
r I 1 I I I I l in storage and to facilitate inspection and maintenance planning. I g Issuance of items from storage for installation or use are to be V l l documented and controlled in accordance with plant procedures. I I I I I l .13.5.4 I I I I . l l Items identified as requiring maintenance during storage are to be l lmaintainedinaccordancewithadocumentedmaintenanceprogram. l 1 l l13.5.5 l l l lStorageareasaretobemonitoreabyindividualsresponsibleforthe l l storage areas so that the integrity and security of stored items is l leffectivelymaintained. Inspections and examinations under the control l l of the Manager, Nuclear Quality Control are to be performed and l i ldocumentedonaperiodicbasistoassurethattheintegrityoftheitems l l and their containers are being maintained. Periodic audits under the l lcontroloftheQualityAssuranceManagerarealsoperformedtoassure l l compliance to storage requirements. I v i l l 13.6 HANDLING CONTROLS I I I I I l 13.6.1 l l l l l l Special handling requirements are to be specified in the procurement l ldocumentsandplantprocedurestoprotectthequalityofitems l l susceptible to handling damage. Special tools and equipment are to be I provided to handle these items and are to be controlled and maintained l l per written procedure to assure safe and adequate handling. I I I I I l -13.6.2 I I I I I l Special handling tools and equipment are to be inspected and tested at l specific times in accordance with written procedures to verify that the l 1 1 I I O I l A I I TOPICAL REPORT I [REV. 7 I l l P l lDATE 5/31/85 l l & l SECTION: 13.0 HANDLING, STORAGE AND lPAGE 13-4 l l L I SHIPPING l l l l l l
I I I I I- 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l l 1 (3 v' I i 15.1 SCOPE I l l l l l l Nonconforming items are to include materials, parts, components, I l processes,documentsandasapplicable, services (includingcomputer I codes) that do not conform to applicable regulations, codes, standards, I l specifications,drawingsorlicensingdocuments. Nonconforming items are l i I to be controlled in accordance with approved procedures to prevent their l linadvertantuseorinstallation. These procedures are to contain l l measures to assure the prompt identification and notification, I l documentation, segregation,technicalreview,dispositionand l l verification of a nonconforming item. l I I I I i 15.2 GENERAL l l l 1 I l 15.2.1 I I I I I l It is the responsibility of each individual to identify a nonconforming l l condition,whetherrelatedtoaproduct,processordocumentation,andto l report it to their cognizant supervisor for review and concurrence. The l l linitiatoristodocumentthenonconformanceonanappropriate l nonconformance report, per approved procedures unless the nonconformance l l lisdeterminedtobeatechnicalspecificationviolationand/orreportable l to the NRC. See paragraph 15.3 for reportable nonconformances. l l l l l l l 15.2.2 1 1 I I l l Nonconforming items are to be tagged with a hold tag, or otherwise l lidentifiedperplantprocedures,topreventinadvertantuseor l l installation of the item. Nonconforming items are to be segregated from l lacceptableitemsunlesstheyarecurrentlyinstalledortheirsize, l l l l l l l l l l l O V I I I I l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, lPAGE 15-1 l l L l PARTS AND COMPONENTS l l l I I I
1 I I I l weight, configuration, etc., makes it impractical to move to a segregated l l area. Hold tags are to remain on the item until the disposition is I b complete per plant procedures. I I I I l 15.2.3 l l l 1 l l Nonconformance reports are to identify the group responsible for l ldispositioningthenonconformance. The assigned individual within the l l responsible group is to evaluate the nonconformance and confer, as l l appropriate,withinterfacinggroupstodetermineitscauseand l l recommended disposition. The disposition, which may be reject, rework, l lrepairoruse-as-is,andthecorrectiveactiontakentoprevent l l recurrence is to be documented on the report. l 1 I l l l 15.2.4 l l l l l 1 The initiator of the nonconformance report and his supervisor are to l lreviewthedispositionforacceptancepriortoimplementingcorrective l l action. If they cannot agree with the assigned individual on the l disposition,theplantGeneralManageristodecide. For a repair or l l l use-as-is disposition, a cognizant engineer knowledgeable in the design l lrequirementsfortheaffecteditemisalsotoreviewthereportfor l
.l concurrence of the disposition. Written justification for the design l change,repairordeviationthathasbeenacceptedistobedocumentedto l
l denote the as-built condition and is to be made a part of the report. l I I I I l 15.2.5 I I I I I l The acceptability of rework or repair of materials, parts, components, l systems and structures are to be verified by reinspecting the item as l l originally inspected or by a method which is at least equal to the l original inspection method. The rework and repair inspection records are l l l , I I I I l l I I I I I I \] l A I TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l
! & 1 SECTION: 15.0 NONCONFORMING MATERIAL, lPAGE 15-2 l 1 L l PARTS AND COMPONENTS l l l l l l
l l I I l to be documented and become part of the permanent records for the item. l l Upon completion of the corrective action, the Manager, Nuclear Quality U l Control is to verify completion of corrective actions in accordance with l l plant procedures and if acceptable, close the nonconformance report. l l l l15.2.6 l 1 l l For ASME Code, Section III, Division 1 materials, parts and components l l dispositioned repair or use-as-is, the nonconformance report is to be l l subject to review and concurrence by the Code Inspector. l l l l 15.3 REPORTABLE NONCONFORMANCES l l l l15.3.1 l l l l Nonconforming items or conditions which are reportable per the Technical l l Specifications to the NRC are to be documented by the initiator and I , forwarded to the Special Projects Manager so the appropriate report, per I l ,, I u l plant, procedures, can be prepared. l , I 15.3.2 I I I I I , i Upon disposition of the report by the responsible group the PSC reviews l l the report for concurrence and possible assignment of additional l l corrective actions and forwards the report to the plant General Manager l l for final approval. l l l 15.3.3 l I I 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 I l Specifications and Licensing procedures. l l i I I I I I I I I A I TOPICAL REPORT IREV. 7 l l P I IDATE 5/31/85 l I & l SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-3 I l , L I PARTS AND COMP 0NENTS I l l l l l
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I I I I l 15.4 SUPPLIER NONCONFORMANCES l I I I (v7 i 15.4.1 I I I I I l l Procurement documents are to contain requirements for the l Vendor / contractor to identify nonconforming conditions to AP&L which l l 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 l nonconformances are to be reported to AP&L for evaluations and l
' l
,' acceptance. The vendor / contractor is to document such nonconformances on I g
, 7 hair applicable nonconformance report which is to be included in the l lfinaldocumentationpackagesubmittedtoAP&L,inaccordancewiththe l procurement documents. l I
I I I I I 15.4.2 l l l 1 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 l the nonconforming conditions have been properly dispositioned and I lacceptedbyAP&L. l 1 l l15.5 RECORDS l l 1 l15.5.1 l l l lUponcompletionofdispositionandverificationactivities,thecompleted ! I nonconformance reports, and related documents generated to ensure proper l ldispositionandresolutionofthenonconformancearetobeforwardedto l l and maintained by the Document Control Center. l l I ! I I I I l I I I I l I I I I I I I I I O V I A I I I l l TOPICAL REPORT lREV. '/ l l P l lDATE 5/31/85 l l & l SECTION: 15.0 NONCONFORMING MATERIAL, lPAGE 15-4 l l L l PARTS AND COMPONENTS l l l l l l
I I I I I i 15.5.2 I I I O I l The Manager, Nuclear Quality Control is to maintain and issue a monthly l l lreporttotheplantGeneralManager,identifyingthecurrentstatusof l all open nonconformance reports for management review. l I I l l l 1 I I I I I I I I I . 1 I i l l I I I i-I 1 I I I I I I I I I l i I I I I I I I O i l I i i I l i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I l l I I I I I O l I A i l TOPICAL REPORT I IREV. 7 I I l P I lDATE 5/31/85 I I & I SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-5 I I L I PARTS AND COMPONENTS I l l l l 1
1 I I I i 16.0 CORRECTIVE ACTION l l l . I 16.1 SCOPE I I I l l l A corrective actions system is to be established to assure that l lconditionsadversetoplantsafety,suchasfailure, malfunctions, l deficiencies, deviations, defective material and equipment, abnormal l I occurrences an'd nonconformances are promptly identified and corrected. I In the case of significant conditions adverse to safety, this system is l ltoassurethatthecauseoftheconditionisdeterminedandcorrective l
- l. action taken, documented and reported to appropriate levels of management l lforindependentrevie.
1 l l l16.2 GENERAL l l l 16.2.1
-l l lWhendeviations, deficiencies,malfunctionsorotherabnormaloccurrences l or conditions are encountered, they are to be reported to responsible.
l I O leetheritiesforrevieanddisPesitionineccordancewithSection15of l l this manual. l 1 I I I
'l 16.2.2 I
I I I I l Cognizant supervisors are to review discrepancies discovered during the l lcourseofstationoperations,andinthecaseofsignificantconditions l adverse to safety, initiate action to identify their cause and take l l necessary corrective action to prevent their recurrence. Corrective l action measures to resolve the discrepancies and to prevent their I recurrence are to be documented in accordance with Section 15 of this 1 manual. l 1 l l I i 1 I I I I l i I I I
- O lA P
! TOPICAL REPORT REV. 7 1 l lDATE 5/31/85 I I & l SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-1 l
, I L 1 l l l l l l
I I I l l 18.3.2 l 1 I O I V l Audit schedules assure that as a minimum, those audit areas identified I l lwithintheTechnicalSpecificationsapplicabletoeachnuclearunitare l l audited, under the cognizance of the SRC, at the indicated frequencies I within AP&L. l l l l18.3.3 l l l Audits of vendor / contractor activities are to be scheduled as identified l i1 Section 7, paragraph 7.3.3 of this manual. These audits are to l l I evaluate and verify their quality assurance program, procedures and f I activities, to assure compliance with the procurement documents, and to l l verify they periodically review and audit their suppliers quality l assurance program. l I I I I I I 18.3.4 l l l 1 l l Periodic reviews of the audit programs are to be performed by the SRC or l O ltheireppointedmenegementrepresentetiveetieestsemi-enneeiiyto l l assure that audits are being accomplished in accordance with the l lrequirementsofthetechnicalspecifications,thismanualandRegulatory l l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1. I I I l I l 18.3.5 l l l l l l Regularly scheduled audits may be supplemented, as required, to cover l lunforeseeneventsorchangedrequirements. l 1 I I I I I I I I I I I I I I I I I l l l 1 O I I l l V I A l TOPICAL REPORT lREV. 7 l l P l IDATE 5/31/85 l l & 1 SECTION: 18.0 AUDITS lPAGE 18-3 I I L l l l l l I I _I
I I l l l 18.4 AUDIT IMPLEMENTATION l l 1 f3 I U l 18.4.1 I l l l 1 l l Audit plans and checklists are to be prepared by the auditor and approved I by the Quality Assurance Manager prior to performing the audit. l l Checklists are to be used during the audit to assure that all l lrequirementsoftheactivitiesauditedareaddressedduringtheauditand that those procedures and instructions issued to control the audited l l l lactivityareadequate. l l l l18.4.2 l 1 - l lUponcompletionofanaudit,awrittenreportistobepreparedwhich l l includes at least the following items: l l
- l I I I (1) Description of audit scope and date. l l (2) Identification of the auditor (s). l q l (3) A summary of audit results. I V (4) Details of nonconformances or programmatic deficiencies.
l l (5) Recommendations for correcting nonconformances or improving the 1 l Quality Assurance Program, as appropriate. l l l l18.4.3 l l l Deficiencies identified as a result of an internal audit are to be l l recorded on an Audit Finding Report (AFR) by the auditor and issued to I ( lthedepartmentheadresponsiblefortheareaauditedforcorrective l l action. The department head or their assigned designee is to provide l lpromptcorrectiveactiontothedeficienciesidentifiedanddocumenton l l the AFR the action taken or to be taken to prevent recurrence. l lAppropriatefollow-upincludingre-auditsbytheassignedauditgroupis l l 1 1 I I I I I l 1 O i l A l l TOPICAL REPORT i IREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 18.0 AUDITS lPAGE 18-4 l l L l l l 1 I I I
r : l I l l l l l conducted in the deficient areas to verify proper and timely l I implementation of corrective action commitments. Follow-up actions are I to be documented on the AFR. I I I I l 18.4.4 l l l l 1 l Audit reports pertaining to plant activities are to be independently l l reviewed by the PSC and the SRC to determine if additional corrective l actions need to be initiated to assure continued safe operation of the l l l plant. Audit reports pertaining to LRGO activities are to be l independently reviewed by the SRC. In addition to these reviews, the l l l audit reports are to be distributed, as a minimum, to the Nuclear l
- l. Operations Vice President, Quality Assurance Manager and appropriate l l levels of management having responsibility in the area audited to assure l their awareness of the findings. l l
l l ! l I i l 18.4.5 l l l 4 l 4 l l Audit results and findings related to external audits conducted by QA l O l gersonnei are to be recorded aed distributed to the ceaiity Assurance l Manager and a designated representative of the audited organization. l l f 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 l l recurrence on the AFR. Corrective actions are to be verified by QA l personnel and documented on the AFR. l l l l 1 l l 18.5 RECORDS l 1 I I I l Written internal audit reports, including checklists, AFR's and related l documentation supporting the follow-up activities are to be forwarded to 1 - the Administrative Manager for storage in accordance with Section 17 of l l l 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 l l l 1 A l TOPICAL REPORT 7 lREV. i P l lDATE 5/31/85 l l & l SECTION: 18.0 AUDITS lPAGE 18-5 l l L l l l l l l l
i . I I I I 2 1 18.6 NUCLEAR FUEL AUDITS I l l O i Arxansas eo ,& Lio8t Co.nemy deieoates to Middie Soeth Services, inc., i l a wholly owned subsidiary of Middle South Utilities, Inc. , the I responsibility for performing those quality assurance functions necessary l l to assure that its nuclear fuel is designed and fabricated in accordance l I with regulatory requirements and accepted codes, standards and I l specifications. The MSS Quality Assurance section monitors the design l l and fabrication of the fuel through a program of audits of the fuel l l fabricator,includingbothdesignreviewauditsandfuelfabrication l I
.I audits. MSS also conducts audits of component suppliers as deemed I j lnecessarybytheManager,QualtiyAssurance(MSS),toensurethequality I of the fuel. Formal audit reports are issued by MSS to document their l l
l audit activities and to identify nonconformances or other items requiring I action by the fuel fabricator. Resolution of nonconformances or other 1 j litemsrequiringactionisverifiedbyMSSanddocumentedinfollow-up ), I reports. The AP&L Quality Assurance Manager is on distribution for all l l lauditandfollow-upreports. l l l 1 O l l I I , I I I I I- 1 I I I I ' I I I l I I I ' I
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# l ANSI N45.2.2 Inert Gas Blankets There may be cases involving l l large or complex shaped items b l l for which an inert or dry air I purge is provided, rather I than a static gas blanket, in I order to provide adequate l protection due to difficulty l l of providing a leak proof l
l barrier. In these cases, a l l positive pressure purge flow l may be utilized as an alter-l l l nate to a leak proof barrier. 1 l l ANSI N45.2.2 Limits halogen and Engineering may allow the use l Appendix A, sulphur content of l of tapes containing greater l lA.3.5.2,(1),(a) tape. amounts of halogens after l l appropriate evaluation, I l however, the quantities shall l l not be such that harmful l O l conceatrations couid be l l 1eached or released by break- l l down of the compounds under l l expected environmental l l conditions. l l l lRegulatoryGuide General Altern1tive equivalent 1.39 ANSI N45.2.3 l l requirements may be utilized l l to cover those situations not l l I included in the subject l Standard; for example, situa-l l tions in which shoe covers l I I I I I I I I I I I I I I I lA l P l l TOPICAL REPORT lREV. 7 10 ATE 5/31/85 I l I & I SECTION: TABLE 1 lPAGE T1-6 I ! I L I ' l l l I I I
r I I I I l R.G. 1.94/ Section 1.4 defines This requirement for rein- l I ANSI N45.2.5 inprocess tests and forcing steel will be I (Section 1.4) states: interpreted to permit taking I l the rebar test specimen at
" l l ... samples of these the fabrication shop, prior l l tests must be taken to start of fabrication of l from the lot or l the rebar from the heat or l l batch of materials fraction thereof represented l supplied to the site by the test specimen. For l
l for use." those tests performed at the l l fabrication shop, certifica- l tion shall be available to l provide objective evidence l l that the test specimens l l represent the material sup- l l plied for use at the site. l l l Requirement: lANSIN45.2.5 l l (Section 4.5) Section 4.5, Con- l O l crete eiacement. l l references American l l Concrete Institute l (ACI) standards l l ACI-305-72, l l l " Recommended Prac- 1 l tice for Hot Weather l Concreting" and ACI-l l 306-66, " Recommended l l l Practice for Cold l l Weather Concreting." l l l 1 l l I I I I I I I I I I I A l TOPICAL REPORT lREV. 7 P 1 l lDATE 5/31/85 l l & l SECTION: TABLE 1 lPAGE TI-9 l l L l l l l l l I
r I l i I I a) For bar sizes #3 through #11, one full size l l specimen from largest bar size rolled from each (j l mill heat, unless material from one heat l I differs by three or more designation numbers. I When this occurs, one bend test shall be made l l from both the highest and lowest designation I number of the deformed bars rolled. I I I I I l b) For bar sizes #14 through #18, Supplementary l l Requirements S1 of ASTM A615 will be applied. l l One full size specimen for each bar size for l l each mill heat. If supplementary requirements l l are not followed for mill tests, they will be l l applied as in process tests. l l l l The above interpretation is consistent with l l Regulatory Guide 1.15, " Testing Reinforcing bars l l for Category I Concrete Structures," Revision 1, l December 1972. l I b v I l I l l In process test specimens may be selected at the l l rebar fabrication shop, prior to start of I fabrication of the rebar from the heat or fraction l l thereof represented by the test specimen. l l 1 l Acceptance criteria for any failed test l l (qualifications as well as in process) may be the I same as that for tensile tests specified in l l Subarticle CC-2331.2 of ASME Section III, Div. 2 l l Code (1975). This states that if a test specimen l l fails to meet the specified strength requirements, I I I I I I I I I I I l l I I o () I i l A P I I TOPICAL REPORT I IREV. 7 I l I IDATE 5/31/85 l l & 1 SECTION: TABLE 1 lPAGE T1-13 l l L l I l l l 1 I i
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, l QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION I 's l MANUALS LIST I I
I I l l 1. Quality Assurance Program for Operations l I I I i l The Quality Assurance Program for Operations establishes the l l policies and guidelines of the AP&L quality assurance program for l its operating nuclear plants. This program is to be followed by all l l l organizations involved in safety related work applicable to l operating nuclear plants. l I I l l l l 2. Eneray Supply Procedures Manual l I I I I l The Energy Supply Department - Little Rock General Office (LRGO) l l employs a system of procedures designated as Energy Supply l 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 O l ePeratiao giant. l I I l l The ESP's and revision thereto are prepared by Energy Supply LRGO l l personnel, reviewed and approved by the Quality Assurance Manager, I l the Energy Supply (LRGO) Procedures Task Force and the responsible l department head. l I I I I I l 3. Quality Assurance Procedures Manual I i i I I I i l The Quality Assurance Organization employs a system of procedures l l designated as Quality Assurance Procedures (QAP) in order to assure I proper imp 1 wentation of the program. The QAP's and revisions l I I i I l I l l l l l 1 1 I l l i I O lA I P l I W ICAL REPORT !REV.7 10 ATE 5/31/85 l l & I SECTION: TABLE 3 lPAGE T3-1 I I L I l l l 1 I I L
T l l 1 l l thereto are prepared by the Quality Assurance Organization, reviewed I and approved by the Quality Assurance Manager and approved by the C) l Energy Supply Services Director and the Sr. Vice President, Energy l Supply. l l l l4. Quality Assurance Administrative Procedures Manual l l 1 The Quality Assurance Organization also employs a system of I procedures designated as Quality Assurance Administrative Procedures I (QAA). Therie procedures provide technical and administrative l l instructions to the Quality Assurance staff to aid in implementing l l their responsibilities within the quality program. l l l lS. Overall Plant Adminstrative Procedures Manual l I l l The plant operation organization employs a system of procedures l l designated as Overall Plant Administrative Procedures. These l l procedures implement QJality Assurance Program requirements and l l control on site activities. Overall Plant Administrative Procedures l O l aad chanoes therete ere PrePered ey the Pieet steff. reviewed by the l l Plant Safety Committee and approved by the plant's General Manager. l l The procedures and revisions are also reviewed by the Manager, l l Nuclear Quality Control to assure that Quality Assurance Program l l commitments are met. l l l l6. l Departmental Plant Administrative Procedures l l l Each department (operations, maintenance, engineering and technical l l support, training, quality control, etc.) at the plant has developed l l procedures in support of the Overall Plant Administrative Procedures l l and this Quality Assurance Program. These procedures provide l l technical and administrative instructions to the various departments l 1 l l l l l l l l l lA l P l TOPICAL REPORT IREV. 7 lDATE 5/31/85 l l & 1 SECTION: TABLE 3 lPAGE T3-2 l l L l l l l l l 1
l l 1 I I to aid in implementing their responsibilities within the quality l program. Each department head is responsible to perform a QA review l l I of their procedures to assere conformance with the Quality Assurance l Program. These procedures are reviewed by the Plant Safety l l l Committee and approved by the plant's General Manager. 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 l l 1 1 I I I I I I I I I I I o l l l l l l l l l l l l l l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I A I TOPICAL REPORT lREV. 7 l l p I IDATE 5/31/85 I I & I SECTION: TABLE 3 lPAGE T3-3 I I L I I l l l I I
I I I I l APPENDIX A I I I I QUALITY PROGRAM FOR TRANSPORT PACKAGES l J l ' I I I l 1.0 _ INTRODUCTION l l - 1 l 1.1 The quality program for transport packages is designed to I I comply with the requirements of this manual and with the l l l quality assurance guidelines identified in 10CFR71, Subpart H - I i l Quality Assurance, subject to exceptions noted in Attachment A l 1 I to this Appendix. I i l I { l 1. 2 Attachment A to this Appendix identifies the applicability of I I each section of the Quality Assurance Manual - Operations to 1 i i the Quality Program for Transport Packages. ! 1 I i i 1. 3 Attachment B to this Appendix contains the Quality Assurance 1
- 1 Program Approval document which shows NRC approval of this l I program on January 23, 1985. l I
I l I i i I J l I i i l i l I I I , O l l i l I ! , I i ! I I l l l i I i i l I l l l - l I I l I i l I
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' l l lDATE 05/31/85 l l & 1 SECTION: APPENDIX A - QUALITY PROGRAM lPAGE AA-1 i L l l TRANSPORT PACKAGES l l l l l
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- - _ _ ~ _ _ _ _ _ _ _ . . _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ . . _ _ _ _ - _ _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ - _ _ . . - - _ _ _ _ _ _ _ _ _ _ _ . I I I I I I I I ATTACHMENT A i 10 CFR 71 Appendix H I I I I The following section of the most currently approved revision of AP&L TOP-1A l will be applied as stated below (Note specific paragraphs are to rev. 6 ! l paragraph numbers which could change curing subsequent revisions). l Section 1 - Appilcable l Section 2 - Applicable l l Section 3 - Not applicable. 1 l AP&L will use only licensed packaging which has been designed under a QA program which has been submitteo l to the NRC for approval. g l Section 4 - Applicable - '~ l Section 5 - Appitcable l Section 6 - Applicable l section 7 - Applicable l Section 3 - Generally applicable, except for paragraph 8.2.2 and 8.2.3. l Oue to size, uniqueness, low volume, and the method of supplier l g identification of each package, AP&L tagging of each package is not necessary. l g l section 9 - Not applicable; we do not consider this subject as a "Special l l Process" in the context of 10 CFR 71, Appenofx H Section 71.119 which is a re statement of 10 CFR 50, Appenoix B Criterion 9. l
- O- l Section 10 - Applicable 1 l
l l t 1 l Section 11 - Not applicable; AP&L will not be testing the package in the context of 10 CFR 71. Accendix H, section 71.123 which is a l I restatement of 10 CFR 50, Appendix B Criterion 11. ! I I l Section 12 - Applicable l l section 13 - Generally applicable except for otragraph 13.5. AP&L does not l
" store
- package, therefore the storage section does not apply. !
l I g section 14 - Not applicaDie; see Section 11 comments above. l l Section 15 - Generally applicable, ascent for references to the various I l types of dispositions in paragraohs 15.2.3 to 15.2.5. l l Nonconforming material or equipment will be returned to tre vendor or will be replaced. l g g l Section 16 - Applicable ! I I l section 17 Applicable l l Section 18 - Applicable I i 1 I I I I I I I I I I O i l A p i TOPICA' REe0ai iaEv. 7 i l lDATE 05/31/85 l l & l SECTION: APPENDIX A - QUALITY PROGRAM lPAGE AA-2 l l L l TRANSPORT PACKAGES I l l 1 1 I
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;l l Activities conducted under applicable criteria of Appendix 8 of 10 CFR I l Part 50 to be executed in accordance with Attachrient A to QA Hanual 6 (AP&L-TOP-1A) for Arkansas Power Station Nuclear One. Units 1 and 2 >l ll lh (Occket Nos. 50-313 and 50-368) with regard to transportation packages.
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l I I I l ATTACHMENT B l O lA g p i l roarcat acaoat iaev- 7 lDATE 05/31/85 I l L & l SECTION: APPENDIX A - QUALITY PROGRAM lPAGE AA-3 i L l TRANSPORT PACKAGES I l l l l I
l l l l l APPENDIX B l l n l QUALITY PROGRAM FOR FIRE PROTECTION 1 V l l l l l l l l 1. 0 INTRODUCTION l l l l 1.1 The AP&L fire protection program was developed to define the l l organizational responsibilities, procedural controls, fire l l brigade staffing and training and the quality assurance l l provisions that have been established for the nuclear plant. l l The overall objective of the fire protection program is to l l minimize both the probability and consequences of postulated l l fires and to maintain the capability to safely shut down the l l plant if a fire should occur. l l l l 1. 2 The scope of the AP&L fire protection program includes those l l fire protection and detection systems, and those structures and l l components (such as fire doors, fire dampers, and penetration l l seals) which, as identified in the plant's fire hazards l l analysis report, are required to restrict the damage caused by l l a single exposure fire to safet.y related equipment and l l equipment required to achieve and maintain safe plant shutdown l l to within those limits set forth in Section 1 of Appendix R to l l 10 CFR 50. l l l l 1. 3 The quality program for fire protection is designed to comply l (]V l with the requirements of this manual and with the quality l l assurance guidelines identified in BTP-APCSB 9.5-1, Rev. 2, l l July 1981, Guidelines for Fire Protection for Nuclear Power l l Plants, subject to exceptions noted in this Appendix. l I l l 1.4 With respect to regulatory commitments, AP&L is committed to l l implementing the requirements of the following, subject to l l exceptions noted in this Appendix: l l I l 1. 10CFR50, Appendix A, General Design Criterion 3 - Fire l l Protection. I l l l 2. Specific sections of 10CFR50.48, Fire Protection and l l 10CFR50, Appendix R. Fire Protection for Nuclear Power l l Facilities Operating Prior to January 1, 1979. These l l sections are as follows: l l 1 l III.G. Fire Protection Safe Shutdown Capability l l l l III.J. Emergency Lighting l l I l III. L. Alternative and Dedicated Shutdown Capability l l I ! I I l l O l l l l l V l A l TOPICAL REPORT lREV. 7 l p l l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-1 l l L l FOR FIRE PROTECTION l l l l l l
I l 1 l l III.O. Oil Collection System for Reactor Coolant Pumps I i l O V l l
- 1. 5 Other fire protection commitments are contained in the following AP&L/NRC references and documents:
l l 1 I l 1. AP&L Facility Operating License (s) including Technical l l Specification (s) l l l l 2. AP&L Final Safety Analysis Reports (FSAR) l l l l 3. AP&L Fire Protection Safety Evaluation Reports (SER) I I l l 4. AP&L and NRC regulatory correspondence (includes l l applicable NRC generic letters and AP&L exemption l l letters), identified in Division 4.0 to the Fire l l Protection Program Manual (FPPM). I I l l 1. 6 The above requirements are implemented by controlling l l activities as described in this manual and appendix and by l l procedures referenced in this manual and appendix. l l l l 2.0 ORGANIZATION I I l l 2.1 The organizational structure and responsibilities of key l l personnel associated with the administration, implementation l l and evaluation of the fire protection program are described in l l Section 1.0 of this manual and as follows: l O l l
- 1. The Nuclear Operations Vice President is the offsite management position which has the responsibility for the l l development, implementation, and assessment of the l l effectiveness of the fire protection program. He reports l l directly to the Energy Supply Senior Vice President. l I l l 2. Reporting to the Nuclear Operations Vice President is the l l Nuclear Services General Manager. Under his direction is l l the Nuclear Programs Manager. The Nuclear Programs l l Manager has responsibility for development of the plant l l fire protection program. He is responsible for providing l l guidance for its implementation and support to the nuclear l l plants in the area of fire protection. These activities l l include assuring that regulatory requirements are included l l in the fire protection program, AP&L commitments regarding l l fire protection are identified and tracked, safety l l evaluations (10 CFR 50.59) for fire protection l l modifications are performed and to provide liaison with l l outside fire protection related organizations. He also l l has responsibility for maintenance and revision of the l l Fire Protection Program Manual through its staff l l supporting fire protection. l l l l l l l O I l A l
l TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-2 l l L l FOR FIRE PROTECTION l l l l l 1
l l l l l 3. The Plant General Manager is the on site manager l l responsible for the overall administration and l O l implementation of plant operations in accordance with the l V l fire protection program. He reports directly to the l l Nuclear Operations Vice President. l l l l 4. The Plant Administrative Manager is responsible for the l l establishment and monitoring of fire prevention aspects of I l the program at the plant including control of l l combustibles, ignition sources, and postings. He reports l l directly to the Plant General Manager. Reporting to the l l Plant Administrative Manager is the Human Resources l l Supervisor. Under his direction are the Plant Safety and l l Fire Prevention Coordinators. The Safety and Fire l l Prevention Coordinators are responsible for implementing, I l maintaining and assessing the fire prevention aspects of I l the program as defined in plant procedures. l l l l 5. The Quality Assurance Manager is responsible for assuring l l that the fire protection program is implemented in l l accordance with the QA Topical Report, Station Technical l l Specifications, and applicable procedures. This is l l accomplished by the performance of audits and other l l provisions of the QA Topical Report. He shall assure that l l corrective action, when necessary, is taken. He reports l l directly to the Energy Supply Services Director. I l l l 6. The Licensing Manager is responsible for providing other l ! O)
l responsible organizations with regulatory information and l I licensing recommendations on regulatory issues related to l l fire protection. He is also responsible for the l l preparation and/or review of fire protection related NRC l l correspondence and proposed changes to the Fire Protection l l Program Manual to ensure that regulatory l l requirements /committments are complied with and to l l identify / control those portions of the Fire Protection l l Program Manual affecting the Licensing basis of the l l nuclear plant. He reports directly to the Nuclear l l Services General Manager. l l l l 7. The Engineering Services General Manager is responsible l l for assuring that the technical requirements specified in l l the plant operating license, Technical Specifications, and l l other design basis documents, with respect to fire l l protection, have been satisfied in design modifications l l and design documents affecting the nuclear plant. He l l reports directly to the Energy Supply Services Director. l l l l 8. The Engineering and Technical Support Manager is l l responsible for the fire protection aspects of the program l l at the plant, such as evaluation and/or inspection of fire l l l l l l I U) l A l TOPICAL REPORT I
lREV. 7 I l l P l lDATE 5/31/85 l l & 1 SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-3 l l L l FOR FIRE PROTECTION l l l l l l
l l l l l detection and suppression equipment, fire barriers, l l dampers and alternate shutdown equipment protection. He l p l reports directly to the plant General Manager. Reporting l V l to the Engineering and Technical Support Manager is the l l Plant Engineering Superintendent. Under his direction is l l the plant Fire Protection Specialist. He is responsible l l for cognizance of the design requirements regarding fire l l protection and maintaining the Fire Protection Program l l Manual at the plant. The plant Fire Protection Specialist l l provides technical support to the plant's Fire Protection l l Program in the form of system evaluations, design l l recommendations and standards coordination. l l l l 3.0 QUALITY ASSURANCE PROGRAM l l l l 3.1 This quality program is to ensure that the fire protection l l systems for safety-related areas (as defined in paragraph 1.2 l 1 of this Appendix) are controlled in accordance with applicable l l NRC regulations, industrial standards and codes and AP&L l l policies, rules, procedures and licensing documents. The l l quality program is implemented through appropriate LRGO and l l plant procedures. The effectiveness of the fire protection l l program is verified through surveillances and scheduled audits l l conducted by the QA organization, under the cognizance of the l l SRC. General requirements for this program are also described l l in subsections 2.4 through 2.7 of this manual, except that l l personnel performing inspections need not be certified to ANSI l l N45.2.6, when inspections are performed on equipment not listed l (v ) l on the Q-list. l l l l 3.2 Employees whose duties and responsibilities are related to this l l fire protection program at or in support of the nuclear plant l l are to participate in appropriate training programs to assure l l that suitable proficiency is achieved and maintained in the l l work they are performing. l l l l 3.3 Fire protection training for plant personnel is included as l l part of industrial safety in the General Employee Training l l Program. Personnel are periodically retrained in industrial l l safety in accordance with plant procedures. Personnel assigned l l to the plant Fire Brigade are to receive additional l l indoctrination and training to assure their capability to fight l l fires is established and maintained. The Safety and Fire l l Prevention Coordinators have the overall responsibility for l l these training programs. l l l l 4.0 DESIGN CONTROL l l l l 4.1 Section 3.0 of this manual is applicable for design control l l activities pertaining to the fire protection system. l l l l l l l n i l l l C) l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-4 l l L l FOR FIRE PROTECTION l l l l I I s
i l l l l 5.0 PROCUREMENT DOCUMENT CONTROL l l l O l 5.1 The control of procurement documents for fire protection l d l related materials, parts and components is described in Section l l 4.0 of this manual with the exception of paragraph 4.2.3, when l l these items are not associated with the Q-list. The l l procurement document is to include the requirement that items l l be U.L. or F.M. listed for fire protection use, where l l applicable, in accordance with LRGO and plant procedures. l l l 1 6.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS l 1 l l 6.1 Inspections, tests, administrative controls, fire drills and l l training that govern the fire protection program are prescribed l l by documented instructions, procedures and drawings and are l l accomplished in accordance with these documents. A listing and l l brief description of procedures relating to fire protection l l activities is provided in the AP&L Fire Protection Program l l Manual. Instructions, procedures and drawings are prepared, l l reviewed, approved and revised in accordance with applicable l l LRG0 and plant procedures. l 1 l l 7.0 DOCUMENT CONTROL l l l l 7.1 Section 6.0 of this manual is applicable for the control of I l quality program documents related to fire protection. l l l l 8.0 CONTROL 0F PURCHASED MATERIAL, EQUIPMENT AND SERVICES l f") l l The control of purchased fire protection related materials, l l l equipment and services is described in Section 7.0 of this manual, l l with the following exception related to subsections 7.2, 7.3 and l l 7.5. For the procurement of fire protection related items or l l services not associated with the Q-list, the vendor / contractor l l qualification criteria (including periodic reassessment of their l l program), is not required. Nonconformances dispositioned repair or l l use-as-is by the vendor are to be submitted to and accepted by AP&L l l only when so designated on the procurement document. l l l l 9.0 IDENTIFICATION AND CONTROL 0F MATERIALS, PARTS AND COMPONENTS l 1 l l 9.1 Section 8.0 of this manual is not applicable for the l l identification and control of materials, parts and components l l related to the fire protection system. No particular l l requirements for this Section have been identified in BTP-APCSB l l 9.5-1, Rev. 2. The identification and control of materials, l l parts and components are conducted in accordance with existing l l procurement and materials management procedures and practices. l l l l l l l l l l l A l TOPICAL REPORT lREV. 7 l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-5 l l L l FOR FIRE PROTECTION l l l l l 1 1
l I I I l 10.0 CONTROL OF SPECIAL PROCESSES l l l (') V I l 10.1 Section 9.0 of this manual is not applicable for the control of special processes, as applicable to fire protection systems. l l l No particular special process controls have been identified by l l BTP-APCSB 9.5-1 Rev. 2. The control of special processes for l l the maintenance of the fire protection system are performed in l l eccordance with applicable plant procedures and practices. I l l l 11.0 INSPECTION l l l 1 l 11.1 Inspection activities applicable to the fire protection system l l are described in Section 10.0 of this manual with the exception l I of paragraphs 10.2.2 and 10.3.2.3, when inspections are l l performed on equipment not associated with the Q-list. The l l Regulatory Guides referenced in paragraph 10.2.2 are not l l applicable to the fire protection system. Individuals outside l l the'QA and QC organizations who perform inspections only need l l to meet paragraphs 10.3.2 and 10.3.2.1. l l l l In addition to the provisions of this manual, inspections and l l surveillances are provided for in applicable portions of the l l Fire Protection Program Manual and the Technical Specifications l l for each nuclear unit. I I I l 12.0 TEST CONTROL l l l p -l 12.1 A test program is to be established and implemented to ensure l Q l l that testing is performed and verified on applicable systems and components to demonstrate conformance with design and l
, l l system readiness requirements. The tests are to be performed l in.accordance with written test procedures and test results
-l - I !
t le evaluated for conformance to the test objectives. I
< l l
- l. 12.2 The control of testing activities is described in Section 11.0 l l
of this manual. Surveillance testing requirements are l l identified in the Technical Specifications for each nuclear l 5 h l IJ
' (l' unit. I l
M* f t , d 13.0 CCNTROL OF MEASURING AND TEST EQUIPMENT l
" l -'s ,.
l e' l 'i3(1Section12.0ofthismanualisnotapplicableforthecontrol l l c' , < of measuring and test equipment. No particular measuring and
~
I a 1, , ' ' ~ test equipment controls have been identified in BTP-APCSB9.5-1, I ( if < . Red. 2. Measuring and test equipment is controlled in l
. A5- l laccordance with applicable plant procedures and practices. I A+ ,%,,
l l N;jll' 14.0 HANDClNG STORAGE AND SHIPPING l l l
)l1'
. l 14.QS+ction13.0ofthismanualisnotapplicableforthehandling, l 4torage and shipping of fire protection related materials and l
, j ll '
< l
,y I '- 1 O i - ' - i i
\\l A' ' g TOPICAL REPORT lREV. 7 l i{l s0 ?, l lDATE 5/31/85 l
\1 .34 ;# ) 4 l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-6 i
,., ... h h 7 j" / l FOR FIRE PROTECTION l l
' l1 . 5
~
l l l cc~' .v _- _L_______-___ - _ _ - __ ____ _ _ . -
E l l I l l equipment. No particular requirements for this Sect. ion have l l been identified in BTP-APCSB 9.5-1, Rev. 2. Handling, storage l p) L I l and shipping activities are controlled in accordance with applicable plant procedures and practices. l I l l l 15.0 INSPECTION TEST AND OPERATING STATUS l l l l 15.1 Measures are established to provide for the identification of l
, I items that have satisfactorily passed required inspections and l l tests and are documented per approved instructions or l I procedures. I I (
l 15.2 Section 14.0 of this manual is applicable for identifying the l l inspection, test and operating status of the fire protection l l system. l l l l 16.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l l l l 16.1 The control of nonconforming materials, parts and components l
'l related to the fire protection system is described in Section l l 15.0 of this manual, with the exception of paragraph 15.4, when l l the item is not associated with the Q-list. Vendor i l nonconformances are to be submitted to AP&L only when so l l designated on the procurement document. I l l l 17.0 CORRECTIVE ACTIONS l l l l 17.1 A corrective action system is to be established to ensure that l P l l
conditions adverse to fire protection, such as failures, malfunctices, deficiencies, deviations, defective components, I l l uncontrolled combustible materials and nonconformances, are l , I promptly identified, reported and corrected. l l l l 17.2 Corrective action activities are controlled as described in l l Section 16.0 of this manual, with the following exception l l related to paragraph 16.2.5. Vendors furnishing fire l l protection items not associated with th? Q-list are not l l required to be listed on the QVL. d i l I l 18.0 QUALITY ASSURANCE RECORDS l l l l l 18.1 Records which furnish evidence that the criteria enumerated in l l this program are being met for activities affecting the fire l l protection program are to be prepared and maintained as l l described in Section 17.0 of this manual. A listing of I l documents and records (including calculations, test reports, I I code reports and design change packages) relating to fire i i protection is included within the AP&L Fire Protection Program l l Manual. I I I I l l 1 I I O I l l I t/ l A l TOPICAL REPORT IREV. 7 l l P I lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-7 l l L l FOR FIRE PROTECTION I l l l I I
I l I i
, i 19.0 AUDITS l
l n l i 19.1 Audits are to be conducted and documented to verify compliance
.U l with the fire protection program, including design and i
l I procurement documents, instructions, procedures and drawings l l and inspection and test activities. Section 18.0 of this l I manual is applicable for the control of audits related to the l I fire protection program. I I I i 19.2 As a minimum, audits of the fire protection program are to be l I scheduled at specified frequencies in accordance with the l l Technical Specifications applicable to each nuclear unit. I I I I I ! l I I I , I i I l 1 l l l l l l l l l I I F l' l l l l 1 I I I I l l l l l ? I I l I l l l l l l l i i l l I I I l l l 1 I I I I I I I I I I I I I I I I I l l l 1 I l l 1 l l l O lA l p l l 10eicAt Ree0RT IRev. 7 IDATE 5/31/85 i I I & I SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-8 l I L l FOR FIRE PROTECTION l l ! I I I I
r 1 I l- I , I I I I 1 I b^' l' l l QUALITY ASSURANCE MANUAL OPERATIONS l l l
- l. REVISION 7 APPROVALS l I! !
I I l l l' I l i
- 1. I
- 1: I I: I l- 1 I I I I I I I l ll l
- l. I l' I I I I I I I I I l Attached are the revised pages to the subject manual for your review and l
/'l l approval. Please sign and date in the applicable space below to signify l
(_/ l your approval. Upon approval, these revisions are to be issued to the NRC l l per the provisions of 10CFR50.54(a) and to all manual holders. l APPROVED: 6/23/g3 l UALTTP ASSURANCE MANAGER' l APPROVED: / , [ -/ O /2%,a /a l l
~ DIRECTOR, ENERGY SUPPLY ERV.
l l APPROVED: - l l SR. VICE PRESIDENT, g PLY l 1 I I I I I I I I I I I I I I I I I I I A I TOPICAL REPORT IREV. 7 l l P I IDATE 5/31/85 l l & I I I I L I I I 1 I I I
I I RECORD OF REVISIONS l l l l l l REVISION DESCRIPTION DATE l l NUMBER O i l 0 Initial Issue 6/11/74 i 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 I I 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 changes. l l l 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 5 Incorporate Organizational Changes 10/10/80 l l t l and responses to subsequent NRC l l Questions. Incorporate Regulatory l Guides and retype document in its l O l l entirety in standardized format. l l l 6 Incorporate organizational changes, 5/30/84 l 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 l l safe operation of AP&L nuclear plants. l l Manual has been reformated and retyped l in its entirety. l l l l 7 Changes given below are identified 05/31/85 l l l on the pages by a bar in the left i 1 margin, placed next to the affected l area. l l l l l l l l l l l l l l l l I 1 I I O lA l P i l 10elCAt REe0R1 iRev. 7 lDATE 5/31/85 i l l & l SECTION: RECORD OF REVISIONS lPAGE 1 l l l l L l l 1 l l
" ' " - ~
e*,a_, .1. m4_,; >. a h JK Ei. Gw - *+---*4 *8*"'- #N' ' l l l REC 040 0F REVISIONS l l 1 l REVISION l l NUMBER DESCRIPTION DATE l O- l Corrected by errata (includes misspelled l l 7 (cont.) l l words) on the following pages: l l l l A-1 2-5' 10-6 TI-9 l ' l A-2 3-2 11-5 T1-13 l l 1-10 3-3 13-2 T3-1 l l 1-12 3-4 13-4 T3-2 l l 1-18 4-2 15-2 T3-3 l 1- 1-19 5-2 15-3 l l 1-20 5-3 15-5 l l 1-22 5-4 15-4 l l l-23 6-2 16-1 l l 7-2 T1-6 l l 9-1 l l- l l Page C-7: revised definition l l Page C-8: revised definition l l Page 1-9: revised paragraph 1.4.2(1) l l Page 1-10: revised paragraph 1.4.2.1 l l Page 1-11:added paragraph 1.4.2.1.1 l l' : paragraph 1.4.2.2 redesignated l l 1.4.2.1.2 .l l :added paragraph 1.4.2.1.3 l l : paragraph 1.4.2.3 redesignated l 1.4.2.2 and revised O l l Page 1-12: paragraph 1.4.2.3.1 redesig-l l l nated 1.4.2.2.1 l I Page 1-13:added 7) to paragraph 1.5.1.3 1 7 l Page 1-14 & 15: revised paragraph 1.5.3 l l- to delete Planning / Scheduling Supervisor l l Page 1-21:added paragraph 1.5.8 l l Pages 1-1 to 1-23: paragraph locations l l changed l l Page 2-2: paragraph 2.2.2 redesignated l l 2.2.3 and revised l l Page 2-2: paragraph 2.2.3 redesignated l l 2.2.4 l l Page 2-2: paragraph 2.2.4 redesignated l l 2.2.5 l l Page 2-2: new paragraph 2.2.2 added l I I l Page2-3: revised paragraph 2.2.5(2) l l Page 2-7 and 2-8: revised paragraph 2.6.4 l l Pages 2-3 to 2-9: paragraph locations l l changes l l l l 1
-l l l l O l l.
A P l l TOPICAL REPORT REV. 7 lDATE 5/31/85 l l l & 1 SECTION: RECORD OF REVISIONS lPAGE 2 l l L l l l l l l 1
r-
-1 I l RECORD OF REVISIONS l l l l REVISION l r l NUMBER DESCRIPTION DATE l k-]> I l l 7 (cont.) Page 7-3: revised paragraphs 7.2.3 and l l 7.2.4 l l Pages 7-3 to 7-7: paragraph locations l l changes l l Page 15-1: revised paragraph 15.2.1 l l Page 18-3: revised paragraph 18.3.2 l l Pages 18-3 to 18-6: paragraph locations l l changes l l Page F-1: revised Figure 1 l l Page F-2: revised Figure 2 l l Page F-3: revised Figure 3 l l Page F-5: revised Figure 5 l l Page F-6: revised Figure 6 l l Page T2-1: revised titles l l Page AA-1 to AA-3: new Appendix A added l l Page AB-1 to AB-8: new Appendix B added l l l l l I I I I I I I I l l l l l 1 I I I I I l I I I I l l l l l l l l l
l l l l l l l l l l ! I I l- I I I I 1 I I I I
'l I 5
'. l l l l l i I I U^ l A l TOPICAL REPORT , IREV. 7 I t l P l IDATE 5/31/85 I l & I SECTION: RECORD OF REVISIONS lPAGE 3 I I L l l l l l l l
I- 1 I I I TABLE OF CONTENTS l 1 1 I Section Subject Tab _Page_ Rev. l l l l l l APPROVAL COVERSHEET l RECORD OF REVISIONS l -TABLE OF CONTENTS TC-1 7 l TC-2 7 l l TC-3 7 l l TC-4 7 l l TC-5 7 l l TC-6 7 l l TC-7 7 l
, TC-8 7 POLICY STATEMENT l
l A-1 7 l l A-2 7 INTRODUCTION l l B-1 6 l B-2
- l. 6 l
l B-3 6 i O l 8-4 6 l l B-5 6 l TERMS AND DEFINITIONS C-1 6 l l 1 C-2 6 i C-3 6 l l C-4 6 l C-5 6 l l C-6 6 l C-7 7 l l C-8 7 l C-9 6 l l C-10 6 l l l l l l l l l l l l l l l A I TOPICAL REPORT REV. 7 l l P l lDATE 05/31/85 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-1 l l L I l l l I I I
I I I I l 1. 0 ORGANIZATION 1 1-1 7 l I I 1-2 7 O i 1-3 7 i 1-4 7
-l l l 1-5 7 l 1-6 7 l l ,
1 1-7 7 l. 1-8 7 l , l l 1-9 7 l 1-10 7 l l l 1-11 7 l 1-12 7 l l 1-13 7 l l 1-14 7 l l 1'15 7 l 1-16 7 l l 1-17 7 l 1-18 7 l 1-19 7 l -O l 1-20 7 l l 1-21 7 l 1-22 7 l l 1-23 7 l 2.0 QUALITY ASSURANCE PROGRAM 2 2-1 6 l l l 2-2 7 l l 2-3 7 l l l 2-4 7 l 2-5 7 l l 2-6 7 l 2-7 7 l l l 2-8 7 l 2-9 7 l l l l l l l l l I < l 1 O lA l P l l T0e1 cat Ree0RT iRev. 7 lDATE 05/31/85 i l l & 1 SECTION: TABLE OF CONTENTS lPAGE TC-2 l l L l l l l l l 1
I l
-1 l 1 3.0 DESIGN CONTROL 3 3-1 6 I I I 3-2 7 l 3-3 7 l l 3-4 7 l
1 3-5 6 l _4.0 PROCUREMENT DOCUMENT 4 4-1 l 6 l l CONTROL 4-2 7 l l 4-3 6 5.0 INSTRUCTIONS, PROCEDURES l l 5 5-1 6 l l AND DRAWINGS 5-2 7 l l 5-3 7 l l 5-4 7 6.0 l l DOCUMENT CONTROL 6 6-1 6 l l 6-2 7 l 1 6-3 6 l 7.0 CONTROL OF PURCHASED 7 7-1 l 6 l l MATERIAL, EQUIPMENT AND 7-2 7 l SERVICES 7-3 7 l l 7-4 7 I
.l 7-5 7 l
l 7-6 7 l l 7-7 7 l
.l 8.0 IDENTIFICATION AND CONTROL 8 8-1 6 l l OF MATERIALS, PARTS AND 8-2 6 l
l COMPONENTS 8-3 6 l 9.0 CONTROL 0F SPECIAL 9 9-1 7 l l l PROCESSES 9-2 6 l 9-3 6 l l l l 1 I I I l l l l l l l l 1 1 I I I l l lA l P-l l TOPICAL REPORT REV. 7 lDATE 05/31/85 l l & l SECTION: TABLE OF CONTENTS lPAGE TC-3 l l L l l l l l 1 l
I I
-l l l 10.0 . INSPECTION 10 10-1 6 l l
10-2 6 I 10-3 6 l l 10-4 6 l l 10-5 6 l l 10-6 7 l 11.0 TEST CONTROL 11 11-1 l 6 l l 11-2 6 l , l 11-3 6 l l 11-4 6 l l~ 11-5 7 l 12.0 CONTROL OF MEASURING AND 12 12-1 l 6 l l TEST EQUIPMENT 12-2 6 l l 12-3 6 l l 12-4 6 l 13.0 -HANDLING, STORAGE AND 13 13-1 6 SHIPPING l l 13-2 7 l 13-3 6 l l 13-4 7 I O- l 13-5 6 l l 14.0 INSPECTION, TEST AND 14 14-1 6 l OPERATING STATUS 14-2 6 l l_ 14-3 6 l l 14-4 6 ' l l 14-5 6 l l: 15.0 NONCONFORMING MATERIAL, 15 15-1 7 l l PARTS OR COMP 0NENTS 15-2 7 l
- . 15-3 7 l
l 15-4 7 l IS-S 7 l i- I I 1 I I I I I I I I I I I l l 3-A l TOPICAL REPORT lREV. 7 l P. l lDATE 05/31/85 l . l & l SECTION: TABLE OF CONTENTS lPAGE TC-4 l l L. I I I
; i l I I I
,.m..r __ _ , . . . . _ . , . _ _ _ . . . _ , . . . . _ . _ . _ _ _ _ . . _ _ ~ . . _ _ . _ . , . _ . , . _ . _ . . . _ . . , , . . _ _ _ . _ _ _ _ . . , _ _ . _*
I I I I l 16.0 CORRECTIVE ACTION 16 16-1 7 I l 16-2 6 _ bs . l I 16-3 6 l 16-4 6 l 17.0 QUALITY ASSURANCE RECORDS 17 17-1 6 l 17-2 6 l l 17-3 6 I l 17-4 6 l l 17-5 6 l 18.0 AUDITS 18-1 l 18 6 l l 18-2 6 l 18-3 7 l l 18-4 7 1 18-5 7 l l 18-6 7 I I I
, I I I I
-l i I I I I O l l l l l l l l l l
't. 1 I I I I I I I I I I
-l i I I I I I I I I I I I I 1 l I .
I I I I I I I l -__l n U I l A l TOPICAL REPORT l 7 I I IREV. l l P I lDATE 05/31/85 I I & I SECTION: TABLE OF CONTENTS IPAGE TC-5 I I L I l l l l l l
F I I I I l FIGURES l Number Tab Title Pm Rev. 1 AP&L Corporate F-1 7 l l Organization l 2 AP&L Corporate Services F-2 7 l 3 AP&L Energy Supply F-3 7 l Organization l _ l 4 AP&L Quality Assurance F-4 6 l I- Organization l 5 AP&L Nuclear Plant F-5 l 7 l Organization l l l 6 AP&L Nuclear Plant F-6 7 l Organization (Plant I l l Operations and Main- l tenance) l l l 7 AP&L Nuclear Plant F-7 6 l l Organization (Plant Engineering and Technical l l l O l Su, Port) l l 8 AP&L Nuclear Plant 19 F-8 6 l Organization (Plant l l Administrative Services) l , I i I I i i i l l I I I l l l l l l 1 ! I I !. I I I I I l l I l l l l l 1 I I l A l TOPICAL REPORT lREV. 7 P I l l0 ATE 05/31/85 l l & 1 SECTION: TABLE OF CONTENTS IPAGE TC-6 l l L l l l l l l l L
I I I I I TABLES I I I O ' i Number Title Tab M Rev. i l 1 AP&L Exceptions / Inter- T1-1 l 6 l l pretations of Regulatory T1-2 6 l l Guides and ANSI Standards T1-3 6 l l T1-4 6 I l T1-5 6 l l T1-6 7 I l T1-7 6 l l TI-8 6 I l T1-9 7 l l T1-10 6 l l T1-11 6 l l T1-12 6 l l T1-13 7 l l T1-14 6 I ! T1-15 l 6 l 2 I T1-16 6 i Quality Assurance 2 T2-1 ' l 7 l I Procedures Matrix l 3 Quality Program Policies, T3-1 l 7 l j l Procedures and Instruc- T3-2 7 I tion Manuals List T3-3 l 7 l l l 1 I I I I I I I I I I I l I I I l l l 1 1 I I I I I l l l l l 1 O i I A i I TOPICAL REPORT IREV. 7 l l P I lDATE 05/31/85 l I & 1 SECTION: TABLE OF CONTENTS IPAGE TC-7 l l L l l l I I I I
T I 1 I l I 1 APPENDICES l l 1 Number Title Pm Rev. l l l l l l I A Quality Program For AA-1 7 l Transport Packages l AA-2 7 l l l AA-3 7 l '. 1 ! I l l l _I B Quality Program For AB-1 7 i l Fire Protection AB-2 7 l l AB-3 7 l l AB-4 7 l l AB-5 7 l l l AB-6 7
-l l
AB-7 7 l l AB-8 7 ! I l I I I I I I I l O l l I l l l l l l 1 1 I l l l l l l 1 I i i l l I I I I I i 1 1 I I I I I I I I I I I I I l I [ i l i I l l l I i l O !A l p l TOPICAL REPORT !REV.7 lDATE 05/31/85 l l & l SECTION: TABLE OF CONTENTS IPAGE TC-8 { L l l I l l ! I l l I L
I I I I l ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l g l QUALITY ASSURANCE PROGRAM FOR OPERATION l V l l lItisthepolicyoftheArkansasPower&LightCompany(AP&L),fromthe l l highest level of corporate management, that its Quality Assurance Program I for Operation meet the requirements of the Code of Federal Regulations, l l 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, l lrepairandmodifications,andinserviceinspectionofAP&Lnuclear l l The program shall also meet the requirements of the ASME Boiler l l plants. and Pressure Vessel Codes with respect to items constructed, repaired or l l replaced to Code requirements. l l l 1 l l Under the Program the Energy Supply Sr. Vice President, is the final l lmanagementauthorityresponsibleforassuringthatthispolicystatement l l and the Quality Assurance Program are implemented within AP&L. The l lNuclearOperationsVicePresidentandeachEnergySupplyDirectoris l l responsible for the procedural implementation of the program within his l lassignedarea. The plant's General Manager is responsible for the daily l l implementation of the Program's procedural requirements at the plant. I l l I The Quality Assurance Manager is responsible for establishing the l l Program. The Quality Assurance Manager, Energy Supply Services Director l l and the Energy Supply Sr. Vice President are responsible for approval of l ltheProgram. l l l lQualityAssurancepersonnelreportingtotheQualityAssuranceManager l l are responsible for auditing the Program as necessary and monitoring l lactivitiesrequiredbytheProgramtoassurecompliancewithits l l requirements. Disputes involving quality, arising from difference of l lopinionsbetweenQApersonnelandotherpersonnel,whichcannotbe l l settled interdepartmentally, shall be presented to the Energy Supply l lSeniorVicePresidentforresolution. l l l l l l l l l 1 I l A TOPICAL REPORT REV. 7 l l P l lDATE 5/31/85 l l & l SECTION: STATEMENT OF POLICY IPAGE A-1 l l L l l l l l I 1
I I I I l The Quality Assurance Manager is to provide for annual review of the l ladequacyandoveralleffectivenessoftheProgram. Any defects in the l 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 I I I I I I Implementation of this policy is necessary in order to achieve the l lreliabilityandsafetyrequiredatournuclearplants. Each person l l involved in activities concerning our nuclear plants is to be responsible l l for assuring quality in his own work, and for compliance with the requirements of the Program. f I The Quality Assurance Program policies, l l manuals, and procedures are mandatory requirements which must be l implemented and enforced by all responsible organizations and l I l individuals. l l l l s/Jd?2 ',2M/ ' ' I J. Griffin MUb' l l Energy Supply Sr. Vice President l l l O l oete: s~/2w sw l l l l 1 I I I I l l l l l l l l 1 I l l l l l l l l l l l l l l l 1 I I l I I I I l l I l l O lA l p l l ToPICAt aEeoaT inev. 7 lDATE 5/31/85 i l l & l SECTION: STATEMENT OF POLICY IPAGE A-2 l I L l l l l l l l
I I I I I Purchaser - The organization or organizations responsible for issuance I I a nd administration of a contract, subcontract, or purchase order. I O I l lQ-List-Alistofsafety-relatedstructures, systems,andcomponents- l l that is, those structures, systems, and components that are relied upon I to remain functional during and following design basis events to I ensure: (1) the integrity of the reactor coolant boundary, (2) the l lcapabilitytoshutdownthereactorandmaintainitinasafeshutdown l l condition, and (3) the capability to prevent or mitigate the l l consequences of accidents that could result in potential offsite l l exposure comparable to the guidelines of 10 CFR Part 100. 1 I I I I l Qualification (Personnel) - The characteristics or abilities gained l lthroughtrainingorexperienceorboththatenableanindividualto l l perform a required function. I I I I I l Qualified Party - A person or organization competent and recognized as l lknowlegeabletoperformcertainfunctions. l l l lQualifiedProcedure-Aprocedurewhichincorporatesallapplicablecodes l l and standards, manufacturer's parameters, and engineering specifications l landhasbeenprovenadequateforitsintendedpurpose. l l l lQualifiedVendorList-Alistingofvendorshavingqualityassurance l l programs consistent with the requirements of applicable portions of I l10CFR50,AppendixB. l l l Quality Assurance - All those planned and systematic actions necessary to i provide adequate confidence that an item or a facility will perform l lsatisfactorilyinservice. l l l
, lQualityControl-Thosequalityassuranceactionswhichprovideameans l l to control and measure the characteristics of an item, process, or l lfacilitytoestablishedrequirements. l l l 1 I I I I I O- l A I TOPICAL REPORT IREV. 7 l l P l IDATE 05/31/85 l l & l SECTION: TERMS AND DEFINITIONS IPAGE C-7 l l L l l I l I I l
l l l l l Receiving - Taking delivery of an item at a designated location. l l l l Repair - The process of restoring a nonconforming characteristic to a 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 l loriginalrequirement. l l l l Report-Something(document)thatgivesinformationforrecordpurposes. l 1 l l Review-Anelementofinspectiontodetermineconformancetospecified l l requirements, which can be determined by examination of documents and I activities. l l l l Rework-Theprocessbywhichanonconformingitemismadetoconformto l l a prior specified requirement by completion, remachining, reassembling or l lothercorrectivemeans. I l l Safety-Related (Q) - Safety related structures, systems, and components I are those that are relied upon to remain functional during and following l O ldesignbasiseventstoensure: (1) the integrity of the reactor coolant l l boundary, (2) the capability to shut down the reactor and maintain it in l lasafeshutdowncondition,and(3)thecapabilitytopreventormitigate l l the consequences of accidents that could result in potential offsite I exposures comparable to the guidelines of 10 CFR Part 100. l l l Source Surveillance - A review, observation, or inspection for the l purpose of verifying that an action has been accomplished as specified at l the location of material procurement or manufacture. l l l Specification - A concise statement of a set of requirements to be l l satisfied by a product, material or process indicating, whenever i appropriate, the procedure by means of which it may be determined whether l l the requirements given are satisfied. l l l l l l l l l A TOPICAL REPORT lREV. 7 l l P l lDATE 05/31/85 l l & l SECTION: TERMS AND DEFINITIONS lPAGE C-8 I I L l l l l l l l
L I I l l- l l 1. 0 ORGANIZATION I I I O i l 1.1 SCOPE i I l I 1 l l This section describes the AP&L organizational structure and l responsibilities for establishing and executing the Quality Assurance i Program for AP&L operational nuclear plants in compliance with 10CFR50, I Appendix B and applicable Regulatory Guides and ANSI Standards identified l l l in the Introduction. It also includes a description of the interfaces l lwithotherorganizationswhomaybedelegatedtheworkofestablishing l l and executing portions of the Quality Assurance Program. The AP&L I lCorporateOrganizationrelevanttotheoperationofitsnuclearplantsis l l shown in Figure 1. l l l l l . I 1. 2 GENERAL RESPONSIBILITIES I I I I 1 l 1.2.1 l 1 I l l I The ultimate responsibilities for operational nuclear plants within AP&L, l O' lincludingQualityAssurance,lieswiththeEnergySupplySeniorVice l l President. He provides management assessment of the Quality Assurance l lProgramthroughreviewofQAAuditReportsandreportsofNRCactivities. l l l l1.2.2 l l l l lTheAdministrativeServicesVicePresidentisresponsibleforthe ! I purchasing functions affecting plant operation as described in Subsection l l1.3. l l l l l1.3 CORPORATE SERVICES l , I I
- 1. 3.1 l l l l l l l l l 1 l l l l l l Q l l A l
l TOPICAL REPORT l IREV. 7 l l l P l 10 ATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION IPAGE l-1 l l L I l l I I I I
- . _ , _ _ ,3 __ --_ . _ - - _ _ _ _ . _ - . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_
I I I i l Corporate Services is responsible for the procurement of materials, parts l landcomponentsrequestedbyLittleRockGeneralOffice(LRG0) personnel l l and for supporting the procurement activities at the plant. Procurement l organization is noted in Figure 2. l l l l1.3.2 l l l lTheNuclearBuyerreportstotheSupervisorofPurchasingwhoreportsto l l the Manager, Purchasing and Stores and is responsible for the following 1
-ldutiesandactivities: l l l l 1. Prepares purchase orders based upon receipt of reviewed and l
l approved Purchase Requisitions. I I l l l l 2. Performs the commercial interface functions between AP&L and l l contractors or vendors. l l l
- 3. Assures that quality documentation prepared by Energy Supply l l l personnel are included in purchasing documents.
l l l 1.4 ENERGY SUPPLY l l l l l l Energy Supply, headed by the Energy Supply Senior Vice President is l lresponsibleforallactivitiesrelatedtotheoperationofAP&LNuclear l Plants. These activities include as a minimum: design, modification, I l maintenance,inserviceinspectionandtest,operationandthose I additional activities discussed in Sections 2 through 18 of this manual. l lWithinEnergySupply,theNuclearOperationsandEnergySupplyService l l organizations are involved in activities requiring execution of the l lQualityAssuranceProgram (See Figure 3). l l l Energy Supply Services l1.4.1 l l l l l l l l l l O i i A i l TOPICAL REPORT i lREV. 7 i l l P l IDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-2 l 1 L l l l l l l l
p i l i I I Energy Supply Services is under the direction of the Energy Supply I l Services Director, who reports to the Energy Supply Senior Vice I d(~ l i President. The Energy Supply Services Director is responsible for I 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, I l administrative guidance and supervision to the: I I I l l l a. Energy Supply Administrative Services General Manager l
- b. Engineering Services General Manager l l l c. Technical Services General Manager l
- d. Quality Assurance Manager l l l l Quality Assurance Manager l1.4.1.1 I I The AP&L Quality Assurance Organization (QAO) as shown in Figure 4 is I under the direction of the Quality Assurance Manager, who reports to the l Energy'SupplyServicesDirector. The QA0 performs review, surveillance, l l l inspection and audit functions during the operational phase of AP&L's I nuclear plants and is independent of Nuclear Operations, and from cost l
l and scheduling considerations when opposed to safety and quality l considerations. The QA Manager shall have direct access to management 1evels, which assures his ability to: identify quality problems; l l l initiate, recommend or provide solutions through designated channels; and verify implementation of solutions. l l I I I I I l The qualification requirements of the QA Manager are established within l his AP&L job description which includes the following prerequisites: l I I
- 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 I l I l l I I I I I I I I O' - I A I TOPICAL REPORT [REV. 7 I I P l IDATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION IPAGE 1-3 l l L I ., I l l 1 I I
r I I I I l 2. Possess a minimum of five years experience in the quality l l assurance or quality control disciplines with atleast two years I in the nuclear field; and l l l I l l l 3. Exhibit the ability to plan, schedule and direct the activities I of others assigned to or functioning within the QA0. l l l lThedutiesandresponsibilitiesoftheQualityAssuranceManagerinclude l the following: l l I l l 1 l 1. Develop Quality Assurance Program requirements for l 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 l 2. Audit of the quality assurance activities as described in l l Section 18 of this manual. l l 1 I I q V l 3. Review, approval and verification of the quality assurance l l requirements placed upon contractors or vendors that provide l l equipment, material, or services for AP&L nuclear plants. I I I I I l 4. Authority to stop work where conditions exist that prohibit l l effective quality control inspections, or if faulty materials, l l incorrect workmanship or procedures are detected. l l l l l l 5. Review, approval, distribution and control of QA Manuals and QA l Procedures and revisions thereto. l l 1 l 6. Review and approval of QA programs for outside organizations l l participating in the AP&L QA program. l l l l 1 l 7. Serve as chairman of the Safety Review Committee. I l l I I I I I I O' I l A I l TOPICAL REPORT l lREV. 7 l l P
; l l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-4 l l L i l I l l 1 l L
1 I I I l 8. Provide and maintain a qualified and suitable trained staff to l
/m I I carry out required staff functions.
Q l l l l
- 9. Formulate programs for maintaining the professional competence l
l of personnel within the QA0 and provide assistance in QA l training and indoctrination programs for division management, l engineering and plant personnel whose activities affect l quality. l l 1 I l 10. Provide technical direction and guidance to the Quality l Engineering Supervisors. l I I I l l 1.4.1.1.1 Quality Engineering Supervisor l l l l l l The Quality Engineering Supervisor reports to the Quality Assurance l Manager, supervises QA Engineers and Auditors / Inspectors as assigned, l l and assists the Quality Assurance Manager in the coordination of l l activities within the QA Section. The Quality Engineering Supervisor may l q l also perform duties normally assigned to Quality Assurance Engineers. l l v i l l l l i 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 l Supervisor,asassigned. The Quality Assurance Engineers are to be l l 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 l lindependenceandauthorityto: identify quality problems, initiate, l l recommend or provide solutions through designated channels, and verify l implementation of solutions. Specifically: l l l i l 1. The QAE's are to have the authority to inspect, audit or review l l I practices, records, files, instructions, directions or l l documents concerned with all areas affecting quality. l l l l l O O I l l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION IPAGE 1-5 l l L l l l l l l l
I I I - I l' 2. The QAE's are to schedule and coordinate audits or surveillance l l efforts in the areas assigned, document findings, and report l l results to the Quality Assurance Manager and the Manager of the l l audited area. l l l l1.4.1.1.3 Quality Assurance Auditors / Inspectors l 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. I I I I I l 1.4.1.2 Technical Services General Manager I I I I l l The Technical Services General Manager reports to the Energy Supply I lServicesDirectorandisresponsibleforprovidingsupporttoAP&L l l nuclear plants in the areas of plant performance, maintenance and l l availability, chemistry,environmentalmonitoring,metallurgyand l nondestructive examination. His duties include the following: I I i 1. Provides technical direction and administrative guidance to: l l l l l 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 instituting the necessary quality-related procedures and l instructions within the Technical Services Department.
l l l l
- 3. Provide for coordination of environmental surveillance programs f f I l l l l 1 l l l l O i l A i
I TOPICAL REPORT i IREV. 7 i I l P I lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-6 I I L l l l l l l l
I I I I l 4. Direct development of programs aimed at maximizing efficiency l -{ l and availability. l l
- 5. Provide for review and analysis of outage data and make l recommendations for correcting deficiencies which affect l availability or performance.
l l l l
- 6. Direct the plant maintenance support activities that are l
l assigned to the LRGO. l l l l l l 7. Serve as a member of the Safety Review Committee. l l l l l l 8. Provide and maintain a qualified and suitably trained staff to l carry out required departmental functions. l l l l 1.4.1.3 Engineering Services General Manager l l l lTheEngineeringServicesGeneralManagerreportstotheEnergySupply l l Services Director and is responsible for LRGO design and engineering l activities related to nuclear plant operations. His duties include the l l following: l l l l l l 1. Provide technical direction and administrative guidance to: l l 1 I I l a. Mechanical Engineering Manager l
- b. Electrical Engineering Manager l
l c. Civil Engineering Manager l
- d. Instrumentation and Controls Engineering Manager 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 l l l l l l l l l pJ l I A i l TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-7 l l L l l l l l l l
I I l l l 3. Provide for review and approval of LRGO design and engineering I p l activities performed by contractors, vendors, and AP&L l l personnel. l I I I I I 4. Provide for review and approval of procurement documents for i equipment, material and services for LRGO engineering projects, I as appropriate. l I l l l l 5. Provide and maintain a qualified and suitable trained staff to l l carry out required departmental functions. l l l l'1.4.1.4 Energy Supply Administrative Services General Manager l l l lTheEnergySupplyAdministrativeServicesGeneralManagerreportstothe l l Energy Supply Services Director and is responsible for the development of I ladministrativeprograms,systemsandservicessupportivetomanagement. l l His duties include the following: l I I I I l 1. Provide technical direction and guidance to: I I l a. Energy Supply Training Manager l
- b. General Services Manager l l l c. Planning, Scheduling & Cost Control Manager I
- d. Contract Administration Manager l
l l
- 2. Maintain overall department fiscal direction and control, and l l
l provides supportive accounting functions. I I I I I I 3. Provide contract administration and administration of I procedures for Energy Supply Little Rock General Office (LRGO) l I activities. l I I I I l 4. Administration of the training and development effort for i Energy Supply LRGO personnel. l l l l l O i I A i l TOPICAL REPORT i IREV. 7 l l P l lDATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION lPAGE 1-8 l l l L I l l l l l 1
l l l . I l 5. Ancillary support services to Energy Supply operation sections. l l l Cm l l 6. Provide and maintain a qualified and suitable staff to carry l l I out required departmental functions. I I I l 7. Serve as a member of the Safety Review Committee. l l l l l l 8. Assure conformance to the Quality Assurance Program by l l instituting the necessary quality-related procedures and l I I l instructions within Administrative Services. l l l l l l 1.4.2 Nuclear Operations l l 1 I i l Nuclear Operations is under the direction of the Nuclear Operations Vice l l President who reports to the Energy Supply Senior Vice President and is l responsible for the formulation, licensing, implementation and discharge l of operating policies and procedures relative to nuclear plant operations l l and for nuclear fuel management. His duties include the following: l l 1 1 I p l 1. Provide technical direction and administrative guidance to the: l V I I I I l a. Plant's General Manager l l b. Nuclear Services General Manager I I I l c. ANO Projects Manager l l l l 1 l 2. Assure conformance to the Quality Assurance Program by l instituting the necessary procedures and instructions within l the Nuclear Operations Department. l l 1 I I l 3. Provide for review and approval of design and engineering l performed for the operating nuclear plants. l l l
- 4. Provide for review and approval of procurement documents for l
l equipment, material and services. l l l l l l l O' I l A I I TOPICAL REPORT I IREV. 7 I l l P l lDATE 5/31/85 I I & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-9 l l L I I I I I I I
(
~
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~ .
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s + . s l l 5. Povide for' H aison between AP&L and applicable regulatory l I I agencies. (m~j l o l l l
- 6. Provide and aintain a qualified and suitable staff to carry g
l , g out required d.epartmental functions. < l 1 - a + . l 1 yl f ,a _ cProvide tor procdrement and design review of nuclear fuel.
'_N- l
'l e J._ l p 's
, i A ' '
l 5 jf N q l q- l' 8. Syeral!, responsibility for the fire protection program l g4 a .s - g
.\ . implemented at the nuclear plants.
.; I l
,4-l .
i ( , o 6\ l , L.4. 2'.1 Nuclear Services General Manager l
\ le l
,' lITheNuclearServicesGeneralManagerreportstotheNuclearOperations l
l Vice President and is responsible for providing the necessary support l l l g services <relatedtopeeffectiveoperationandmaintenanceoftheAP&L g , l nuclear plan. Re futies idclude the following: l l 's i 3 l 1 - l
- 1. Provide technical direction and administrative guidance to the:
() l . l l l I I
< o), a. Lictasing Manager l g,'/ h~ b. Nuclear Pr'op ams Manager Nucle'ar Fbs1 Supervisor l / c. l l l l ' l l ,' 2. Interface with other; departments to assure effective l implementation of Regulatory and Company requirements.
l l l t'g % 3. Communication interface dealing with all activities at the l
.: l, nuclear plants. I o -
, 1 I I
+
l 4j Serve as a member of and provide administrative support to the I i f Safety Review Committee.
/g / y
" l g
I ( l I 4 l r l t,
.-f l l_i l P) l J l l TOPICAL REPORT I
lREV. 7 l l s,i4 l f [A P l lDATE 5/31/85 l T ,3 . iI
+- , & { SECTION: 1.0 ORGANIZATION lPAGE 1-10 l V, ', ' L, ,y l I 7[ l & I I i
._ ___\_____i_
l I I I
! 3.4.4 I I
g' i l Design work performed by organizations outside of AP&L is to receive a I I l l l l documented review and approval by engineering personnel in accordance ; I with LRGO and plant departmental procedures. 1 I I I I l 3.5 DESIGN CHANGE I I I I I I 3.5.1 I I I I I I Methods for the preparation, review, approval and implementation of l I I l design changes, including field changes, are documented in departmental l l procedures for Engineering Services and Plant Engineering. Design l I I l changes are subject to review and verification by the same organization l l which reviewed and verified the original design unless otherwise l I I l specified in departmental procedures for design control. If minor l l changes to an approved design are required to meet plant requirements or l l conditions,FieldChangeNotices(FCN)maybeissuedorotherwise l I documented by a cognizant engineer and transmitted with the changes for l O/ I l review and approval in accordance with Plant Engineering Administrative I l l Procedures. l l l l l l 3.5.2 I I I I i l Changes from specified design inputs, such as design bases, regulatory I I l l requirements, codes and standards (including quality standards) are to be ; I identified, approved, documented and controlled through applicable LRG0 l l l l and plant departmental procedures. l 1 1 1 l l 3.5.3 l l l l l l During preparation of a design change, the responsible engineering g I organization is to perform a safety and environmental evaluation per l l l l l I I I I O\ I l A I I TOPICAL REPORT I IREV. 7 I l l P l IDATE 5/31/85 I I & 1 SECTION: 3.0 DESIGN CONTROL IPAGE 3-4 l l L l l l l l l l
l l l I l "off-the-shelf" items, reference to the items catalog number and l g identification number may be included on the procurement document in lieu V l of a design specification. New or revised specifications for replacement l l l litemsaretobeevaluatedbytheresponsibleengineeringorganization l against the original specification for the item. The evaluation is to be l l linaccordancewithapplicableengineeringproceduresandresultsinthe l l establishment of new baseline and technical quality requirements, which l laretobeusedforsubsequentprocurements. l l l l4.2.3 l l l lProcurementdocumentsarealsotoincludetheidentificationofquality l assurance program requirements applicable to the items or services l l procured. Procurement documents also establish requirements for source l l audits and insp#tien, extension of the procurement requirements to lower l l tier suppliers or subcontractors, and preparation and delivery of l l documentation. These requirements n:ay eithcr be in the form of documents l lattachedtotheP0orContractorbyincorporatingtheminthespecific l l design specifications. Quality programs are to be specified by invoking l ltheappropriatesectionsof10CFR50, App.B,theappropriateANSI l l standards and/or the appropriate AP&L generated quality requirements for l litemsorservices. The appropriate sections of the ASME Boiler and l l Pressure Vessel Code are to be invoked for items originally designed to l lmeetASMErequirements. l l 1 l4.3 REVIEW OF PROCUREMENT DOCUMENTS l l 1 lTheresponsibleQualityAssuranceorQualityControlorganization,as l l identified in the LRG0 and plant procedures for procurement and contract l ladministrationactivities,istoreviewallprocurementdocumentsto l l assure that the required quality requirements (including source l surveillance and/or inspection) are imposed on suppliers / contractors. l l 1 I I I I I I I I A l l l l kl l A l TOPICAL REPORT lREV. 7 l l p l lDATE 5/31/85 l l & l SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l l L l l l l l l I e )
r I I l l l 1.4.2.1.1 Nuclear Fuel Supervisor l I fw l Q l l The Nuclear Fuel Supervisor reports to the Nuclear Services General l l lManagerandisresponsiblefortheprocurement,designreviewand l performance evaluation of nuclear fuel. The Nuclear Fuel Supervisor also l lprovidessupporttotheplantintheareasofreactorcoreperformance l and assessment of core design analysis. l l l l l l i l 1.4.2.1.2 Licensing Manager I i lTheLicensingManagerreportstotheNuclearServicesGeneralManagerand I is responsible for the coordination of all licensing documents, l lrequirementsandrevisionstheretowhicharerequiredtobereviewed and/or approved by the NRC and for interfacing with the NRC. l l The l lLicensingmanagerisalsoresponsibleforthereviewandapprovalof l l Q-List changes and for the tracking of possible nuclear safety concerns l ltoassuretimelycloseout. O l I C 1.4.2.1.3 Nuclear Programs Manager l l l The Nuclear Programs Manager reports to the Nuclear Services General l l Manager and is responsible for providing support to the nuclear plants in l ltheareasoffireprotection,emergencyplanning,radioactivewasteand l health physics / radiation protection. I I I I I l 1.4.2.2 Projects Manager l l l l l l The Projects Manager reports to the Nuclear Operations Vice President and l is responsible for providing services to the nuclear plants in the areas l l of construction activities, control room simulator modifications used for l
,I operator training, and review, approval and coordination of design l l changes through the Little Rock General Office. His duties include l I
providing technical direction and administrative guidance to the: l 1 1 I
]
l l A l l TOPICAL REPORT l lREV. 7 l l l P l 10 ATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-11 l l L l l l 1 I I l
I l l l l a. Field Construction Manager i q l b. Project Services Supervisor l l c. Special Projects Coordinators l l l l l l 1.4.2.2.1 Field Construction Manager l l l l l l The Field Construction Manager is responsible for directing the l lactivitiesofhisstaffrelatingtoworkassociatedwithplant l l construction and modifications. His duties include: 1 I l l l l 1) Interface with other departments to assure effective l l implementation of job assignments l l l l 2) Provide cost and schedule controls for departmental activities l l l l 3) Provide technical and administrative guidance to the l Construction Quality Control (CQC) Supervisor. The CQC l l Supervisor is responsible for the surveillance and inspection l l of activities performed under the direction of the Field l l Construction Manager, and shall have sufficient authority and l l organizational freedom to: identify quality problems; I l initiate, recommend or provide solutions through designated l l channels; and verify implementation of solutions. The CQC l l Supervisor is also responsible for assuring adequate inspection l l points have been assigned for the work activity, inspectors I have been certified to ANSI N45.2.6, directing the activities l of the inspectors, and interfacing with the Code Inspector for l [l activities involving Code items. l l l l1.5 PLANT ORGANIZATI'ON l l l General Manager l1.5.1 l 1 I I I l l l l l l O i I A l TOPICAL REPORT i lREV. 7 l l l P l lDATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-12 l l L l l l l l l l l
- - - - - - . _--_--_----__-.___-_----J
I I I l l 1.5.1.1 l l l I (] l The General Manager reports to the Nuclear Operations Vice President on l I the corporate level (see figure 5) and has direct responsibility for operating the plant in a safe, reliable and efficient manner. l l He is I responsible'for operating the plant in accordance with the provisions of l the operating licenses, including the on site quality program. l l l l l l 1.5.1.2 1 I I 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 i 1.5.1.3 l l l The General Manager is to provide technical direction and administrative l guidance to the: l l l l l l 1) Operations Manager l C l
- 2) Maintenance Manager l
, g l 3) Administrative Manager l
- 4) Engineering and Technical Support Manager Special Projects Manager l
l 5) l
- 6) Manager, Nuclear Quality Control l l j
l 7) Work Control Center Manager I I l l l l l 1.5.2 Operations Manager l l 1 , I I 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 and interfaces with the Maintenance Manager to accomplish I operation-related maintenance activities. The Operations Manager is to l provide technical direction and administrative guidance to the: l l l l 1 I I
- I I
l O O I l A I I TOPICAL REPORT I lREV. 7 I l P l l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION lPAGE 1-13 l l L l l l I I I I l
I I I I I 1) Operations Superintendents I (' 2) Operations Technical Staff l l l l l1.5.2.1 l l l
'The Operations Superintendents report to and assist the Operations l Manager in directing the day-to-day operation of the power plants. They I are responsible for coordination of the daily review of operating l surveillance tests and coordination of operation-related maintenance I activities. They are to assist the Operations Manager in the supervision l
l of core refueling, which includes advance planning for the outage, plant l l preparation,equipmentcheck-outandtherefuelingoperations. l l l l1.5.2.2 l l l The Shift Supervisors report to the Operations Superintendent and are l l responsible for the actual operation of the unit and for the activities l of the operators during their assigned shift. The Shift Supervisor is to l be cognizant of operation activities being performed while on duty. The I g Shift Supervisor on duty has the authority to shut down the unit if, in g I his judgement, conditions warrant such action. I I I I I l 1.5.3 Maintenance Manager I I I I l l The Maintenance Manager (Figure 6) is responsible for the maintenance of l lplantequipmentandfacilitiesasdefinedbyplantmaintenanceprogram l l implementing procedures and to assure that maintenance of equipment is I conducted in conformance with applicable standards, codes, specifications l l and procedures. The Maintenance Manager is also to coordinate l l operation-relatedmaintenanceactivitieswiththeOperationsManagerand l is responsible to make repairs on any structure, system or component l under his control. The Maintenance Manager is to provide technical l I direction and administrative guidance to the: l I I I l l l l l fj v l l I I I A l TOPICAL REPORT lREV. 7 I I P l 10 ATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE l-14 l l L I l l l l 1 I
I I l l l 1. Mechanical Maintenance Superintendent l I
/ 2. Electrical Maintenance Superintendent I t, I l l 3. Instrument & Control Superintendent l
- 4. Senior Maintenance Coordinator l 5. Shift Maintenance Superintendent l l l 1
l l 1.5.4 Engineering and Technical Support Manager l l l i I l The Engineering and Technical Support Manager (Figure-7) is responsible l for providing plant engineering support services as well as technical and l plant analysis and health physics support services to the plant staff. l The Engineering and Technical Support Manager is to provide technical direction and administrative guidance to the: l l l l 1 l l l 1) Technical Analysis Superintendent l
- 2) Plant Analysis Superintendent l
l 3) Plant Engineering Superintendent l
- 4) Operations Assessment Superintendent g l 5) Health Physics Superintendent. l
. V I I I i l 1.5.4.1 Technical Analysis Superintendent l l l I I l The Technical Analysis Superintendent maintains overall responsibility l for radiochemistry, chemistry and environmental programs at the plant. l l The Technical Analysis Superintendent is also responsible for maintaining l ltheStationEmergencyPlanandensuringtheplantstaffiscapableof l implementing the requirements delineated in the Plan and its procedures. l l l l l l 1.5.4.1.1 l l l l l l The Radiochemistry Supervisor reports to the Technical Analysis l l Superintendent and is responsible for analyzing the reactor plant water conditions and providing recommendations to maintain conditions. l l l l l l l l l l l A I TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-15 l l L l l l l l l 1
I l l l l 1.5.4.1.2 l l C l I I l The Chemistry and Environmental Supervisor reports to the Technical l lAnalysisSuperintendentandisresponsibleforestablishingwater l l chemistry criteria, analyzing secondary plant water and auxiliary water I conditions an,d providing recommendations to maintain conditions within l l acceptable limits. I I I I I l 1.5.4.2 Plant Analysic Superintendent l l l l l l The Plant Analysis Superintendent is responsible for the areas of plant l performance,nuclearsupportandcomputersupport. A supervisor is l l l provided for each of these areas. I I I I I i 1.5.4.2.1 I I I I I I The Plant Performance Supervisor reports to the Plant Analysis l Superintendent and is responsible for: evaluating equipment and system l l l performance over extended periods, recommending methods of improving and I lmaintaininggoodplantefficiency,investigatingandevaluatingequipment l l malfunctions or failures and recommending corrective action to prevent l recurrences,andcoordinatingtheactivitiesoftheInserviceTesting l l l Program at the plant. l I I I I i 1.5.4.2.2 I I I I I l The Nuclear Support Supervisor reports to the Plant Analysis l lSuperintendentandisrespcnsibleformonitoringreactorcoreandNuclear l l l Steam Supply System (NSSS) performance; conducting reactor performance l landphysicstestingtoassuresafeandreliableoperationandtoprovide i l current accurate information to operations; collection and transmittal of I lnuclearfuelmanagementdatatotheNuclearFuelSupervisorinLittle l l Rcck and the reactor vendors as required; on-site safeguards and l laccountabilityofthenucleacfuel;andassistingintheplanningofall l l l l l l C I I A I l TOPICAL REPORT I IREV. 7 I l l P I lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-16 l l L I I I I I I I
I I I I l fuel movements including new fuel receipt and inspection, fuel shuffling l at refueling, inspection of irradiated fuel and shipment of spent fuel. I I l1.5.4.2.3 l l l The Computer Support Supervisor reports to the Plant Analysis l Superintendent and is responsible for the maintenance, revision and l development of computer software for the plant monitoring computers and l l for providing technical assistance to the Nuclear Support Supervisor and l lNuclearEngineersindevelopmentanduseoftestapparatusforevaluation of fuel, core and NSSS performance. l l l l l 1 I l 1.5.4.3 Plant Engineering Superintendent l l l l l l The Plant Engineering Superintendent is responsible for drawing control, l limplementationandcoordinationoftheInserviceInspectionProgramand design and plant engineering activities at the plant. The Plant l l l Engineering Superintendent is to provide technical direction and g l administrative guidance to the: l W l i I I l 1) Mechanical Engineering Supervisor [
- 2) Electrical Engineering Supervisor l l l 3) Drafting and Drawing Control Supervisor. l l l l l l 1 5.4.4 Operations Assessment Superintendent l l l 1 l l The Operations Assessment Superintendent provides the capability to l perform engineering evaluations of operating experiences which occur both l at the AP&L nuclear plants and at other nuclear power plants and to l recommend corrective actions as a result of these evaluations to help l
l plant operations personnel in preventing or dealing with similar l locurrences. I I I I I I I I I : l O' l A l l TOPICAL REPORT I lREV. 7 l l l P I 10 ATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-17 l l L l l l l l l 1
o I l l I l 1.5.4.5 Health Physics Superintendent l l l O i l The Health Physics Superintendent is directly responsible for and has the i I 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 work in radiation areas if he determines that a potential for an l unanticipated excessive exposure to plant personnel or the environment I may exist. l l l l l l 1.5.5 Administrative Manager l l l l l l The Administrative Manager (Figure 8) reports to the General Manager and I aids him in the administrative aspects of the plant's operation. The l Administrative Manager directs the activities of the administrative staff I and provides technical direction and administrative guidance to the: 1 I
- 1) Office Services Supervisor l 2) Material Management Supervisor l V 3) Human Resources Supervisor l l l 4) Training Superintendent l
- 5) Plant Controller l l l l l1.5.5.1 l l l The Office Services Supervisor is responsible for administration of the l clerical staff activities and the accumulation and disposition of quality I assurance records related to all phases of the nuclear plant.
I I l1.5.5.2 l l l The Material Management Supervisor is responsible for plant procurement, l l storage of materials, parts and equipment, issuance of tools and test l equipment and the disposal of surplus materials. l l l l l O' v I A I TOPICAL REPORT I 7 I l l lREV. l l P l lDATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION lPAGE 1-18 l l L l l l l l 1 I
1 I I l l 1.5.5.3 l , 1 l The Human Resources Supervisor is responsible for employment, industrial relations, industrial safety and fire prevention and security. Reporting I to him are the Safety and Fire Prevention Coordinators, the Security l Coordinator, and the Employment and Industrial Relations Coordinator. l l l l1.5.5.3.1 l l l The Safety and Fire Prevention Coordinators are responsible for l conducting periodic checks to examine control of combustables, l housekeeping and other fire prevention / protection efforts as well as to l provide a centralization of OSHA and plant safety programs. l l l 1 l l 1.5.5.3.2 l l 1 l l l The Security Coordinator is responsible for coordination of the efforts l lofthesecurityforceandtomanagetheoperationofthesecuritysystem. c'] l l l1.5.5.4 l l l lTheTrainingSuperintendentisresponsibleforthetrainingand l retraining of plant personnel and of Little Rock General Office personnel I as established by Plant procedures. Ie l I 1.5.6 Manager, Nuclear Quality Control I l l l l The Manager, Nuclear Quality Control (Figure 5) is responsible for 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 Plant Quality Control department shall have sufficient authority and l lorganizationalfreedomto: identify quality problems; initiate, l recommend or provide solutions through designated channels; and verify l implementation of solutions. His duties include the following: I I I (,) I l I I I l A l TOPICAL REPORT lREV. 7 l l P l 10 ATE 5/31/85 l l & l SECTION: 1.0 ORGANIZATION lPAGE 1-19 l l L l 1 l 1 I I l
I I I I l 1) Provide technical direction and administrative assistance to l the: I l
- a. Quality Control Engineering Supervisor
- b. Quality Control Supervisor l
l l
- c. Quality Control Engineers l l l d. Quality Control Inspectors l l l l 1 l 2) Interface with the Quality Assurance Manager or his l representative for technical assistance in resolving l
l significant conditions adverse to quality. l l l l l l 3) Authority to place an item in a nonconforming status when such I an item is determined to be in violation of purchase documents, l l applicable codes and standards or FSAR requirements. I I I I I l 4) Assuring surveillances, inspections and reviews of plant l 1 l activities and documents are conducted in accordance with plant procedures. l l l l l l 1.5.7 Special Projects Manager l l l l l l The Special Projects Manager is responsible for the administration and I control of special projects pertaining to plant operations, maintenance and administration and is to provide technical direction and l l l ladministrativeguidancetoastaffofSpecialProjectCoordinators. l Additional duties include: I I I l l l 1) Serving as chairman of the Plant Safety Committee I l l i I l 2) Interfacing with on site regulatory agencies l l l 1 l l 3) Providing evaluations and recommendations to regulatory l requirements and meeting regulatory commitments. l l l l l C I l A l l TOPICAL REPORT l lREV. 7 l l l l P l lDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-20 I I L l l l l l l l
I l l l l 1.5.8 Work Control Center Manager l l The Work Control Center Manager is responsible for the l I planning / scheduling of station work activities and the maintenance of the l equipment history and associated reports. He supervises the Work Control l Center staff and interfaces with the Operation Manager and Maintenance l Manager to accomplish the scheduling of the outage /non outage work l activities. The Work Control Center Manager is to provide technical direction and administrative guidance to the: l l l l l l l l 1) Scheduling Supervisor l
- 2) Flanning Supervisor Maintenance History Supervisor l
l 3) l I I I I l 1.6 INDEPENDENT REVIEW ORGANIZATIONS l l l 1 I 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 q l established the following committees as a management tool to l V independently review activities occurring during the operational phase of l a nuclear plant. l l l l l l 1.6.1 Safety Review Committee (SRC) l 1 I I I l The SRC reports to the Nuclear Operations Vice President and is l responsible for providing off-site independent reviews, and/or audits l l relating to: the Safety Analysis Report, Technical Specifications, l Procedures and changes thereto; unreviewed safety questions; violations, l l deviations and reportable events; and any other matter involving safe l operation of the nuclear plant which the committee deems appropriate or l is referred to them by the on-site operating group. The SRC is also to l review the reports and meeting minutes generated from the Plant Safety I l Committee. l l l l l l 1 C) l l A I l TOPICAL REPORT I lREV. 7 I l l P l 10 ATE 5/31/85 l l & I SECTION: 1.0 ORGANIZATION lPAGE 1-21 l l L l l l j l i I l
l I I I l 1.6.2 Plant Safety Committee (PSC) I o l l The PSC reports to the plants' General Manager and is responsible for l I reviewing activities specified in the Administrative Technical l l Specifications for the purpose of: I l l l I l 1) Rendering determinations in writing with regard to whether or l not an unreviewed safety question (defined by 10CFR50.59) is l l involved; and l I I l l l 2) Furnishing written recommendations to the plants' General l l Manager for approval of disapproval. l l l These activities include changes to plant procedures and Technical l l Specifications, proposed modifications to plant systems, changes to l l plant security and emergency plans, and review of facility l l operations to detect potential nuclear safety hazards. l I I I I q l 1.6.3 Committee Structure I U l l I l l The organization structure and administrative requirements specific to l leachcommitteearedescribedintheplants'TechnicalSpecificationsand l l in internal procedures /docLmentation. I I I I I l 1. 7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES I I I
; I I l As owner and operator, AP&L assumes full responsibility and authority for l ltheplantincludingactiontoassurethattheplantisoperatedin l l accordance with sound engineering practices, Licensing requirements and l lapplicablecodes,specificationsandprocedures. l l 1 l lEachsupplierofequipment,materialorservicesandeachmaintenanceor l I modification contractor is responsible for administering the applicable l lqualitycontrolfunctionsasrequiredbyAP&L. The Quality Assurance and l
l l l l O i l A i l TOPICAL REPORT i lREV. 7 l l l P I 10 ATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-22 l l L l l l l l l l t
I l I I l Quality Control organizations are responsible for assuring by l v l surveillance, inspection,auditorreviewofobjectiveevidence(e.g., l review audit reports conducted by others, etc.) that these functions are I accomplished for systems and structures that affect the safety and I integrity of the plant. I I I l l l Visits to manufacturer's shops by Quality Assurance organization l l personnel are conducted, when deemed necessary, based upon safety I significance, complexity, method of acceptance and past history of the l l vendor,toestablishproductqualityandtoassurethatqualityassurance l l and quality control programs function in accordance with AP&L l requirements. l l l l lTheAP&LEnergySupplyOrganizationalChart(FigureF-3)showsthe I reporting relationships and the lines of communication established l lbetweentheQualityAssuranceandQualityControlorganizations. These I lines of communication are established between the various quality I organizations in order to provide assistance and/or information, when I requested, in verifying satisfactory implementation of the quality l lprogramandinresolvingsignificantconditionsadversetoquality. l l l l l l l l l l l 1 1 I I I I I I l l l l l l l l l l l l l l l l l l l l l l l l l l l l l A I TOPICAL REPORT IREV. 7 l l p I IDATE 5/31/85 l l & 1 SECTION: 1.0 ORGANIZATION IPAGE 1-23 l l "L l l l l I I l
r I I I I l 2.2.2 l o L' l l The quality program for transport packages is addressed in Appendix A of l l this manual, and implemented through appropriate LRGO and plant l procedures. The effectiveness of this program is verified through l scheduled audits conducted by the QAO, under the cognizance of the SRC. l l l
- 2. 2. 3 l l 1
I lThequalityprogramforfireprotectionisaddressedinAppendixBof l this manual and in the applicable section of the FSAR for each operating l nuclear unit, and implemented through appropriate LRGO and plant l procedures. The effectiveness of the fire protection program is verified l through scheduled audits conducted by the QA organization, under the cognizance of the SRC. l l l l l l l l 2.2.4 l l l l l l The Q-list is under the control of the Licensing Manager. The Licensing l Section maintains an up-to-date list of personnel issued a copy of the lQ-listandassuresthatreviews,approvalsanddistributionso l l l lQ-listandchangestheretoareperformedinaccordancewithapproved l l procedures. Changes to the Q-list require review / approval by the l I discipline Engineerirg Manager, Quality Assurance Manager and Licensing l Manager. l l l I I I l 2.2.5 l l l l l l The following expendable and/or consumable items are to be controlled in l the following manner to assure service quality: l l l l 1. Diesel Fuel - Service quality is assured by applicable provisions / tests required by the Technical Specification for l l l each operating nuclear unit. l l l l O l V l A l l TOPICAL REPORT l lREV. 7 l l l P l 10 ATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-2 l l L l l l l l l l
1 I 1 l l
+
l 2. Welding Rod - Service quality is assured by procurement from an l n evaluated source, requiring material test results when l j U l specified by the ASME Code or applicable design document, and l j l controlling the rod on-site prior to use, to prevent l degradation. l l l l I l 3. Boric Acid - Service quality is assured by procurement from an l evaluated source, requiring a batch analysis to assure l l conformance with our specification requirements, and on-site l control prior to use, to prevent degradation. l l l l l RESPONSIBILITIES l2.3 l 1 l l2.3.1 l l l AP&L recognizes that quality assurance is an interdisciplinary function l l involving many organizational groups, encompasses many functions and l activities and extends to various levels in all participating l l organizations (from the Energy Supply Senior Vice President to all l V lworkerswhoseactivitiesmayinfluencequality). This quality program l l designates responsibilities and duties of specific individuals, which may I lbeperformedbytheirappointeddesignees. l l l l2.3.2 l l l This quality program assigns the responsibility for quality to the l l departments performing the work and includes as a basic requirement that l individuals responsible for verification of conformance are qualified and l l do not perform or directly supervise the work. Additionally, independent l reviews, audits and surveillances are provided by individuals not l l reporting to the groups responsible for performing the work. l l l l l I I I I I I I l l l A l l l l V l A l TOPICAL REPORT lREV. 7 l l P l 10 ATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-3 l l L i i l l I I l
i 1 , I I J l 2.3.3 l ; I i ) p> I 1 l This quality program also includes provisions that require suppliers, l contractors, subcontractors, consultants, etc. to maintain and use l quality assurance programs reviewed and approved by the Quality Assurance l l Manager. Audits or surveillances by the QA0 provide assurance of compliance with applicable procedures. l l l l 1 1 I l 2.3.4 l l l l I l The Nuclear Fuel Supervisor within Nuclear Operations is responsible for l ltheassurancethatnuclearfuelusedinAP&Lnuclearplantsisdesigned, l l procured, manufactured, and utilized in accordance with regulatory l requirements,andrelatedindustrialcodesandstandards. On-site i l l l quality control of nuclear fuel is implemented through the use of plant l l ladministrativeprocedures. These procedures include the receipt, l , l inspection, handling, storage, and accountability of Special Nuclear l I Material (SNM). The Nuclear Support Supervisor maintains a listing of those individuals qualified to perform receipt inspections. l l l O i I i l l 2.4 PROCEDURES l l l l l l 2.4.1 l l l l l l Activities which affect quality are defined in appropriate procedures, l which are developed to cover AP&L administration and control. The l 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 lsurveillancesandaudits.The program and the procedures shall be l l modified or supplemented from time to time as the need for change arises l lduringthelifeoftheplant. Quality program policies, procedures and l l instructions are contained in the documents listed in Table 3. l l l l l l l l l O I l A I l TOPICAL REPORT I lREV. 7 I l l P l lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-4 l l L l l l l l l l
I I I I l 2.4.2 l l 1 P I l l Procedures assure that activities affecting quality are performed under l lsuitablycontrolledconditions. Controlled conditions include the use of l appropriate equipment; suitable environmental conditions for performing l l ltheactivitysuchasadequatecleanness;andassurancethatrequired prerequisites for the given activity have been satisfied. l l Administrative l lproceduresalsoassurethattheneedforspecialcontrols, processes, l test, and equipment to attain the required quality and the need for l l lverificationofqualitybyinspections,evaluationortestistakeninto l account. l 1 1 I I l 2.4.3 l l I I I l Other AP&L organizations outside of Energy Supply may establish written l lprocedurestocontrolsupportactivitiesaffectedbytherequirementsof l this quality program. Procedures developed by such organizations are l lpreparedandreviewedfortechnicaladequacywithinthecognizant l organization, reviewed by the Quality Assurance Manager and approved by l l lthecognizantorganization'sdepartmenthead. l l l l2.5 PROGRAM REVISION AND CONTROL l l l l2.5.1 l l l lProgramrevisionandcontrolshallbetheresponsibilityoftheQuality l l Assurance Manager. l 1 I I I l 2.5.2 l l l l l l Proposed changes to the Quality Assurance Program for Operations are to l lbesubmittedbytheQualityAssuranceManagertoaffectedLRGOandplant l l l l l l l l l Od I l A I l TOPICAL REPORT I lREV. 7 1 l l P l lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-5 l l L l l l l l l l
I I I I I management personnel for review and coment prior to approval and l I transmittal to the Nuclear Regulatory Comission. After resolution of I l comments, changes are to be approved by the Quality Assurance Manager, lEnergySupplyServicesDirector,andtheEnergySupplySeniorVice President. l l l 1 1 I l l 2.5.3 l l 1 I I l The Nuclear Regulatory Commission is to be notified of changes to this l lqualityprogramannuallyforthosechangesthatdonotreducethe l l commitments in the program description previously accepted by the Nuclear l lRegulatoryCommission. Changes to the program description that reduce l l the commitments are to be submitted and approved by the Nuclear l Regulatory Commission prior to implementation. The Quality Assurance l l Manager is to determine if changes do or do not reduce the commitments of l lthisqualityprogram. l l l l2.6 PERSONNEL l l l O l2.6.1 l l l l Erployees whose duties and responsibilities are related to the quality l l p.*ogram activities at or in support of the nuclear plant are to I participate in appropriate indoctrination and training programs to assure l l that suitable proficiency is achieved and maintained in the work they are l performing. Such training shall include, as a minimum: plant security; l l l discussion of the overall Company policies, procedures and instructions l lwhichestablishthequalityprogram;anexplanationoftheAP&Lquality l l organizations; and a discussion of those procedures which implement the l lqualityprogramrelatedtotheemployee'sspecificjob-relatedactivity. l l 1 I I I l l l l 1 I I l l 1 I I l O- l A l TOPICAL REPORT lREV. 7 l l P l l0 ATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 l l L l l l l l l l
I I I l l 2.6.2 I l l l .Q l The education, experience and responsibility requirements of individuals l l linvolvedinthisqualityprogramaredocumentedinjobdescriptionswhich l l are approved and periodically reviewed by management. Requirements for l l education,experienceandproficiencylevelsarecommensuratewiththe l degree of importance of the job assignment. Experience and training l l l requirements for plant staff personnel are to meet the requirements of l l ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted l linTable1. Personnel whose qualifications do not meet those specified l l in ANSI N18.1-1971, and who are performing inspection, examination and l ltestingactivitiesduringtheoperationalphaseoftheplant,aretomeet l the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. l l 1 I I i l 2.6.3 l 1 I I I l Personnel performing inspection and examination activities are to be l lindoctrinatedandtrainedtoassuretheyareawareoftherequirements l l which govern their activity. Inspection and examination personnel are to l O leequaiifiedaccordingtothea,,iica.iecodes, standards, j l specifications, regulatory requirements and LRGO and plant procedures. l lPersonnelperforminginspectionsonthoseactivitiesoccurringduringthe l l operational phase that are comparable in nature and extent to related l lactivitiesoccurringduringinitialplantdesignandconstructionareto l l meet the provisions of Regulatory Guide 1.58, rev. 1 (9/80) and ANSI l lN45.2.6-1978, in lieu of ANSI N18.1-1971. l l 1 l2.6.4 l l l lPersonnelinvolvedwithweldingofmaterials,systemsorcomponentsare l l to meet the appropriate qualification requirements of the ASME Boiler and l lPressureVesselCode,SectionsIIIandXI,orforstructuralwelds,the l l 1 I I I I I I I I O I l A p I l TOPICAL REPORT I lREV. 7 l l l l lDATE 5/31/85 l l & l SECTION: 2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-7 l l L l l l l l l l
l i I l l American Welding Society (AWS) Structural Steel Code 01.1. Personnel l involved with nondestructive examination of materials, components or l systems are to meet the qualification requirements of the American l l Society Nondestructive Testing Standard SNT-TC-1A, or ASME Section III l and XI for ASME Code materials, components or systems. Personnel are to l l lbecertifiedtoperformthesetasksinaccordancewiththesecodesand l standards. l l l l l l l 2.6.5 l l l l l l Personnel performing audits of the quality program are to meet the l experience, training and qualification / certification requirements of l lANSIN45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise l l lnotedinTable1. l l l l2.6.6 l l l l Training records are to be maintained in accordance with approved procedures. For formal training programs, documentation is to include l l l ltheobjective,contentoftheprogram, attendees,anddateofattendance. l l l l 2.7 PROGRAM REVIEW l l l 2.7.1 l l l l I The Quality Assurance Manager is responsible for a review of this program on an annual basis to determine the effectiveness and proper l l l limplementationofthequalityprogram. l l l 2.7.2 l l l lManagementreviewsofthestatusandadequacyofthequalityprogramare l l accomplished through regular reports and presentations by the QA0 and l l 1 I I O d I I I l I A I TOPICAL REPORT IREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-8 l l L l l l l l l l
i l i I l through reviews of quality assurance audit reports. Quality Assurance l lreportssupplydataonthestatusofoutstandingauditandcorrective l d I action items and may identify the status of other significant quality l lprogramactivitiesasrequestedbymanagement. l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I . I I I I I I I I I I I I I I I o l l l l l 1 I I I I I I I I l l I l i I I I I I I I I I I I I I I I l l I I I I I I I I I I I l I O- l A I I TOPICAL REPORT I IREV. 7 I l l P l IDATE 5/31/85 I I & 1 SECTION: 2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-9 I I L I I I I I I I
- I I
I I I 3.2.2 l .I I ' I Q l l Design standards and requirements are to be at least equivalent to those I l lemployedduringtheconstructionoftheplantandaretobeconsistent l l with the technical specifications and license requirements. l 4 I I I l 1 3.3 DESIGN INTERFACE I l l l l l Design control activities include measures for the identification and l lcontrolofdesigninterfacesbetweenthevariousengineeringdisciplines ' l I within the department, between LRGO and plant engineering personnel, I l between engineering personnel and other AP&L support organizations, and l I between engineering personnel and firms / suppliers outside the AP&L l organization. These measures include the development of procedures among l i l the participating organizations for the review, approval, release, I distribution and revision of documents involving design interface. l l l Coordination of the interface control is the responsibility of the I , loriginatingorganization'smanagementunlessotherwisespecifiedinan l l AP&L procedure applicable to the design activity. Design information l lbetweeninterfacingorganizationsistobedocumentedandretainedfor l l permanent records. l I I l l l i 3.4 DESIGN VERIFICATION l l l l l l 3.4.1 l l l ' l l l To assure the design is adequate and the above requirements and I t l l l prou.hres are implemented, Engineering Services for LRGO design or Plant ; l l Engineering for plant design are to verify the adequacy of the design l
- lthroughtheperformanceofdesignreviews,theuseofalternateor l l simplified calculation methods, or the performance of a qualification I ll l l
1 L I
> l I
- l l I l l i I O
V I I I I I A I TOPICAL REPORT IREV. 7 l l P l 10 ATE 5/31/85 l I & 1 SECTION: 3.0 DESIGN CONTROL IPAGE 3-2 l l L l l l l l l l
1
' I I
I I testing program. The extent and depth of design verification performed l p lbytheresponsibleorganizationisdeterminedbyanassignedengineering b l reviewer based upon the importance and complexity of the design, the l degree of standardization and its similarity with proven designs. In all l l cases, the design verification is to be complete prior to relying upon l lthecomponent,systemorstructuretoperformitsfunction. l l l3.4.2 l l l lTheverificationprocessistobeperformedbycompetentindividualsor l groups other than those who performed or supervised the design but who l l lmaybefromthesameorganization. This verification, however, may be l performed by the originator's supervisor in accordance with departmental l l lproceduresifheistheonlyindividualintheorganizationcompetentto l perform the verification and provided the need is individually documented l l landapprovedinadvancebytheresponsibleManagerorSuperintendent. l The frequency and effectiveness of use of Supervisors as design verifiers l l listobeverifiedbyQAthroughscheduledauditstoguardagainstabuse. l n l Where changes to previously verified designs have been made, design l U lverificationsarerequiredforthechange,includingevaluationofthe l effects of the changes on the overall design. l l l l l l l 3.4.3 I I I I I l When a test program is used to verify the adequacy of a design, it is to l lincludesuitablequalificationtestingofaprototypeorinitial 4 l production unit under the most adverse conditions and carried out in l l accordance with documented procedures and/or instructions. Testing is to l be performed as early as possible prior to installation of plant l l l equipment,orpriortothepointwhentheinstallationwouldbecome I irreversible. I I I l l l 1 1 I I I I I (~') G l l A l l TOPICAL REPORT 1 i lREV. 7 l P l l lDATE 5/31/85 l l & l SECTION: 3.0 DESIGN CONTROL lPAGE 3-3 l l L I I l l I I I
l l l l l accomplished. Each procedure is to be sufficiently detailed so that a l q lqualifiedindividualmayperformtherequiredfunction(s)withoutdirect l 'd I supervision and is to include measures to document the activity being l performed. I l l l 5.2.2 l l l l lToassuretheaccomplishmentofactivitiesinaccordancewithapproved l instructions, procedures and drawings, each supervisor is responsible for l lqualitycomplianceofhispersonnel. Verification that activities are l l accomplished in accordance with approved instructions, procedures and l ldrawingsisobtainedthroughvariouslevelsofsurveillanceand l l inspection by Quality Control personnel and through periodic surveillance l landauditsbytheQA0. l 1 l REVIEW 0F INSTRUCTIONS, PROCEDURES AND ORAWINGS l5.3 l l l l5.3.1 l i i (o> l Instructions,proceduresanddrawingsareprepared,reviewedandapproved l l in accordance with applicable plant administrative procedures, when l loriginatedattheplant,orinaccordancewithapplicableEnergySupply l l procedures, when originated from LRGO. l l l l l l 5.3.2 l
, I I I I l Plant procedures identified in the Technical Specifications for each unit l 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 plant General Manager for approval and subsequent l
l issuance. Plant Administrative procedures (1000.XX Series) are also l lreviewedbytheQualityControlstafftoverifycompliancetoAP&L's l l l l l l l C' I l A l l TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/31/85 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l l L l AND DRAWINGS l l l l l l
l I I I I quality program requirements. LRGO Energy Supply procedures describing l q lactivitiesrequiredtoimplementthisqualityprogramaretobereviewed V l and approved by a procedures task force committee and Quality Assurance l ltoassurecompliancetoAP&L'squalityprogramrequirementspriorto l l submittal of the procedures to the Department Head responsible for l implementation,forapprovalandsubsequentissuance. l l l l l5.3.3 l l l lPlantandLRGOproceduresandinstructionsaretobereviewednoless l l than every two years to determine if changes are necessary to meet NRC l lcommitmentsandcurrentAP&Lpractices. Applicable procedures (i.e. l l those that relate to the incident cause) are to be reviewed following an l lunusualincidentsuchasanaccident,unexpectedtransient,significant l l operator error or equipment malfunction. Applicable procedures are also l
.ltobereviewedfollowinganymodificationtoaplantsystem. l l l l5.3.4 l Drawings related to plant changes and modifications are controlled as I described in Section 3 and 6 of this manual. l l l l l l 5.4 CHANGES TO PROCEDURES l l l l l l 5.4.1 1 I I I I l Changes or revisions to approved instructions, procedures and drawings l laretobereviewedandapprovedbythesameorganizationsorgroupsthat l l performed the original review unless otherwise noted in specific AP&L l lproceduresandcontrolledinthesamemannerastheoriginal. l l l l l 1 I I I I l l l l l l l
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, l; documented, reviewed by the PSC, and approved by the plant's General l Manager within 14 days of implementation. Temporary changes to approved h,s (y plant procedures'which change the intent of the procedure may be made l provided such (hanges are reviewed by the PSC and approved by the plant's l General Manacer prior to implementation. Temporary changes to approved l
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i plant procedu,es are to specify the period of time during which they may a eadily available to affected members of the plant l
;J l be used and made l staff. In the esent of an emergency not covered by an approved l l l procedure, o(erations personnel may take ' action, without obtaining l
[ approvals,;soas'to'minimizepersonnelinjuryanddamagetothefacility l l and to pmtect health and safety. l
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l O d l l l I l A l TOPICAL REPORT IREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-4 l l L l AND DRAWINGS l l l l l l
I I I I l approved historical plant documents, and the storage of historical i ldrawingrecords. The Engineering and Technical Support Manager is Os l responsible for the control and issuance of drawings and revisions l l ltheretotoassurethattheyreflecttheas-builtconditionsoftheplant. l l 1 l6.3 IDENTIFICATION I I I lDocumentsaretobeidentifiedbyatitledescriptiveoftheirpurposeor l applicability and marked or stamped as to their current status (Draft, l l lForInformationOnly, Void,etc.)perdepartmentalprocedures. Revision l status of document is to be identified in document registers, l l ldistributionlistsand/orwithintherevisionrecordpage/blockofthe l document. l l I l I l l 6.4 DISTRIBUTION l l l l 1 l Distribution lists and/or document registers are to be maintained by the l lorganizationresponsibleforissuanceofthedocument. These lists are l to identify the revision status of the document and are to be reviewed l l land!!pdatedperiodicallybytheresponsibleorganizationtomaintainthem l in a current status. These lists are available to individuals using the l l ldocumenttoassuretheyareinreceiptofthecurrentdocument. These l measures are to preclude the possibility of using outdated or l l linappropriatedocuments. l l 1 l6.5 CHANGES l l l 6.5.1 l l 1 l lChangestocontrolleddocumentsaretobereviewedandapprovedbythe l same organizations which performed the original review and approval l l lunlessotherwisespecifiedindepartmentalproceduresapplicabletothe l affected activity. l l I I i l 1 I l l l l {') - l A l TOPICAL REPORT l 1REV. 7 1 l P l l lDATE 5/31/85 l l & l SECTION: 6.0 DOCUMENT CONTROL lPAGE 6-2 l 1 L l l l
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e l I I I l 7.2.2 l 1 l
/7 l V l Vendors / Contractors are evaluated and placed on the QVL by any of the l
l following methods, as approved by the Quality Assurance Manager: l l 1 l(1) Source survey by AP&L to verify compliance to applicable 10CFR50, l l Appendix B requirements or to applicable ASME Section III Quality l l Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG l components). l l l 1 I l l (2) Evaluation and acceptance of source surveys performed by others l l (ex. CASE, other utilities, NSSS suppliers, and prime contractors) l indicating a program meeting the appropriate requirements of l l 10CFR50, Appendix 8. (This method is not applicable for ASME l l l procurements.) l l 1 I I l (3) A review of the vendors / contractors current quality records l l supported by evidence of documented qualitative and quantitative l information which can be objectively evaluated. This includes l l l review and approval of the vendor's/ contractor's quality assurance ) l program, manual and procedures, when available. (This method is not l l applicable for ASME procurements). l l l l l(4) Evaluation of the vendor's/ contractor's history of providing a l product / service which performs satisfactorily in actual use. l l l Evaluation information includes: experience of users of identical l l or similar products / services of the prospective vendor / contractor; l and/or procurement records that have been accumulated in connection l with previous procurement activities and operating experiences. l l (This method is not applicable to ASME procurements). l l 1 l(5) Verification that a vendor is a holder of an ASME Certificatel of l Authorization issued as a result of an ASME survey may be used in l lieu of method (1) for ASME procurements. l l l 1 I I l I (d' i A l TOPICAL REPORT I lREV. 7 I l l P l lDATE 5/31/85 l l & l SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-2 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l 1 l
l l I I l (6) Verification that a contractor is a holder of a NRC letter l I confirming QA program implementation may be used in lieu of I l method 1. I I I I l 7.2.3 l l l l 1 l Vendors / contractors listed on the QVL are to be selected for procurement l l of material, equipment or services except for items designated
" commercial grade" per plant and LRGO procedures and as noted in l
l l paragraph 7.2.4. Standard catalog items may be procured from a l l l vendor / contractor not listed on the QVL provided the manufacturer of the l item is on the QVL and all AP&L requested documentation originates from the manufacturer. The QVL is to be periodically reviewed and updated per l l l lqualityassuranceprocedurestoensurethecurrentstatusofqualified l l vendors / contractors is available to personnel involved in the procurement l process. l l I l l7.2.4 l Services by contractors which provide only technical guidance / support or l which require work activities to be performed under the scope of the AP&L l QA Program may be furnished by contractors not listed on the QVL. The l l contractors work activities and personnel are to be controlled in l laccordancewithLRG0/plantprocedurestoassurethatthecontractor l l conforms to the procurement documents. l l l l 1 l 7.3 SOURCE SURVEILLANCE AND AUDIT l l l I I
- l 7.3.1 l
- l l l l l The effectiveness of a vendor's/ contractor's quality assurance program is l assessed by QA personnel at intervals consistent with the importance, l
l l l l l l l l l l I I l l O l A I TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l I & 1 SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-3 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l 1 1 i
I I I I l complexity, method of receipt and quantity of the products or services. I
) lThisassessmentmaybethroughsourcesurveillance,sourceaudit, receipt 1 inspection, independent testing or review of source documentation files. I I
I I . l l 7.3.2 l l l l l l Requests for source surveillance are made by the originator of the PR/ I l Contract,and/ortheresponsibleQualityControlorQualityAssurance l l organization during their review of the procurement document (reference I section 4.3) Source surveillance is to be performed by QA personnel or l l their appointed representative in accordance with surveillance plans I approved by the Quality Assurance Manager and the results documented per I quality assurance procedures. Reports documenting inspections performed f l landdiscrepanciesobservedarepreparedbythepersonperformingthe I surveillance to document compliance to the procurement documents and for l lfutureuseashistoricalqualityperformancedata. l l l l7.3.3 l 1 O l Audits of the vendor's/ contractor's quality assurance programs are l I l periodically performed under the direction of the Quality Assurance l lManagertoverifyimplementationofasatisfactoryqualityprogramonthe l l items or services being procured by AP&L. Audits performed by others l l(e.g., CASE,otherutilities,orprimecontractors),asevaluatedand l l approved by the Quality Assurance Manager, may be used as an alternative l ltoauditsbyAP&Ltoverifythevendor/contractorisimplementinga satisfactory quality program. l l Audits are to be conducted in accordance l lwithSection18ofthismanual. (This alternative method does not apply l l to ASME procurements.) l I I i l l i I I I I I I I I I I I I I I I A TOPICAL REPORT lREV. 7 l P l IDATE 5/31/85 l l & I SECTION: 7.0 CONTROL OF PURCHASED lPAGE 7-4 I I L I MATERIAL, EQUIPMENT AND SERVICES l l l l I 1
I I I l 1 7.4 RECEIPT INSPECTION l l I ( 7.4.1 1 l l 1 I I I Materials and ec;uipment, including ASME Code materials and equipment, are l lsubjecttoinspectionuponreceiptattheplant. The degree of l inspection is specified in the procurement documents and is to be l lperformedinaccordancewithplantproceduresforreceiptinspection. I I l7.4.2 I I I lReceiptinspectionactivitiesaretobedocumentedandinclude,asa l minimum: l examination of material or equipment for shipping damage, l lproperidentification,andquantity;andthereviewofvendor l documentation, to verify compliance with the procurement document. In l addition, if material and equipment received at the plant were not l inspected at the vendor's facility by AP&L, an inspection is to be l l performed by a Quality Control Inspector at the point of receiving to 8 verify that the material or equipment conform to the inspection l g l l U lrequirementsidentifiedintheprocurementdocuments. l l l l7.4.3 l l l Vendors are to furnish documentation as required by the procurement l documents for objective evidence that the material or equipment conforms l ltotheprocurementrequirements. Review and acceptance of this l l l documentation is to be performed by a Quality Control Engineer prior to l linstallationoruseofsuchmaterialorequipmentanddocumentedunless l l l otherwise specified in plant procedures. Certificates of Conformance may l be required by procurement documents which identify the requirements met l l by the vendor. The validity of the vendor's certification program is to l lbeperiodicallyverifiedthroughscheduledsourcesurveillanceandaudit l l l activities or through independent testing of the item by AP&L. l l l l l l l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: 7. 0 CONTROL OF PURCHASED IPAGE 7-5 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l l I I
I I I I l 7.4.4 I I I Accepted material and equipment is released, identified as to its l linspectionstatusandforwardedtoacontrolledstorageareaorreleased l for installation per applicable plant procedures. l I I I I I I 7.4.5 l l l 1 I I Acceptance of services furnished by a contractor is to be identified in l ltheprocurementdocuments. Depending upon the service performed, l l acceptance may be by technical verification of the data produced, I lsurveillanceand/orauditoftheactivity,orreviewofobjective l l evidence for conformance to the procurement document requirements. The l lacceptancemethodistobeperformedbyqualifiedindividuals I knowledgeable in the service provided. l I I I I l 7.4.6 l l l l l l Independent testing of selected material is to be performed in accordance I
) lwithplantprocedures/instructionstoverifyconformancetoprocurement l l criteria and the validity of the vendor's certification documents. I I I I I l 7.5 NONCONFORMING ITEMS l l l l l l 7.5.1 I
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l Nonconformances identified by the vendor / contractor which adversely I laffectreliability,performanceorinterchangeabilityoftheitemand l 1 l dispositioned repair or use-as-is are to be submitted to and accepted by l lAP&Lpriortoclosureofthenonconformancebythevendor/ contractor. l l l These nonconformances are to be documented and become part of'the l lprocurementdocumentationfurnishedbythevendor/contractorforthe l l material, equipment or services procured. I I I I I
- I I l l l A l TOPICAL REPORT IREV. 7 l P l IDATE 5/31/85 l l & I SECTION
- 7.0 CONTROL OF PURCHASED lPAGE 7-6 l l I L I MATERIAL, EQUIPMENT AND SERVICES I l l l l l
r I I I I l 7.5.2 l l l l Material and equipment found to be deficient or missing procurement l documentation during receiving inspection or found to be deficient as a l l result of independent testing is to be clearly identified, segregated l from acceptable items and dispositioned per plant procedures and as l described in Section 15 of this manual. l l l l I l 7.6 SPARE PARTS l 1 I I I l 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 design requirements. The applicable quality assurance requirements and l l documentation requirements for spare parts are to be included in the l procurement documents. l l l l l l l 7.7 STORAGE l l l 1 I l Material and equipment are to be handled and stored as described in plant l O l nrecedures end Section 13 of tnis menuei. j l l 1 l l I I I I I I I I I I I l I 1 1 I I I I I I
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I i l I l l A l TOPICAL REPORT IREV. 7 P I l lDATE 5/31/85 I I & I SECTION: 7.0 CONTROL OF PURCHASED [PAGE 7-7 l l L l MATERIAL, EQUIPMENT AND SERVICES I l l l l 1 1 (
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I l 9.0 CONTROL OF SPECIAL PROCESSES l I I l 9.1 SCOPE l I l l l l Special processes are to be controlled through the use of qualified l lpersonnelandplantprocedureswhichmeettherequirementsofapplicable l l codes, specifications, standards and other criteria stipulated in AP&L l llicensingdocuments. l l l l9.2 GENERAL I I l9.2.1 l 1 l lSpecialprocessesarethoseactivitieswhichrequireinteriminprocess l l controls in addition to final inspection to assure quality and include l lsuchactivitiesaswelding,nondestructiveexamination,heattreating, l costing, plating and chemical cleaning. l I I l l 1 l 9.2.2 l l
, l Technically qualified LRGO or plant personnel are to establish the l lproceduralandqualificationrequirementsforthosespecialprocessesnot l l covered by existing codes or standards or where AP&L quality requirements l lexceedtherequirementsofestablishedcodesorstandards. l 1 l l9.2.3 l l l lTherequirementsforweldingandnondestructiveexaminationaretocomply I with the applicable portions of the ASME Boiler and Pressure Vessel Code l lorforstructuralwelds,theAWSStructuralSteelCodeD1.1,andthe l l American Society of Nondestructive Testing (SNT-TC-1A and supplements). l lTherequirementsforcleaningandflushingoffluidsystemsaretocomply l l to the requirements of NRC regulatory guide 1.37, dated 3/16/73 unless l lotherwisenotedinTable1. l l l l I n
U A I TOPICAL REPORT I 7 I l l lREV. l l P l l0 ATE 5/31/85 l l & l SECTION: 9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-1 l l L l l l l l I I
I I I l l inspections and monitoring activities were performed in compliance with l l procedures,instructionsordrawingstoverifydesignrequirements;show l l compliance with acceptance criteria or identify the cause of rejected l l items;andidentifytheappropriateinspectionpersonnelapprovingthe l l results. I I I I I I 10.5.2 l l l l l l Records are to be maintained in accordance with plant procedures and l Section 17 of this manual. Inspection results on ASME Code items are l available to the Code Inspector for his review. l I I I I I I 10.5.3 l l l l l 1 The results of all inspection and monitoring activities are periodically l levaluatedperplantproceduresandtheresultsdocumentedtodetermine I whether the individual inspection programs demonstrate that the plant can I be operated safely and as designed. l l O V I 10.6 NONCONFORMANCES l I l l l 1 lNoncomformingitemsfoundasaresultofinspectionandmonitoring l l activities are identified, segregated and dispositioned in accordance l with plant procedures and Section 15 of this manual. Rework, repair or l l replacement performed after completion of inspections are to require l lreinspectiontotheextentnecessarytodetermineacceptabilityto I established criteria. 1 I l l l 1 1 I I I I I I I I I I I I I I I I I I I I I A p l TOPICAL REPORT IREV. 7 l l I IDATE 5/31/85 l l & 1 SECTION: 10.0 INSPECTION lPAGE 10-6 l l L l l l 1 1 I I
1 I I l l have been satisified. Nonconforming conditions, are to be identified l I I O landcontrolledinaccordancewithSection15ofthismanua l l11.4 RECORDS I I l lTestresultsaretoprovideobjectiveevidencethatthetestingwas l performed in compliance with approved procedures. Test records are to be l maintained and transmitted to the plant Document Control Center for I l retention in accordance with Section 17 of this manual. l l l I I l 11.5 TEST STATUS l l l l I l Inspection and test status is to be controlled in accordance with the l I provisions of Section 14 of this manual. l l 1 I I I
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' I l 1 I I I I I I I I I I I lA O .p TOPICAL REPORT !REV.7 l l lDATE 5/31/85 1 l & 1 SECTION: 11.0 TEST CONTROL lPAGE 11-5 1 I L l l l l l l 1
I I I l l documents and furnished to the plant prior to or upon receipt of the item l I I
^ at the plant.
l l13.3SHIPPINGCONTROLS l l l l13.3.1 l l 1 lShippingrequirementsaretobespecifiedintheprocurementdocuments. l l Suppliers compliance to these requirements are to include controls to l lassurethatitemsarecompleteandassembledasrequired;itemshavebeen l l I lpreservedandpackagedinaccordancewiththeprocurementdo items have been marked and identified in accordance with specifications l l and procurement documents; items have been loaded for shipment in such a l manner as to prevent damage; and required documentation is complete and l l furnished in accordance with the procurement documents. 1 I I I I l 13.3.2 l l l l l l Special nuclear material and sources are to be shipped and stored as l b V I g specified in the AP&L operating license and other appropriate regulatory l l documents. The Health Physics Supervisor is responsible for assuring l lthatradioactivesourcesandinstrumentscontainingradioactivesources l l are shipped, stored and handled per these requirements and plant l l procedures. The Nuclear Support Supervisor is responsible for assuring l l that special nuclear material (SNM), as defined in plant procedures, is l l shipped,storedandhandledpertheserequirementsandplantprocedures. l l l l l13.4 RECEIVING l l l l13.4.1 l l I j lMaterialsandequipmentaretobereceivedattheplantperplant l l l lproceduresandsubjectedtoareceiptinspectioninaccordance Section 7 of this manual. As part of the inspection activity, received l l l l l (s~') l l A I I TOPICAL REPORT I IREV. 7 I l l l P I IDATE 5/31/85 I l & 1 SECTION: 13.0 HANDLING, STORAGE AND lPAGE 13-2 I l L l SHIPPING l l l l I I
I I I l
'l in storage and to facilitate inspection and maintenance planning. l Issuance of items from storage for installation or use are to be O_ l documented and controlled in accordance with plant procedures. l l l l l l 13.5.4 l l l l l l Items identified as requiring maintenance during storage are to be I maintained in accordance with a documented maintenance program.
l 1 l l13.5.5 l l 1 lStorageareasaretobemonitoredbyindividualsresponsibleforthe l l storage areas so that the integrity and security of stored items is l leffectivelymaintained. Inspections and examinations under the control l l of the Manager, Nuclear Quality Control are to be performed and l i ldocumentedonaperiodicbasistoassurethattheintegrityoftheitems l l and their containers are being maintained. Periodic audits under the l lcontroloftheQualityAssuranceManagerarealsoperformedtoassure l l compliance to storage requirements. l O. i l i l l 13.6 HANDLING CONTROLS l 1 1 I I l 13.6.1 l l l 1 l l Special handling requirements are to be specified in the procurement I documents and plant procedures to protect the quality of items l l susceptible to handling damage. Special tools and equipment are to be l provided to handle these items and are to be controlled and maintained l l per written procedure to assure safe.and adequate handling. I I I I I l 13.6.2 I I I I I l Special handling tools and equipment are to be inspected and tested at l specific times in accordance with written procedures to verify that the l l l 1 l 1 l l 1 l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l &_ l SECTION: 13.0 HANDLING, STORAGE AND lPAGE 13-4 l
'l L l SHIPPING l l l- 1 I I
I l l l l 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l 1 (~' l I C)' l 15.1 SCOPE l l l l 1 l l Nonconforming items are to include materials, parts, components, l l processes,documentsandasapplicable, services (includingcomputer l l codes) that do not conform to applicable regulations, codes, standards, l l specifications,drawingsorlicensingdocuments. Nonconforming items are l l to be controlled in accordance with approved procedures to prevent their l linadvertantuseorinstallation. These procedures are to contain l 1 measures to assure the prompt identification and notification, I l documentation, segregation,technicalreview,dispositionand l verification of a nonconforming item. l 1 l l l l 15.2 GENERAL l l l l l 1 15.2.1 l 1 l l l g l It is the responsibility of each individual to identify a nonconforming i d l condition,whetherrelatedtoaproduct,processordocumentation,andto I report it to their cognizant supervisor for review and concurrence. The l linitiatoristodocumentthenonconformanceonanappropriate l l nonconformance report, per approved procedures unless the nonconformance l lisdeterminedtobeatechnicalspecificationviolationand/orreportable l l to the NRC. See paragraph 15.3 for reportable nonconformances. l 1 I I I i 15.2.2 l l l l l l Nonconforming items are to be tagged with a hold tag, or otherwise l lidentifiedperplantprocedures,topreventinadvertantuseor l installation of the item. Nonconforming items are to be segregated from I acceptable items unless they are currently installed or their size, I I I I l l l 1 I I T (J l l A l l TOPICAL REPORT l lREV. 7 l l l P l lDATE 5/31/85 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-1 l l L l PARTS AND COMPONENTS l l l l l l
I l l l l weight, configuration, etc., makes it impractical to move to a segregated l area. Hold tags are to remain on the item until the disposition is d complete per plant procedures. l l l l l l l l 15.2.3 l l l I I l Nonconformance reports are to identify the group responsible for l dispositioning the nonconformance. The assigned individual within the l 1 responsible group is to evaluate the nonconformance and confer, as l l appropriate,with.interfacinggroupstodetermineitscauseand l l recommended disposition. The disposition, which may be reject, rework, I repair or use-as-is, and the corrective action taken to prevent l l recurrence is to be documented on the report. l 1 I I I i l 15.2.4 l l l 1 l l The initiator of the nonconformance report and his supervisor are to l review the disposition for acceptance prior to implementing corrective action. If they cannot agree with the assigned individual on the l g I l
\j disposition,theplantGeneralManageristodecide. For a repair or l l l use-as-is disposition, a cognizant engineer knowledgeable in the design l requirements for the affected item is also to review the report for l concurrence of the disposition. Written justification for the design l I
change, repair or deviation that has been accepted is to be documented to l l denote the as-built condition and is to be made a part of the report. l l l l l l 15.2.5 l 1 I I I l The acceptability of rework or repair of materials, parts, components, l systems and structures are to be verified by reinspecting the item as l l originally inspected or by a method which is at least equal to the l original inspec'. ion method. The rework and repair inspection records are l l l l l l l l l l l O ' l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-2 l l L l PARTS AND COMPONENTS l l l l l l
I l I. 1 l to be documented and become part of the permanent records for the item. l lUponcompletionofthecorrectiveaction,theManager,NuclearQuality l Control is to verify completion of corrective actions in accordance with l lpientproceduresandifacceptable,closethenonconformancereport. l l l l15.2.6 l l l l Fo.' ASME Coa'e, Section III, Division 1 materials, parts and components l l dispositioned repair or use-as-is, the nonconformance report is to be l lsubjecttoreviewandconcurrencebytheCodeInspector. I I l15.3REPORTABLENONCONFORMANCES l l l
.l15.3.1 l l l Nonconforming items or conditions which are reportable per the Technical l
l Specifications to the NRC are to be documented by the initiator and I forwarded to the Special Projects Manager so the appropriate report, per l l I O lplantprocedures,canbeprepared. l l 15.3.2 l l l l l l Upon disposition of the report by the responsible group the PSC reviews I the report for concurrence and possible assignment of additional l l corrective actions and forwards the report to the plant General Manager l lforfinalapproval. l l 1 15.3.3 l l l lTheLRGOLicensingsectionistoberesponsiblefortransmittingapproved l l reports to the NRC within the time period specified in the Technical I Specifications and Licensing procedures. l 1 1 I I I l l l l 1 l A l TOPICAL REPORT lREV. 7 I p l lDATE 5/31/85 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-3 l l L I PARTS AND COMPONENTS l l l l l l
1 I l l l 15.4 SUPPLIER NONCONFORMANCES l l a O l l 1 l 15.4.1-l l l l l l Procurement documents are to contain requirements for the l l vendor / contractor to identify nonconforming conditions to AP&L which l violate a technical or material requirement of the procurement document l l landwhichresultsinadispositionofrepairoruse-as-is. All such l nonconformances are to be reported to AP&L for evaluations and l l acceptance. l The vendor / contractor is to document such nonconformances on l l their applicable nonconformance report which is to be included in the l lfinaldocumentationpackagesubmittedtoAP&L,inaccordancewiththe 1 procurement documents. l i l i I l l 15.4.2 l 1 I l l l Upon receipt of items at the plant, a Quality Control Engineer is to l review any nonconformance reports in the documentation package to assure l the nonconforming conditions have been properly dispositioned and l l
,) lacceptedbyAP&L.
l l l l15.5 RECORDS l l l l15.5.1 l l l lUponcompletionofdispositionandverificationactivities,thecompleted I nonconformance reports, and related documents generated to ensure proper l ldispositionandresolutionofthenonconformancearetobeforwardedto l and maintained by the Document Control Center. l l l ' .I
'l l l
l l l l I l l l l 1 1 I I I I l A l TOPICAL REPORT lREV. 7 P l l lDATE 5/31/85 l l & 1 SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-4 l l L l PARTS AND COMPONENTS l l l l l l
/
I I IL I I 15.5.2 1 1 I The Manager, Nuclear Quality Control is to maintain and issue a monthly l report to the plant General Manager, identifying the current status of l l ~a ll open nonconformance reports for management review. I I I I I I I I I I i 1 I I I l 1 1 I I I I I I I I I I I I I I I 1 I I I I I. I I I I O l l l 1 I I I I I I l l 1 I I I I I I I I I I I I I I I I I I I I I I I _l 1 1 I I I I I I I I I O I
-I A I
I TOPICAL REPORT I IREV. 7 I l l _P l lDATE 5/31/85 I I & I SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-5 l l L I PARTS AND COMPONENTS I I l l I l
I I I I I 16.0 CORRECTIVE ACTION l l l 16.1 SCOPE l l l l 1 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 loccurrencesandnonconformancesarepromptlyidentifiedandcorrected. l l In the case of significant conditions adverse to safety, this system is l ltoassurethatthecauseoftheconditionisdeterminedandcorrective l l action taken, documented and reported to appropriate levels of management I for independent review. I I l16.2 GENERAL l l l l16.2.1 l l 1 When deviations, deficiencies, malfunctions or other abnormal occurrences l l l or conditions are encountered, they are to be reported to responsible l O leuthoritiesforrevieweaddisPositioaineccordencewithSection15of l l this manual. I l l I I l 16.2.2 I I I I l I Cognizant supervisors are to review discrepancies discovered during the l lcourseofstationoperations,andinthecaseofsignificantconditions I 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 l lrecurrencearetobedocumentedinaccordancewithSection15ofthis l l manual. I I I I I I I I I I I I I I I n i I I I U l A I TOPICAL REPORT IREV. 7 l l P l IDATE 5/31/85 l l & 1 SECTION: 16.0 CORRECTIVE ACTION lPAGE 16-1 l l L l l l l I I I
I l 1 l l 18.3.2 I I I
~3 l (V l Audit schedules assure that as a minimum, those audit areas identified I l
within the Technical Specifications applicable to each nuclear unit are l l audited, under the cognizance of the SRC, at the indicated frequencies I within AP&L. I I l18.3.3 l l l Audits of vendor / contractor activities are to be scheduled as identified l in Section 7, paragraph 7.3.3 of this manual. These audits are to l I l evaluate and verify their quality assurance program, procedures and ' l I activities, to assure compliance with the procurement documents, and to l lverifytheyperiodicallyreviewandaudittheirsuppliersquality l assurance program. l I I I I I l 18.3.4 l l l 1 1 _ l Periodic reviews of the audit programs are to be performed by the SRC or l ltheirappointedmanagementrepresentativeatleastsemi-annuallyto I assure that audits are being accomplished in accordance with the I requirements of the technical specifications, this manual and Regulatory l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1. l l I I l l I 18.3.5 I I I l l I Regularly scheduled audits may be supplemented, as required, to cover l lunforeseeneventsorchangedrequirements. l l l l l l 1 I I I I I I I I I I I I I I I I t l I I I l A I TOPICAL REPORT lREV. 7 I l P l lDATE 5/31/85 l l & 1 SECTION: 18.0 AUDITS lPAGE 18-3 l l L l I I I I I I I
I I I i l 18.4 AUDIT IMPLEMENTATION l I l Q, l I i 18.4.1 l l l l l l Audit plans and checklists are to be prepared by the auditor and approved l lbytheQualityAssuranceManagerpriortoperformingtheaudit. l Checklists are to be used during the audit to assure that all l l lrequirementsoftheactivitiesauditedareaddressedduringtheauditand l that those procedures and instructions issued to control the audited l I activity are adequate. I l I l18.4.2 l l 1 lUponcompletionofanaudit,awrittenreportistobepreparedwhich l includes at least the following items: l I l l l l l (1) Description of audit scope and date. l l (2) Identification of the auditor (s). -p l (3) A summary of audit results. l I V (4) Details of nonconformances or programmatic deficiencies. l l l (5) Recommendations for correcting nonconformances or improving the l l Quality Assurance Program, as appropriate. l l l l18.4.3 I I lDeficienciesidentifiedasaresultofaninternalauditaretobe I recorded on an Audit Finding Report (AFR) by the auditor and issued to l lthedepartmentheadresponsiblefortheareaauditedforcorrective l action. The department head or their assigned designee is to provide l l prompt corrective action to the deficiencies identified and document on I the AFR the action taken or to be taken to prevent recurrence. I lAppropriatefollow-upincludingre-auditsbytheassignedauditgroupis 1 l I I I I I I I I I O i l A i l TOPICAL REPORT i lREV. 7 i l P l I lDATE 5/31/85 l l & I SECTION: 18.0 AUDITS IPAGE 18-4 l 1 L I I I I I I I
I I I I l conducted in the deficient areas to verify proper and timely l I implementation of corrective action commitments. Follow-up actions are I to be documented on the AFR. l l l l l l 18.4.4 l l l 1 I l Audit reports pertaining to plant activities are to be independently l l reviewed.,bythePSCandtheSRCtodetermineifadditionalcorrective l l actions need to be initiated to assure continued safe operation of the 1 l plant. Audit reports pertaining to LRGO activities are to be l independently reviewed by the SRC. In addition to these reviews, the l l lauditreportsaretobedistributed,asaminimum,totheNuclear l l Operations Vice President, Quality Assurance Manager and appropriate l llevelsofmanagementhavingresponsibilityintheareaauditedtoassure l their awareness of the findings. l l l l l l l 18.4.5 l I I I I l Audit results and findings related to external audits conducted by QA l O lnersonneieretoberecordedenddistributedtothequeistyAssurance l l Manager and a designated representative of the audited organization. l lDeficienciesaretoberecordedonanAFR,andtheauditedorganization I is to describe actions taken to correct deficiencies and prevent l recurrence on the AFR. Corrective actions are to be verified by QA l personnel and documented on the AFR. l I I I l l l - 18.5 RECORDS l l l l l l l Written internal audit reports, including checklists, AFR's and related l ldocumentationsupportingthefollow-upactivitiesaretobeforwardedto l l the Administrative Manager for storage in accordance with Section 17 of l l lthismanual. External audit reports are to be maintained / stored in the l f I applicable vendor / contractor file maintained by the Quality Assurance l Manager. l l l l 1 I I A l TOPICAL REPORT 7 lREV. l P l lDATE 5/31/85 l l l & l SECTION: 18.0 AUDITS lPAGE 18-5 l 1 L I I l l I I I
I I I l l 18.6 NUCLEAR FUEL AUDITS 1 l l l Arkansas Power & Light Company delegates to Middle South Services, Inc., I lawhollyownedsubsidiaryofMiddleSouthUtilities,Inc.,the l l responsibility for performing those quality assurance functions necessary l ltoassurethatitsnuclearfuelisdesignedandfabricatedinaccordance l with regulatory requirements and accepted codes, standards and l l specifications. The MSS Quality Assurance section monitors the design l l and fabrication of the fuel through a program of audits of the fuel l l fabricator,includingbothdesignreviewauditsandfuelfabrication l l audits. MSS also conducts audits of component suppliers as deemed l l necessary by the Manager, Qualtiy Assurance (MSS), to ensure the quality l of the fuel. Formal audit reports are issued by MSS to document their l l l audit activities and to identify nonconformances or other items requiring l l action by the fuel fabricator. Resolution of nonconformances or other l litemsrequiringactionisverifiedbyMSSanddocumentedinfollow-up l reports. The AP&L Quality Assurance Manager is on distribution for all l l lauditandfollow-upreports. I l 1 O l l l l l 1 I I I I I I I I I I I I I I I I I I I I I l l I I I I I I I I I I I I I l l l 1 I I O I I I I V I A I TOPICAL REPORT lREV. 7 l l P l 10 ATE 5/31/85 l l & 1 SECTION: 18.0 AUDITS lPAGE 18-6 l l L l l l l l l l
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r: I I I I I R.G._1.94/ .Section 1.4 defines This requirement for rein- 1 I ANSI N45.2.5 inprocess tests and forcing steel will be I (Section 1.4) states: interpreted to permit taking l l the rebar test specimen at
" l l ... samples of these the fabrication shop, prior l l tests must be taken to start of fabrication of I from the lot or the rebar from the heat or l batch of materials fraction thereof represented l supplied to the site by the test specimen. For l
l l for use." those tests performed at the l l fabrication shop, certifica- l l tion shall be available to l l provide objective evidence l l that the test specimens
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represent the material sup- I plied for use at the site. l l 1 Requirement: lANSIN45.2.5 l (Section 4.5) Section 4.5, Con- l O l crete Piacemeat. l l references American l Concrete Institute l l (ACI) standards l ACI-305-72, l l " Recommended Prac- l l tice for Hot Weather Concreting" and ACI-l
-l l 306-66, " Recommended l
l Practice for Cold l Weather Concreting." l l l I
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TOPICAL REPORT lREV. 7 lDATE 5/31/85 l l l & 1 SECTION: TABLE 1 lPAGE T1-9 l l L l l l l I 1 I
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l l l a) For bar sizes #3 through #11, one full size l q l specimen from largest bar size rolled from each I I b l mill heat, unless material from one heat I differs by three or more designation numbers. l When this occurs, one bend test shall be made l l l from both the highest and lowest designation l l number of the deformed bars rolled. 1 I I I I l b) For bar sizes #14 through #18, Supplementary l l Requirements S1 of ASTM A615 will be applied. l l One full size specimen for each bar size for l l each mill heat. If supplementary requirements l l are not followed for mill tests, they will be l l applied as in process tests. l l l l The above interpretation is consistent with l l Regulatory Guide 1.15, " Testing Reinforcing bars l l for Category I Concrete Structures," Revision 1, l l December 1972. I O l l l In process test specimens may be selected at the l l rebar fabrication shop, prior to start of l l fabrication of the rebar from the heat or fraction l l thereof represented by the test specimen. I l l Acceptance criteria for any failed test l l (qualifications as well as in process) may be the l l same as that for tensile tests specified in l l Subarticle CC-2331.2 of ASME Section III, Div. 2 l l Code (1975). This states that if a test specimen l l fails to meet the specified strength requirements, I I I I I I I I I I I I I I I I A l TOPICAL REPORT lREV. 7 l P I lDATE 5/31/85 I I & l SECTION: TABLE 1 lPAGE T1-13 l l L l l l l l l I
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l, I l l l l TABLE 3 l l l p) ( l l QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION MANUALS LIST l l l l l l l 1. Quality Assurance Program for Operations l l l 1 i l The Quality Assurance Program for Operations establishes the l l policies and guidelines of the AP&L quality assurance program for l its operating nuclear plants. This program is to be followed by all l I organizations involved in safety-related work applicable to l operating nuclear plants. l l I I I l 2. Energy Supply Procedures Manual l l l l l l The Energy Supply Department - Little Rock General Office (LRG0) l l employs a system of procedures designated as Energy Supply l l Department Procedures (ESP) in order to implement Program I requirements for the control of design, engineering, nuclear fuel, l l licensing, training and procurement activities in support of the l l operating plant. l l l l The ESP's and revision thereto are prepared by Energy Supply LRGO l l personnel, reviewed and approved by the Quality Assurance Manager, I l the Energy Supply (LRGO) Procedures Task Force and the responsible l department head. l I I I I I l 3. Quality Assurance Procedures Manual l I I I I l The Quality Assurance Organization employs a system of procedures l l designated as Quality Assurance Procedures (QAP) in order to assure l proper implementation of the program. The QAP's and revisions l I I I I i I I I I I I I l I O lA 1 P l l T0e1 cat Ree0aT iRev. 7 10 ATE 5/31/85 l l l & l SECTION: TABLE 3 lPAGE T3-1 l l L I I I I I I I
r I I I I I thereto are prepared by the Quality Assurance Organization, reviewed I g and approved by the Quality Assurance Manager and approved by the ( l l Energy Supply Services Director and the Sr. Vice President, Energy l l Supply. l l l l4. Quality Assurance Administrative Procedures Manual l I l The Quality Assurance Organization also employs a system of l l procedures designated as Quality Assurance Administrative Procedures I (QAA). These procedures provide technical and administrative l instructions to the Quality Assurance staff to aid in implementing l their responsibilities within the quality program. l l l l5. Overall Plant Adminstrative Procedures Manual l I l The plant operation organization employs a system of procedures I designated as Overall Plant Administrative Procedures. These l I procedures implement Quality Assurance Program requirements and l l control on site activities. Overall Plant Administrative Procedures l O, ( I l and changes thereto are prepared by the plant staff, reviewed by the g l 1 Plant Safety Committee and approved by the plant's General Manager. l l The procedures and revisions are also reviewed by the Manager, l l Nuclear Quality Control to assure that Quality Assurance Program I l l l commitments are met. ; I I l6. Departmental Plant Administrative Procedures l I l Each department (operations, maintenance, engineering and technical l l support, training, quality control, etc.) at the plant has developed i procedures in support of the Overall Plant Administratii;e Procedures l l and this Quality Assurance Program. These procedures provide l l technical and administrative instructions to the various departments l I I I I I I I I I A I TOPICAL REPORT lREV. 7 i P l IDATE 5/31/85 I I & I SECTION: TABLE 3 lPAGE T3-2 l l L l l l I I I I
I I I I I to aid in implementing their responsibilities within the quality i program. Each department head is responsible to perform a QA review O, l l I of their procedures to assure conformance with the Quality Assurance. l Program. These procedures are reviewed by the Plant Safety l l l Committee and approved by the plant's General Manager. I 1 I I I I I l l l 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 I l i i I O l 1 l I I I I I I I I I 1 I I I I I I I l l I I I I I I I I I I I I I I I I I I I I I I I l l I O I I A' I l TOPICAL REPORT I IREV. 7 I l l P l lDATE 5/31/85 l l & 1 SECTION: TABLE 3 lPAGE T3-3 l l L l l I I I I I
1 I I I I APPENDIX A l l p v I l QUALITY PROGRAM FOR TRANSPORT PACKAGES 1 l 1 I I I I l 1. 0 INTRODUCTION l l l l 1.1 The quality program for transport packages is designed to 1 i comply with the requirements of this manual and with the i I quality assurance guidelines identified in 10CFR71, Subpart H - l l Quality Assurance, subject to exceptions noted in Attachment A l l to this Appendix. I I I l 1. 2 Attachment A to this Appendix identifies the applicability of I l each section of the Quality Assurance Manual - Operations to l I the Quality Program for Transport Packages. l I I l 1.3 Attachment B to this Appendix contains the Quality Assurance l l Program Approval document which shows NRC approval of this l l program on January 23, 1985. l I I I I l l l l l I I I l O l l l l l t i I 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 l l i I I I I I I I I I l l I I I A l TOPICAL REPORT 7 lREV. l l P l lDATE 05/31/85 l l & l SECTION: APPENDIX A - QUALITY PROGRAM lPAGE AA-1 l l L I TRANSPORT PACKAGES l l 1 I I I
1 I I I I I I I n l I I ATTACHMENT A l 10 CFR 71 Appendix H l 1 I I The following section of the most currently approved revision of AP&L TOP-1A I will be applied as stated below (Note specific paragraphs are to rev. 6 ! l paragraph numbers which could change during subsequent revisions). I I I g Section 1 - Applicable l l 'Section 2 - Applicable ! I I l Section 3 - Not applicable. AP&L will use only licensed packaging which has been designed under a QA program which has been submitted l l to the NRC for approval. l I I l Section 4 - Applicable - l Section 5 - Applicable l Section 6 - Applicable l Section 7 - Applicable l Section 8 - Generally applicaole, except for paragraph 8.2.2 and 8.2.3. l l Oue to size, uniqueness, low volume, and the method of supplier l l identification of each package, AP&L tagging of each package is not necessary. l g I Section 9 - Not applicable; we do not consider this subje:t as a "Special l l Process" in the context of 10 CFR 71, Appendix H Section 71.119 p g which is a re-statement of 10 CFR 50, Appenoix B Criterion 9. l g l Section 10 - Applicable . l l ! l l Section 11 - Not applicable; AP&L will not be testing the package in the context of 10 CFR 71 Accendix H, Section 71.123 which is a l I restatement of 10 CFR 50, Appendix B Criterion 11. I I I l Section 12 - Applicable l l Section 13 - Generally applicable except for paragraph 13.5. AP&L does not i " store" package, therefore the storage section does not apply. I I I l Section 14 - Not applicable; see Section 11 comments above. l l Section 15 - Generally applicable, except for references to the various i types of dispositions in paragraphs 15.2.3 to 15.2.5. l l Nonconforming material or equipment will be returned to the l g vendor or will be replaced. l l Section 16 - Applicable ! I I l Section 17 - Applicable l l Section 18 - Applicable l I I I I I I I I I I I O lA l P i l T0eICAt REe0RT iREv. 7 l0 ATE 05/31/85 i [ l & l SECTION: APPENDIX A - QUALITY PROGRAM lPAGE AA-2 l l L l TRANSPORT PACKAGES l 1 I I I I
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l Auoust 27, 1979 and January 4, 1985 l l e conoirions g l l l l Activities conducted under applicable criteria of Appendix B of 10 CFR {.t l l kg I Part 50 to be executed in accordance with Attachrient A to QA Manual b, l g (AP&l.-TOP-1A) for Arkansas Power Station Nuclear One, Units 1 and 2 >; (Docket Nos. 50-313 and 50-368) with regard to transportation packages. l g h.i F y I.til .- I if BI i'irI I$ I? . kI 5: 1 I$ EI I !( Id ,NI lsi l !?ti l .:c h': II',l l9 >
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1 I l 1 I l APPENDIX B l l 73 1 QUALITY PROGRAM FOR FIRE PROTECTION l V I l l l l l l
1.0 INTRODUCTION
l l 1 I l 1.1 The AP&L fire protection program was developed to define the l l organizational responsibilities, procedural controls, fire l l brigade staffing and training and the quality assurance l l provisions that have been established for the nuclear plant. l l The overall objective of the fire protection program is to l l minimize both the probability and consequences of postulated l l fires and to maintain the capability to safely shut down the l plant if a fire should occur. l l l l l 1.2 The scope of the AP&L fire protection program includes those l l fire protection and detection systems, and those structures and l l components (such as fire doors, fire dampers, and penetration l l seals) which, as identified in the plant's fire hazards l l analysis report, are required to restrict the damage caused by l l a single exposure fire to safety-related equipment and l l equipment required to achieve and maintain safe plant shutdown l l to within those limits set forth in Section 1 of Appendix R to l l 10 CFR 50. l 1 l l 1.3 The quality program for fire protection is designed to comply l pd l with the requirements of this manual and with the quality l l assurance guidelines identified in BTP-APCSB 9.5-1, Rev. 2, l l July 1981, Guidelines for Fire Protection for Nuclear Power l l Plants, subject to exceptions noted in this Appendix. l l l l 1.4 With respect to regulatory commitments, AP&L is committed to l l implementing the requirements of the following, subject to l l exceptions noted in this Appendix: I l l l 1. 10CFR50, Appendix A, General Design Criterion 3 - Fire l l Protection. l l l l 2. Specific sections of 10CFR50.48, Fire Protection and l l 10CFR50, Appendix R, Fire Protection for Nuclear Power l l Facilities Operating Prior to January 1, 1979. These l l sections are as follows: l l l l III.G. Fire Protection Safe Shutdown Capability l l l l III.J. Emergency Lighting l l 1 l III.L. Alternative and Dedicated Shutdown Capability l l l l l l l A l TOPICAL REPORT 7 lREV. l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-1 l l L l FOR FIRE PROTECTION l l l l l l
I I I l l III.O. Oil Collection System for Reactor Coolant Pumps l l l () v l 1.5 Other fire protection commitments are contained in the l l following AP&L/NRC references and documents: l
-1 l
l 1. AP&L Facility Operating License (s) including Technical l l Specification (s) l 1 l l 2. AP&L Final Safety Analysis Reports (FSAR) l l l l 3. AP&L Fire Protection Safety Evaluation Reports (SER) l l l l 4. AP&L and NRC regulatory correspondence (includes l l applicable NRC generic letters and AP&L exemption l l letters), identified in Division 4.0 to the Fire l l Protection Program Manual (FPPM). l l l l 1.6 The above requirements are implemented by controlling l l activities as described in this manual and appendix and by l l procedures referenced in this manual and appendix. l l l l 2.0 ORGANIZATION l 1 I I 2.1 The organizational structure and responsibilities of key l l personnel associated with the administration, implementation l l and evaluation of the fire protection program are described in l l Section 1.0 of this manual and as follows: 1 O I l
- 1. The Nuclear Operations Vice President is the offsite management position which has the responsibility for the l l development, implementation, and assessment of the l l effectiveness of the fire protection program. He reports l l directly to the Energy Supply Senior Vice President. l l 1 l 2. Reporting to the Nuclear Operations Vice President is the l l Nuclear Services General Manager. Under his direction is l l the Nuclear Programs Manager. The Nuclear Programs l l Manager has responsibility for development of the plant l l fire protection program. He is responsible for providing l l guidance for its implementation and support to the nuclear l l plants in the area of fire protection. These activities l l include assuring that regulatory requirements are included l l in the fire protection program, AP&L commitments regarding l l fire protection are identified and tracked, safety l l evaluations (10 CFR 50.59) for fire protection l l modifications are performed and to provide liaison with l l outside fire protection related organizations. He also l l has responsibility for maintenance and revision of the l l Fire Protection Program Manual through its staff l l supporting fire protection. l l l l l l l
(] L l l A l l TOPICAL REPORT l lREV. 7 I l l P l l0 ATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-2 l l L l FOR FIRE PROTECTION l l l l l 1 b
I I l l l 3. The Plant General Manager is the on-site manager l l responsible for the overall administration and I (~') l implementation of plant operations in accordance with the l V l fire protection program. He reports directly to the l l Nuclear Operations Vice President. l I I l 4. The Plant Administrative Manager is responsible for the l l establishment and monitoring of fire prevention aspects of I l the program at the plant including control of I l combustibles, ignition sources, and postings. He reports l l directly to the Plant General Manager. Reporting to the l l Plant Administrative Manager is the Human Resources l l Supervisor. Under his direction are the Plant Safety and l l Fire Prevention Coordinators. The Safety and Fire l l Prevention Coordinators are responsible for implementing, I l maintaining and assessing the fire prevention aspects of l l the program as defined in plant procedures. I i l l 5. The Quality Assurance Manager is responsible for assuring l l that the fire protection program is implemented in l l accordance with the QA Topical Report, Station Technical l l Specifications, and applicable procedures. This is l l accomplished by the performance of audits and other l l provisions of the QA Topical Report. He shall assure that l l corrective action, when necessary, is taken. He reports l l directly to the Energy Supply Services Director. I I I l 6. The Licensing Manager is responsible for providing other I (n) l responsible organizations with regulatory information and l l licensing recommendations on regulatory issues related to l l fire protection. He is also responsible for the l l preparation and/or review of fire protection related NRC l l correspondence and proposed changes to the Fire Protection l l Program Manual to ensure that regulatory l l requirements /committments are complied with and to l l identify / control those portions of the Fire Protection l l Program Manual affecting the Licensing basis of the l I nuclear plant. He reports directly to the Nuclear l l Services General Manager. l l l l 7. The Engineering Services General Manager is responsible l l for assurirg that the technical requirements specified in l l the plant operating license, Technical Specifications, and l l other design basis documents, with respect to fire l l protection, have been satisfied in design modifications l l and design documents affecting the nuclear plant. He l l reports directly to the Energy Supply Services Director. I I I l 8. The Engineering and Technical Support Manager is l l responsible for the fire protection aspects of the program l l at the plant, such as evaluation and/or inspection of fire l l 1 l l OV l l l l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & I SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-3 l l L l FOR FIRE PROTECTION l l l l l I
I l l l l detection and suppression equipment, fire barriers, l l dampers and alternate shutdown equipment protection. He' l l reports directly to the plant General Manager. Reporting l
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- l. to the Engineering and Technical Support Manager is the l l Plant Engineering Superintendent. Under his direction is l
- l. the plant Fire Protection Specialist. He is responsible l l for cognizance of the design requirements regarding fire l l protection and maintaining the Fire Protection Program l l Manual at the plant. The plant Fire Protection Specialist l l provides technical support to the plant's Fire Protection l l Program in the form of system evaluations, design l l recommendations and standards coordination. l l l l 3.0 QUALITY ASSURANCE PROGRAM l l l l 3.1 This quality program is to ensure that the fire protection l
-l systems for safety-related areas (as defined in paragraph 1.2 l l of this Appendix) are controlled in accordance with applicable l l NRC regulations, industrial. standards and codes and AP&L l l policies, rules, procedures and licensing documents. The l l quality program is implemented through appropriate LRGO and l l plant procedures. The effectiveness of the fire protection l l program is verified through surveillances and scheduled audits l l conducted by the QA organization, under the cognizance of the l
.l SRC. General requirements for this program are also described l l in subsections 2.4 through 2.7 of this manual, except that l l personnel performing inspections need not be certified to ANSI l l N45.2.6, when inspections are performed on equipment not listed l l on the Q-list. l l 3.2 Employees whose duties and responsibilities are related to this l l fire protection program at or in support of the nuclear plant l l are to participate in appropriate training programs to assure l l that suitable proficiency is achieved and maintained in the l l work they are performing. l l l l 3.3 Fire protection training for plant personnel is included as l
,. l part of industrial safety in the General Employee Training l l Program. Personnel are periodically retrained in industrial l l safety in accordance with plant procedures. Personnel assigned l l to the plant Fire Brigade are to receive additional l l indoctrination and training to assure their capability to fight l l fires is established and maintained. The Safety and Fire l l Prevention Coordinators have the overall responsibility for l l these training programs. l l l l 4.0 DESIGN CONTROL l l l l 4.1 Section 3.0 of this manual is applicable for design control l l activities pertaining to the fire protection system. l l l l 1 l l l A. l TOPICAL REPORT lREV. 7 l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-4 l l L l FOR FIRE PROTECTION l l l l l l
I I I l l 5.0 PROCUREMENT DOCUMENT CONTROL l l I p l 5.1 The control of procurement documents for fire protection l v l related materials, parts and components is described in Section l l 4.0 of this manual with the exception of paragraph 4.2.3, when l l these items are not associated with the Q-list. The l l procurement document is to include the requirement that items l l be U.L. or F.M. listed for fire protection use, where l l applicable, in accordance with LRG0 and plant procedures. l l l l 6.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS l l l l 6.1 Inspections, tests, administrative controls, fire drills and l l training that govern the fire protection prcgram are prescribed l l by documented instructions, procedures and drawings and are l l accomplished in accordance with these documents. A listing and l l brief description of procedures relating to fire protection l l activities is provided in the AP&L Fire Protection Program l 1 Manual. Instructions, procedures and drawings are prepared, l l reviewed, approved and revised in accordance with applicable l l LRG0 and plant procedures. l l l l 7.0 DOCUMENT CONTROL I l l l 7.1 Section 6.0 of this manual is applicable for the control of I l quality program documents related to fire protection. l l l l 8.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l l (] C l The control of purchased fire protection related materials, l I l equipment and services is described in Section 7.0 of this manual, l l with the following exception related to subsections 7.2, 7.3 and l l 7.5. For the procurement of fire protection related items or l l services not associated with the Q-list, the vendor / contractor l l qualification criteria (including periodic reassessment of their l l program), is not required. Nonconformances dispositioned repair or l l use-as-is by the vendor are to be submitted to and accepted by AP&L l l only when so designated on the procurement document. l l l l 9.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS l l l l 9.1 Section 8.0 of this manual is not applicable for the l l identification and control of materials, parts and components l l related to the fire protection system. No particular l l requirements for this Section have been identified in BTP-APCSB l l 9.5-1, Rev. 2. The identification and control of materials, I l parts and components are conducted in accordance with existing l l procurement and materials management procedures and practices. 1 I I l l l l l l I I A l TOPICAL REPORT lREV. 7 l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-5 l l L l FOR FIRE PROTECTION l l l l l l
I I l l l 10.0 CONTROL OF SPECIAL PROCESSES l [ } 10.1 Section 9.0 of this manual is not applicable for the control of I l special processes, as applicable to fire protection systems. l l No particular special process controls have been identified by l l BTP-APCSB 9.5-1 Rev. 2. The control of special processes for l l the maintenance of the fire protection system are performed in l l accordance with applicable plant procedures and practices. l l l l 11.0 INSPECTION l l l l 11.1 Inspection activities applicable to the fire protection system l l are described in Section 10.0 of this manual with the exception l l of paragraphs 10.2.2 and 10.3.2.3, when inspections are l l performed on equipment not associated with the Q-list. The l l Regulatory Guides referenced in paragraph 10.2.2 are not l l applicable to the fire protection system. Individuals outside l l the QA and QC organizations who perform inspections only need l l to meet paragraphs 10.3.2 and 10.3.2.1. l l l l In addition to the provisions of this manual, inspections and l l surveillances are provided for in applicable portions of the l l Fire Protection Program Manual and the Technical Specifications l l for each nuclear unit. l l l l 12.0 TEST CONTROL l l l n l 12.1 A test program is to be established and implemented to ensure l C) l that testing is performed and verified on applicable systems l l and components to demonstrate conformance with design and l l system readiness requirements. The tests are to be performed l l in accordance with written test procedures and test results l l evaluated for conformance to the test objectives. l l l l 12.2 The control of testing activities is described in Section 11.0 l l of this manual. Surveillance testing requirements are l l identified in the Technical Specifications for each nuclear l l unit. I l l l 13.0 CONTROL OF MEASURING AND TEST EQUIPMENT l l l l 13.1 Section 12.0 of this manual is not applicable for the control l l of measuring and test equipment. No particular measuring and l l test equipment controls have been identified in BTP-APCSB9.5-1, l l Rev. 2. Measuring and test equipment is controlled in l l accordance with applicable plant procedures and practices. i l l l 14.0 HANDLING STORAGE AND SHIPPING l l l l 14.1 Section 13.0 of this manual is not applicable for the handling, l l storage and shipping of fire protection related materials and I l l n'"' l , , l l A l TOPICAL REPORT lREV. 7 l l P l lDATE 5/31/85 l l & l SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-6 l l L l FOR FIRE PROTECTION l l l l l 1
n i l I I I I equipment. No particular requirements for this Section have l l been identified in BTP-APCSB 9.5-1, Rev. 2. Handling, storage I n I and shipping activities are controlled in accordance with l V l applicable plant procedures and practices. l I I i 15.0 INSPECTION TEST AND OPERATING STATUS l l l l 15.1 Measures are established to provide for the identification of l
; l items that have satisfactorily passed required inspections and l l tests and are documented per approved instructions or i l procedures. l l
l l 15.2 Section 14.0 of this manual is applicable for identifying the i l inspection, test and operating status of the fire protection i I t,ystem. l l l l 16.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS I l l l 16.1 The control of nonconforming materials, parts and components l
'l related to the fire protection system is described in Section l l 15.0 of this manual, with the exception of paragraph 15.4, when i i the item is not associated with the Q-list. Vendor i l nonconformances are to be submitted to AP&L only when so l l designated on the procurement document. l l l l 17.0 CORRECTIVE ACTIONS l l l l 17.1 A corrective action system is to be established to ensure that l
,Q l conditions adverse to fire protection, such as failures, l V l malfunctions, deficiencies, deviations, defective components, l l uncontrolled combustible materials and nonconformances, are l l promptly identified, reported and corrected. I I l l 17.2 Corrective action activities are controlled as described in l l Section 16.0 of this manual, with the following exception l l related to paragraph 16.2.5. Vendors furnishing fire l I protection items not associated with the Q-list are not l l required to be listed on the QVL. I I I l 18.0 QUALITY ASSURANCE RECORDS l l l l 18.1 Records which furnish evidence that the criteria enumerated in l l this program are being met for activities affecting the fire l l protection program are to be prepared and maintained as l l described in Section 17.0 of this manual. A listing of l l documents and records (including calculations, test reports, I l code reports and design change packages) relating to fire l I protection is included within the AP&L Fire Protection Program l l Manual. I I I l l l 1 I I l A l TOPICAL REPORT lREV. 7 l l P l IDATE 5/31/85 l l & 1 SECTION: APPENDIX B - QUALITY PROGRAM lPAGE AB-7 l l L l FOR FIRE PROTECTION l l I l l I
/
I I I I
, i 19.0 AUDITS I l l i 19.1 Audits are to be conducted and documented to verify compliance pd l with the fire protection program, including design and i
I l procurement documents, instructions, procedures and drawings l I and inspection and test activities. Section 18.0 of this l I manual is applicable for the control of audits related to the i I fire protection program. l l l l 19.2 As a minimum, audits of the fire protection program are to be i I scheduled at specified frequencies in accordance with the i I TechnicalSgcificationsapplicabletoeachnuclearunit. I I I l l l 1 1 I I I I I l l l 1 1 I I I I I I I I l l I I l 1 1 I I I I I I I I I I I I I I I I I I I I I l l l l l , I I I I I l l l l 1 I I l l I I I I { l l 1 A l TOPICAL REPORT IREV. '7
- 1 P l lDATE 5/31/85 l 1 l & 1 SECTION
- APPENDIX B - OVALITY PROGRAM IPAGE AB-8 l l L l FOR FIRE PROTECTION l l l l l l L
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_a ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000 July 10, 1985 0CAN078504 Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Quality Assurance Manual-Operations, Revision 7 Gentlemen: Revision 6 of the subject manual was accepted by your office on May 30, 1984. Per the requirement of 10CFR50.71(e)(i), attached are two copies of Revision 7 to the Quality Assurance Manual-Operations. Please indicate receipt by signing, dating and returning this transmittal letter to the attention of Sally Benson, Licensing Section, P.O. Box 551, Little Rock, AR 72205. Very truly you s,
/
. Ted Enos Manager, Licensing JTE/SAB/sg Attachments Copy Nos.
Signature Date l
, \
MEMBER MtOOLE SOUTH UTILITIES SYSTEM
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Attachment - Record of Revisions Replace / add the following pages to the Quality. Assurance Manual Operations. The revised pages are identified by revision number and vertical lines.
' indicating the area of change. The approval page for Revision 7 is to be
'. inserted in front of the approval page for. Revision 6. (Do not remove the Revision 6 approval page.)
Remove Pages Insert Pages 1 1 thru 3 TC-1 thru TC-6 - TC-1 thru TC-8 A-1 A-1 A-2 A-2 C-7 C-7 C-8' C-8 1-1 thru l-23 1-1 thru l-23
'2-2 thru 2-8 2-2 thru 2-9 3-2 thru 3-4 3-2 thru 3-4 4-2. 4-2 5-2 thru 5-4 5-2 thru 5-4 6-2 6-2 7-2 thru 7-7 7-2 thru 7-7 9-1 9-1 10-6. 10-6 11-5 11-5 13 13-2 13-4 13-4 15-1 thru 15-5 15-1 thru 15-5 16-1 16-1 18-3 thru 18-6 18-3 thru 18-6 F-1:thru F-3 F-1 thru F-3 F-5 F-5 T1-6 T1-6 T1-9 T1-9 T1-13 T1-13 T2 T2-1
-T3-1 thru T3-3 T3-1 thru T3-3 Appendix A Tab AA-1 thru AA-3 Appendix B Tab AB-1 thru AB-8}}