ML20076C795
| ML20076C795 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/22/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20076C793 | List: |
| References | |
| NUDOCS 9107240315 | |
| Download: ML20076C795 (170) | |
Text
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O ARKANSAS NUCLEAR ONE D11AllTY ASSURANCE MANUAL OPERAUMS REVISION 13 APPROVED:
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MANAGER,'QUAllIY ASSURANCE APPROVED:
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GENERAllJANAGER,'QUALIT(/
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APPROVED:
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VICEtRESIDENT,OPERATiONSANO QA MANUAL OPERATIONS REV. 13 W Entergy DATE 05/01/91 Operations SECTION:
APPROVAL SIGNATURES
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Arkansas tJuelear One ADOCK0500t)g3 DR j
l TABLE OF CONTENTS SECTION-il)B1EGI PAGES REY APPROVAL COVERSHEET N/A 13 RECORD OF REVISIONS RR-1 to RR-36 13 i
TABLE OF CONTENTS TC-1 to TC-4 13 POLICY STATEMENT A-1 to A-3 13 INTRODUCTION B-1 to B-6 12 TERMS AND DEFINITIONS C-1 to C-11 13 1.0 ORGANIZATION 1-1 to 1-27 13 O
2,0 QUALITY ASSURANCE PROGRAM 2-1 to 2-9 13 3.0 DESIGN CONTROL 3-1 to 3-6 13 4.0-PROCUREMENT DOCUMENT 4-1 to 4-3 13 CONTROL 5.0 INSTRUCTIONS, PROCEDURES 5-1 to 5-3 13 AND DRAWINGS 6.0 DOCUMENT CONTROL 6-1 to 6-3 13 7.0 CONTROL OF PURCHASED 7-1 to 7-7 13 MATERIAL, EQUIPMENT AND SERVICES i
- h. Entegy QA MANUAL OPERATIONS REV.
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TABLE OF CONTENTS PAGE TC-1 Arkansas Nuclear One
TABLE OF CONTENTS ALEllDU-SUBJECI PEES REY t
8.0 IDENTIFICATION AND CONTROL 8-1 to 8-3 13 0F MATERIALS, PARTS AND COMPONEN15 9.0 CONTROL OF SPECIAL 9 1 to 9-2 13 PROCESSES 10.0 INSPECTION 10-1 to 10-6 13 11.0 TEST CONTROL 11-1 to 11-5 13 12.0 CONTROL OF MEASURING AND 12-1 to 12-4 13 TEST EQUIPMENT 13.0 ilANDLING, STORAGE AND 13-1 to 13 5 12 SHIPPING 14.0 INSPECTION, TEST AND 14-1 to 14-5 13 OPERATING STATUS 15.0 NONCONFORMING MATERIAL.
15-1 to 15 4 12 PARTS OR COMPONENTS 16.0 CORRECTIVE' ACTION 16-1 to 16-3 13 17.0 QUALITY ASSURANCE RECORDS 17-1 to 17-5 12 18.0 AUDITS 18-1 to 18-6 13 O
- a. = Entergy QA MANUAL OPERATIONS REV.
13 operations DATE 05/01/91 SECTION:
TABLE OF CONTENTS PAGE TC-2 Arkansas Nuclear One
TABLE OF CONTENTS SECTION 10Blf11 EAGES BEV FIGURE 1 AND CORPORATE ORGANIZATION F-1 13 FIGURE 2 NUCLEAR OPERATIONS DEPARTMENT F-2 13 FIGURE 3 UNIT 1 OPERATIONS ORGANIZATION F-3 12 FIGURE 4 UNIT 2 OPERATIONS ORGANIZATION F-4 13 FIGURE 5 QUALITY DEPARTMENT F-5 13 FIGURE 6 ENGINEERING DEPARTMENT F-6 13 FIGURE 7 NUCLEAR SUPPORT DEPARTMENT F-7 13 O
FIGURE 8 MATERIALS mat lAGEMENT DEPARTMENT F-8 12 FIGURE 9 LICENSING DEPARTMENT F-9 13 TABLE 1 ANO EXCEPTIONS / INTERPRETATIONS T1-1 to T1-28 10 0F REGULATORY Gul0ES AND ANSI STANDARDS TABLE 2 QUALITY ASSURANCE T2-1 13 PROCEDURES MATRIX TABLE 3 QUALITY PROGRAM POLICIES, T3-1 to T3-2 13 PROCEDURES AND INSTRUCTION MANUALS LIST
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ntergy QA MANUAL OPERATIONS REV.
13 q357 E DATE 05/01/91
()perations SECTION:
TABLE OF CONTENTS PAGE TC-3 Arkansas Nuclear one
1 TABLE OF CONTENTS SEC110B -
SUBJECT PAGES BEY APPENDIX A QUALITY PROGRAM FOR AA-1 to AA-4 12 TRANSPORT PACKAGES APPENDIX B QUALITY PROGRAM FOR AB-1 to AB-12 13 FIRE PROTECTION f
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Entergy QA MANUAL OPERATIONS Operat ons E
/01/91 SECTION: TABLE OF CONTENTS PAGE TC-4 Arkansas Nuclear One
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RECORD OF REVISIONS O
REVISION NUMBER DESCRIPTION DAlf 0
Initial Issue 6/11/74 1
Respnnse to AEC questions submitted 12/13/74 11/21/74. Revisions to Section 2, 4, and 7 as indicated.
2 Response to NRC questions submitted 3/4/75 2/7/75. Procedure numbers 1005.xx changes to 1004.xx (number change only).
3 General revision to change AEC to NRC, 9/8/76 update organization, reflect NSP revisions, minor program implementation changes.
4 Eliminate Quality Assurance Committee 9/8/77 changes to Procurement Control -
Qualification of Vendors.
Organizational changes.
Incorporate Technical Specification changes.
5 Incorporate organizational changes 10/10/80 and responses to subsequent NRC O.
questions.
Incorporate Regulatory Guides and retype document in its entirety in standardized format.
6 Incorporate organizational changes, 5/30/84 delete procedural references throughout manual, and accurately.
reflect current regulatory commitments and QA practices related to the safe operation of AP&L nuclear plants.
Manual has been reformatted and retyped in its entirety.
7 Changes given below are identified 5/31/85 on the pages by a bar in the left margin, placed next to the affected area.
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 3-3 13-2 T3-1 g Entergy-QA MANUAL OPERATIONS REV.: 13 DATE: 05/01/91 Operations SECTION: RECORD OF REVISIONS PAGE: RR-1 Arkansas Nuclear One
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.- - s-
'tECORD OF REVISIONS REVISION
(
NUMBER DESCRIPTIDN DAIE 7(Cont.)
1-12 3-4 13-4 T3-2 i
1-18 4-2 15-2 T3-3 1-19 5-2 15-3 1-20 5-3 15-5
+
1-22 5-4 15-4 1-23 6-2 16-1 7-2 T1-6 9-1 Page C 7: revised definition Page C-8: revised definition Page 1-9: revised paragraph 1.4.2(1)
Page 1-10: revised paragraph 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 revised Page 1-12: paragraph 1.4.2.3.1 redesig-nated 1.4.2.2.1 Page 1-13:added 7) to paragraph 1.5.1.3 Page 1-14 & 15: revised paragraph 1.5.3 i
to delete Planning / Scheduling Supervisor O
Page 1-21:added paragraph 1.5.8 Pages 1-1 to 1-23: paragraph locations changed Page 2-2: paragraph 2.2.2 redesignated 2.2.3 and revised 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: revised paragraph 2.2.5(2)
Page 2-7 and 2-8: revised paragraph 2.6.4 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: paragraph locations changes Page 15-1: revised paragraph 15.2.1 Page 18-3: revised paragraph 18.3.2 Pages 18-3 to 18-6: paragraph locations changes Page F-1: revised Figure 1 g Enterg!f QA MANUAL OPERATIONS REV.: 13
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DATE: 05/01/91 Operat ons SECTION: RECORO OF REVISIONS PAGE: RR-2
- Arkansas Nuclear One
RECORD OF REVi,!aNS I
REVISION iMiEfjL.
DESCRIPTION pg 7 (Cont.)
Page F 2: revised figure 2 Page F-3: revised Figure 3 Page F-5: revised Figure 5 Page F-6: revised figure 6 Page T2-1: revised titles Page Ab1 to AA-3: new Appendix A added Page AB-1 to AB-8: new Appendix B added 8
Changes given below are identified 6/10/86 on the pages by a bar in the left inargin, 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 3-5 15-1 17-4 AB-11 4-1 O
Page A-1
- Revised 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 to 1-23 new organization Page 2-1
- Revised paragraph 2.2.1
- Added paragraph 2.2.2 Page 2-2
- Paragraphs 2.2.3 and 2.2.4 were,,'.2 and 2.2.3
- Reviseo paragraphs 2.2.3 and 2.2.4 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
- Paragraph 2.3.1, title change QA MANUAL OPERATIONS REV.: 13 E=== Entergy DATE: 05/01/91 Operations SECTION: RECORD OF REVISIONS PAGE: RR-3 Arkansas Nuclear One
RECORD OF REV1510NS O
REV1510N NLMEIL_
DESCRIPTION DAIE 8 (Cont.)
Page 2-4: Title changes, paragraphs 2.3.3 and 2.3.4 Revised paragraph 2.4.1 Page 2-5: Title changes, paragraphs 2.4.3, 2.5.1, 2.5.2 Page 2-6: Revised paragraph 2.5.2 and 2.6.1 Title change, paragraph 2.5.3 Page 2-8: New paragraph 2.6.5 added Paragraph 2.6.7 was 2.6.6 Revised pcragraph 2.6.7 & 2.7.1 Page 2-9: Title change, paragraph 2.7.2 Page 3-1: Revised paragraph 3.2.1 Page 3-2:
Title changes, paragraph 3.4.1 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 Page 5-2: Revised paragraph 5.3.1 Title changes, paragraph 5.2.2 and 5.3.2 Page 5-4: Revised paragraph 5.4.2 Page 6-1: pevised paragraphs 6.1 & 6.2.2 O
Page 6-2: Title change, paragraph 6.2.3 Added paragraph 6.2.4 Page 7-1: litle changes, paragraphs 7.2.1
& 7.2.2 Page 7-3: Revised 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: Revised 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
& 15.2.2 l
h Entergif QA MANUAL OPERATIONS REV.: 13 DATE: 05/01/91 Operat ons SECTION:
RECORD OF REVISIONS PAGE: RR-4 Arkansas Nuclear One
m RECORD OF REV1510NS REVISION WMER__
DESCRIPTION DALE 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 revisions 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: Subtection 16.4 was 16.3 Revised paragraph 16.4(1) & (3)
Subsection 16.5 was 16.3.2 and O
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 Revised organization charts Thru F-8 Page T1-1: Revised first paragmph, third column Page T1-2: Add ANSI N18.7 (Sections 5.2.7.1)
Page T1-3: Add ANSI N18.7 (Section 5.2.17)
Page T2-1: Revised Table 2 Page T3-1: Revised all paragraphs Page T3-2: Revised all paragraphs Page T3-3: Deleted QA MANUAL OPERATION 5 REV.: 13 5 :: Entergy DATE: 05/01/91 Operations SECTION:
RECORD OF REVISIONS PAGE: RR-5 Arkansas Nuclear One
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DAlf 8(Cont.)
Page AA-1: Revised paragraph 1.1 Page AA-2: Revised introductory paragraph Page AA-3: Revised Section 12 Page AA-4: Added Page AB-3: Title change, paragraph 2.1(1)
Revised paragraph 2.1(2)
Page AD-4: T.cle changes, paragraphs 2.1(3)
(4) & (5)
Page AB-5: Revised paragraph 2.1(6) & 2.1(8)
Title changes, paragraph 2.1(7)
Page AB-7: Revised paragraph 5.1 All pages in Manual: Title block revised 9
Changes given below are identified on 7/22/87 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:
B-5 C-10 10-5 C-1 1-4 AA-2 O
C-2 5-4 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 Commitments Page C-1: Added definition Page C-3:
Revised definition and added new 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 QA MANUAL OPERATIONS REV.: 13 W Entergy DATE: 05/01/91 Operations SECTION: RECORD OF REVISIONS pAGE: RR-6 Arkansas Nuclear One
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DAI.E 9 (Cont.)
Page 1-14: Revised responsibilities within paragraphs 1.4.1.3.2.1 and 1.4.1.3.2.3 Page 1-15: Changed name title Pages 1-15 thru l-16: Revised responsibilities in p3ragraphs 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 Page 1-18: Delete 1.4.1.3.3.e and changed name _' title Page 1-19: Clarified paragraph Page 1-20: Revised responsibilities Page 1-21: Revised responsibilities in paragraph 1.4.2.2 Pages 1-21 thru l-23: 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 G
Page 2-1: Revised paragraph 2.2.1 V
Page 2-3: Revised paragraph 2.2.5 and Added paragraph 2.2.6 Page 2-4: Changed name title 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 Page 3-5: Changed name title Page 4-1: Changed titles 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:. Revised paragraph 6.2.4 Page 7-2: Revised paragraphs
'.2(1) and 7.2.2(5). Deletsd paragraph 7.2.2(6)
Page 7-5: Revised paragraph 7.4.3 Page 10-3: Revised paragraph 10.3.2.2 Page 10-6: Revised paragraphs 10.5.2 and 10.6 Page 11-3: Title changes Page 13-2: Revised paragraph 13.3.2 g Entergy
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QA MANUAL OPERATIONS REV.: 13 2.
DATE: 05/01/91 Operat onS SECTION:
RECORD OF REVISIONS PAGE: RR-7 Arkansas Nuclear One
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RECORD OF REVISIONS p
REVISION v
NUMBER
.0,ESCRIPTIQH QAlE 9 (Cont.)
Page 13-4: Revised parsgraph 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.
Revised 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 to Table 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 The following pages were revised due to format changes:-
w C-4 1-11 2-6 AB-8 1-5 1-12 2-7 AB-9 1-6 1-23 2-8 AB-10 1-7 2-2 AB-6 AB-11 1-8 2-5 AB-7 AB-12 10 Retype manual in its entirety on new pages; 8/31/88 also made grammatical corrections (including misspelled words and punctuations throughout).
L 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 "AN0" in the following sections:
i g Entergy QA MANUAL OPERATIONS REV.: 13 e.
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v.v.., -.,
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a m
RECORO OF REVISIONS REVISION O
NUMBER DEICRIPTION DAIE 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 3.7 i
Page #-1: Section 4.2.1 I
Page 4-2:
Section 4.2.3 Page 5-1: 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 i
f
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 T1-2: ANSI N18.7 Page TI-9: R.G. 1.58 Page T3-1: #1 & #2 Page AB-1: Sections 1.1 & 1.2 Page AB-2: Sectior 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 l
Page AB-11: Sections 16.1 & 18.1 l
"AN0", " Plant", "LRG0" and " Departmental" l
was deleted or replaced with " Approved" in the following sections:
g Entergy l-t QA MANUAL OPERATIONS REV.: 13 e
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RECORD OF REV1510NS O
REVISION NUMBER DESCRIPTIQB DJJE 10 (Cont.)
Page 2-3:
Sections 2.2.4 & 2.2.6 Page 2-4:
Section 2.3.2 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 3-1:
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 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 Page 7-6:
Section 7.4.6 Page 7-7: Sections 7.5.2 & 7."
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: Sections 9.3.2 & 9.4 Page 9-3:
Section 9.5 Page 10-3: 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 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 Page 15-3: Section 15.2.6 Page 16-1: Section 16.2.1 Page 16-2: Sections 16.2.3 & 16.3 Page 16-3: Section 16.5.2 Page 17-1: Section 17.1.2 h
QA MANUAL OPERATIONS REV.: 13
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RECORD OF REVISIONS O
REVISION iMfL DESCRIPTION DALE 10 (Cont.)
Page 17-3: Sections 17.3.1.2, 17.3.2.2 &
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 T3-1: #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" 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 2-7:
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 18-1: Sections 18.1.2 & 18.2.1 Page 18-4: Section 18.4.2 Page T1-1: Heading Page T3-2: #4 & #5 Other specific changes as follows:
Page A-1:
1st Paragraph, Revised 1st sentence g Entergy QA MANUAL OPERATIONS REV.
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Operations SECTION:
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RECORD OF REVISIONS REVISION 4
EMBER..
_DESCRIPTIQ8 DAIf 10 (Cont.)
Page A-1: 2nd Paragraph, Revised titles Page-A-2:
1st Paragraph, Revised responsibility Page B-1:
1st Paragraph, Revised 1st sentence Page B-5: ASME Section III, Updated code edition Page B-5: ASNT SNT-TC-1A-1980, Added Sentence Page B-5: Revised "*" Sentence Page C 4: Added "F-List" Definition Page C-7: Modified Definition Page J-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, Revised responsibilities in last sentence Page 2-2:
Section 2.2.3, Added " quality" O
Page 2-3:
Section 2.2.5, Revised
\\
responsibilities, 1st, 2nd
& last sentence Page 2-3:
Section 2.2.6, Revised 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,-Revised section Page 2-7:
Section 2.5.2, Revised first 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, Revised responsibilities Page 3-4:
Section 3.4.4, Revised responsible organization
'j g Entergy OA MANUAL OPERATIONS REV.
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RECORD OF REVISIONS n
REVISION-G NUMBER DESCRIPTION DAIE i
-10(Cont.)
Page.3-4: Section 3.5.1, Revised responsible organization 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 "off-site" Page 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, Revised 1st sentence Page 5-4: Section 5.4.2, Revised responsibilities Page 6-1:
6.2.2 Revised title Page 6-2:
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 O
Page 7-3: Section 7.2.3, Revised 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, Revised responsibilities Page 8-3: Section 8.3, Revised section Page 9-3:
Section 9.5, Added " review" &
title 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, Revised section Page 11-5: Section11.3.7, Revised section Page 12-2: Section 12.2.3, Revised 1st-sentence
-Page 13-4: Section 13.5.5, Title change Page 14-1: Section 14.2.1 Title change g Entergy -
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i RECORD OF REVISIONS REVISION O
NUMBER DESCRIPTION DAIE 10 (Cont.)
. Page 14-3: Sections 14.2.5 & 14.2.6, Title change Page 14-4: Section 14.3.2, Revised responsibilities & title change Page 14-5: Section 14.4.1, Title change Page 15-2: 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" & revised 3rd sentence Page 16-2: Section 16.3, Revised responsibilities Page 16-3: Section 16.5, Revised heading Page 16-3: Section 16.5.1, Revised heading Page 16-3: Section 16.5.2, Revised O-responsibilities-Page 16-4: Section 16.5.4, Revised section Page 17-1: Section 17.1.1, Added " operation" ist sentence Page 17-1: Section 17.1.2, Added
" maintenance" and " personnel experience" Page 17-1: Section 17.1.2, Revised last sentence Page 17-2: Section 17.2.2, Revised responsibility Page 17-3: Section 17.3.1.2, Revised section Page 17-4: Secticn 17.3.4, Revised responsibilities Page 17-4: Section 17.4.1, Revised section Page-17-4: Section 17.4.2, Revised section 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 g Entergy QA MANUAL OPERATIONS REV.: 13 DATE: 05/01/91
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REVISION
. NUMBER DESCRIPTION DALE 10(Cont.)
Page 18-5: Section 18.4.4, Revised section Page 18-5: Section 18.5, Revised responsibility Page F-1 to F-7: Updated Figures Page T1-2: Added ANSI N18.7 (Section 5.2.7)
Page T1-5: Added ANSI N45.2.2 (Section 6.4.2)
Page T1-15
& T1-16: Added ANSI N45.2.9 (Section 4.3)
Page T1-17:Added ANSI N45.2.23 (Section 2.3.1.3)
Page T1-18:Added AWS D1.1 (Section 5.2.8.4)
Page T2-1: Updated matrix Page T3-1: Revised #2 & #3 Page T3-2: Revised responsibilities #4 & #5 8
Page AB-2: Revised Section 1.5, #4 Page_AB-3: Revised Section 2.1, #2 & #3 Page AB-5: Revised Section 2.1, #5, #6 & #7 to #4, #5 & #6 Page AB-6: Changed "QA" to "NQ" Pige AB-6: Section 3.3, Revised 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 punctuations on the following pages:
A-1 2-10 14-3 B-1 3-1 14-5 1-1 3-4 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.
2-4 13-1 AB-6 2-5 14-1 AB-9 2-6 g Entergy QA MANUAL OPERATIONS REV.: 13 DATE: 05/01/91 Operations SECTION: RECORD OF REVISIONS PAGE: RR-15 Arkansas Nuclear One
RECORD OF REVISIONS p
REVISION Q
NUMBER DESCRIPTION DAIE 11 (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 Reg. Guide 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 Organization structure Page 1-23: 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 ti+.le, 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 Page 2-3: Section 2.2.6 changed 2nd sentence to reflect Engineering Coasolidation under New Organization Section 2.2.2 cha.ged 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 changed 1st and 4th sentences to reflect Engineering Consolidation under New Organization QA MANUAL OPERATIONS REV.: 13 W Entergy DATE: 05/01/91 Operations SECTION:
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@MBER DESCRIPTIDS DE 11 (Cont.)
Page 3-2:
Section 3.3 changed 1st. sentence to reflect Engineering Consolidation under New Organization I
Section 3.4.1 changed 1st.
sentence to reflect Engineering l
Consolidation under New Organization, replaced
" organization" with " engineering section" in 2nd sentence Page 3-3:
Section 3.4.2 1st 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
'! organization" with "section" Section 3.7 changed title
'0 Page 5-1:
Section 5.1.1 added "Rev 2" last sentence Page 5-2:
Section 5.3.2 revised section Page-5-3:
Section 5.4.2 revised section Fage 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)"
-1st 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 g Entergy QA MANUAL OPERATIONS REV.: 13
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REVISION NUMBER DESCRIPTION DAIE 11(Cont.)
Page 12-3: Section 12.3.3 changed " National Bureau of Standards" to new name Page 13-2: Section 13.3.2 changed titles 2nd and 3rd sentences Page 14-1: Section 14.2.1 added " appropriate" ist sentence Page 14-4: Section 14.3.1 added " appropriate" 1st and last sentences 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 " Quality Assurance" to " Nuclear Quality" Page=15-4: Section 15.5 revised section Pege 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" Page 17-1: Section 17.2.1 changed title 1st sentence Page 17-5: Section 17.5.2.'1 changed title 1st sentence Section 17.6 changed title 1st sentence Page 18-4: Section 18.4.1 revised 2nd sentence Page 18-5: Section 18.4.4 revised 1st and L
2nd sentences Page 18-6: Section 18.6 revised section Pages F-1 to F-2: Revised organization char _ts Page T2-1: Revised table 2 i:
Pages T3-1 to T3-2: Rewrote' Table 3 to reflect new organization Page AA-3: Section 12 revised titles 1st and 2nd sentences g Entergy QA MANUAL OPERATIONS REV.: 13
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NUMBER DEICAIP_Il0B DAIE 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 ounctuation errors on the following pages:
A-1 1-16 14-1 A-2 1-17 14-3 B-1 1-18 14-4 1-1 1-19 14-5 1-2 1-20 15-2 9
1-3 1-21 15-4 1-4 1-22 16-3 1-5 1-23 16-4 1-6 1-24 18-2 1-7 2-3 18-5 1-8 2-5 AB-3 1-9 2-6 AB-4 1-10 2-7 AB-5 1-11 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:
Page A-2, 1st Para.
Page 1-1, Sect. 1.3, 1st Para.
Page 2-4, Sect. 2.3.1 Page AB-3, Sect. 2.1(1) lh AdBk QA MANUAL OPERATIONS REV.
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REVISION d
NUMBER DESCRIPTION DAIE 12 (Cont.)
Figure numbers were changed or added at the following locations to reflect new numbers resulting from addition of 2 new figures:
Page 1-2, 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 2-6 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 1-22 14-5 T3-2 F-5 1-3 1-11 1-23 15-2 AB-3 F-7 1 1-24 15-4 F-8
" Superintendent Quality Control / Quality n
Engineering" was changed to " Manager, G
Quality Control / Quality Engineering" on the following.pages:
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1-9 1-11 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-;0 13-4 1-12 16-2 2-3 17-4 2-5 18-1 2-6 18-2 f3
, C/
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NUMBER DESCRIPTION DAIE 12 (Cont.)
2-7 18-4 2-10 18-5 7 18-6 7-4 T3-1 T3 Page A-1: Revised responsibilies in second paragraph to reflect Entergy Operations consolidation.
Page B-5: Changed 4th and 8th paragraphs to update ASME Code commitments for Inservice Inspection and Repair / Replacement; changed 5th paragraph to update SNT-TC-1A commitment from 1980 to 1984.
Page C-6: Removed reference to construction from definition of "0wner".
Page 1-1:
Section 1.1, Added "and Entergy Operations, Inc.'s (Entergy Operations)"; Section 1.2, replaced O
" Ultimate" with_"On-site"; Section U
1.3, deleted "All.
Page 1-2:
Section 1.3 (1) f, changed 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 Page 1-4:
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 responsibilities-l 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, O
a Entergy o^ "^"ux' Oeea^11o"S aev.: 15
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("
REVISION
(
NUMBER DESCRIPTIRB D21E 12 (Cont.)-
Page 1-6: new section developed to describe planning and scheduling functions; Section 1.3.1.2, Deleted " Operations" from title in two places and revised responsibilities.
Page 1-6:
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 "Manaaer, Central Support";
changed supervisory 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, chaiged title, deleted " Operations." Section 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 l
"various".
I Page 1-10: Section 1.3.2.1 (3) and (5),
reworded for clarification.
l Page 1-12: Section 1.3.3, Functional and responsibilities and position 1
Page 1-13: titles reporting to the General Manager, Engineering changed to reflect 2/1/90_ on-site reorganization.
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RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DAll v
12 (Cont.)
Page 1-14: Section 1.3.3.3, changed to described functional responsibi-lities of Manager, Engineering Support, a new title created by 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, O
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; 8
QA MANUAL OPERATIONS REV.: 13 s Entergy DATE: 05/01/91 Operations SECTION:
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.O REVISION
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NUMBER DESCRIP1108 Q&lE 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, revised and responsibilities 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 Services; Page 1 19: Responsibility ~for Computer Support has been assigned to the Manager, Engineering Support, responsibility for Office Services and Human Resources has been assigned to the General Manager, Nuclear Support, 1-and responsibility for Materials Management assigned to the General Manager,-Materials Management.
Page 1-17: Section 1.3.4.2 (was 1.3.4.3 in and Rev. 11) 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. 11), changed " Manager Industry Event Review" to " Manager, Industry Events Analysis."
Page 1-19: Section 1.3.4.3 (was 1.3.4.4 in Rev. 11), chtnged-" Manager Training" to " Manager, Training and_ Emergency Planning."
g Entergy QA MANUAL OPERATIONS REV.: 13
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RECORD OF REVISIONS REVISION HUMBER DESCRIPTION-DAIE 12-(Cont.)
Page 1-19: Section 1.3.4.4 (was 1,3,4.5 in Rev. II), changed." Superintendent-Security" to " Manager, Security" Section 1.3.4.5 (in Rev. 11) 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).
Page 1-20: Section 1.3.6, added section to and describe the functional
\\
Page 1-21: responsibilities-of the new position General Manager, Materials Management, d
Page 1-21: Section 1.3.7, changed from 1.3.6 2
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 j -
1_.3.6.3 Page 1-22: Section 1.4 and 1.5, complete thru
-re-write, due to Entergy 1-25:
Operations consolidation.
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NUMBER DESCRIPTION QAIE 12(Cont.)
Page 2-5:
Section 2.3.4, change " Nuclear Design Services" to " Nuclear Engineering Design"; added onsite Quality Control of Nuclear Fuel as a " Responsibility of System Engineering";
Removed responsibility-for assurance that Nuclear Fuel used at ANO is designed, procured, manufactured and utilized in accordance with regulatory requirements, and related industrial codes and standards from the Superintendent Reactor Engineering.
The Supervisor, Core Reload Design is now responsible <for this.
Page 2-6:
Section 2.4.3, deleted section as a result of Entergy Operations consolidation.
O 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 L
Administrative Services"~to Manager, Office' Services" to i
reflect the 2/1/90 on-site reorganization, and combined 1st t
i and 2nd sentences for clarity.
Page 4-2:
Section 4.3, replaced "all" with
" safety related", for clarity.
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REVISION NUMBER DESCRIPTION DAIE 12 (Cont.)
Page 6-1: Section 6.2.3, changed " Manager Administrative Services" to
" Manager Office Services 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 7.4.2 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 O
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 clarity.
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.: 13 5E Entergy DATE: 05/01/91 Operations SECTION:
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RECORD OF REVISIONS 7
REVISION A
NUMBER
-DESCRIPTION Dale 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, Divided responsibilities of " Manager ANO Engineering" between " Manager, 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 O-significant conditions from d
responsibility of the department heads, full responsibility assigned to Licensing Department.
l 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 Services" to ll
" Manager, Office Services."
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 Services" to " Manager, Office Services."
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REVISION
_U NUMBER-DESCRIPTION Q&IE 12(Cont.)_
Page 18-4: Section-18.4.1, add "or his designee" in 2nd line.
Page 18-6: Section 18.6, revised organizational 1
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.
Section 2.1 (3) (7), deleted, Licensing Department.is responsible for ANO commitments, identification ana tracking.
See Section 2.1 (5):
Section 2.,1 (3) (8), deleted responsibility for performing safety evaluations for modifications. This is the
. responsibility of the General Manager, Engineering.
See L
Section 2.1;(6);
_Section 3.3, changed responsibility for training to the Manager, Training snd Emergency Planning.
l l-
-Page AB-4: Section 2.1 (3), " Superintendent Engineering Services" changed to
" Superintendent, Engineering Programs."
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-NUMBER DESCRIPTION DAIE 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.
Page 1-3: Section 1.3.1,_ changed title to Manager, Standards / Executive
. Q 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
, ~ -
L Department and Computer Support l
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.l.2.1, added Computer Support and Work History under Manager, Central Support.
Section 1.3.1.2.2, changed from Manager to Supt., Chemistry-and Radiochemistry.
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O REVISION NUMBER QELCRIPTION DA1E 13 (Cont.)
Page 1-8:
Sections 1.3.1.2.4 & 1.3.1.2.5 now shown under Manager, Plant Central.
Deleted descriptions given in 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, Administra-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 Emergenc.'. Planning.
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.
O QA MANUAL OPERATIONS REV.
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REVISION.
NUMBER DESCRIPTION DAIE 13 (Cont.)
.Page-1-14: Section 1.3.2.3, Manager, Plant Assessment now shown under General Manager, Quality. Deleted examples of areas under Assessment.
Section 1.3.2.3.1 & 1.3.2.3.2 shown as reporting to Manager, Plant Assessment.
Section 1 3.2.3.2 redefined how to accomplish responsibilities.
Page 1-15: Section 1.3.2.3.2, redefined 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.
O 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-Review Officer.
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.
Page-1-21: Section 1.3.7.1, description of "offsite" independent review deleted.
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RECORD OF REVISIONS PAGE: RR-32 Arkansas Nuclear One
RECORD OF REVISIONS q
REVISION h
NUMBER Df1CRIPT10N DAlf 13(Cont.)
Page 1-25: Section 1.4.4, added as per and 1-26: Supplier QA Organization change.
Section 1.4.4.1 & 1.4.4.1.1 added as per above.. Section 1.4.4.1, clarifies Service QA Program application to nuclear fuel procurement.
Section 1.5, defines on-site surveillance, inspection, etc., for materials and services.
Removed " Nuclear" from titles on the following pages:
1-1 1-3 1-10 1-11 2-2 2-3 2-9 3-3 4-2 5-2 6-1 6-3 8-3 10-4 12-2 16-4 18-2 T3-1 T3-2 Crammatical Corrections:
(V)
Page 1-4: Deleted "s" from Reactor Operator (s) License.
Titles 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 char.ged from QA to Licensing.
Page 2-9:
Section 2.6.6, PSC composition revised to include varied members at or above the superintendent level.
g Entergy QA MANUAL OPERATIONS REV.: 13 DATE: 05/01/91 Operations SECTION:
RECORD OF REVISIONS PAGE: RR-33 Arkansas Nuclear One
RECORD OF REVISIONS REVISION O
1R!MBEIL.
DESGifl10S DAIE 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 /
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 by CASE now done by NUPlc 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 O
of this application to ASME procurement.
Page 11-3: Section 11.3.2.2, Departmental name change from Engineering
" Services" 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 renuires that only "significant" conditions adverse to safety require root cause identification.
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13 TEEP Entergy DATE: 05/01/91 Olperations SECTION: RECORD OF REVISIONS PAGE: RR-34 Arkansas Nuclear One
=
RECORD OF REVISIONS REVISION O.
NUMBER DE1CRIPTION DAIE 13 (Cont.)
Page 16-2: Section 16.3, Supplier QA will evaluate vendors' who furnish products or services that do not conform to the requiremeras of the applicable purchase contract.
4 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
_ (h_.
-QA.
, ()
Page 18-4: Section 18.4.1, clarifies approval level 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 f._
Nuclear Fuels Audit defined to specific position (Supervisor, Services QA) instead of Entergy Corporation, g Entergy QA MANUAL OPERATIONS REV.
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RECORD OF REVISIONS PAGE: RR-35 Arkansas Nuclear One
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RECORD OF REVISIONS p
REVISION
()
NUMBER DESCRIPTION DAIE 13(Cont.)
Page T2-1: Change title of 2000.12 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 Procram-Requirements; superseded by 1000.06, Procedure Contrcl 1
Change title of. 1000.05 to " Procedure
- l Control".
j Delete LRNP-210 %: lear Drawing Control Design Engineering; superseded by 1032.013, Drawing Preparation Receipt, Review and Approval.
_O Delete 1000.05, h etedure Format and V
Content; superseded by 1000.06, Procedure Control..
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 2.1(2), added responsibility for fire protection training to.
the Director, Operaitons.
Page AB-5: Functional responsibility for Licensing transferred to Vice President,-Operations-ANO.
Page F-1 thru F-7: Revised organization charts.
h QA MANUAL OPERATIONS REV.: 13
= Entergy DATE: 05/01/91 Operations SECTION: RECORD OF REVISIONS PAGE: RR-36 Arkansas Nuclear One
ARKANSAS NUCLEAR ONE POLICY STATEMENT.
-QUALITY ASSURANCE PROGRAM FOR OPERATIONS-O 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, 1
- repaired or replaced to Code requirements.
The Entergy Operations President and Chief Executive Officer has the L
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 Executive Vice President and Chief' Operating Officer; Entergy Operations Senior Vice President,. Planning and Assurance; and Entergy Operations.Vice President, Human Resources and Administration are-responsible ~for the-procedural implementation of the QA Program within g Entergy QA MANUAL OPERATIONS REV.
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SECTION:
STATEMENT OF POLICY PAGE A-1 Arkansas Nuclear One -
. ~. - -. - - -
i their assigned areas.
The Director, G y rations; General Manager, Oi Engineering; General Manager, Quality; General Manager, Support; General Manager, Materials Management; and Manager, Licensing are responsible for the daily implementation of the QA Program's procedural requirements at i
.ANO, in'their respective areas.
The General Manager, Quality is responsible for establishing the QA Program.
Responsibility for approval of the QA Program shall be identified within this manual.-
l Quality personnel reporting to the General Manager, 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 involving quality, arising
'A from difference of opinions betweeii Quality personnel and other D
personnel, which cannot be settled interdepartmentally, shall be
- presented-to the-Vice President, Operations ANO for resolution. The General Manager, Quality has direct access to the Entergy Operations, President and Chief Executive Officer and the Entergy 0;,erations Executive Vice President and Chief Operating Officer on matters concerning' quality.
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STATEMENT OF POLICY PAGE A-2 Arkansas Nuclear One
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i Ihe General Manager, Quality through the Manager, Quality Assurance is to l
_ provide for an annuai review of the adequacy and overall effectiveness of i
the QA Program. Any defects in the implementation of either this policy or the QA Program thu are revealed during the review are to be reported to appropriate levels of management together with appropriate recommendations.
Implementation 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 'or 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 l
organizations and individuals.
'T (w/..,_
~*
N. S. Carns Vics President, Operations ANO Date:
1"M l '5 1
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STATEMENT OF POLICY PAGE A-3 Arkansas fduelear One
TERM. AND DEFINI110NS 1he terms used in this manual follow the definitions provided in ANSI N45.2.10-1973, supplemetited by additional terms and definitions
~
applicable to this manual.
Anptoyd - An act of endorsing or adding positive authorization, or both.
Anourtenance - A part that is attached to a component which has been j
completed.
As-Built Data - Documented data that describes the condition actually achieved in a product.
611tably - A combination of subassemblies 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 requirementr, and the effectiveness of implementation.
Snic Comoonent - A nuclear plant structure, system or component necessary-to assure the nuclear safety criteria, Bid Evtluation - 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 qualified party, c6rtifying that items or services comply with specific requirements, i
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, -. _ ~, _ _ _..
~. _.
i W
[ertificate of Comnliance - A written statement, signed by a qualified party, attesting that the items or services are in accordance with V) specified requirements and accompanied by additional information to substantiate the statement.
[ertified Test Report - A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual properties of items and the actual results of all required te s t s.-
Certification - The action of determining, verifying and attesting, in writing, to the qualifications of personnel or material.
Characteristic - Any property or attribute of an item, process, or service that is. distinct, describable, and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings which describe the item, process, or service.
I
' O Checks - The tests,. measurements, verifications or controls placed on an V
activity 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 ANII) 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 inservice inspection of ASME Boiler and Pressure Vessel items designated safety-related.
QA MANUAL OPERATIONS REV.
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TERMS AND DEFINITIONS PAGE C-2 Arkansas Nuclear One
CornmerriahGIAde - Those items contained in Q systems and equipment that are:
(1) not subject to design or specification requiremt>nts unique to nuclear facilities or activities; (2) used in application other than nuclear facilities or activities; and (3) to be ordered on the basis of specifications set forth in manufacturer's pub'ished product description.
Ca nongni - A piece of equipment such as a vrssel, piping, pump, valve or core support structure, which will be combired w!th other components to form an assembly.
Computer Code - The application sof ware 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 gnd safety of the public or relied 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.
Contaminants - Foreign materials such.s mill scale, dirt, oil, chemicals and any matter than renders a fluid, solid or surface impure and unclean according to preset standards of acceptable cleanness.
Contractnt - Any organization under contract for furnishing items or services.
It includes the terms Vendor, Supplier, Subcontractor, Fabricator and sub-tier levels of these where appropriate.
Ihutication - 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 Malerial - A material or component which has one or more characteristics that do not comply with specified requirements.
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Operations DATr 05/01/91 i
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Arkansas Nuclear One
L Deviation - A nonconformance or departure of a characteristic from specified requirements.
O DEumgn.taliga o / written or pictorial information describing, defining, specifying, reporting or certifying activities, requirements, procedures, or results.
Examination - An element of inspection consisting of in/estigation of materials, components, supplies or serv 8ces to determine confornance to those specified requirements which can be o'etermined by such investigation.
Examination is usually nondestructive and incluves simple physical manipulation, gaging, 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 maintain safe plant shutdown to within those limits set forth in Section I of Appendix R to 10CFR50.
This list is maintained current in the SIMS computer data base.
Handlina - An act of physically moving items by hand or mechanical means, but not including transport modes.
Inauirv - A document that contains the necessary information for a vendor to make a proposal. An inquiry may include specifications pertaining to j
the equipment, materials or services proposed to be procured.
Jnnector (Owner's) - A qualified inspector employed by the Owner whose duties include the verification of quality-related activities or installations or both.
i OV
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l In.iplc.tioB - A phase of quality control which by means of examination, observation or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements, 11010 - Any level of unit assembly, including structure, system, subsystem, subassembly, component, part or material, datLDrdet (J.O.) - The document used for identifying and administrative 1y controlling the work effort on station equipment and systems.
It identifies applicable procedures and drawings; documents reviews, approvals and results of inspections and tests; and provides a mechanism for planning, scheduling and authorizing work.
Maantatu ttt - One who constructs any class of component, part, or appurtenance to meet prescribed design requirements, h61trM - A substance or combination of substances forming components, parts, pieces and equipment items.
(Intended to incit.de such as machinery, castings, liquids, formed steel shapes, aggr* gates, and cement.)
hodification - A planned change in plant design or operation and accomplished in accord 3nce with the requirements and limitations of applicable codes, standards, specifications, licenses and predetermined safety restrictions.
Maat.QB10mants - 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, incorrect or inadequate documentation, or deviation from prescribed l
processing, inspection or test procedures.
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TERMS AND DErlNITIONS PAGE C-5 Arkansas Nuclear Ore
Nuclear Safety Criteria - (1) Integrity of the reactor coolant pressure boundary; (2) capability to shutdown the reactor and maintain it in a safe shutdown condition; and (3) capability to prevent or mitigate the consequences of accidents which could result in potential offusite exposures comparable to those referred to in 10CFR100.11.
Obitc111e Evidence - Any statement of fact, information or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, tneasurements or tests which can be verified.
Operation - The total of administrative, mainteriance and monitoring activities necessary to sustain the power-generating capabilities of the plant af ter initial start-up.
Qat - The person, group, company or corporation who has title to the facility or installation.
PE lage - A wrapping or container including its contents of materials or equipment, hi} aged Unit - An assembly of items and parts which can be disassembled without destroying the integrity of the individual parts.
h ti - An item which has work performed on it and which is attached to and becomes part of a component before completion of the component.
Plait.t - The equipment, piping, structures, buildings and property that comprise an installation or facility.
Przed.ute - 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, QA MANUAL OPERATIONS REV.
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_ Arkansas Nuclear One i
PacRLemenLDocuments - Contractually binding documents that identify and define the requirements that items or services must meet in order to be considered acceptable by the purchaser.
blini - A planned ser.es of activities including all actions necessary to provide, utilize, and maintain a facility or portion thereof.
Etop.asal - A bid, usually written by a vendor in response to an inquiry, which provides the issuing party v'th the vendor's proposed compliance to the inquiry and the cost.
EunchunQtder f or Contract) - A document authorizing a vendor to provide equipment, material or services in accordance with stated terms and conditions.
Eurchun - The organization or organizations responsible for issuance and administration of a cor, tract, subcontract or purchase order.
Qdisi - A list of safety-related structures, systems, and components -
that is, those structures, systems and components that must remain t
functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.
Qualifica11on (Personnel) - The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.
Qualified Party - A person or organization competent-and recognized as knowledgeable to perform certain functions.
Qualified Precedure - A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose.
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Qualified.Yendor List - A listing of vendors having quality assurance programs consistent with the requirements of applicable portions of O
For vendors supplying'ASME Code items, they shall also have,a quality program consistent with the requirements of applicable portions of ASME Section 111, Division 1, subsection NCA.
l Quality Assurance - All those planned and systematic actions necessary to provide adequate confidence that an item or a facility will perform satisfactorily in service, t
Outlity Control - Those quality assurance actions which provide a means to control and measure the characteristics of an item, process or facility to established requirements.
Receiving - Taking delivery of an item at a designatea 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 O
original requirement.
Rentt - Something (document) that gives information for record purposes.
Reyieg - An element of inspection to determine conformance to specified requirements, which can be determined by examination of documents and activities.
Rexcri - 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 the QA Program requirements of 10CFR50, Appendix B.
This list is maintained current in the SIMS Computer Data Base.
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TERMS AND DEFINITIONS PAGE C-8 Arkansas Nuclear One
lafetv-Re1Aled (0) - safety-related structures, systems and components are those that must remain functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.
Source Shy.eillants - A review, observation or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture.
SRe_CifiG11120 - 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.
116.nier.d - The result of a particular standardization ef fort approved by a recognized authority.
Sigrjtge The act of holding items at the construction site or in an area other than its permanent location in the plant.
itthlyitsm - A group of assemblies or components or both combined to perform a single function.
Suty211Lanca - The continuing analysis and evaluation of records, methods and procedures, including the act of verification, to assure conformance with technical requirements.
Syltsm - A group of subsystems united by some interaction or interdependence, performing many duties but functioning as a single unit.
System PerfarRancelit - A test perf ormed on a completed system including electric, instrumentation, controls, fluid and mechanical subsystems under norma' or simulated normal process conditions such as temperature, flow, level, and pressure.
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Operat ons SECTION:
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Testina The 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 of' individuals such as General Manager, Quality when used in this manual, assign the responsibility of performing the requirement to the noted individuals or their appointed designees.
Iransit - The state of being conveyed or transported from one place to another.
Transit Carrier (Onen) - Trucks, trailers, railroad cars, barges, aircraft or ships which do not afford items protection from the environment.
Transit Carrier (Closed) - Trucks, trailers, railroad cars, barges, aircraft or ships which provide protection of items from the environment by nature of their closed design.
OV Use-As-Is - A disposition which may be imposed for a ncnconformance 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.
Vendor - Any organization under contract for furnishing items or services.
It includes the terms Contractor, Subcontractor, Supplier, Fabricator and sub-tier levels of these where appropriate.
Verification - An act of confirming, substantiating and assuring that an activity or condition has been implemented in conformance with the specified requirements.
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~.. -
Work Instructions - Written instructions used to transmit detailed information on the specific measures necessary to comply with the i
requirements of quality assurance procedures or any complex or difficult quality-related task.
Work Packagg - 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 the job.
Ov
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TERMS AND DEFINITIONS PAGE C-11 Arkansas Nuclear One
1.0 QRGANIZATION 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 (AND) in compliance with 10CFR50, Appendix B and applicable licensing commitments identified in the Introduction.
It also includes a 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 Organizations relevant to the operation of ANO are shown in Figure 1.
1.2 GENERAL RESPONSIBILITIES The on-site responsibility for AND, including quality assurance, lies with the Vice President, Operations ANO.
He provides management l
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, inservice inspection and test, modification and those additional activities discussed in Sections 2.0 through 18.0 of this manual.
The l
Vice President, Operations ANO, who reports to the Entergy Operations l
Executive Vice President and Chief Operating Officer is responsible for the formulation, lic sing, implementation and discharge of operating policies and procedu.es relative to nuclear plant operations, nuclear quality and nuclear fusi management.
The Nuclear Organizatinn is shown i
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1.0 ORGANIZATION PAGE 1-1 l
Arkansen Nuclear One
_ _. ~
- - -. -. - ~.
in figures 1 thru 9.
The Vice President, Operation AN0's duties include the following:
(1),Providing technical direction and administrative guidance to the:
a.
Director, Operations i
b.
General Manager Quality c.
General Manager, Engineering d.
General Manager Support e.
General Manager, Materials Management f.
Manager, licensing (2) Ensuring conformance to the QA Program by instituting the f
necessary procedures and instructions within the Nuclear Organization (3) Providing for review and approval of design and engineering i
performed for ANO (4) Previding for review and approval of procurement documents for equipment, material and services (5) Providing for liaison between ANO and applicable regulatory agencies (6) Providing and maintaining a qualified and suitable staff to carry out required departmental functions (7) Providing for procurement and design review of nucleer fuel (8) _ Assuming overall responsibility for the fire protection, emergency planning and radiation protection programs implemented at ANO
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1.0 ORGANIZATION PAGE 1-2 Arkansas Nuclear One
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1.3.1 Director._Doerationi O
The Director, Operations reports to the Vice President, Operations AND and has direct responsibility for operating AND in a safe, reliable and efficient' 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.
1he Director, Operations has the authority to shut down either unit if required.
The Director, Operations provides technical direction and administrative i
guidance to the:
(1) Plant Manager, ANO-1 (2) Plant Manager, ANO-2 (3) Plant Manager, Central (4) Manager, $tandards/ Executive Assistant (5) Manager, Training / Emergency Planning 1.3.1.1 Plant Managers, ANO-1 & 2 The Plant Managers, ANO-1 & 2 report to the Director, 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 Managers, ANO-1 &
2 provide technical direction and administrative guidance to their respective:
(1) Manager, Operations, ANO-1 & 2 (2) Manager, Maiatenance, ANO-1 & 2 (3) Project Manager, Outages, ANO-1 & 2 (4) Manager, System Engineering, ANO-1 & 2 (5) Technical Assistant to Plant Manager, ANO-2 g EnterW
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1.0 ORGANIZATION PAGE 1-3 Arkansas Nuclear One l'
(
)
1.3.1.1.1 The Managers, Operations, AND-1 & 2 are responsible for directing the actual day-to-day operations of their assigned unit.
They supervise each unit's operating staff and interface with the respective Managers, Maintenance, AND-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. The Managers, Operations, ANO-1 & 2 are also responsible for supervision of core refueling, which includes advance planning for the outage, plant preparation, equipment checkout and the refueling uperations.
The Managers, Operations each hold an NRC Senior Reactor Operator License.
The Managers, Operations ANO-1 & 2 provide technical direction and administrative guidance to the Supervisors, Shift Operations of their assigned unit.
1.3.1.1.1.1 The Supervisors, Shift Operations report to the applicable Manager, Q
Operations and are responsible for the actual operation of the unit and V
for the activities of the Operators during their assigned shifts.
The Supervisor, shift Operations is cognizant of operation activities being performed while on duty. The Supervisor, Shift Operations on duty has the authority to shut down the unit if, in his judgement, conditions warrant such action.
The Supervisors, Shift Operations each hold an active Senior Reactor Operator License.
The Superviso s, Shift Operations provide technical direction and administrative nuidance to the:
(1) Control Room Supervisors (Holders of active Senior Heactor Operations License)
(2) Shift Administrative Assistants (3) Control Board Operations (Holders of active Reactor Operator License) g Entergy O
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(4) Waste Control Operators (5) Auxiliary Operators O
1.3.1.1.2 The Managers, Maintenance, ANO-1 & 2 report to the applicable Plant Manager, ANO-1 & 2 and are responsible for the maintenance of plant equipment and facilities as defined by plant maintenance program implementing procedures and ensuring that maintenance of equipment is performed in compliance with applicable standards, codes, specifications and procedures.
The Managers, Maintenance, ANO-1 & 2 are also to coordinate operation-related maintenance activities with the applicable Managers, Operations, ANO-1 & 2 and are responsible to make repairs on any structure, system or component under their control.
The Managers, Maintenance, AND-1 & 2 provide technical direction and administrative guidance to the Maintenance Technical Staff.
1.'t.1.1.3 The project Managers, Outages ANO-1 & 2 report to the applicable Plant Manager, ANO-1 & 2 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 sch9duling of refueling outages and other scheduled or forced outages requiring cold shutdown, and directing activities during outages.
1.3.1.1.4 The Managers, System Engineering, ANO-1 & 2, report to the applicable Plant Manager. ANO-1 & 2 and are responsible for reactor, performance, and system engineering activities required for the safe and efficient production of electricity.
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1.0 ORGANIZATION PAGE 1-5 Arkansas Nuclear One
related engineering issues that do not alter the design bases of the respective plants.
O 1.3.1.1.5 The planning and scheduling of plant work activities are executed under the AND 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.
1.3.1.2 Plant Manager, Central The Plant Manager, Central reports to the Director, Operations and provides planning, direction, control and overall supervision to the Central Support Department, the Security Department, Modifications Department, Computer Support Department, the Work History section, the Radiation Protection /Radwaste section, the Chemistry / Radiochemistry section, and the Maintenance Engineering Programs section in operating and maintaining 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 supervision of personnel and daily work activities involving the safe, efficient and reliable operation of ANO. The Plant Manager, Central provides technical direction and administrative guidance to the:
(1) Manager, Central Support l
(2) Superintendent, Chemistry and Radiochemistry (3) Manager, Radiation Protection and Radwaste (4) Manager, Security (5) Manager, Modifications O
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1.3.1.2.1 The Manager, Central Support reports to the plant Manager, Central and provides planning, direction, control and overall supervision of the Central Support functions (e.g., Security Maintenance, Maintenance Engineering, Central Support, Computer Support, Work History, Metrology, Welding, Machine Shop, Plant Services, etc.) operating and maintaining ANO. Responsibilities involve the development and administration of programs which support the capability of AND to meet or exceed industry standards and regulatory requirements.
Responsibilities also involve the supervision of personnel and daily work activities involving the safe, efficient and reliable operation of ANO.
1.3.1.2.2 l
The Superintendent, Chemistry and Radiochemistry reports to the Plant Manager, Central and is responsible for implementing the Nuclear Organization chemistry policies, programs. and procedures.
The l
Superintendent, Chemistry and Radiochemistry is directly responsible for implementing controls as required to maintain chemistry and radiochemistry parameters in specification and establish chemistry and radiochemistry controls conducive to maximizing plant life.
l 1.3.1.2.3 The Manager, Radiation protection and Radwaste reports to the Plant Manager, Central and is 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 r
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personnel radiation exposure (ALARA), minimize personnel contamination, minimize radwaste volume, and establish uniform procedures and methods for contamination control and radiation protection.
The Coordinator, Industrial Safety reports to the Manager, Radiation Protection and Radwaste.
1.3.1.2.4 Manager, Security The Manager, Security reports to the Plant Manager, Central and is responsible for plant security including coordination of efforts of the i
security force and managing the operation of the security system.
1.3.1.2.5 Manager, Modifications l
The Manager Modifications reports to the Plant Manager, central and is responsible for directing the activities of his staff relating to work associated with plant construction and modifications and interfacing with other departments to assure effective implementation of job assignments. The Manager, Modifications is also responsible for f
providing engineering support during the implementation and closecut of design modifications generated in support of ANO.
The Manager, Modifications provides technical direction and administrative guidance to the:
+
i (1) Superintendent, Installation (2) Superintendent, Modification Engineering 1.3.1.3 Manager, Standards / Executive Assistant The Manager, Standards / Executive Assistant reports to the Director, Operations and provides planning, direction, control and overall supervision to the Standards Department in developing and maintaining policies and procedures for the surveillance and maintenance programs of-Entergy QA MANUAL OPERATIONS REV.
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ANO. Responsibilities involve the development and administration of programs which support the capability of ANO to meet or exceed industry O
standards and regulatory requirements.
Responsibilities also involve the Chairmanship of the F' ant Safety Committee which reviews the various aspects of operation, maintenance, modification and support to assure the safety of ANO.
The Manager, Standards / Executive Astistant provides technical direction and administrative guidance to:
(1) AdministrativeAssistant(PSC)
(2) Supervisor, Surveillance Testing (Technical Specifications)
(3) Superintendent, Maintenance Standards Department 1.3.1.4 Manager, Training and Emergency Planning The Manager, Training and Emergency Planning reports to the Director, Operations and is responsible for the training and retraining of plant personne1'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 AND Emergency G
Plan.
The Manager, Training and Emergency Planning directs the aethities of the ANO training staff and provides technical direction and administrative guidance to the:
(1)
Superintendent, Operations Training (2) Superintendent, Technical Training (3)
Superintendent, Emergency Planning (4) Supervisor, Cirriculum Standards 1.3.2 General Manager. Quality l-The Quality Department's organization shown in Figure 5 is under the direction of.the General Manager, Quality who reports to the Vice l
President, Operations ANO.
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i The Quality Organization performs reviews, assessments, analysis, l
surveillance, inspection, nondestructive examination and 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 General Manager, Quality has direct access to all management levels, which assures his staff the ability to:
identify quality problems; initiate, recommend or provide solutions through designated channels; and verify implementation of solutions.
The qualification requirements of the General Manager, Quality are established within his job 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 minimum 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 supervisory position with at least one year experience in the implementation of the quality assurance program (3) Exhibit the abilhy to plan, schedule and direct the activities of others assigned to or functioning within the l
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Duties and responsibilities of the General Manager, Quality include the following:
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(1) Technical direction, administrative guidance and supervision j
to the Manager, Quality Assurance; Manager, Quality Control / Quality Engineering; and Manager, plant Assessment (2) Approving of the QA Manual Operations and revisions thereto (3) Approving of QA and QC/QE procedures and revisions thereto as established within NQA procedures 1.3.2.1 Manager, Quality Assurance l
The Manager, Quality Assurance reports to the General Manager, Quality.
Duties and responsibilities of the Manager, Quality Assurance 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 l-(2) Auditing of the quality activities as described in Section 18.0 of this manual (3) Reviewing, approving and ensuring the verification of quality assurance requirements placed upon contractors or vendors tSat provide equipment, material or services for ANO l
(4) Authority to stop work where conditions exist that prohibit effective quality programs, or if faulty materials, incorrect workmanship or procedures are detected l
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(
(5) Ensuring review, approval, and control of vendor quality manuals and procedures and revisions thereto (6) Ensuring approval and control of quality assurance programs for outside organizations participating in the QA Program (7) Providing and maintaining a qualified and suitably trained i
staff to carry out required staff functions (8) Formulating programs for maintaining the professional competence 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 affect quality (9) Providing technical direction and guidance to the Supervisors, Quality Assurance and their staff (10) Inspecting, auditing or reviewing practices, records, files, instructions, directions or documents concerned with all areas affecting quality (11) Scheduling and coordinating audits or surveillance efforts in the areas assigned, documenting findings and reporting results to the General Manager, Quality and management of the audited area (12) Providing to the General Manager, 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
)
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1.3.2.2 Manager, Quality control / Quality Engineering The Manager, Quality Control / Quality Engineering reports to the General Manager, Quality and is responsible for verifying the implementation of the Quality Control program at ANO.
The duties and responsibilities of the Manager, Quality Control / Quality Engineering include the following:
(1)
Interface with plant staff in developing quality control requirements and inspection points for operation, maintenance and modification activities related to safety-related i
(Q-listed) and fire protection-related (F-listed) systems, structures and components (2)
Interface with the Manager, Quality Assurance or his regresentative for technical assistance in resolving significant conditions adverse to quality
{
(3) Authordty to stop unsatisfactory work and authority to place an iterc in a conconforming status when such an item is j
determined to oe in violation of purchase documents, applicable G, des 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 the Supervisor, Quality Engineering, Supervisor, Nondestructive Examination, and Supervisors, Quality Control and their staffs o
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v (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 / Quality Engineering section 1.3.2.3 Manager, Plant Assessment The Manager, Plant Assessment reports to the General Manager, Quality and is responsible for providing assessments of plant and industry operating experiences, oversight of plant and industry operation experiences, oversight of selected key station programs.
The Manager, Plant Assessment provides support and membership on the Plant Safety Committee and Safety Review Committee.
The Manager, Flant Assessment also manages the plant operation experience review program in accordance with INPO guidelines.
The Manager, Plant Assessment provides technical direction and administrative guidance to the:
(1) Manager, Industry Events Analysis (2) Manager, Safety Assessment (3)
Supervisor, In-house Events Analysis 1.3.2.3.1 The Manager, Industry Events Analysis reports to Manager, Plant Assessment and 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 50ER's, SER's, O&MR's, SEE-IN documents, NRC Information Notices and vendor notifications (including 10CFR21-reports).
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Additionally, this section is the interface for reporting to Nuclear Network concerning events that occur at AND.
1.3.2.3.2, The Manager, Safety Assessment reports to the Manager, Plant Assessment and is responsible for assisting station management in monitoring and evaluating ANO performance to ensure that effective management programs are developed, implemented and maintained to achieve the goals and Standards of Excellence as prescribed by senior nuclear 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 assessment of overall plant activities.
The Safety Assessment Department provides independent, objective assessments (outside the traditional auditing role) of the overall effectiveness of nuclear programs to help assure that performance expectations are being met.
The inputs to this process include the assessment of prior and current AND 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.
1.3.3 Ggnen1 Manaaer. Engineerina The General Manager, Engineering reports to the Vice President, Operations ANO and provides direction, planning, support and overall supervision to Mechanical / Civil / Structural Design; Electrical /I&C Design; Engineering Standards and Programs (including engineering backlog reduction), Engineering Support (configuration management, QA MANUAL OPERATIONS REV.
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I design documentation, drafting, and engineering training); Nuclear l
Engineering Design, and specific projects.
Responsibilities include the development of programs, policies, procedures and providing engineering services 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, efficiency, 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 6.
The General Manager, 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 Standards and programs (5) Manager, Nuclear Engineering Design 1.3.3.1 Manager, Mechanical / Civil / Structural Design The Manager, Mechanical, Civil, & Structural Design reports to the General Manager, Engineering and directs engineering activities in support of ANO, primarily in the areas of plant modifications, operability assessments 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 &
Maintenance concerns at the request of plant staff, and is directly related to power generation operations.
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.!M 1.3.3.2 Manager, Electrical / Instrumentation and Control Design
_The Manager, Electrical, Instrumentation and Centro 1_ Design reports'to the General Manager, Engineering and directs engineering activities in support oI ANO, primarily in the areas of plant modifications, operability assessments and maintenance of the Electrical Engineering and Instrumentation & Control Engineering design bases for AN0; the primary benefit of which'is safe ef ficient operation of ANO in compliance with applicable regulatory requirements. This positi provides technical assistance in the rer.olution of Ooeration &
Maintenance concerns at the request of plant staff, and is directly related to power generation operations.
i 1.3.3.3 Manager, Engineering Support The Manager, Engineering Support reports to the General Manager, Engineering and directs configuration controls, drafting and administrative activities in support of ANO, primarily in the areas of plant modifications, computer support, drawing control, engineering records control, 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 direct:; the Design Configuration Documentation Project and is directly related to power generation operations.
1.3.3.4 Manager, Engineering Standards and Programs
-The Manager, Engineering Standards and Programs reports to the General
}
- Manager, Engineering and is responsible for' providing on-site l}
engineering program services including coordination of the ANO fire
_ protection and fire prevention programs, and implementation and coordination of the inservice inspection, inservice testing, on-site welding, environmental. qualification and backlog elimination project O
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1.0 ORGANIZATION PAGE 1-17 Arkansas Nuclear One
programs. LThe Manager, Engineering Standards and Programs provides technical direction and administrative guidanceito the:
4 d
(1) Superintendent, Engineering-Programs
~
(2) ' Project Manager, Backlog
-(3)
Supervisor, Engineering Standards l
1.3.3.5 Manager, Nuclear Engineering Design The Manager, Nuclear Engineering Design reports to the General Manager, Engineering and-directs nuclear engineering activities in support of ANO. The position provides nuclear engineering, nuclear safety analysis, core reload and availability, reliability technical assistance in~the. resolution of operations'and maintenance concerns at the rc-quest of plant. staff, and is dir'ectly related to power generation operations.
1.3.4 General Mangoer. Sucoort
.The~ General. Manager, Support reports to the Vice President, Operations ANO and is responsible for managing the nuclear five-year business plan, l, '-
including establishing-the budget,_ managing the goals and objectives program for the Nuclear Organization and preparing and maintaining the administrative controis program, including input to training,' oversight of the progr'am, and advice to senior nuclear management on administrative issues.
Payroll and accounting is also provided Fy the
. General Manager, Support.
He also provides planning, direction, control and overa11: supervision to Fitness for Duty Department.
He additionally serves as a member and Secretary of the Safety Review Committee.
The l
Nuclear Support Department's organization is shown in Figure 7.
The General. Manager, Support is responsible for providing direction and general supervision to'the-following_ technical and administrative individuals in support of the Vice President, Operations ANO:
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1.0 ORGANIZATION PAGE 1-18 Arkt.nsas Nuclear One -
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j (1) Manager, Business Planning and Analysis (2) Site Controller-(3) Manager,' Project Support (4) Manager, Office Services
-(5) ' Medication' Review Officer / Physician
'[
1.3.5 General Manaaer. Materials Manaaement The General Manager, Materials Manageme_nt reports to the Vice President, Operations ANO and has direct responsibility for procurement, receipt, storage and issue _of materials, parts and components to be used in plant maintenance and modification activities. The Materials _ Management Organization is shown-in Figure 8.
The General Manager, Materials Management provides technical direction and administrative guidance to the-following:
(1) - Manager, Materials Support 1
(2) Manager, Stores Operations (3) Manager, Materials Engineer (4) Manager, Inventory Control-
-1.3.6
' Manager, Licensing The Manager, Licensing' reports to the Vice President,. Operations ANO and has overall responsibility for the management and oversight of NRC inspection activities and-interactions with the NRC regional and Washington, DC' offices. The Licensing Department's organization'is shown on Figure 9.
The Manager, Licensing provides technical direction
- and administrative guidance to the:
(1) -Superviso_r, Plant Licensing (2) Supervisor, Licensing g Entergy C
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1.3.6.1 St.pervisor, Plant Licensing The Supervisor, Plant Licensing reports to the Manager, Licensing and is responsible for the following duties:
(1)
Interfacing with on-site and regional regulatory agencies and the Manager, Licensing pertaining to Licensing and regulatory matters (2)
Providing evaluations and recommendations in meeting regulatory commitments
(~)
Establishing and maintaining a system for monitoring License Event Reports and NRC Inspection Reports (4)
Providing technical direction and administrative guidance to the Nuclear Safety and Licensing Specialists 1.3.6.2 Supervisor, Licensing The Supervisor, Licensing reports to th! Manager, Licensing and is responsible for the following duties:
(1)
Interfacing with NRC, Washington, DC offices and the Manager, Licensing pertaining to Licensing and regulatory matters (2) Establishing and maintaining programs for the maintenance of Licensing Base Documents (!icense, SAR, Technical Specification, Emergency Plan, QA Manual Operations)
(3) Reviewing NRC Correspondence (incoming and outgoing) and related industry documents to remain cognizant of activities that may affect AND QA MANUAL OPERATIONS REV.
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b (4).Providug technical direction and administrative guidance to-the-Nuclear Safety and Licensing Specialists DO
-1,3.7~
,ludeDiadent' Review Organizations 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 review activities occurring during -the operational phase of ANO.
1.3.7.1 Safety Review Committee (SRC)
The SRC is chaired by the Vice President Operations ANO and is responsible for providing independent reviews and/or audits relating to:
-thef Safety. Analysis Reports, Technical Specifications, procedures and-changes thereto; unreviewed safety questions; violations, deviations and eportable events; and any other matter involving safe operation of ANO r
which the committee deems appropriate or is referred to them by the on-site operating group. The SRC is also to review the reports and meeting minutes generated from the Plant Safety Committee.
1.3.7.2 Plant' Safety Committce'(PSC) l The PSC reports to the~ Director, Operations and is responsible for reviewing ~ activities specified in the Technical Specifications for the purpose of:
(1) Rendering determinations in writing with regard to whether or not an unreviewed safety question (defined by 10CFR50.59) is-involved (2) Furnishing written recommendations to the Director, Operations l
for approval
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These activities include changes to plant procedures and Technical l
Specifications, proposed modifications to plant systems, changes to plant security and emergency plans and review of facility operations to detect potential nuclear safety hazards.
1.3.7.3 Committee Structure The organizational structure and administrative requirements specific to each committee are described in the Technical Specifications for each operating unit and in internal procedures / documentation.
1.4 ENTERGY OPERATIONS OFFSITE ORGANIZATION 1.4.1 President & Chief Executive Officer The President & Chief Executive Officer 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 internal audit policy. He deltgates authority and responsibility for the operation and support of AND through the Executive Vice President &
Chief Operating Officer, the Senior Vice President, Planning and Assurance, and the Vice President, Human Resources & Administration.
1.4.2 Executive Vice President & Chief Ooeratina Officer The Executive Vice President & Chief Operating Officer has the responsibility to oversee all operations and engineering functions of Entergy Operations. He delegates authority and responsibi',ity for the operation and support of AND through the Vice President, Operations AN0; the Vice President, Operations Support; the Vice President, Nuclear Engineering & Support and the Director, Nuclear Fuels.
It is the responsibility of the Executive Vice President & Chief Operating Officer to assure that all safety related activities under his direction are EnterU QA MANUAL OPERATIONS REV.
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1.0 ORGANIZATION PAGE 1-22 Arkansas Nuclear One
aerformed following the guidelines of the Corporate Quality Assurance Frogram and the ANO QAMO.
O 1.u.2.1 Vice President, Operations Support 3
The Vice President, Operations Support is responsible for the Corporate Support functicns of Licensing, Maintenance, and Radiological and Ervironmental Support.
'. 4.2.2 Director, Fuels The Director, Fuels, is responsible for the procurement of nuclear fuel for AND, the establishment of policies for the nuclear fuels cycle reload management process, the direction of nuclear fuel cycle planning, the provision of nuclear fuel cash flow and cost projections for use in company business plan and fuel financing activities, the maintenance of the Official Enttrgy Operations Nuclear Operating Schedule, and the oversight of nuclear fuel accounting activities.
1.4.2.3 Vice President, Engineering The Vice President, Engineering is responsible for providing nuclear engineering services for ANO, as requested.
1.4 3 Vice President. Human Resources & Administration The Vice President, Human Resources & Administration is responsible for the administration of functions associated with Corporate Services and Humal Resources. He delegates authority and responsibility for the acconplishment of the above activities through the Director, Corporate Services and the Director, Human Resources.
It is the responsibility of the \\ ice President, Human Resources & Administration to assure that the G
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safety related activities under his di ection are performed following the guidelines of the Corporate Quality Assurance Program and the ANO
-QAMO.
1.4.3.1 irector, 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.
1.4.3.2 Director, Corporate Services The Entergy Operations, Inc.-Director, Corporate Services is responsible for the procurement'of materials, parts and components requested by Nuclear personnel offsite and for supporting procurement activities at ANO.
(')
'd 1.4.3.2.1 Manager, Purchasing The Entergy Operations; Inc. Manager, purchasing is responsible f e the following activities:
(1) Preparing ANO purchase orders based upon. receipt of reviewed and approved purchase requisitions.
(2) performing the commercial-interface functions between ANO and vendors.
1:
(3) Ensuring-that quality documentation prepared by ANO personnel is
[;
included in appropriate procurement documents.
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He delegates authority and responsibility for purchasing activities at ANO through the Supervisor, Purchasing-ANO.
1.4.4 $1Dinr_yke Presidera_Plannina & Asiur_anct 4
The Senior Vice President, Planning and Assurance is responsible for Nuclear Safety Oversight, Total Quality, Planning and Professionalism, technical interface with the state pubile service commissions, coordinatien of foreign visits and interface with the World Association of Nuclear Operations. He establishes, directs or conducts programs, studies and analyses of the nuclear safety, engineering, and operations activities. Other responsi'ilities include strategic planning, direction of total quality improvement company-wide and direction of the Supplier and Services Quality Assurance Groups.
He delegates the authority for the accomplishment of the above activities through the Director, Total Quality, the Manager, Nu:: lear Safety Oversight and the Manager, Planning and Professionalism.
It is the responsibility of the Senior Vice President, Planning and Assurance to assure that all safety related activities are performed following the guidelines of the Services Quality Assurance Program and the Quality Programs of the
\\
Entergy Operatiens' nuclear sites.
1.4.4 1 Manager, Nuclear Safety Oversight 1he Manager, Nuclear Safety Oversight is responsible for Nuclear Assurance, Supplier Quality Assurance and Services Quality Assurance.
He assures development and maintenance of the Service Quality Assurance program and implementing procedures covering services safety related activities. He assures performance of audits and assessments of the sites' Quality Assurance Programs.
Other duties include performing Quality Assurance reviews and audits of corporate engineering and safety related activities and conducting audits and surveillances of the nuclear fuel procurement and fabrication processes.
He delegates QA MANUAL OPERATIONS REV.
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1 Arkansas Nuclear One
authority for the accomplishment of the above activities through Nuclear Assurance, the Superintendent, Supplier Quality /*.surance and the Services Quality Assurance Supervisor.
1.4.4.1.1 Superintendent, Supplier Quality Assurance The Superintendent, Supplier Quality Assurance is responsible for the performance of supplier audits, surveys, assessments, product inspections, evaluations and surveillances for ANO, GGNS and WSES-3. He also develops, maintains and controls Qualified Supplier Lists (QSL) or Qualified Vendors list (QVL) for ANO, GGNS and WSES-3. Additional duties include the development, maintenance and control of procedures that govern the supplier quality assurance activities.
Se delegates authority and responsibility for Supplier Quality Assurance activities at ANO to the Supervisor, Supplier Quality Assurance, ANO.
1.5 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES Ap&L and Entergy Operations are joint licensees under the facility operating license condition, each responsible for specific areas and jointly responsible fer 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 services 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 services that affect the safety and integrity of the plant.
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Supp_ lier Quality Assurance personnel are responsible for surveillance / audits at vendor / contractor shops when deemed necessary, O
based upon safety significance, complexity,1 method of acceptance and
- N.)
past history of the vendor, to establish product quality and to assure-
- that quality assurance and quality control programs function in accordance with ANO requirements.
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1.0 ORGANIZATION PAGE 1-27 Arkansas Nuclear One
2.0 QUALITY ASSURANCE PROGRM)
'O 2.1 SCOPE
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This QA Program is to assure that ANO is operated in a safe, reliable and efficient manner and in accordance with NRC regulations, a'pplicable 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 included 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 l
consequences of such accidents if they were to occur.
These structures, l
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 SARs 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
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safety function as determined by Engineering are to be considered Non-Q, unless otherwise dispositioned by Engineering.
- Expendable and/or consumable itams are to include, as a minimum:
nuclear fuel, weld rods, boric acid, and diesel fuel.
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2.2.2 Expendable and/or consumable items where qcality is necessary for the performance.of Q-listed structures, systems and components are identified and controlled in accordance with Technical Specifications and/or procedures.
The-following expendable and/or consumable items are to be controlled in the following manner to assure service quality:
(1) Diesel Fuel - Service quality is ensured by applicable provisions / tests required by the Technical Specification for each operating nuclear un;t (2) Welding-Rod - Service quality is ensured by procurement from an evaluated source', requiring material test results when specified by the ASME Code or. applicable design document, and controlling the rod on-site prior to use to prevent degradation l
(3) Boric Acid - Service quality is ensured by procurement fron. an i
evaluated source, requiring a batch analysis to ensure conformance with our specification requirements, and on-site control prior to use to prevent degradatior 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 effectiveness of this quality program is verified through scheduled audits conducted by the
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- Quality Organization, under the cognizance.of the SRC.
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2.2.4 The quality program for firc protetion is addressed in Appendix B of this manual and in the applicable section.'of-the SAR and Technical Specifications 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, G
2.2.5 The SLQL (as part.of the-SAR) is under the control of the Manager, Licensing. The Licensing section maintains an up-to-date list of personnel issued a copy of the SAR for each nuclear unit and assures that L
reviews, approvals, distributions and changes thereto are performed in accordance with approved procedures.
Changes to the SLQL require review / approval b) the applicable Manager,-Engineering; Manager, Quality L
Assurance; and Manager, Licensing.
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 administrative controls of.the i
CLQL within SIMS. -Evaluations, reviews and approvals to changes to the CLQL are performed in accordance with applicable procedures.
.2.2.7 The Component Level F-list (CLFL) is maintained on the SIMS comporent data base by' Engineering. Components classified as "F" on this list fall under the requirements of Appendix B'of this manual. The controls for
-this list are similar to the controls utilized for the Q-list.
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2.2.8 Components that are not Q-listed or F-listed and which are subject to ASME code requirements or similar design standards, regulatoty 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 0-list.
This list is also referred b
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 tn various levels in all participating organizations (from the Entergy Operations President and Chief Executive Officer to all wonkers whose activities may influence quality).
The QA Program designates responsibilities and duties of specific individuals, which may be periormed by their appointed designees, 2.3.2 The QA Program assigns the responsibility for quality to the departments performing the work and includes as a basic requirement that individuals responsible for verification of conformance are qualified and do not perform or directly supervise the work. 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 QA MANUAL OPERATIONS REV.
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quality assurance programs reviewed and approved by the Superintendent.
Supplier QA. Audits or surveiliances by, Supplier QA provide assurance.
of compliance with applicable procedures.
2.3.4 The Supervisor, Core Reload Design within the Nuclear Engineering Design section is responsible for the assurance that nuclear fuel used at ANO is designed, procured, manufactured and utilized in accordance with regulatory requirements, and related industrial codes end standards.
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 flaterial (SNM).
Individuals who perform receipt inspections are qualified in accordance with paragraph 2.6.3 of this manual.
The Manager, Quality Control /
Quality Engineering 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 administration and control. The procedures state the policies and instructions necessary to fulfill the intent of-the~QA Program.
Precedures 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.
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l 2.4.2
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O Procedures assure that activities 'affecting quality are performed under 1
suitabiy controlled conditions.
Controlled conditions include the use of appropriate equipment, suitabic environmental 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 qualit.y and the need for verification of quality by inspections, evaluations or tests is taken into account.
2.5 PROGRAM REVISION AND CONTROL I
2.5.1 Program revision and control shall be the responsibility of the General Manager,Qoality, p
2.5.2 V
Proposed changes to this manual are to be submitted by tne Manager, Licensing 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 the Manager, Quality Assurance, General Manager, 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 descriptior previously accepted by the Nuclear Regulatory Commission. Changes to the program description that reduce g Entergy QA MANUAL OPERATIONS REV.
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the teamiurients are to be submitted and approved by the Nuclear Regulatory Commission prior to implementation.
The General Manager, Quality, or-his O
designee, is to determine if changes do or do not reduce the commitments O
of the QA Program.
2.6 PERSONNEL 2.6.1 Employees whose duties and responsibilities are related to the QA Program activitias at or in support of ANO are to participate 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 overail 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 0A Program related to the employee's specific job-related activity.
2.6.2 The education, experience and responsibility requirements of individuals involved in the QA Program are documented in job descriptions which are approved and periodically reviewed by management.
Requirements for education, experience and proficiency levels are commensurate with the degree of importance of the job assignment.
Experience 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 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.
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2.6.3-
..~N' l(d Personnel performing inspection and examination activities are to be indoctrinated ar.d trained to assure they are aware of the requirements which govern their activity.
Inspection and examination personnel 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 tent to related-activities occurring during initial plant design ana construction.are to meet the provisions of Regulatory Guide 1.58, Rev.1 (9/80) and ANSI N45.2.6-1978, in lieu of ANSI N18.1-1971.
2Property "ANSI code" (as page type) with input value "ANSI N18.1-1971.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..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 01.1.
Persnnnel j
involved with nondestructive examinatio.n of materials, components or systems are to meet the qualification requirements of the American Society Nondestructive Testing Recommended Practice SNT-TC-1A or ASME Section III and XI for A5ME Code materials, components or systerns.
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.
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-Personnel appointed to the SRC shall collectively have the experience and competence required by-ANSI /ANS N3.1-1981.
Personnel appointed to the PSC shall'be composed of eight members of ANO onsite management organization at the superintendent level-or above.
i 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 l
2.7.1 1he Genera! Manager, Quality-through the Manager, Quality Assurance is responsible for a review of the QA Program on an annual basis to determine the effectiveness and proper implementation of the QA Program.
.2.7.2 1
Management reviews of the status and adequacy of the QA Program are l.
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 ; DESIGN CONTROL O
3.1~ SCOPE V
Design activities are to be controlled to assure that proposed plant changes to the structures, systems, equipment and components conform to applicable regulatcry requirements and that design bases are correctly t rt. slated into appropriate design documents.
Design control activities are to be in accordance with the requirements of Regulatory Guide 1.64, Rev. 2 (6/76), unless otherwise noted in Table 1.
32 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 accordance with NRC licensing requirements.
Design activities may include calculations, analyses, materials selection, equipment arrangement and-layouts, accesstbility for inservice. inspection, and the specification of test.and inspection criteria.
Those design activities performed by J
individuals within Engineering are controlled by the use of Plant Modification Process _(PMP) control procedures and by applicab1_e F
administrative and departmental procedures.
These procedures include controls to assure that verified computer codes are certified for use and that their.use is specified.
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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.
3.3 DESIGN INTERFACE 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 involving design interface.
Coordination of the interface control is the responsibility of the originating organization's management unless otherwise specified in a procedure applicabit 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 simplified calculation methods, or the performance of a qualification testing program.
The extent and depth of design verification performed by the responsible engineering section is determined by an assigned engineering reviewer based upon the importance and complexity of the QA MANUAL OPERATIONS REV.
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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 supervised the design but who 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 Supervisors as design verifiers is to be verified by Quality personnel through scheduled audits to guard against abuse. Where 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.
3.4.3 When a. test program is used to verify the adequacy of a design, it is to include suitab_le qualification testing of a prototype or-initia!
production unit under the mo'.,t adverse design conditions and cariied 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 installation would become irreversible.
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Design work performed by organizations outside of the Nuclear Organizati.on_ is _to receive a documented review and approval by engineering personnel _in accordance with PMP control procedures and applicable departmental procedures.
3.5' DESIGN CHANGE 3.5.1 Methods for the-preparation, review, approval and implementation of design changes, including field changes, are documented in PHP control procedures and departmental procedures for Engineering.
Design changes are subject to review and verification 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 R quests (FCR) may be issued or otherwise documented by a i
cognizant engineer and transmitted with the changes for review and i
approval in accordance with PMP control procedures and applicable departmental procedures.
3.5.2 Changes from specified design inputs, such as design bases, regulatory requirements, codes and standards (including quality standards) are to be identified, approved, documented and controlled through pMP control procedures and applicable departmental procedures.
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-3.5.3-f During preparation of a design change, the responsible engineering section is to perform a review 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 is to be reviewed and approved by the PSC.
In addition, any 10CFR50.59 evaluations shall also be reviewed and approved by the SRC.
3.5.4 Design changes are also to be submitted to the Manager, Quality Control / Quality Engineering 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 Q
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.
3.7 DESIGN RECORDS The Manager, Office Services is responsible for maintaining permanent records of the design documents for the construction and testing phases, and for maintaining records of the upgradirq or modification of these documents as described in this section. The controls for maintaining these records are established by specific procedures described in
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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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d 4.0 P.RQCUREMENT DOCL' MENT CONTR01.
4.1 SCOPE Requirements for the procurement of items and services are to be clerrly stated and documented to assure that applicable regulatory requirements, design bcses, technical requirements and quality assurance criteria are included or referenced in the procurement documents.
Procurement document control activities are to be in accordance with approved procedures and are to meet the provisions set forth in NRC Regulatory Guide 1.123, Rev. 1 (7/77), 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 services from the Vendor are required, through the preparation and issuance of a Contract. The procurement of services 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 procurcment and contract administration procedures.
Purchase Orders for items are issued through the Procurement section.
Contracts for items and/or services 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 which define specific codes, standards, tests, inspections, environmental qualifications, and records to be applied and/or furnished.
For standard "off-tne-shelf" items, reference to the item's catalog number and QA MANUAL OPERATIONS REV.
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identification-number may be included on the procurement document in lieu of a design specification. New or revised specifications for replacement
.Q
-items are to be evaluated by the responsible engineering organization against the original 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.
4.2.3 Procurement documents are also to include the_ identification of quality assurance program requirements applicable to the items or services 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'P0 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 services.
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 l
The Quality Assurance section within the Quality organization, as identified in the applicable procedures for procurement and contract administration activ_ities,-is to review safety related procurement documents to assure that the required quality requirements (including source surveillance and/or inspection) are imposed on suppliers /contrtctors.
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4.4 CHANGES TO PROCUREMENT DOCUMENTS i
Changes to procurement documents are to have the same degree of control and reviey as imposed on the original documents.
Changes $uch as inconsequential editorial corrections or changes to :ommercial terms and conditions may be made by Procurement or Contract Administration personnel, as appropriate, after concurrence from the originator or organization which originated the document.
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5.0 JR$JPl!CJ10N
S. PROCEDURE
S AND DRAWINGS O
5.1 SCOPE V
5.1.]
e 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 i
changing, process monitoring, fuel 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 off-site activities in support of ANO.-
The format, content and philosophy of instructions and procedures are to comply with the guidelines in ANSI N18.7-1976 and Regulatory Guide 1.33, Rev. 2 (2/78) unless otherwise noted in Table 1.
5.1.2 O
Instructions and procedures are also provided for the control of activities relating tu the repair, replacement or modifications to ASME Code,Section III, Class 1, 2 or 3 components 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 ap;:ropriate quantitative criteria such as dimensions, tolerances and operating limits and/or qualitative criteria such as comparative workmanship samples to determine that important activities have been satisfactorily QA MANUAL OPERATIONS REV.
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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.
5.2.2 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 l
and audit by the Quality Organization.
5.3 REVIEW 0F INSTRUCTIONS, PROCEDURES !.ND DRAWINGS 5.3.1 Instructions, procedures and drawings are prepared, reviewed and approved in accordance with applicable administrative procedures.
5.3.2 Procedures identified in the Technical Specifications for each unit and l
intent changes thereto which describe activities required to impletrent the QA Program are to be reviewed by the PSC prior to submittal of the procedures to designated department head for approval and subsequent issuance. Overall Administrative procedurns (0P-1000.XXX & OP-6000.XXX l
Series) are also reviewed by the Quality Organization to verify compliance to the QA program requirements.
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5.3.3 Procedures and instructions are to be reviewed no less than every two years, or prior to 4.ach use if utilized less frequently than once 4ery two years, to determine if changes are necessary to meet NRC comn.ents and current ANO practices. Applicable procedures (i.e. those that relate to the incident cause) are to be reviewed following an unusual incident 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.
5.3.4 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 l
are to be reviewed and approved by the same organizations or groups that 1
performed the original review, unless otherwise noted in specific ANO procedures and controlled in the same manner as the original.
5.4.2 1
Temporary changes to approved procedures may be made in accordance with either the applicable Technical Specifications or appreved procedures for those procedures which are not Technical Specifications re!ated. In the event of an emergency not covered by an approved procedure, operations personnel may take ection, without obtaining approvals, to minimize personnel injury and damage to the facility and to protect health and safety.
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6.0 QQCLEENT 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 calculations, 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 prescrioe activities affecting quality is responsible for the establishment of documunt 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 individuals or groups.
6.2.2 Review of these documents for concurrence with quality-related l
requirements is to be perfort'ad by the Ouality Organization and/or by the appropriate reviewer as described in approved procedures.
6.2.3
'The Manager, Office Services is responsible for the control and issuance of procedures and revisions thereto, to assure distribution in accordance with approved procedures.
The Manager, Office Services is also responsible for the storage and control of approved historical plant documents and the storage of historical drawing records.
The General i
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Manager, Engineering is responsible for the control and issuance of drawings and revisions thereto to ensure that tl' y reflect the as-built conditions of the plant.
6.3 IDENTIFICATION Documents are to be identified by a title descriptive of their purpose or applicability and markert or stamped as to their current status (Draf t, For Information Only, Void, etc.) per departmental procedures.
Revision status of a docuent is to be identified in document registers, distribution lists and/or within the revision record page/ block of the document.
6.4 OISTRIBUTION 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 O-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 6,5 CHANGES 6.5.1 Changes to controlled document are to be reviewed and approved by the same organizations which perfor..cd the o-iginal revia and approval unless otherwise specified in departmental procedures applicable to the affected activity.
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i 6.5.2 Obt.olete or superceded documents are to be destroyed or marked to prevent inadvertent use in accordance with applicable document control procedures.
- 6. 6 STORAGE Dacuments 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.
P 5.7 VERIFICATION l
Quality personnel, through their various levels of quality review, j
surveillance, audit, and inspection activities assure proper documents are being used and made available to those individuals performing the work.
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7.0 [0RIRQL OF PURCHAS10 AATERIAL. EOUIPMENT AND SEgylfES 7.1 SCOPE The purchase of material, equipment and services is controlled to assure that, whether purchased directly or through vendors, the material, equipment and services which affect ouality conform to the procurement documents.
Procurement control includes provisions for source evaluation and selection, objective evidence of quality furnished by the contractor, surveillance ar.d 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 uniaveness and complexity of the item / service, procurement frequency with the same supplier and past supplier performance for the specific it ms or services coverad by the procurement document.
The control-of purchased material, equipment and services is to be in accordance with the requirements of i gulatory Guide 1.38 Rev. 2 (5/77) arrd;1.123, Rev.1 (7/77) unless otherwise noted in Table 1.
7.2 SOURCE EVALUATION AND SELECTION e
7.2.1 A Qualified Vendors List (QVL) is to be maintained and controlled under the direction of the Superintendent, Supplier QA.
The QVL identifies
-those vendors / contractors that have been evaluated and approved by Supplier QA to furnish material, equipment or services, and identifies any restrictions imposed on the vendor /contracter as a result of their evaluation..
7.2.2 Vendors / Contractors are evaluated and placed on the QVL by any of the l
following methods, as approved by the Superintendent, Supplier QA:
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r (1) Source survey by Supplier QA personnel to verify compliance to applicable 10CFR50, Appendix B requirements or to applicable ASME Section ill quality assurance program requirements.
(2) Evaluation and acceptance of source surveys performed by others (e.g., NVPIC, other utilities, NSSS suppliers, and prime contractors) indicating a program meeting the appropriate requirements of 10CFRSO, Appendix B.
(3) A review of the vendors / contractors current quality records supported by evidence of documented qualitative and quantitative information which can be objectively evaluated.
This includes review and approval of the vendor's/ contractor's quality assurance program, manual and procedures, when available.
l (4) Evaluation of the vendor's/ contractor's history of providing a product / service which performs satisfactorily in actual use.
Evaluation information includes:
experience of users of identical or similar products / services of the prospective vendor / contractor; and/or procurement records that have been accumulated in connection with previous procurement activities and operating experiences.
(5)
In ad/ttion te une above, for ASME Code Suppliers, verification that a /r.ndor is a holder of an ASME Certificate of Authorization issued as a result of an ASME survey.
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7.2.3 l
Vendors / contractors listed on the QVL are to be selected for procurement of material, equipment or services except for items designated
" commercial-grade" per approved procedures and as noted in paragraph 7.2.4.
Standard catalog items may be procured from a vendor / contractor not listed on the QVL provided the manufacturer of the item is on the QVL and all requested documentation originates from the manufacturer.
The Q'll is periodically reviewed and upda'.ed per applicible procedures to ensure it is maintained current.
The list of qualified vendors / contractors is available to personnel involved in the procurement process.
7.2.4 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 OVL.
The contractors work activities and personnel are to be controlled in accordance with approved procedures to assure that the contractor conforms to the procurement documents.
7.3 SOURCE SURVEILLANCE AND AUDIT 7.3.1 The effectiveness of a v?ndor's/ contractor'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 services.
This assessment may be through source surveillance, source audit, receipt inspection, independent testing or review of source documentation files.
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f 7.3.2 The need for source surveillance is determined by Supplier QA.
Source surveillance may also be requested by the originator of the PR/ Contract, or Quality Assurance section within the Quality organization during their review of the procurement document (reference section 4.3).
l Source surveillance is to be performed by Supplier QA personnel or their appointed representative in accordance with surveillance plans approved l
by t'e Superintendent, Supplier QA and the results documented por o
quality assurance procedures.
Reports documenting inspections performed and discrepancies observed are prepared by the person performing the surveillance to document compliance to the procurement documents and for future use as historical quality performance data.
7.3.3 Audits of the vendor's/ contractor's quality assurance programs are periodically performed under the direction of the Manager, Supplier QA to verify implementation of a satisfactory quality program on the items or services being procured. Audits performed by others (e.g.,
j NUPIC, other utilities, or prime contractors), as evaluated and approved by the Superintendent, Supplier QA, may be used as an alternative to audits by Supplier QA personnel to verify the vendor / contractor is implementing a satisfac'ory quality program.
Audits are to be conducted in accordance with Section 18 of this manual.
I 7.4 RECEIPT INSPECTION T
7.4.1 Materials and equipment, including ASME Code materials and equipment, are subject to inspection upon receipt at ANO.
The degree of inspection is specified in the procurement documents.
Receipt. inspection is performed in accordance with approved procedures.
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n 7.4.2 Receipt inspection activities are to be documented and include, as a minimum:
examination of material or equipment for shipping damage, proper identification and quantity; and the review of vendor documentation to verify compliance with the procurement document.
In addition, if material and equipment received at ANO were not l
inspected at the vendor's facility by Supplier QA personnel, an inspection is to be performed by qualified personnel at the point of receiving to verify that the material or equipment conforms to the inspection requirements identified in the procure" ant documents.
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.
Review 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 schedu1~4 source surveillance and audit activities or through independent testing of the item by ANO.
7.4.4 Accepted material and equipment is released, identified as to its inspection status and forwarded to a controlled storage area or released for installation per applicable approved procedures.
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7.4.5 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, or 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 accordance with approved procedures / instructions to verify conformance to procurement criteria and the validity of the vendor's certification documents.
7.5 NONCONFORMING ITEMS 7.5.1 O
Nonconformances identified by the vendor /contracto which adversely affect reliability, performance or interchangeability of the item and dispositioned repair or use-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 precured.
7.5.2 Material and equipment found to be deficient or nissing procurement documentation during receiving inspection or found-to be deficient as a result of independent testing are to be clearly identified, segregated L
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from acceptable items and dispositioned per approved procedures and as described in Section 15.0 of this manual.
O 7.6 SPARE PARTS 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 applicable quality arturance requirements and-i documentation requirements for spare parts are to be included in the i
7.7 STORAGE Material and equipment are to be handled and stored as described in approved procedures and Section 13.0 of this manual.
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J 8.0 JDENilflCAUDN AND CR!i1RQL0f MATERIALS. paris AND COMP 0NENTS 8.1 SC0pE 8.1.1 Measures for the identification and control of materials, (including consumabits), 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, I
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 t
specific inspection aed test records, when required by codes, s..ndards, specifications or proctorement documents, are to be established within approved procedures and ma ntained throughout the life or consumption of i
the item.
8.2 IDENilFICATION 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.
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Haterials, 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.
8.2.3 Identification of materials, parts and components is accomplished by either marking or tagging on the item or through records traceable to the item.
1 8.2.3.1 4
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.
LO 8.2.3.2
-When identification markings are employed, the markings are to be clear, unambiguou-and indelible and applied in such a manner as not to af fect 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 containers, r
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8.2.3.3 Identification markings are to be recorded on records or as-built documents if current markings are to be hidden or subject to obliteration by surfacie treatment or coatings during fabrication, installation, repair or modifications.
8.3 CONTROL Plant organizations receiving materials, parts and components are to verify that they are properly identified while under their conttol.
Quality audit surveillance and inspection activities ensure compliance to requirements and also ensure that :naterials, parts, and components are being identified in accordance with this manual.
,l 8.4 DEFECTIVE OR INCORRECT ITEMS 1
8.4.1
.t Defective or incorrect materials, parts and components identified by
[
plant personnel or support grouns are to be handled in accordance with Section 16.0 of this manual and approved orocedures for nonconformances and corrective action.
Defective or incorrect items are to be tagged with a " hold tag" affixed to the item or otherwise identified pea approved procedures.
8.4.2.
L Defective or incorrect iteuis are to be stored in segregated areas except for those iteins 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 CMIRQL.0f_SPECIAL PROCESSES 9.1 SCOPE Special processes are to be controlled through the use of qualified personnel and approved procedures which meet the requirements of crplicable 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 O
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 Ver.sel Code or for structural velds, the AWS Structural Steel Code 01.1, and the American Society of Hondestructive Testing Recommended Practices (SNT-TC-1A 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 QUAllFICATION 9.3.1 Special p'rocess procedures for velding and nondestructive examinations are to be qualified prior to use to ensure compliance with applicable codes, standards or specifications. Those qualifications are to be documented and also made available for review 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 supervisor O
responsible for that special process to ensure that the appropriate documents are up-to-date and personnel are periodically re-qualified and/or re-certified in accordance with approved procedures.
9.4 RECORDS The results of special processes are to be documented, reviewed, approved
.j and stored in accordance with apprcpriate approved procedures and as addressed in other sections of this manual.
9.5 VERIFICATION Performance of special processes in accordance with applicable codes, l
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 1R$fECllDB 10.1 SCOPE Inspectio55 relating to normal operating activities and inspections relating to operating activities comparable in natura and extent to those accurring 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 (2/i5), 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 services routinely assigned to the on-site nperating organization (4) Non-routine ma;.tenance 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 l
l l-Inspection activities relating to operating activities comparable in l
nature and extent to related activities occurring during design and construction (Construction Inspections) include:
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1)
Non-routine maintenance, except as noted in paragraph 10.2.1 2)
Modifications, except as noted in paragraph 10.2.1 O
The following Regulatory Guides are to be applied, as applicable, in determining the basis for required construction inspections:
R.G. 1.30, Rev. 0 (8/72); R.G.1.37, (3/73); R.G.1.38, Rev. 2 (5/77); R.G.1.39, Rev. 2 (9/77); R.G. 1.94, Rev. 1 (4/76); and R.G. 1.116, Rev. 0-R (6/76).
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 OF INSPECTIONS 10.3.1 Inspections are to be performed in accordance with approved written instructions or procedures, which set forth the requirerents and acceptance limits and specify the inspection responsibilities.
If inspections 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 the inspection and any limiting conditions (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 EnteN QA MANUAL OPERATIONS REV.
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or measuring and test equipment, such additional accuracy requirements are to be specified within those inspection prueedures)
(4) A step-by-step description of the method of inspection,
' examination, measurement or test to be performed (5)
Identification of those inspects ~n 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 10.3.2 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 i
individuals other than those who performed or directly supervised the i
-activity being inspected and do not report directly to the immediate supervisors who are responsible _ for the activity being inspected.
I 10.3.2.1 Operational inspections may be performed by second-line supervisory 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.
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10.3.2.3 If individuals performing inspections are not part of the Quality Oroanization, the inspection procedures, personnel qualification criteria,'and independence from undue pressure such as cost and schedule are to t:e reviewed and found acceptable by the Manager, Quality Assurance or Manager, Quality Control / Quality Engineering prior to initiation of the activity.
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.
10.4 INSPECTION POINTS 10.4.3 Inspection hold points are established within non-routine maintenance procedures and Plant Modification Packages (PMPs) by Engineering and
)
reviewed by the Manager, Quality Control / Quality Engineering for concurrence and possible assignment of additional inspection hold po'nts to further assure conformance with applicable instructions, procedures.
drawings and related documents or to meet appropriate code and raguhtory requirements.
Inspection hold points for work functions assorsated with activities other than non-routine maintenance and PMPs are r.stiblished by l
the originating department, Quality personnel or other ret,prAsible individuals and reviewed by the Manager, Quality Contrei/ Quality Engineering for concurrence and possible assignment ef additional inspection hold points.
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i t!ork is not to proceert past a designated inspection hold point until signed by a qualified inspector or waived, in writing, by the Manager, Quality Control / Quality Engineering.
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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 item or activity, past performance of the item or activity and the ability to verify quality by job-site testing.
I 10.4.3 Inspection responsibilities, requirements, information and acceptance criteria for the work activity are to be identified in appropriate, approved documents (e.g. procedures, checklists, etc.).
' u. 4. :o Rr 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 review and assignment of inspection hold points.
The depn tment responsible for the work activity 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 j
waived by the Code Inspector.
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1 10.5 DOCUMENTATION 10.5.1 Inspections and process monitoring activities are to be performed and the results documented in accordance with approved procedures or instructions.
Records are to:
provide objective evidence that the inspections and monitoring activities were 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 review.
10.5.3 The results of inspection 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 manua'.
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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i 11.0 TEST CONTRQl, 11.1 SCOPE A test program is to be established to assure that testing required to demonstrate that an item will perform satisfactorily in service 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 reouired as a result of modifications, repairs or maintenance.
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.nd 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 this manual and in the applicable Regulatory Guides pertaining to quality assurance requirements for testing activities.
11.2.2 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 11.3.1 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 perform major testing at specified power plateaus.
11.3.2 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.
11.3.2.1 Mandatory in-plant surveillance tests and inspections required to assure operation within the limiting conditions of operation are identified in the Technical Specifications applicable to each unit.
To ensure that the required tests are performed as scheduled within the specified time interval, surveillance procedures are established and maintained for mandatory surveillances identified in the 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.
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11.3.2.2 Inservice inspections required to meet the requirements of ASME Boiler and Pressure Vessel Code,Section XI, are to be identified in the Inservice' Inspection (ISI) Programs applicable to each unit.
l Engineering Programs is to establish and maintain an ISI plan for each unit.
The plan specifies the inspection items, inspection procedures, l
inspection intervals and types of inspections.
Engineering Programs is to coordinate the implementation of the ISI plans at appropriate scheduled outages.
The plans are also to be made available for review by the Code Inspector.
11.3.3 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.
11.3.4 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 raet:
(1) Test equipment and measuring devices are calibrated in accordance with the requirements of Section 12.0 of this manual and are functioning properly (2) Test 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 QA MANUAL OPERATIONS REV.
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(4)' Test prerequisites completed (5) When accuracy requirements for tests exceed the accuracy of p
normally-evailable process or measuring and test equipment, M
such additional accuracy requirements are to be specified
'within those test procedures 11,3,5 Testing e.ctivities are to be subject to sur"eillance/ 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 b he Code Inspector.
The assignment of inspection hold points !< 6 ;cribed in Section 10.0 of this
- manual, 11.3.6 Test results are to bc documented in accordance with the applicable procedures / instructions.
Test docur
.s are to contain at least the following:
b (i)
Identity of item tested (2) 'Date of test (3) As-found condition (4)
Identification of individuals performing test (5)
Test results (6) Corrective actions performed, if any (7) As-left condition
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11.3.7
.O 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.
11.4 RECORDS Test results are to provide objective evidence that the testing was performed in coinpliance 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 EQUIPMENT 12.1 SCOPE _
12.1.1-A program is established to assure that devices used for measurements, tests and. calibrations 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 L/
to comply with the prosisions of Regulatory Guide 1.33, Rev. 2, Appendix A, Section 10.0, and performed in accordance with chemical and radiochemical control' procedures.
12.1.3 This section _does -not apply to rulers, tspe measures, levels or other such devices-where normal commercial practices provide adequate accuracy.
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12.2 RESPONSIBILITIES--
12.2.1-L The cognizant supt-rintendents/ group supervisors are responsible for.
establishing and' maintaining lists of measuring and test equipment under a
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12.0 CONTROL OF MEASURING PAGE 12-1 AND TEST EQUIPMENT
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their control that require periodic calibration and for the calibration of this equipment, as assigned within approved procedure:.
12.2.2 The cognizant supervisor is responsible for identifying measuring and test equ.pment riauired for the activity and assures that the devices are used only by qualified personnel.
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.?.4 The Quality Organization is responsible for monitoring test equipment control and use in order to verify compliance with the program.
O 12.3 GENERAL 12.3.1 Calibration procedures are to be established for each type of measuring and test equipment.
These procedures are to conform to recognized codes and standards and to local, state and federal regulations and are to be referenced on the calibration reports / logs.
12.3.2 Measuring and test equipment are to be properly controlled, calibrated and adjusted at specific intervals or prior to use to assure the necessary accuracy of calibrated equipment.
Calibration intervals are to O
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Arkansas Nuclear One l
be based upon the type of equipment, manufacturer's recommendations, stability and reliability characteristics, required accuracies, use and Q
other conditioni affecting calibration.
V 12.3.3 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 fot., times that of the measuring and test equipmer.t.
In any instance where the four times criteria is unable to be met, standards are to have an accuracy level, acceptable calibration range and precision equal to or better than those required for the ranges affected by the calibration.
Accuracies less than four times will be acceptable when warranted by statistical analysis or limited by the state-of-the-art as auth<arized by responsible management.
Reference standards are to be maintained in an environment with temperature, humidity and cleanliness :ontrols compatible with maintaining accuracy and operating characteristics of the standards.
O 12.3.4 When measuring and test equipment are found to be out of calibration, an evaluation of the validity of previous 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 eithtr insta 1ed or calibrated equipment is questionable.
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12.0 CONTROL OF MEASURING PAGE 12-3 Arkansas Nuclear One
12.4 EQUIPMENT IDENTIFICATION 12.4.1 Measuring'and test equipmert lists are to contain sufficient information to uniquely identify each item listed and is to include, as a mininium, calibration intervals, tolerances and storage locations.
The lists are also to identify the group responsible for the control of each item.
12.4.2 Items listed on measuring and test equipment lists are to be tagged, labeled or otherwise identified per approved procedures in such a manner that c1carly identifies the equipment and their calibration status and provides traceability to the calibration records.
12.4.3 Measuring and test equipment found to be out of calibration is to be tagged ard segregated from acceptable equipment in accordance with approved procedures until repaired and/or re-calibrated.
12.5 RECORDS Calibratien documentation is to be maintained to verify calibration status, condition, accuracy and out-of-tolerance trends of the equipment.
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12.0 CONTR0!
MEASURING PAGE 12-4 Arkansas Nuclear One AND TE51 t0VIPMENT
14.0 INSPECTION. TEST AND OPERATING STATUS 14.1 SCOPF 14.1.1
~
The removal from service, 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 contrc1s 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 theii intended function.
14.2 EQUIPMENT CONTROL 14.2.1 Prior to removal of equipment, components or systems from service for maintenance, modification, repair, test or inspection activities, permission is to be received and documented from the appropriate Supervisor, Shift Operations.
The Supervisors, Shift Operations are to assure that the item can be released without affecting plant safety.
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14.0 INSPECTION, TEST AND PAGE 14-1 Operations OPERATING STATUS Arkansas Nuclear One
14.2.2 OD-The status of equipment, components and systems during these activities is to be identified in accordance with approved procedures / instructions, which contain, as a minimum, the following:
(1) Methods for control of equipment to maintain personnel and reactor safety and to avoid unanthorized operation of equipment or systems (2) The use of markings or other suitable means to indicate the status of activities being performed upon individual items.
Suitable means are to include identification numbers which are traceable to records or to the status of these activities (3) Provisions for the identification of items which have satisfactorily passed the required activities.
In rases where required documentary evidence is not available, the associated equipment.or system is to be considered nonconforming and N
handled in accordance with Sect on 15.0 of this manual V
(4) Provisions for independent verifications to ensure that necessary measures (locking or tagging) to secure and identify equipmant or systems in a controlled status have been implemented correctly 14.?.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 !Ystem is reclosed.
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14.0 INSPECTION, TEST AND PAGE 14-2 Operations OPERATING STATUS Arktr.sas Nuclear One
14.2.4
. (}
During maintenance or modification activities, certain portions of V
systems, as ldentified in approved procedures, may be subject to potentia 1' 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, electrical jumpers, 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 the temporary modification program shall delineate requirements to:
(1) maintain appropriate status logs of temporary modifications,
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(2) perform independent verification of temporary modifications, by an l-individual cognizant of the purpose and effect of the temporary modification, and (3) document temporary modifications to assure the r'equired actions are taken to return the equipment or system to its original operating configuration and status, f -
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14.2.6
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When equ!pment or a system is properly identified as being ready to be returned to service, the appropriate Supervisor, 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 documented to verify current status of the item.
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 proceduras and Section 15.0 of this manual.
14.3 MAINTENANCE CONTROL 14.3.1
/O In addition to the requirements and controls identified in V
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 quality 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 performance and procedures for repair of equipment are to be improved as directed by the appropriate Manager, Maintenance.
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- Operations OPERATING STATUS Arkansas Nuclear One
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t 14.3.2 A preventive maintenance program, including procedures and instructions for-systems, structures nd 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 ruintenance program requirements, including associated engineering evaluations, procedures and instructions associated with the preventive maintenance program will be maintained under the Manager, Central Support.
Implementation of the program is the responsibility of the appropriate Plant Manager and is' implemented by qualified maintenance personnel in accordance with approved procedures and instructions which specify the work activities, acceptance requirements and the control measures to assure adequate quality. When equipment malfunctions occer, 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 The Supervisors, Shif t Operations are providec; suf ficient 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 maintain a ready reference of plant systems, equipment and component alignments, as well as a status board summary of their conditions.
l-l l-14.4.2 The turnover of duties to personnel on succeeding shif>.s 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 affect the performance of their duties) and transfer of authority.
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14.0 INSPECTION, TEST AND PAGE 14 - 5.-
Operations OPERATING s1ATuS Arkansas Nuclear One -
16.0 LORRECTIYE ACTION
.O 16.1 SCOPE V
A corrective cetion system is established to assure that conditions adverse to plant safety, such as failures, malfunctions, deficiencies, deviations, defective materials and equipment, abnormal occurrences 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 review.
16.2 GENERAL 16.2.1 When deviations, deficiencies, malfunctions, nonconformances or other abnormal occurrences or conditior,s are encountered,- they are to be
!O reported to responsible authorities for review and disposition in iV accordance with approved procedures.
16.2.2 Cognizant supervisors are to review discrepancies discotered during 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 l-individual / group identified within approved procedures to determine its l
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16.0 CORRECTIVE ACTION PAGE '16-1 Arkansas Nuclear One l
adequacy and completeness and to assure the need for additiona 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.
e 16.2.4 If agreement upon the resolution cannot be achieved, the condition it to be referred to the appropriate level of management as specified in approved procedures.
-16.3 SUPPLIER DEFICIENCIES When vt:ndors furnish products or services that do not conform to the requirements of the applicable purchase contract and, in the opinion of Supplier QA, warrants additional evaluation, Supplier QA will evaluate j
the venoor's past performance using available information such as audits,-receiving inspection reports,-industry notices, etc.
Results of I
the evalu'ation will be used to determine the status of the vender, 16.4 SIGNIFICANT CONDITIONS
.Significant conditions adverse to safety are to include, as a minimum, the following:
(1) Conditions that have a direct adverse effect on the safety of the plant per the plant Operating License and Technical y
Specifications (2) Conditions that have caused the uncontrolled release of radioactive materials (liquid, solid, gaseous or air j
particulate) to the environs (3) Adverse quality trends which could lead to unsafe plant operations-l' ALb g Entergy QA MANUAL OPERATIONS REV.
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16.0 CORRECTIVE ACTION PAGE 16-2 Ar%..: as Nuclear One
IE,5 rep 0RTABLE 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 NRC.
16.5.2 Upon determination that significant adverse condition is reportable, the Manage, Licensing ensures that the appropriate report is initiated and subsequently transmitted to the NRC.
16.5.3 The PSC reviews Root Cause and Corrective Action plars for r oortable events-through_its review of Licensee Event Reports (LERs).
16.5.4 The Licensing Department is responsible for transmitting approved reports to the NRC yithin the time period-specified in the Technical Specifications and approved procedures.
16.6 VERIFICATION Verification by sur.a111ance or audit of the effective implementation of
' corrective actions is to be periodically performed and-documented by l
responsible-Quality personnel.
Audits are to be performed in accordance-with Section 18.0 of this manual.
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16.0 CORRECTIVE ACTION PAGE 16-3 Arkansas Nuclear One ~
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18.0 AW115 18.1 SCOPE
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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 portions of-Reguiatory Guides 1.144, Rev. 1 (9/80), and-1.146, Rev. 0 (8/80), unless otherwise noted in Table 1.
18.1.2 The audit program is to include provisions to determine the compliance
~
with and effectiveness of the OA Program in controlling structures, systems, components and activities in accordance with the rules set forth in the codes, standards and regulations identified in the Introduction of this manual.
18.2 AUDIT PERSONNEL 18.2.1 The Manager, Quality Assurance and the Superintendent, Supplier QA 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 rep:rt to a management representative who has direct responsibility for the activity being audited.
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18.0 AUDITS PAGE 18-1 Arkansas Nuclear One
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18.2.2 Auditors assigned auditing responsibilities are to have experience and training commensurr.te_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 p.tinent expertise, personal characteristics, education and capability.
It no one within the Quality Organization 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 perforining the required audits.
Proficiency of audit personnel is mainte.ined by one or more of the following methods:
(1). Regular, active participation in the audit process -
(2) Review and study of codes, standards, procedures and instructions (3) Participation n training e orientation programs 18.3 AUDIT SCHEDULE 18.3.1-Audits are 'o be t wf,rmea on & % anned and periodic basis in accordance with an audit sched..u. Audit schedules are to be prepared at the
]
beginning of each rear by the Quality Organization and approved by the Manager, Quality
-sace, General Manager, Quality and the SRC.
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18.0 AUDITS PAGE 18-2 Arkansas Nuclear One
18.3.22 Audit schedules assure that, as a minimum, those audit areas ideniified within.the Technical Specifications applicable to each nuclear unit are audited,Onderthe.cognizanceoftheSRC,attheindicatedfreque1cies within'ANO.
18.3.3~
. 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-their 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 app"oved by the Superintendent, Supplier QA.
18.3.4 Periodic reviews of the audit programs are to be performe'd by the SRC or
-their appointed management representative at least semiannually to assure l -:
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.
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18.0 AUDITS PAGE 18-3
- Arkansas Nuclear One
.18'4 AUDIT IMPLEMENTATION
_18.4.1
--Audit plans and checklists are to be prepared by the auditor _and approved
.l by the responsible Quality management, or designee, prior to performing the audit, Checklists are to be used to ensura 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 scope and date (2)
Identification of the auditor (s)
(3) A summary of audit results (4) Details of nonconformances or programmatic. deficiencies (5) Recommendations for correcting nonconformances or improving the l'
QA Program, as appropriate i-18.4.3 i
Deficiencies identified as a result of an internal audit are to be l
recorded on a Quality Assurance Finding-Report (QAFR) by the auditor and-l issued to the Department Head responsible for the area audited for E
-corrective action. 'The Department Head or the assigned designee is to provide prompt corrective action to the deficiencies identified and document on-the AFR the action taken.or to be taken to preclude recurrence. ' Appropriate follow-up including re-audits by the assigned
'-audit grou,, is conducted in the deficient areas to verify proper and timely implementation of corrective action commitments.
Follow-up l
- [
-actions are to be documented on the QAFR.
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18.0 AUDITS PAGE 78-4 Arkansas Nuclear One
18.4.4 Internal audit reports pertaining to plant operations activities are to be independently reviewed by the SRC to determine 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 repor*- are to be distributed, as a minimum, to the General Manager, Quality, Manager. 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 per>onnel are to be recorded and distributed to the M6 nager, Quality Assurance 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 ver iied by Supplier QA personnel and documented.
18.5 RECORDS Written internal / external audit reports, including checklists, QAFR's, vendor / contractor findings, and related documentation supporting the follow-up activities are to be forwarded to the Document Control Center for storage in accordance with Section 17.0 of this manual.
/3
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18.0 AUDITS PAGE 18-5 Arkansas Nuctsar One r
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18.6 NUCLEAR FUEL AUDITS-l The Supervisor, Services QA, 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, star.Jards and specifications.
Services QA monitors the design and fabricatiei of the fuel through a program of audits of the fuel fabricator, including both design review audits and fuel l
fabrication audits.
Services QA also conducts audits of component suppliers as deemed necessary to assure the quality of the fuel, and issues formal audit reports to document eudit activities and to identify nonconformances or other items requiring action by the fuel fabricator.
Resolution of nonconformances or other items requiring action is
.l verified by Services QA and documented in follow-up reports.
The ANO Manager, Quality Assurance is on distribution for all audit and follow-up reports. These audit reports are to be forwarded to ANO and stored in accordance with Sectiori 17.0 of this manual.
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18.0 AUDITS PAGE 18-6 Arkansas Nue! ear One
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-TABLE 3 QUALITY PROGRAM POLI R
DURES AND INSTRUCTION I.
Qualliv Assurance Manual Operationi 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 i
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-relate 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 s
are also reviewed by the Manager, Quality Assuran'ce to assure that the QA Program commitments are met.
Review and approval of Quality administrative procedures is described in paragraph 4 below.
3.
.Deoartmental 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 responsibilities within the QA Program.
Each Department Head is responsible to perform a review of their procedures to assure conformance with the QA Program.
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Operations SECTION:
TABLE 3 PAGE T3-1 Arkansas Nuclear One
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Procedures required by the Technical Specifications are reviewed by the; Plant safety Committee.
Department procedures are approved by IO the appropriate Department Head.
V.
l 4.
Quality Procedures l
l The Quality Organization employs a system of procedures developed to assure proper implementation of the QA Program.
These procedures provide technical and administrative instructions to the l
Quality staff to aid in implementing their responsibilities within the QA Program. These procedures are reviewed / approved by the Manager, Quality Assurance and/or Manager, Quality Control / Quality Engineering and the General Managur, Quality.
The Suppler QA organization employs a system of procedures dev. sloped to assure implementation of their resnonsibilities within the QA Program.
Supplier QA management assure conformance with the QA Program.
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APPENDIX B-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 staffing 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 consequences 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 i.
protection and detection systems, and those structures and components (such as fire doors, fire dampers, and penetration sesis) which, as identified in the plant's Fire Protection L
Program Manual, are required to restrict the damage caused by a single exposure fire to safety-related equipment and equipment required to achieve and maintain safe plant shutdown to within those limits set forth in Section 1 of Appendix R to 10CFR50.
1.3 The quality program f_or 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.
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Operations FOR FIRE PROTECTION Arkansas Nuclear One L.
i 1.4 With respect to regulator y ommitments, ANO is committed to I
implementing the requiren..c.;, of the following, subject to exceptions noted in this Appendix:
'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:
III.G.
Fire Protection Safe Shutdown Capability Ill.J.
Emergency Lighting Ill.L.
Alternative and Dedicated Shutdown Capability 111.0.
Oil Collection System for Reactor Coolant Pumps O
1.5 Other fire protection commitments are contained in the following references and documents:
1.
Facility Operating License (s) including Technical Specification (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), identified in Division 4.0 to the Fire Protection Program Manual (FPPM).
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___..m_.__
t 1.6 The?above requirements are implemented by controlling activities as described in this manual and appendix and by procedures referenced in this manual and appendix..
2.0'ORGAAIZATION 2.1 The organizational structure and responsibilities of key personnel associated with the administration, imple' mentation 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 Director, Operations is responsible for the overall administration and implementation of plant operations and l
training in accordance with the fire protection program.
I He reports directly to the Vice President. Operations ANO.
3.
The Manager, Engineering Standards and Programs 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 l
of the program at the plant, such as evaluation of fire detection and suppression equipment, fire barriers and alternate shutdown equipment protection.
The Manager,
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L
-~_
q Engineering Standards and Programs reparts directly to Reporting to the the General Manager Engineering, Manager, Engineering Standards and Programs is the Under his Superintendent, Engineering Programs.
The direction is the Supervisor, Fire Protection.
Supervisor, Fire Protection is responsible for:
Implementing, maintaining and assessing the fire (1) prevention aspects of the program as defined in plant procedures Performing fire protection evaluations (2)
Developing inspection and surveillance criteria (3)
Coordinating ANI fire protection inspections at the (4) plant Providing guidance and technical support to the (5) nuclear plant in the area of fire protection Assuring that applicable regulatory requirements are (6) included in the fire protection program Assuring design reviews for fire protection (7) modifications are performed Assuring that evaluations / assessments of the fire (B) protection program are performed and results reported to management Maintenance and revision of the Fire Protection (9)
Program Manual t
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PAGE AB-4 APPENDIX B - QUALITY PROGRAM 9&T Entergy FOR FIRE PROTECTION SECTION:
J Operations i
j
, Arkansas Nuclear One
~_
~(30) Classification of F-list components for the-component level F-list 4.
The General Manager, Quhlity is responsible for assuring that the fire protection program is implemented in a,:cordance with the QA Manual Operations, Ter iical-Specifications and applicable procedures.
This is accomplished by the performance of audits and other provisions of the QA Manual Operations.
He shall assure that corrective action, when necessary, is taken.
He reports directly to the Vice President, Operations.
1 5.
The Manager, Licensing is responsible for providing other responsible organizations with regulatory information and int'rpretations on regulatory issues related to fire pcctection. 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 of license-based documents relating to fire protection.
He reports directly to the Vice President, Operations ANO.
6.
The General Manager, Engineering is responsible for assuring that the technical requirements specified in the Operating License, Technical Specifications and other-design basis documents, with respect to fire protection,-
have been satisfied in design modificacions and design documents affecting ANO.
He reports directly to the Vice president, Operations ANO.
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j 3.0' DEALITY ASSURANCE PROGRAM-3.1 This quality program is to ensure that the fire protection
~
systems for safety-related areas (as defined 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 effeci.iveness of the fire protection program is verified through curveillances and scheduled audits conducted by the NQ 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 of industrial 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 Manager, Training and Emergency Planning has the overall responsibility for these training programs.
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4.0 DESIGN CONTROL =
0 Section 3.0 of this manual-is applicable for design control 4.1 activities pertaining to the fire protection system.
9 5.0 P_ROCUREMENT'00CUMENT CONTROL 5.1 The control of procurement documents for fire protection related materials, parts and components 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 requirement 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 DRAWINGS 6.1 Inspections, tests, administrative controls, fire drills and training that govern the fire protection program are q
prescribed by documented instructions, procedures and drawings O
and are accomplished in accordance with these documents. A listing and brief description of procedures relating to fire protection activities are provided in the AN0 Fire Protection Program Manual.
Instructions, procedures and drawings are prepared, reviewed, approved and revised in accordance 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.
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i 3.0' CONTROL OF' PURCHASED MATERIAL. EOUIPMENT AND SERVICES j
8.1 The control of purchased fire protection related materials, equipment and services 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 services not associated with the Q-list, the vendor / contractor qualification criteria (including periodic reassessment of their program) is not required.
Nonconformances dispositioned repair or use-as-is by the vendor are to be submitted to and accepted by AND only when so designated on the procurement document.
9.0 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS 9.1 Section 8.0 of this manual is not applicable for the
-r identification and control of materials, parts and components related tc the fire protection system.
No particular requirements for this section have been identified in BTP-APCSB 9.5-1, Rev. 2.
The identification and control of materials, parts and components are conducted in accordance with existing procurement and materials management procedures and practices, 10.0 CONTROL OF SPECIALfROCESSES 10.1 Section 9.0 of this manual is not applicable for the control of special processes, es applicable to 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.
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11.0 INSPECTION 11.1 Inspection activities applicabie 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 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 perfcrm inspections only need to meet paragraphs 10.3.2 and 10.3.2.1.
In addition to the provisions of this manual, inspections and surveillances are addressed in applicable portions of the Fire Protection Program Manual and the Technical Specifications for each nuclear unit.
12.0 TEST CONTROL 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 Technical Specifications for each nuclear unit.
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6 13.0 CONTROL OF MEASURING AND TEST E0QlPR EI t
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 ljAMQLING STORAGE AND SHIPPIN(i 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 contrclied in accordance with applicable approved procedures and practices.
15.0 INSPECTION. TEST AND OPERATING STATUS O
15.1 Measures are established to provide for the identification of items 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 16.0 NONCONFORMING MATERIAL. PARTS AND COMPONENTS 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 evception of subsection 15.3, when the item is not associated with the Q-list.
Vendor nonconformances are to ba submitted to ANO only when so designated on the procurement document.
17.0 CORRECTIVE ACTIONS 17.1 A corrective action system is established to ensure that conditions adverse to fire protection, such as failures, malfunctions, deficiencies, deviations, 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 QVL.
18.0 OVAllTY ASSURANCE REC.QEDji 18.1 Records which furnish evicience 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. A listing of documents and records (inclucing calculations, test reports, code reports and design change packages) relating to fire protection is included within the ANO Fire Protection Program Manual.
QA MANUAL OPERATIONS REV.
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1 19.0 MQllS 19.1 Audits are to be conducted and documented to verify compliance U
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, audits of the fire protection program are to be scheduled at specified frequencies in accordance with the Technical Specifications applicable to each nuclear unit.
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