0CAN079404, Quality Assurance Manual Operations,Rev 17
| ML20071K474 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/22/1994 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20071K472 | List: |
| References | |
| 0CAN079404, CAN79404, NUDOCS 9407290429 | |
| Download: ML20071K474 (230) | |
Text
ENTERGY OPERATIONS INCORPORATED SET # ARKA2iSAS NUCLEAR ONE CONTROLLED DOCUMENTS TRANSMITTAL 07/22/94 SEND TO: b 00Ah . fcul&II)*0 r RETURN TO: ARKANSAS NUCLEAR ONE s . - u Ulm/Ewo (bw DOCUMENT CONTROL ROUTE 3 BOX 137G RUSSELLVILLE. ARKANSAS 72801 (501) 964-5957 Ti1IS FORM TRANSMITS THE FOLLOWING APPROVED DOCUMENT UPDATE:
ANO-1 { ]
REVISION 17 ANO-2 { ]
GENERIC { Xl REISSUE { ]
DOCUMENTS:
ANO STATION POLICY { ] MAIN
T. PROCEDURE
WRITERS GUIDE { ]
ALTERNATE SHUTDOWN BASIS DOCUMENT { ] 0FFSITE DOSE CALCULATION MANUAL [ ]
AOP '?ECHNICAL GUIDELINES { } OPEPATIONS PROCEDURE WRITERS GUIDE { ]
B&W OWNERS GROUP GENERIC E0P BASES { ] OPERATIONS GUIDE { ]
BASIS DOCUMENT ALTERNATE SHUTDOWN { ] PMEE'S { ]
CONFIRMATORY ORDERS { ] PRE-FIRE PLAN { ]
CONSUMABLE CHEMICAL MATERIAL LIST (CCML) { ] PRINCIPLES MANAGE NUCLEAR PERSONNEL { ]
E0P SETPOINT DOCUMENT { ] QA MANUAL OPERATIONS {X 3 EMERGENCY PROCEDURF GUIDELINES CEN-152 { ] QAO'S { ]
E0P BASES DOCUMENT { ] QAD'S [ ]
E0P TECHNICAL GUIDELINES { ] QCO'S { ]
EMERGENCY PLAN { ] QAP'S [ ]
ENTERGY OPERetTION MGMT. MANUAL (VOL. II) { ] RADIATION SAFETY PROGRAM { ]
EMERGENCY TELEPHONE DIRECTORY { ] RADIOLOGICAL EMERG. RESPONSE PLAN { }
EMERGENCY RESOURCES MANUAL { ] TITLE 49 CFR { ] j FIRE HAZARD ANALYSIS (FHA) { ] PIPING & INSTRUMENT DIAGRAMS (P&ID) { ] ,
HOLDCARD COMPUTER INSTRUCTION GUIDE { ] SAR (SAFETY ANALYSIS REPORT) { ] ,
INDUSTRIAL SECURITY PLAN { ] SAR PROPRIETARY { ] !
INDEX (STANDARDS & PROCEDURES) { ] SER (SAFETY EVALUATION REPORT) { ]
LICENSING DIRECTIVES { ] TECH SPECS { ]
SIGNATURE DATE +
PLEASE SIGN AND RETURN THIS SHEET ;
i l
l g7290429940718 l p ADOCK 05000313 PDR l 1
QUALITY ASSURANCE MANUAL OPERATIONS (QAMO)
REVISION 17 Revise the QAMO with the attached pages. Revised pages are identified by revision number and vertical bar indicating the area of change.
This will be a complete revision.
REMOVE REPLACE WITH Signature Sheet Signature Sheet RR-1 thru RR-49 RR-1 thru RR-51 -
TC-1 thru TC-4 TC-1 thru TC-4 A-1 thru A-3 A-1 thru A-2 B-1 thru B-6 B-1 thru B-5
- C-1 thru C-11 C-1 thru C-9 1-1 thru l-28 1-1 thru l-28 2-1 thru 2-10 2-1 thru 2-8 3-1 thru 3-6 3-1 thru 3-4 4-1 thru 4-3 4-1 thru 4-2 5-1 thru 5-4 5-1 thru 5-4 6-1 thru 6-3 6-1 thru 6-3 !
I 7-1 thru 7-7 7-1 thru 7-6 8-1 thru 8-3 L
8-1 thru 8-3 9-1 thru 9-2 9-1 thru 9-2 10-1 thru 10-6 10-1 thru 10-5 0 11-1 thru 11-5 12-1 thru 12-4 13-1 thru 13-5 11-1 thru 11-4 12-1 thru 12-4 13-1 thru 13-4 14-1 thru 14-5 14-1 thru 14-5 15-1 thru 15-4 15-1 thru 15-4 16-1 thru 16-3 16-1 thru 16-3 17-1 thru 17-5 17-1 thru 17-5 1 18-1 thru 18-6 18-1 thru 18-6 F-1 thru F-8 F-1 thru F-8 i T1-1 thru T1-18 l T1-1 thru T1-18 T2-1 T2-1 T3-1 thru T3-2 T3-1 thru T3-2 3 i
AA-1 thru AA-4 AA-1 thru AA-4 AB-1 thru AB-13 AB-1 thru AB-11 i
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CONTROLLED SET # I ARKANSAS NUCLEAR ONE OUALITY ASSURANCE MANUAL OPERATIONS REVISION 17 APPROVED: r x; DATE:) /d 9 SUPERVISOR, QUALITY ASSURANCE b, .
APPROVED: w6 , tyvr L4 ct DATE: 7 ' '
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APPROVED: d/z) 7/ DATE: 7
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pE PRES) DENT, OPERATIONS ANO b Entergy Operations QA MANUAL OPERATIONS REV.17 DATE 07/22/94 Arkansas Nuclear One
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE O InitialIssue 6/1104 1 Response to AEC questions submitted 12/13n4 11/21n4. Revisions to Section 2, 4, and 7 as indicated.
2 Response to NRC questions submitted 3/4n5 2nn5. Procedure numbers 1005.xx changes to 1004.xx (rumber change only).
3 General revision to change AEC to NRC, 9/806 update organization, reflect NSP revisions, minor program implementation changes.
4 Eliminate Quality Assurance Committee 9/857 changes to Procurement Control-Qualification of Vendors. Orgamzational changes. IncorporateTechnical Specification changes.
5 incorporate organizational changes 10/10/80 and responses to subsequent NRC questions: Incorporate Regulatory Guides and retype document in its entirety in standardized format.
9 6 Incorporate organizational changes, delete procedural references 5/30/84 throughout manual, and accurately reflect current regulatory commitments and QA practices related to the i safe operatinn of AP&L nuclear plants. j Manual has been reformatted and retyped in its entirety.
Changes given below are identified 5/31/85 on the pages by a bar in the left margin, placed next to the affected I area. l 1
Corrected by errata (includes misspelled words) on the following pages:
A-1 2-5 10-6 TI-9 A-2 3-2 11-5 T1-13 1-10 33 13-2 T3-1
/~T QA MANUAL OPERATIONS REV.: 17
(,) DATE: 07/22/94
= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-1 Operations Arkansas Nuclear One
RECORD OF REVISIONS I I REVISION NUMBER DESCRIPTION DATE 7 (Cont.) 1-12 34 13-4 T3-2 1-18 4-2 15-2 T34 1-19 52 15-3 1-20 5-3 15-5 1-22 5-4 15-4 1-23 6-2 16-1 72 TI-6 9-1 Page C-7: Revised definition Page C-8: Revised definition Page 1-9: Rnised paragraph 1.4.2(1)
Page 1 10: Rnised F.ragraph 1.4.2.1 Page 1-11: Added paragraph 1.4.2.1.1 Paragraph 1.4.2.2 redesignated 1.4.2.1.2 Added paragraph 1.4.2.1.3 Paragraph 1.4.2.3 redesignated 1.4.2.2 and rnised Page 1-12: Paragraph 1.4.2.3.1 redesignated 1.4.2.2.1 Page1 13: Added 7) to paragraph 1.5.1.3 Page1 14 ,
& 15: Rnised paragraph 1.5.3 to delete Planning / Scheduling Supenisor Page 121: Added paragraph 1.5.8 Pages 1-1 to 1-23: Paragraphlocations changed Page 2-2: Paragraph 2.2.2 redesignated 2.2.3 and rnised Page 2-2: Paragraph 2.2.3 redesignated 2.2.4 Page 2-2: Paragraph 2.2.4 redesignated 2.2.5 Page 2-2: New paragraph 2.2.2 added Page 2-3: Rnised paragraph 2.2.5(2)
Page 2 7 and 2-8: Roised paragraph 2/ 4 Pages 2-3 to 2-9: Paragraph locations changes Page 7-3: Revised paragraphs 7.2.3 and 7.2.4 )
Pages 7-3 to 7-7: Paragraphlocations changes Page 151: Revised paragraph 15.2.1 Page 18-3: Rnised paragraph 18.3.2 Pages 18-3 to 18-6: Paragraph locations changes Page F-1: Rnised Figure 1
)
i t QA MANUAL OPERATIONS REV.: 17 k DATE: 07/22/94 1
= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-2 Operations Arkansas Nuclear One
RECORD OF REVISIONS S REVISION NUMBER DESCRIPTION Page F-2: Revised Figure 2 DATE 7 (Cont.)
Page F-3: Rnised Figure 3 Page F 5: Rnised Figure 5 Page F-6: Raised Figure 6 Page T2-1: Revised titles Page AA-1 to AA-3: New Appendix A added Page AB-1 to AB-8: New Appendix B added 8 Changes given bdow are identified 6/10/86 on the pages by a bar in the left margin, placed next to the affected area. ;
Corrected by errata (including misspelled words) on the following pages:
A-1 5-1 16-1 17-5 B-1 6-1 16-3 AB-2 2-1 7-5 17-1 AB-4 2-6 11-5 17-2 AB-10 35 15-1 174 AB Il 4-1 Page A 1: Rnised 2nd,3rd, and 4th paragraphs Page A-2: Revised 1st paragraph Changed signature Page B-5: Added ANSI N3.1 Added paragraph at end of section Page C-7: Revised definition Page C-9: Revised definition Pages 1-1: Rewritten to reflect j to 1-23 new organization Page 2-1: Revised paragraph 2.2.1 l Added paragraph 2.2.2 ,
Page 2-2: Paragraphs 2.2.3 and 2.2.4 l were 2.2.2 and 2.2.3 1 Rnised paragraphs 2.2.3 and 2.2.4 l Page 2-3: Title changes, paragraph 2.2.5 Paragraph 2.2.5 was 2.2.4 Old paragraph 2.2.5 incorporated into paragraph 2.2.2 !
I Paragraph 2.3.1. title change QA MANUAL OPERATIONS REV.: 17 g] DATE: 07/22/94 L/ Entergy SECTION: RECORD OF REVISIONS PAGE: RR-3 e
Operations Arkansas Nuclear One 1
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RECORD OF REVISIONS REVISION j DATE NUMBER DESCRIPTION ,
Pace 2 4: Title changes, paragraphs 2.3.3 8 (Cont.) I and 2.3.4 i Revised paragraph 2.4.1 Page 2-5: Title changes, paragraphs 2.4.3, 2.5.1, 2.5.2 Page 2-6: Redsed paragraph 2.5.2 and 2.6.1 Title change, paragraph 2.5.3 Page 2-8: New paragraph 2.6.6 added Paragraph 2.6.7 was 2.6.6 l Revised paragraph 2.6.7 & 2.7.1 l Page 2-9: Title change, paragraph 2.7.2 Page 31: Rnised paragraph 3.2.1 -
Page 3 2: Title changes, paragraph 3.4.1 i
Page 3 4: Revised paragraphs 3.5.1 & 3.5.3 Page 3 5: Title change, paragraph 3.5.4 Page 4-1: Title change, paragraph 4.2.1 Page 4-2: Revised paragraph 4.3 Page 4-3: Revised paragraph 4.4 Revised paragraph 5.3.1 l Page 5-2:
Title changes, paragraph 5.2.2 and 5.3.2 i Page 5-4: Revised paragraph 5.4.2 Page 6-1: Revised paragraphs 6.1 & 6.2.2 O Page 6-2: Title change, paragraph 6.2.3 Added paragraph 6.2.4 Title changes, paragraphs 7.2.1 Page 7-1:
& 7.2.2 ,
Page 7-3: Rnised paragraph 7.2.3 Title change, paragraph 7.3.1 Page 7 4: Title changes, paragraphs 7.3.2
& 7.3.3 Page 7-5: Revised paragraph 7.4.3 Page 10-4: Title changes, paragraphs 10.3.2.3
& 10.4.1 Page 10-5: Revised paragraph 10.4.2 ,
Page 10-6: Raised paragraph 10.5.3 Page 12-1: Added paragraphs 12.1.2 & 12.1.3 ,
Page 12-2: Title change, paragraph 12.2.4 -
Revised paragraph 12.3.1 Page 13-2: Title changes, paragraph 13.3.2 ,
Page 13-3: Title change, paragraph 13.5.3 Page 13-4: Title change, paragraph 13.5.5 l' Page 15-1: Revised paragraphs 15.1, 15.2.1 t
& 15.2.2 i
1 REV.: 17 O w Entergy QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-4 l
Operations ,
Arkansas Nuclear One
i RECORD OF REVISIONS I REVISION NUMBER DESCRIPTION DATE 8 (Cont) Page 15-2: Revised paragraphs 15.2.3 & 15.2.4 Page 15-3: Added paragraph 15.2.6 Paragraph 15.2.7 was 15.2.6 Moved old subsection 15.3 to Section 16 Subsection 15.3 was 15.4 Revised paragraph 15.3.1 & 15.3.2 Page 15-4: Subsection 15.4 was 15.5 Subsection 15.5 was 15.5.2 with TCvi'sions Page 16-1: Revised paragraph 16.2.1
& 16.2.2 Page 16 2: Deleted paragraphs 16.2.4
& 16.2.4.1 Paragraphs 16.2.4 & 16.2.5 were 16.2.4.2 and 16.2.4.3 Revised paragraphs 16.2.3, 16.2.4 & 16.2.5 Subsection 16.3 was 16.2.5 with revisions Page 16-3: Subsection 16.4 was 16.3 Rnised paragraph 16.4(1) & (3) e Subsection 16.5 was 16.3.2 and and Subsection 15.3 Page 16-4: Subsection 16.6 was 16.4 Page 17-4: Title change, paragraph 17.3.4 Revised paragraph 17.4.1.2 Page 18-1: Title change, paragraph 18.2.1 Page 18-2: Title change, paragraph 18.2.2 Revised paragraph 18.3.1 Page 18 4: Title change, paragraph 18.4.1 Page 18-5: Revised paragraphs 18.4.4, 18.4.5 & 18.5 Page 18-6: Revised paragraph 18.6 Page F1 Rnised organization charts Thru F-8:
Page TI 1: Revised first paragraph, tidrd column Page TI-2: Add ANSI N18.7 (Sections 5.2.7.1)
Page TI 3: Add ANSI N18.7 (Section 5.2.17)
Page T2-1: Rnised Table 2 Page T3-1: Rnised all paragraphs Page T3-2: Revised all paragraphs Page T3-3: Deleted 1
O QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 h ntergyE SECTION: RECORD OF REVISIONS PAGE: RR-5
= Operations Arkansas Nuclear One l
RECORD OF REVISIONS
'I REVISION NUMBER DESCRIPTION DATE 1
8 (Cont.) Page AA-1: Raised paragraph 1.1 i
Page AA-2: Raised introductory paragraph Page AA-3: Raised Section 12 Page AA-4: Added i Page AB-3: Title change, paragraph 2.l(1) i Rnised paragraph 2.l(2)
Page AB-4: Title changes, paragraphs 2.l(3)
(4)&(5)
Page AB-5: Revised paragraph 2.l(6) & 2.l(8) ;
Title changes, paragraph 2.l(7)
Page AB-7: Revised paragraph 5.1 l All pages in Manual: Title block revised 9 Changes given below are identified on 7/22/87 j the pages by a bar in the left margin, placed next to the affected area.
Corrected by errata (including misspelled (
words) on the following pages:
i B5 C-10 10-5 I C-1 1-4 AA-2 C-2 54 AA-3 C-6 7-5 Page A-1: Title change in 2nd paragraph ;
Page A 2: Resigned policy Page B 5: Clarify ANO Unit 2 Code i commitments l Page C-1: Added definition Page C-3: Revised definition and added new l
~
definition !
Page C-5: Added definition Page C-7: Revised definition (
Page C-8; Revised definition ;
Page 1-1 thru l-3: Rewritten to reflect current organization Page 1-9: Revised responsibilities Page 1-10: Changed name title !
Page 1-13: Revised responsibilities in paragraph 1.4.1.3.2.
Changed name title ,
h QA MANUAL OPERATIONS REV.; 17 DATE: 07/22/94 4
= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-6 Operations Arkansas Nuclear One l
RECORD OF REVISIONS l REVISION :
NUMBER DESCRFMON DATE
+
9 (Cont.) Page 1 14: Revised responsibilities within paragraphs 1.4.1.3.2.1 and 1.4.1.3.2.3 Page1 15: Changed name title Pages 1-15
, thru l 16: Resised responsibilities in paragraphs 1.4.1.3.2.3.3 and 1.4.1.3.2.4 Page 1-17: Added paragraph 1.4.1.3.2.5.
Changed name title Page1 18: Delete 1.4.1.3.3.c and changed name title Page 1-19: Clarified paragraph Page 1-20: Revised responsibilities Page 1-21: Resised responsibilities in paragraph 1.4.2.2 Pages 121 thru 123: Paragraph 1.5 deleted and paragraphs 1.6, 1.6.1, 1.6.2, 1.6.3, and 1.7 renumbered accordingly '
Page 1-22: Changed name title Page 21: Revised paragraph 2.2.1 Page 2-3: Revised paragraph 2.2.5 and p Added paragraph 2.2.6 ,
Page 2-4: Changed name title (d .
Page 2-9: Revised paragraph 2.6.6. ,
Page 3-1: Revised paragraph 3.2.1 !
Page 3-4: Revised paragraphs 3.4.4 !
3.5.1, and 3.5.2 . i.
Page 3-5: Changed name title Page 4-1: Changed titles i Page 4-3: Revised paragraph 4.4 Page 5 2: Changed name title Page 5-3: Changed organization titles Page 5-4: Changed name title ,
Page 6-2: Revired paragraph 6.2.4 Page 7-2: Revised paragraphs 7.2.2(1) and 7.2.2(5). Deleted patagraph 7.2.2(6) .
Page 7 5: Revised pr agraph 7.4.3 >
Page 10-3: Revised paragraph 10.3.2.2 Page 10-6: Revised paragraphs 10.5.2 and 10.6 Page Il-3: Title changes ,
Page 13-2: Revised paragraph 13.3.2 QA MANUAL OPERATIONS REV.:17
_O h ntergy DATE: 07/22/94
=E Operations SECTION: RECORD OF REVISIONS PAGE: RR-7 Arkansas Nuclear One l
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RECORD OF REVISIONS l I REVISION NUMBER- DESCRIPTION DATE 9 (Cont ) Page 13-4: Revised paragraph 13.5.3 Page 15-2: Changed name title Page 16.1: Revised paragraph 16.2.2 Page 16.2: Deleted paragraph 16.2.3 and renumbered 16.2.4 and 16.2.5 accordingly. Resised new paragraph 16.2.3 Page 16-3: Revised paragraph 16.5.2 Page 16-4: Changed name title Page 18-6: Title changes Pages F-1 thru F-7: Revised organization charts Page F-8: Deleted page Page T2-1: Revised Table 2 Page T3-1: Revised section 2 totable 3 Page T3-2: Changed name title in section 4.
Revised section 5 to Table 3 Page AB 3: Moved from page AB-4 Page AB-4: Changed name title in paragraph 2.1.3 and Revised paragraph 2.1.4 Page AB-5: Deleted paragraph 2.1.8 9 The following pages were resised due to format changes:
C-4 1-11 2-6 AB-8 1-5 1-12 2-7 AB-9 l-6 1-23 2-8 AB-10 1-7 2-2 AB-6 AB-11 1-8 25 AB-7 AB-12 10 Retype manual in its entirety on new pages; 8/31/88 also made grammatical corrections (including misspelled words and punctuation throughout).
Changes given below are identified on the pages by a bar in the left margin, placed next to the affected area.
"AP&L" or " Plant" was deleted or replaced with *ANO" in the following sections:
REV.: 17 O
h ntergy
-:: E QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-8 Operations Arkansas Nuclear One
RECORD OF REVISIONS I I~ REVISION DESCRIPTION DATE NUMBER.-
10 (Cont.) Page A 1: Paragraphs 1,2 & 3 Page A-2: Paragraph 3 Page 2-1: Section 2.1 Page 2-2: Section 2.2.2 Page 2-4: Section 2.3.1 Page 2-5: Sections 2.3.4 & 2.4.1 Page 2-6: Section 2.4.3 Page 2-7: Section 2.6.1 Page 3-5: Section 3."'
Page 4-1: Section 4.2.1 Page 4-2: Section 4.2.3 Page5 1: Section 5.1.1 Page 5-3: Sections 5.3.2,5.3.3 & 5.4.1 Page 7-3: Sections 7.2.3 & 7.2.4 Page 7-4: Sections 7.3.3 & 7.4.1 Page 7-5: Sections 7.4.2 & 7.4.3 Page 7-6: Section 7.5.1 Page 12-3: Section 12.3.3 Page 13-2: Section 13.3.2 Page 15-3: Sections 15.3.1 & 15.3.2 Page 17-1: Section 17.2.1 Page 17-2: Section 17.2.2 g, Page 17-4: Sections '17.3.4 & 17.4.1 Page 18-2: Section 18.3.2 Page 18 5: Section 18.4.4 Page 18-6: Section 18.6 Page T1-1: Heading & General Page TI-2: ANSI N18.7 Page TI-9: R.G.1.58 Page T3-1: #1 & #2 Page AB-1: Sections 1.1 & l.2 Page AB-2: Section 1.4 Page AB-5: Section 2.1, #4 & #6 Page AB-6: Sections 3.1 & 3.3 Page AB-7: Section 6.1 Page AB-8: Section 8.1 Page AB 11: Sections 16.1 & 18.1 "ANO", " Plant", "LRGO" and " Departmental" were deleted or replaced with " Approved" in the following sections:
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REV.: 17
! O h EMY QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS DA'E: 07/22/94 PAGE: RR-9 i
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RECORD OF REVISIONS l REVISION NUMBER DESCRFnON DATE 10 (Cont.) Page 2-3: Sections 2.2.4 & 2.2.6 Page 2 4: Section 2.3.2 l Page 2 5: Section 2.3.3 ,
Page 2-7: Section 2.5.2 ;
Page 2-8: Section 2.6.3 Page 2-10: Section 2.6.7 Page 31: Section 3.2.1 Page 3-2: Section 3.3 Page 3-4: Sections 3.4.4,3.5.1 & 3.5.2 Page 4-1: Section 4.1 Page 4 2: Section 4.3 i
Page 5-3: Section 5.3.3 Page 6-1: Section 6.2.2 Page 7-3: Sections 7.2.3 & 7.2.4 ,
Page 7-5: Sections 7.4.3 & 7.4.4 l Page 7-6: Section 7.4.6 !
i Page 7-7: Sections 7.5.2 & 7.7 t Page 8-1: Sections 8.1.1 & 8.1.2 :
Page 8 2: Sections 8.2.2 & 8.2.3.1 Page 8-3: Section 8.4.1 Page 9-1: Sections 9.1 & 9.2.2 O Page 9 2:
Page 9-3:
Page 10-3:
Sections 9.3.2 & 9.4 Section 9.5 Sections 10.3.2 2 Page 12-2: Section 12.2.1 Page 12-3: Sections 12.3.4 & 12.3.5 Page 12-4: Sections 12.4.2 & 12.4.3 Page 13-2: Section 13.3.2 Page 13-3: Sections 13.4.2 & 13.4.4 Page 13-4: Sections 13.5.3 & 13.6.1 Page 14-1: Section 14.1.1 Page 14 2: Section 14.2.2 Page 14 3: Sections 14.2.4 & 14.2.5 Page 14-4: Sections 14.2.7 & 14.3.2 i
Page 14 5: Sections 14.3.2 & 14.4.2 Page 15-1: Sections 15.2.1 & 15.2.2 Page 15-2: Section 15.2.4 g
Page 15-3: Section 15.2.6 Page 16-1: Section 16.2.1 l i
Page 16-2: Sections 16.2.3 & 16.3 Page 16-3: Section 16.5.2 Page 17-1: Section 17.1.2 l
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O ?_e Entergy QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS REV.: 17 DATE: 07/22/94 PAGE: RR-10 Opertuons Arkansas Nuclear One
P RECORD OF REVISIONS I REVISION NUMBER _ p_ESCRIPTION DATE Page 17-3: Sections 17.3.1.2, 17.3.2.2 &
10 (Cont.)
17.3.3 Page 17-4: Sections 17.3.4, 17.4.1, 17.4.1.1 & 17.4.1.2 Page 17-5: Sections 17.5.1 & 17.6 Page T31: #2 Page AA-2: Sections 3 & 5-Page AA-3: Sections 11 & 13 Page AB 6: Section 3.1 Page AB-7: Sections 5.1 & 6.1 Page AB-8: Section 10.1 Page AB-10: Sections 13.1 & 14.1 Changed " quality program" and " Quality ,
Assurance Program" to "the QA Program" r
in the following sections:
Page A-1: Paragraphs 1,2,3 & 4 Page A-2: Paragraphs 2 & 3 Page B-1: Paragraphs 2,3 & 4 Page B 3: Paragraph 1 Page B-5: Paragraphs 2 & 9 Page 2-1: Sections 2.1 & 2.2 Page 2-5: Section 2.4.1 Page 2-6: Section 2.4.3 Page'.A: Sections 2.5.3 & 2.6.1 Page 2-8: Section 2.6.2 Page 2 9: Sections 2.6.5 & 2.7.1 Page 2-10: Section 2.7.2 Page 3-5: Section 3.6 Page 5-2: Section 5.3.2 Page 5-3: Section 5.3.2 Page 9-1: Section 9.2.2 Page 181: Sections 18.1.2 & 18.2.1 Page 18-4: Section 18.4.2 Page TI-1: Heading Page T3-2: #4 & #5 Other specific changes as follows:
Page A-1: 1st paragraph. revised 1st sentence O QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 h::=ntergy E SECTION: RECORD OF REVISIONS PAGE: RR-11 Operations Arkansas Nuclear One
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. l RECORD OF REVISIONS 1 l
Y k REVISION DATE l NUMBER DESCRIPTION l
10 (Ccnt.) Page A-1: 2nd paragraph, revised titles Page A-2: 1st paragraph, rnised responsibility Page B-1: 1st paragraph, rnised 1st sentence Page B-5: ASME Section Ill, Updated code edition Page B-5: Astir SNT-TC 1 A-1980, Added sentence Page B-5: Revised "*" sentence Page C-4: Added "F List" definition Page C-7: Modified definition Page C-8: Added "S-List" definition Page C-9: Modified definition Page C-10: Modified definition Page 1-1 '
to 1-23: Rewritten to reflect current organization.
Page 2-1: Section 2.2, rnised responsibilities in last sentence Page 2-2: Section 2.2.3, added " quality" O Page 2-3: Section 2.2.5, rnised responsibilities,1st,2nd
& last sentence Page 2-3: Section 2.2.6, rnised responsibilities. 2nd sentence Page 2-3: Added Section 2.2.7 Page 2-4: Added Section 2.2.8 Page 2-4: Section 2.3.1, changed title ;
Page 2 5: Section 2.3.4, rnised section Page 2 7: Section 2.5.2, redsed first l
section Page 2-10: Section 2.7.2, deleted " audit" Page 3-1: Section 3.2.1, changed title and deleted " required" Page 3-2: Section 3.3, revised 1st sentence Page 3-2: Section 3.4.1, revised 1st sentence Page 3-3: Section 3.4.2, rnised responsibilities Page 3-4: Section 3.4.4, revised responsible organization QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 w Entergy SECTION: RECORD OF REVISIONS PAGE: RR-12 Operations Arkansas Nuclear One
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RECORD OF REVISIONS S REVISION NUMBER DESCRFDON Page 3-4: Section 3.5.1, revised responsible DATE 10 (Cont.)
orgamzation Page 3-4 and 3-5: Section 3.5.3, revised section Page 3 5: Section 3.5.4, changed title Page 3-5: Section 3.6, added " root" Page 4-1: Deleted *whether procured by ;
LRGO or plant procurement group" Page 5-1: Section 5.1.1, added " quality engineering" and " oft-site" Pcge 5-2: Section 5.2.2, revised last sentence Page 5-2: Section 5.3.2, added "6000.XX",
revised responsibilities and revised last sentence Page 5-3: Section 5.3.3, rnised 1st sentence Page 5-4: Section 5.4.2 revised '
responsibilities Page 6-1: Section 6.2.2, rnised title Page 6-2: Section 6.2.3, revised title Page 6-2: Section 6.2.4, revised section Page 6-3: Section 6.7, revised 1st sentence Page 7-2: (1), revised responsibilities Page 7-3: Section 7.2.3, rnised last sentence Page 7-4: Section 7.3.2, deleted
" Quality Control" Page 7-4: Section 7.4.1, revised last sentence Page 7-5: Sections 7.4.2 & 7.4.3, mised responsibilities Page 8-3: Section 8.3, rnised section Page 9-3: Section 9.5, added "rniew" &
litle change Page 10-4: Section 10.3.2.3, revised section and title change Page 10-4: Section 10.4.1, title change Page 10-4: Section 10.4.1, rnised section Page Il-5: Section 11.3.7, rnised section Page 12-2: Section 12.2.3, rnised ist sentence Page 13-4: Section 13.5.5, title change Page 14-1: Section 14.2.1, title change I
1 QA MANUAL OPERATIONS REV.: 17 V DATE: 07/22/94 gw Entergy SECTION: RECORD OF REVISIONS PAGE: RR-13 Operations Arkansas Nuclear One l
l
l:
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE 10 (Cont.) Page 14-3: Sections 14.2.5 & 14.2.6, title change Page 14-4: Section 14.3.2 rnised responsibilities & title change Page 14-5: Section 14.4.1, title change '
Page 15 Section 15.2.3, revised 1st sentence Page 15-2: Section 15.2.4, revised 2nd sentence Page 15-3: Section 15.3.2, revised responsibilities ,
Page 15-4: Section 15.5, revised responsibilities ,
Page 16-1: Section 16.1, revised 1st sentence Page 16-1: Section 16.2.2, deleted "and evaluate their safety significance" & rnised .
3rd sentence Page 16-2: Section 16.3, revised f responsibilities Page 16-3: Section 16.5, revised heading Page 16-3: Section 16.5.1, rnised heading ,
Page 16 3: Section 16.5.2, revised ,
p responsibilities g Page 16-4: Section 16.5.4, revised section i
Page 17-1: Section 17.1.1, added " operation" Ist sentence Page 171: Section 17.1.2, added :
" maintenance" and
- personnel ,
experience" Page 171: Section 17.1.2, rnised last t sentence Page 17-2: Section 17.2.2, rnised responsibility Page 17-3: Section 17.3.1.2, revised section Page 17-4: Section 17.3.4, revised responsibilities Page 17-4: Section 17.4.1, rnised section .
Section 17.4.2, revised section !
Page 17 4: '
Page 17-5: Section 17.5.2, revised 1st sentence Page 17-5: Section 17.5.2, revised (2)
Page 18-1: Section 18.1.1, revised 1st sentence REV.: 17 (3 QA MANUAL OPERATIONS DATE: 07/22/94 Entergy SECTION: RECORD OF REVISIONS PAGE: RR-14
= Operations Arkansas Nuclear One
I RECORD OF REVISIONS I
l REVISION NUMBER plSCRIPTION DfJE 10 (Cont.) Page 18 5: Section 18.4.4, resised section Page 18-5: Section 18.5, resised responsibility Page F-1 to F-7: Updated figures Page TI-2: Added ANSI N18.7 (Section 5.2.7)
Page TI 5: Added ANSI N45.2.2 (Section 6.4.2)
Page TI-15
& TI-16: Added ANSI N45.2.9 (Section 4.3) ;
Page TI-17: Added ANSI N45.2.23 (Section 2.3.1.3) (
Page TI 18: Added AWS Dl.1 (Section 5.2.8.4)
Page T2-1: Updated matrix Page T3-1: Rnised #2 & #3 Page T3-2: Raised responsibilities #4 & #5 '
Page AB-2: Raised Section 1.5, #4 Page AB-3: Rnised Section 2.1, #2 & #3 Page AB 5: Raised Section 2.1, #5, #6 & #7 l to #4, #5 & #6 Page AB-6: Changed "QA" to "NQ" Page AB-6: Section 3.3, rnised responsibilities Page AB-9: Change "QA and QC" to "NQ" 11 Changes given below are identified on the 7/22/89 pages by a bar in the left margin, placed next to the affected area. !
Made grammatical corrections, including misspelled word and punctuation on the following pages:
A-1 2-10 14-3 B-1 3-1 14-5 ,
1-1 3-4 16-4 1-2 5-2 18-1 1 24 5-3 18 2 1-25 10-4 18-4 2-1 10-6 18 5 2-3 12-2 AA-3 24 13-1 AB 6 25 14-1 AB-9 2-6 QA MANUAL OPERATIONS REV.: 17 l h-::= Entergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-15 Operations Arkansas Nuclear One
l RECORD OF REVISIONS REVISION NUMBER DESCRFnON DATE I1 (Cont.) Page A-1: Changed title 2nd paragraph Page A-2: Changed title 1st paragraph Page B-1: Corrected issue date on Reg. Guide Page B-2: Corrected issue date of R'eg. Guide I Page 1-1: Section 1.3 revised 1st sentence, replaced " President" with Chairman of the Board",
deleted "(see figure 1)",
added last sentence Page 1-2: Section 1.3 (1) changed titles Pages 1-3 to 1-22: Rewritten to reflect new Nuclear Orgnmvation structure Page 123: All Sections in 1.3.6 were numbered 1.3.5,1.3.6.2 changed titles, two places Page 1-24: Section 1.4.1 changed titles, three places Page 1-25: Section 1.4.1.1.1 changed title, deleted */ contractors" Page 2-1: Section 2.2.1 changed last O sentence to reflect Engineering consolidation under new organization Page 2-3: Section 2.2.5 changed title l Page 2-3: Section 2.2.6 changed 2nd l sentence to reflect Engineering consolidation under New Organization l Section 2.2.4: Changed title Page 2-4: Section 2.3.1 replaced
" President" with " Chairman of the Board" Page 2-5: Section 2.3.4 changed title Page 2-9: Section 2.6.6 revised last sentence Page 3-1; Section 3.2.1 c^ _,:d 1st and 4th sentences to reflect Engineering consolidation under New l Organization I
, b V
QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 l hwE ntergy SECTION: RECORD OF REVISIONS PAGE: RR-16 4
Operations l Arkansas Nuclear One I
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________________________________________________________________________________j
RECORD OF REVISIONS REVISION NUMBER . DESCRWTION DATE I1 (Cont.) Page 3-2: Section 3.3 changed 1st sentence to reflect Enginecaing consolidation under New Organization Section 3.4.1 changed 1st sentence to reflect Engineering consolidation under New Organization replaced
" organization" with " engineering section" in 2nd sentence l I
Page 3-3: Section 3.4.21st sentence replaced " organizations" with
" engineering section" Page 3-4: Section 3.5.1 changed 1st sentence to reflect Engineering consolidation under New Organization, replace
" organization" with " engineering section" 2nd sentence Page 3-5: Section 3.5.3,1st sentence "organizz: ion" with "section" Section 3.7 changed title O' Page 5-1: Section 5.1.1 added "Rev 2" last sentence Page 5-2: Section 5.3.2 rnised section Page 5-3: Section 5.4.2 revised section Page 6-1: Section 6.2.2 revised section Section 6.2.3 revised title 1st and 2nd sentences, replaced " plant" with " approved" ist sentence, added "(excluding NQ procedures)"
ist sentence Page 6-2: Section 6.2.3 revised title last sentence Section 6.2.4 deleted section Page 6-3: Section 6.7 revised section Page 9-3: Section 9.5 revised section Page 10-2: Section 10.2.2 corrected issue dates of two Reg. Guides Page 10-4: Section 10.4.1 changed 1st sentence to reflect Engineering consolidation under New Organization Page 10 5: Section 10.4.1 added last sentence O h C :- Entergy QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS REV.: 17 DATE: 07/22/94 PAGE: RR-17 Operations Arkansas Nuclear One
i RECORD OF REVISIONS I REVISION DESCRIPTION DATE NUMBER Page 12-3: Section 12.3.3 changed " National II (Cont.)
Bureau of Standards" to new name Page 13-2: Section 13.3.2 changed titles 2nd ard 3rd sentences Page 14-1: Section 14.2.1 added " appropriate" ist sentence Page 14-4: Section 14.3.1 added " appropriate" ist and last sentences i
Section 14.3.2 added " appropriate" 2nd sentence, changed title 2nd sentence ,
Page 15-2: Section 15.2.4 changed titles 2nd sentence Page 15-3: Section 15.3.2 changed "Quahty Assurance" to " Nuclear Quality" Page 15-4: Section 15.5 revised section {
l Page 16-1: Section 16.2.2 replaced " station
- with " Plant" ist sentence Page 16-3: Section 16.5.1 revised section Section 16.5.2 revised section Page 16-4: Section 16.5.3 revised section Section 16.6 changed " Quality Assurance" to " Nuclear Quality" O Page 17-1:
Page 17-5:
Section 17.2.1 changed title 1st sentence Section 17.5.2.1 changed title 1st sentence Section 17.6 changed title 1st sentence j
Page 18 4: Section 18.4.1 resised l
2nd sentence Page 18 5: Section 18.4.4 revised 1st and 2nd sentences Page 18 6: Section 18.6 revised section ,
Pages F-1 Revised organization charts j to F-2:
Page T2-1: Revised table 2 i Pages T3-1 l l
to T3-2: Rewrote Table 3 to reflect new organization Section 12 mised tides i-t l Page AA-3:
and 2nd sentences ;
QA MANUAL OPERATIONS REV.: 17 hw E ntergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR 18 Operations Arkansas Nucisar One
DICORD OF REVISIONS l l REVISION NUMBER DESCRIPTION DATE 11 (Cont.) Page AB 3: Section 2.1 #1 deleted "Off-site" added "Overall" and replaced
" President" with " Chairman of the Board", #2 changed title and deleted "on-site", #3 changed title Page AB-5: Section 2.1 #5 changed title,
- 6 changed title 12 Changes described below are identified on the 06/15/90 pages by a bar in the left margin, placed beside the affected area.
Made grammatical corrections, including misspelled words and punctuation errors on the following pages:
A-1 1-16 14-1 A-2 1-17 14-3 B-1 1-18 14-4 11 1-19 14 5 1-2 1-20 15-2 9 l-3 1-4 1-5 1-21 1-22 1-23 15-4 16-3 16-4 1-6 1 24 18-2 1-7 2-3 18-5 1-8 2-5 AB-3 1-9 24 AB-4 1-10 2-7 AB-5 ;
l-11 2-9 T3-1 1-12 2-10 1-13 6-2 1-14 7-6 1-15 10-4 ,
Titles were changed at the following locations to reflect new offsite organization. ,
i Page A-2,1st Para.
Page 1-1. Sect.1.3,1st Para.
Page 2-4, Sect. 2.3.1 Page AB-3, Sect. 2.l(1)
QA MANUAL OPERATIONS REV.: 17 )
( DATE: 07/22/94 l
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RECORD OF REVISIONS l l REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Figure numbers were changed or added at the following locations to reflect new numbers resulting from addition of 2 new figures:
Page 12. Sect.1.3,1st Para.
Page 1-3, Sect.1.3.1 Page 1-3, Sect.1.3.1.1 Page 1-8, Sect.1.3.2 Page 1 12, Sect.1.3.3 Page 1-16, Sect.1.3.4 Page 1-20. Sect.1.3.5 and Sect.1.3.6 Removed " Nuclear" from titles on the following pages:
A-1 1-6 1-15 24 18-2 AB-5 A-2 1-7 1-20 2-7 18-5 F-1 1-1 1-8 1 21 2-9 T3-1 F-2 1-2 1-9 l-22 14 5 T3-2 F-5 1-3 1-11 1-23 15-2 AB-3 F-7 1-12 1-2/ 15-4 F-8
" Superintendent Quality ControFQuality Engineering" was changed to " Manager, Quality Control / Quality Engineering" on
{ }
the following pages:
1-9 l-11 2-5 3-5 10-4 10-5 13-4 T3-2
" Superintendent Quality Assurance" changed to " Manager. Quality Assurance" at the following locations:
1 10 13-4 1 12 16-2 2-3 17-4 2-5 18-1 2-6 18-2 REV.: 17 9 WOEntergy QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS DA~E: 07/22/94 PAGE: RR-20 Operations Arkansas Nuetear One
I RECORD OF REVISIONS
{ { REVISION NUhBER DESCRIPTION DATE i 2-7 18-4 l 12 (Cont.) !
2-10 18-5 I
7-1 18-6
)
7-4 T3-1 T3-2 Page A-1: Revised responsibilities in second paragraph to reflect Entergy l Operations consolidation.
Page B-5: Changed 4th and 8th paragraphs !
ta update ASME Code commitments l for Insenice Inspection and Repair / Replacement; changed 5th paragraph to update SNT-TC-1 A l
commitment from 1980 to 1984.
Page C-6: Removed reference to construction from duinition of" Owner".
i Page 1-1: Section 1.1, added "and Entergy Operations,Inc.'s (Entergy Operations)"; Section 1.2, replaced
' Ultimate" with "On-site"; Section 6 1.3, deleted "All".
Page 1-2: Section 1.3 (1) f, clumged to add General Manager, Materials Management Title.
Page 1-3: Section 1.3.1 (3), changed title, deleted " Operations"; Section 1.3.1 (4) new title Page1 4: Section 1.3.1.1.1.1, added positions and responsibilities removed from Section 1.3.1.1.1.1.1 and 1.3.1.1.1.1.2.
Page 1-5: Sections 1.3.1.1.1.1.1 and 1.3.1.1.1.1.2, positions and responsit.ilities reassigned in Section 1.3.1.1.1.1.
Page 1-5: Section 1.3.1.1.4, description and of new position; Section 1.3.1.1.5, QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 d h:-: Entergy SECTION: RECORD OF REVISIONS PAGE: RR-21 Onorations Arkansas Nuclear One
RECORD OF REVISIONS l REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Page 16: new section developed to describe planning and scheduling functions; Section 1.3.1.2, deleted " Operations" from title in two plar.:es and resised responsibilities. ,
Page 16: Section 1.3.1.2, (1), (2), (3),
and and (4), changed titles; Section Page 1-7: 1.3.1.2.1, changed title, deleted
" Operations"; changed " Manager Central Maintenance" title to
" Manager, Central Support";
changed supenisory functions; Section 1.3.1.2.2, complete rewrite due to 2/1/90 on-site reorganization.
Page 1-7: Section 1.3.1.2.3, changed title, and deleted " Operations"; changed Page 1-8: " Superintendent Chemistry and Radiochemistry
- to Manager, Chemistry and Radiochemistry";
section 1.3.1.2.4 changed title, deleted " Operations." Section ,
'd 1.3.1.3,7th Line, deleted "All".
Page 1-8: Section 1.3.1.3 (1), (2), (3),
and (4), positions revised due to on-site reorganization and in 1st line changed "ALL" to "various".
Page 1 10: Section 1.3.2.1 (3) and (5),
seworded for clarification.
Page 1-12: Section 1.3.3, functional and responsibilities and position Page 1-13: titles reporting to the General Manager, Engineering changed to reflect 2/1/90 on-site )
reorganization.
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QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 w Entergy SECTION: RECORD OF REVISIONS PAGE: RR-22 Operations Arkansas Nuclear One
RECORD OF REVISIONS l I REVISION NUMBER DESCRIPTION DE[E )
12 (Cont.) Page 1-14: Section 1.3.3.3, changed to !
described functional responsibi- I lities of Manager, Engineering l Support, a new title created by l 2/1/90 on-site reorganization; deleted responsibilities were transferred to Manager, Nuclear Engineering Design (Section 1.3.3.6)
Page 1-14: Section 1.3.3.4, changed to describe functional responsibi-lities of Manager, Engineering Standards and Programs, a new title created by 2/1/90 on-site reorganization.
Page 1-15: Section 1.3.3.4.1, deleted, responsibilities for reactor engineering transferred to the Managers, System Engineering, ANO-1 & 2, See Section 1.3.1.1.4; Section 1.3.3.4.2, deleted, responsibilities transferred to
{
Manager, Engineering Support (Sect.1.3.3.3) and Managers, System Engineering, ANO 1 & 2 (Sect.1.3.1.1.4);
Section 1.3.3.4.3, deleted, responsibilities transferred to the Manager, Engineering Standards and Programs (Sect.1.3.3.4); Section 1.3.3.5, removed " cost and schedule" responsibilities.
Page 1-14: Section 1.3.3.5, changed title of and " Superintendent Project Engineering" Page 1-15: to " Superintendent, Modification Engineering", and deleted Administrative Coordinator title; l l
l REV.: 17
/7 QA MANUAL OPERATIONS V h-~ Entergy SECT 10N: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-23 l
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RECORD OF REVISIONS l REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Section 1.3.3.6, added Manager, Nuclear Engineering Design position and described responsibilities, per 2/1/90 on-site reorganization.
Page 1-15: Section 1.3.4, resised and responsibinties of and reporting Page 1-16: to the General Manager. Technical Support and Assessment as per 2/1/90 on-site reorganization.
Section 1.3.4.1, added responsibility for management of ANO participation in industry groups.
Page 1-18: Section 1.3.4.2, deleted Manager ,
and Administrative Senices; Page 1-19: Responsibility for Computer Support has been assigned to the Manager, Engineering Support, responsibility for Office Senices and Human Resources has been assigned to the General Manager, Nuclear Support, g and responsibility for Materials
- V Management assigned to the General Manager, Materials Management.
Page 1-17: Section 1.3.4.2 ('ns 1.3.4.3 in and Rev. I1) changed positions Page 1-18: reporting to the Manager, Plant ,
Assessment per 2/1/90 on-site reorganization and deleted "and on-shift technical advice to operations";
Section 1.3.4.2.1 (was 1.3.4.3.1 in Rev. I1), changed ' Manager Industry Event Review" to
- Manager, Industry Events Analysis."
- Page 1-19: Section 1.3.4.3 (was 1.3.4.4 in i Rev. I1), changed " Manager l Training
- to " Manager, Training l
and Emergency Planning."
QA MANUAL OPERATIONS REV.: 17 i C DATE: 07/22/94
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RECORD OF REVISIONS l l REVISION NUMBER DESCRIIFTION DATE 12 (Cont.) Page 1-19: Section 1.3.4.4 (was 1.3.4.5 in Rev. I1), changed " Superintendent Security" to " Manager, Security" Section 1.3.4.5 (in Rev. I1) deleted this section, functional responsibility transferred to the General Manager, Nuclear Support.
Page 1-20: Section 1.3.5, changed the positions reporting to the General Manager Nuclear Support per onsite reorganization; deleted responsibility "for the overall management of ANO participation in the B&W and CE Owners Groups, and other industry groups
- This responsibility transferred to Manager, Licensing (Section 1.3.4.1).
Section 1.3.6, added section to e
Page 1-20:
and describe the functional Page 1-21: responsibilities of the new position General Manager, Materials Management.
Page 121: Section 1.3.7, changed from 1.3.6 ,
Section 1.3.7.1, changed from 1.3.6,1 Section 1.3.7.2, changed from 1.3.6.2 Page 1-22: Section 1.3.7.3, changed from 1.3.6.3 Page 1-22: Section 1.4 and 1.5, complete thru rc-write, clue to Entergy 1-25: Operations consolidation.
/) QA MANUAL OPERATIONS REV.: 17 O h.: - Entergy DATE: 07/22/94 SECTION: RECORD OF REVISIONS PAGE: RR-25 Operations Arkanses Nuclear One
RECORD OF REVISIONS l I REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Page 2-5: Section 2.3.4, change " Nuclear Design Senices" to " Nuclear Engineering Design"; added onsite Quality Control of Nuclear Fuel as a " Responsibility of System Engineermg';
Removed responsibility for assurance that Nuclear Fuel used at ANO is designed, procured, manufactured and utilized in acc.ordance with regulatory requirements, and related industrial codes and standards from the Superintendent Reactor Engineering. The Supenisor, Core Reload Design is now responsible for this.
Page 2-6: Section 2.4.3, deleted section as a result of Entergy Operations consolidation.
9 Page 2-7: Section 2.5.3, added "or his designee" in 7th Line Page 3.3: Section 3.4.3, added " design" in 3rd line for clarification.
Page 3-5: Section 3.5.3, reworded 2nd sentence for clarification.
Section 3.7, changed " Manager Administrative Senices" to Manager, Office Senices" to reflect the 2/1/90 on-site reorganization, and combined 1st and 2nd sentences for clarity, Page 4 2: Section 4.3, replaced "all" with
- safe:y related", for clanty.
O QA MANUAL OPERATIONS REV.: 17 b O DATE: 07/22/94 W Entergy SECTION: RECORD OF REVISIONS PAGE: RR-26 Operations Arkansas Nuclear One
RECORD OF REVISIONS l l REVISION NUMBER DESCRFnON DATE 12 (Cont.) Page 6-1: Section 6.2.3, changed " Manager Administrative Senices" to
" Manager Office Senices to reflect 2/1/90 on-site organization, deleted "(excluding NQ procedures)", and reworded 2nd sentence for clarity.
Page 7-1: Section 7.2.1, added "or his designee" in 2nd line and deleted "by the NQ organization" in the 5th line; Section 7.2.2, added "or his designee"in 2nd line.
Page 7-3: Section 7.2.3, replaced " Quality Assurance" with " Applicable" Page 7 5: Section *i.4.2 deleted "NQ" third line from bottom.
Section 7.4.3 deleted "by NQ personnel" fourth line from top.
Page 10-2: Section 10.2.2, deleted redundant G R.G.1.37 entry; Section 10.3.1, added " Instructions or" to ist sentence for clarification.
Page 10-4: Section 10.4.1, Design Change Package changed to Plant Modification Package and minor rewording for clanty.
Page 13 2: Section 13.3.2, changed
" Superintendent Radiation Protection and Radwaste" to
" Manager, Radiation Protection and Radwaste"; changed responsibility for assuring proper shipment, storage and handling of special Nuclear Material from
- Superintendent Reactor Engineering" to " Managers, System Engineering, ANO-1 & 2."
O QA MANUAL OPERATIONS REV.: 17 kj M DATE: 07/22/94 W Entergy SECTION: RECORD OF REVISIONS PAGE: RR 2't Operations Arkansas Nuclear One
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{ ) REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Page 13-4: Section 13.5.3, changed
" Superintendent Materials Management" to " General Manager, Materials Management";
Page 14-3: Section 14.2.5, rewritten to clarify intent.
Page 14-5: Section 14.3.2, disided responsibilities of" Manager ANO Engineering" between % nager.
Operations Standards" and
" Manager, Central Support."
Page 15-3: Section 15.3.2, changed
- Nuclear Quality" to "ANO Receipt inspection".
Page 15.4: Section 15.5, changed " Manager Industry Event Review" to
" Manager, Plant Assessment."
Page 16-3: Section 16.5.1, deleted determination of reportability of G signi5 cant conditions from responsibility of the department heads, full responsibility assigned to Licensing Department.
Page 16-4: Section 16.5.3, changed "Significant Condition Reports" to ' Licensee Event Reports (LERs)."
Page 17-1: Section 17.2.1, changed " Manager Administrative Senices" to
% nager, OfHce Senices."
Page 17 4: Section 17.3.4, rewritten to reflect current practices.
Page 17-5: Sections 17.5.2.1 and 17.6, changed
" Manager Administrative Senices" to % nager, Office Senices."
REV.: 17
(~h QA MANUAL OPERATIONS V Entergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-28
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RECORD OF REVISIONS l REVISION EIJMBER DESCRIPTION DATE 12 (Cont.) Page 18-4: Section 18.4.1, add "or his designee" in 2nd line.
Page 18-6: Section 18.6, revised organizational names to reflect Entergy Operations consolidation.
Page AA-1: Section 1.3, changed " January 23, 1985" to " January 26,1990."
Page AA-4: Replaced expired NRC approval certificate with current certificate.
Page AB-1: Section 1.2, changed " Fire Hazards Analysis Report" to " Fire Protection Program Manual."
Page AB-3: Section 2.1 (3), " Manager ANO .
Engineering" changed to " Manager, Engineering Standards and Programs" and minor rewording
- for clarification.
[V Section 2.1 (3)(7), deleted, Licensing Department is responsible for ANO commitments, identification and tracking. See Section 2.1 (5):
Section 2.1 (3)(8), deleted responsibility for performing safety evaluatior.s for modifications. This is the responsibility of the General Manager, Engineering. See Section 2.1 (6),
Section 3.3, changed responsibility for training to the Manager, Training and Emergency Planning.
Page AB-4: Section 2.1 (3), " Superintendent Engineering Services" changed to
" Superintendent Engineering Programs "
,O QA MANUAL OPERATIONS REV.: 17 V gw Entergy DATE: 07/22/94 PAGE: RR 29 SECTION: RECORD OF REVISIONS Operations Arkansas Nuclear One
RECORD OF REVISIONS j ) REVISION NUMBER DESCRIPTION DATE 12 (Cont.) Page AB-6: Section 3.3," Supervisor Fire Prevention / Protection" changed to
" Manager, Training and Emergency Planning."
Page T2-1: Deleted procedure LANP-201, superseded by OP-6010.001 (already in Table 2).
Page F-1: Changed organization charts to thru reflect 2/1/90 on-site organization Page F 9: and Entergy Operations consolidation.
13 Changes described below are identified on 05/01/91 the pages by a bar in the left margin, placed beside the affected area.
Page 1-2: Section 1.3 (1), deleted General Manager, Assessment,added Manager, Licensing.
Page1 3. Section 1.3.1, changed title to Manager, Standards / Executive 9 Assistant, added Manager, Training /
Emergency Planning.
Section 1.3.1.1, added Technical Assistant to Plant Manager, ANO-2.
Page 1-6: Section 1.3.1.2, added Security Department, and Modifications Department and Computer Support Department to the responsibility of the Plant Manager, Central.
Changed from Manager to Supt.,
Chemistry and Radiochemistry.
Deleted Supt., Work History and Supt., Computer Support.
Page 1-7: Section 1.3.1.2.1, added Computer Support and Work History tmder Manager, Central Support.
Section 1.3.1.2.2, changed from Manager to Supt., Chemistry and Radiochemistry.
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i RECORD OF REVISIONS l REVISION NUMBER DESCRIPTION DATE 13 (Cont.) Page 1-8: Sections 1.3.1.2.4 & l.3.1.2.5 now shown under Manager, Plant Central.
Deleted descriptions givenin 1.3.1.2.6 and 1.3.1.2.7. Section 1.3.1.3, now shown under Director, Operations includes revised responsibilities.
Page 1-9: Added Supt., Maintenance Standards Department. Section 1.3.1.4 now shown under Director, Operations.
Delete listing of Supv., Emergency Planning; Supv., Maintenance Training; Supervisor, Administ's-tion; Supv., Technical Support Training; and Supv., Simulator Support under Manager Training and Emergency Planning. Add listing of Supt., Technical Training; Supt., Emergency Planning; and Supv., Curriculum Standards under Manager, Training and Emergency Planning.
A Page 1 12: 1.3.2.1 (6), Manager, Quality Assurance no longer specifically reviews and approves QA programs for outside organizations but ensures approval and control of such programs.
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QA MANUAL OPERATIONS REV.: 17
('.
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Arkansas Nuclear One
RECORD OF REVISIONS l l REVISION NUMBER DESCRIPTION PATE 13 (Cont.) Page 1-14: Section 1.3.2.3, Manager, Plant Assessment now shown under General Manager, Q.sality. Deleted examples of areas under Assessment.
Section 1.3.2.3.1 & l.3.2.3.2 shown as reponing to Manager, Plant Assessment. Section 1.3.2.3.2 redefmed how to accomplish responsibilities.
Page 1-15: Section 1.3.2.3.2, redefmed how to accomplish assisting management in monitoring and evaluating ANO performance.
Page 1-16: Section 1.3.3, delete responsibility and 1-18: for Modifications Department from General Manager, Engineering.
Section on Modifications Department deleted. Section 1.3.4, deletes Contract Administration support responsibilities from General Manager, Support.
Page 1-18: Section 1.3.4, Fitness for Duty Department now shown under General Manager, Support and changed titles of Controller, Manager, Staff Support and added Medical Resiew OIIicer.
Page 1-19: Section 1.3.6, Manager, Licensing now shown reporting to Vice President, Operations. Supv.,
Plant Licensing / Compliance changed to Supv., Plant Licensing.
Page1 21: Section 1.3.7.1, der:ript;on of "offsite" independent review deleted.
QA MANUAL OPERATIONS REV.: 17 h[N e Entergy DATE: 07/22/94 PAGE: RR-32 SECTION: RECORD OF REVISIONS Operations Arkansas Nuetear One
RECORD OF REVISIONS l l REVISION NUMBER DESCRFNON DATE 13 (Cont.) Page 1-25: Section 1.4.4, added as per and 126: Supplier QA Organization change.
Section 1.4.4.1 & l.4.4.1.1 added as per above. Section 1.4.4.1, clarifies Senice QA Program application to nuclear fuel procurement. Section 1.5, defines on-site surveillance, inspection, etc , for materials and senices.
Removed " Nuclear" from tides on the following pages:
11 1-3 1-10 1-11 2-2 2-3 29 3-3 4-2 5-2 6-1 6-3 83 10-4 12-2 16-4 18-2 T3-1 T3-2 Grammatical Corrections:
Page 1-4: Deleted "s" from Reactor l }
Operator (s) License.
Tides and Responsibilities were changed to reflect changes in the Quality Organization for the Supplier QA function:
1 12 1 25 1-26 2-5 7-1 7-2 7-3 7-4 7-5 16-2 18-5 T3 2 AB-9 Page 2-6: Section 2.5.2, responsibility for submittal of changes to the QA Manual to management for review prior to approval changed from QA to Licensing.
Page 2-9: Section 2.6.6, PSC composition revised to include varied members at or above the superintendent level.
I e = Entergy QA MANUAL OPERATIONS SECTION: RECORD OF REVISIONS REV.: 17 DATE: 07/22/94 PAGE: RR 33 1
Operations l Arkansas Nuclear One
RECORD OF REVISIONS l REVISION NUhEER DESCRIPTION DATE 13 (Cont.) Page 5 2: Section 5.3.2, non-intent changes to procedures identified in Tech Specs no longer require PSC review prior to approval /
l issuance.
Page 7-1: Section 7.2.1 and 7.2.2, changes Manager, Supplier QA to Supt.,
Supplier QA.
Page 7-2: Section 7.2.2, deletion of where ASME Procurements do not apply replaced by where it does apply. Section 7.2.2(2),
function previously performed I by CASE now done by NUPlc f Section 7.3.3, same as above.
Page 7 4: Section 7.3.2, change Manager, Supplier QA to Supt., Supplier QA. Section 7.3.3, change Manager Supplier QA to Supt.,
Supplier QA. Delete reference of this application to ASME procurement.
Page Il-3: Section 11.3.2.2 departmental name change from Engineering "Senices" to Engineering
" Programs".
Page 14-5: Section 14.3.2, responsibility for procedures and instructions associated with preventive maintenance changed from Manager.
Ops Standards to Manager, Central Support.
Page 16-1: Section 16.2.2, change requires that only "significant" conditions adverse to safety require root cause identification.
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t REVISION f
DESCRIPTION DATE l NUMBER _
Page 16-2: Section 16.3, Supplier QA will 13 (Cont.)
evaluate vendors' who furnish products or services that do not conform to the requirements of the applicable purchase contract.
Page 16-3: Section 16.5.3, requirement for final approval of corrective action by the General Manager, Assessment is deleted. Section 16.5.2, only "significant" adverse conditions are reportable.
Section 16.6, added " responsible" for clarity.
Page 18-1: Section 18.2.1, Supt., Supplier QA designated as co-responsible for audits.
Page 18-3: Section 18.3.3, audit schedules for vendor / contractor are approved by the Supt., Supplier ,
QA.
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\' Page 18-4: Section 18.4.1, clarifies approvallevel of audit plans and checklist. Section 18.4.3, deficiencies now identified on Quality Assurance Finding Report (QAFR) and not Audit Finding Report.
Page 18 5: Section 18.4.5, reference to Audit Finding Report (AFR) deleted. ,
External audit reports to only be distributed to Manager, QA.
Section 18.5, vendor / contractor findings to be forwarded to Document Control Center.
Page 18-6: Section 18.6, responsibility for Nuclear Fuels Audit defined to specific position (Supervisor, Services QA)instead of Entergy Corporation.
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QA MANUAL OPERATIONS DATE: 07/22/94 1
- Entergy SECTION: RECORD OF REVISIONS PAGE: RR-35 Operations l Arkansas Nuclear One l
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RECORD OF REVISIONS l REVISION NUMBER DESCRIPTION DATE ,
1 13 (Cont.) Page T2-1: Change title of 1000.12 to " Contract Administration".
Delete 1009.03, " Contract Administration Procedure" Delete 1000.11, Purchase Requisition Preparation and Control; superseded by 1033.05, Control and Use of Material Requests. ,
Delete 1000.04, Procedural Program l j Requirements; superseded by 1000.06, l
1 Procedure Control.
1 Change title of 1000.06 to Procedure Control" Delete LRNP-210 Nuclear Drawing Control Design Engineering; superseded by 1032.013, Drawing Preparation Receipt, Review and Approval.
Delete 1000.05, Procedure Format and Content; superseded by 1000.06, A Procedure Control.
lg Delete LRNP-204, Design Deficiency /
Corrective Action.
Delete 1000.17, Records Management; superseded by 1013.05, Receipt and Processing of Records.
Add 1013.006, Micrographics.
Page AB 3: Section 2.l(2), added responsibility for fire protection training to the Director, Operations.
Page AB 5: Functional responsibility for Licensing transferred to Vice President, Operations ANO.
Page F-I thru F-7: Revised organization charts.
O QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94
= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-36 Operations Arkansas Nuetear One
RECORD OF REVISIONS REVISION
, l ) NUMBER DESCRIPTION PATE l 14 The change described below is identified 07/25/91 by a bar in the left margin, placed beside f
I the aficcted area.
1 Page 14-3: Section 14.2.5, provides clarification which describes under what circumstances a temporary modification does not need to be maintained on a status log.
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RECORD OF REVISIONS REVISION NUMBER DESCRIFFION p_A]I l l 15 Page A-1: Added Entergy Operations 7/22/92 Vice President, Engineering to executives responsible for the proceduralimplementation of the QA Program within the assigned area.
Title changes: President & Chief Executive Officer, Executive Vice President & Chief Operating Officer, and Senior Vice President, Plarming and Assurance.
15 Page A 2: Title changes - direct reports 7/22/92 Vice President, Operations ANO.
Title Changes: President & Chief Executive OfIicer, Executive Vice President & Chief Operating Officer.
15 Page A-3: Title changes-direct reports 7/22/92 Vice President, Operations ANO.
Page B-6: Revised "AWS DI.1,1985" 7/22/92 G 15 to read "AWS DI.I.,1990."
15 Page C-10: Title change - direct reports 7/22/92 Vice President Operations ANO.
15 Page 1-1: Title change - Executive Vice 7/22/92 President & Chief Operating Officer.
15 Pa;;c t-2: Section 1.3(1), items a-f, 7/22/92 title change - direct reports Vice President, Operations ANO; 1.3(2) - added "(2) priority of Engineering task to (new title) Director, Engineering," and renumbered items 2-8.
15 Page 13: Section 1.3.1, title change - 7/22/92 direct reports Vice President. Operations ANO.
/ QA MANUAL OPERATIONS REV.: 17
(],) w Entergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-38 Operations l Arkansas Nuclest Or.a
RECORD OF REVISIONS REVISION l l NUMBER DESCRIFFION DATE 15 Page 1-4: Section 1.3.1.1, title change, 7/22/92
" Director, Operations" to " General Manager, Plant Operations."
15 Page 1-7: Section 1.3.1.2, title change 7/22/92
" Director Operations" to " General Manager, Plant Operations." Added fire protection and fire prevention and safety section to responsibilities of (new title) General Manager, Plant Operations.
Title change: " Superintendent, Chemistry and Radiochemistry" to " Superintendent, Chemistry."
Title change: " Manager, Security" to
" Superintendent, Plant Security."
15 Page 1-8: Section 1.3.1.2.1, added " Fire 7/22/92 Protection. Fire Prevention and Safety" to Central Support functions.
Section 1.3.1.2.2, title change, " Superintendent, h
V '
Chemistry and Radiochemistry" to " Superintendent, Chemistry."
Section 1.3.1.2.3, deleted reporting requirement: ,
" Coordinator Industry Safety reports to Manager, Radiation Protection and Radwaste.
15 Page1 9: Section 1.3.1.2.4, title change 7/22/92
" Manager,Secunty, to " Superintendent, Plant Security."
0 w: tion 1.3.1.3, title change " Director, ,
Ope. rations" to
- General Manager, Plant ,
Operations."
15 Page 1-10: Section 1.3,1.4, title changes 7/22/92
" Director, Operations," to " General Manager, Plant Operations," "Supenisor, Curriculum Standards" to " Supervisor, Training Standards,"
and " Superintendent, Emergency Planning" to
" Supervisor, Emergency Planning."
p QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 g= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-39 Operations
. yrkanses Nuclear One 1
I RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE
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15 Pages 1-11,1-12,1-14: Sections 1.3.2, 7/22/92 1.3.2.1, and 1,3.2.2; title change " General Manager, Quality" to " Director Quality." ;
15 Page 1-15: Section 1.3.2.3, title changes, 7/22/92
" General Manager Quality," to " Director, '
Quality," and " Manager, Safety Assessment" to " Supervisor, Safety Assessment." Deleted industry operations responsibilities from Director, Quality. Deleted title " Manager, Industry Events Analysis," from this section. ;
15 Page 1-16: Section 1.3.2.3.1, moved and 7/22/92 renumbered "Section 1.3.4.1;" changed repon-ing requirement for Manager, Industry Events Analysis from Manager, Plant Assessment to l Director, Licensing. (p 1-18)
Section 1.3.2.3.2, renumbered Section 1.3.2.3.1; title change, " Manager, Safety Assessment," to " Supervisor Safety Assessment."
Page 1-16: Section 1.3.4, renumbered 1.3.3; l V tide change " General Manager, Support" to
" Director Support". Added responsibility for materials management to Director, Support.
15 Page 1-17: Added responsibility for control 7/22/92 and maintenance of ANO records to Director, Suppon. Tide changes direct repons Director Suppon Section 1.3.5 moved and renumbered Section i 1.3.3.1; tide changes, " General Manager, i Materials Management" to " Manager, Materials, Purchasing and Contracts"; added responsibi-lity for rnaterials organization to Director, Suppon; corrected tides for direct repons of Manager, Material, Purchasing and Contracts.
l QA MANUAL OPERATIONS REV.: 17 f i
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RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE 15 Page 1-18: Section moved and renumbered 7/22/92 1.3.4, title changes; New titles Director, Licensing Supervisor, Licensing - Region Supenisor, Licensing - NRR Added reporting responsibility for
" Manager, Industry Events and Analysis" to Director, Licensing (Section 1.3.4.1).
15 Page 1-19: Section renumbered, (1.3.4.2 & 7/22/92 1.3.4.3; title changes:
Supenisor, Licensing - Region Supervisor, Licensing NRR Director, Licensing Added word " Operating" before license (1.3.4.3(2)).
15 Page 1-20: Title change, " General Manager, 7/22/92 O
'd Engineering," to " Director, Engineering".
Changed reporting requirement for Director, Engineering to Vice President, Engineering; Section moved and renumbered 1.3.5.
15 Page 1-21: Sections moved and renumbered 7/22/92 1.3.5.1 and 1.3.5.2; title change, " General Manager Engineering," to " Director, Engineering."
15 Page 1-22: Section 1.3.3.3, renumbered 7/22/92 -
Section 1.3.5.3; title change, " General Manager Engineering," to " Director, Engineering." Deleted responsibilities for drawing control and control of engineering records from Manager, Engineerir g Support.
Section 1.3.3.4, renumbered Section 1.3.5.4; 7/22/92 title change, " General Manager, Engineering,"
to " Director, Engineering;" and deleted 1
)
REV.: 17
/3 QA MANUAL OPERATIONS b g= Entergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-41 l Operations Arkansas Nueteer One I
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE l l responsibilities for ANO fire protection and fire prevention program from Manager, Engineer-ing Standards and Programs; title changes, direct reports of Manager, Engineering Standards and Programs.
Page 1-23: Section renumbered 1.3.5.5; 7/22/92 15 title change," General Manager, Engineering," to " Director, Engineering."
Sections renumbered 1.3.6 and 1.3.6.1 Page 1-24: Section renumbered 1.3.6.2, 7/22/92 15 title change, " Director, Operations" to
" General Manager, Plant Operations."
Section 1.4.1, title change. " President
& Chief Executive Omcer" to Chairman
& Chief Executive Omcer."
Page 1-25: Section 1.4.1, title change, 7/22/92 15
" Executive Vice President & Chief Operating Omcer" to " President & Chief Operating Omcer," and " Senior Vice President, Planning and Assurance," to "Vice President, ;
Planning and Assurance."
Section 1.4.2, title change " Executive Vice President & Chief Operating Omcer/ to
" President & Chief Operating Omcer." Added "Vice President, Engineering to reporting chain of President & Chief Operating Omcer.
Page 127 and 1-28: title change, " Senior, 7/22/92 15 Vice President, Planning and Assurance" to Vice President, Planning and Assurance."
Pages 128 and 1-29: Section 1.4.4.1.1, 1/22/92 15 deleted reference to Qualified Vendors List (QVL). Added reporting responsibilities "Supenisor Supplier QA Programs ANO, Supervisor Supplier QA Auds and Site Super-visor QA Representative to Superintendent Supplier QA.
REV.: 17
/O QA MANUAL OPERATIONS U M DATE: 07/22/94 PAGE: RR-42 W Entergy SECTION: RECORD OF REVISIONS Operations Arkansas Nuclear One
RECORD OF REVISIONS l I REVISION NUMBER DESCRIPTION DATE 15 Page 2-3: Deleted reference to Tech Spec 7/22/92 for fire protection quality program. Section 2.2.5, title change " Manager, Licensing, to
" Director, Licensing." Changed distribution responsibility for SAR (SLQL) to ANO Document Control.
15 Page 2-4: Section 2.3.1, title change, 7/22/92
" President & Chief Executive Officer" to
- Chairman & Chief Executive Officer "
15 Page 2-6: Sections 2.5.1 and 2.5.2, title 7/22/92 change, " General Manager, Quality," to
" Director, Quality."
15 Page 2-7: Section 2.5.3, title change, 7/22/92
" General Manager, Quality," to " Director, Quality."
15 Page 2-9: Section 2.7.1, title change, 7/22/92
" General Manager, Quality," to
- Director, Quality."
15 Page 3 5: Section 3.7, title change " Manager, 7/22/92 Office Senices" to " Superintendent, Admini-strative Senices."
15 Page 5 2: Section 5.3.2, added "OP-5000.xxx 7/22/92 Series - Engineering Administrative Procedures" to procedures required for resiew by the ,
Quality organization.
15 Page 5-3: Sectjon 5.3.3, deleted requirement 7/22/92 to conduct biennial procedure resiews.
15 Pages 6-1 and 6-2: Section 6.2.3, title 7/22/92 change,
- Manager, Office Senices" to
" Superintendent, Administrative Senices."
Changed responsibility for control and issuance of drawings and drawing resisions from " General Manager, Engineering," to
" Superintendent, Administrative Senices."
15 Page 7-1:Section 7.2.1, changed reference 7/22/92
- Quahfied Vendors List (QVL)," to
- Qualified Suppliers List (QSL)."
QA MANUAL OPERATIONS REV.: 17
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Operations i Arkansas Nuclear One
RECORD OF REVISIONS I I REVISION NUMBER PESCRIPTION DATE -
15 Page 7-2:Section 7.2.2, changed reference 7/22/92 "QVL" to "QSL".
15 Page 7-3:Section 7.2.3 and 7.2.4, changed 7/22/92 reference "QVL" to "QSL".
15 Page 13-4: Section 13.5.3, title change, 7/22/92
" General Manager, Materials Management," to
" Manager, Materials Purchasing and Contracts."
15 Page 15-2: Section 15.2.4, tide change, " 7/22/92 Director Operations," to " General Manager, Plant Operations." Changed reference
" appropriate General Manager" to " appropriate Director or Manager."
i 15 Page 16-3: Section 16.5.2, tide change, 7/22/92
" Manager, Licensing" to " Director, Licensing."
15 Page 17-1: Section 17.2.1, title change, 7/22/92 9 " Manager Office Senices," to " Superintendent, Administrative Senices." i 15 Page 17-5: Sections 17.5.2.1 and 17.6, tide 7/22/92 change, " Manager, Office Senices," to " Super-intendent, Administrative Senices." j 15 Page 18-2: Section 18.3.1, tide change, 7/22/92 I
' General Manager, Quality," to " Director, l Quality."
15 Fage 18-5: Section 18.4.4, title change, 7/22/92
" General Manager, Quality," to " Director, Quality."
Figures: The following figures were modified, 7/22/92 i l
deleted, and renumbered, if necessary, to reflect the ntrrent organization.
F-1 ANO & Corporate Organization (modified)
F-2 Plant Operations Department (modified)
F-3 Unit-1 Operations Organizauon (modified)
F-4 Unit 2 Operations Organization (modified)
C QA MANUAL OPERATIONS REV.: 17 C)/ g Entergy DATE: 07/22/94 PAGE: RR-44
~ ;- SECTION: RECORD OF REVISIONS Operations Arkansas Nuclear One
RECORD OF REVISIONS l l REVISION NUMBER DESCRIPTION DATE F-5 Quality Department (modified)
F-6 Support Department (modified)
F-7 Licensing Department (modified)
F-8 Engineering Department F-9 (Deleted) 15 Page TI 3: Added exception to ANSI N18.7 7/22/92 (Section 5.2.15), " Biennial reviews of ANO procedures."
15 Page T1-18: Deleted exception to AWS D1.1 7/22/92 (Swtion 5.2.8.4).
Table T2-1: Modified to reflect procedure 7/22/92 changes / deletions.
15 Page T3 2: Title change," General Manager, 7/22/92 Quality" to " Director, Quality."
15 Page AA 1: Revised approval date for Quality 7/22/92 9 Program for Transpc.. Packages to August 20, 1991.
15 Page AA-4: Incorporated Quality Assurance 7/22/92 Program Approval for Radioactive Material Packages, Rev. 5.
15 Page AB-2: Section 1.5, deleted reference to 7/22/92 FPPM.
15 Page AB-3: Section 2.1.2, title change, 7/22/92
" Director, Operations" to "" General Manager, Plant Operations.
15 Pages AB-4, AB-5, AB-6, AB-7: Fire Pro- 7/22/92 tection/ Fire Prevention changes due to change in organization; title changes.
15 Page AB 9: Deleted reference to FPPM. 7/22/92 15 Page AB 11: Deleted reference to FPPM. 7/21/92 15 Page AB-13: Section 17.2, changed reference 7/22/92 REV.: 17
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RECORD OF REVISIONS l
REVISION NUMBER DESCRIPTION DATE "QVL" to 'QSL;" Deleted reference to FPPM.
16 Page A-1: Added Entergy Operations Vice 7/22/93 President, Operations Support, Director, Human Resources, and Director, Materials, Purchasing. and Contracts to executives responsible for the procedural implementation of the QA program within the assigned area.
Deleted Vice President, Planning and Assurance l
- and Vice President Human Resou
- ces.
16 Page A-1 and A-2: Title changes- 7/22/93 l Chairman and CEO to President and CEO and President and COO to Executive Vice President and COO.
16 Page A-3: Title change - Manager, QA to 7/22/93 Supenisor, QA and changed N.S. Carns to J.W. Yelverton.
16 Page B-5: Changed ASME 1986 to 1989 Code. 7/22/93 16 Page B-6: Clarified use of ASME Code 7/22/93 through 7/22/931989.
16 Section 1.0: Incorporated new titles and 7/22/93 rearranged functions to re' lect flattening oforganization.
16 Page 2-3: Section 2.2.5 title change - 7/22/93 Manager. QA to Supenisor QA 16 Page 2-4: Section 2.3.1 title change - 7/22/93 Chairman and CEO to President and CEO.
16 Page 2 5: Title changes - Superintendent 7/22/93 Supplier QA to Manager, Quality, Supenisor, Core Reload Design to Supenisor, Fuel Fabrication, Nuclear Engineering Design to Nuclear Engineering Analysis, and Manager, QC to Director, Quality REV.: 17 b]
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-:-: Entergy QA MANUAL OPERATIONS SECTION: RECOPD OF REVISIONS DATE: 07/22/94 PAGE: RR-46 Operations Arkansas Nuclear One
)
l RECORD OF REVISIONS l l REVISION NUMBER DESCRIPTION ETg )
16 Page 2-6: Section 2.5.2 title change - 7/22/93 Manager, QA to Supenisor, QA.
16 Page 2-9: Section 2.6.6 changed PSC 7/22/93 composition from 8 members to as described in Technical Specifications. Section 2.7.1 title change - Manager, QA to Supenisors, QA.
16 Page 3-5: Section 3.5.4 title change - 7/22/93 Manager, QC/QE to Supenisor, QE.
16 Page 4-2: Changed QA section to appropriate 7/22/93 sections within Quality.
16 Page 5-2: Section 5.3.2 outlined PSC as 7/22/93 described in Technical Specifications.
16 Pages 7-1 and 7-2: Sections 7.2.1 and 7/22/93 7.2.2 title change - Superintendent, Supplier QA to Manager, Quality.
16 Pages 7-4 and 7-5: Section 7.3.2,7.3.3 7/22/93 and 7.4.3 added source verification. Title change -Superintendent, Supplier QA to Manager.
Quality and Supplier QA to Quality.
16 Page 10-4: Section 10.3.2.3 title change - 7/22/93 Manager, QA to Director, Quality. Section 10.4.1 changed Manager, QC/QE to Quality persotmel and Manager, QC/QE to Director, Quality.
16 Page 11-2: Section 11.3.2.1 added SAR. 7/22/93 16 Page 13-4: Section 13.5.5 title change - 7/22/93 Manager. QC/QE to Supenisors, QC and Manager, QA to Supenisors, QA.
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QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94 gw Entergy SECTION: RECORD OF REVISIONS PAGE: RR-47 Operations Arkansas Nuclear One
RECORD OF REVISIONS l
REVISION NUMBER DESCRIPTION DATE 16 Page 14 5: Section 14.3.2 added Managers, 7/22/93 Maintenance Unit I and 2 and changed Plant Manager, to General Manager, Plant Operations.
16 Page 15-4: Section 15.5 title change - 7/22/93 Manager, Plant Assessment to Manager, Standards or designee.
16 Page 16-1: Sections 16.1 and 16.2.1 deleted 7/22/93 reference to abnormal occurrences.
16 Pages 18-1,18-2,18 3, and 18-5: 7/22/93 Sections 8.2.1, 18.3.1, 18.3.3,18.4.4, and 18.4.5 title change - Manager, QA to Supenisors, QA and Superintendent, Supplier QA to Manager, Quality.
16 Page 18-6: Title change - Supenisors, 7/22/93 Senices QA to Manager, Quality and Senices QA to Supplier QA.
I 7/22/93 V 16 Pages F-1 through F-8: Revised to reflect ;
flattening of organization.
16 Pages T3-1 and T3 2: Title change - 7/22/93 j Manager, QA to Supenisor, QA and Manager, j QC/QE to Supenisor, QC/QE/NDE. Added procedure approval as described in the Technical Specifications.
16 Pages AB-1: Changed Fire Protection Program 7/22/93 Manual to Fire Hazards Analysis. j 16 Page AB-4: Title change - Plant Manager, 7/22/93 Central to General Manager, Plant Operations ;
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Q ntergy E SECTION: RECORDOFREVISIONS PAGE: RR-48
= Operations Arkansas Nuclear One
RECORD OF REVISIONS l
REVISION NUMBER DESCRIPTION DATE 16 Page AB-5: Title change-Director, 7/22/93 Engineering to Director, Design Engineering, Manager, Engineering Standards and Programs to Manager Engineering Programs, and Superintendent, Engineering Programs to Supervisor, Engineering Programs.
16 Page AB-6: Title change - Vice President, 7/22/93 :
Operations to Vice President, Operations ANO.
16 Page AB-7: Title change - Director, 7/22/93 Engineering to Director, Design Engineering.
Changed Technical Specifications to SAR.
16 Page AB-ll: Section 12.2 changed Technical 7/22/93 Specifications to SAR.
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/ QA MANUAL OPERATIONS REV.: 17
( hw Entergy SECTION: RECORD OF REVISIONS DATE: 07/22/94 PAGE: RR-49 Operations Arkansas Nuclear One
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RECORD OF REVISIONS l I REVISION DESCRIFTION DATE NUMBER Page C-4: Changed definition of. Modification 7/22/94 17 to support an enhanced design change process.
Section 1.0(All): Revised reporting 7/22/94 17 responsibilities and rearranged functions to reflect organizational flattening and span of control.
Section 1.3.8(All): Incorporated SRC/PSC 7/22/94 17 i
review functions to duplicate the requirements from the Technical Specifications.
Page 2-7 and 2-8: Section 2.6.6 Incorporated 7/22/94 17 experience and competence requirements frou the Technical Specifications, Section 6.5 for each operating unit. l Page 3-4: Section 3.5.4 Changed to Quality 7/22/94 l 17 '
Organization due to deletion of Supenisor, Quality Engineering.
Section 5.3.2(All):. Incorporated procedural 7/22/94 17 review requirements from the Technical Specifications, Section 6.5 for each operating unit.
Page 7 3: Section 7.3.2 - Changed to Quality 7/22/94 17 Organization to permit review at the appropriate level without section specificity.
Page 10 4: Section 10.4.1 - Changed Quality 7/22/94 17 Engineering to Quality Control; Quality -
Engineers now report to Supenisors, Quality i
Control.
Page 141: Section 14.2.1 - Changed title 7/22/94 17 from Super.isor to Superintendent.
Page 14-3: Section 14.2.6 - Changed title 7/22/94 17 from Supenitor to Superintendent.
Page 14-4: Section 14.3.2 - PM engineering 7/22/94 17 evaluations are maintained by the applicable l
Manager, Maintenance.
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EntergV SECTION: RECORD OF REVISIONS PAGE: RR-50 l
= operations l
Arkansas Nuclear One
PECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE 17 Page 14-4: Section 14.4.1 - Changed title 7/22/94 from Supenisors to Superintendents.
17 Page 15-4: Section 15.5 - Changed Manager, 7/22/94 Standards to Director Licensing due to rearranging functions.
17 Section 18.3.2(All): Incorporated audit 7/22/94 requirements from the Technical Specifica-tions, Section 6.5 for each operating unit.
17 Page 18 5: Section 18.4.5 - Changed Super- 7/22/94 visors, Quality Assurance to Superintendent, Procurement Engineering due to rearranging functiens.
17 Page 18-6: Section 18.6 - Changed ANO 7/22/94 Supenisor, Quality Assurance to Superinten-dent, Procurement Engineering due to rearranging functions.
17 Pages F-1 through F-7: Revised to reflect 7/22/94 organizational flattening and span of control.
17 Page T3-1: Section 3 - Changed Technical 7/22/94 Specifications reference to the applicable paragraph of the QA Manual.
17 Page T3-2: Section 4 - Changed Quality 7/22/94 Engineering to Quality Control or NDE due to deletion of the position of Supenisor, Quality Engineering.
u Page AB-3: Section 2.3 - Changed Manager, 7/22/94 Industrial Support to Manager, Standards and reporting relationship to reflect organiza-tional changes.
17 Page AB 5: Section 2.4(7)-Deleted the 7/22/94 word, calculation, due to the FHA being maintained as an ANO LBD vice calculation.
17 Fage AB-10 and AB 11: Section 19.2 - 7/22/94 incorporated audit requirements from the Technical Spccifications. Section 6.5 for cach operating unit.
Oh QA MANUAL OPERATIONS REV.: 17 DATE: 07/22/94
= Entergy SECTION: RECORD OF REVISIONS PAGE: RR-51 Operations Arkansas Nuclear One
l l TABLE OF CONTENTS SECTION SUBJEG PAGES APPROVAL COVERSHEET N/A RECORD OF REVISIONS RR 1 to RR-51 TABLE OF CONTENTS TC-1 to TC-4 POLICY STATEhENT A-1 to A-3 INTRODUCTION B-1 to B-5 TERMS AND DEFINITIONS C-1 to C-9 1.0 ORGANIZATION 1-1 to 128 2.0 QUALITY ASSURANCE PROGRAM 2-1 to 2-8 3.0 DESIGN CONTROL 3-1 to 3-4 4.0 PROCUREhENT DOCUMENT 4-1 to 4-2 CONTROL 5.0 INSTRUC110NS, PROCEDURES 5-1 to 5-4 l
AND DRAWINGS l I
6.0 DOCUhENT CONTROL 6-1 to 6-3 l
7.0 CONTROL OF PURCHASED 7-1 to 7-6 l MATERIAL, EQUIPMENT AND SERVICES .
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TABLE OF CONTENTS SECTION SUBJECT PAGES
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I 80 IDENTIFICATION AND CONTROL 8-1 to 8-3 OFMATERIALS PARTS AND COMPONENTS 9.0 CONTROL OF SPECIAL 9-1 to 9-2 PROCESSES 10.0 INSPECTION 10-1 to 10-5 11.0 TEST CONTROL 11-1 to 11-4 12.0 CONTROL OF MEASURING AND 12-1 to 12-4 TEST EQUIPMENT 13.0 HANDLING, STORAGE AND 13-1 to 13-4 l l SHIPPING 14.0 INSPECTION. TEST AND 14-1 to 14-5 OPERATING STATUS 15.0 NONCONFORMING MATERIAL, 15-1 to 15-4 PARTS OR COMPONENTS 16.0 CORRECTIVE ACTION 16-1 to 16 3 17.0 QUALITY ASSURANCE RECORDS 17-1 to 17-5 i
18.0 AUDITS 18-1 to 18-6 ,
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Operations SECTION: TABLE OF CONTENTS PAGE TC-2 Arkansas Nuclear One
TABLE OF CONTENTS SECTION SUBJECT PAGES l k FIGURE 1 ANO CORPORATE OFGANIZATION F1 FIGURE 2 PLANT OPERATIONS DEPARThENT F-2 UNIT 1 OPERATIONS ORGANIZATION F-3 FIGURE 3 FIGURE 4 UNIT 2 OPERATIONS ORGANIZATION F-4 QUALITY DEPARThENT F-5 FIGURE 5 FIGURE 6 SUPPORT DEPARThENT F-6 FIGURE 7 LICENSING DEPARTMENT F-7 FIGURE 8 ENGINEERING DEPARTMENT F-8 l TABLEI ANO EXCEPTIONS / INTERPRETATIONS TI I to TI 18 OF REGULATORY GUIDES AND ANSI STANDARDS i
TABLE 2 QUALITY ASSURANCE T2-1 PROCEDURES MATRIX TABLE 3 QUALITY PROGRAM POLICIES, T3-1 to T3-2 j
PROCEDURES ANDINSTRUCTION MANUALS LIST f I
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TABLE OF CONTENTS SECTION SUBJECT PAGES
{ l APPENDIX A QUALITY PROGRAM FOR AA 1 to AA 4 TRANSPORT PACKAGES APPENDIX B QUALITY PROGRAM FOR AB-1 to AB-1 FIRE PROTECTION i
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ARKANSAS NUCLEAR ONE POLICY STATEMENT l I QUALITY ASSURANCE PROGRAM FOR OPERATIONS It is the policy at Arkansas Nuclear One, Units 1 & 2 (ANO) and its supporting organizations that the Quality Assurance Program for Operations (QA Program) meets the requirements of the Code of Federal Regulations, :
Title 10, Part 50, Appendix B, with respect to operation, maintenance, refueling, repair and modifications, and inservice inspection. The QA Program shall also meet the requirements of the ASME Boiler and Pressure Vessel Code with respect to items constructed, repaired or replaced to Code requirements.
The Entergy Operations President and Chief Executive Officer has the ultimate responsibility for the safe and reliable operation of the Entergy Operations Nuclear Sites.
Under the QA Program, the Vice President, Operations ANO is the final on-site management authority responsible for assuring that this policy statement and the QA Program are implemented within ANO. The ,
Entergy Operations President and Chief Executive OfIicer; Executive Vice President and Chief Operating OfIicer; Entergy Operations Vice President Operations Support; Entergy Operations Vice President, Engineering; Director Human Resources; and l>irector, Licensing and Quality Assurance are responsible for the procedural implementation of the QA Program within their assigned areas.
The General Manager, Plant Operations; Director, Engineering; Director, Quality; Director, Support; and Director, Licensing are responsible for the daily implementation of the QA Program's procedural requirements at ANO, in their respective areas.
The Director, Quality is responsible for establishing the QA Program. Responsibility for approval of the QA Program shall be identified within this manual.
Quality personnel reporting to the Director Quality are responsible for auditing the QA Program as necessary and internal inspecting / monitoring activities required by the QA Program to assure compliance with its requirements. Disputes invohing quality, arising from ditTerence of opinions between Quality personnel and f~~N U e Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: STATEMENT OF POLICY PAGE A-1 Arkansas Nuclear One 1
other personnel, which cannot be settled interdepartmentally, shall be presented to the Vice President, g Operations ANO for resolution. The Director Quality has direct access to the Entergy Operations President and I Chief Executive Officer and the Entergy Operations Executive Vice President and Chief Operating Officer on i
matters concerning quality.
The Director, Quality through the Supervisors, Quality Assurance is to preside for an annual review of the ,
adequacy and overall effectiveness of the QA Program. Any defects in the implementation of either this policy or the QA Program that are revealed during the review are to be reported to appropriate levels of management together with appropriate recommendations.
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1 Impicmentation of this policy is necessary in order to achieve the reliability and safety required at ANO. Each person involved in activities concerning ANO is to be responsible for assuring quality in his own work, and for !
compliance with the requirements of the QA Program. The QA Program policies, manuals, and procedures are mandatory requirements which must be implemented and enforced by all responsible organizations and individuals.
ow/ aM ~
/.J W. Yelverton i Vice President. Operations ANO Date: 7//td<,/
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Arkansas Nuclear One
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INTRODUCTION I '
This manual describes the Quality Assurance Program for Operations (QA Program) applied to Arkansas Nuclear One, Units 1 & 2 (ANO) and its supporting organizations. This manual is intended to serve as a standard reference for safety analysis reports to fulfill the requirements of the Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants, Section 17, published by the Nuclear Regulatory Commission.
The objective of the QA Program is to control those phases, as applicable, for the design, procurement, manufacture and fabrication, installation, operation, testing, refueling, repair, maintenance or modification to existing safety-related (Q-List) structures, systrms and components that prevent or mitigate the consequences of a postulated accident which may cause undue risk to the health and safety of the public.
The QA Program is an outgrowth of the principle that quality assurance emanates from each individual contributor and that management is responsible for creating an awareness of quality.
The QA Program is designed to comply with the requirements of 10CFR50. Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, and also to comply with the quality assurance requirements of the ASME Boiler and Pressure Vessel Code,Section XI for repair, replacement, and inservice inspection of items covered by the Code and Licensing commitments.
O The QA Program is also designed to comply with the NRC positions contained in the following regulatory
- g. tides, subject to specific exceptions noted in Table 1 of this manual:
1.8, Rev.1-R Personnel Selection and Training (905) 1.28. Rev.1 QA Program Requirements-Design and Construction (3D8)
- 1.30 QA Requirements for Installation, inspection and Testing ofInstrumentation and Electrical Equipment (802) 1.33, Rev. 2 QA Program Requirements-Operations (2n8) 1.37 QA Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants (303)
W Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: INTRODUCTION PAGE B-1 Arkansas Nuclear One
1.38,Rev.2 QA Requirements for Packaging, Shipping, Receising.
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Storage and llandling ofitems for Water Cooled Nuclear Power Plants (5n7) 1.39, Rev. 2 Housekeeping Requirements for Water Cooled Nuclear Power Plants (907) 1.58, Rev.1 Qualification of Nuclear Power Plant inspection, Examination and Testing Personnel (9/80) 1.64, Rev. 2 QA Requirements for the Design of Nucicar Power Plants (606) 1.74 QA Terms and Definitions (2n4) 1.88,Rev.2 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records (10n6)
@ 1.94, Rev.1 QA Requirements for Installation. inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (4n6) 1.116, Rev. 0-R QA Requirements for Installation. Inspection and Testing of Mechanical Equipment and Senices (606) 1.123, Rev.1 QA Requirements for Control of Procurement ofitems and Services For Nuclear Power Plants (7/77) 1.144. Rev.1 Auditing of Quality Assurance Programs for the Nuclear Powtr Plant (9/80) 1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (8/80)
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. QA MANUAL OPERATIONS REV. 17 Operations DATE 0'fce/94 SECTION: INTRODUCTION PAGE B 2 Arkansas Nuclear One
Based upon compliance to these regulatory guides, the QA Program also complies with the following g g American National Standards Institute (ANSI) standards subject to exceptions noted in Table 1 of this manual:
N45.2-1977 Quality Assurance Program Requirements for Nuclear Facilities N45.2.1-1973 Cleaning of Fluid System and Associated Components During the Construction Phase of Nuclear Power Plants N45.2.2-1972 Packaging, Shipping, Receiving, Storage and Handling of items for Nuclear Power Plants (During the Construction Phase)
N45.2.3-1973 Housekeeping During the Construction Phase of Nuclear Power Plants N45.2.4-1972 Supplementary Quality Assurance Requirements for Installation, inspection and Testing ofInstrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations N45.2.5-1974 Supplementary Quality Assurance Requirements for Installation and Testing of Structural Concrete and
- Structural Stect During the Construction Phase of Nuclear Power Plants N45.2.6-1978 Qualifications ofInspection, Examination and Testing Personnel for Nuclear Power Plants Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: INTRODUCTION PAGE B-3 Arkansas Nuclear One
N45.2.81975 Supplementary Quslity Assurance Requirements for Installation, inspection and Testing of Mechanical g
Equipment and System for the Construction Phase of Nuclear Power Plants N45.2.9-1974 Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants N45.2.10 1973 Quality Assurance Terms and Definitions N45.2.11 1974 Quality Assurance Requirements for the Design of Nuclear Power Plants N45.2.12-1977 Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants i
N45.2.13 1976 Quality Assurance Requirements for Control of Procurement ofItems and Services for Nuclear Power I Plants j I
N45.2.23-1978 Qualification of Quality Assurance Program Audit l Personnel for Nuclear Facilities 1
l N18.1-1971 Selection and Training of Nuclear Power Plant Personnel N18.7-1976 Administrative Controls and Quality Assurance for the l
Operational Phase of Nuclear Power Plants l l
1 N3.1 1981 Selection, Qualification, and Training of Personnel for l
Nuclear Power Plants I
The above requirements are implemented by controlling activitics as described in this manual and by procedures )
referenced in this manual.
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Arkansas Nuclear One l
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i The following codes and standards are also utilized within the QA program as applicable to those activities to which they r.re referenced within various sections of this manual:
1 ASME Section 111, Division 1 - 1989 Edition, No Addenda
- l ASME Boiler and Pressure Vessel Code - Nuclear Power Plant Components 1
ASME Section XI - 1986 Edition, No Addenda (ANO Unit 2)" )
{ - 1980 Edition, Winter 81 Addenda (ANO Unit 1)"
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ASME Boiler and Pressure Vessel Code - Rules for Inservice Inspection of Nuclear Power Plant Components l
ASNT SNT-TC-I A-1984 (Endorsed thru ASME Code Case N-445, dated 50/87) l Recommended Practice for Nondestructive Testing Personnel Qualification and Certification (This edition shall be used in lieu of earlier editions that might be referenced in other codes or standards to which ANO is committed).
AWS DI.l.1990 American Welding Society Structural Steel Welding Code p
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- In lieu of the original Construction Code, all or portions oflater editions / addenda of the Code (through the 1989 edition) may be specified for repair or replacement (including system changes) of components or.-
systems, within the rules of ASME Section XI. Iflater editions / addenda are selected, design, fabrication, 3 and examination requirements shall be reconciled with the Owner's specification.
" Repair / replacement activities shall be to the 1986 Edition, No Addenda Definitions of terms applicable to the QA Program are found in the Terms and Definitions section of this manual.
O aw Entergy QA MANUAL OPERATIONS REV.17 Operations DATE 07/22/94 SECTION: INTRODUCTION PAGE B-5 Arkansas Nuclear One
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ . _ . _ . - - ___._._____o
TERMS AND DEFINITIONS l
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The terms used in this manual follow the definitions provided in ANSI N45.2.101973, supplemented by additional terms and definitions applicable to this manual.
Annroval - An act of endorsing or adding positive authorization, or both.
Anourtenance - A part that is attached to a component which has been completed.
As-Built Data - Documented data that describes the condition actually achieved in a product.
Assembly - A combination of subassemblics or components, or both, fitted together to form a unit.
Audit - An activity to determine through investigation, the adequacy of and adherence to, established procedures, instructions, specifications, codes, and standards or other applicable contractual and licensing requirements, and the eficctiveness ofimplementation.
Basic Component - A nuclear plant structure, system or component necessary to assure the nuclear safety f
O criteria.
V Bid Evaluation - A formal evaluation of all proposals received in response to an inquiry to determine the vendor to whom the purchase order will be awarded.
Certificate of Conformance - A written statement. signed by a quali6cd party, certifying that items or services comply with specific requirements.
Cenincate of Compliance - A written statement, signed by a qualined pany, attesting that the items or services are in accordance with specified requirements and accompanied by additional information to substantiate the statement. i Ceni0ed Test Report - A written and signed document, approved by a qualified pany, that contains P
sufficient data and information to verify the actual properties of items and the actual results of all required tests.
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Certification - The action of determining, verifying and attesting, in uTiting, to the qualifications of personnel or material.
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Characte[igi.q - Any property or attribute of an item, process, or senice that is distinct, describable, and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings which describe the item, pocess, or senice.
Checks - The tests, measurements, verifications or controls placed on an actisity by means of investigations, comparisons, or examinations, to determine satisfactory conditions, accuracy, safety or performance.
Cleanness - A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other contaminating impurities.
Code insoector - A qualified nuclear inspector (ANI or AN!!) employed by a legally constituted agency of a Municipality or State of the United States, or Canadian Province, or regularly employed by an Authorized Inspection Agency and having authorized jurisdiction at the site of manufacture for installation, repair, modification, and insenice inspection of ASME Boiler and Pressure Vessel items designated safety-related.
Commercial-Grade -Those items contained in Q systems and equipment that are: (1) not subject to design or specification requirements unique to nuclear facilities or activities; (2) used in application other j than nuclear facilities or activities, and (3) to be ordered on the basis of specifications set forth in manufacturer's published product description.
Component - A piece of equipment such as a vessel, piping, pump, valve or core support structure, which will be combined with other components to form an assembly, Computer Code -The application software utilized within a digital computer to accomplish a specific function or task. Computer codes requiring quality assurance are those whose satisfactory performance is required to prevent accidents which may cause undue risk to the health and safety of the public or relied ,
i upon to mitigate the consequences of such accidents if they were to occur. This involves those computer codes utilized in design and analyses of Q-list components, and those utilized as an active portion of Q-list components.
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Contaminants - Foreign materials such as mill scale, din, oil, chemicals and any matter than renders a l )-
fluid, solid or surface impure and unclean according to preset standards of acceptable cicanness.
Contractor - Any organization under contract for furnishing items or senices. It includes the terms Vendor Supplier, Subcontractor, Fabricator and sub-tier levels of these where appropriate.
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Dedication - Designating a commercial-grade item for use as a basic component after receipt. This implies that all required inspections, examinations, testing, and documentation are completed to assure compliance with the Procurement Documents.
Defective Material - A material or component which has one or more characteristics that do not comply with specified requirements.
pesiation - A nonconformance or departure of a characteristic from specified requirements.
Documentalign - Any written or pictorial information describing, defining, specifying, reporting or certifying activities, requirements, procedures, or results.
O Examination - An element ofinspection consisting ofinvestigation of materials, components, supplies or services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gaging, j I
and measurement.
F-List - A list of Non-Q fire protection' equipment within the scope of the " Quality Program for Fire Protection" (Appendix B) - that is, those fire protection and detection systems, and those structures and components (such as fire doors, fire dampers, and penetration seals) which, as identified in the plant's fire hazards analysis report, are required to restrict the damage caused by a single exposure fire to safety-related equipment and equipment required to achieve and maintait safe plant shutdown to within those limits set forth in Section I of Appendix R to 10C17t50. This list is maintained current in the SIMS computer data base.
Handlinc - An act of physically moving items by hand or mechanical means, but not including transport modes.
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]ngyin - A document that contains the necessary information for a vendor to make a proposal. An
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inquiry may include specifications pertaining to the equipment, materials or sersices proposed to be procured.
Inspecter (Owner's)- A qualified inspector employed by the Owner whose duties include the verification of quality-related activities or installations or both.
Inspection - A phase of quality control which by means of examination, observation or measurement determmes the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.
]Em - Any level of unit assembly, including structure, system, subsystem. subassembly, component, pan or material.
Job Order (J.O.)- The document used for identifying and administratively controlling the work effort on station equipment and systems. It identifies applicable procedures and drawings; documents resiews, approvals and results ofinspections and tests; and provides a mechanism for planning, scheduling and authorizing work.
Manufacturer - One who constructs any class of component, pan, or appunenance to meet prescribed design requirements.
hiaterial - A substance or combination of substances forming components, pans. pieces and equipment items. (Intended to include such as machinery, castings, liquids, formed steel shapes, aggregates, and cement.)
Modification - A physical change in plant structure, system or component which alters the design bases of the item or its applicable interfaces or requires changes to those technical requirements which govern performance of the item's design bases.
Nonconformance - A deficiency in characteristic, document or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformance include: physical defects, test failures, a g::-Entergy QA MANUAL OPERATIONS REV.17
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1 incorrect or inadequate documentation, or deviation from prescribed processing, inspection or test q procedures.
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Nuclear Safety Criteria - (1) Integrity of the reactor coolant pressure boundary; (2) capability to shutdown the tr. actor and maintain it in a safe shutdown enndition; and (3) capability to prevent or mitigate the consequences of accidents which could result in potential o!T-site exposures comparable to those referred to in 10CFR100.11.
Obiective Evidtagg - Any statement of fact, information or reeard, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements or tests which can be verified.'
Qperation - The total of administrative, maintenance and monitoring activities necessary to sustain the power generating capabilities of the plant after initial start-up.
Owner - The person, group, company or corporation who has title to the facility or installation.
Package - A wrapping or container including its contents of materials or equipment.
O Packaced Unit - An assembly ofitems and parts which can be disassembled without destroying the integrity of the individual parts.
Eau - An item which has work performed on it and which is attached to and becomes part of a component before completion of the component.
Plant - The equipment, piping. structures. buildings and property that comprise an installation or facility.
Procedure - A document that specifies or describes how an activity is to be performed. It may include methods to be employed. equipment or materials to be used and sequence of operations.
Procurement Documents - Contractually binding documents that identify and define the requirements that items or services must meet in order to be considered acceptable by the purchaser, j
V -:- . Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TERMS AND DEFINITIONS PAGE C-5 Arkansas Nuclear One
ELgig.g1 - A planned series of activities including all actions necessary to provide, utilize, and maintain a facility or portion thereof.
Erf.pgs! - A bid, usually written by a vendor in response to an inquiry, which provides the issuing pany with the vendor's proposed compliance to the inquiry and the cost.
Purchase Order (or Contract)- A document authorizing a vendor to provide equipment, material or services in accordance with stated terms and conditions.
Purchaser - T1.e organization or organizations responsible for issuance and administration of a contract, subcontract or purchase order.
O-List - A list of safety-related structures, systems, and components - that is, those structures, systems and components that must remain functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.
Oualincation (Personnel)- The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.
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O9 OualiGed Party - A person or organization competent and recognized as knowledgeable to perform cenain J functions.
Oualined Procedure - A procedure which incorporates all applicable codes and standards, manufacturcr's parameters, and engineering specifications and has been proven adequate for its intended purpose.
l Qualined Vendor List - A listing of vendors having quality assurance programs consistent with the )
l requirements of applicable ponions of 10CFR50, Appendix B. For vendors supplying ASME Code items, j thej thall s!re have a qus!ity program consistent with the requirements of applicable ponions of ASME l Section Ill, Division 1 subsection NCA. f I
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Ouality Assurance - All those planned and systematic actions necessary to provide adequate con 0dence l that an item or a facility will perform satisfactorily in service. l O aw Entergy QA M ANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TERMS AND DEFINITIONS PAGE C-6 Arkansas Nuclear One
i Ouality Control - Those quality assurance actions which provide a means to control and measure the characteristics of an item, process or facility to established requirements.
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&ceiving - Taking delivery of an item at a designated location.
Repair - The process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement,
&pgn - Something (document) that gives information for record purposes.
Review - An element ofinspection to determine conformance to specified requirements, which can be determined by examination of documents and activifes.
Rework - The process by which a nonconforming item is made to conform to a prior specified requirement by completion, remachining, reassembling or other corrective means S-List - A list of non-Q, non-F Components subject to one or more of the QA Program requirements of ,
10CFR50, Appendix B. This list is maintained current in the SIMS Computer Data Base.
Safetv Related (Q)- Safety related structures, syst ;.. .nd components are those that must remain ,
functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.
Source Surveillance - A review, observation or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procuremern or manufacture.
Specification - A concise statement of a set of requirements to be satisfied by a product, material or process indicating, whenever appropriate. the procedure by means of which it may be determined whether the requirements given are satisfied.
Standard - The result of a particular standardization c! Tort approved by a recognized authority.
Storage - The act of holdmg items at the construction site or in an area other than its permanent location in the plant.
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q g Submtu!1 - A group of assemblies or components or both combined to perform a single function. )
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Surveillance - The continuing analysis and evaluation of records, methods and procedu'es, including the act of verification, to assure conformance with technical requirements.
Syng!1 - A group of subsystems united by some interaction or interdependence, performing many duties !
but functioning as a single unit.
System Performance Test - A test performed on a completed system including electric, instrumentation, controls, fluid and mechanical subsystems under normal or simulated normal process conditions such as temperature, flow, level, and pressure.
TestincThe determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental or operating conditions.
Titles - Titles ofindividuals such as Director, Quality when used in this manual, assign the responsibility of performing the requirement to the noted individuals or their appointed designees.
O Irrpn._sil - The state of being conveyed or transported from one place to another.
Transit Carrier (Open) - Trucks, trailers, railroad cars, barges, aircrafi or ships which do not afTord items protection from the environment.
Transit Carrier (Closed) - Trucks, trailers, railroad cars, barges, aircraft or ships u hich provide protection ofitems from the em%nment by nature of their closed design.
Use-As-Is - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.
y_gndor - Any organization under contract for furnishing items or sersices. It includes the terms Contractor, Subcontractor, Supplier, Fabricator and sub-tier levels of these where appropriate, f3 b he Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 l SECTION: TERMS AND DEFINITIONS PAGE C-8 Arkansas Nuclear One l
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Verification - An act of confirming, substantiating and assuring that an activity or condition has been implemented in conformance with the specified requirements.
Work Instructions - Written instructions used to transmit detailed information on the specific measures necessary to comply with the requirements of quality assurance procedures or any complex or difTicult j quality-related task.
Work Packace - A collection of applicable documents, such as procedures, cleanliness control forms, inspection and test forms, hold card forms. Ignition Source Permits, drawings, technical manuals, etc.,
needed to perform thejob.
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Operations SECTION: TERMS AND DEFINITIONS PAGE C-9 Arkansas Nuclear One
1.0 ORGANIZATION 1.1 SCOPE This section describes the Nuclear Organizational structure and responsibilities for establishing and ,
executing the QA Program for Arkansas Nuclear One, Units 1 & 2 (ANO) in compliance with 10CFR50, Appendix B and applicable licensing commitments identified in the Introduction. It also includes a I
description of the interfaces with other organizations which may be delegated the work of establishing and executing portions of the QA Program. The Arkansas Power & Light Company's (AP&L) and Entergy Operations, Inc.'s (Entergy Operations) Corporate Organizatio*.s relevant to the operation of ANO are [
shown in Figure 1.
1.2 GENERAL RESPONSIBILITIES The on-site responsibility for ANO, including quality assurance, lies with the Vice President, Operations ANO. lie provides management assessment of the QA Program through review of reports generated by the Quality Organization and reports of NRC activities.
1.3 NUCLEAR ORGANIZATION The Nuclear Organization, headed by the Vice President, Operations ANO is responsible for activities related to the operation of ANO. These activities include as a minimum: design, operation, maintenance, j inservice inspection and test, ' n'ification and those additional activities discussed in Sections 2.0 through 18.0 of this manual. The Vice cresident, Operations ANO, who reports to the Entergy Operations Executive Vice President and Chief Operating Officer is responsible for the formulation, licensing, implementation and discharge of operating policies and procedures relative to nuclear plant operations, nuclear quality and training. The Nuclear Organization is shown in Figures I thru 8. The Vice President.
Operation ANO's duties include the following:
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(1) Providing technical direction and administrative guidance to the:
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- a. General Manager, Plant Operations
- b. Director, Quality
- c. Director, Support
- d. Director, Licensing
- e. Manager, Training & Emergency Planning
- f. Manager, Modifications (2) Prosiding priority of engineedng tasks to the Director, Engineering (3) Ensuring conformance to the QA Program by instituting the necessary procedures and instructions within the Nuclear Organization (4) Providing for review and approval of design .and engineering performed for ANO (5) Providing for review and approval of procurement documents for equipment, material and services (6) Providing for liaison between ANO and applicable regulatory agencies (7) Providing and maintaining a qualified and s.iitable stalT to carry out required departmental functions (8) Assuming overall responsibility for the fire protection, emergency planning and radiation protection programs implemented at ANO i
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1.3.1 General Manacer. Plant Operations l I The General Manager, Plant Operations reports to the Vice President, Operations ANO and has direct responsibility for operating ANO in a safe, reliable and efHeient manner. He is responsible for operating ANO in accordance with the provisions of the operating licenses. The Operations Department's organization is shown in Figure 2. The General Manager, )l:.nt Operations has the authority to shut down either unit if required. The General Manager, Plant Operations provides technical direction and administrative guidance to the:
(1) Plant Manager, Unit 1 (2) Plant Manager, Unit 2 (3) Manager, Radiation Protection and Radwaste (4) Manager in Ops Certification Training 1.3.1.1 Plant Managers, Unit-1 & 2 The Plant Managers, Unit 1 & 2 report to the General Manager, Plant Operations and are responsible for ,
the actual operation of their assigned nuclear unit, the maintenance of plant equipment and facilities and the planning / scheduling of plant work activities. The Units' Operations organizations are shown in Figures 3 and 4. The Plant Managen, Unit 1 & 2 provide technical direction and administrative guidance to their respective:
(1) Manager, Operations. Unit-1 & 2 (2) Manager, Maintenance, Unit 1 & 2 (3) Project Manager, Outages, Unit-1 & 2 (4) Manager, System Engineering. Unit 1 & 2 (5) Superintendent, Chemistry. Unit 2 (6) Manager Standards. Unit I (7) Technical Assistants to Plant Manager (8) Senior Engineers O QA MANUAL OPERATIONS REV. 17
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1.3.1.1.1 l
The Managers. Operations, Unit-1 & 2 are responsible for directing the actual day-to-day operations of their assigned unit. They supenise each unit's operating staff and interface with the respective Managers, Maintenance, Unit-1 & 2 to accomplish operation-related maintenance activities. They are responsible for coordination of the daily review of operating surveillance tests and coordination of operation-related maintenance activities. T'he Managers Operations, Unit-1 & 2 are also responsible for supenision of core refueling, which includes advance planning for the outage, plant preparation, equipment checkout and the refueling operations. The Managers, Operations each hold an NRC Senior Reactor Operator License. The Managers, Operations, Unit-1 & 2 provide technical direction and administrative guidance to the Superintendents Shift Operations of their assigned unit.
1.3.1.1.1.1 The Superintendents, Shift Operations report to the applicable Manager, Operations and are responsible for the actual operation of the unit and for the activities of the Operators during their assigned shifts. The Superintendent, Shift Operations is cognizant of operation activities being performed while on duty. The Superintendent, Shift Operations on duty has the authority to shut down the unit if, in hisjudgement, ,
O ,
conditions warrant such action. The Superintendents. Shift Operations each hold an active Senior Reactor b Operator License. The Superintendents. Shift Operations provide technical direction and administrative guidance to the:
(1) Control Room Supenisors Gioiders of active Senior Reactor Operator License)
(2) Shift Engineers (3) Control Board Operators Oloiders of active Reactor Operator License)
(4) Waste Control Operators (5) Auxiliary Operators QA MANUAL OPERATIONS REV. 17
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1.3.1.1.2 l I The Managers, Maintenance, Unit 1 & 2 report to the applicable Plant Manager and are responsible for the maintenance of plant equipment and facilities as defined by plant maintenance prograrn implementing procedures and ensuring that maintenance of equipment is performed in compliance with applicable standards, codes, specifications and procedures. The Manager, Unit 2 Maintenance has responsibility for activities common to Unit I and Unit 2 administered by the Superintendent, Central Support Maintenance.
The Managers, Maintenance, Unit 1 & 2 are also to coordinate operation-related maintenance activities with the applicable Managers. Operations, Unit-1 & 2 and are responsible to make repairs on any structure, system or :omponent under their control. The Managers, Maintenance, ANO-1 & 2 proside technical direction and administr-tNe guidance to the Maintenance Technical Staff.
1.3.1.1.3 The .'roject Managers, Outages Unit 1 & 2 report to the applicable Plant Manager and are responsible for management and direction of activities to prepare for and control scheduled and non-scheduled unit outages. The responsibilities include detailed planning, preparation and scheduling of refueling outages and other scheduled or forced outages requiring cold shutdown, and directing activities during outages.
O 1.3.1.1.4 The Managers, System Engineering, Unit 1 & 2, report to the applicable Plant Manager and are responsible for reactor, performance, and system engineering activities required for the safe and eflicient production of electricity. These activities include resolving plant related engineering issues that do not alter the design bases of the respective plants.
1.3.1.1.5 The planning and scheduling of plant work activities are executed under the ANO Plant Manager for Unit 1 & 2, respectively. The unit outage manager reports to the respective unit plant manager and is responsible for scheduling outage and non-outage work activities for that unit, supervising the scheduling staff, and interfacing with the respective unit maintenance manager, who has responsibility for planning and execution of plant work activities.
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1.3.1.1.6 l I The Manager, Standards reports to the Plant Manager, Unit I and provides planning, direction, antrol and overall supervision to the Standards Department in developing and maintaining policies and procedures for the surveillance and maintenance programs of ANO. The Manager, Standards also provides p! arming, direction, control and overall supervision to the Fire Protection, Fire Prevention, and Safety Sections, m operating and maintaining ANO. Responsibilities involve the supervision of personnel and daily work activities invohing the safe, efficient and reliable operation of ANO. Responsibilities involve the development and administration of programs which support the capability of ANO to meet or exceed industry standards and regulatory requirements. Responsibilities also involve the Chairpersonship of the Plam Safety Committee which reviews the various aspects of operation, maintenance, modification and support to assure the safety of ANO. The Manager, Standards provides technical direction and administrative guidance to:
(1) Administrative Coordinators (PSC)
(2) Planning & Scheduling Coordinators (Surveillance)
(3) Operations Coordinators (4) HPES Coordinator 1.3.1.1.7 l
The Superintendent, Chemistry reports to the Plant Manager, Unit 2 and is responsible for implementing the Nuclear Organization chemistry policies, programs, and procedures. The Superintendent, Chemistry is directly responsible for implementing controls as required to maintain chemistry and radiochemistry 1 parameters in specification and establish chemistry and radiochemistry controls conducive to maximizing (
plant life.
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1.3.1.2 Manager, Radiation Protection and Radwaste )
The Manager, Radiation Protection and Radwaste reports to the General Manager, Plant Operations and is l responsible for implementing the Nuclear Organization radiation protection and health physics policies, programs, and procedures. The Manager, Radiation Protection and Radwaste is directly responsible for implementing controls which will minimize personnel radiation exposure (ALARA). minimize personnel contamination, minimize radwaste volume, and establish uniform procedures and methods for contamination control and radiation protection.
1 REV. 17
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1.3.2 pirector. Qualin-l I The Quality Department's organization showti in Figure 5 is under the direction of the Director, Quality who reports to the Vice President, Operations ANO.
The Quality Organization performs resiews, analysis, surveillance, inspection, nondestructive examination c.nd audit functions during the operational phase of ANO. The Quality Organization is also independent of plant operations and has sufficient independence from cost and schedule when opposed to safety considerations. The Director Quality has direct access to all management levels, which assures his stafT the ability to: identify quality problems; initiate, recommend or provide solutions through designated channels; and verify implementation of solutions.
The qualification requirements of the Director, Quality are established within hisjob description which include the following prerequisites:
(1) Possess a degree from an accredited school in engineering or a related scientific discipline or equivalent (2) Possess a reinimum of four years experience in the field of quality assurance / control with at least two years in the nuclear field or equivalent number of years of nuclear plant experience in a supenisory position with at least one year experience in the implementation of the quality assurance program (3) Exhibit the ability to plan schedule and direct the activities of others assigned to or functioning within the Quality Organization Duties and responsibilities of the Director. Quality include the following:
(1) Technical direction, administrative guidance and supenision to the Coordinator, Quality; Supenisors. Quality Assurance: Supenisors, Quality Control; and Supenisor NDE (2) Approval of the QA Manual Operations and revisions thereto QA MANUAL OPERATIONS REV.17
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(3) Approval of QA and QC/QE procedures and revisions thereto as established within Quality' procedures
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1.3.2.1 Coordinator. Quality The Coordinator, Quality reports to the Director, Quality. Duties and responsibilities of the Coordinator, Quality include assisting the Director, Quality with his duties and responsibilities.
1.3.2.2 Supervisors, Quality Assurance The Supenisors, Quality Assur: ace report to the Director, Quality. Duties and responsibilities of the Supenisors, Quality Asso mcc include the following:
(1) Developing the QA Program requirements for operation, maintenance, and modification activities related to safety related (Q listed) systems, structures and components (2) Auditing of the quality activities as described in Section 18.0 of this manual (3) Providing to the Director, Quality, on an annual basis, the results of a review of the QA Program to determine the effectiveness and proper implementation of the QA Program (4) Authority to stop work where conditions exist that prohibit cfrective quality programs, or if faulty materials, incorrect workmanship or procedures are detected (5) Ensuring approval and control of quality assurance programs for outside organizations participating in the QA Program (6) Providing and maintaining a qualified and suitably trained stafTto carry out required stafT functions (7) Formulating programs for maintaiaing the professional cernpctence of personnel within the Quality Assurance section and providing assistance in Quality Assurance training and indoctrination programs for management, engineering and plant personnel whose activities afTect quality QA MANUAL OPERATIONS REV. 17
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l (8) Providing technical direction and guidance to the Quality Assurance staff (9) Inspecting, auditing or reviewing practices, records, files, instructions, directions or documents concerned with all areas affecting quality (10) Scheduling and coordinating audits or surveillance efforts in the areas assigned, documenting findings and reporting results to the Director Quality and management of the audited area 1.3.2.3 Supenisors, Quality Control / NDE The Supenisors, Quahty Control / NDE report to the Director, Quality and are responsible for venfying the implementation of the Quality Control program at ANO. The duties and responsibilities of the Supenisors include the following:
(1) Interface with plant staffin developing quality control requirements and inspection points e for operation, maintenance and modification activities related to safety-related (Q-listed) and fire protection related (F-listed) systems, structures and components t
(2) Interface with the Supenisors Quality Assurance or their representatives for technical assistance in resolving significant conditions adverse to quality (3) Authority to stop unsatisfactory work and authority to place an item in a nonconforming status when such an item is determined to be in violation of purchase documents, applicable codes and standards or SAR requirements (4) Assuring surveillances, inspections, examinations, and reviews of plant activities and documents are conducted in accordance with approved procedures (5) Providing technical direction and guidance to their staffs
/'N QA MANUAL OPERATIONS REV. 17 V = Entergy SECTION: 1.0 ORGANIZATION DATE 07/22/94 PAGE l-9 Operatio 3 i
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(6) Providing and maintaining a qualified and suitably trained staff to carry out required staff functions and formulate programs for maintaining the professional competence of personnel within the Quality Control /hi)E sections (7) Reviewing, approving and ensuring the verification of quality assurance requirements placed upon contractors or vendors that provide equipment, material or senices for ANO 1.3.3 Director. Sunnort The Director, Support reports to the Vice President, Operations ANO and is responsible for managing the nuclear five-year business plan, including establishing the budget anc. managing the goals and objectives program for the Nuclear Organization. Management of payroll, accounting and materials management is also provided by the Director, Support. He also provides planning, direction, control and overall supenision to the Fitness for Duty Department and Plant Secunty Depanment. Additionally, the control and maintenance of ANO records are a responsibility of the Director, Support. The Nuclear Support Department's organization is shown in Figure 6. The Director, Support is responsible for prosiding direction and general supenision to the following technical and administrative individuals in support of the Vice President, Operations ANO.
(1) Manager, Site Business Senices (2) Manager, Materials, Purchasing & Contracts (3) Manager, Support (4) Medical Review Officer / Physician (5) Superintendent, Administrative Senices (6) Superintendent, Plant Security (7) Coordinators, Special Projects
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1.3.3.1 Manager, Materials. Purchasing and Contracts l :
The Manager, Materials, Purchasing and Contracts reports to the Director, Suppon and has direct responsibility for procurement, receipt, storage and issue of materials, pans and components to be used in plant maintenance and modification activities. The Materials Organization is shown in Figure 6. The Manager, Materials, Purchasing and Contracts provides technical direction and administrative guidance to the following:
(1) Superintendent Procurement Engineering (2) Superintendent, Stores Operations (3) Superintendent,Inventon Control 1.3.3.2 Supenntendent, Plant Security The Superintendent, Plant Security repons to the Director, Support and is responsible for plant security including coordination of efTorts of the security force and managing the operation of the security system. ,
1.3.4 Director. Licensine O
The Director, Licensing reports to the Vice President. Operations ANO and has overall responsibility for the management and oversight of NRC inspection activities, industry and in house operation experiences, safety assessments, and interactions with the NRC regional and Washington, DC ofDees. The Licensing Department's organization is shown on Figure 7. The Director, Licensing provides technical direction and administrative guidance to the:
(1) Supervisor, Licensing-Region (2) Supervisor, Licensing-NRR (3) Supervisor, Industry Events Analysis (4) Supenisor,in-House Events Analysis and Assessment QA MANUAL OPERATIONS REV. 17
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1.3.4.1 Supenisor, Licensing-Region l
The Supenisor, Licenstr.g-ncpon repons to the Director, Licensing and is responsible for the following duties:
^
(1) Interfacing with on-site and regional regulatory agencies and the Director, Licensing pertaining to Licensing and regulatory matters (2) Providing evaluations and recommendations in meeting regulatory commitments (3) Establishing and maintaining a system for monitoring Licensee Event Reports and bHC Inspection Reports (4) Performing SAR updates i
(5) Providing technical direction and administrative guidance to the Nuclear Safety and Licensing Specialists A 1.3.4.2 Supenisor, Licensing-NRR ;
The Supervisor, Licensing NRR reports to the Director. Licensing and is responsible for the following duties:
1 (1) Interfacing with NRC, Washington, DC omces and the Director, Licensing pertaining to j Licensing and regulatory matters l (2) Establishing and maintaining programs for the maintenance of Licensing Base Documents f (Operating License SAR. Technical Specification, Emergency Plan, QA Manual j Operations) with the assistance of other department's expertise {
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(3) Responding to Generic Letters and Bulletins (4) Resiewing NRC Correspondence (incoming and outgoing) and related industry documents ,
to remain cognizant of activities that may alTect ANO
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($) Providing technical direction and administrative guidance to the Nuclear Safety and l
Licensing Specialists 1.3.4.3 Supenisor, Industry Events Analysis The Supenisor, Industry Events Analysis repons to the twector, Licensing sad observes the nuclear industry for indicators and lessons learned which can be of use to correct existing ANO problems or to avoid problems others have experienced. The section assesses applicability of current industry issues to ANO and develops proposed action plans for consideration and implementation by line management.
Inputs to this function are SOERs, SERs, O&MRs SEE IN documents, NRC Information Notices and vendor notincations (including 10CFR21 repons). Additionally, this section is the interface far reponing to Nuclear Network concerning events that occur at ANO.
1.3.4.4 Supenisor,in-House Events Analysis and Assessment The Supenisor, in-House Events Analysis and Assessment repons to the Director Licensing and has the responsibility for administration of ANO's primary corrective action program, the Condition Reporting System. This responsibility includes:
)
(1) Resiewing identined conditions adverse to quality in order to recommend appropriate dispositions to plant management (2) Assisting in the performance of root cause determinations to ensure their adequacy (3) Resiewing the actions taken to resolve conditions and taking action to ensure resolution of the condition (4) Maintaining a tracking system and reporting mechanism for identified conditions Additionally, the Supenisor,in-House Events Analysis and Assessment is responsible for providing assessments of plant and industry operating experiences, oversight of plant experiences, oversight of selected key station programs, and assisting station management in monitoring and evaluating ANO performance to ensure that effective management programs are developed, impicmented and maintained to achieve the goals and Standards of Excellence as prescribed by senior management. This responsibility is accomplished through a variety of methods including: evaluating plant programs or functional areas, independent investigations of selected plant events or conditions, and a periodic assessmet of overall plant O QA MANUAL OPERATIONS REV. 17 DATE 07/22/94
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activities. The In-House Events Analysis and Assessment section provides independent, objective assessments (outside the traditional auditing role) of the overall etTectiveness of nuclear programs to help ]
j g assure that performance expectations are being met. The inputs to this process include the assessment of f prior and current ANO performance contrasted against, comparable industry performance, the Standards of Excellence identified by INPO, and the evaluation of industry strengths and good practices for applicability to ANO, and other applicable nuclear industry requirements. The Supenisor,In-House Events Analysis i and Assessment manages the plant operation experience resiew program in accordance with INPO guidelines.
1.3.5 Manacer. Modifications
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The Manager, Modifications reports to the Vice President, Operations ANO and provides direction, control and overall supenision to the Modifications Department in directing and overseeing the implementation of plant modifications and the performance of related support activities at ANO. Responsibilities include:
directing the activities of the ANO Maintenance and Modifications Contractor and other contractors performing modification work at ANO, monitoring the efTectiveness of the ANO Plant Modifications l Program, and coordinating the resolution of related problems and the implementation of needed program improvements; and providing engineering senices to support the review, preplanning, installation, testing, inspection, and closcout of Modification Packages. The Manager, Modifications provides technical
(
direction and administrative guidance to the:
(1) Superintendent, Modifications (2) Supenisor, Cost Estimating (3) Supenisor, Startup (4) Supenisor, Modifications Central Support 1.3.6 Manacer. Traininc and Emercency Plannine The Manager, Training and Emergency Planning reports to the Vice President, Operations ANO and is responsible for the training and retraining of plant personnel and general office personnel as established by approved procedures. The Manager, Training and Emergency Planning is also responsible for the implementation and maintenance of the ANO Emergency Plan. The Manager Training and Emergency Planning directs the activities of the ANO training stafTand provides technical direction and administrative guidance to the:
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(1) Supenisor, Operations Training g ,
(2) Supenisor, Simulator Training (3) Supenisor, Simulator Support (4) Supenisor, Emergency Planning (5) Supenisor, Maintenance Training (6) Supenisor, Technical Support Training (7) Coordinator,INPO Accreditation (8) Technical Assistant to Manager, Training & Emergency Planning 1.3.7 Director. Desien Encineerine The Director, Design Engineering reports to the Vice President, Engineering and prosides direction, planning, support and overall supenision to Mechanical / Civil / Structural Design, Electrical /l&C Design.
Engineering Programs, Engineering Support (configuration management, design documentation, engmeering standards, drafting, and engineering training), and Nuclear Engineering Design.
Responsibilities include the development of programs, policies, procedures and prosiding engineering senices in support of design, evaluation, analysis, installation, testing, inspection, and operation of ANO.
This position is also responsible to ensure effective design modifications to correct deficiencies in plant systems and equipment, improve plant availability, efliciency, safety or productivity and assure thorough and complete design documentation to support effective configuration management for ANO. The Engineering Department's organization is shown in Figure 8. The Director, Design Engineering provides technical direction and administrative guidance to:
(1) Manager, Mechanical, Civil, Structural Design (2) Manager, Electrical Instrumentation & Control Design (3) Manager, Engineering Support ,
(4) Manager, Engineering Programs (5) Manager, Nuclear Engineering Design (6) Technical Assistant to Director C '
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1.3.7.1 Manager, Mechanical / Civil / Structural Design O The Manager, Mechanical, Civil, & Structural Design repons to the Director, Design Engine . ring and directs engineering activities in support of ANO, primarily in the areas of plant modifications, operability summents and maintenance of the Mechanical Engineering, Civil Engineering & Structural Engineering design bases of ANO, the primary benefit of which is safe, efficient operation of ANO in compliance with applicable regulatory requirements. This position provides technical assistance in the resolution of Operations and Maintenance concerns at the request of plant staff and is directly related to power generation operations.
1.3.7.2 Manager, Electrical / Instrumentation and Control Design The Manager, Electrical, Instrumentation and Control Design reports to the Director, Design Engineering and directs engineering activities in support of ANO, primarily in the areas of plant modifications, operability assessments and maintenance of the Electrical Engineering and Instrumentation & Control Engineering design bases for ANO, the primary benefit of which is safe, efficient operation of ANO in compliance with applicable regulatory requiremer'<. This position provides technical assistance in the resolution of Operations and Maintenance c9ncerns at the request of plant staff and is directly related to O power generation operations.
V 1.3.7.3 Manager, Engineering Support The Manager, Engineering Support repons.to the Director, Design Engineering and directs configuration controls, drafting and administrative activities in support of ANO, primarily in the areas of plant modifications, computer support. engineering standards, technical manual and engineering data bases. and cost and schedule controls for department activities, the primary benefit of which is safe, efficient operation of ANO in compliance with applicable regulatory requirements. The position directs the Design Configuration Documentation Project and is directly related to power generation operations.
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1.3.7.4 Manager, Engineering Programs l k The Manager, Engineering Programs reports to the Director, Design Engineering and is responsible for monitoring and over-viewing fire protection programs and design fire protection modifications, providing on-site engineering program senices, implementation and coordination of the insenice inspection, insenice testing, and on-site welding. The Manager, Engineering Programs provides technical direction and administrative guidance to the:
(1) Supenisors EngineeringPrograms (2) Fire Prote. tion Engineers /Specialistsfrechnicians 1.3.7.5 Manager, Nuclear Engineering Design The Manager, Nuclear Engineering Design reports to the Director, Design Engineering and directs nuclear engineering activities in support of ANO. The position provides nuclear engineering. nuclear safety analysis, environmental qualifications, technical assistance in the resclution of Operations and Maintenance concerns at the request of plant staff and is directly related to power generation operations.
1.3.8 Independent Review Orcanizations In addition to the responsibilities of key individuals within the Nuclear Organization who are involved with the overall quality program, the following committees have been established as management tools to independently resiew activities occur.i.is during the operational phase of ANO.
1.3.8.1 Safety Resiew Committee (SRC) 1.3.8.1.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear power plant operations
- b. Nuclear engineering
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- d. Metallurgy
- e. Instrumentation and control q g
- f. Radiological safety
- g. Mechanical and electrical engineering
- h. Quality assurance practices 1.3.8.1.2 Composition 1.3.8.1.2.1 The SRC shall be composed of a chairman and eight to twelve members whose collective qualifications satisfy the requirements of paragraph 2.6.6 of this manual.
1.3.8.1.2.2 The Vice President, Operations ANO shall designate, in writing, the Chairman and all SRC members.
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1.3.8.1.2.3 l l l The Chairman shall designate, in writing. the alternate Chairman in the absence of the SRC Chairman.
1.3.8.1.2.4 ,
l All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time. I 1.3.8.1.2.5 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
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1.3.8.1.3 Review Function l
1.3.8.1.3.1 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter. The minimum quorum of the SRC necessary for the performance of the SRC resiew and audit functions of these technical specifications shall consist of the Chairman or his designated alternate and at least a majority of the SRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
1.3.8.1.3.2 The SRC shall report to and advise the Vice President, Operations ANO on those areas of responsibility specified in paragraph 1.3.8.1.3.3 below.
1.3.8.1.3.3 The SRC shall review; V a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in '10 CFR 50.59.
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
- d. Proposed changes to Technical Specifications or Operating Licenses.
- e. Violations of applicable statutes, codes. regulations, orders, Technical Specifications, license requirements or ofinternal procedures or instructions having nuclear safety significance.
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- f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
- g. All REPORTABLE EVENTS pursuant to Technical Specification 6.6.2 and 6.6.1 (for Unit I and Unit 2 respectively).
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
- i. Reports and meetings minutes of the Plant Safety Committee.
J. Proposed changes to the ODCM and PCP.
- k. Audits of facility activities as specified in paragraph 18.3.2 of this manual.
1.3.8.1.4 Records of SRC activities shall be prepared, approved and distributed as indicated below;
- a. Minutes of each SRC meeting shall be prepared, appioved and forwarded to the Vice President, Operations ANO within 14 days following each meeting.
- b. Reports of reviews encompassed by paragraph 1.3.8.3.3 above shall be prepared, approved and fonvarded to the Vice President, Operations ANO within 14 days following completion of the review.
- c. Audit reports encompassed by paragraph 18.3.2 of this nainual shall be forwarded to the Vice President, Operations ANO and to the management positions responsibt? for the areas audited within 30 days after completion of the audit.
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1.3.8.2 Plant Safety Committee (PSC) l l 1.3.8.2.1 The Plant Safety Committee for each operating unit shall function to advise the General Manager, Plant Operations and applicable Plant Manager on all matters related to nuclear safety.
l 1.3.8.2.2 Composition I 1
1.3.8.2.2.1 i I
l The Pl:.nt Safety Committee for each operating unit shall be composed of eight members of ANO onsite management organization whose selection is described in internal procedures and whose qualifications satisfy the requirements of paragraph 2.6.6 cf this manual.
I 1.3.8.2.2.2 i The General Manager, Plant Operations shall designate in writing a PSC Chairman and at least one Alternate Chairman. l 1.3.8.2.2.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.
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1.3.8.2.2.4
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i For Unit 2 PSC. if Core Protection Calculator (CPC) Software is being reviewed a nuclear software expert )
shall be present as a voting member. If one of the members of the Plant Safety Committee meets the qualification requirements for this position, the requirement to have this member is satisfied. This membership may be filled by two apprnpriately qualified individuals who shall ballot with a single combined vote. Generic qualifications for this rnembership shall be as follows:
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One Individual l
The Nuclear Software Expert shall have as a minimum a Bachelor's degree in Science or Engineering, Nuclear preferred (in accordance with ANSI N18.1). In addition, he shall have a minimum of four years of technical experience, of which a minimum of two years shall be in Nuclear Engineering and a minimum of two years shall be in Software Engineering. (Software Engineering is that branch of science and technology which deals with the design and use of sonware. Software Engineering is a discipline directed to the production and modification of computer programs that are correct, efficient, flexible, maintainable, and understandable, in reasonable time spans, and at reasonable costs.) The two years of technical experience in Software Engineering may be general software experience not necessarily related to the software of the Core Protection Calculator System. One of these two years of experience shall be with certified computer programs.
Two Individuals One of the individuals shall meet the requirements of the Nuclear Engineering portion of the above. The second individual shall have a Bachelor of Science degree (digital computer speciality) and meet the Software Engineering requirements of the above.
O The membership (the Nuclear Software Expert or the Digital Computer Specialist) shall be knowledgeable of the Coie Protection Calculator System with regard to:
- a. The software modules, their interactions with each other and with the data base.
- b. The relationship between operator's module inputs and the trip variables.
- c. The relationship between sensor input signals and the trip variabic.
- d. The design basis of the Core Protection Calculator System.
- c. The approved sollware change procedure and documentation requirements of a software change,
- f. The security of the computer memory and access procedures to the memory.
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q 1.3.8.2.3 Review Function i
1.3.8.2.3.1 l The PSC for each operating unit shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternate. The minimum quorum of the PSC necessary for the performance of the PSC responsibilities designated in this manual shall consist of the Chairman or his designated alternate and four members including alternates. The PSC Chairman shall ensure that adequate expertise is present i during meetings to evaluate material before the PSC.
1.3.8.2.3.2 The Plant Safety Committee shall be responsible for:
- a. Review of 1) all station administrative procedures recommended in Appendix A of Reg Guide 1.33 (November,1972 for Unit I and Revision 2, February,1978 for Unit 2) and changes in intent thereto,2) changes to the Emergency Operating Procedures for each operating unit required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic Letter 82-33,3) changes to Core i
Protection Calculator (CPC) Software (for Unit 2), and 4) any other proposed procedures or changes thereto as determined by the General Manager Plant Operations or applicable i
Plant Manager. ;
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Appendix "A" Technica.1 Specifications for each operating unit.
- d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
- c. Investigation of all violations of the Technical Specifications, including the preparation and q forwarding of reports covering evaluation and recommendation to prevent recurrence to the l l
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applicable Plant Manager, General Manager, Plant Operations and the Chairman of the Safety Roiew Committee.
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- f. RMew of all REPORTABLE EVENTS.
- g. Roiew of facility operations to detect potential nuclear safety hazards.
l l h. Performance of special seviews, investigations or analyses, and reports thereon as requested 1
1 by a Plant Manager, General Manager, Plant Operrtions or the Safety Review Committee.
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- i. Review of the Plant Security Plan and submittal of recommended changes to the General Manager, Plant Operations and bafety Review Committee.
J. Review of the Emergency Plan and submittal of recommended changes to the General Manager, Plant Operations and Safety Resiew Committee.
- k. Review of changes to the Offsite Dose Calculation Manual and Process Control Program.
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- 1. Resiew of changes to the Fire Protection Program and submittal of recommended changes to g
the General Manager, Plant Operations and Safety Review Committee. l l
- m. Resiew of proposed procedures and changes to procedures which involve an unresiewed safety question as defined in 10CFR30.59.
1 1.3.8.2.3.3 l The Plant Safety Committee shall:
I
- a. Recommend in writing their approval or disapproval ofitems considered under paragraph 1.3.8.2.3.2(a) through (d) above.
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- b. Render determinations in writing with regard to w hether or not each item considered under paragraph 1.3.8.2.3.2(a) through (c) above constitutes an unresiewed safety question.
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- c. Provide wTitten notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Operations ANO and the Safety Resiew Committee of dis::greement between the PSC and a Plant Manager or the
{ )
General Manager, Plant Operations; however, the General Manager, Plant Operations shall
' have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1 for each operating unit.
1.3.8.2.4 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of a!! PSC activities performed under paragraphs 1.3.8.2.3.2 and 1.3.8.2.3.3 above.
Copies shall be provided to the applicable Plant Manager, General Manager, Plant Operations and Chairman of the Safety Resiew Committee.
1.4 ENTERGY OPERATIONS OFFSITE ORGANIZATION 1.4.1 Ernident & Chief Executive Ompn The President & Chief Executive Omcer has the ultimate responsibility for the safe and reliable operation of the Entergy Operations' nuclear sites. He provides guidance with regard to quality assurance and 1 internal audit policy, coordinates foreign visits, interfaces with World Association of Nuclear Operations, interfaces with the state public seruce commissions, and oversces strategic planning.
He delegates authority and responsibility for the operation and suppon of ANO through the Executive Vice President & Chief Operating Omccr; the Director Business Sersices; the Director, Nuclear Fuels; and the Director, Total Quality.
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1.4.2 Decutive Vice President & Chief Oncratine Omcer The Executive Vice President & Chief Operating Omccr has the responsibility to oversee all operations and engineering functions of Entergy Operations. He delegates authority and responsibility for the operation l
and suppon of ANO through the Vice President. Operations ANO. the Vice President. Engineering; the Vice President, Operations Support; and the Director, Materials, Purchasing and Contracts. It is the responsibility of the Executive Vice President & Chief Operating Omcer to assure that all safety-related l
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activities under his direction are performed following the guidelines of the Echelon Quality Assurance Program and the ANO QAMO.
1.4.2.1 Vice President, Operations Support The Vice President, Operations Support is responsible for the Echelon Support functions of Supplier QA, Licensing, Maintenance Support. Security, Emergency Planning, and Nuclear Support. Operations Sup; ort provides technical support to nuclear plant operations. In addition, the incumbent is responsible for the Ecnelon QA program and the Echelon audit program. The authority for the accomplishment of the above is delegated to the incumbent's staff.
1.4.2.1.1 The Manager, Quality reports to the Vice President, Operations Support and is responsible for the performance of supplier audits, sun'eys, assessments, product inspections, evaluations and surveillances for ANO. He also develops, maintains and controls the Qualified Supplier List (QSL). Additional duties include the development, maintenance and control of procedures that govern the supplier quality assurance activities; development and maintenance of the Echelon Quality Assurance Program and Echelon Administrative procedures; performance of audits / assessments of the sites' Quality Assurance programs,;
performance of audits of safety related activities performed at Echelon; and performance of audits /surveillances of the nuclear fuel procurement and fabrication process.
He delegates authority and responsibility for Supplier Quality Assurance activities at ANO to the Supenisor, Supplier Quality Assurance Audits and the Supenisor, Supplier Quality Assurance Programs.
The Supervisor Supplier QA Programs is the designated individual through which supplier related interface and communication with ANO is maintained.
Supplier Quality Assurance personnel are responsible for surveillance / audits at vendor / contractor shops when deemed necessary, based upon safety significance. complexity, method of acceptance and past history of the vendor, to estab'ish product quality and to assure that quality assurance and quality control programs function in accordance with ANO requirements. They also ensure review, approval, and control of vendor quality manuals and procedures and revisions thereto.
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1.4.2.1.2 l l The Manager, Plant Support and Assessments reports to the Vice President, Operations Support and is responsible for Nuclear Assurance, Nuclear Safety Oversight, and Planning and Professionalism. He establishes, directs or conducts programs, studies and analyses of the nuclear safety, engineering, and operations activities.
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1.4.2.2 Director, Nuclear Fuels The Director, Nuclear Fuels, is responsible for the procurement of nuclear fuel for ANO, the prosision of nuclear fuel cash fiow and cost projections for use in company business plan and fuel financing actisitics, the maintenance of the Official Entergy Operations Nuclear Operating Schedule, and the oversight of nuclear fuel accounting actisities.
1.4.2.3 Vice President, Engineering The Vice President, Engineering is responsible for prosiding nuclear engineering services for ANO, as requested. The incumbent is responsible for Design Engineering, fuel design and core design.
O 1.4.2.4 Director, Materials, Purchasing & Contracts The Director, Materials, Purchasing and Contracts is responsible for the procurement of nuterials, parts {j and components requested by Nuclear personnel otTsite and for supporting procurement actisities at ANO.
The incumbent is also responsible for the oversight and development of purchasing policies and procedures consistent across Entergy's nuclear sites and Echelon.
1.4.2.4.1 The Manager, Purchasing is responsible for the following actiities:
(1) Preparing ANO purchase orders bad upon receipt of reviewed and approved purchase requisitions.
(2) Performing the commercial interface functions between ANO and designated vendors.
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(3) Ensuring that quality documentation prepared by ANO personnel is included in appropriate q
procurement documents.
1.4.3 Vice President. Human Resources & Administration The Vice President,11uman Resources & Administration is responsible for the adannistration of functions associated with Corporate Senices and Human Resources. He delegates authority and responsibility for the accomplishment of the above activities through the Director, Human Resources, it is the responsibility of the Vice President, Human Resources & Administration to assure that the safety-related actisities under his direction are performed following the guidelines of the Echelon Quality Assurance Program and the ANO QAMO.
1.4.3.1 Director, Human Resources The Director, Human Resources is responsible for functions associated with programs dealing with employees compensation, benefits, employee and labor relations, affirmative action, recruitment, industrial safety, succession planning and human resource development. He delegates authority and responsibility for employee relations activities at ANO through the Manager, Human Resources-ANO.
1.5 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES AP&L and Entergy Operations arsjoint licensees under the facility operating license condition, each responsible for specific areas andjointly responsible for regulatory compliance and response. AP&L is licensed to possess the facility and Entergy Operations is licensed to possess, use and operate the facility.
Each supplier of equipment, material or senices and each maintenance or modification contractor is responsible for administering the applicable quality assurance / quality control functions as required by ANO. The Quality Organization is responsible for assuring by surveillance, inspection, audit or review of objective evidence that onsite functions are accomplished for systems, structures and senices that affect the safety and integrity of the plant.
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2.0 OUALITY ASSURANCE PROGRAM l l 2.1 SCOPE This QA Program is to assure that ANO is operated in a safe, reliable and efficient manner and in accordance with NRC regulations, applicable industrial standards and codes and applicable Company policies, rules, procedures and licensing documents. A matrix of quality procedures cross-referenced to each criterion of 10CFR50, Appendix B, is meluded in Table 2 to this manual.
2.2 GENERAL 2.2.1 This QA Program is applied to those safety related structures, systems and components and to those expendable and/or consumable items
- whose satisfactory performance is required to prevent accidents which may cause undue risk to the health and safety of the public or to mitigate the consequences of such accidents if they were to occur. These structures, systems and components are identified in the summary level and component level Q-lists for each nuclear unit. The Summary Level Q-Lists (SLQL) are located in the S ARs and information for the Component Level Q-lists (CLQL) is maintained current in the Station Information Management System (SIMS) for each nuclear unit. When structures, systems and components as a whole are on the SLQL or CLQL, portions not associated with a loss of safety function as determined by Enginec:ing are to be considered Non-Q. unless otherwise dispositioned by Engineering.
- Expendable and/or consumable items are to include. as a minimum: weld rods bori acid, and dicsci fuel.
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2.2.2 i i l
Expendable and/or consumable items where quality is necessary for the performance of Q-listed structures, systems and components are identified and contmited in accordance with Technical Specifications and/or procedures.
The following expendable and/or consumab!c items are to be controlled in the following manner to assure senice quality; (1) Diesel Fuel . Senice quality is ensured by applicable provisions / tests required by the Technical Specification for each operating nuclear unit.
(2) Welding Rod . Senice quality is ensured by procurement from an evaluated source, requiring material test results when specified by the ASME Code or applicabic design document, and controlling the rod on-site prior to use to prevent degradation.
1 (3) Boric Acid - Service quality is ensured by procurement from an evaluated source, requiring a batch analysis to ensure conformance with our specification requirements, and on-site control
,Q prior to use to prevent degradation.
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2.2.3 The quality program for transport packages containing radioactive materials is addressed in Appendix A of this manual and implemented through appropriate approved procedures. The elTectiveness of this quality program is verified thmugh scheduled audits conducted by the Quality Organization under the cognizance of the SRC.
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2.2.4 l I The quality program for fire protection is addressed in Appendix B of this manual and in the applicable section of the SAR for each operating nuclear unit and implemented through appropriate approved procedures.
The effectiveness of the fire protection program is verified through scheduled audits conducted by the Quality Organization under the cognizance of the SRC.
2.2.5 The SLQL (as part of the S AR) is under the control of the Director, Licensing. The Licensing Department ensures that reviews, approvals, and changes thereto are performed in accordance with approved procedures.
Changes to the SLQL require review / approval by the applicable Manager, Engineering; Supersisors, Quality Assurance; and Director, Licensing. ANO Document Control shall make distributions to the SAR in accordance with approved procedures 2.2.6 The CLQL is maintained on a computer data base (SIMS) and is controlled in accordance with approved procedures. Engineering is responsible for the technical adequacy of the CLQL and the administrttive 9 controls of the CLQL within SIMS. Evaluations, resiews and approvals to changes to the CLQL are performed in accordance with applicable procedures.
I 2.2.7 l
The Component Level F-list (CLFL) is maintained on the SIMS component data base by Engineering. j Components classified as *F" on4his list fall under the requirements of Appendix B of this manual. The !
I controls for this list are similar to the controls utilized for the Q-list.
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2.2.8 l
Components that are not Q-listed or F-listed and which are subject to ASME code requirements or similar design standards, regulatory requirements or licensing commitments or other ANO commitments are classified as 'S" in the SIMS component data base. The controls for this list are similar to controls for the Q-list. This list is also referred to as the Component Level S-list (CLSL).
2.3 RESPONSIBILITIES 2.3.1 ANO recognizes that quality assurance is an interdisciplinary function involving many organizational groups, encompasses many functions and activities and extends to various levels in all participating organizations (from the Entergy Operations President and Chief Executive Officer to all workers whose activities may influence quality). The QA Program designates responsibilities and dotics of specific individuals, which may be performed by their appointed designees.
2.3.2 O The QA Program assigns the responsibility for quality to the departments performing the work and inch. des as a basic requirement that individuals responsible for verification of conformance are qualified and do not perform or directly supervise the work. )
i Additionally, independent reviews, audits and surveillances are provided by individuals not reporting to the groups responsible for performing the work.
2.3.3 The QA Program also includes provisions that require suppliers, contractors subcontractors, consultants, etc.
to maintain and use quality assurance programs reviewed and approved by the Manager, Quality. Audits or surveillances by Supplier QA provide assurance of compliance with applicable procedures.
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2.3.4 l l On-site quality control of nuclear fuel is the responsibility of System Engineering and is implemented through the use of plant administrative procedures. These procedures include the receipt, inspection, handling, storage and accountability of Special Nuclear Material (SNM). Individuals who perform receipt inspections are qualified in accordance with paragraph 2.6.3 of this manual. The Director, Quality or designee maintains a listing of those individuals qualified to perform receipt inspection on nuclear fuel.
2.4 PROCEDURES 2.4.1 Activities which affect quality are defined in appropriate procedures, which are developed to cover adrninistration and control. The procedures stata the policies and instructions necessary to fulfill the intent of the QA Program. Procedures provide for standard forms, lists, and checkoffs used in documenting the inspections, certifications, reviews, surveillances and audits. Programs and procedures are modified or supplemented from time-to-time as the need for change arises during the life of the plant. Quality program policies, procedures and instructions are contained in the documents listed in Table 3.
l 2.4.2 Procedures assure that activities affecting quality are performed under suitably centrolled conditions.
Controlled conditions include the use of appropriate equipment, suitable emironmental conditions for performing the activity such as adequate cleanness and assurance that required prerequisites for the given activity have been satisfied. Administrative procedures also assure that the need for special controls, processes, tests and equipment to attain the required quality and the need for verification of quality by inspections, valuations or tests is taken into account.
2.5 PROGRAM REVISION AND CONTROL 2.5.1 Program revision and control shall be the responsibility of the Director, Quality.
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2.5.2 I I Proposed changes to this manual are to be submitted by the Director, Quality to affected management personnel for review and comment prior to approval and transmittal to the Nuclear Regulatory Commission.
After resolution of comments, changes are to be approved by a Supenisor, Quality Assurance; Director, Quality; and the Vice President, Operations ANO.
2.5.3 The Nuclear Regulatory Commission is to be notified of changes to this quality program annually for those changes that do not reduce the commitments in the program description previously accepted by the Nuclear Regulatory Conunission. Changes to the program description that reduce the commitments are to be submitted and approved by the Nuclear Regulatory Commission prior to implementation. The Director, Quality, or his designee, is to determine if changes ou or do not reduce the commitments of the QA Program.
2.6 PERSONNEL 2.6.I G Employees whose duties and responsibilities are related to the QA Program activities at or in support of ANO are to participtte in appropriate indoctrination and training programs to assure that suitable proficiency is achieved and maintained in the work they are performing. Such training shall include, as a minimum: plant security (badged personnel only), discussion of the overall company policies, procedures and instructions which establish the QA Program, an explanation of the quality organization and a discussion of those procedures which implement the QA Program related to the employee's specificjob-related activity.
2.6.2 The education, experience and responsibility requirements of individuals involved in the QA Program are documented injob descriptions which are approved and periodically reviewed by management. Requirements for ulucation, experience and proficiency levels are commensurate with the degree ofimportance of thejob assignment. Erperience and training requirements for plant staff personnel are to meet the requirements of ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted
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l in Table 1. Personnel whose qualifications do not meet those specified in ANSI N18.1-1971, and who are performing inspection, examination and testing activities during the operational phase of the plant, are to meet the requirements of ANSI N45.2.6-1978 unless otherwise noted in Table 1.
2.6.3 I
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Personnel performing inspection and examination activities are to be indoctrinated and trained to assure they are aware of the requirements which govern their activity, inspection and examination persomiel are to be qualified according to the applicable codes, standards, specifications, regulatory requirements and approved procedures. Personnel performing inspections on those activities occurring during the operational phase that are comparable in nature and extent te related activities occurring during initial plant design and construction are to meet the provisions of Regulatory Guide 1.58, Rev.1 (9/80) ani ' S 245.2.61978 in lieu of ANSI N18.1-1971.
2.6.4 Personnel involved with welding of materials, systems or components are to meet the appropriate qualification requirements of the ASME Boiler and Pressure Vessel Code, Sections III and XI, or for structural welds, the American Welding Society (AWS) Structural Steel Code DI.l. Personnel involved mth nondestructive q ,
examination of materials, components or systems are to meet the qualification requirements of the American Society Nondestructive Testing Recommended Practice SNT-TC-1 A or ASME Section 111 and XI for ASME Code materials, components or systems. Personnel are to be certified to perform these tasks in accordance with these codes and standards.
2.6.5 Personnel performing audits of the QA Program are to meet the experience, training and qualification / certification requirements of ANSI N45.2.23-1978 and Regulatory Guide 1.146 (8/80) unless otherwise noted in Table 1.
2.6.6 Personnel appointed to the SRC shall collectively have the experience and competence required by ANSI /ANS 3.1-1981 to review problems in the areas specified in paragraph 1.3.8.1 of this manual. Onsite management G = Enterg'f QA MANUAL OPERATIONS SECTION: 2.0 QUALITY ASSURANCE PROGRAM REV. 17 DATE 7/22/94 PAGE 2-7 Operatons Arkansas Nuclear One
personnel appointed ta the PSC shall have the technical experience and competence required by ANSI /ANS 3.1 1981 for Managers, Professional-Technical, or Engineering and Technical Support personnel.
2.6.7 Training records are to be maintained in accordance with approved procedures. For formal training programs, documentation is to include the objective, content of the program, attendees and date of attendance.
2.7 PROGRAM REVIEW 2.7.1 The Director, Quality through the Supenisors, Quality Assurance is responsible for a resiew of the QA Program on an annual basis to determine the efTectiveness and proper implementation of the QA Program.
2.7.2 Management resiews of the status and adequacy of the QA Program are accomplished through regular reports and presentations by the Quality Organization and through reviews of quality assurance reports. Quality Assurance reports supply data on the status of outstanding audit and corrective action items and may identify the status of other significant QA Program activities as requested by management.
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3.0 PESIGN CONTRQL 3.1 SCOPE Design activities are to be controlled to assure that proposed plant changes to the structures, systems, equipment and components conform to applicable regulatory requirements and that design bases are correctly translated into appropriate design documents. Design control activities are to be in accordance with the requirements of Regulatory Guide 1.64, Rev. 2 (606), unless otherwise noted in Table 1, 3.2 GENERAL 3.2.1 Engineering is responsible for the continued upgrading and modification of plant design. Design documents (drawings, specifications, procedures and instructions) originating or released through these departments are to be based upon the regulatory requirements, licensing-based documents, functional requirements, quality standards and design bases in accorda ce with NRC licensing requirements. Design activities may include calculations, analyses, materials selection, equipment arrangement and layouts, accessibility for insenice e inspection, and the specification of test and inspection criteria. Those design actisities performed by indisiduals within Engineering are controlled by the use of Plant Modification Process (PMP) control procedures and by applicable administrative and departmental procedures. These procedures include controls to assure that verified computer codes are certified for use and that their use is specified.
3.2.2 Design standards and requirements are to be at least equivalent to those employed during the construction of the plant and are to be consistent with the Technical Specifications and License requirements.
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3.3 DESIGN INTERFACE G' Design control activities include measures for the identification and control of design interfaces between the various engineering sections within Engineering, between Engineering and other Nuclear Organizations, and between Engineering and firms / suppliers outside the Nuclear Organization. These measures include the development of procedures among the participating organizations for the review, approval, release, distribution and revision of documents invohing design interface. Coordination of the interface control is the responsibility of the originating organization's management unless otherwise specified in a procedure applicable to the design activity. Design information between interfacing organizations is to be documented and retained for permanent records 3.4 DESIGN VERIFICATION 3.4.1 To assure the design is adequate and the above requirements and procedures are implemented, Engineering is to verify the adequacy of the design through the performance of design reviews, the use of alternate or simpidied calculation methods, or the performance of a qualN' ion testing program. The extent and depth of design verification performed by the responsible engineering section is determined by an assign:d engineering resiewer G based upon the importance and complexity of the design, the degree of standardization and its similarity with proven designs. In all cases, the design verification is to be complete prior to relying upon the component, system or structure to perform its function.
3.4.2 The verification process is to be performed by competent individuals or groups other than those who performed or supenised the design but w ho may be from the same engineering section. This verification, however, may be performed by the originator's supervisor in accordance with departmental procedures if he is the only individual in the organization competent to perform the verification and provided the need is individually documented and approved in advance by the responsible Manager or Superintendent. The frequency and effectiveness of the use of Supenisors as design verifiers is to be verified by Quality personnel through scheduled audits to guard against abuse Whe.e changes to previously verified designs have been made, design verifications are required for the change. including evaluation of the effects of the changes on the overall design.
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3.4.3 .
l When a test program is used to verify the adequacy of a design, it is to include suitable qualification testing of a prototype or initial production unit under the most adverse design conditions and carried out in accordance with documented procedures and/or instructions. Testing is to be performed as early as possible prior to installation of plant equipment, or prior to the point when the irrtallation would become irreversible. l I
3.4.4 Design work performed by organizations outsidn of the Nuclear Orgamzation is to receive a documented resiew and approval by engineering personnel in accordance with PMP control procedures and appicable departmental procedures.
i 3.5 DESIGN CHANGE e
3.5.1 !
1 Methods for the preparation, review, approval and implementation of design changes, including field changes, p are documented in PMP control procedures and departmental procedures for Engineering. Design changes are V subject to miew and vedfication by the same engineering section which reviewed and verified the original design unless otherwise specified in departmental procedures for design control. If changes to an approved ;
design are required to meet plant requirements or conditions, Field Change Requests (FCR) may be issued or otherwise documented by a cognizant engineer and transmitted with the changes for review and approval in accordance with PMP control procedures and applicable departmental procedures.
3.5.2 Changes from specified design inputs, such as design bases, regulatory requiremens, codes and standards ,
(including quality standards) are to be identified, approved, documentth=4 controlled through PMP control procedures and applicable departmental procedures.
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F 3.5.3 During preparation of a design change, the responsible engineering section is to perform a resiew per 10CFR50.59 to verify compliance with the SAR and to determine if NRC approval of the design change is required. The documented 50.59 review ss to be reviewed and approved by the PSC. In addition, any 10CFR50.59 cvaluations shall also be reviewed and approved by the SRC.
i 3.5.4 Design changes are also to be submitted to the Quality Organization prior to plant implementation to verify the use of appropriate quality codes, standards and inspection requirements in the design documents.
3.6 CORRECTIVE ACTIONS When design changes are made as a result of design deficiencies or errors, corrective actions (for significant conditions) are to be taken in accordance with Section 16.0 to determine the root cause and to institute ,
appropriate changes in the design process and/or QA Program to prevent recurrence. When a significant design !
change is necessary because of an incorrect design, the design process and verification procedures shall be reviewed and modified as necessary.
Cp i 3.7 DESIGN RECORDS ,
The Superintendent Administrative Services is responsible for maintaining permanent records of the design documents for the construction and testing phases, and for maintaining records of the upgrading or modification j of these documents as described in this section. ,
t The controls for maintaining these records are established by specific procedures described in Section 17.0 of this manual. These records provide the historic reference necessary for the safe and reliable operation of ANO.
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4.0 PROCUREMENT DOCUMEtU CONTROL l I 4.1 SCOPE Requirements for the procurement ofitems and services are to be clearly stated and do,:umented to assure that applicable regulatory requirements, design bases, technical requirements and quality assurance criteria are included or referenced in the procurement documents. Procurement document control actisities are to be in accordance with approved procedures and are to meet the provisions set forth in NRC Regulatory Guide 1.123 Rev.1 (7n7), unless otherwise noted in Table 1.
4.2 PROCUREMENT DOCUMENTS 4.2.1 The procurement of materials, parts and components are generated through the preparation of a Purchase Requisition (PR) and subsequent issuance of a Purchase Order (PO), or when additional senices from the Vendor are required, through the preparation and issuance of a Contract. The procurement of senices is initiated through the preparation and issuance of a Contract. The preparation, review, approval and issuance of these procurement documents are to be in accordance with applicable procurement and contract administration procedures. Purchase Orders for items arc issued through the Procurement section. Contracts for items and/or senices are issued through the Contracts Administration Section.
4.2.2 Procurement documents are to include or reference specific design specifications for the items or services to be procured w hich define specific codes, standards, tests. inspections. environmental qualifications, and records to be applied and/or furnished. For standard "off-the-shcif' items, reference to the item's catalog number and identification number may be included on the procurement document in lieu of a design specification. New or revised specifications for replacement items are to be evaluated by the responsible engineering organization against the ontmal specification for the item. The evaluation is to be in accordance with applicable engineering procedures and will result in the establishment of new baseline and technical quality requirements, which are to be used for subsequent procurements.
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l 4.2.3 l I Procurement documents are also to include the identification of quality assurance program requirements applicable to the items or senices procured. Procurement documents also establish requirements for source audits and inspections, extension of the procurement requirements to lower-tier suppliers or subcontractors, and preparation and delivery of documentation. These requirements may either be in the form of documents attached to the PO or Contract or by incorporating them in the specific design specifications. Quality programs are to be specified by invoking the appropriate sections of 10CFR50, Appendix B, the appropriate ANSI standards and/or the appropriate ANO-generated quality requirements for items or senices. The appropriate sections of the ASME Boiler and Pressure Vessel Code are to be invoked for items originally designed to meet ASME requirements.
4.3 REVIEW OF PROCUREMENT DOCUMENTS The appropriate sections within the Quality organization, as identified in the applicable procedures for procurement and contract administration activities, are to review safety-related procurement documents to assure that the required quality requirements (including source surveillance and/or inspection) are imposed on suppliers / contractors.
l 4.4 CHANGES TO PROCUREMENT DOCUMENTS Changes to procurement documents are to have the same degree of control and review as imposed on the original documents. Changes such as inconsequential editorial corrections or changes to commercial terms and conditions may be made by Procurement or Contract Administration personnel, as appropriate, after concurrence from the originator or organization which originated the document, n
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5.0 INSTRUCTION
S. PROCEDURE
S AND DRAWINGS l I 5.1 SCOPE 5.1.1 Instructions, procedures and drawings are provided for the control of those activities which affect quality and safety at ANO. Activities covered by written procedures include, as a minimum: administrative, general plant operations, start-up, shutdown, power operation and load changing, process monitoring, fuct handling, modification, maintenance and repair, radiation control, calibration and test, chemical-radiochemical control, plant emergencies, test and inspection, quality assurance, quality control, quality engineering and o!T-site activities in support of ANO. The format, content and philosophy ofinstructions and procedures are to comply with the guidelines in ANSI N18.7-1976 and Regulatory Guide 1.33 Rev. 2 (2n8) unless otherwise noted in Table 1.
5.1.2 Instructions and procedures are also provided for the cont:31 of activities relating to the repair, replacement or e modifications to ASME Code, Section 111, Class 1,2 or 3 co nponents required to be operable to mitigate the consequences of a postulated accident.
5.2 GENERAL 5.2.1 Instructions, procedures and drawings are to include appropriate quantitative criteria such as dimensions, tolerances end operating limits and/or qualitative criteria such as comparative workmanship samples to determine that important activities have been satisfactonly accomplished. Each procedure is to be sufficiently detailed so that a qualified individual may perform the required function (s) without direct supervision and is to include measures to document the activity being performed.
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5.2.2 l I To assure the accomplishment of activities in accordance with approved instructions, procedures and drawings, each supervisor is responsible for quality compliance of his personnel. Verification that activities are accomplished in accordance with approved instructions, procedures and drawings is obtained through various levels of surveillance, inspection and audit by the Quality Organization.
5.3 REVIEW OF INSTRUC.TIONS, PROCEDURES AND DRAWINGS 5.3.1 Instructions, procedures and drawings are prepared, resiewed and approved in accordance with applicable administrative procedures.
5.3.2 Procedures required by Technical Specifications 6.8.1 and 6.5.1 (for Unit I and Unit 2 respectively) which affect nuclear safety, as determined by the General Manager, Plant Operations, and changes thereto, shall be resiewed as follows:
- a. Each procedure or change shall be independently resiewed by a qualified individual knowledgeable in the area afTected other than the individual who prepared the procedure or procedure change. This resiew shall include a determination of whether or not additional cross-disciplinary resiews are necessary. If deemed necessary, the reviews shall be performed by the resiew personnel of the appropriate discipline (s).
- b. Individuals performing these reviews shall meet the applicable qualifications of ANSI /ANS 3.1-1981, Section 4.0, excluding sabsections 4.3.2 and 4.5, and by approved to perform these resiews in a given area by the General Manager, Plant Operations.
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- c. Those procedures and programs specified by Technical Specifications 6.5.1.6 and 6.5.1.7 (for i
Unit I and Unit 2 respectively), and changes in intent thereto, shall be reviewed by the PSC j j ;
and approved by the General Manager, Plant Operations, or the applicable Plant Manager prior j to implementation.
- d. Those procedures and programs specified by Technical Specification 6.8.1, and changes in intent thereto, with the exception of those specified in 6.5.1.6 and 6.5.1.7 (for Unit I and Unit 2 respectively), shall be ap, mved by the appropriate Department Head as specified in station administrative procedures.
- c. Review of the procedure or procedure change will include a determination of whether or not an unreviewed safety question is involved. This determination will be based on the review of a written safety evaluation prepared by a qualified individual, or documentation that a safety evaluation is not required. PSC review, SRC review, and NRC approval of items involving unresiewed safety questions shall be obtained prior to station approval for implementation.
- f. Overall Administrative Procedun:.:(OP-1000.XXX and OP-6000.XXX Series) and Engineering Administrative Procedures (OP-5000.XXX Series) are also reviewed by the Quality Organization to verify compliance to the QA program.
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- g. Written records of resiews shall be prepared and maintained in accordance with Technical Specifications 6.9 and 6.10 (for Unit I and Unit 2 respectively) and Section 17.0 of this manual.
5.3.3 Procedures and inrtructions are to be reviewed upon identification of new or revised rource material potentially alTecting the content of procedures. or prior to use if the procedure / instruction is not used routinely to determine if changes are necessary or desirable. Audits by the Quality Assurance Department are performed on at least a biennial basis to verify the effectiveness of controls used to maintain procedures current. Applicable procedures (i.e.. those that relate to the incident cause) are to be reviewed following an unusual incider.t such as an accident, unexpected transient, significant operator error or equipment malfunction. Applicable procedures are also to be reviewed following any modification to a plant system.
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5.3.4 l I Drawings related to plant changes and modifications are controlled as described in Section 3.0 and 6.0 of this manual.
5.4 CHANGES TO PROCEDURES 5.4.1 Changes or revisions to approved instructions, procedures and drawings are to be reviewed and approved by the same organizations or groups that performed the original resiew, unless otherwise noted in specific ANO procedures, and controlled in the same manner as the original.
5.4.2 Temporary changes to approved procedures may be made in accordance with either the applicable Technical Specifications or approved procedures for those procedures w hich are not Technical Specifications related. In the event of an emergency not covered by an approved procedure, Operations personnel may take action, without obtaining approvals, to minimize personnel injury and damage to the facility and to protect health and safety.
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6.0 DOCUMENT CONTROL 6.1 SCOPE The various quality program documents identified in Table 3 provide means to control the review, approval, issuance, use and retrievability of documents, such as cale dations, computer codes, analyses QA Manual Operations, SAR, instructions, procedures, specifications, manuals and drawings, including changes thereto, which prescribe activities affecting quality.
6.2 RESPONSIBILITIES 6.2.1 Each organization originating documents which prescribe activities affecting quality is responsible for the establishment of document control procedures which identify individuals or groups responsible for preparation. review, approval and maintenance of the document and for the issuance of these procedures to the affected moniduals or groups.
6.2.2 G
Resiew of these documents for concurrence with quality-related requirements is to be performed by the Quality Organization and/or by the appropriate resiewer as described in approved procedures.
6.2.3 The Superintendent, Administrative Senices is responsible for the control and issuance of procedures and revisions thereto to assure distribution in accordance with approved procedures. The Superintendent, Administrative Senices is also responsible for the storage and control of approved historical plant documents and the storage of historical drawing records. The Superintendent, Administrative Senices is responsible for the control and issuance of drawings and revisions thereto to ensure that they reflect the as-built conditions of the plant.
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I 6.3 IDENTIFICATION I l Documents are to be identified by a title descriptive of their purpose or applicability and marked or stamped as to their current status (Draft, For Information Only, Void, etc.) per departmental procedures. Revision status of a document is to be identified in document registers, distribution lists and/or within the resision ]
j record page/ block of the document.
6.4 DISTRIBUTION Distribution lists and/or document registers are to be maintained by the organization responsible for issuance of the document. These lists are to identify the revision status of the document and are to be reviewed and updated periodically by the responsible organization to maintain them in a current status.
These lists are available to individuals using the document to assure they are in receipt of the current document. These measures are to preclude the possibility of using outdated or inappropriate documents.
4 6.5 CHANGES 6.5.I Changes to controlled documents are to be reviewed and approved by the same organizations which performed the original review and approval unless otherwise specified in departmental procedures applicable to the affected actisity.
6.5.2 Obsolete or superceded documents are to be destroyed or marked to prevent inadvenent use in accordance with applicable document control procedures.
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l 6.6 STORAGE e Documents which affect quality are to be stored and maintained at the plant in permanent storage facilities and controlled as described in Section 17.0 of this manual.
6.7 VERIFICATION Quality personnel through their various levels of quality review, surveillance, audit, and inspection actisities assure proper documents are being used and made available to those individuals performing the work.
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7.0 CONTROL OF PURCHASED MATERI AL. EOUIPMEVr AND SERVICES l I 7.1 SCOPE The purchase of material, equipment and senices is controlled to assure that, whether purchased directly or through vendors, the material, equipment and senices which affect quality conform to the procurement documents. Procurement control includes provisions for source evaluation and selection, objective esidence of quality furnished by the contractor, surveillance and audit at the source, examination of products upon delivery and testing of received material for conformance to procurement criteria. The depth and necessity of procurement controls depend upon the uniqueness and complexity of the item /senice, procurement frequency with the same supplier and past supplier performance for the specific items or senices covered by the procurement document. The control of purchased material, equipment and senices is to be in accordance with the requirements of Regulatory Guide 1.38 Rev. 2 (5n7) and 1.123. Rev.1 (7/77) unless otherwise noted in Table 1.
7.2 SOURCE EVALUATION AND SELECTION 7.2.1 l
A Qualified Suppliers List (QSL) is to be maintained and controlled under the direction of the Manager.
Quality. The QSL identifies those vendors / contractors that have been evaluated and approved by Supplier QA to furnish material, equipment er senices, and identifies any restrictions imposed on the vendor / contractor as a result of their evaluation.
7.2.2 Vendors / Contractors are evaluated and placed on the QSL by any of the following methods, as approved by the Manager, Quality:
(1) Source survey by Supplier QA personnel to verify compliance to applicable 10CFRSO, Appendix B requirements or to applicable ASME Section til quality assurance program requirements.
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(2) Evaluation and acceptance of source surveys performed by others (e.g., NUPIC, other utilities, NSSS suppliers, and prime contractors) indicating a program rnecting the appropriate requirements of 10CFR50, Appendix B.
(3) A review of the vendor's/ contractor's current quality records supported by evidence of documented qualitative and quantitative information which can be objectively evaluated. This includes resiew and approval of the vendor's/ contractor's quality assurance program, manual and procedures, when available (4) Evaluation of the vendor's/ contractor's history of providing a product /senice which performs satisfactorily in actual use. Evaluation information includes: experience of users ofidentical or similar products /senices of the prospective vendor / contractor; and/or procurement records that have been accumulated in connection with previous procurement activities and operating experiences.
(5) In addition to the above, for ASME Code Suppliers, verification that a vendor is a holder of an ASME Certificate of Authorization issued as a result of an ASME sun'ey.
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7.2.3 Vendors / contractors hsted on the QSL are to be selected for procurement of material, equipment or senices except for items designated " commercial-grade" per approved procedures and as noted in paragraph 7.2.4. 1 Standard catalog items may be procured from a vendor / contractor not listed on the QSL provided the ]
manufacturer of the item is on the QSL and all requested documentation originates from the manufacturer.
The QSL is periodically resiewed and updated per applicable procedures to ensure it is maintained current.
The list of qualified vendors / contractors is available to personnel involved in the procurement process.
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7.2.4 l Services by contractors which provide only technical guidance / support or which require work activities to be performed under the scope of the QA Program may be furnished by contractors not listed on the QSL The contractor's work activities and personnel are to be controlled in accordance with approved procedures to assure that the contractor conforms to the procurement documents.
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7.3 SOURCE SURVEILLANCE AND AUDIT l
7.3.1 The effectiveness of a vendor's/centractor's quality assurance program is assessed by Supplier QA personnel at intervals consistent with the importance, complexity, method of receipt and quantity of the products or senices. This assessment may be through source surveillance, source audit, receipt inspection, independent testing or review of source documentation files.
7.3.2 The need for source surveillance / verification is determined by Supplier QA. Source surveillanceA crification may also be requested by the originator of the PR/ Contract, or the Quality Organization during their resiew of the procurement document (reference section 4.3). Source surveillance is to be performed by Supplier QA personnel or their appointed representative in accordance with surveillance plans approved by the Manager, Quality and the results documented per quality assurance procedures. Reports documenting inspections performed and discrepancies observed are prepared by the person performing the surveillance to document l 1
compliance to the procurement documents and for future use as historical quality performance data. l i
l O 7.3.3 Audits of the vendor's/ contractor's quality assurance programs are periodically performed under the direction of the Manager, Quality to verify implementation of a satisfactory quality program on the items or senices being procured. Audits performed by others (e.g., NUPIC, other utilities, or prime contractors), as evaluated and approved by the Manager, QualityJmay be used as an alternative to audits by Supplier QA personnel to verify the vendor / contractor is implementing a satisfactory quality program. Audits are to be conducted in accordance with Section 18.0 of this manual.
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l 7.4 RECEIFT INSPECTION l I 7.4.1 l
Materials and equipment, including ASME Code materials and equipment, are subject to inspection upon !
receipt at ANO. The degree ofinspection is specified in the procurement documents. Receipt inspection is performed in accordance with approved procedures.
7.4.2 i
Receipt inspection activities are to be documented and include, as a miniu r... examination of material or equipment for shipping damage, proper identification and quantity; and the resiew of vendor documentation to verify compliance with the procurement domment. If a source surveillance has been performed on material and equipment received at ANO. requiremer.:s identified in procurement documents that have been addressed in the Source Surveillance report do not have to be re-verified during receipt.
I 7.4.3 Vendors are to furnish documentation as required by the procurement documents for objective evidence that the material or equipment conforms to the procurement requirements. Resiew and acceptance of this documentation is to be performed prior to installation or use of such material or equipment and the results documented unless otherwise specified in approved procedures. Certificates of Conformance may be required ,
by procurement documents which identify the requirements met by the vendor. The validity of the vendor's certification program is to be periodically verified through scheduled source surveillanec/ verification and audit activities or through independent testing of the item by ANO. i
. l 7.4.4 Accepted material and equipment is released identified as to its inspection status and forwarded to a controlled storage arca or released for installation per applicable approved procedurcs.
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7.4.5 l I Acceptance of services furnished by a contractor is to be identified in the procurement documents.
Depending upon the service performed, acceptance may be by technical verification of the data produced, surveillance and/or audit of the activity lor review of objective evidence for conformance to the procurement document requirements. The acceptance method is to be performed by qualified individuals knowledgeable in the service provided.
7.4.6 Independent testing of selected material is to be performed in accordiace with approved procedures / instructions to verify conformance to procurement critena and the validity of the vendor's certification documents.
7.5 NONCONFORMING ITEMS 7.5.I Nonconformances identified by the vendor / contractor which adversely alTect reliability, performance or
'd interchangeability of the item and dispositioned repair or usc-as-is are to be submitted to and accepted by ANO prior to closure of the nonconformance by the vendor / contractor. These nonconformances are to be documented and become part of the procurement documentation furnished by the vendor / contractor for the material, equipment or services procured.
7.5.2 Matenal and equipment found to be deficient or missing procurement documentation during receiving inspection or found to be deficient as a result ofindependent testing are to be clearly identified, segregated from acceptable items and dispositioned per approved procedures and as described in Section 15.0 of this manual.
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l Spare parts are to be purchased to the original design requirements or to those specified by a properly reviewed and approved revision to the design requirements. The applicab!c quality assurance requirements and documentation requirements for spare parts are to be included in the procurement documents.
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Material and equipment are to be handled and stored as described in approved procedures and Section D.0 of this manual.
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8.0 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS l I 8.1 SCOPE 8.1.1 Measures for the identification and control of materials (including consumables), parts and components, including partially fabricated subassemblies, are to be established within approved procedures. These procedures are to relate an item of production (batch, component, part, etc.) at any stage, from initial receipt through fabrication, installation, repair or modification to an applicable drawing, specification or other pertinent technical documents. These measures are to assure that only correct and accepted items are used and installed.
8.1.2 Methods for the traceability of materials, parts and components to specific inspection and test records, when required by codes, standards, specifications or procurement documents, are to be established within approved procedures and maintained throughout the life or consumption of the item.
G 8.2 IDENTIFICATION 8.2.1 Materials, parts and components are to be identified by the vendor in accordance with the applicable design standards, codes and/or instructions specified in the procurement documents.
8.2.2 Materials, parts and components are to be identified and/or tagged at the plant in accordance with applicable approved procedures. These tags identify the status of and provide traceability to the item throughout storage and release for installation.
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8.2.3 l I Identincation of materials, parts and components is accomplished by either marking or tagging on the item or through records traceable to the item.
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l Physical identification is to be used to the maximum extent possible. Where physical identification is either impractical or insufficient, physical separation, procedural controls or other appropriate means are to be employed in accordance with approved procedures.
8.2.3.2 When identification markings are employed the markings are to be clear, unambiguous and indelible and applied in such a manner as not to affect the integrity or function of the item. Markings are also to be transferred to each piece of material (plate, barstock, tubing. etc.) when subdivided. Large quantities of small items may be identified by applying markings or tags to their shipping packages, boxes or other suitable coriainers.
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Identification markings are to be recorded on records or as-built documents if current markings are to be hidden or subject to obliteration by surface treatment or coatings during fabrication, installation, repair or modifications.
8.3 CONTROL I
Plant organizations receiving materials, parts and components are to verify that they are properly identified while under their control. Quahty audit surveillance and inspection activities ensure compliance to requirements and also ensure that materials parts. and components are being identified in accordance with this manual.
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8.4 DEFECTIVE OR INCORRECT ITEMS e 8.4.1 Defective or incorrect materials, parts and components identified by plant personnel or support groups are to be handled in accordance with Section 15.0 of this manual and approved procedures for nonconformances and corrective action. Defective or incorrect items are to be tagged with a " hold tag" affixed to the item or otherwise identified per approved procedures.
8.4.2.
Defective or incorrect items are to be stored in segregated areas except for those items installed or which, due to their size, weight configuration, etc., are impractical or impossible to store in the designated controlled storage area.
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9.0 CONTROL OF SPECIAL PROCESSES l I l 9.1 SCOPE Special processes are to be controlled through the use of qualified personnel and approved procedures which meet the requirements of applicable codes, specifications, standards and other criteria stipulated in ANO licensing documents.
9.2 GENERAL 9.2.1 Special processes are those activities which require interim in-process controls in addition to final inspection to ensure quality and include such activities as welding, nondestructive examination, heat treating, coating, plating and chemical cleaning.
9.2.2 Technically qualified personnel are to establish the procedural and qualification requirements for those special processes not covered by existing codes or standards or where the QA Program requirements exceed the requirements of established codes or standards.
9.2.3 The requirements for welding and nondestructive examination are to comply with the applicable portions of the ASME Boiler and Pressure Vessel Code or for structural welds, the AWS Structural Steel Code DI.1, and the American Society of Nondestructive Testing Recommended Practices (SNT-TC-l A and supplements).
The requirements for cleaning and flushing of fluid systems are to comply with the requirements of NRC Regulatory Guide 1.37. dated 3/16/73 unless otherwise noted in Table 1.
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9.3 QUALIFICATIOPP"^~
- l I 9.3.1 Special process procedures for welding and nondestructive examinations are to be qualified prior to use to ensure compliance with applicable codes, standards or specifications. These qualifications are to be documented and also made available for resiew to the Code Inspector for activities on ASME items.
9.3.2 Personnel responsible for the performance and verification of special processes are to be qualified and/or certified according to applicable codes, standards, specifications, regulatory guides and approved procedures.
These qualifications and certifications are to be documented and made available for review to the Code Inspector for activities on ASME items. Personnel qualification and/or certification records for a special process are to be regularly reviewed by the supersisor responsible for that special process to ensure that the appropriate documents are up-to-date and personnel are periodically re-qualihed and/or re-certified in accordance with approved procedures.
9.4 RECORDS The results of special processes are to be documented, resiewed, approved and stored in accordance with appropriate approved procedures and as addressed in other sections of this manual.
9.5 VERIFICATION Performance of special processes in accordance with applicable codes. standards, specifications and approved procedures is verified by Quality personnel through performance of their audit, review, surveillance and inspection activities.
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10.0 INSPECTION l I 10.1 SCOPE Inspections relating to normal operating activities and inspections relating to operating activities comparable in nature and extent to those occurring during initial plant design and construction are to be controlled to assure that inspections are performed in accordance with applicable design documents, codes, standards, specifications and procedures. Inspection activities are to be in accordance with Regulatory Guide 1.33, Rev. 2 (2n8), unless otherwise noted in Table 1.
10.2 GENERAL 10.2.1 Inspection activities relating to normal operating activities (Operational Inspections) include:
(1) Work functions associated with normal operation of the plant (2) Routine maintenance (3) Technical sersices routinely assigned to the on-site operating organization (4) Non-routine maintenance activities and minor modifications made by the on-site operating organization that are not comparable in nature and extent to related activities occurring during initial plant design and construction 10.2.2 Inspection activities relating to operating activities comparable in nature and extent to related activities occurring during design and construction (Construction Inspections) include:
- 1) Non-routine maintenance, except as noted in paragraph 10.2.1
- 2) Modifications, except as noted in paragraph 10.2.1 The following Regulatory Guides are to be applied, as applicable, in determining the basis for required construction inspections: R.G.1.30. Rev. 0 (802); R.G.1.37. (3n3); R.G.1.38, Rev. 2 ($n7); R.G.1.39, Rev. 2 (907); R.G. l.94, Rev.1 (4n6), and R.G.1.116. Rev. 0-R (606).
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10.2.3 Personnel performing inspection activities to verify quality are to be qualified as stated in Section 2.0 of this manual. When inspection techniques require specialized qualifications or skills, personnel performing the inspection are to meet applicable licensing requirements, codes and standards appropriate to the discipline involved.
10.3 CONTROL OFINSPECTIONS 10.3.1 Inspections are to be performed in ae.ordance with approved written instructions or procedures, which set forth the requirements and acceptance inmits and specify the inspection responsibilities. Ifinspections require detailed written procedures to perform the task, the procedures are to contain, as a minimum, the following:
(1) Qualitative and/or quantitative acceptance criteria (2) Prerequisites for performing t'he inspection and any limiting conditions t
O (3) Identification of any special equipment and tools required to perform the inspection (when accuracy requirements for inspections exceed the accuracy of normally available process or measuring and test equipment, such additional accuracy requirements are to be specified within those inspection procedures)
(4) A step-by-step description of the method ofinspection, examination, measurement or test to be performed (5) Identification of those inspection results to be documented. Inspection forms or checklists are to be used as an aid in documenting the inspection activity to assure quality requirements have been met REV. 17 O QA MANUAL OPERATIONS DATE 07/22/94 b -:-=. Entergy SECTION: 10.0 INSPECTION PAGE 10-2 Operations Arkansas Nuclear One l
10.3.2 I
Operational inspections are to be performed by qualified individuals other than those who performed or directly supervised the activity being inspected. Construction inspections are to be performed by qualified individuals other than those who performed or directly supenised the activity being inspected and do not report directly to the immediate supervisors who are responsible for the activity being inspected.
10.3.2.1 Operational inspections may be performed by second-line supenisory personnel or by other qualified personnel not assigned first line supervisory responsibility for conduct of the work.
10.3.2.2 Construction inspections are to be conducted in a manner similar to that associated with construction phase activities in accordance with applicable approved procedures.
10.3.2.3 Ifindividuals performing inspections are not part of the Quality Organization, the inspection procedures, personnel qualification criteria, and independence from undue pressure such as cost and schedule are to be reviewed and found acceptable by the Director. Quality or designee prior to initiation of the actisity.
10.3.3 If an inspection determined to be required is impossible or disadvantageous, indirect control by monitoring processing methods, equipment and personnel is to be provided to verify conformance with applicable documented instructions, procedures and drawings. Both inspection and process monitoring are to be provided when control is inadequate without both, i
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l 10.4 INSPECTION POINTS l I 10.4.1 l Inspection hold points are established within non-routine maintenance procedures and Plant Modification Packages (PMPs) by Engineering and reviewed by Quality Control personnel for concurrexe and possible assignment of additional inspection hold points to funher assure conformance with applicable instructions, procedures, drawings and related documents or to meet appropriate code and regulatory requirements.
Inspection hold points for work functions associated with activities other than non-routine maintenance and PMPs are established by the originating department, Quality personnel or other responsible individuals and reviewed by Quality Control personnel for concurrence and possible assignment of additional inspection hold points.
Work is not to proceed past a designated inspection hold point until signed by a qualified inspector or waived, in writing, by the Director, Quality or designee. ;
10.4.2 Inspection hold points are inserted in procedures based upon safety significance, complexity of the item or activity, degree of standardization of the i'em or activity, past performance of the item or activity and the ability to verify quality by job-site testing.
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Inspection responsibilities, requirements, information and acceptance criteria for the work activity are to be identified in appropriate, approved documents (e.g., procedures, checklists).
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10.4.4 For work involving the modification, repair, replacement or inservice inspection of ASME Code materials, parts and components, the work packages are to be made available to the Code inspector prior to commencing ,
work for his resiew and assignment ofinspection hold points. The department responsible for the work activity 1
is responsible for notifying the Code Inspector when the hold point is reached. Work is not to proceed past a Code Inspector's inspection hold point until signed or waived by the Code Inspector.
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1 10.5 DOCUMENTATION l I 10.5.1 Inspections and process monitoring activities are to be performed and the results documented in accordance 1 with approved procedures or instructions. Records are to: provide objective evidence that the inspections and monitoring activities w re performed in compliance with procedures, instructions or drawings to verify design requirements; show compliance with acceptance criteria or identify the cause of rejected items; and identify the ,
appropriate inspection personnel approving the results.
10.5.2 Records are to be maintained in accordance with approved procedures and Section 17.0 of this manual.
Inspection results on ASME Code items are available to the Code inspector for his resiew.
10.5.3 The results ofinspection and monitoring activities are periodically evaluated per approved procedures and the results documented to determine whether the individual inspection programs demonstrate that the plant can be operated safely and as designed.
10 6 NONCONFORMANCES Nonconforming items found as a result of inspection and monitoring activities are identified, segregated and dispositioned in accordance with approved written procedures and Section 15.0 of this manual. Rework, repair or replacement performed after completion of inspections requires re-inspection to the extent necessary to determine acceptability to established criteria.
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I1.0 TEST CONTROL e 11.1 SCOPE i
A test program is to be established to assure that testing required to demonstrate that an item will perform satisfactorily in senice is identified, documented and performed in accordance with written test procedures.
These procedures are to incorporate or reference the requirements and acceptance criteria contained in applicable codes, standards and specifications and in the licensing documents. These activities include testing during the ,
operational phases of the plant and those tests required as a result of modifications, repairs or maintena' ice.
These activities are also to comply with the applicable provisions of Regulatory Guide 1.33, Rev. 2, unless otherwise noted in Table 1, and with the applicable sections of the ASME Boiler and Pressure Vessel Code for ASME-designated items.
11.2 PROCEDURES 11.2.1 Written procedures / instructions are to be prepared to describe the requirements for conduct of the testing activities. These procedures / instructions are to contain or reference the information required in Section 5.0 of V this manual and in the applicable Regulatory Guides pertaining to quality assurance requirements for testing activities.
I1.2.2 Test procedures / instructions and revisions thereto are to be subject to the same review and approval process as outlined in Section 5.0 of this manual.
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11.3 TEST CONTROLS l
11.3.1 ;
1 Tests relating to plant start-up following a unit shutdown or fuel loading are to be conducted per written procedures / instructions in order to evaluate plant performance as the start-up progresses. Initial start-up test programs are to be planned to permit safe fuel loading and start-up, to increase power in safe increments and to I
perform major testing at specified power plateaus.
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Surveillance tests during the operational phase of the plant are to be conducted per written ,
procedures / instructions to assure that failures or substandard performances do not remain undetected and that the required operability is maintained to ensure they will continue to operate. keeping parameters within normal bounds, or will act to put the plant in a safe condition if they exceed normal bounds. ;
i1.3.2.1 p Mandatory in-plant surveillance tests and inspections required to assure operation within the limiting conditions of operation are ider.tified in the SAR and Technical Specifications applicable to each unit. To ensure that the required tests are performed as scheduled within the specified time interval, surveillance procedures are l established and maintained for mandatory surveillances identified in the SAR and Technical Specifications.
These procedures are to specify the component or system, type of surveillance activity, frequency of activity and the cognizant individual responsible for completion of the surveillance activity.
11.3.2.2 Insenice inspections required to meet the requirements of ASME Boiler and Pressurc Vessel Code,Section XI, are to be identified in the Inservice Inspection (ISI) Programs applicable to each unit. Engineering Programs is to establish and maintain an ISI plan for each unit. The plan specifies the inspection items inspection procedures, inspection intervals and types ofinspections. Engineering Programs is to coordinate the implementation of the 151 plans at appropriate scheduled outages. The plans are also to be made available for review by the Code Inspector.
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I1.3.3 l I Tests following plant modifications, repairs, maintenance or significant changes in operating procedures are to be conducted to confirm that they are not detrimental to the safe and efficient operation of the plant and that the components or systems demonstrate satisfactory performance.
I1.3.4 Requirements for the given test to be performed are to be identified in the test procedures / instructions. Evidence is to be available to assure the following minimum requirements are met:
(1) Test .quipment and measuring devices are calibrated in accordance with the requirements of Section 12.0 of this manual and are functioning properly.
(2) Ten personnel have been qualified to perform the test in accordance with the requirements of Section 2.0 of this manual.
(3) Appropriate witness and hold point notifications have been provided.
(4) Test prerequisites are completed.
(5) When accuracy requirements for tests exceed the accuracy of normally available process or measuring and test equipment, such additional accuracy requirements are to be specified within those test procedures.
I1.3.5 Testing activities are to be subject to surveillance / inspections in accordance with Section 10.0 of this manual.
Testing as a result of repairs, modifications, replacement or scheduled inservice tests on ASME Code items is also subject to inspection by the Code Inspector. The assignment ofinspection hold points is described in Section 10.0 of this manual.
I1.3.6 Test results are to be documented in accordance with the applicable procedures / instructions. Test documents are to contain at least the following:
(1) Identity ofitem tested (2) Date of test (3) As-found condition
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I (4) Identification ofindividuals performing test (5) Test results (6) Corrective actions performed,if any (7) As-left condition 11.3.7 Test results are to be evaluated by responsible, qualified personnel per approved procedures to assure that test objectives and inspection requirements have been satisified. Nonconforming items are to be identified and controlled in accordance with Section 15.0 of this manual.
I 1.4 RECORDS Test results are to provide objective evidence that the testing was performed in compliance with approved procedures. Test records are to be maintained and transmitted to the Document Control Center for retention in accordance with Section 17.0 of this manual.
11.5 TEST STATUS Inspection and test status is to be controlled in accordance with the provisions of Section 14.0 of this manual.
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12.0 CONTROL OF MEASURING AND TEST EOUIPMair l I 12.1 SCOPE 12.1.1 A program is established to assure that desices used for measurements, tests and cCbrations are identified, controlled and calibrated against reference standards to assure that accuracy is maintained within the limits specified by the inspection or test requirements. Control of measuring and test equipment is to comply with the applicable provisions of Regulatory Guide 1.33, Rev. 2, pertaining to measuring and test equipment, unless otherwise noted in Table 1.
12.1.2 This section is generally applicable to chemical and radiochemical equipment, except for paragraphs 12.3.3, 12.3.4 and 12.4.2. The controls for the calibration of chemical and radiochemical measuring equipment are to comply with the provisions of Regulatory Guide 1.33 Rev. 2 Appendix A Section 10.0, and performed in accordance with chemical and radiochemical control procedures.
l 12.1.3 This section does not apply to rulers, tape measures, levels or other such devices where normal commercial practices provide adequate accuracy.
12.2 RESPONSIBILITIES 12.2.1 The cognizant superintendents / group supenisors are responsible for establishing and maintaining lists of measuring and test equipment under their control that require periodic calibration and for the calibration of this equipment, as assigned within approved procedures.
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The cognizant supervisor is responsible for identifying measuring and test equipment required for the activity and assures that the devices are used only by qualified personnel. i 12.2.3 Personnel performing the activity are responsible for utilizing only properly identified and calibrated ,
measuring and test equipment when performing inspections and tests for record.
12.2.4 1
The Quality Organization is responsible for monitoring test equipment control and use in order to verify compliance with the program.
12.3 GENERAL 12.3.1
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\d Calibration procedures are to be established for each type of measuring and test equipment. These procedures i
are to conform to recognized codes and standards and to local, state and federal regulations and are to be referenced on the calit..ation reports / logs.
12.3.2 Measuring and test equipment are to be properly controlled, calibrated and adjusted at specific intenals or prior to use to assure the necessary accuracy of calibrated equipment. Calibration intervals are to be based upon the type of equipment, manufacturer's recommendations. stability and reliability characteristics, required accuracies, use and other conditions affecting calibration.
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12.3.3 l
Reference standards used in the calibration of measuring and test equipment are to be traceable to the National Institute of Standards and Technology, or if nonexistent, to accepted industry or ANO standards. Reference standards are to have an accuracy at least four times that of the measuring and test equipment. In any instance ,
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where the four times criteria is unable to be met, standards are to have an accuracy level, acceptable l
I calibration range and precision equal to or better than those required for the ranges affected by the calibration. i Accuracies less than four times will be acceptable when warranted by statistical analysis or limited by the state-of-the-art as authorized by responsible management. Reference standards are to be maintained in an emironment with temperature, hur2idity and cicanliness controls compatible with maintaining accuracy and operating characteristics of the standards.
12.3.4 When measuring and test equipment are found to be out of calibration, an evaluation of the validity of presious inspection or test results and the acceptability of items previously inspected or tested is to be made and documented by written report in accordance with approved procedures. If any piece of measuring or test equipment is consistently found to be out of calibration, it is to be repaired or replaced.
12.3.5 Re-calibration per approved procedures is to be performed when the accuracy of either installed or calibrated equipment is questionable.
I2.4 EQUIPMENT IDENTIFICATION 12.4.1 Measuring and test equipment lists are to contain sufTicient information to uniquely identify each item listed and is to include, as a minimum, calibration intervals tolerances and storage locations. The lists are also to identify the group responsible for the control of cach item. t I
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12.4.2 l
Items listed on measuring and test equipment lists are to be tagged, labeled or otherwise identified per j approved procedures in such a manner that clearly identifies the equipment and their calibration status and l
provides traceability to the calibration records.
12.4.3 l
Measuring and test equipment found to be out of calibration are to be tagged and segregated from acceptable equipment in accordance with approved procedures until repaired and/or re-calibrated. j l
l 12.5 RECORDS Calibration documentation is to be maintained to verify calibration status, condition, accuracy and out-of-tolerance trends of the equipment.
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13.0 llANDLING STORAGE AND SHIPPING l I 13.1 SCOPE Activities for the handling, storage and shipping, including cleaning, packaging and presen ation of materials and equipment are to be performed in accordance with established instructions, procedures or drawings, to prevent damage, deterioration or loss of the item. Activities are to comply with the provisions of Regulatory Guide 1.38, Rev. 2, unless otherwise noted in Table 1.
13.2 GENERAL 13.2.1 Instructions for preservation are to be provided for items subject to deterioration or damage through exposure to air, moisture or other emironments during fabrication, processing, assembly and interim storage periods. Items are to be cleaned, preserved and packaged as required to preclude deterioration and prevent damage. When maintenance of specific internal or external emironments is necessary, it is to be included in special packaging instructions and maintenance procedures.
G 13.2.2 l
l Procurement documents assure that any special cleaning, preserving, handling, packaging or shipping l requirements for purchased material or equipment are taken into account. l l
13.2.3 l
1 For critical, sensitive, perishable or high value articles, recommendations for their handling, storage, packaging, shipping and preservation are to be requested from the supplier per the procurement documents and furnished to the plant prior to or upon receipt of the items at the plant.
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13.3 SHIPPING CONTROLS l
13.3.1 Shipping requirements are to be specified in the procurement documents. Suppliers' compliance with these requirements are to include controls to assure that items are complete and assembled as required; items have been preserved and packaged in accordance with the procurement documents; items have been marked and identified in accordance with specifications and procurement documents; items have been loaded for shipment in such a manner as to prevent damage; and required documentation is complete and furnished in accordance with the procurement documents.
13.3.2 Special nuclear material and sources are to be shipped and stored as specified in the operating licenses and other appropriate regulatory documents. The Manager, Radiation Protection and Radwaste is responsible for asuring that radioactive sources and instruments c,ntaining radioactive sources are stored and handled per these requirements and approved procedures. The Manager, Radiation Protection and Radwaste is also responsible for assuring that low-level w~4ste material is stored and alJpned per these requirements and approved procedures.
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The Managers, System Engineering, ANO-1 & 2 are responsible for assuring that special nuclear material (SNM), as defined in approved procedures. is shipped, stored and handled per these requirements and the approved procedures.
13.4 RECEIVING 13.4.1 Materials and equipment are to be received at the plant per approved procedures and subjected to a receipt inspection in accordance with Section 7.0 of this manual. As part of the inspection activity, received materials and equipment are to be inspected for damage, deterioration, cicanliness and proper identification and markings ,
per approved procedures for receipt inspection.
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13.4.2 4
Results of the receiving inspection and disposition of the material or equipment are to be documented on receiving inspection records. Nonconforming items are to be handled in accordance with approved procedures and Section 15.0 of this manual.
i 13.5 STORAGE CONTROLS 13.5.1 Materials and equipment which have completed the receiving process are to be stored based on the classification level of storage specified on the procurement documents or related design documents.
13.5.2 Storage control procedures are to be established which include, as a minimum, provisions for the following:
controlled access and usage of the storage area; cleanliness and good housekeeping controls; fire protection; protection from environmental hazards; segregation of hazardous materials; and control of those items which have a specified shelflife.
V 13.5.3 Only items which have completed the receiving process are to be placed in a controlled storage area. Records of the items' location (s) are to be provided by the Manager, Materials Purchasing and Contracts (see paragraph 13.3.2 for control of radioactive. sources, low-level waste material and SNM) to identify those items currently in storage and to facilitate inspection and maintenance planning. Issuance ofitems from storage for installation or use is to be documented and controlled in accordance with approved procedures.
f 13.5.4 i
Items identified as requiring maintenance during storage are to be maintained in accordance with a documented maintenance program.
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I 13.5.5 O Storage areas are to be monitored by individuals responsible for the storage areas so that the integrity and l 1
I security of stored items are effectively maintained. Inspections and examinations under the control of the Supervisors, Quality Control are to be performed and documented on a periodic basis to assure that the integrity of the items and their containers is being maintained. Periodic audits under the control of the Supersisors.
Quality Assurance are also performed to assure compliance with storage requirements.
13.6 HANDLING CONTROLS t
13.6.1 Special handling requirements are to be specified in the procurement documents and approved procedures to protect the quality of items susceptibic to handling damage. Special tools and equipment are to be prosided to handle these items and are to be controlled and maintained per written procedure to assure safe and adequate handling.
13.6.2 i
Special handling tools and equipment are to be inspected and tested at specific times in accordance with written procedures to verify that the handling tools and equipment are adequately maintained. Inspection and test status of these handling tools and equipment are to be controlled in accordance with the applicabic sections of this manual. l l
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14.0 INSPECTION. TEST AND OPERATING STATUS l
14.1 SCOPE 14.1.1 The removal from senice, inprocess status and return to service of equipment, components and systems for maintenance, modifications, repair, test or inspection is to be controlled per approved procedures.
These controls are to assure that plant personnel are aware of equipment, structure or system conditions and to prevent their inadvertent use unless cleared by Operations personnel.
14.1.2 Maintenance activities are to be performed in accordance with an established maintenance program to assure that equipment, systems and structures are maintained in a condition which allows them to perform their intended function.
14.2 EQUIPMENT CONTROL O 14.2.1 Prior to removal cf equipment, components or systems from senice for maintenance, modification, repair, test or inspection activities, permission is to be received and documented from the appropriate Superintendent, Shift Operations. The Superintendents, Shift Operations are to assure that the item can be released without affecting plant safety.
14.2.2 The status of equipment, components and systems during these activities is to be identified in accordance with approved proc .dures/ instructions, w hich contain, as a minimum, the following:
(1) Methods for control of equipment to maintain personnel and reactor safety and to avoid unauthorized operation of equipment or systems I
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(2) The use of markings or other suitable means to indicate the status of activities being f performed upon individual items (Suitable means are to include identification numbers g g '
which are traceable to records or to the status of these aethities.)
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(3) Provisions for the identification ofitems which have satisfactorily passed the required activities (In cases where required documentary evidence is not available, the associated equipment or system is to be considered nonconforming and handled in accordance with 1 Section 15.0 of this manual.)
(4) Provisions for independent verifications to ensure that necessary measures (locking or tagging) to secure and identify equipment or systems in a controlled status have been implemented correctly 14.2.3 When entry into a closed system is required, control measures are to be established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed.
14.2.4 During maintenance or modification activities, certain portions of systems, as identified in approved procedures, may be subject to potential contamination with foreign materials. To prevent such contamination, control measures. including measures for access control, are to be established.
Immediately prior to closure, an inspection is to be conducted to assure cleanliness and the result of such inspection is to be documented.
14.2.5 If temporary modifications (such as temporary bypass lines, electricaljumpers. lifted electrical leads and temporary trip point settings) are required for a system or piece of equipment, they are to be performed in accordance with approved procedures. Procedures that control such temporary modifications shall delineate requirements to:
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(2) Perform independent verification of temporary modifications, by an indisidual cognir. ant of
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the purpose and effect of the temporary modi 6 cation (3) Document temporary modifications to assure the required actions are taken to return the equipment or system to its original operating configuration and status Additionally, temporary modifications which constitute temporary changes to plant configuration due to routine tasks such as additions of temporaryjumpers or gauges as pan of maintenance, calibration, or troubleshooting, may be installed and removed by use of approved procedures or work plans, providing (2) and (3) above are satisfied. These changes are not maintained on a status log since removal of the temporary chang:is controlled by the same procedure on work plan which installed it.
14.2.6 When equipment or a system is properly identified as being ready to be returned to service, the appropriate Superintendent, Shift Operations is notified and initiates the proper operation procedures. Testing of the equipment or system for functional acceptability is to be in accordance with Section 11.0 of this manual and O documented to verify current status of the item, O
14.2,7 Equipment, structures and systems found to be nonconforming as a result of an activity are to be handled in accordance with approved procedures and Section 15.0 of this manual.
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14.3 MAINTENANCE CONTROL 14.3.1 i
In addition to the requirements and controls identified in subsection 14.2 of this manual, a maintenance program is to be planned and scheduled through the appropriate Manager, Maintenance to assure that the safety of the plant is not compromised nor the Technical Specifications violated. Maintenance activities are to be performed per approved procedures and instructions and conducted in a manner to assure qualitv at least equivalent to that specified in the design documents, material specifications and inspection requirements. As !
experience is gained in operation of the plant, routine maintenance may be altered to improve equipment l
performance and procedures for repair of equipment are to be improved as directed by the appropriate Manager, l Maintenance.
l 14.3.2 A preventive maintenance program, including procedures and instructions for systems, structures and components, is to be established and maintained, which prescribes the frequency and type of maintenance to be performed in order to preclude equipment malfunctions. The preventive maintenance program requirements, including associated procedures and task instructions will be maintained by the appropriate Manager, Maintenance as applicable based on the specific maintenance discipline. The associated engineering evaluations for each unit will be maintained under the applicable Manager, Maintenance. Implementation of l the program is the responsibility of the General Manager Plant Operations and is implemented by qualified maintenance personnel in accordance with approved procedures and instructions u hich specify the work activities, acceptance requirements and the control measures to assure adequate quality. When equipment malfunctions occur, the cause is to be promptly determined, evaluated and recorded per approved procedures and Section 16.0 of this manual.
14.4 OVERALL PLANT STATUS 14.4.1 1
The Superintendents, Shift Operations are provided suflicient knowledge of the overall plant status of equipment, structures and systems to control operation of the plant in a safe manner. The shift operators are to l maintain a ready reference of plant systems, equipment and component alignments, as well as a status board !
summary of their conditions.
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I 14.4.2 l I The tumover of duties to personnel on succeeding shifts is conducted in accordance with approved procedures. )
These procedures include documented turnover action appropriate to the duty station acknowledging the status of the nuclear power plant, its structures, systems and components (including design changes / modifications which may afTect the performance of their duties) and transfer of authority.
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15.0 NONCONFORMING MATERIAL PARTS AND COMPONENTS I
15.1 SCOPE Nonconforming items are to include materials, parts, components and, as applicable, senices (including computer codes) that do not conform to applicable regulations, codes, standards, specifications, diawings or licensing documents. Nonconforming items are to be controlled in accordance with approved procedures to prevent their inadvertent use or installation. These procedures are to contain measures to assure the prompt identification and notification, documentation, segregation, technical resiew and disposition of a nonconforming item.
15.2 GENERAL 15.2.1 It is the responsibility of each individual to identify a nonconformance and to report it to their cognizant supenisor for resiew and concurrence. The initiator is to document the nonconformance as identified within approved procedures. If the nonconformance is determined to be a Technical Specification violation and/or reportable to the NRC, see subsection 16.5.
15.2.2 Nonconforming items are to be identified by tagging, marking or as otherwise identified per approved procedures to control further processing or. when physical segregation is not practical, to prevent inadvertent use or installatiori of the item. Ncnconforming items are to be segregated from acceptable items unless they are cunently installed or their size, weight, configuration, etc., makes it impractical to I l
move to a segregated area. Tags and/or markings are to remain on the item until the disposition is l complete per approved procedures.
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15.2.3 l I Repons of nonconforming items are to identify the group responsible for dispositioning the nonconformance. The assigned individual within the responsible group is to evaluate the nonconformance and confer, as appropriate, with interfacing groups to determine a recommended disposition. The disposition for materials, parts, components and as applicable, services (including computer codes), which may be reject, rework, repair or use-as-is, and any actions taken/ required to be taken as a result of the disposition are to be documented on the repon.
15.2.4 Review of the disposition for concurrence is to be performed by the individual / group identified within approved procedures. If the review group or individual cannot agree with the assigned individual on the disposition, either the General Manager, Plant Operations or the appropriate Director or Manager, is to decide. For a repair or use-as-as disposition, a cognizant individual knowledgeable in the design requirements for the afTected item is also to review the report for concurrence of the disposition. Written justification for the design change, repair or deviation that has been accepted is to be documented to denote the as-built condition and is to be made a part of the report G 15.2.5 The acceptability of rework or repair of materials, parts, components, systems and structures is to be verified by re-inspecting the item as originally inspected or by a method which is at least equal to the original inspection method. The rework and repair inspection records are to be documented and become part of the permanent records for the item.
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15.2.6 l I Upon completion of the disposition, the nonconformance report is to receive an independent resiew in accordance with approved procedures, for concurrence or possible assignment of additional actions pertaining to the disposition.
15.2.7 For ASME Code,Section III, Division 1 materials, parts and components dispositioned repair or use-as-is, the nonconformance report is to be subject to review and concurrence by the Code inspector.
15.3 SUPPLIER NONCONFORMANCES 15.3.1 Procurement documents are to contain requirements for the vendor / contractor to identify to ANO those items which violate a technical or material requirement of the procurement document and which results in a disposition of repair or use-as-is. All such nonconformances are to be reported to ANO for evaluation and acceptance. The vendor / contractor is to document such nonconformances on its applicable nonconformance report which is to be included in the final documentation package submitted to ANO, in accordance with the procurement documents.
15.3.2 Upon receipt ofitems at the plant, ANO Receipt inspection personnel are to review any nonconformance reports in the documentation package to ensure the nonconforming items have been properly dispositioned and accepted by ANO.
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15.4 RECORDS l l 15.4.1 Upon completion of disposition and verification activities, the completed nonconformance repon, and related documents generated to ensure proper disposition and resolution of the nonconformance, are to be forwarded'to and maintained by the Document Control Center.
15.5 DEFICIENCY TRENDING The Director, Licensing or designee is to maintain and issue a trending repon, at least quarterly, of nonconformances to the Vice President. Operations ANO for resiew.
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i 16.0 CORRECTIVE ACTION l
16.1 SCOPE l
A corrective action system is established to assure that conditions adverse to plant safety, such as failures, malfunctions, deficiencies, deviations, defective materials and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to safety, this system is to assure that the cause of the condition is determined and corrective action taken is documented and reported to appropriate levels of management for independent resiew.
16.2 GENERAL, 16.2.1 When deviations, deficiencies, malfunctions, nonconformances or other conditions are encountered, they are to be reported to responsible authorities for review and disposition in accordance with approved procedures.
16.2.2 O Cognizant supervisors are to review discrepancies discovered durh g the course of plant operations and take appropriate action to resolve the discrepancies. For significant conditions adverse to safety, they are to initiate action to identify their root causes and take necessary corrective action to preclude repetition.
16.2.3 Evaluation of the corrective action is to be performed by the individual / group identified witidn approved procedures to determine its adequacy and completeness and to assure the need for additional corrective action.
If the corrective action is acceptable, follow-up action to verify implementation, documentation and close-out of the corrective action commitments is to be performed per approved procedures.
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16.2.4 1
1 8 If agreement upon the resolution cannot be achieved, the condition is to be referred to the appropriate level cf management as specified in approved procedures.
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16.3 SUPPLIER DEFICIENCIES When vendors furnish products or senices that do not conform to the requirements of the applicable purchase l
contract and, in the opinion of Supplier QA, warrants additional evaluation, Supplier QA will evaluate the vendor's past performance using available information such as audits, receiving inspection reports, industry notices, etc. Results of the evaluation will be used to determine the status of the vendor.
16.4 SIGNIFICANT CONDITIONS l
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Significant conditions adverse to safety are to include, as a minimum, the following:
i (1) Conditions that have a direct adverse effect on the safety of the plant per the plant Operating l License and Technical Specifications (2) Conditions that have caused the uncontrolled release of radioactive materials (liquid, solid, gaseous or air paniculate) to the emirons (3) Adverse quality trends uhich could lead to unsafe plant operations 1
16.5 REPORTABLE EVENTS 16.5.1 When significant conditions adverse to safety are discovered, the Licensing Department is to evaluate the condition and determine if it is an event reportable to the hPC.
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16.5.2
.e Upon determination that a significant adverse condition is reportable, the Director, Licensing ensures that the j appropriate report is initiated and subsequently transmitted to the NRC.
16.5.3 The PSC reviews Root Cause and Corrective Action plans for reportable events through its review of Licensee Event Reports (LERs).
16.5.4 The Licensing Department is responsible for transmitting approved reports to the NRC within the time period specified in the Technical Specifications and approved procedures.
16.6 VERIFICATION i
Verification by surveillance or audit of the effective implementation of corrective actions is to be periodically O performed and documented by responsible Quality personnel. Audits are to be performed in accordance with Section 18.0 of this manual.
1 O
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17.0 QUALITY ASSURANCE RECORDS l '
17.1 SCOPE l 17.1.1 l l
Documentation covering design, construction, procurement, fabrication, inspection, operation, l I
maintenance, nonconformance and corrective action, test and audit actisities is to be filed and stored to l
provide objective evidence of quality-related activities and to assure the ability to reconstruct significant events. Control of records is to be in accordance with Regulatory Guide 1.88, Rev. 2 (10n6) unless otherwise noted in Table 1.
l 17.1.2 Quality assurance records are to include operating logs; results of reviews, inspections, tests, maintenance, audits, material analyses; monitoring of work performance; qualification of personnel, procedures, and equipment; historical drawings, specifications, personnel exposure, engineering reports, calculations, I
procurement documents, calibration procedures and reports, nonconformance repons, corrective action j
/ reports, correspondence and related records pertinent to quality as defined in approved procedures.
i V i 17.2 RESPONSIBILITY 17.2.1 l The Superintendent, Administrative Senices is responsible for the establishment, implementation and maintenance of the records management program to be used throughout the operational life of ANO and for ensuring that documentation retention requirements comply with applicable Tecimical Specifications, codes and regulations.
A wE nterg QA MANUAL OPERATIONS REV. 17 DATE 07/22/94 Operat s SEC' HON: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-1 1
j
17.2.2 l I Personnel, other than plant staff, and outside firms who perform work on ANO in the areas of design, procurement, maintenance, modification, testing, quality assurance and special nucIcar materials are to provide documentation /ccrtification records to ANO for subsequent storage and retention by the Document Control Center.
17.2.3 Quality Assurance personnel are to periodically audit qual'ty-related records and records filing and storage procedures to assure that the records management progr - is being properly implemented. Audits are to be performed as outlined in Section 18.0 of tids manual.
17.3 DOCUMENTAT!ON RETENTION 17.3.1 Lifetitae Quality Assurance Records 17.3.1.1 O Lifetime records are defined as those which meet one or more of the following criteria:
(1) Those which would be of significant value in demonstrating capability for safe operation (2) Those which would be of significant value in maintaining, reworking, repairing, replacing or modifying the item ;
1 Those which would be of significant value in determining the cause of an accident or l (3) l mdfunction of an item ,
l (4) Those which provide required baseline data for insenice inspection l i
J 17.3.1.2 l Lifetime quality-related records are to be maintained for the life of the particular item while it is installed I
or stored for future use as prescribed in approved procedures.
p 0 & ntergy E QA MANUAL OPERATIONS REV. 17 1
= Operations DATE 07/22/94 Arkansas Nuclear One
17.3.2 Non-Permanent Quality Assurance Records I
17.3.2.1 Non-permanent records are defined as those which meet all of the following criteria:
(1) Those of no significant value in demonstrating capability for safe operation (2) Those of no significant value in maintaining, reworking, repairing, replacing or modifying the item (3) Those of no significant value in determining the cause of an accident or malfunction of an item (4) Those w hich do not provide baseline data for insenice inspection 17.3.2.2 Non-permanent records are to provide evidence that an activity was performed in accordance with applicable requirements and be retained for specified periods as directed by the approved procedures for document retention and disposition.
O 17.3.3 Categories of permanent and non-permanent records to be maintained and their appropriate retention periods are described in approved pracedures.
17.3.4 Quality Assurance documents received from suppliers are inspected and approved as directed by approved procedures for procurement of material, equipment and senices.
1
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- QA hiANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 l SECTION: 17.0 QUAllTY ASSURANCE RECORDS PAGE 17-3 l
Arkansas Nuclear One l
i 17.4 STORAGE 17.4.1 Permanent records are to be microfilmed and the microfilm stored within a controlled area at ANO per :
approved procedures. A duplicate set of microfilm is also made and stored at a remote location.
17.4.1.1 1
For storage of film and other special processed records, humidity and temperature controls are to be provided to maintain an emironment as recommended by the manufacturer Ond approved procedures.
17.4.1.2 ;
A list is to be prepared in accordance with approved procedures designating those personnel who have access to the storage files.
17.4.2 Records storage systems are to provide for the accurate retrieval ofinformation without undue delay and be sufficient to control and account for records removed from the storage facility.
17,5 RECORDS INDEXING AND RECEIPT CONTROL 17.5.1 Indexing methods and systems for quality-related records are delineated in approved procedures for records ;
management.
i O ae Entergy QA M ANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-4 Arkansas Nuclear One
17.5.2 l I Records submitted for storage in either lifetime or non-permanent files are to be subject to the following requirements for reaipt contral:
(1) Establishment of a records list designating the required quality-rela'ted records (2) Establishment of a system designating criteria for document inspection to assure that records are complete, legible and received in good condition (3) A file system to indicate which quality-related documents have been received 17.5.2.1 Implementation of receipt control requirements for storage is the respc.nsibility of the Superintendent.
Administrative Senices.
17.6 FINAL DISPOSITION The Superintendent Administrative Services is responsible for disposal of quality-related records in accordance with approved procedures for document retention and disposition, which permits periodic l
purging of records retained past their required retention date.
9 a Entergy
= QA M ANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-5 Arkansas Nuclear One
18.0 AUDITS l I 18.1 SCOPE 18.1.1 A comprehensive system of planned and periodic audits is provided to ensure and verify compliance with all aspects of the administrative controls and quality assurance program Audits are to be planned and performed in accordance with written procedures, plans and checklists and are to conform to the applicable ponions of Regulatory Guides 1.144, Rev.1 (9/80), and 1.146, Rev. 0 (8/80), unless otherwise rioted in Table 1.
18.1.2 The audit program is to include provisions to determine the compliance with and efTectiveness of the QA Program in controlling structures, systems, components and activities in accordance with the rules set fonh in the codes, standards and regulations identified in the Introduction of this manual.
AUDIT PERSONNEL 9 18.2 18.2.I The Supenisors, Quality Assurance and the Manager, Quality have assigned auditing responsibility within the QA Program and are responsible for the selection and assignment of auditors. Auditors are to be independent of any direct responsibility for performance of the activity which is to be audited and are not to report to a management representative who has direct responsibility for the activity being audited.
I8.2.2 Auditors assigned auditing responsibilities are to have experience and training commensurate with the scope, complexity and/or special nature of the activities to be audited. When audit assignments are made, considerations are given to special abilities, specialized technical training. prior peninent expenise, personal characteristics, education and capability. If no one within the Quality Organization n
QA MANUAL OPERATIONS REV. 17
- Ente W DATE 07/22/94 Operations PAGE 181 SECTION: 18.0 AUDITS Arkansas Nuclear One
meets these prerequisites completely, technical specialists are to be used to assist in the auditing of the activity. Technical specialists are to meet the requirements of paragraph 18.2.1 of this manual.
18.2.3 Audit personnel are provided appropriate training to assure their competence for performing the required audits. Proficiency of audit personnel is maintained by one or more of the following methods:
(1) Regular, active participation in the audit process (2) Review and study of codes, standards, procedures and instructions (3) Panicipation in training or orientation programs ,
18.3 AUDIT SCHEDULE 18.3.1 Audits are to be performed on a planned and periodic basis in accordance with an audit schedule. Audit schedules are to be prepared at the beginning of each year by the Quality Organization and approved by p the Supervisors, Quality Assurance; Director. Quality; and the SRC.
V I8.3.2 Audit schedules assure that, as a minimum. the following areas are audited, under the cognizance of the SRC, at the indicated frequencies:
- a. The conformanceof each unit's operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training. and qualifications of the entire staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in unit equipment, structure, systems, or method of operation that afTect nuclear safety at least once per 6 months.
e Entergy QA MANUAL OPERATIONS REV.17 Operations DATE 07/22/94 SECTION: 18.0 AUDITS PAGE 18-2 Arkansas Nuclear One
- d. . The performann of activities required by the Operational Quality Assurance Program to t
meet the criteria of 10 CFR 50, Appendix B at least once per 24 months.
{ )
- e. The Offsite Dose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.
- f. The radiological erwironmental monitoring program and the results thereof at least once per 12 months.
- g. Any other area of unit operation considered appropriate by the SRC or the Vice President, Operations ANO.
I8.3.3 Audits of vendor / contractor activities are to be scheduled as identified in paragraph 7.3.3 of this manual. These audits are to evaluate and verify it.cir quality assurance program, procedures and activities, to assure compliance with the procurement documents and to verify they periodically review and audit their suppliers' quality assurance programs. Audit schedules for vendor / contractor audits are O approved by the Manager, Quality.
b 18.3.4 Periodic reviews of the audit programs are to be performed by the SRC or their appointed management representative at least scrniannually to assure that audits are being accomplished in accordance with the requirements of the Technical Specifications, this manual and Regulatory Guide 1.33. Rev. 2 (2/78),
unless otherwise noted in Table 1.
18.3.5 Regularly scheduled audits may be supplemented. as required, to cover unforeseen events or changed requirements.
O a Entergy QA MANUAL OPERATIONS REV. 17
~~~ DATE 07/22/94 Operations PAGE 18 3 SECTION: 18.0 AUDITS r
Arkansas Nuclear One
1 I
l I8.4 AUDITIMPLEMENTATION I I 18.4.1 Audit plans and checklists are to be prepared by the auditor and approved by the responsible Quality management, or designec, prior to performing the audit. Checklists are to be used to ensure depth and continuity of audits in order to verify that those procedures and instructions issued to control the audited activity are adequate.
18.4.2 Upon completion of an audit, a written report is to be prepared which includes at least the following items:
(1) Description of audit scepe and date (2) Identification of the auditor (s)
(3) A summary of audit results (4) Details of nonconformances or programmatic deficiencies (5) Recommendations for correcting nonconformances or improving the QA Program, as appropriate 18.4.3 Deficiencies identified as a result of an internal audit are to be recorded on a Quality Assurance Finding Report (QAFR) by the auditor and issued to the Department Head responsible for the area audited for corrective action. The Department Head or the assigned designee is to provide prompt corrective action to the deficiencies identified and document on the QAFR the action taken or to be taken to preclude recurrence. Appropriate follow-up including re-audits by the assigned audit group is conducted in the deficient areas to verify proper and timely implementation of corrective action commitments. Follow-up actions are to be documented on the QAFR.
= Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: 18.0 AUDITS PAGE 18-4 Arkansas Nuclear One
18.4.4 l
l Internal audit repons pertaining to plant operations activities are to be independently reviewed by the SRC to detennine if additional corrective actions need to be initiated to assure continued safe operation of ANO. Internal audit reports pertaining to other than plant operations activities are to be independently reviewed by the SRC. In addition to this review, the audit reports are to be distributed, as a minimum, to the Director, Quality; Supervisors. Quality Assurance; and appropriate levels of management having responsibility in the area audited to assure their awareness of the findings.
18.4.5 Audit results and findings related to external audits conducted by Supplier QA personnel are to be recorded and distributed to the Superintendent, Procurement Engineering and a designated representative of the audited organization as a minimum. Deficiencies are to be recorded and the audited organization is to describe actions taken to correct deficiencies and prevent recurrence.
Corrective actions are to be verified by Supplier QA personnel and documented.
18.5 RECORDS O Written internal / external audit reports, including checklists, QAFRs, vendor / contractor findings, and related documentation supporting the follow-up activities are to be fonvarded to the Document Control Center for storage in accordance with Section 17.0 of this manual.
I8.6 NUCLEAR FUEL AUDITS 4
The Manager, Quality has the responsibility for performing those quality assurance functions necessary to assure that its nuclear fuel is designed and fabricated in accordance with regulatory requirements and accepted codes, standards and specifications. Supplier QA monitors the design and fabrication of the fuel through a program of audits of the fuel fabricator, including both design review audits and fuel fabrichtion audits. Supplier QA also conducts audits of component suppliers as deemed necessary to }
assure the quality of the fuel and issues formal audit reports to document audit activities and to identify nonconformances or other items requiring action by the fuel fabricator. Resolution of nonconformances or other items requinng action is venfied by Supplier QA and documented in follow-up reports. Th:
O@ Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: 18.0 AUDITS PAGE 18-5 Arkansas Nuclear One 1
Superintendent, Procurement Engineering is on distribution for all audit and follow-up reports. These audit reports are to be forwarded to ANO and stored in accordance with Section 17.0 of this manual.
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Entergy QA MANUAL, OPERATIONS REV.17 Operations DATE 07/22/94 SECTION: 18.0 AUDITS PAGE 18-6 Arkansas Nuclear One
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c TABLE 1 ARKANSAS NUCLEAR ONE EXCEPTIONS / INTERPRETATIONS OF REGULATORY GUIDES AND ANSI STANDARDS APPLICABLE TO THE QA PROGRAM Regulatory Guide / Exceptions /
ANSI Standard Beauirement Intemretation General Certain Regulatory The ANO commitment refers Guides invoke or to the Regulatory Guides and imply Regulatory ANSI Standards, specifically .
Guides and standards identified in this manual.
in addition to the Additional Regulatory Guides, standard each ANSI Standards, Guides and primarily endorses. similiar documents implied Certain ANSI Stan- or referenced in those dards invoke or specifically identified in imply additional this manual are not part of U standards. this commitment.
General Certain ANSI Our commitment to those Standards and/or standards applies only to Regulatory Guides those systems, structures, extend the scope of and components whose satis-applicability to factory performance is include systems, sequired to prevent postu-structures, and lated accidents that could components whose cause undue risk to the satisfactory perfor- health and safety of the mance is required public; or to mitigate for a plant to the consequences of such operate reliably on accidents. Reliable operation O ew Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE 1 PAGE TI-l Arkansas Nuclear One
"high-val.se of the plant may depend upon articles." other systems, structures and l I components which are not covered by this commitment.
ANSI N18.7 The following ANO has committed to R.G.1.58, standards contain Rev,1/ ANSI N45.2.6 - 1978 (Section 5.2.7)
..during initial which shall be used in lieu of plant design and 1973 edition.
construction. AWS Qualification of Inspection, Examination and Testing Personnel for the - -
Construction Phase of Nuclear Power Plants, N45.2.6-1973..
O ANSI N18.7 The causes of the ANO will comply with this (Section 5.2.7.1) malfunctions shall requirement, where applicable.
be promptly This clarification is needed ;
determined, since it is not always possible f evaluated, and to promptly determine the )
recorded. cause of the malfunction. l ANSI N18.7 Where changes are Consistent with the require-(Section 5.2.13.1) made to procure- ments of ANSI N45.2.11, para-ments, they shall graph 7.2, minor changes to be subject to the (procurement) documents, such same degree of as, inconsequential editorial control as was used corrections, or changes to in the preparation commercial terms and conditions f3 b h=Entergy QA MANUAL OPERATIONS REV. 17 Oper'ationS DATE 07/22/94 SECTION: TABLE 1 PAGE TI 2 Arkansas Nuclear One
l 1
l i
I of the original may not require that the re-documents. vised (procurement) document j l l receive the same rniew and 1 approval as the original documents. :
ANSI N18.7 Plant procedures Programmatic controls that are (Section 5.2.15) shall be rniewed equivalent to or better than by an individual the biennial rniew process knowledgeable in have been implemented at ANO.
the area affected These programmatic controls by the procedure are effected in an effort to no less frequently ensure that procedures are than every two reviewed for possible revision years to determine upon identification of new or if changes are revised source material necessary or potentially affecting the desirable. content of procedures, thereby maintaining the procedures 9 current. Entergy Operations believes that this approach better addresses the intent of ANSI N18.71976 and is more acceptable from both a technical and practical perspective than a static two-year review process.
l i
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Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 l I
SECTION: TABLE 1 PAGE TI-3 l Arkansas Nuclear One l
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ANSI N18.7 Records shall be Not allinspections will (Section 5.2.17) kept in sufficient require generation of a l detail to permit separate inspection report.
adequate confir- Inspection requirements may mation of the in- be integrated into appro-spection program. priate procedures or other documents with the procedure or document serving as the record. However, records of inspections will be identi-fiable and retrievable.
ANSI N45.2.1 Fresh water criteria The turbidity requirement on (Section 3.2) for chlorides, and fresh wateris deleted and Jackson Turbidity the chloride requirement is Units. revised to read "less than 250 ppm." The turbidity requirement for demineralim!
water is deleted.
O ANSI N45.2.2 Preliminary visual Inspection after unloading is Subsection 5.2.1 inspection or exami- suflicient to determine the nation shall be per- condition of many items. In formed prior to special instances, pre-tmload-unloading.. ing examination is performed.
ANSI N45.2.2 The (receiving) Receiving inspection is per-Section 5.2.2 inspections shall formed in a manner and in an be performed in an emironment which does not area equivalent to endanger the requisite quality the level of storage of an item. The receiving requirement for the inspection area emironmental item. controls may be less stringent 8= ntergy E QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE I PAGE TI-4 Arkansas Nuclear One
than storage emironmental I requirements for that item; l I however, the short time spent in the less stringent receiv-ing inspection area shall be of such duration that will not adversely affect the item being received.
ANSI N45.2.2 ...The 'Special The "Special Inspection" Paragraph 5.2.3 Inspection
- pro- procedure shall be readily cedure, complete available to inspection with documentation personnel and may be attached instructions shall to the item or container.
be attached to the item or container..
ANSI N45.2.2 The use or storage People working in storage Subsection 6.2.4 of food, drink:, and areas have a right of access 9 salt dispensers in to water dispensers per OSHA any storage area is requirements. Additionally, prohibited. due to the location and layout of the building, per-sonnel may temporarily store lunches in the work place.
This area is policed for sanitation.
ANSI N45.2.2 Care ofitems in Types of components that (Section 6.4.2) storage shall be could require maintenance exercised in while in storage shall be accordance with identified and evaluated l
G Entergy QA MANUAL OPERATIONS REV. 17 OperaUons DATE 07/22/94 Arkansas Nuclear One
the following: for specific maintenance requirements. Maintenance activities 6.4.2(6) through (8) listed in this requirement shall be considered during this evaluation and any deviations shall be justified and documented.
ANSI N45.2.2 Container markings Containers are adequately Appendix (A-3) shall appear on a marked for storage,identifi-A.3.9 (1) Second minimum of two sides cation, and retrieval.
Group of the container, Multiple marking requirements preferably on one are imposed, where necessary, side and one end.
ANSI N45.2.2 Container markings Container markings are of a Appendix (A-3) shall be...no less size which permits easy A.3.9 (4) Second than 3/4" high, recognition.
G Group container permitting.
ANSI N4$.2.2 Container I:wking The information required Appendix (A-3) shallinclude the in container marking is A.3.9 following informa- evaluated on a case-by-tion.. basebasis. Markingis adequate in each case.
ANSI N45.2.2 Non-metallic plugs Non-metal plugs and caps are Appendix (A-3) and caps shall be of a suitably visible color.
Section A 3.5.1 (1) brightly colored.
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w Ent ons QA MANUAL OPERATIONS REV. 17 DATE 07/22/94 Oper-Arkansas Nuclear One
l l
ANSI N45.2.2 Plugs or caps shall In cases where plugs or caps Appendix (A 3) be secured with tape do not snugly fit, additional
-l or other means as secunng desices or measures Section A 3.5.1 (5) necessary to prevent which will not be detrimental accidental removal. to the item will be used.
ANSI N45.2.2 Marking ofitems The last paragraph of Section i J
Appendix (A-3) not within a con- A.3.9 could be interpreted as j Section A 3.9 tainer. prohibiting any direct marking l on bare austenitic-stainless- [
steel and nickel-alloy metal surfaces. In lieu thereof, f
paragraphs A.3.9. (1) and (2) >
willbe used to control marking on the surface of austenitic-stainless-steels ;
I and nickel-base alloys subject to the followinglimitations: ;
s " Marking materials containing
_.) sulfur, lead, zinc, mercury, copper and low melting alloys as a basic chemical consti-i tuent shall not be brought in contact, or shall not be used :
on su faces of corrosion- ,
resistant alloys. Iow-sulfur, l low-fluorine and/or low- !
chlorine compounds may be used on austenitic stainless steels." The maximum limits for the above mentioned mark-ing materials will be as follows: .
I
\
= Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE 1 PAGE TI-7 Arkansas Nuclear One j r
l l
l (a) Totalinorganic and organic halogen content shall not exceed one (1) percent.
(b) The sulfur content shall not exceed one (1) i percent.
l ANSI N45.2.2 Inert Gas Blankets There may be cases invohing large or complex shaped items t for which an inert or dry air purge is provided, rather than a static gas blanket, in I
order to prmide adequate protection due to difficulty of prmiding a leak proof barrier. In these cases, a positive pressure purge flow may be utilized as an alter-G nate to a leak-proof barrier.
ANSI N45.2.2 Limits halogen and Engineering may allow the use Appendix A, sulphur content of of tapes containing greater A.3.5.2, (1), (a) tape. amounts of halogens after appropnate evaluation;
' however, the quantities shall l
l not be such that harmful 1
concentrations could be leached or released by break.
down of the compounds under expected emironmental j conditions.
l l
i V = Entergy REV. 17 QA MANUAL OPERATIONS Operations DATE 07/22/94 SECTION: TABLE I PAGE TI-8 j Arkansas Nuclear One
(
l
t Regulatory Guide General Alternative equivalent 1.39 ANSI N45.2.3 requirements may be utilized G to cover those situations not included in the subject Standard; for example, situa-tions in which shoe covers and/or coveralls are required but material accountability is not. In addition, zones might be combined into the next more restrictive category in order to reduce total number of zones.
ANSI N45.2.3 Identifies various When this standard is applied, housekeeping re- its requirements are imple-1 quirements,includ- mented in those areas affected ing cleanliness, by work activities associated fire prevention, with modifications, opera-() and fire protection tions, or maintenance as which must be determined necessary by plant accomplished during staff.
the progress of construction.
Regulatory Guide Pre-Construction / This section required verifi-1.30/ ANSI N45.2.4 Installation Verifi- cation that items are in
- cation satisfactory condition for Regulatory Guide installation and have not ,
1.116/ ANSI N45.2.8 suffered since initial receiptinspection. Upon i recr;pt,itemt are inspected
]
and stored in 6:n environment I 1
which will not adversely l l
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= Entetgy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 j SECTION: TABLE 1 PAGE TI-9 Arkansas Nuclear One t j 4
affect the item. Documented routine inspections and G periodic audits of the storage areas assure that stored items are maintained in satisfactory conditions. Documentation of pre-construction verifica-tion in addition to documen- ,
1 tation ofinitial receipt inspection, periodic storage inspections, and audits of storage is not required. !
ANSI N45.2.4 Identifies various These tests will be performed tests to be as determined by Engineering l l
performed. or Nuc! car Operations based l
upon the significance of change or modification.
d RG.1.58 In addition... the ANO takes exception to this (Section C.6) candidate should be requirement. ANO's education a high school and experience requirements graduate or have are in accordance with ANSI carned the General N45.2.6 1978. I Education Development (GED) equivalent of !
a high school diploma.
RG.1.74/ Definitions of Based upon the guidance of ANSI N45.2.10 Certificate of ANSI N45.2.13,10.2, the Confonnance and definitions of these two Cenificate of terms will be exd.anged.
Compliance.
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I hw Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94
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Arkansas Nuclear One
R.G.1.94/ Section 1.4 defines This requirement for rein-ANSI N45.2.5 inprocess tests and forcing steel will be O (Section 1.4) states: interpreted to permit taking the rebar test specimen at
" .. samples of these the fabrication shop, prior tests must be taken to start of fabrication of from the lot or the rebar from the heat or batch of materials fraction thereof represented supplied to the site by the test specimen. For for use." those tests performed at the fabrication shop, certifica-tion shall be available to provide objective evidence that the test specimens represent the material sup-plied for use at the site.
ANSI N45.2.5 Requirement:
A (Section 4.5) Section 4.5, Con-crete Placement, references American Concrete Institute (ACl) Standards ACI 305-72,
" Recommended Prac-tice for Hot Weather Concreting" and ACI- )
306-66, " Recon . ;nended Practice for Celd Weather Concreting."
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, Arkansas Nuclear One
Interpretation:
In order to clarify l use of these ACI standards, we will apply the following requirernents:
PLACING TEMPERATURES OF CONCRETE:
A. During hot weather cor.creting:
Placing temperatures of concrete will be limited to the following:
- 1) Concrete members less than 3 feet in least dimension will not exceed 90'F.
- 2) Concrete members from 3 feet to 6 feet in least dimension will not exceed 70*F.
G 3) Concrete members more than 6 feet in least dimension will have placing temperature as near 50*F as can be obtained by use of ice as necessary up to 100 percent of adding mixing water; and by shading aggegatt, and sprinkling the coarse aggregate the t'ay it is to be used. Care will be taken so that no unmelted ice remains in the concrete at the end of the mixing penod.
B. During cold weather concreting:
In beating the water and aggregate, live steam to heat the fine and coarse aggregate shall not be used. The permissible range for concrete temperature shall be as follows:
,m
^
Entertf# QA MANUAL OPERATIONS REV. 17 OperationC DATE 07/22/94 SECTION: TABLE I PAGE TI 12 Arkansas Nuclear One i
- 1) Sections less than 3 feet in least dimensions: 55 to 75'F .
- 2) Mass concrete 3 feet or more in least dimensiod: 45 to 65'F The mixing water and aggregate wiB be purchased as required. The materials will be free ofice, snow and frozen lumps before they enter the g mixer.
ANSI N45.2.5 Requirement:
(Section 4.8)
Section 4.8, "In-process Test on Concrete and Reinforcing Steel" states,
" Samples for in-process test of concrete shall be taken at the sampling point in accordance with ASTM C172. This point may be at the truck mixer discharge if the last piece of conveying equipment is a chute, bucket, conveying system, or similar equipment. Pump concrete must be sampled from the pump line discharge."
Interpretation:
For performance of correlation tests, the requirements of ANSI N45.2.5-1974 shall be followed.
ANEl N45.2.5 Requitement:
Mection 4.8)
Section 4.8 "In-process Tests on Concrete and Reinforcing Steel" contains Table B entitled, " Required in-process Tests." The following modifications to this table will be applied:
Interpretation:
ILEINFORCING STEEL In-process testing of reinforcing steel will include the mechanical properties of yield strength, tensile strength and percent elongation on full size specimens 7-3
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hw Entergy QA MANUAL OPERATIONS REV. 17 DATE 07/22/94 Operations SECTION: TABLE 1 PAGE T1-13 Arkansas Nuclear One
l for each bar size for each 50 tons or fraction thereof from each mill heat. Bend tests are performed during material qualification testing only, except as noted I below for bar sizes #14 through #18.
Table A. " Required Qualification Tests" as applied to reinforcing steel will include bend tests as required by ASTM A615 and summarized below; a) For bar sizes #3 through #11, ene full size specimen from largest bar size rolled from each mill heat, unless material from one heat differs by three or more designation numbers. When this occurs, one bend test shall be made from both the highest and lowest designation number of the deformed bars rolled.
l l
l b) For bar sizes #14 through #18, Supplementary Requirements Sl of ASTM A615 will be applied, i.e., one full-size specimen for each bar size for each mill heat. If supplementary requirements are not followed for mill *.sts, they will be applied as la process tests.
The above interpretation is consistent with Rg'.tlatory Guide 1.15. " Testing 9 Reinforcing bars for Category 1 Concrete Structures," Revision 1, December 1972.
In-process test specimens may be selected at the rebar fabrication shop, prior to start of fabrication of the rebar from the heat or fraction thereof represented by the test specimen.
Acceptance criteria for any failed test (qudifications as well as in-process) may be the same as that for tensile tests specMied in Subarticle CC-2331.2 of ASME Section 111 Div. 2 Code (1975). This states that if a test specimen fails to rnect the specified strength requirements, two (2) additional specimens from the same heat and of the same bar size would be tested, and if either of the two additional specimens fails to meet the specified strength requirements, the material represented by the tests would be rejected for the specified use.
L ) &. Entergy QA MANUAL OPERATIONS REV. 17 Operations D ATE 07/22/94 SECTION: TABLE I PaGE T1-14 Arkansas Nuclear One 1
1
I 1
Alternative use of rejected material under strict control may be subject to evaluation by the Project Engineer.
e ANSI N45.2.5 Requirement: l (Section 4.9)
Section 4.9, Mechanical (Cadweld) Splice Testing states in paragraph 4.9.4
" Separate test cycles shall be established for mechanical splices in horizontal, vertical and diagonal bars, for each bar size and for each splicing crew..
- Interpretation:
The terms " horizontal, vertical and diagonal bars" will be interpreted to apply respectively to the following types of splice positions:
- a. Hozizontal, including 10' to horizontal
- b. Vertical, including 10' to vertical
- c. 45' angle, including 10" to 80* angle The words ' splicing crew" will be interpreted to refer to all members on the A
project that are activitely engaged in preparing and assembling cadweld mechanical splices at the final splice location. Separate test cycles will be established for each bar size and each splice position.
ANSI N45.2.9 As a minimum, a When records are submitted (Section 43) receipt control for storage, personnel system shall receiving the records are include procedures not subject to the for receipt and requirements of ANSI N45.2.6-inspection of 1978 nor Section 10.0 of this incoming records. Manual for inspection of incoming records.
ANSI N45.2.12 An individual audit For those routine audits (Section 4.2.1) plan describing conducted during operations, Entergy QA MANU AL OPERATIONS REV. 17 Operations DATE 07/22/94 OR TEE 1 PAGE TI-15 Arkansas Nuclear One
)
the audit to be a wTitten procedure (s) performed shall be covering each audit may be developed and utilized. Procedure (s)will documented by the identify the audit scope, auditing organiza- a requirement that indisidual tion. This plan checkli-is be utilized list-shallidentify the ing requirements which are to audit scope, the be audited and notification requirements, the of the audited group.
activities to be audited, organiza-tions to be notified, the applicable documents, the schedule, and written procedures or check-lists.
ANSI N45.2.13 The certificate The person attesting to a
(,/ (Section 10.2.d) should be attested ccitificate shall be an to by a person who authorized and responsible is responsible for employee of the supplier, this quality assur- and shall be identified by ance function and the Supplier.
whose function and position are described in the Purchaser's/
Suppliefs quality assurance program.
RG.1.64 (Section While design Consistent with the require-C.2)/ ANSI N45.2.11 verification by the ment of ANSI N45.2.11, designers immediate paragraph 6.1, design verifi-Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE I PAGE T1-16 ,
Arkansas Nuclear One
1
)
supervisor is en- cation may be performed by ccuraged,it should the originator's supenisor, 3 l I not be construed if the supenisor is the only that such verifi- individualin the organization cation constitutes competent to perform the the required inde- verification.
pendent design verification, . .
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A b O W Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE 1 PAGE TI-17 Arkansas Nuclear One s . .
_ _ _ _ _ . _ _ . .___J
1 I
ANSI N45.2.23 Certification of ANO considers holders of NRC- 1 (Section 2.3.1.3) competence in issued Reactor Operator /
engineering, Senior Reactor Operator )
sciences, or License to comply with the quahtyassurance requirements of the section specialties issued and may award two (2) credits and approved by a to those indisiduals. ,
State Agency, or f
National Professional or Technical Society, score two (2) credits.
1 O
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.:-: Entergy QA MANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE I PAGE TI 18 Arkansas Nuclear One
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TABLE 3 QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION 4 g MANUALS LIST
- 1. Quality Assurance Manual Ooerations The Quality Assurance Manual Operations establishes the policies and guidelines of the QA Program for ANO. This program is to be followed by all organizations involved in safety-related work applicable to ANO.
- 2. Overall Adminstrative Procedures The Nuclear Organization employs a system of procedures designated as Overall Administrative Procedures (OP-1000.XXX or OP-6000.XXX series). These procedures implement the QA Program requirements and control safety-related activities. Overall Administrative Procedures and changes thereto are prepared by the responsible department, reviewed by the Plant Safety Committee and approved by the Vice President, Operations ANO. The procedures and revisions are also reviewed by a Supervisor, Quality Assurance to assure that the QA Program commitments are met. Review and approval of Quality administrative procedures is described in paragraph 4 below.
- 3. Denartmental Procedures Each department (excluding Quality) within the Nuclear Organization has developed procedures in support of the Overall Administrative Procedures and the QA Program. These procedures provide technical and administrative instructions to the respective departments to aid in implementing their responsibilitia within the QA Program. Each Department Head is responsible to perform a review of their procedures to assure conformane, with the QA Program.
Procedures required by the Technical Specifications are reviewed and approved as described in paragraph 5.3.2 of this manual.
O V $.:-:. Entergy QA M ANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE 3 PAGE T3-1 Arkansas Nuclear One
i
- 4. Ouality Procedures l
The Quality Organization employs a system of procedures developed to assure proper implementation l of the QA Program. These procedures provide technical and administrative instructions to the Quality staff to aid in implementing their responsibilities within the QA Program. These procedures are reviewed / approved by a Supervisor, Quality Assurance, Supervisor, Quality Control, or Supervisor, NDE and the Director, Quality.
The Supplier QA organization employs a system of procedures developed to assure implementation of their responsibilities within the QA Program. Supplier QA management assures conformance with the QA Program.
C d
O aw Entergy QA M ANUAL OPERATIONS REV. 17 Operations DATE 07/22/94 SECTION: TABLE 3 PAGE T3-2 Arkansas Nuclear One
l 1
APPENDIX A l
QUALITY PROGRAM FOR TRANSPORT PACKAGES
1.0 INTRODUCTION
l.1 The quality program for transport packages containing radioactive material is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in 10CFR71, Subpart H - Quality Assurance, subject to exceptions noted in Attachment A to this Appendix.
1.2 Attachment A to this Appendix identifies the applicability of each section of the Quality Assurance Manual Operations to the Quality Program for Transport Packages.
1.3 Attachment B to this Appendix contains the Quality Assurance Program Approval document which shows NRC approval of this program on August 20,1991.
O V
b
/O QA MANUAL OPERATIONS REV.17 i V SECTION: APPENDIX A -QUALITY PROGRAM DATE 07/22/94 O nie g TRANSPORT PACKAGES PAGE AA 1 Operations Arkansas Nuclear One
A*ITACHMENT A 10CFR71 Appendix H The following sections of the most currently approved revision of the QA Manual Operations will be applied as stated below (Note specific paragraphs are to revision 10 paragraph numbers which could change during subsequent revisions).
Section 1 - Applicable Section 2 - Applicable Section 3 - Not applicable. ANO will use only licensed packaE ngi which has been designed under a QA program which has been submitted to the NRC for approval.
Section 4 - Applicable Section 5 - Applicable 9 Section 6 - Applicable Section 7 - Applicable i
Section 8 - Generally applicable except for paragraph 8.2.2 and 8.2.3. Due to size, uniqueness, low volume and the method of supplier identification of each package, ANO tagging of each package is not necessary.
Section 9 - Not applicable. We do not consider this subject as a "Special Process" in the context of I fj 10CFR71, Appendix H Section 71.119 which is a restatement of 10CFR50, Appendix B Criterion 9.
l l
l O QA MANUAL OPERATIONS REV. 17 DATE 07/22/94 SECTION: APPENDIX A - QUALITY PROGRAM Entergy TRANSPORT PACKAGES PAGE AA-2 Operations Arkansas Nuclear One
ATTACHMENT A (continued) 10CFR71 AppendixH Section 10 - Applicable Section 11 - Not applicable. ANO will not be testing the package in the context of 10CFR71, Appendix H, Section 71.123 which is a restatem:nt of 10CFR50, Appendix B Criterion 11.
Section '12 - Generally applicable except for paragraph 12.3.4. This paragraph only applies to Radiation Protection and Radwaste measuring and testing equipment that is used to calibrate other devices (used as a standard). Radiation Protection and Radwaste sun cy equipment is response checked prior to each use.
Section 13 - Generally applicable except for paragraph 13.5. ANO does not " store" packages, therefore the storage section does not apply.
Section 14 - Not applicable. See Section 11 comments above.
Section 15 - Generally applicable except for references to the various types of dispositions in ,
paragraphs 15.2.3 to 15.2.5. Nonconforming material or equipment will be returned to the vendor or will be replaced.
Section 16 - Applicable Section 17 - Applicable Section 18 - Applicable QA MANUAL OPERATIONS REV. 17 SECTION: APPENDIX A - QUALITY PROGRAM DATE 07/22/94 Entergy TRANSPORT PACKAGES PAGE AA-3 e nS Arkansas Nuclear One 4
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A*ITACHMENT B l ___ _ __,
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- Caos or asse es i asem onsesse t. own rt.wie a seneses en swe===se oas u _ ___ _ e.wisesse mene masm aor es asema se= e massa i i
s.me o,em, e ame ememe sesamies e asin s e asser aarmee we ese==i e emme e soissy se x- - aW i l vues a w com so.i rt.T= asymes as aunse a se aspense ames.=simeneas.o e e.er se n ses, assuses, ce===== a i i.
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i evasti amensas Janusey 31. 1995 i e Route 3. to: 137G
- 880'81 ma*** l l er,, lsvais isp eens i I,l Russel ,111 3 AR 3 7Pam 71.nu t i I, n ... . e- - asscas on. e vas, j lI Janua ry 12.1990. June 15.1990 and Anauet 7. teel
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l i i l' I h 1.
Activities 1
)
! criteria of conducted Appendia I with to 10regard CFR part to transportation 50 authertredpackages under a$ 1 cable by this approva l j j, procurement, maintenance, repair and use. All other activities (i.e., design, i
,1 fabrication, assembly, and sodification) shall be satisfied by obtaining i
,1 certifications from package suppliers that these activities were conducted in i l' accordance with an NRC approv1d R ram. It shall remata the responsibility l l
Il of the licensee-user prM ,
activities seet the requirements of 10 CFR 671.101. g l
[ 2. Records for e'ach paent of Itcensed maters.1I eeutrod by 10 CrA 71.s:(a) l
, -si he ,etain e, e ,eriod of three ,.ars. .1 l e O,4 i i k p i l
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QA MANUAL OPERATIONS REV.17 G & Operations O
SECTION: APPENDIX A -QUALITY PROGRAM TRANSPORT PACKAGES DATE 07/22/94 PAGE AA-4 )
Arkansas Nuclear One
APPENDIX B e QUALITY PROGRAM FOR FIRE PROTECTION
1.0 INTRODUCTION
1.1 The fire protection program was developed to define the organizational responsibilities, procedural controls, fire brigade stalling and training and the quality assurance provisions that have been established for the nuclear plant. The overall objective of the fire protection program is to minimize both the probability and conscquences of postulated fires and to maintain the capability to safely shut down the plant if a fire should occur.
1.2 The scope of the fire protection program includes those fire protection and detection systems, and those structures and components (such as fire doors, fire dampers, and penetration seals) which, as identified in the plant's Fire llazards Analysis Program Manual, are required to restrict the damage caused by a single exposure fire to safety-related equipment and equipment p required to achieve end maintain safe plant shutdown to within those limits set forth in Section 1 of Appendix R to 10CFR$0.
1.3 The quality program for fire protection is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in BTP-APCSB 9.5-1, Rev. 2. July 1981, Guidelines for Fire Protection for Nuclear Power Plants, subject to exceptions noted in this Appendix.
/
( 8 QA MANUAL OPERATIONS REV. 17 e Entergy SECTION: APPENDIX B - QUALITY PROGRAM DATE 07/22/94 Operations FOR FIRE PROTECTION PAGE AB-1 Arkansas Nuclear One
1.4 With respect to regulatory commitments, ANO is committed to implementing the requirements of the following, subject to exceptions noted in this Appendix:
{ l
- 1. 10CFR50, Appendix A, General Design Criterion 3 - Fire Protection.
- 2. Specific sections of 10CFR50.48, Fire Protection and 10CFR50, Appendix R. Fire Protection for Nuclear Power Facilities Operating Prior to January 1,1979. These sections are as follows:
Ill.G. Fire Protection Safe Shutdown Capability Ill.J. Emergency Lighting I!!.L. Alternative and Dedicated Shutdown Capability 111. 0 . Oil Collection System for Reactor Coolant Pumps 1.5 Other fire protection commitments are contained in the following references and documents:
l
- 1. Facility Operating License (s)
- 2. Safety Analysis Reports (SAR)
- 3. Fire Protection Safety Evaluation Reports (SER)
- 4. Regulatory correspondence to and from the NRC (includes applicable NRC generic letters and exemption letters for ANO).
1.6 The above requirements are implemented by controlling activities as described in this m:nual and Appendix and b) procedures referenced in this manual and Appendix.
(q)
/
QA MANUAL OPERATIONS REV. 17 g= Entergy SECTION: APPENDIX B -QUALITY PROGRAM DATE 07/22/94 Operations FOR FIRE PROTECTION PAGE AB-2 Arkansas Nuclear One
l 2.0 ORGANIZATION O 2.1 The organizational structure and responsibilities of key personnel associated with the administration, implementation and evaluation of the fire protection program are described in Section 1.0 of this manual and as follows:
- 1. The Vice President, Operations ANO is the management position which has the overall responsibility for the development, implementation and assessment of the effectiveness of the fire protection program. He reports directly to the Entergy Operations Executive Vice President and Chief Operating Officer.
- 2. The General Manager, Plant Operations is responsible for th overall administration and 5 implementation of plant operations and training in accordar : with the fire protection program.
He reports directly to the Vice President, Operations ANO.
- 3. The Manager, Standards is responsible for the establishment and monitoring of fire prevention aspects of the program at the plant including control of combustibles, ignition sources and postings, and is also responsible for the fire protection aspects of the program at the plant, such as evaluation of fire detection and suppression equipment, fire barriers and alternate shutdown equipment protection. The Manager, Standards reports directly to the Plant Manager, Unit 1.
The Manager, Standards is responsible for:
(1) Implementing, maintaining and assessing the fire prevention aspects of the program as defined in plant procedures (combustible controls, fire watches and fire drills)
(2) Performing fire protection evaluations (3) Developing inspection and surveillance criteria (4) Coordinating ANI. NRC, and other fire protection inspections at the plant (5) Providing guidance and technical support to the nuclear plant in the area of fire protection A
('" ) M QA MANUAL OPERATIONS REV. 17 "EJ' Entergy SECTION: APPENDIX B -QUALITY PROGRAM DATE 07/22/94 Operations FOR FIRE PROTECTION PAGE AB-3 Arkansas Nuclear One
(6) Assuring that applicable regulatory requirements are included in the fire
{
protection program (7) Assuring reviews for procedures & minor fire protection modifications are performed (e.g., plant changes and limited plant changes) ,
(8) Assuring Fire Protection Systems Engineering functions are performed ,
(suppression, detection, barriers, fire pumps and water supplies) f (9) Maintenance and revision of the Pre-Fire Plans 1
(10) Classification of F-list components for the Component Level F-list {
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- 4. The Manager. Engineering Programs is responsible for monitoring and oveniewing fire i
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protection programs and design fire protection modifications. The Manager, Engineering Programs reports directly to the Director, Design Engineering. Reporting to the Manager Engineering Programs is the Supervisor, Engineering Programs. Under his O direction are Fire Protection Engineers / Specialist / Technicians who are responsible for:
(1) Implementing, maintaining and assessing the fire protection aspects of the i program as defined in plant procedures 1
(2) Performing fire protection evaluations for the penetration seal program (3) Providing guidance and technical support to the nuclear plant in the area of fire l protection 1
(4) Assuring that applicable regulatory requirements are included in the fire protection program l
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i Assuring design reviews for fire protection modifications are performed I (5) 1 QA MANUAL OPERATIONS REV. 17
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1 (6) Assuring that evaluations / assessments of the fire protection program are performed and results reported to management (7) Maintenance and resision of the Fire Hazards Analysis (FHA) i (8) Classification of F list compenents for the Component Level F-list
- 5. The Director, Quality is responsible for assuring that the fire protection program is implemented in accordance with the QA Manual Operations, SAR and applicable procedures. This is accomplished by the performance of audits and other prosisions of the QA Manual Operations. He shall assure that corrective action, when necessary, is taken. He reports directly to the Vice President Operations ANO.
- 6. The Director, Licensing is responsible for providing other responsible organizations with regulatory information and interpretations on regulatory issues related to fire protection.
He is also responsible for providing interface with the NRC on fire protection matters, engineering evaluations and analysis of fire protection systems, as related to regulatory commitments and control oflicense-based documents relating to fire protection. He
/S reports directly to the Vice President, Operations ANO.
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- 7. The Director, Design Engineering is responsible for assuring that the technical requirements specified in the Operating License, Safety Analysis Report, and other design basis documents, with respect to fire protection, have been satisfied in design modifications and design documents afTecting ANO.
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l 3.0 OUALITY ASSURANCE PROGRAM
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b 3.1 This quality program is to ensure that the fire protection systems for safety-related areas (as dermed in paragraph 1.2 of this Appendix) are controlled in accordance with applicable NRC regulations, industrial standards and codes, policies, rules, procedures and licensing documents.
The quality program is implemented through approved procedures. The effectiveness of the fire protection program is verified through surveillances and scheduled audits conducted by the Quality Organization, under the cognizance of the SRC. General requirements for this program are also described in subsections 2.4 through 2.7 of this manual, except that personnel performing inspections need not be certified to ANSI N45.2.6, when inspections are performed on equipment not listed on the Q-list.
3.2 Employees whose duties and responsibilities are related to this fire protection program at or in
, support of the nuclear plant are to participate in appropriate training programs to assure that suitable proficiency is achieved and maintained in the work they are performing.
3.3 Fire protection training for plant personnel is included as part ofindustrial safety in the General Employee Training Program. Personnel are periodically retrained in industrial safety in
(] accordance with approved procedures. Personnel assigned to the plant Fire Brigade are to receive additional indoctrination and training to assure their capability to fight fires is established and maintained. The Manar,cr Training and Emergency Planning has the overall responsibility for these training programs.
4.0 DESIGN CONTROL 4.1 Section 3.0 of this manual is applicable for design control activitics pertaining to the fire protection system.
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5.0 PROCUREMENT DOCUMENT CONTROL 9 5.1 The control of procurement documents for fire protection-related materials, parts and cornponents is described in Section 4.0 of this manual with the exception of paragraph 4.2.3, when these items are not associated with the Q-list. The procurement document is to include the rquirement that items be U.L. listed or F.M. approved for fire protection use, where applicable, in accordance with approved procedures.
6.0 INSTRUCTION
S. PROCEDURE
S AND DRAWIN.Q.S 6.1 Inspections, tests, administrative controls, fir drills and training that govern the fire protection program are prescribed by documented instructions, procedures and drawings and are accomplished in accordance with these documents. Instructions. procedures and drawings are prepared, reviewed, approved and revised in accordence with approved procedures.
7.0 DOCUMENT CONTROL 7.1 Section 6.0 of this manual is applicable for the control of quality program documents related to fire protection.
8.0 CONTROL OF PURCHASED MATERIAL EQUIPMENT AND SERVICES 8.1 The control of purchased fire protection-related materials, equipment and senices is described in Section 7.0 of this manual, with the following exception related to subsections 7.2,7.3 and 7.5.
For the procurement of fire protection-related items or senices not associated with the Q-list, the vendor / contractor qualification criteria (including periodic reassessment of their program) is not reauired. Nonconformances dispositioned repair or use-as-is by the vendor are to be submitted to and accepted by ANO only when so designated on the procurement document.
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9.0 IDENTIFICATION AND CONTetOL OF M ATERIALS. PARTS AND COMPONEWS l I 9.1 Section 8.0 of this manual is not applicable for the identification and control of materials, parts and components related to the fire protection system. No particular requirements for this section
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j have been identified in BTP-APCSB 9.5-1, Rev. 2. The identification and control of materials, i parts and components are conducted in accordance with existing procurement and materials management procedures and practices.
10.0 CONTROL OF SPECI AL PROCESSES l
1 10.1 Section 9.0 of this manual is not applicable for the control of special processes, as applicable to l i fire protection systems. No particular special process controls have been identified by BTP-APCSB 9.5-1, Rev. 2. The control of special processes for the maintenance of the fire protection system is performed in accordance with applicable approved procedures and practices.
I 1.0 INSPECTION 1 11.1 Inspection activities rpplicable to the fire protection system are described in Section 10.0 of this manual with the exception of paragraphs 10.2.2 and 10.3.2.3, when inspections are performed l l on equipment not associated with the Q-list. The Regulatory Guides referenced in paragraph 10.2.2 are not applicable to the fire protection system. Individuals outside the Quality Organization who perform inspections only need to meet paragraphs 10.3.2 and 10.3.2.1.
In addition to the provisions of this taanual, inspections and surveillances are addressed in applicable portions of the SAR for each nuclear unit.
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12.0 TEST CONTROL O 12.1 A test program is to be established and implemented to ensure that testing is performed and verified on applicable systems and components to demonstrate conformance with design and system readiness requirements. The tests are to be performed in accordance with written test procedures and test results evaluated for conformance to the test objectives.
12.2 The control of testing activities is described in Section 11.0 of this manual. Surveillance testing requirements are identified in the Safety Analysis Report for each nuclear unit.
13.0 CONTROL OF MEASURING AND TEST EGUIPMENT 13.1 Section 12.0 of this manual is not applicable for the control of measuring and test equipment.
No particular measuring and test equipment controls have been identified in BTP-APCSB 9.5-1, Rev. 2. Measuring and test equipment is controlled in accordance with applicable approved procedures and practices.
14.0 HANDLING STORAGE AND SHIPPING b
14.1 Section 13.0 of this manual is not applicable for the handling, storage and shipping of fire protection-related materials and equipment. No particular requirements for this section have been identified in BTP-APCSB 9.5 1, Rev. 2. Handling, storage and shipping activities are controlled in t.ccordance with applicr' ie approved procedures and practices.
15.0 INSPECTION. TEST AND OPERATING STATUS 15.1 Measures are established to provide for the identification ofitems that have satisfactorily passed required inspections and tests and are documented per approved instructions or procedures.
15.2 Section 14.0 of this manual is applicable for identifying the inspection, test and operating status of the fire protection system.
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I 16.1 The control of nonconforming materials, parts and components related to the fire protection system is described in Section 15.0 of this manual, with the exception of subsection 15.3, when j q ,
the item is not associated with the Q-list. Vendor nonconformances are to be submitted to ANO only when so designated on the procurement document.
17.0 CORRECT 7VE ACTIONS 17.1 A corrective action system is established to ensure that conditions adverse to fire protection, such as failures, malfunctions, deficiencies, desiations, defective components, uncontrolled combustible materials and nonconformances, are promptly identified, reported and corrected.
17.2 Corrective action activities are controlled as described in Section 16.0 of this manual, with the following exception related to subsection 16.3. Vendors furnishing fire protection items not associated with the Q-list are not required to be listed on the QSL.
18.0 OUALITY ASSURANCE RECORDS 18.1 Records which furnish evidence that the criteria enumerated in this program are being met for activities affecting the fire protection program are to be prepared and maintained as described in Section 17.0 of this manual.
19.0 AUDITS 19.1 Audits are to be conducted and documented to verify compliance with the fire protection program, including design and procurement documents. instructions, procedures and drawings and inspection and test activities. Section 18.0 of this manual is applicable for the control of audits related to the fire protection program.
19.2 As a minimum, the following audits of the fire protection program are to be scheduled at the indicated frequencies:
- a. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
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- b. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel g
or an outside fire protection firm.
- c. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.
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