0CAN098809, Forwards Rev 10 to QA Manual Operations. Rev Pertains Primarily to Organizational Changes & Changes to Reflect Current Practices in Implementing Manual Requirements
| ML20058K012 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/09/1988 |
| From: | Howard D ARKANSAS POWER & LIGHT CO. |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 0CAN098809, CAN98809, NUDOCS 8809300141 | |
| Download: ML20058K012 (1) | |
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p' q 4 mW e w~ oY5Mb-POST Omet 90X 561 UTTLE PT da 22203 (Boi)377 4o00 Septerbei % 488 BCAN998859-Mr. Robert D.-Martin Re U.gional Administrators. Nuclear, Regulatory Commission Region IV. 611 Ryan 'laza Drive, Suite 1000 Arlington,TX 76011
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. OPR-51 and NPF-6 Quality Assurance Manual Operations, Revision 10 g
Dear Mr. Martin:
j In accordance with 10CFR50.71, attached is Quality Assurance Manual Operations The(QAMO).your coay of10 Revisioni10 to t c1anges made in Revision to the subiect manual have been evaluated as required by 10CFR50.54(a) to determinelfqualitycommitmentshavebeenreduced. Results of our evaluation have-determined that these-changes do not reduce any commitments o in the Quality Program description previously accepted by the NRC. Revision 10-pertains primarily to organizational changes and changes to reflect our current practices in implementing the requirements of this manual. The record of revisions section of the manual identifies changes implemented by this revision. Please replace all pages in your controlled copy of the QAMO and indicate receipt of this revision by signing bel'ow aad returning this transmittal
>1etter to Ms. Sally Benson, Licensing Section, P. 0.- Box 551, Little Rock, ()
, Arkansas-72203.
Ver truly yours,
' A bh fu Dan R. Howard Manager, Licensing ORH:SAB: 1g i
Attachments Copy No. Signature Date-8809300141 880909 m , DR ADOCK 050 3 vsMesa uom.a sovv i uTuties sysTsu Nd 2P:0T 06, BT .LQL_ _ J:
_ R_fCORD OF RFVISIONSy
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REVISION - 3 NUMBER- DESCRIPTION DATE OCT 3 01990-0 Initial. Issue j 6/11/74 1 Response to AE i 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- i 2/7/75. Procedure Numbers 1005.xx changes to 1004.xx (Number Change Only).
r 3 General revision to change AEC to NRC,- 9/8/76 update organization, reflect NSP-revisions, minor program implementation ' changes.- t 4 Eliminate Quality Assurance Committee 9/8/77 J Changes to Procurement Control - Qualification of Vendors. Organizational Changes. Incorporate Technical ; Specification Changes.- 3 5 Incorporate Organizational Changes 10/10/80 b and responses to subsequent NRC Questions. Incorporate Regulatory , Guides and retype document in its entirety in standardized format. 6 Incorporate organizational changes, 5/30/84 ; delete procedural references. j throughout manual, and accurately i reflect current regulatory commitments ._ and QA practices related to the I safe operation of AP&L nuclear plants. I Manual has been reformated and retyped in its entirety. ' 7 Changes given below are identified 05/31/85 on the pages by a bar in the left margin, placed next to the affected ; area. 5 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 i 1-10 3-3 13-2 T3-1 QA MANUAL OPERATIONS REV.: 10 ANO DATE: 08/31/88 SECTION: RECORD OF REVISIONS PAGE: RR-1
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RECORDOFREVISIONSl . p = ; REVISION NUMBER'- DESCRIPTION .DATE
-7.(Cont.): 1-12 3 13-4 T3-2 1-18= 4-2 15-2 T3-3 l 1-19 5-2 15 1-20 5-3 15 l 1-22 5-4 4 + 1-23 .6-2 16-1 7-2 T1-6 9-1
- Page C-7: revised definition 4 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 L :added paragraph 1.4.2.1.3 I l- : paragraph 1.4.2.3 redesignated '
1.4.2.2 and revised i 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 l L Page'l-14 & 15: revised para,raph 1.5.3 . to delete Planning / Scheduling Supervisor l 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 f l1 2.2.3 and revised .
! Page 2-2: paragraph 2.2.3 redesignated p 2.2.4 L Page 2-2: paragraph 2.2.4 redesignated L 2.2.5 i Page 2-2: new paragraph 2.2.2 added e Page 2-3: revised paragraph 2.2.5(2) 1. " 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 4 Page 15-1: revised paragraph 15.2.1 Page'18-3: revised paragraph 18.3.2 l- Pages 18-3 to 18-6: paragraph locations changes Page F+1: revised Figure 1 QA MANUAL OPERATIONS REV.: 10 [ L, ANO Arkonsos Nuclear One SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-2
m . . _ _ _ _ _- f! e RECORD OF REVISIONS , REVISION : ; NUMBER: DESCRIPTION DATE 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 AA-1 to AA-3: new Appendix A added Page AB-1 to AB-8: new Appendix B added
- l 8 -. Changes given below are identified 06/10/86 on the pages by a bar.in the left margin, placed next to the affected area.
Corrected by errata (including misspelled words) on the following pages: A-1 5 16-1 17-5 B-1 6-1 16-3 AB-2 I 2-1 7-5 17-1 AB-4 I 2-6 11-5 17-2 AB-10 3-5 15-1 17-4 AB 1 ~l 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 ' l Page C-9 _: Revised definition i L Pages 1-1 : Rewritten to reflect L to 1-23 new organization L Page 2-1 : Revised paragraph 2.2.1 , i
- Added-paragraph 2.2.2 Page 2-2 : Paragraphs 2.2.3 and 2.2.4 l
L were 2.2.2 and 2.2.3
- Revised paragraphs 2.2.3 and 2.2.4 1 l
L QA MANUAL OPERATIONS REV.: 10 ANO Arkansos Nuclear One SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-3 i
a RECORD OF REVISIONS REVISION-NUMBER DESCRIPTION .DATE .- 8-(Cont.) 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, . -ti tl e . change 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 l
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1 Page 2-6 : Revised paragraph 2.5.2 and 2.6.1 1
- Title change, paragraph 2.5.3 Page 2-8 :New paragraph 2.6.6 added l
- Paragraph 2.6.7 was 2.6.6 l Revised paragraph 2.6.7 & 2.7.1 jl 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 paragraph 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.
u- Page 5-4 : Revised paragraph 5.4.2 . p Page 6-1 : Revised Paragraphs 6.1 & 6.2.2 ' L Page 6-2 : Title change, paragraph 6.2.3
- Added paragraph 6.2.4 Page 7-1 : Title changes, paragraph 7.2.1 -
p & 7.2.2 L Page 7-3 : Revised paragraph 7.2.3 i' : Title change, paragraph 7.3.1 L Page 7-4 : Title changes, paragraphs 7.3.2
& 7.3.3 l= Page 7-5 : Revised paragraph 7.4.3 i 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 QA MANUAL OPERATIONS REV.: 10 > ANO Arkansas Nuclear One SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-4
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N I RECORD OF REVISIONS REVISIbN l
+ a NUMBER DESCRIPTION- DATE 8 (Cont.). 'Page 15-1 : Revised paragraph 15.1, 15.2.1 J
&'15.2.2
& 15.2.2 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 -i
- Moved old subsection 15.3 L .
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 l Page 16-1 : Revised paragraph 16.2.1
& 16.2.2 Page 16-2 : Deleted paragraphs 16.2.4
& 16.2.4.1
- Paragraphs 16.2.4 & 16.2.5 were ,
16.2.4.2 and 16.2.4.3
- Revised paragraphs 16.2.3, 16.2.4 & 16.2.5 -
- Subsection 16.3 was 16.2.5 with revisions Page 16-3 : Subsection 16.4 was 16.3 ;
- Revised paragraph 16.4(1) & (3)
- Subsection 16.5 was '16.3.2 and- 3 and. Subsection.15.3 Page 16-4 : Subsection 16.6 was 16.4 i Page 17-4 : Title change, paragraph 17.3.4
- Revised paragraph.17.4.1.2 1
Page 18-1 : Title change, paragraph 18.2.1 - Page 18-2 : Title change, paragraph 18.2.2 ,
- Revised paragraph 18.3.1 Page 13-4 : Title change, paragraph 18.4.1 3 Page 1.0-5 : Revised paragraphs 18.4.4, 18,4.5 & 18.5 Page 18-6 : Revised paragraph 18.6
- Page F1
- Revised organization charts j Thru F-8
- L Page T1-1 : Revised first paragraph, third L celumn p Page T1-2.: Add ANSI N18.7 (Sections 5.2.7.1)
Page T1-3 : Add ANSI N18.7 (Section 5.2.17) l L Page T2-1 : Revised Table 2 ) 1 1 Page T3-1 : Revised all paragraphs Page T3-2.: Revised all paragraphs L- Page T3-3 : Deleted i I' QA MANUAL OPERATIONS REV.: 10 ANO Arkonsos Nucl eor One SECTION: RECORD OF REVISIONS DATE:'08/31/88 PAGE: RR-5 i
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RECORD OF REVISIONS I<EVISION
' NUMBER DESCRIPTION- DATE
'8 (Cont.)- Page' AA-1 : Revised paragraph I'.1 Page AA-2 : Revised introductory paragraph Page AA-3 : Revised Section 12
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Page:AA-4 :Added ! Page AB-3 : Title change, paragraph 2.1(1) '
- Revised paragraph 2.1(2)
Page AB-4 : Title 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 lef t margin, placed next to the affected area. . Corrected by errata (including misspelled-words) on the-following pages: ; B -C-10 10-5 ' C-1 1-4 AA-2' C-2 5-4 AA-3 J C-6 7-5 fi Page A-1:
Title:
change in 2nd paragraph ' l Page A-2: Resigned Policy i Page B-5: Clarify ANO Unit 2 Code : Commitments Page C-1: Added definition 4 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 I paragraph 1.4.1.3.2. Changed name title L u
. QA MANUAL OPERATIONS REV.: 10 ANO
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RECORD OF REVISIONS ! REVISION p NUMBER DESCRIPTION .DATE-k' _.9 (Cont.) Page 1-14: Revised responsibilities 7/22/87 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
-paragraphs 1.4.1.3.2.3.3 and 1.4.1.3.2.4 i 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 1! name title
-Page 1-19: Clarified paragraph J Page 1-20: Revised responsibilities ;
Page 1-21: Revised responsibilities in paragraph 1.4.2.2 'j Pages 1 . 4 thru l-23: Paragraph 1.5 deleted and ' paragraphs.l.6, 1.6.1, 1.6.2, j 1.6.3, and 1.7 renumbered I accordingly i
.Page 1-22: Changed name title:
Page 2-1: Revised paragraph 2.2.1 Page 2-3: Revised paragrapn 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 l Page 3-5: Changed name title Page 4-1: Changed titles
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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-m Page 7-2: Revised paragraphs 7.2.2(1) and 7.2.2(5). Deleted 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 Page 13-4: Revised paragraph 13.5.3 7/22/87 ;, Page 15-2: Changed name title QA MANUAL OPERATIONS REV.: 10 A Arkansas Nuclear Dne SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-7
RECORD OF REVISIONS s i REVISION i NUMBER. DESCRIPTION. DATE i 9 (Cont.) Page 16.1: . Revised paragraph 16.2.2 4
-Page 16.2: Deleted paragraphJ16.'2.3 and- j renumbered 16.2.4 and 16.2.5 ,
accordingly. Revised new j paragraph.16.2.3-
., Page 16-3: Revised paragraph 16.5.2 Lj 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. a Revised section 5 to Table 3 i 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 2.3.8- . The following.pages were revised'due to' d format changes:
'C-4 1-11 2-6 AB-8 1-5 1-12 2-7 AB-9 1 1-23 2-8 AB-10 1-7 2-2 AB-6 AB-11 .i 1-8 2-5 AB-7 AB-12 10 Retype manual in its entirety on new pages; also made grammatical corrections (including '
misspelled words and punctuations throughout). j Cha.1ges given below are identified'on the i pages by a bar in the left margin, placed next to the affected area.
"AP&L" or '! Plant" was deleted or replaced k with "AN0" in the following sections: !
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 ' QA MANUAL OPERATIONS REV.: 10 ANO Arkonsos Nuclear one SECTIONi RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-8
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t RECORD OF REVISIONS-REVISION"
, NUMBER DESCRIPTION DATE 10 (Cont.) . 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' 7 Page 4-1:. Section 4.2.1 ;
Page 4-2: Section.4.2.3 Page 5-1:: Section 5.1.1 i 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 i
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 .j Page 17-4: Sections 17.3.4 & 17.4.1 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 T1-9: R.G. 1.58 - Page T3-1: #1~& #2 Page AB-1: Sections'1.1 & 1.2 ' Page AB-2: Section 1.4 : Page AB-5: Section 2.1, #4 & #6 Page AB-6: Sections 3.1 & 3.3 Page AB-7: Section 6.1 Page AB-8: Section 8.1 Page AB-11: Sections 16.1 & 18.1 "AN0", " Plant", "LRG0" e-1 " Departmental" was deleted or. replaced '<ith " Approved" in the following secticas: Page 2-3: Sections 2.!.4 & 2.2.6 Page 2-4: Section 2.3.2 Page 2-5: Section 2.3.3 Page 2-7: Section 2.!>.2
. .Page 2-8: Section 2.6.3 Page 2-1G: Section 2.6.7 Page 3-1: Section 3.2.1 Pago 3-2: Section 3.3
' QA MANUAL OPERATIONS REV.: 10 DATE: 08/31/88 i SECTION: RECORD OF REVISIONS PAGE: RR-9 L 1 Arkansos Nuclear One
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A RECORD OF REVISIONS
.i REVISION-NUMBER DESCRIPTION - DATE 10 (Cont.) Page 3-4: Sections 3.4.4, 3.5.1 & 3.5.2 1 3 Page 4-1: Section 4.1 l Page 4-2: Section 4.3
' Page 5-3: Section 5.3.3 :i 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.'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 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 i 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 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 QA MANUAL OPERATIONS REV.: 10 ANO
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-1 RECORD OF REVISIONS REVISION i NUMBER DESCRIPTION DATE l
101(Cont.)_ Changed " quality program" and " Quality Assurance Program" to "the QA. Program"' 1 in the following sections:
-A- Page -1: _ Paragraphs 1, 2, 3 & 4 '
Page A-2: . Paragraphs 2 & 3 i Page B-1: Paragraphs 2, 3 & 4 l Page B-3: Paragraph 1 Page B-5: Paragraphs 2 & 9 , Page 2-1: Sections 2.1 & 2.2 ' Page E-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. ~
Section 3.6' Page 3-5: . _Section 5.3.2 Page 5-2: ! Page 5-3: Section 5.3.2 Page 9-1: Section 9.2.2-p
.Page 18-1:' Sections 18.1.2 & 18.2.1 l Page'18-4: Section 18.4.2 H Page T1-1: Heading 1 L Page T3-2: #4 & #5 L Other specific changes as follows:
Page A-1: 1st Paragraph, Revised t 1st sentence Page A-1: 2nd Paragraph, Revised titles Page A-2: 1st Paragraph,= Revised i responsibility ' l Page B-1:- 1st Paragraph, Revised R .1st. sentence a L Page B-5: ASME Section III, ! Updated code edition Page B-5: ASNT SNT-TC-1A-1980, Added Sentence Page B-5: Revised "*" Sentence .! L Page C-4: Added "F-List" Definition < !=
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Page C-7: Modified Definition ! L Page C-8: Added "S-List" Definition a L Page C-9: Modified Definition ! L -Page C-10: Modified Definition 1 I l-l
. QA MANUAL OPERATIONS REV'.: 10 ANO Arkonoce Nuclear one SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-11
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RECORD OF: REVISIONS D
' REVISION NUMBER DESCRIPTION- DATE j 10 (Cont.) Page 1-1 to 1-23: Rewritten to reflect current. i o organization. l K Page 2-1: Section 2.2, Revised responsibilities in '
'last sentence .
3 Page 2-2: Section 2.2.3, Added " quality" 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.
t 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 -l 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 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 responsibiliities Page 6-1: 6.2.2 Revised title Page 6-2: 6.2.3 Revised title QA MANUAL OPERATIONS REV.: 10 ANO Arkoneos Nuclear one SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-12
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i I RECORD OF REVISIONS 4 REVISION + g NUMBER . DESCRIPTION .DATE' ( 10 (Cont.) Page 6-2: -Section 6.2.4, Revised section
- Page1 6-3: Section 6.7, Revised 1st sentence Page 7-2: (1), Re' vised responsibilities 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 d Page.7-b: 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 a Page 10-4:-Section 10;4.1, Revised section ! Page 11-5: Section 11.3.7, Revised section 1 Page 12-2: Section 12.2.3, Revised'Ist 3 sentence > Page 13-4: Section 13.5.5, Title change Page 14-l': Section 14.2.1, Title change 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 j' sentence Page 15-2: Section 15.2.4, Revised 2nd ' sentence i 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 4 3rd sentence ' Page 16-2: Section 16.3, Revised responsibilities Page 16-3:_Section 16.5, Revised heading i Page 16-3: .Section 16.5.1, Revised heading Page 16-3: Section 16.5.2, Revised responsibilities REV.: 10 QA MANUAL OPERATIONS ANO Arkoneos Nuclear One: SECTION: RECORD OF REVISIONS DATE: 08/31/88 PAGE: RR-13
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. RECORD OF< REVISIONS- ! , REVISION .
8 NUMBER DESCRIPTION. DATE-s 10 (Cont.) .Page 16-4: Section 16.5.4,-Revised section . Page 17-1: Section'17.1.1, Added " operation" C, 1st' sentence Page.17-1: Section 17.1.2,-Added
" maintenance" and." personnel experience" Page 17-1: Section 17.1.2, Revised last 4 sentence l Page 17-2: .Section 17.2.2, Revised.
responsibility .
.l Page 17-3: Section 17.3.1.2, Revised section Page 17-4: Section 17.3.4, Revised- 1 responsibilities Page 17-4:. Section 17.4.1, Revised section j
.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 Page 18-5: Section 18.4.4, Revised section l Page 18-5: Section 18.5, Revised ' responsibility i Page F-1 to F-7: Updated Figures : Page T1-2: Added ANSI N18.7 (Section 5.2.7) 1 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
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(Section 2.3.1.3) Page T1-18:Added AWS D1.1 (Section 5.2.8.4) j 1 Page T2-1: Updated matrix 1 Page T3-1: Revised #2 & #3 ! Page T3-2:- Revised' responsibilities #4 & #5 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"- Page AB-6: Section 3.3, Revised ' responsibilities Page AB-9: Change "QA and QC" to "NQ" ', QA MANUAL OPERATIONS REV. : 10 ANO DATE: 08/31/88 SECTION: RECORD OF REVISIONS PAGE: RR-14
' Arkansas Nuclear One
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m,' , 1 TABLE OF CONTENTS e SECTION SUBJECT - PAGES- REV: APPROVAL <COVERSHEET N/A ; 10 ' RECORD OF REVISIONS , RR-1 to RR-14 10 TABLE OF CONTENTS TC-1 to TC-4 10 POLICY. STATEMENT .A-1 to A-2 10 INTRODUCTION B-1 to B-5 10 t i TERMS AND DEFINITIONS C-1 to C-11 10 -{ t 1.0 ORGANIZATION 'l-1 to 1-23 10 2.0 QUALITY ASSURANCE PROGRAM 2-1 to 2 10 i \ l I' 3.0 DESIGN CONTROL 3-1 to 3-5 10 t p 40 PROCUREMENT DOCUMENT 4-1 to 4-3 10 p CONTROL p
- 5. 0' INSTRUCTIONS, PROCEDURES 5-1 to 5-4 10
- AND DRAWINGS 6.0 DOCUMENT CONTROL 6-1 to 6-3 10 :t l:
j-a ! 7.0 CONTROL OF PURCHASED 7-1 to 7-7 10 MATERIAL, EQUIPMENT AND SERVICES QA MANUAL OPERATIONS REV. 10 l ANO Arkansos Nuclear One SECTION: TABLE OF CONTENTS DATE 08/31/88 PAGE TC-1 E
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'M . TABLE OF CONTENTS
, .SECTION. SUBJECT PAGES- REV-p j l: . .
- 8. 0 -IDENTIFICATION AND CONTROL 8-1 to 8-3 -10 0F MATERIALS,. PARTS AND COMPONENTS-9.0 CONTROL OF SPECIAL 9-1.to 9-3 10 g PROCESSES 10.0 INSPECTION 10-1 to 10 10 11.0 TEST CONTROL 11-1 to 11-5 10 12.0 CONTROL OF MEASURING AND 12-1 to 12-4 10 TEST EQUIPMENT 1
13.0 HANDLING, STORAGE AND 13-1 to 13 10~ SHIPPING 14.0 INSPECTION, TEST AND 14-1 to 14 10 l OPERATING STATUS i 15.0 1 NONCONFORMING MATERIAL, 15-1 to 15-4 10 1 PARTS OR COMPONENTS j 16.0 CORRECTIVE ACTION- 16-1 to 16-4 10 . 17.0 QUALITY ASSURANCE RECORDS 17-1 to 17-5 10 .l 18.0 AUDITS 18-1 to 18-6 10 4 i QA MANUAL OPERATIONS REV. 10 ANO
. Arkonees Nuclear One .
SECTION: TABLE OF CONTENTS DATE 08/31/88 PAGE TC-2
c s 1 i I l 1 TABLE OF CONTENTS . SECTION SUBJECT PAGES. REV FIGURE 1 CORPORATE & OUTSIDE F-1 10
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SUPPORT ORGANIZATION l FIGURE 2 NUCLEAR ORGANIZATION F-2 10 FIGURE 3 NUCLEAR OPERATIONS F-3 10 ORGANIZATION l FIGURE 4 PLANT OPERATIONS F-4 10 ORGANIZATION 4 FIGURE 5. PLANT SUPPORT- F-5 10' l ORGANIZATION ' FIGURE 6' . NUCLEAR QUALITY F-6 10 j ORGANIZATION FIGURE 7 LITTLE ROCK NUCLEAR F-7 10 i SUPPORT ORGANIZATION TABLE 1 AN0 EXCEPTIONS / INTERPRETATIONS T1-1 to T1-28 10 0F REGULATORY GUIDES AND ANSI STANDARDS TABLE'2 QUALITY ASSURANCE T2-1 10 PROCEDURES MATRIX i 1 QA MANUAL OPERATIONS REV. 10 ANO A&onses Nuclear One SECTION: TABLE OF CONTENTS DATE 08/31/88 PAGE TC-3 _____.__n_-_-______---_--_-_.._-__. . .-. . -_
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. TABLE OF-CONTENTS j j
4 SECTIONl SUBJECT PAGES REV j ' h
-TABLE 3 QUALITY PROGRAM POLICIES, T3-1 to.T3-2 10 PROCEDURES AND INSTRUCTION-MANUALS LIST APPENDIX A QUALITY PROGRAM FOR -AA-1 to AA-4 10 TRANSPORT PACKAGES
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APPENDIX B QUALITY PROGRAM FOR AB-1 to AB-12 10 FIRE PROTECTION 1
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1 1 QA MANUAL OPERATIONS REV. 10 ' ANO DATE 08/31/88 SECTION: TABLE OF CONTENTS PAGE TC-4
- A&onses Nuclear One
y l , ARKANSAS NUCLEAR ONE POLICY STATEMENT '
- QUALITY ASSURANCE PROGRAM FOR OPERATIONS i
l 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 1
Regulations, Title 10,.Part 50, Appendix B, with respect to operation, maintenance, refueling, repair and modifications, and inservice l inspection. The QA Program shall also meet the requirements of the ASME Boiler and Pressure Vessel Code with respect to items constructed, repaired or replaced to Code requirements. '
.Under the QA Program, the Vice President Nuclear is the final management l authority responsible for assuring that this policy statement and the QA l
Program are implemented within ANO and its supporting organizations. The .l l Executive Director Human Resources, and Executive Director Administrative h Services are responsible for the procedural implementation of the QA' l Program within their assigned areas.- The Executive Director Nuclear ' Operations is responsible for the daily implementation of the QA Program's procedural requirements at ANO. L The General Manager Nuclear Quality is responsible for establishing the l QA Program. Responsibility for approval _of the QA Program shall be identified within this manual. > Nuclear Quality personnel reporting to the General Manager Nuclear Quality are responsible for auditing the QA Program as necessary and l inspecting / monitoring activities required by the QA Program to assure g compliance with its requirements. Disputes involving quality, arising l from difference of opinions between Nuclear Quality personnel and other l L i ANO Arkansas Nuclear one QA MANUAL OPERATIONS SECTION: STATEMENT OF POLICY REV. 10 DATE 8/31/88 PAGE A-1
i personnel,'which cannot be settled.interdepartr.:ntally,'shall be i presented to the.Vice President Nuclear 'Or resolution. The General Manager Nuclear Quality has direct access to the President and Chief i
- Executive.0fficer on matters concerning nuclear quality'. I
.The General Manager Nuclear Quality-through the Superintendent Quality ,
Assurance is to provide for an annual review of the adequacy and overall .{ effectiveness of the QA Program.- Any defects in the implementation of i either this policy or the QA Program that are revealed during the review -i are to be reported to appropriate levels of management together with -l appropriate recommendations. 4 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 for assuring quality in-his own work, and for compliance with the requirements of the QA Program. The QA Program policies, manuals, and procedures are mandatory ! requirements which must be implemented and enforced by all responsible organizations and individuals. i AW T. G. CampbeJT l Vice President Nuclear l Date: P-99-ff L L L L L ANO Arkonsos Nuclear One QA MANUAL OPERATIONS SECTION: STATEMENT OF POLICY REV. 10 DATE 8/31/88 PAGE A-2
t INTRODUCTION This eanual describes the Quality Assurance Program for Operations (QA PrograA applied to Arkansas Nuclear One, Units 1&2 (ANO).and its supporting Organizi.tions. This manual is intended to serve as a standard reference for , safety analysis reports to fulfill the requirements of the Standard Format s and Contents of Safety Analysis Reports for Nuclear Power Plants, Section 17, published by the Nuclear Regulatory Commission.
! The objective of the QA Program is to control those phase's, as applicable, for the design, procurement, manufacture and fabrication, installation, operation, testing, refueling, repair, maintenance or modification to '
existing safety related (Q-List) structures, systems and components that i prevent or mitigate the consequences of a postulated accident which may l cause undue risk to the health and safety of the public. The QA Program is- 1 an outgrowth of the principle that quality assurance emanates from each individual contributor and that management is responsible for creating an ' awareness of quality. l The QA Program is designed to comply with the requirements of 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, and also to comply with the quality assurance requirements of the ASME Boiler and Pressure Vessel Code, Section XI for repair, replacement, and inservice inspection of items covered by the Code and Licensing commitments.
'l The QA Program is also designed to comply with the NRC positions contained in the following regulatory guides, subject to specific exceptions noted in Table 1 of this manual:
1 1.8, Rev. 1-R Personnel Selection and Training (5/77) o 1.28, Rev. 1 QA Program Requirements-Design and Construction (3/78) l ANO Arkaneos Nuclear One QA MANUAL OPERATIONS SECTION: INTRODUCTION REV. 10 DATE 8/31/88 PAGE B-1 {
9 y 1.30 QA~ Req'uirements for Installation.- Inspection and Testing of Instrumentation 'l
*' ' 1
_and Electrical' Equipment-(8/12) d 1.33, Rev.:2~ QA Program Requirements-Operations (2/78) 1.37- QA Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear: Power P.lants (3/73) l 1.38, Rev. 2 QA Requirements for Packaging, Shipping, , l Receiving, Storage and Handling of Items 1 for Water Cooled Nuclear Power _ Plants r, (5/77) 1.39, Rev. 2 Housekeeping Requirements for Water Cooled- I Nuclear Power Plants (9/77) [ 1.58, Rev. 1 Qualification of Nuclear Power Plant ' Inspection, Examination and Testing j Personnel (9/80) 1.64, Rev. 2 QA Requirements for the Design of Nuclear. Power Plants (6/76)
' 1. 74 '
QA Terms and Definitions (2/74) 1.88, Rev. 2 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance : Records'(10/76) 4 1.94, Rev l' QA Requirements-for Installation, 4 Inspection and Testing of Structural Concrete and Structural Steel'During the Construction Phase of Nuclear Power Plants (4/76) ' 1.116, Rev. 0-R QA Requirements for Installation,. 1 Inspection and Testing of Mechanical L Equipment and Services (5/77) ' 1.123,.Rev. 1 QA Requirements for Control of Procurement of Items and Services For Nuclear Power ! Plants (7/77)' L l' QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 l SECTION: INTRODUCTION PAGE B-2
' Arkoneos Nuclear One
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l'.144 Rev. ' l-
, ' Auditing of Quality. Assurance Programs for the Nuclear Power Plant (9/80) 'I .
3 1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants j (8/80) l Based upon compliance to.these regulatory guides, the QA Program also. l complies with the following American National Standards Institute (ANSI) I standards' subject to exceptions noted in Table 1 of this manual: 1 N45.2-1977 Quality Assurance Program Requirements for Nuclear
' Facilities N45.2.1-1973 C1eaning of Fluid Systems and Associated Components During the. Construction ~ Phase of Nuclear Power Plants ,
N45.-2.2-1972 Packaging, Shipping, Receiving, Storage *and 3 Handling of Items for Nuclear Power Plants (During the Construction Phase)- N45.2.3-1973 Housekeeping During the Construction Phase of Nuclear. Power Plants N45.2.4-1972 Supplementary Quality Assurance Requirements for. Installation, Ins,tection and Testing of [ Instrumentatico and Electric Equipment During the Construction of Nuclear Power Generating Stations N45.2.5-1974 Supplementary Quality Assurance Requirements for Installation and Testing of Structural Concrete E and Structurai Steel-During the Construction Phase of-Nuclear Power Plants r ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: INTRODUCTION REV. PAGE B-3 10 DATE 8/31/88 ,
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N45.2.6-1978 Qualifications of Inspection, Examination and t Testing Personnel for Nuclear Power Plants N45.2.8-1975;
~ Supplementary Quality Assurance Requirements for.
Installation, Inspection andLTesting of Mechanical Equipment and System for the Construction Phase-off l Nuclear Power Plants
- N45.2.9-1974 Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants
. N45.2.10-1973 Quality Assurance Terms and Definitions i N45.2.11-1974 Quality Assurance Requirements for the Design of -
Nuclear Power Plants N45.2.12-1977 Requirements for Auditing of Quality Assurance Programs for Nuclear' Power Plants ; N45.2.13-1976 Quality Assurance Requirements for Control of Procurement of. Items and Services for Nuclear s Power-Plants a N45,2.23-1978 Qualification of Quality Assurance. Program Audit i '
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Personnel for Nuclear Facilities ~
-N18.1-1971 Selection and Training of Nuclear Power Plant.
Personnel N18.7-1976 Administrative Controls and Quality Assurance for-the Operational Phase-af. Nuclear Power Plants N3.1-1981 Selection, Qualification, and Training of h Personnel for Nuclear Power Plants ANO
. Arkansos Nuclear One QA MANUAL OPERATIONS SECTION: INTRODUCTION RE*/. 10 DATE 8/31/88 PAGE B-4
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3 TheLabove requirements-are implemented by contro11.ing' activities as ,
?Z described in this manual and by procedures referenced in this manual. .'
a- , g,l The QA Program is also designed to comply with the following codas and-standardsg as applicable to those activities to which they are referenced within various sections of this manual:> l ASME 5ection III, Division 1 - 1986 Edition,.No Addenda
- ASME Boiler and Pressure Vessel-Code - Nuclear Power Plant Components ASME Section XI - 1974 Edition, Summer 75 Addenda (ANO Unit 2)**
- 1980 Edition, Winter 81 Addenda (ANO Unit 1) ,
I ASME Boiler and Pressure Vessel Code - Rules for Inservice Inspection of Nuclear Power Plant Components
!I ASNT SNT-TC-1A-1980 l
9 Recommended Practice for Nondestructive Testing Personnel r L Qualification and Certification-(This edition shall be used-in lieu < of earlier editions that might be referenced in other codes or standards to which ANO is committed). AWS D1.1-1985 American Welding Society Structural Steel Welding Code l 5 Earlier editions / addenda of the Code may be specified for repair or l replacement (including system changes) of components or systems, ; within the' rules of ASME Section XI. ! i
-Repair / replacement activities shall be to the 1980 Edition, Winter -i 81 Addenda l l Definitions of terms applicable to the QA Program are found in the Terms l
and Definitions section of this manual. 1 L QA MANUAL,0PERATIONS REV. 10 DATE 8/31/88 SECTION: INTRODUCTION PAGE B-5
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- 1. 0 ORGANIZATION 1.1 SCOPE -
This section describes the Nuclear organizational structure and responsibilities for establishing and executing the QA Program for, j l Arkansas Nuclear One, Units 1 & 2 (ANO) in compliance with 10CFR50, Appendix B and applicable licensing commitments identified in the Introduction. It also includes a description of the interfaces with other organizations who may be delegated the work of establishing and executing portions of the QA Program. The Arkansas Power & Light Company's (AP&L) Corporate Organization relevant to the operation of ANO is shown in figure 1. i 1.2 GENERAL RESPONSIBILITIES The ultimate responsibility for ANO, including quality assurance, lies ; with the Vice President Nuclear . He provides management assessment of the QA Program through review of reports generated by the Nuclear Quality (NQ) Organization and reports of NRC activities. 1.3 NUCLEAR ORGANIZATION i This Organization, headed by the Vice President Nuclear is responsible for all 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 Vice President Nuclear who reports to the President and Chief Executive Officer (see figure 1) is responsible for the formulation, licensing, implementation and discharge of operating policies and procedures relative to nuclear plant operations, nuclear quality and nuclear fuel management. His duties include the following: ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-1
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-(1) Proviaing technical direction tad administrative guidance to ?
the:
- a. Executive Dirt"cr Nuclear Operations i
- b. General Manager Nuclear Quality
, c. General Manager Design Engineering
- d. General Manager Nuclear Oversight / Support
)
i (2) Ensuring conformance to the QA Program by instituting the necessary procedures and instructions within the Nuclear i organization l (3) Providing for review and approval of design and engineering performed for ANO i (4) Providing for review and approva'l of procurement documents for equipment, material and services j i (5) Providing for liaison between ANO and applicable regulatory [ i agencies (o) Providing and maintaining a qualified and suitable staff to carry out required departmental functions (7) Providing for procurement and design review of nuclear fuel (8) Assuming overall responsibility for the fire protection, emergency planning and radiation protection programs implemented at ANO 1.3.1 Executive Director Nuclear Operations i The Executive Director Nuclear Operations reports to the Vice President Nuclear (see figure 2) and has direct responsibility for operating ANO in ANO Arkoneos Nuclear One
' QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-2
i i a safe, reliable and efficient manner. He is responsible for operating l ANO in accordance with the provisions of the operating licenses. , The Executive Director Nuclear Operations has the authority to shut down I the plant if required and has final approval of overall plant administrative procedures. ' The Executive Director Nuclear Operations provides technical direction 1 and administrative guidance to the: l (1) General Manager ANO Plant (2) General Manager Plant Support (3) Manager ANO Engineering (4) Manager Licensing (5) Manager Budgets and Planning : 1.3.1.1 General Manager ANO Plant The General Manager ANO Plant (see figure 3) reports to the Executive Director Nuclear Operations and is responsible for the actual operation of the nuclear units, the maintenance of plant equipment and facilities and the planning / scheduling of plant work activities. The operations organization is shown in figure 4. The General Manager ANO Plant provides technical direction and administrative guidance to the: (1) Manager Operations (2) Manager Maintenance (3) Manager Work Control Center (4) Manager Plant Modifications 1.3.1.1.1 The Manager Operations is responsible for directing the actual day-to-day operations of the plant. He supervises the operating staff and l f' QA MANUAL OPERATIONS REV. 10
- j. DATE 8/31/88
- j. SECTION: 1.0 ORGANIZATION PAGE 1-3 Arkoneos Nuclear one
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interfaces with the Manager Maintenance to accomplish operation-related maintenar.ce activities. The Manager Operations provides technical ; direction and administrative guidance to the Superintendent Operations ! for each unit. 1.3.1.1.1.1 The Superintendents Operations report to and assist the Manager Operations in directing the day-to-day operation of each unit of ANO. They are responsible for coordination of the daily review of operating surveillance tests and coordination of operation-related maintenance activities. They assist the Manager Operations in the supervision of core refueling, which includes advance planning for the outage, plant ' preparation, equipment checkout and the refueling operations. The , Superintendents Operations provide technical direction and administrative ~ guidance to the: a r (1) Supervisors Shift Operations (2) Supervisors Technical Operations 1.3.1.1.1.1.1 L The Supervisors Shift Operations report to the applicable Superintendent Operations and are responsible for the actual operation of'the unit , during their assigned shif ts. 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 are holders of Senior Reactor Operator Licenses. The Supervisors Shift Operations provide technical direction l and administrative guidance to the: (1) Supervisors Control Room L (2) Shift Administrative Assistants L ANO Arkonees Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-4
1.3.1.1.1.1.1.1 The Supervisors Control Room report to and assist the applicable Supervisor Shift Operations and are responsible for the actual operations ' in the Control Room and for the activities of the operators during their assigned shift. The Supervisors Control Room are holders of Reactor 4 Operator Licenses. The Supervisors Control Room provide technical ; direction and administrative guidance to the: (1) Assistant Plant Operators (Holders of Reactor Operators Licenses) 7 (2) Waste Control Operators (3) f.uxiliary Operators l 1.3.1.1.1.1.1.2 :
. i The Shift Administrative Assistants report to the applicable Supervisor Shift Operations and are responsible for general operations i I
administrative duties. l l l 1.3.1.1.1.1.2 ' The Supervisors Technical Operations report to the applicable l Superintendent Operations and are responsible for providing coordination, j- supervision and control of the Operations Technical Staff for the unit ! assigned and also act as single points of contact for each unit's staff when interfacing with other groups. L l i 1.3.1.1.2 The Manager Maintenance is responsible for the maintenance of plant equipment and facilities as defined by plant maintenance program 1 implementing procedures and ensuring that maintenance of equipment is ANO A&oneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-5
l performed in compliance with applicable standards, codes, specifications and procedures. The Manager Maintenance is also to coordinate ' operation-related maintenance activities with the Manager Operations and r is responsible to make repairs on any structure, system or component under his control. The Manager Maintenance provides technical direction - and administrative guidance to the: -' (1) Superintendent Mechanical Maintenance (2) Superintendent Electrical Maintenance (3) Superintendent Instrumentation & Control (4) Superintendent Shift Maintenance (5) Senior Maintenance Coordinator 1.3.1.1.3 The Manager Work Control Center is responsible for the planning / ! scheduling of station work activities and the maintenance of the i. equipment history and associated reports. He supervises the Work Control Center staff and interfaces with the Manager Operations and Manager , Maintenance to accomplish the scheduling of the outage /non-outage work activities. The Manager Work Control Center provides technical direction ! and administrative guidance to the:- i (1) Superintendent Planning & Scheduling ' I (2) Superintendent Outage Management (3) Supervisor Maintenance History 1.3.1.1.4 The Manager Plant Modifications reports to the General Manager ANO Plant {- and is responsible for directing the activities of his staff relating to . work associated with plant construction and modifications, interfacing ! with other departments to assure effective implementation of job i 1 ANO Arkonoce Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-6
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I I l l assignments and providing cost and schedule controls for department ' activities. He is also responsible for providing engineering support-during the implementation and close-out of design modifications generated , in support of ANO. He provides technical direction and 6dministrative guidance to the: (1) Superintendent Installation ! (2) Superintendent Project Engineering (3) Administrative Coordinator 1.3.1.2 General Manager Plant Support The General Manager Plant Support (see figure 5) reports to the Executive Director Nuclear Operations and is responsible for providing the necessary on-site support services for ANO in the areas of health physics, technical analysis, radwaste, security, training and administrative services. The General Manager Plant Support provides ! technical direction and administrative guidance to the: (1) Manager Plant Administration ! (2) Manager Training (3) Manager Technical Support (4) Superintendent Security (5) Superintendent Operations Assessment 1.3.1.2.1 The Manager Plant Administration reports to the General Managte Plant Support and is responsible for providing administrative service:s in support of plant activities. The duties and responsibilities of the Manager Plant Administration include the following: ANO Arkansos Nuclear One
' QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV.
DATE 8/31/88 PAGE 1-7 10
l (1) Technical direction and administrative guidance to the: ,
- a. Superintendent Office Services
- b. Superintendent Materials Management l
- c. Superintendent Computer Support
- d. Administrator Human Resources (2) Accumulation, storage and dispos' tion of quality assurance l records related to all phases of ANO I
l (3) Material management, storage of materials, parts and equipment, issuance of tools and test equipment and the identification of surplus materials (4) Personnel employment and industrial relations at the plant ! (5) Maintenance, revision and development of computer software for ) the plant monitoring and control room simulator computers and ! for providing technical assistance to the Superintendent Reactor Engineering in development and use of test apparatus for evaluation of fuel, core and Nuclear Steam Supply System (NSSS) performance 1.3.1.2.2 The Manager Training reports to the General Manager Plant Support and is responsible for the training and retraining of plant personnel and general office perso7nel as established by approved procedures. The i Manager Training is a1so responsible for the implementation and maintenance of the AND Emergency Plan. The Manager Training directs the ' activities of the ANO training staff and provides technical direction and administrative guidar.ce to the: ANO Arkonsos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-8
-(1) Superintendent Operations Training (2) Supervisor Emergency Planning -
(3) Supervisor Maintenance Training (4) Supervisor Administrative Training ' (5) Supervisor Technical Support Training ; (6) Supervisor Simulator Support t 1.3.1.2.3 The Manager Technical Support reports to the General Manager Plant I Support and is responsible for the establishment and implementation of the health physics, radiochemistry, chemistry and environmental monitoring and radioactive waste programs at ANO. -His duties and responsibilities include the following:
?
(1) Providing technical direction and administrative guidance to f the:
- a. Superintendent Health Physics f
- b. Superintendent Technical Analysis
- c. Superintendent Radwaste
- d. Health Physics Specialist (2) Analyzing the reactor plant water conditions and providing recommendations to maintain conditions (3) Prot.essing, packaging, storing, and shipping radwaste generated at ANO in accordance with plant procedures and state and L federal regulation i
(4) Establishing water chemistry criteria, analyze secondary plant l water and auxiliary water conditions and provide recommendations to maintain conditions within acceptable limits ANO Arkoneos Nuclear one QA KANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-9
i (5) Assuring radiation exposure to plant personnel is maintained as 1 low as reasonably achievable and authority to stop work in radiation areas if it is determined that'a potential for an unanticipated excessive exposure to plant personnel or the environment may exist , 1.3.1.2.4 The Superintendent Security reports to the General Manager Plant Support ' and is responsible for plant security including coordination of efforts , of the security force and managing the operation of the security system. 1.3.1.2.5 The Superintendent Operations Assessment provides the capability to perform engineering evaluations of equipment and system performance over extended periods of operating experiences which occur both at ANO and at other nuclear power plants and to make recommendations as a result of these evaluations to helti plant operations personnel in preventing or dealing with similar occurrences. He also provides technical direction and administrative guidance to the Shift Technical Advisers. 1.3.1.3 Manager AND Engineering 1 The Manager ANO Engineering reports to the Executive Director Nuclear Operations and is responsible for providing on-site engineering support services (including fire protection and prevention) to the plant staff. The Manager ANO Engineering provides technical direction and administrative guidance to tre: 1 i i
- . (1) Superintendent r.eactor Engineering (2) Superintendent Plant Engineering (3) Superintent'ent Engineering Services l i
1 l l
. 1 ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-10 1
mu I eI 1.3.1,3.1 The Superintendent Reactor Engineering is responsible for monitoring reactor core and NSSS perfotmance; conducting reactor performance and physics testing to ensure safe and reliable operation; providing current, accurate information to operations; collection and transmittal of nuclear fuel management data to the Core Reload Design Senior Engineer in Little Rock and the reactor vendors as required; on-site safeguards and accountability of the nuclear fuel; and assisting in the planning of all fuel movements including new fuel receipt and inspection, fuel shuffling at refueling, inspection of irradiated fuel and shipment of spent fuel. 1.3.1.3,2 The Superintendent Plant Engineering is responsible for drawing control, engineering support of plant activities, evaluating equipment and system performance and plant efficiency, and investigating and evaluating equipment malfunctions or failures. 1.3.1.3.3 The Superintendent Engineering Services is responsible for the implementation and coordination of the Inservice Inspection program, on-site Welding program, and the Inservice Testing program at ANO. He is ' also responsible for coordination of the ANO fire protection and fire prevention programs. These programs include conducting periodic checks to examine control of combustibles, housekeeping and other fire prevention efforts. He is also responbisle for the steam generator integrity program, check valve inspection program, secondary piping erosion-corrosion monitoring, fan and filter performance testing, evaluation of possible consequences of boric acid corrosion on carbon steel, and for coordinating the technical manual, component data base and preventive maintenance programs at ANO. ANO Arkansos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-11 l l
1.3.1.4 Manager Licensing The Manager Licensing reports to the Executive Director Nuclear Operations 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 organization is shown in figure 5. The Manager Licensing provides technical direction and administrative guidance to the: (1) Supervisor Licensing (on-site) (2) Supervisor Licensing (off-site) 1.3.1.4.1 The Supervisor Licensing (on-site). 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 (3) Establishing and maintaining a system for monitoring License Event Reports and NRC Inspection Reports (4) Providing technical direction and administrative guidance to the on-site Nuclear Safety and Licensing Specialists , 1.3.1.4.2 The Supervisor Licensing (off-site) reports to the Manager Licensing and is responsible for the following duties: ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. DATE 8/31/88 PAGE 1-12 10 l
(1) Interfacing with NRC, Washington, DC offices and the Manager i Licensing pertaining to Licensing and regulatory matters ; (2) Establishing and maintaining programs for the maintenance of Licensing Base Documents (License, SAR, Technical Specification, Emergency Plan, QA Manual Operations) t (3) Reviewing NRC Correspondence (incoming and outgoing) and related industry documents to remain cognizant of activities ' that may affect ANO i (4) Providing technical direction and administrative guidance to i the Little Rock based Nuclear Safety and Licensing Specialists 1.3.1.5 Manager Nuclear Budgets and Planning The Manager Nuclear Budgets and Planning reports to the Executive Director Nuclear Operations and provides budgetary and fiscal planning,- ; scheduling, and management support to the Nuclear Organization. The responsibilities involve the development and administration of fiscal and long-range planning programs to provide accurate and effective tools,. information and analysis for the overall management of ANO. The Manager ; Nuclear Budgets and Planning provides technical direction and administrative guidance to: (1) Superintendent Nuclear Planning (2) Plant Controller (3) Supervisor Plant Projects 1.3.2 General Manager Nuclear Quality The Nuclear Quality (NQ) organization as shown in figure 6 is under the direction of the General Manager Nuclear Quality who reporte to the Vice President Nuclear. The NQ organization performs reviews, surteillance, 1 ANO ktensos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-13
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inspection and audit functions during the operational phase of ANO. The NQ Organization is also independent of plant operations and has sufficient independence from cost and schedule when opposed to safety considerations. The General Manager Nuclear Quality has direct access to all management levels, which assures his staff the ability to: identify quality problems; initiate, recommend or provide solutions through l designated channels; and verify implementation of solutions. The qualification requirements of the General Manager Nuclear Quality are establishedwithinhisjobdescriptionwhichincludethefollowing prerequisites: i 1 (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 , l experience in a supervisory position with at least one year experience in the implementation of the quality assurance program l (3) Exhibit the ability to plan, schedule and direct the activities of others assigned to or functioning within the NQ organization l Duties and responsibilities of the General Manager Nuclear Quality ' include the following: (1) Technical direction, administrative guidance and supervision to , the Superintendent Quality Assurance and Superintendent Quality Control / Quality Engineering (2) Approving of the QA Manual Operations and revisions thereto t ANO Arkoneos Nuclear one QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 I i V w - -++i a - , , - . -
1 (3) Approving of QA and QC/QE procedures and revisions thereto as established within NQA procedures i i 1.3.2.1 Superintendent Quality Assurance The Superintendent Quality Assurance reports to the General Manager ) NuclearQuality. Duties and responsibilities of the Superintendent { Quality Assurance include the following: (1) Developing the QA Program requirements for operation, t maintenance, and modification activities related to { safety-related (Q-listed) systems, structures and components .j (2) Auditing of the quality activities as described in Section 18.0 1 of this manual (3) Reviewing, approving and verifying of the quality assurance requirements placed upon contractors or vendors that provide equipment, material or services for AND (4) Authority to stop work where conditions exist that prohibit ' effective quality programs, or if faulty materials, incorrect ' workmanship or procedures are detected I (5) Reviewing, approving, and controling of vendor quality manuals and procedures and revisions thereto (6) Reviewing and approving of quality assurance programs 'or outside organizations participating in'the QA Program (7) Providing and maintaining a qualified and suitably trained staff to carry out required staff functions ANO Arkaneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-15
(8). Formulating programs for maintaining the professional ' competence of personnel within the Quality Assurance section i and providing assistance in Quality Assurance training and indoctrination programs for management, engineering and plant j personnel whose activities affect quality .I (9) Providing technical direction and guidance to the Supervisors Quality Assurance and their staff 1 (10) Inspecting, auditing or reviewing practices, records, files, instructions, directions or documents concerned with all areas affecting quality l (11) Scheduling and coordinating audits or surveillance efforts in t the areas assigned, documenting findings and reporting results to the General Manager Nuclear Quality and the Manager of the audited area l (12) Providing to the General Manager Nuclear Quality on an annual [ basis the results of a review of the QA Program to determine . l the effectiveness and proper implementation of the QA Program 1.3.2.2 Superintendent Quality Control / Quality Engineering t The Superintendent Quality Control / Quality Engineering reports to the General Manager Nuclear Quality and is responsible for verifying the implementation of the Quality Control program at ANO. The duties and ( responsibilities of the Superintendent 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 l . 1 ANO Arkansos Nuclear One SECTION: QA MANUAL OPERATIONS 1.0 ORGANIZATION REV. 10' DATE 8/31/88 PAGE 1-16
j 1 (Q-listed) and fire protection-related (F-listed) systems, , structures and components ! (2) Interface with the Superintendent Quality Assurance or his ! representative for technical assistance in resolving I significant conditions adverse to quality (3) Authority to stop unsatisfactory work and authority to place an item in a nonconforming status when such an item is determined to be in violation of purchase documents, applicable codes and standards or SAR requirements (4) Assuring surveillances, inspections 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 and Supervisors Quality Control and their , staff i (6) Providing and maintaining a qualified and suitable 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 I s ! 1.3.3 General Manager Desion Engineerino The General Manager Design Engineering (see figure 7) reports to the Vice President Nuclear and is responsible for maintaining the design of ANO. His duties include the following: 1 (1) Providing technical direction and administrative guidance to; ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-17
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- a. Manager Mechanical, Civil, Structural Design
- b. Manager Electrical, Instrumentation & Control Design
- c. Manager Nuclear Design Services
, (2) Assuring conformance to the QA Program by instituting the necessary quality-related procedures and instructions within Design Engineering (3) Providing for review and approval of design and engineering activities performed by contractors, vendors, and Nuclear personnelinDesignEngineeringprojects 1
(4) Providing for review and approval of procurement doct.ments for equipment, material and services for off-site engineering projects,asappropriate l (5) Providing and maintaining a qualified and suitably trained ! staff to carry out required departmental functions ! 4 (6) Directing the development of programs aimed at maximizing
- r. efficiency and availability (7) Providing for review and analysis of outage data and make i recommendations for improving availability or performance l l
(8) Providing pioject control systems', methods and reporting i formats to support managerial requirements (9) Providing for procurement and design review of nuclear fuel i 4 (10) Providing for development and control of design-basis , information j. i i-
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ANO Arkonses Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-18 L.
l 1.s.4 General Manager Nuclear Oversicht/ Support The General Manager Nuclear Oversight / Support (see figure 7) reports to ! the Vict President Nuclear and is responsible for providing off-site support to ANO in the areas of: 1 (1) Staff support for the Safety Review Committee (SRC) I (2) Corporate management oversight of various line functions (3) Administrative support for radiological protection and chemistry programs 1 (4) Management of Owners' Group and Industry Group activities I l (5) Technical direction and administrative guidance to: '
- a. Corporate Health Physicist
- b. Project Manager Nuclear Industry Support ,
- c. Senior Maintenance Coordinator ;
- d. SRC Administrative Assistant
- e. SpecialProjectCoordinators ;
1.3.5 Independent Review Organizations a 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. L QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 1.0 ORGANIZATION PAGE 1-19 Arkonnos Nuclear One
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i 1.3.5.1 Safety Review Committee (SRC) i
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The SRC is chaired by the Vice President Nuclear and is responsible for providing off-site independent reviews and/or audits relating to: the Safety Analysis Reports, Technical Specifications, procedures and changes thereto; unreviewed safety questions; violations, deviations and reportable events; and any other matter involving safe operation of ANO 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 l meeting minutes generated from the Plant Safety Committee. ' 1.3.5.2 Plant Safety Committee (PSC) The PSC reports to the Executive Director Nuclear 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 i not an unreviewed safety ouestion (defined by 10CFR50.59) is l involved i (2) Furnishing written recommendations to the Executive Director L Nuclear Operations for approval These activities include changes to plant procedures and Technical Specifications, proposed modifications to plant systems, changes to plant security and emergency plans and review of facility operations L to detect potential nuclear safety hazards. 1.3.5.3 Committee Structure i 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. ANO Arkoneos Nuclear one QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. DATE 8/31/88 PAGE 1-20 10
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i S 1.4 OUTSIDE SUPPORT ORGANIZATIONS- " i 1 1.4.1 Senior Vice President Finance & Administration & Chief Financial Officer Administrative Services and Human Resources headed by the Senior Vice President Finance & Administration & Chief Financial Officer is involved i in procurement and training activities requiring execution of the QA Program. The organization is noted in figure 1. The Senior Vice President Finance & Administration & Chief Financial Officer provides technical direction and administrative guidance to-the: (1) Executive Director Corporate Services (2) Executive Director fiuman Resources i 1 r.xecutive Director Corprate Services The Executive Director Corporate Services, who reports to the Senior Vice Preradent Finance & Administration & Chief Financial Officer, is responsible for the procurement of materials, parts and components requested by Nuclear personnel off-site and for supporting the procurement activities at ANO. 1.4.1.1.1 The General Manager Procurement & Materials Management reports to the Executive Director Corporate Services and is responsible for the following duties and activities: (1) Providing technical direction and administrative guidance to the Manager of Procurement (2) Preparing purchase orders based upon receipt of reviewed and approved Purchase Requisitions ~ QA MANUAL OPERATIONS REV. 10' DATE 8/31/88 SECTION: 1.0 ORGANIZATION PAGE 1-21 Arkoneos Nuclear One
.(3) Performing the commercial interface functions between ANO and ;
vendors / contractors ' 3 i (4) Ensuring that quality documentation prepared by ANO personnel l 1s included in appropriate procurement documents l
- 1. 4. '. 2 Executive Director Human Resources The Exe utive Director Human Resources reports to the Senior Vice L
President Finance & Administration & Chief Financial Officer and is responsible for the administration of the. training and development effort . of Nuclear personnel off-site. The Executive Director Human Resources provides technical direction and administrative guidance to the AP&L ! Manager Training. 1.5 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES As owner, AP&L assumes full responsibility and authority for the plant I including action to assure that the plant is operated in accordance with : sound engineering practices, licensing requirements and applicable codes, specifications and procedures. Each supplier of equipment, material or services and each maintenance or modification contractor is responsible for administering the applicable quality control functions as required by ANO. The NQ organization is responsible for assuring by surveillance, inspection, audit or review of. objective evidence (e.g., review audit reports conducted by others, etc.) that these functions are accomplished for systems, structures and services that affect the safety and integrity of the plant. Visits to manufacturers' shops by Quality Assurance personnel are conducted, when deemed necessary, based upon safety significance, ANO Arkansas Nuclear One QA MANUAL OPERATIONS SECTION: 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-22
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4 I 1 i complexity, method of. acceptance and past history of the vendor, to j
, establish product quality and to assure that quality assurance and ),
quality' control programs function in accordance with ANO requirements. l l l 1 1 1 t i i } q! c ANO Arkoneos Nucleor One SECTION: QA MANUAL OPERATIONS 1.0 ORGANIZATION REV. 10 DATE 8/31/88 PAGE 1-23
2.0 QUALITY ASSURANCE PROGRAM ! 2.1 SCOPE i , l This QA Program is to assure that ANO is operated in a safe, reliable and efficient manner and in accordance with NRC regulations, applicable ' industrial standards and codes and applicable Company policies, rules, procedures and licensing documents. A matrix of quality procedures cross referenced to each criterion of 10CFR50, Appendix B, is. included in Table 2 to this manual.
- 2. 2 GENERAL ;
2.2.1 ' A l This QA Program is applied to those safety-related structures, systems and components and to those expendable and/or consumable items
- whose satisfactory performance is required to prevent accidents which may cause undue risk to the health and safety of the public or to mitigate the consequences of such accidents if they were to occur. These structures, systems and components are identified in the summary level and component level Q-lists for each nuclear unit. The Summary Level Q-Lists (SLQL) ;
are located in the 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 l safety function as determined by Design Engineering or Plant Engineering are to be considered Non-Q, unless otherwise dispositioned by Design Engineering or Plant Engineering
- Expendable and/or consumable items are to include, as a minimum: ,
nuclear fuel, weld rods, boric acid, and diesel fuel. ANO A&onnos Nuclear 0ne SECTION: QA MtNUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-1
l 2.2.2 l Expendable and/or consumable items where quality is necessary fo the performance of Q-listed structures, systems and components are identified l and controlled in accordance with Technical Specifications and/or l procedures, i i The following expendable and/or consumable items are to be controlled in l 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 unit . (2) Welding Rod - Service quality is ensured by procurement from an t 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 (3) Boric Acid - Service quality is ensured by procurement from an evaluated source, requiring a batch analysis to ensure conformance with our specification requirements, and on-site control prior to use to prevent degradation , 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 NQ Organization, under the cognizance of the SRC. ANO Arkoneos Nuclear One SECTION: QA MANUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-2
i 2.2.4 i The quality program for fire protection 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 j appropriate approved procedures. The effectiveness of the fire protection program is verified through scheduled audits conducted by the ; NQ organization, under the cognizance of the SRC. I 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 reviews, approvals, distributions and changes thereto are performed in accordance with approved procedures. Changes to the SLQL require l
- eview/ approval by the applicable Manager Design Engineering, ;
Superintendent Quality 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. Design Engineering is responsible for the technical adequacy of the CLQL and ANO Engineering is responsible for the administrative controls on the CLQL within SIMS. Evaluations, reviews and approvals to changes to the CLQL are performed in accordance with applicable procedures. 2.2.7 1 The component level F-list (CLFL) is maintained on the SIMS component data base by ANO Engineering. Components classified as 'F" on this list fall under the requirements of Appendix B of this manual. .Te controls for this list are similar to the controls utilized for the Q-1 st. ANO Arkoneos Nuclear One SECTION: QA MANUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-3
I 2.2.8 i Components that are not Q-listed or F-listed and which are subject to l ASME code requirements or similar design standards, regulatory requirements or licensing commitments or other ANO commitments are classified as "S" in the SIMS component data base. The controls for this list are similar to controls for the Q-list. This list is also I referred to as the component level S-list (CLSL). { l 2.3 RESPONSIBILITIES l 2.3.1 l l ANO recognizes that quality assurance is an interdisciplinary function involving many organizational groups, encompasses many functions and I activities and extends to various levels in all participating I organizations (from the President and Chief Executive Officer to all, workers whose activities may influence quality). The QA Program designates responsibilities and duties of specific individuals, which may be performed by their appointed designees. 1 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 i perform or directly supervise the work. Additionally, independent re views, audits and surveillances are provided by individuals not reporting to the groups responsible for performing the work. l- , i ANO QA MANUAL OPERATIONS REV. 10 l DATE 8/31/88 l SECTION: 2.0 QUALITY ASSURANCE PROGRAM PAGE 2-4 Arkansos Nuclear One i
2.3.3 l The QA Program also includes provisions that require suppliers, contractors, subcontractors, consultants, etc. to maintain and use quality assurance programs reviewed and approved by the Superintendent Quality Assurance. Audits or surveillances by the NQ organization provide assurance of compliance with applicable procedures. 2.3.4 The Senior Engineer Core Reload Design within the Nuclear Design Services section and the Superintendent Reactor. Engineering are responsible for the assurance that nuclear fuel used at ANO is designed, procured, l manufactured and utilized in accordance with regulatory requirements, and ! related industrial codes and standards. On-site quality control of nuclear fuel is implemented through the use of plant administrative procedures. These procedures include the receipt, inspection, handling, { storage and accountability of Special Nuclear Material (SNM). j Individuals who perform receipt inspections are qualified in accordance with paragraph 2.6.3 of this manual. The Quality Control / Quality l l Engineering Superintendent maintains a listing of those individuals ; qualified to perform receipt inspection on nuclear fuel. I i 2.4 PROCEDURES i 2.4.1 l 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 ' l the QA Program. Procedures provide for standard forms, lists, and checkoffs used in documenting the inspections, certifications, reviews. ANO Arkonsos Nuclear One SECTION: QA PANUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-5
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.suaveillances and_ audits. -Programs and procedures are modified or. !
supplemented from time-to-time: as the need for change arises during< the i
' life of the plant.. Quality program policies, procedures and instructions i are contained in the documents listed in Table'3.
'2.4.2 Procedures assure that activities affecting quality are performed under
-suitably controlled conditions. Controlled conditions include the use of appropriate equipment,. suitable ~ environmental conditions for performing q the activity such cs adequate. cleanness and assurance that required.
t prerequisites for-the given activity have been satisfied. Administrative 1 procedures also assure that the need for special controls, processes, ! tests and equipment to attain the required quality and the need for ! verification of quality by inspections, evaluations or tests is taken- t into account. t 2.4.3- i l Other organizations outside of the Nuclear organization may establish written procedures to control support activities affected by the. 1 l requirements of the QA Program. Procedures developed by such 1 organizations are prepared and reviewed for tecnnical adequacy within the i cognizant organization, reviewed by the Superintendent Quality Assurance
.and approved by the cognizant organization's department head, i L 2.5 PROGRAM REVISION AND CONTROL i
2.5.1
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Program revision and control shall be the responsibility of the General Manager Nuclear Quality. .L ANO Arkansco Nuclear One SECTION: QA MANUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-6
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T' , j (? 2.5.2 Proposed changes to this manual are to be submitted by the Superintendento (
-Quality Assurance to.affected management personne1'for review and comment prior to approval and transmittal to' the. Nuclear Regulatory Commission.
After resolution of comments, changes are to b'e approved by the ' Superintendent Quality Assurance,. General Manager Nuclear Quality and the . Vice President Nuclear. 2.5.3 , The Nuclear' Regulatory Commission is to be notified of changes to this I quality program annually for those changes that do not. reduce the ' commitments in the program description previously accepted by the Nuclear Regulatory Commission. ' Changes to the program description that reduce , I the commitments are to be submitted and approved by the Nuclear ! Regulatory Commission prior to implementation. The General Manager i Nuclear Quality is to determine if changes do or do not reduce the i
-l commitments of the QA Program. ,
i 2.6 PERSONNEL 2.6.1 Employees whose duties and responsibilities are related to the QA Program activities at or in support of AN0 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 overall Company policies, procedures and
'l instructions which establish the QA Program, an explanation of the quality organization and a discussion of those procedures which implement l the QA Program related to the employee's specific job-related activity.
l l: L ANO Arkansos Nuclear One SECTION: QA MANUAL OPERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. PAGE 2-7 10 DATE 8/31/88
2.6.2 The education, experience and responsibility requirements ofLindividuals
-l !in'volved 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 mee't the requirements of -)
ANSI N18.1-1971 and Regulatory Guide .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 onerational phase of the plant, are to meet the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. 2.6.3 Personnel performing inspection and examination activities are to be ! indoctrinated and trained-to assure they are aware of the requirements which govern their activity. Inspection and examination personnel are to be qualified according to the applicable codes, standards, '
.l specifications, regulatory requirements and approved procedures.
Personnel performing inspections on those activities occurring'during the operational phase that are comparable in nature end extent to related activities occurring during initial plant design;and construction are to j ! meet the provisions of Regulatory Guide 1.58, Rev. 1 (9/80) and ANSI l N45.2.6-1978, in lieu of ANSI N18.1-1971. 2.6.4 l Personnel involved with welding of materials, systems or components are 2 to meet the appropriate qualification requirements of the ASME Boiler and Presr,ure Vessel Code, Sections III and XI, or for structural welds, the - American. Welding Society (AWS). Structural Steel Code 01.1. Personnel i i L [ ANO Arkansas Nuclear One SECTION: QA MANUAL.0PERATIONS 2.0 QUALITY ASSURANCE PROGRAM REV. 10 DATE 8/31/88 PAGE 2-8 l l
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involved with nondestructive examination of materials, components or. systems are to meet the qualification requirements _ of the American 1 (l SocietyLNondestructiveTestingRecommendedPracticeSNT-TC-1AorASME 'I Section III and XI for.ASME Code materials, components or' systems. Personnel are to be certified to perform these tasks in accordance with l these codes and' standards. 2.6.5
! Personnel performing audits of the QA Program are to meet the experience, i training and qualification / certification requirements of ANSI N45.2.23-1978, and Regulatory Guide 1.146 (8/80), unless otherwise 1
noted in Table 1. 2.6.6 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 collectively meet those requirements identified in the
-Technical Specifications applicable to each nuclear unit. t 2.6.7 l Training records are to be maintained in accordance with approved ,
procedures. For formal training programs, documentation is to include the objective,= content of the program, attendees and date of attendance. 2.7 PROGRAM REVIEW 2.7.1 The General Manager Nuclear Quality through the Superintendent 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 ANO Arkansas Nuclear One SECTION: QA MANUAL OPERATIONS 2.0 QUALITY ASSURANCE-PROGRAM REV. 10 DATE 8/31/88 PAGE 2-9
i 1 :. d Program. 2.7.2 i l Management reviews of'the status and adequacy of the QA Program are. accomplished through regular reports and presentations by the NQ T l organization and through reviews of quality assurance repor'ts.. Quality I assurance reports supply data on the status of outstanding audit and corrective' action items and may identify the status of other significant l QA Program activities as requested by management.
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1 l s l' l QA MANUAL OPERATIONS REV. 10 l DATE 8/31/88 SECTION: 2.0 QUALITY ASSURANCE PROGRAM PAGE 2-10
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3- -3.0! DESIGN CONTROL q 3.1 SCOPE.' .
- t Design-activ'ities are to be controlled to assure that~ proposed plant-changes to the structures, systems, equipment and components conform to applicable regulatory requirements and that design bases are correctly ;
translated into appropriate design documents. Design control activities I are to be in accordance with the requirements of Regulatory Guide 1.64, - Rev. 2 (6/76), unless otherwise noted in Table 1. 3.2 GENERAL .
'l l ,
3.2.1 f l Design Engineering, Project Engineering and Plant Engineering are .; L -responsible for the continued ' upgrading and modification of plant design. ! h Design documents (drawings, specifications, procedures and instructions) originating or released through these departments are to be based upon l the regulatory requirements, licensing based documents, functional requirements, quality standards and design bases in accordance with NRC l licensing' requirements. Design activities may include calculations, analyses, materials selection, equipment arrangement and layouts, ' accessability.for inservice inspection, and the specification of test and inspection criteria. Those design activities performed by individuals
;l ~
within Design Engineering, Project Engineering and Plant Engineering are i controlled by the use of plant modification process (PMP) control l procedures and by applicable administrative and departmental procedures. These procedures include controls to assure that verified computer codes are certified for use and that their use is specified. L L i ANO Arkansos Nuclear One QA MANUAL OPERATIONS SECTION: 3.0 DESIGN CONTROL REV. 10 DATE 8/31/88 PAGE 3-1
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]'I 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. i
.i 3.3 DESIGN INTERFACE Design' control activities include measures for the identification and i
control of design interfaces between the various engineering disciplines : within Design Engineering, between Design Engineering, Project Engineering, and Plant Engineering personnel, between engineering personnel and other support organizations, ano between engineering l personnel 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 1 revision of documents involving design interface. Coordination of the 1 interface control is the responsibility of the originating organization s i j l . management unless otherwise specified in a procedure applicable to the design activity. Design information between interfacing organizations is d to be documented and retained for permanent records. L 3.4 DESIGN VERIFICATION I. 3.4.1 , t To assure the design is adequate and the above requirements and ; l~ procedures are. implemented, Design Engineering, Project Engineering, and Plant Engineering are 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 I ? responsible organization is determined by an assigned engineering L 1 ANO
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QA MANUAL OPERATIONS SECTION: 3.0 DESIGN CONTROL REV. 10 DATE 8/31/88 PAGE 3-2
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reviewer based upon the.importance and complexity of the design, the degree of' standardization and its similarity with proven designs.- In all cases, the. design verification is to be complete prior to. relying upon
~
the component,; system or structure to perform its function. 3.4.2 i 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 organization. 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. i and approved in advance by the responsible Manager or Superintendent. The freco n y.and effectiveness of the use of Supervisors as design ; 1 , verifiers is to be verified by Nuclear 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 adequa:y of a design, it is to: l include suitable qualification testing of a prototype or initial production unit mder the most adverse conditions and carried out in accordance with documented procedures and/or instructions. Testing is to be performed as early as possible prior to installation of plant equipment, or prior to the point when the installation would become irreversible. ANO Arkansas Nuclear one QA MANUAL OPERATIONS SECTION: 3.0 DESIGN CONTROL REV. 10 DATE 8/31/88 PAGE 3-3 __ _ i _.________________ _ _ _ _____ _ ___.____.__ _ .__ _ ___.._______.____________ _ ._ _.
i l
- 3. 4. 4 I Design work performed by organizations outside of the Nuclear- k organization is to receive a documented review'and approval by 1 engineering personnel in accordance with PMP control procedures and
'l applicable departmental procedures. ;
i- 3. 5 DESIGN CHANGE 3.5.1- 1 Methods for the preparation, review, approval-and implementation of l design changes, including field changes, are documented in PMP control '[ ' l procedures and departmental procedures for Design Engineering, Project Engineering and Plant Engineering. Design changes are subject to review ' and verification by the same organization which reviewed and verified the original design unless otherwise :pecified in departmental procedures for j design control'. If changes to an approved design are required to meet plant requirements or conditions, Field Change Requests (FCR)'may be issued or otherwise documented by a cognizant engineer and transmitted I l- with the changes for review and approval in accordance with PMP control '
-l procedures and applicable departmental procedures.
3.5.2 .
- i. Changes from specified design inputs, such as design bases, regulatory L requirements codes and standards (including quality standards) are to be identified, approved, documented and controlled through PMP control !
l procedures and applicable departmental procedures. = 4 3.5.3 During preparation of a design change, the responsible engineering ! organization is to perform a review per 10CFR50.59 to verify compliance ANO
' Arkonsos Nuclear one QA MANUAL OPERATIONS SECTION: 3.0 DESIGN CONTROL E
PAGE 3-4 31/88 i
6 , r,
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t
'f with the SAR and to determine if NRC' approval-of the design change.is 3
. required. _The review is to be documented, reviewed and approved by ,
.the PSC. In addition, any 10CFR50.59 evaluations shall also be reviewed 'I j
and' approved by the SRC; 3.5.4 l
-Design changes are also to'be submitted-to the Superintendent Quality ,
H Control / Quality Engineering prior to plant implementation to verify the L use of appropriate quality codes, standards and inspection requirements in the design documents. ' 3.6 CORRECTIVE ACTIONS - I o When design changes are.made as a result of design deficiencies or errors, corrective actions (for significant conditions) are to be taken ! in accordance with Section 16.0 to determine the root cause'and to institute appropriate changes in the design process -'and/or QA Program to prevent recurrence. When a'significant design change is necessary because of an incorrect design, the design process and verification , procedures shall be reviewed and modified as necessary. i
- 3. 7 DESIGN RECORDS 1
The. Manager Plant Administration is responsible for maintaining permanent records of the design. documents for the construction and testing phases. In~ addition, he'shall be responsible for maintaining records of the
; upgrading or modification of these documents as described in this L section. The controls for maintaining these records are established by specific procedures described in Section 17.0 of this manual. These records provide the historic reference necessary for the safe and
-l reliable operation of ANO.
b l . L L-ANO Arkonses Nuclear one QA MANUAL OPERATIONS SECTION: 3.0 DESIGN CONTROL REV. 10 DATE -8/31/88 PAGE 3-5
[ i
- 5. 0 : INSTRUCTIONS, PROCEDURES AND DRAWINGS' 5.1- SCOPE
.)
5.1'.'1 Instructions, procedures and drawings are provided for the control of i l ~'those activities which affect quality and safety at ANO. Activities y t. covered by written procedures include, as a minimum: administrative,- general plant operations, start-up, shutdown, power operation and load 5 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 (2/78) unless otherwise noted in Table 1.- 5.1. 2 Instructions and~ procedures are also provided for the control of activities relating to 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 appropriate
- 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 1
i QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 5.0 INSTRUCTIONS, PROCEDURES PAGE 5-1 Arkansas Nuclear One AllD DRAWINGS a u
, , , , , , , . , ,,-----n, -
ji 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 NQ organization. 5.3 REVIEW OF INSTRUCTIONS, PROCEDURES AND DRAWINGS 5.3.1-Instructions, procedures and drawings are prepared, reviewed and approved
-in accordance with applicable administrative procedures.
5.3.2 Plant procedures identified in the Technical Specifications for each unit and changes thereto which describe activities required to implement the QA Program are to be reviewed by the PSC prior to submittal of the procedures to designated plant management for approval and subsequent-issuance. Plant Administrative procedures (1000.XX & 6000.XX Series) are also reviewed by the NQ organization to verify compliance to the QA Program requirements. Procedures describing Little Rock activities
. required to implement the QA Program are to be reviewed and approved by a :
ANO
- Arkonnos Nuclear One SECTION:
QA MANUAL OPERATIONS 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS REV. 10 DATE 8/31/88 PAGE 5-2
/
I s procedures task force committee and'NQ organization'to assure compliance
'l .to the QA Program. requirements prior to submittalfof the procedures to-
~
the Department Head rasponsible for implementation for hisi approval and ! 3 subsequent issuance. .;
- 5. i 3 '
Procedures and instructions are to be reviewed no less than every two-( years or prior to each use, if utilized less frequently, then once very ;
- two years, to determine if changes are' necessary to meet NRC commitments [
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, si,,'ificant operator error or equipment malfunction. Applicable procedures are also to be reviewed following any modification to a plant system.
- 5. 3. 4 '
7 Drawings-related to plant changes and modifications are controlled as ! described in;Section 3.0'and 6.0 of this manual. ! 1 5.4 CHANGES TO PROCEDURES 4 5.4.1 ' 1 Changes or revisions to approved instructions, procedures and drawings , are to be reviewed and approved by the same organizations or groups that l performed the original review, unless otherwise noted in specific ANO - procedures and controlled in the same manner as the original. I
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l ANO L Arkansas Nuclear one-SECTION: QA MANUAL OPERATIONS 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS REV. 10 DATE 8/31/88 PAGE 5-3 g j
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+ .h 9.0 CONTROL OF SPECIAL PROCESSES. -
9.1-- - SCOPE-l Special processes are to be controlled through the use of qualified 4 l personnel and approved procedures which meet the requirements of r applicable codes, specifications, standards and other criteria stipulated l in ANO licensing documents. 9.2 GENERAL-t n 9.2.1 I t u l 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. i l , 9.2.2 ,. l Technically qualified personnel are'to establish the procedural and ' qualification requirements for those special processes not covered by i l existing codes or standards or where the QA Program requirements exceed I s the requirements of established codes or standards. L E 9.2.3 y The requirements for welding and nondestructive examination'are to comply l with the' applicable portions of the ASME Boiler and Pressure Vessel Code or for structural welds, the AWS Structural Steel Code D1.1, and the American Society of Nondestructive 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. 1 ' QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES PAGE 9-1 Arkansos Nuclear One L . . .. _. t
l r 9.3-QUALIFICATION' ( d .; g
"" , 9.3.1 4
Special process procedures for welding and nondestructive examinations i are to be qualified prior to use to ensure compliance with applicable codes, standards or specifications. These qualifications are to be ! documented-and also made available for review to the Code Inspector for activities on ASME items, 9.3.2 a Personnel responsible for the performance and verification of special processes are to be qualified and/or certified according to applicable r l codes, standards, specifications, regulatory guides and approved ' procedures. These qualifications and certifications are to be documented 2 and made available for review to the Code Inspector for activities-on ASME items. Personnel qualification and/or certification records for a i special process are to be regularly reviewed by the supervisor responsible for that special process to ensure that the appropriate documents' are up-to-date and personnel are periodically re qualified l and/or _re-certified in accordance with approved. procedures. 9.4 RECORDS
>l The results of special processes are to be documented, reviewed, approved and stored in accordance with appropriate approved procedures and as addressed in other sections of this manual.
l ANO A&onsos Nuclear One SECTION: QA MANUAL.0PERATIONS 9.0 CONTROL OF SPECIAL PROCESSES REV. 10 DATE 8/31/88 PAGE 9-2 l
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4 i 4 9.5 . VERIFICATION. f a Performance of special processes in accordance with applicable codes, i standards, specifications and! approved procedures is verified by Quality
- Control / Quality Engineering personnel through their review, surveillance j and inspection activities, and by Quality Assurance personnel through I their audit' activities. '
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ANO Arkansas Nuclear one SECTION: QA MANUAL OPERATIONS 9.0 CONTROL OF SPECIAL PROCESSES REV. DATE 8/31/88 PAGE 9-3 10
4 + L i^ L10.0 INSPECTION. 10.1; SCOPE-t I s
> Inspections relating to normal operating activities and inspections' i relating to operating activities comparable in nature'and extent-to those occurring during initial plant design and construction are to be- t controlled to assure that inspections are performed in a'ccordance with- '
applicable design documents, codes, standards, specifications and .i procedures. Inspection activities are to be in accordance with l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1. 10.2 GENERAL j 1 10.2.1 j
)
Inspection activities relating to normal operating activities- { (Operational Inspections) include: , (1) Work functions associated with normal operation of the plant (2) Routine maintenance- :i (3) Technical services routinely assigned to the on-site operating , organization I (4) Non-routine maintenance activities and minor modifications made : by the on-site operating organization that.are not comparable i in nature and extent to related activities occurring during initial plant design and construction 21 10.2.2 Inspection activities relating to operating activities comparable in nature and extent to related activities occurring during design and construction-(Construction Inspections) include: , ANO
- Arkansas Nuclear One SECTION:
QA MANUAL OPERATIONS 10.0 INSPECTION REV. 10 DATE 8/31/88 PAGE 10-1
I i g f 1 h
- 1) Non-routine maintenance, except as noted in paragraph 10.2.1
- 2) : Modifications, except as noted in paragraph 10.2.1 The following Regulatory Guides are to be applied, as applicable,;in determining the basis- for required construction inspections: R.G.~1~30, Rev. 0'(4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77); .t
' R.G. 1.37, Rev. 0 (3/73); R.G. 1.94, Rev. 1-(4/76); and R.G. 1.116,. t Rev. 0-R (7/76),
t 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, j 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 procedures, which set forth the requirements and acceptance limits and specify the inspection responsibilities. If inspections require detailed written procedures to perform the task, the proced'ures are to contain, as a minimum, the following: , j, l L 1 (1)- Qualitative and/or quantitative acceptance criteria- ' l- ! (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 p ANO Adoneos Nuclear One QA MANUAL OPERATIONS SECTION: 10.0 INSPECTION REV. 10 DATE S/31/88 PAGE 10-2 1
e , H a
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~
l or measuring and=t'est equipment, such additional ~ accuracy-- requirements are to be specified'within those inspection , 1
- procedures)
(4) A. step-by-step _ description of the~ method.of inspection, examination, measurement or test'to be performed. (5), Identification of those inspection results to be documented. I Inspection forms or checklists are to be used as an aidiini j documenting the inspection at.tivity to assure quality l
' 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 activity being inspected and do not report directly to the'immediate supervisors who are responsible for the activity being inspected. t 10.3.2.1 l Operational inspections may be performed by second-line supervisory j personnel.or by other qualified personnel not assigned first-line supervisory responsibility for conduct of.the work. L 10.'3.2.2 ' Construction inspections are- to be conducted in a manner similar to.that " L associated with construction phase activities in accordance with
] applicable approved procedures.
4 L QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 10.0 INSPECTION PAGE 10-3 Arkonses Nuclear One h
10.3.2.3-
~If individuals performing inspections are not part of the NQ.
organization ,the inspection procedures, personnel qualification
- criteria, and independence from undue pressure such as' cost and schedule are to be reviewed and.found acceptable by the Superintendent Quality l Assurance or Quality Control / Quality Engineering prior to initiation'of the activity, i
10.3.3 1 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. .
1 10.4-INSPECTION POINTS ; r 10.4.1 Inspection hold points are established for non routine maintenance l procedures and design change packages (DCPs) by Project Engineering or-Plant Engineering and reviewed by the Superintendent Quality l l . Control / Quality Engineering for concurrence and possible assignment of ~
-additional inspection hold points to further assure conformance with-applicable instructions, procedures, drawings and related documents or to meet appropriate code and regulatory requirements. Inspection hold points for work functions associated with activities other than , non-routine maintenance and DCPs are established by the originating department, NQ personnel or other responsible individuals and reviewed by the Superintendent Quality Control / Quality Engineering for concurrence.
L ANO Arkansas Nuclear one QA MANUAL OPERATIONS SECTION: 10.0 INSPECTION REV. 10 DATE 8/31/88 PAGE 10-4
e , , _f .5 i i 10.4.2 i
.i Inspection hold points are inserted in procedures based upon safety I significance, complexity of the item or activity, degree of standardization of the ~ item or activity, past performance of the Litem or activity and the ability _ to verify quality by job-site testing.
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)
10.4.3
]
1' y Inspection responsibilities, requirements, information and acceptance criteria for the work activity are to be identified in appropriate,_ ! approved documents (e.g. procedures, checklists, etc.) l
- I L 10.4.4 I i
lt For work involving the modification, repair, replacement or inservice ; inspection of ASME Code materials, parts and' components, the work ; packages are to be made available to the Code Inspector prior to ' commencing work for his review and assignment of inspection hold points. _The' department 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 I; waived-by the Code Inspector.
10.5 DOCUMENTATION
~
10.5.1 p 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 o
L l
-QA MANUAL OPERATIONS REV. 10 '
DATE 8/31/88 ' SECTION: 10.0 INSPECTION PAGE 10-5 Arkansas Nuclear One l.
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. procedures,. instructions or drawings to verify design. requirements; show' I
{ compliance with~ acceptance criteria or identify the cause of rejected ~! items; and identify the appropriate inspection personnel l approving the results. i L 10,5.2 "
- i. ,
Records are.to be maintained in accordance with. approved written 4 procedures and Section'17.0 of this manual. Inspection results on ASME. ' Code' items are available to the Code Inspector for.his review. q 10,5.3-t i 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. 1 10.6 NONCONFORMANCES Noncomforming items found as-a result of. inspection and monitoring activities are identified, segregated and dispositioned in accordance with approved written procedures and Section 15.0 of this manual. -- Rework, repair or replacement performed af ter completion of inspections requires re-inspection to the extent necessary to determine acceptability to established criteria. 1 l ANO Arkonsos Nuclear one
' QA MANUAL OPERATIONS SECTION: 10.0 INSPECTION REV. 10 DATE 8/31/88 PAGE 10-6 l
-.. . . _ _ _ _ _ _ _ __ _ a
a- , i.. I 12,0; CONTROL OF MEASURING AND TEST EQUIPMENT l 12.1 SCOPE
.12.1.1 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 l equipment, unless otherwise noted in Table 1. l 12.1.2 This section.is generally applicable to chemical and. radiochemical equipment, except for. paragraphs 12.3.3, 12.3.4 and 12.4.2. The. controls for the calibration of chemical and radiochemical measuring equipment are to comply with the provisions of Regulatory Guide 1.33, Rev. 2, m Appendix A, Section 10.0, and performed in accordance with chemical.and ; radiochemical control procedures. 12.1.3 4 This section does not apply to rulers, tape measures, levels or other such devices where normal commercial practices provide adequate accuracy. 12.2 RESPONSIBILITIES i 12.2.1 The cognizant superintendents / group supervisors are responsible for establishing and maintaining lists of measuring and test equipment under '~ ANO Arkansas Nuclear one - SECTION: QA MANUAL OPERATIONS 12.0 CONTROL OF MEASURING AND. TEST EQUIPMENT REV. 10 DATE 8/31/88 PAGE 12-1
b j x-their control # that require periodic calibration and for the calibration
] of- this ~ equipment, ~as assigned within approved procedures. d 12.2.2 l
The cognizant supervisor is responsible for identifying measuring and 1 test equipment required for the activity and assures that the devices are used only by qualified personnel, t D 12.2.3 H l Personnel performing the activity are responsible for utilizing only ? properly identified and calibrated measuring and test equipment when-performing inspections and tests for record. -t 12.2.4 - The NQ. organization-is respansible for monitoring test equipment control and use in order to verify compliance with the program. 12.3 GENERAL 1 W :.1
' Calibration procedures are to be established for each type of measuring g 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 " 9 t 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 ANO Arkaneos Nuclear on. SECTION: QA MANUAL OPERATIONS 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT REV. 10 DATE 8/31/88 PAGE 12-2 <
N be based upon the type of equipment, manufacturer's recommendations, 3 st' ability _and. reliability characteristics, required accuracies, use and -
. 'other conditions affecting calibration.
1 12.3.3
~
u Reference standards used in the calibration of measuring and test
~
equipment are to be traceable to the National Bureau of Standards, or if 1 l nonexistent, to accepted industry or ANO standards. Reference standards are to have an accuracy at least four times that of the measuring and I test equipment. In any instance where the four times criteria is unable 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 authorized by responsible management. Reference standards are to be maintained in an environment with temperature, humidity and cleanliness controls compatible with .. maintaining accuracy and operating characteristics of the standards, 12.3.4 i 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 l documented by written report in accordance with approved procedures. If any piece of measuring or test equipment is consistently found to be out-
.e of calibration, it is to be repaired or replaced.
12.3.5 Re-calibration per approved procedures is to be performed when the ' l accuracy of either installed or calibrated equipment is questionable. ANO Arkansos Nuclear one SECTION: QA MANUAL OPERATIONS 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT REV. 10-DATE 8/31/88 PAGE 12-3
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-12.4 EQUIPMENT IDENTIFICATION ~
12.4.1' r Measuring and test equipment lists are to contain sufficient information to uniquely identify each item listed and is to include, as a minimum, [ calibration intervals, tolerances and storage locations. The lists are " also to identify the group responsible for.the control of each item. 1 12.4;2 i Items listed on measuring and test equipment lists are to be tagged, , l labeled or otherwise identified per approved procedures in such a manner that clearly identifies the equipment and their calibration status and provides traceability to the calibration records. I 12.4.3 I Measuring and test equipment found to be out of calibration is to be , tagged and segregated from acceptable equipment in accordance with l approved procedures until repaired and/or re-calibrated. L 12.5 RECORDS i i i- Calibration documentation is to be maintained to verify calibration status, condition, accuracy and out-of-tolerance trends of the equipment. 1 L l l \ o l 1 i I l N I ANO kkeece Nuclear One SECTION:
'QA MANUAL OPERATIONS 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT REV. 10 DATE 8/31/88 PAGE 12-4 l l
13.0 HANDLING STORAGE AND SHIPPING [ 13.1 SCOPE Activities for the handling, storage'and shipping, including cleaning, packaging and preservation of materials and equipment are to be performed. in accordance with' established instructions, procedures or drawings, to. prevent damage, deterioration or loss of the item. Activities are to-comply with the provisions of Regulatory Guide 1.38, Rev.-2,- unless' l
,, otherwise noted in Table 1. t 13.2 GENERAL 13.2.1 !
Instructions for preservation are to be provided for items subject to e deterioration or damage through exposure to air, moisture or other ' environments during fabrication, processing, assembly and interim storage periods. Items are to be cleaned, preserved and packaged as required to preclude deterioration and prevent damage. When maintenance of specific ~ internal or external environments is necessary, it is to be included in' 4 special packaging instructions and maintenance procedures. ' 13.2.2 i: i p Procurement documents assure that any special cleaning, preserving, handling, packaging or shipping requirements- for. purchased material or equipment are taken into account. j- 13.2.3 b l c
'l For critical, . sensitive, perishable or high-value articles, p recommendations for their handling, storage, packaging, shipping and preservation are to be requested from the supplier per the procurement QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 13.0 HANDLING, STORAGE AND PAGE 13-1 L Arkansos Nuclear one SHIPPING
_ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.s ,
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-.5 documents'and furnished to the plant prior'to or upon receipt of.the? 3
' items at_the plant, t [
13.3' SHIPPING CONTROLS. 13.3.1
,, j
. Shipping requirements are to be specified in the procurement documents.
Suppliers' compliance with these requirements are:to include controls to, assure that items are complete and assembled as required; items have been y preserved and packaged in accordance with the procurement documents ' items have been marked and identified-in.accordance with. specifications-and procurement documents; items have been loaded for shipment in such a. - manner as to prevent damage; and required documentation is complete and ; p furnished in accordance with the procurement documents. 13.3.2 L l Special nuclear material and sources are to be shipped and stored as l- .l specified in the operating. licenses and other appropriate regulatory { documents. The Superintendent Health Physics is responsible for assuring 3 l ~that radioactive sources and instruments containing radioactive sources l are stored and handled per these requirements and approved procedures. 7 The Supervisor Radwaste is responsible for assuring that_ low-level. waste
-(
I
'l material is stored and shipped per these requirements and approved procedures. The Superintendent Reactor Engineering is responsible-for' .
assuring that special nuclear material (SNM), as defined in approved I procedures, is shipped, stored and handled per these requirements and the l approved procedures.
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l l l: ANO Arkansas Nuclear one SECTION: QA MANUAL OPERATIONS 13.0 HANDLING, STORAGE AND SHIPPING REV. 10 DATE 8/31/88 PAGE 13-2
'i
t 13.4 RECEIVING r i 13.4.1 l l Materials and equipment are to be received at the plant per approved procedures and subjected to a receipt inspection in accordance with { Section 7.0 of this manual. As part of the inspection activity, received l materials and equipment are to be inspected for damage, deterioration, { l cleanliness and proper identification and markings per approved I procedures for receipt inspection, l 13.4.2 Results of the receiving inspection and disposition of the material or ; equipment are to be documented on receiving inspection records. l Nonconforming items are to be handled in accordance with approved procedures and Section 15.0 of this manual. 13.5 STORAGE CONTROLS I 13.5.1 i Materials and equipment which have completed the receiving process are to be stored based on the classification level of storage specified on the ' procurement documents or related design documents. 13.5.2 Storage control procedures are to be established which include, as a minimum, provisions for the following: controlled access and usage of the storage area; cleanliness and good housekeeping controls; fire protection; protection from environmental hazards; segregation of hazardous materials; and control of those items which have a specified , shelf life. ANO Arkonoce Nuclear One SECTION: QA MANUAL OPERATIONS 13.0 HANDLING, STORAGE AND SHIPPING REV. 10 ~ DATE 8/31/88 PAGE 13-3
i 13.5.3 i Only items which'have completed the receiving process are to be placed in a controlled storage area. Records of the items' location (s) are to be provided by the Superintendent Materials Management (see paragraph 13.3.2 i for control of radioactive sNrces, low-level waste material and SNM) to - identify those items currently in storage and to facilitate inspection i and maintenance planning. Issuance of items from storage for installation or use is to be documented and controlled in accordance with l approved procedures. 13.5.4 Items identified as requiring maintenance during storage are to be , maintained in accordance with a documented maintenance program. 13.5.5 Storage areas are to be monitored by individuals responsible for the storage areas so that the integrity and security of stored items are effectively maintained. Inspections and examinations under the control ( of the Superintendent Quality Control / Quality Engineering are to be performed and documented on a periodic basis to assure that the integrity of the items and their containers is being maintained. Periodic audits under the control of the Superintendent Quality Assurance are also performed to assure compliance with storage requirements. 13.6 HANDLING CONTROLS 13.6.1 Special handling requirements are to be specified in the procurement l documents and approved procedures to protect the quality of items ANO Arkansos Nucleor one SECTION:
- QA MANUAL OPERATIONS 13.0 HANDLING, STORAGE AND SHIPPING REV. 10 DATE 8/31/88 PAGE 13-4
l l susceptible to handling damage. Special tools and equipment are to be provided to handle these items and are to be controlled and maintained < per written procedure to assure safe and adequate handling. .! t 13.6.2 Special handling tools and equipment are to be inspected and tested at specific times in accordance with written procedures to verify that the handling tools and equipment are adequately maintained. Inspection and , test status of these handling tools and equipment are to be controlled in accordance with the applicable sections of this manual, I l i i t QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 13.0 HANDLING, STORAGE AND PAGE 13-5 Arkonoce Nuclear one SHIPPING l t L .
4 14.0 INSPECTION. TEST AND OPERATING STATUS , 14.1 SCOPE ' 14.1.1 The removal from service, inprocess status and return to service of equipment, components and systems for maintenance, modifications repair, l test or inspection is to be controlled per approved procedures. These : controls are to assure that plant personnel are aware of equipment, structure or system conditions and to prevent their inadvertent use unless cleared by operations personnel. 14.1.2 Maintenance activities are to be performed in accordance with an established maintenance program to assure that equipment, systems and structures are maintained in a condition which allows them to perform their intended function. 14.2 EQUIPMENT CONTROL 14.2.1 1 Prior to removal of equipment, components or systems from service for j maintenance, modification, repair, test or inspection activities, j permission is to be received and documented from the Supervisor Shift l Operations. The Supervisor Shift Operations is to assure that the item l- c6^ be released without affecting plant safety. L ANO A&accos Nuclear one SECTION: QA MANUAL OPERATIONS 14.0 INSPECTION, TEST AND OPERATING STATUS REV. PAGE 14-1 10 DATE 8/31/88 l
14.2.2 The status of equipment, components and systems during these activities l l is to be identified in accordance with approved procedures / instructions, which contain, as a minimum, the following: 1 (1) Methods for control of equipment to maintain personnel and reactor safety and to avoid unauthorized operation of equipment l' 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 cases where required documentary evidence is not available, the associated
- equipment or system is to be considered nonconforming and handled in accordance with Section 15.0 of this manual l
(4) Provisions for independent verifications to ensure that
- necessary measures (locking or tagging) to secure and identify equipment or systems in a controlled status have been -
implemented correctly 14.2.3 When entry into a closed system is required, control measures are to be i established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed. l I ANO Arkonoce Nuclear One SECTION: QA MANUAL OPERATIONS 14.0 INSPECTION, TEST AND OPERATING STATUS REV. 10 DATE 8/31/88 PAGE 14-2
14.2.4 i During maintenance or modification activities, certain portions of l systems, as identified in approved procedures, may be subject to potetitial contamination with foreign materials. To prevent such ; contamination, control measures, including measures for access control, I 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. l I 14.2.5 i 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. A status log is to be maintained by the Supervisor Shift' Operations, identifying the current status of such l temporary modifications. Temporary modifications are to be verified by individuals independent of the group performing the activity and documented to assure the required actions are taken to return the equipment or system to its original operating configuration and status. 14.2.6
- When equipment or a system is properly identified as being ready to be l 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 l of the item. l l L QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 Arkonese Nucleor One bER b5
m I 14.2.7 ] Equipment, structures and systems found to be nonconforming as a result ) l of an activity are to be handled in accordance with approved procedures and Section 15.0 of this manual. J l 14.3 MAINTENANCE CONTROL 14.3.1 l In addition to the requirements and controls identified in subsection 14.2 of this manual, a maintenoce program is to be planned and scheduled through the Manager Maintenance to assure that the safety of the plant is not compromised nor the Technical Specifications l 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 spe:ified in the' design documents, material I 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 Manager Maintenance. 14.3.2 A preventive maintenance program, including procedures and instructions for systems, structures and components, is to be established and ' l maintained under the Manager ANO Engineering which prescribes the frequency and type of maintenance to be performed in order to preclude equipment malfunctions. Implementation of the program is the responsibility of the ANO Plant Manager and is implemented by qualified ' maintenance personnel in accordance with approved procedures and ANO
. Arkansos Nuclear On.
SECTION: QA MANUAL OPERATIONS 14.0 INSPECTION, TEST AND OPERATING STATUS REV. 10 DATE 8/31/88 PAGE 14-4
i 1 instructions which specify the work activities, acceptance requirements j and the control measures to assure adequate quality. -When equipment malfunctions occur, the cause is to be promptly determined, evaluated and. l recorded per approved procedures'and Section 16.0 of this manual. 14.4~ OVERALL PLANT STATUS I 14.4.1 l The Supervisor Shif t Operations is provided sufficient 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. 14.4.2 The turnover of duties to personnel on succeeding shifts is conducted in l 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. 4 A 1 i. l i i ANO Arkonses Nucleor One SECTION: QA MANUAL OPERATIONS 14.0 INSPECTION, TEST AND OPERATING STATUS REV. 10 DATE 8/31/88 PAGE 14-5
15.0 NONCONFORMING MATERIAL PARTS AND COMPONENTS 15.1 SCOPE t Nonconforming items are to include materials, parts, components and, as applicable, services (including computer codes) that do not conform to ' applicable regulations, codes, standards, specifications, drawings or licensing documents. Nonconforming items are to be controlled in accordance with approved procedures to prevent their inadvertent use or installation. These procedures are to contain measures to assure the prompt identification and notification, documentation, segregation, technical review and disposition of a nonconforming item. , 15.2 GENERAL 15.2.1 It is the responsibility of each individual to identify a nonconformance and to report it to their cognizant supervisor for review and concurrence. The initiator is to document the nonconformance as l . identified within approved procedures. If the nonconformance is determined to be a Technical Specification violation and/or reportable to the NRC, see subsection 16.5. 15.2.2 l Nonconforming items are to be identified by tagging, marking or as l otherwise identified per approved procedures to control further processing or, when physical segregation is not practical, to provent inadvertent use or installation of the item. Nonconforming items are to be segregated from acceptable items unless they are currently installed or their size, weight, configuration, etc., makes it impractical to move to a segregated area. Tags and/or markings are to remain on the item
-l until the disposition is complete per approved procedures.
ANO kkoneos Nuclear On. SECTION: QA MANUAL OPERATIONS 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS REV. 10 DATE 8/31/88 PAGE 15-1
P 15.2.3 i l Reports of nonconforming items are to identify the group responsible for dispositioning the nonconformance. The assigned individual within the responsible group is to evaluate the nonconformance and confer, as ! appropriate, with interf acing groups to determine a recommended disposition. The disposition for materials, parts, components and as 1 applicable, services (including computer codes), which may be reject, rework, repair or use-as-is, and any actions taken/ required to be t& ken , as a result of the disposition are to be documented on the report. 15.2.4 Review of the disposition for concurrence is to be performed by the l individual / group identified within approved procedures. If the review group or individual cannot agree with the assigned individual on the disposition, the Executive Director Nuclear Operations or the Vice President Nuclear, as appropriate, is to decide. For a repair or use-as-is disposition, a cognizant individual knowledgeable in the design requirements for the affected item is also to review the report for concurrence of the disposition. Written justification for the design change, repair or deviation that has been accepted is to be documented to denote the as-built condition and is to be made a part of the report. 15.2.5 The acceptability of rework or repair of materials, parts, components, systems and structures is to be verified by re-inspecting the item as originally inspected or by a method which is at least equal to the original inspection method. The rework and repair inspection records are t to be documented and become part of the permanent records for the item. ANO kkoneos Nuclear One . SECTION:
' QA MANUAL OPERATIONS 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS REV. 10 DATE 8/31/88 PAGE 15-2
15.2.6 i Upon completion of the disposition, the nonconformance report is to l receive an independent review in accordance with approved procedures, for concurrence or possible assignment of additional actions pertaining to , the disposition. 15.2.7 i For ASME Code, Section III, Division 1 materials, parts and components dispositioned repair or use-as-is, the nonconformance report is to be subject to review and concurrence by the Code Inspector. 15.3 SUPPLIER NONCONFORMANCES 15.3.1 Procurement documents are to contain requirements for the l vendor / contractor to identify to AND those items which violate a technical or material requirement of the procurement document and which results in a disposition of repair or use-as-is. All such l nonconformances are to be reported to ANO for evaluation and acceptance. The vendor / contractor is to document such nonconformances on its applicable nonconformance report which is to be included in the final l documentation package submitted to ANO, in accordance with the procurement documents. 15.3.2 Upon receipt of items at the plant, Quality Assurance personnel are to review any nonconformance reports in the documentation package to ensure the nonconforming items have been properly dispositioned'and accepted by
-l ANO.
QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 15.0 NONCONFORMING MATERIAL, PAGE 15-3 > Arkoneos Nuclear one PARTS AND COMPONENTS
j l 15.4 RECORDS
]
15.4.1 1 l Upon completion of disposition and verification activities, the completed ' nonconformance report, and related dncuments generated to ensure proper disposition and resolution of the nonconformance, are to be forwarded to ' and maintained by the Document control Center. 4 15.5 DEFICIENCY TRENDING l The Superintendent Operations Assessment through the Supervisor In-House ' Events Analysis is to maintain and issue a quarterly trending report of nonconformances to the Vice President Nuclear for review. 1 l l ) ANO A&onsos Nuclear On. SECTION: QA MANUAL.0PERATIONS 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS REV. 10 DATE 8/31/88 PAGE 15-4 \-. - - - -. .. . . . . . - . --
i l 16.0 CORRECTIVE ACTION l 16.1 SCOPE I l l A corrective action system is established to assure that conditions adverse to plant safety, such as failures, malfunctions, deficiencies, deviations, defective materials and equipment, abnormal occurrences and i 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 et other abnormal occurrences or conditions are encountered, they are to be reported to responsible authorities for review and disposition in ' l accordance with approved procedures. 16.2.2 Cognizant supervisors are to rev:ew discrepar.cies discovered during the course of station operations and teke appropriate action to resolve the .l discrepancies. For conditions adverte to safety, they are to initiate corrective action to preclude recurrence. For significant conditions l adverse to safety, they are to initiate action to identify their root causes and take necessary corrective action to preclude repetition. ANO Arkonsos Nuclear One QA MANUAL OPERATIONS SECTION: 16.0 CORRECTIVE ACTION REV. 10 DATE 8/31/88 PAGE 16-1 i _ _ _ ._
I 1 I i 16.2.3 ' Evaluation of the corrective action is to be performed by the i l individual / group identified within approved procedures to determine its adequacy and completeness and to assure the need for additional i corrective action. If the corrective action is acceptable, follow-up action to verify implementation, documentation and close-out of the l corrective action commitments is to be performed per approved procedures. : 16.2.4 1 If agreement upon the resolution cannot be achieved, the condition is to be referred to the appropriate level of management as specified in ' approved procedures. 16.3 SUPPLIER DEFICIENCIES
- When vendors furnish products or services that do not conform to the '
requirements of the applicable purchase contract and, in the opinion of ' the cognizant supervisor, the vendor warrants consideration for reappraisal, the cognizant supervisor is to submit a vendor reappraisal ' ! request to the Superintendent Quality Assurance for determination of I action to be taken. Results of the reappraisal, together with a request for specific corrective actions, are to be transmitted to the vendor. If ; i the vendor does not improve his quality assurance system and products as I requested, the Superintendent Quality Assurance is to remove the vendor I. l from the Qualified Vendor List (QVL) in accordance with approved i !. procedures. ' 16.4 SIGNIFICANT CONDITIONS t Significant conditions adverse to safety are to include, as a minimum, the following: ANO QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: 16.0 CORRECTIVE ACTION PAGE 16-2 Arkonnos Nuclear One
l i (1) Conditions that have a direct adverse effect on the safety of the plant per the plant Operating License and Technical l Specifications (2) Conditions that have caused the uncontrolled release of 1 radioactive materials (liquid, solid, gaseous or air particulate) to the environs (3) Adverse quality trends which could lead to unsafe plant operations l 16.5 REPORTABLE EVENTS 16.5.1' When-significant conditions adverse to safety are discovered, the responsible supervisor and department head are to evaluate the condition l and determine if it is a reportable event, t 16.5.2 Adverse conditions which are determined to be reportable per the Technical Specifications to the NRC are to be documented by the initiator per approved procedures, reviewed by the responsible supervisor and forwarded to the Manager Licensing so the appropriate report can be prepared. I 16.5.3 Upon disposition of the report by the responsible group, the PSC reviews the report for concurrence and possible assignment of additional corrective actions and forwards the report to the Executive Director Nuclear Operations for final approval. l. ANO kkonsos Nuclear one QA MANUAL OPERATIONS SECTION: 16.0 CORRECTIVE ACTION REV. 10 DATE 8/31/88 PAGE 16-3 l
16.5.4 i l The Licensing department is responsible for transmitting approved reports to the NRC within the time period specified in the Technical ! l Specifications and approved procedures. 16.6 VERIFICATION i 1 Verification by surveillance or audit of the effective implementation of l corrective actions is to be periodically performed and documented by - i Quality Assurance personnel. Audits are to be performed in accordance with Section 18.0 of this manual. I i' l 1 l l V ANO Arkonsos Nuclear One QA MANUAL OPERATIONS SECTION: 16.0 CORRECTIVE ACTION REV. 10 DATE 8/31/88 PAGE 16-4
17.0 QUALITY ASSURANCE RECORDS . 17.1 SCOPE 17.1.1 l Documentation covering design, construction, procurement, fabrication. l inspection, operation, maintenance, nonconformance and corrective action, test and audit activities is to be filed and stored to provide objective ' evidence of quality-related activities and to assure the ability to reconstruct significant events. Control of records is to be in accordance with Regulatory Guide 1.88, Rev. 2 (10/76) unless otherwise noted in Table 1. 17.1.2 Quality assurance records are to include operating logs; results of l reviews, inspections, tests, maintenance, audits, material analyses; monitoring of work performance; qualification of personnel, procedures. l and equipment; historical drawings, specifications, personnel exposure, engineering reports, calculations, procurement documents, calibration procedures and reports, nonconformance reports, corrective action reports, correspondence and releted records pertinent to quality as l defined in approved procedures. ' 17.2 RESPONSIBILITY 17.2.1 The Manager Plant Administration, is responsible for the establishment, implementation and maintenance of the records management program to be l used throughout the operational life of ANO and for ensuring that L documentation retention requirements comply with applicable Technical Specifications, codes and regulations. l ANO Arkonses Nuclear One SECTION: QA MANUAL OPERATIONS 17.0 QUALITY ASSURANCE RECORDS REV. 10 DATE 8/31/88 PAGE 17-1 l
17.2.2
)
Personnel, other than plant staff, and outside firms who perform work on ANO in the areas of design, procurement, maintenance, modification, testing, quality assurance and special nuclear materials are to provide-documentation / certification records to ANO for subsequent storage and l retention by the Document Control Center. i 17.2.3 Quality Assurance personnel are to periodically audit quality-related records and records filing and storage procedures to assure that the records management program is being properly implemented. Audits are to be performed as outlined in Section 18.0 of this manual. 17.3 DOCUMENTATION RETENTION t 17.3.1 Lifetime Quality Assurance Records t 17.3.1.1 ' Lifetime records are defined as those which meet one or more of the following criteria: (1) Those which would be of significant value in demonstrating capability for safe operation (2) Those which would be of significant value in maintaining, reworking, repairing, replacing or modifying the item (3) Those which would be of significant value in determining the cause of an accident or malfunction of an item (4) Those which provide required baseline data for inservice inspection ANO ktoneos Nuclear one SECTION:
' QA MANUAL OPERATIONS 17.0 QUALITY ASSURANCE RECORDS REV. 10 DATE 8/31/88 PAGE 17-2
l 1 17.3.1.2 Lifetime quality-related records are to be maintained for the life of the particular item while it is installed or stored for future use as I prescrioed in approved procedures, i 1 17.3.2 Non-Permanent Quality Assurance Records I l 17.3.2.1 Non permanent records are defined as those which meet all of the ' following criteria: (1) Those of no significant value in demonstrating capability for safe operation (2) Those of no significant value in maintaining, reworking, repairing, replacing or modifying the item (3) Those of no significant value in determining the cause of an accident or malfunction of an item < (4) Those which do not provide baseline data for inservice inspection 17.3.2.2 Non-permanent records are to provide evidence that an activity was ' performed in accordance with applicable requirements and be retained for l specified periods as directed by the approved procedures for document retention and disposition. 17.3.3 Categories of permanent and non-permanent records to be maintained and l their appropriate retention periods are described in approved procedures. i ANO Arkoneos Nuclear one SECTION: QA MANUAL OPERATIONS 17.0 QUALITY ASSURANCE RECORDS REV. 10 DATE 8/31/88 PAGE 17-3
1 i' i i 17.3.4 1 i The Superintendent Quality Assurance is responsible for receiving, inspecting and authenticating such documents as directed by approved ! procedures for turnover of quality assurance documents from suppliers to ! ANO. When approved for receipt by Quality Assurance, such records are to be transmitted to the Document Control Center for filing and storage. 1 17.4 STORAGE i 1 17.4.1 , 1 Permanent records are to be microfilmed and the microfilm stored within a controlled area at ANO per approved procedures. A duplicate set of microfilm is also made and stored at a remote location. 17.4.1.1 > For storage of film and other special processed records, humidity and temperature controls are to be provided to maintain an environment as
'l recommended by the manufacturer and approved procedures.
I 17.4.1.2 i I A list is to be prepared in accordance with approved procedures ' designating those personnel who have access to the storage files. 17.4.2 l Records storage systems are to provide for the accurate retrieval of information without undue delay and be sufficient to control and account for records removed from the storage facility. l l' l-ANO htoncos Nuclear One SECTION: QA MANUAL OPERATIONS 17.0 QUALITY ASSURANCE RECORDS REV. 10 DATE 8/31/88 PAGE 17-4
!- l 17.5 RECORDS INDEXIhG AND RECEIPT CONTROL ;
17.5.1 . i Indexing methods and systems for quality-related records are delineated ! l in approved procedures for records management. 17.5.2
- Records submitted for storage in either lifetime or non-permanent files are to be subject to the following requirements for receipt control:
(1) Establishment of a records list designating the required i quality-related records - (2) Establishment of a system designating criteria for document ' l inspection to assure that records-are complete, legible and received in good condition (3) A file system to indicate which quality related documents have been received 17.5.2.1 Implementation of receipt control requirements for storage is the responsibility of the Manager Plant Administration, 17.6 FINAL DISPOSITION The Manager Plant Administration is responsible for disposal of
- l quality-related records in accordance with approved procedures for j
document retention and disposition, which permits periodic purging of . records retained past their required retention date. l l ANO
- Arkonees Nuclear One SECTION:
QA MANUAL OPERATIONS 17.0 QUALITY ASSURANCE RECORDS REV. 10 DATE 8/31/88 PAGE 17-5
4 18.0 AUDITS 18.1 SCOPE-18.1.1 l 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 check lists and are to conform to the applicable portions of Regulatory Guides 1.144, , Rev. 1 (9/80), and 1.146, Rev 0 (8/80), unless otherwise noted in Table
- 1. ,
18.1.2 i The audit program is to include provisions to determine the compliance l with and effectiveness of the QA Program in controlling structures, I systems, components and activities in accordance with the rules set forth in the codes, standards and regulations identified in the Introduction of this manual, i 18.2 AUDIT PERSONNEL l 18.2.1 The Superintendent Quality Assurance is assigned auditing responsibility
.l within the QA Program and is responsible for the selection and assignment
[ of auditors. Auditors are to be independent of any direct responsibility
- for performance of the activity which is to be audited and are not to
[ report to a management representative who has direct responsibility for l the activity being audited. ANO Arkoneos Nuclear One
' QA MANUAL OPERATIONS SECTION: 18.0 AUDITS REV.
DATE 8/31/88 PAGE 18-1 10
i 18.2.2 Auditors assigned auditing responsibilities are to have experience and training commensuate 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 pertinent expertise, personal characteristics, education ' and capability. If no one within the NQ 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 performing the required audits. Proficiency of audit
- personnel is maintained by one or more of the following methods:
(1) Regular, active participation in the audit process (2) Review and study of codes, standards, procedures and instructions (3) Participation in training or orientation programs 18.3 AUDIT SCHEDULE 18.3.1 Audits are to be performed on a planned and periodic basis in accordance with an audit schedule. Audit schedules are to be prepared at the beginning of each year by the NQ organization and approved by the Superintendent Quality Assurance, General Manager Nuclear Quality and the SRC. ANO htonoce Nuclear one QA MANUAL OPERATIONS SECTION: 18.0 AUDITS REV. 10 DATE 8/31/88 PAGE 18-2 i
"- ~ ~ r
s-I L 18.3.2 l Audit schedules assure that, as a minimum, those audit areas identified within the Technical Specifications applicable to each nuclear unit are audited, under the cognizance of the SRC, at the indicated frequencies l within ANO. i l 18.3.3 4 i 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 l 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. 1 18.3.4 e Periodic reviews of the audit programs are to be performed by the SRC or their appointed management representative at least semi-annually to assure that audits are being accomplished in accordance with the ' requirements of the Technical Specifications, this manual and Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1. ; 18.3.5 ! Regularly scheduled audits may be supplemented, as required, to cover
- unforeseen events or changed requirements.
ANO Arkoneos Nuclear One QA MANUAL OPERATIONS SECTION: 18.0 AUDITS REV. 10 DATE 8/31/88 PAGE 18-3
9 18.4 AUDIT IMPLEMENTATION t 18.4.1 Audit plans and checklists are to be prepared by the auditor and approved by the Superintendent Quality Assurance prior to performing the audit. : Checklists are to be ustd during the audit to assure that all requirements of the activities audited are addressed during the audit and I 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 18.4.3 Deficiencies identified as a result of an internal audit are to be ! recorded on an Audit Finding Report (AFR) by the auditor and issued to the department head responsible for the area audited for corrective action. The department head or their assigned designee is to provide L 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 group is i l ANO ktonoce Nuclear One QA MANUAL OPERATIONS SECTION: 18.0 AUDITS REV. 10 DATE 8/31/88 PAGE 18-4
. _ _ . . . , _ _ _ . _ . _ . . . . . _ ___ . . . ~ . _ _ _ - - _ _ _ _ _ . . _ . _ - - . _ _ _ _ _ _ _
- . . ~ . - . . _
conducted in the deficient areas to verify proper and timely implementation of corrective action commitments. Follow-up actions are to be documented on the AFR. 18.4.4 l Internal audit reports pertaining to plant activities are to be , independently reviewed by the PSC and the SRC to determine if additional corrective actions need to be initiated to assure continued safe 3 l operation of ANO. Internal audit reports pertaining to off-site activities are to be independently reviewed by the SRC. In addition to these reviews, the audit reports are to be distributed, as a minimum, to l the General Manager Nuclear Qu'ality, Superintendent 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 conduc.ted by QA i personnel are to be recorded and distributed to the General Manager Nuclear Quality, Superintendent Quality Assurance and a designated representative of the audited organization. Deficiencies are to be recorded on an AFR, and the audited organi:ation is to describe actions taken to correct deficiencies and prevent recurrence on the AFR. Corrective actions are to be verified by Quality Assurance personnel and documented on the AFR. 18.5 RECORDS Written internal / external audit reports, including checklists AFR's and related documentation supporting the follow-up activities are to be l forwarded to the Document Control Center for storage in accordance with Section 17.0 of this manual. ANO Arkansos Nuclear One QA MANUAL OPERATIONS SECTION: 18.0 AUDITS REV. 10' DATE 8/31/88 PAGE 18-5
18.6 NUCLEAR FUEL AUDITS ' l ANO delegates to System Services Inc. (SSI), a wholly-owned subsidiar of Middle South Utilities, Inc., the responsibility for performing those quality assurance functions necessary to assure that its nuclear fuel is designed and fabricated in accordance with regulatory requirements and accepted codes, standards and specifications. The SSI Quality Assurance , section monitors the design and fabrication of the fuel through a program of audits of the fuel fabricator, including both design review audits and fuel fabrication audits. SSI also conducts audits of component suppliers as deemed necessary by the Manager, Quality Assurance (SSI), to ensure the quality of the fuel. Formal audit reports are issued by SSI to document their audit activities and to identify nonconformances or other , items requiring action by the fuel fabricator. Resolution of nonconformances or other items requiring action is verified by SSI and documented in follow-up reports. The Superintendent Quality Assurance l (ANO) is on distribution for all audit and follow-up reports. These audit reports are to be forwarded to the plant and stored in accordance with Section 17.0 of this manual. I ! 1 QA MANUAL OPERATIONS REV. 10 I
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h NOTE- Procedures merked with an w shall either be superceded by Per control procedures (6000.XX series) or revised to reflect n h 93 ggg hL h gh Fy i requirements of the Plant Nodification Manual by end of 1988. g un g d ai , P .En i
; gaND-f1 Lit #EL_ORCAMIZATIW4 CHARTS x 3P-1000.01 ORGAN!lifl0N ApG h IBILITY
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.1ABLE 3- 1 m 7 QUALITY PROGRAM . POLICIES, PROCEDURES' AND INSTRUCTION [
MANUALS-LIST
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3
.1. Quality Assurance Manual Operations-l 1
The Quality Assurance Manual. Operations establishes the policies'and .i a guidelines of the QA Program for ANO ,This program is to be l
, .followed by all, organizations involved in safety-related work- .,
applicable to ANO. I ( 2. Little Rock Procedures
)
The Nuclear organization in Little. Rock employs a system of .;
/j . procedures in order to implement the QA Program requirements for the~. ;!
control.of design, engineering, nuclear fuel, licensing, training
-l cand procurement activities in support of ANO.
,' ' fl l These procedures and revisions thereto are prepared by Nuclear personnel, reviewed and approved by the General Manager Nuclear. 1
-l Quality, the Procedures Task Force and the responsible department $
head.
- 3. Nuclear Quality Procedures i
'The HQ organization employs a system of' procedures developed to '
y assure proper implementation of the.QA Program. These procedures-L provide technical and administrative' instructions to the NQ staff to'
. aid in implementing their responsibilities within the QA Program.
.g These procedures are reviewed / approved by the Superintendent Quality Assurance and/or' Quality Control / Quality Engineering and the General I; Manager Nuclear Quality.
V QA MANUAL OPERATIONS REV. .10 DATE 8/31/88 SECTION: TABLE 3 PAGE T3-1 Arkoneos Nuclear One l 4=< s. - - - -. . . . 4
^*^.f [,- ' so, x ~ - -, j ? o
^ '
- 4. Overall' Plant Adminstrative Procedures Manual
!f w (The plant operation. organization employs a system _of proceduresL ! +
designated as'Overall Plant Administrative Procedures. These )' :l procedures implement;the-QA Program requirements and control on-site , L ,
' activities. 'Overall Plant Administrative Procedures' and changes ;
thereto are prepared by the plant staff, reviewed by.the Plant t l . Safety. Committee and: approved _by the Executive Director Nuclear Operations. The procedures and revisions are also reviewed by the [ ' l Superintendent Quality Assurance to assure that the QA Program F q commitments-are met. .!
- 5. Departmental' Plant Administrative Procedures iI Eachd'epartment (operations, maintenance, engineering and technical .i support, training, etc.) at the plant has developed procedures'in .
i support of the Overall Plant Administrative Procedures and the QA. . L Program. These procedures provide technical and administrative instructions to:the various departments to aid in implementing their. j ll responsibilities within the.QA Program.. Each department head is , responsible to perfonn a review of their procedures to assure conformance with the QA Program. These procedures are reviewed by
-the Plant Safety Committee and approved by designated plant I management. Plant Modification Process procedures (6000.XX Series) which stipulate activities for Design Engineering'are also reviewed 4 and approved by the General Manager Design Engineering. !
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i ANO Arkaneos Nuclear One QA MANUAL OPERATIONS SECTION: TABLE 3 REV. PAGE T3-2 10' DATE 8/31/88 l
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I t P APPENDIX:A -
-QUALITY PROGRAM FOR. TRANSPORT PACKAGES T '
1.0 INTRODUCTION
4 1.1 _The quality program for transport packages containing' -l radioactive material is designed to comply with the- , q
. requirements of_this manual and with.the quality assurance .t guidelines identified in-10CFR71~,.Subpart H -_ Quality i Assurance, subject to exceptions noted in Attachment A to~this 1 Appendix. . -'
1.2 ~ Attachment A to-this Appendix identifies the applicability of . each section of'the Quality Assurance Manual OperationsJ to the d Quality _ Program for Transport Packages.- 1.3 Attachment B to this_ Appendix contains the Quality Assurance i
-Program Approval document which shows NRC approval of this program on ' January 23, .198S.
l 4 5
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l-ANO QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: APPENDIX A - QUALITY PROGRAM PAGE AA-1 ' l9 1ktonsos Nuclear One TRANSPORT PACKAGES o w. ' 1' : 7, -.- .- . ,
e i ATTACHMENT A 10CFR71 Appendix H. The following sections of the most currently approved revision of the QA Manual Operations'will be applied as stated below (Note specific l paragraphs are to revision 10 paragraph numbers which could change during *
-subsequent revisions).-
Section 1 - Applicable Section 2 - Applicable-l Section 3 - Not applicable. ANO will use only licensed packaging which has been designed under a QA program which has been submitted to the NRC for approval. Section:4 - Applicable Section 5 - Applicable' Section 6 - Applicable Section 7 - Applicable Section 8 - Generally applicable except for paragraph 8.2.2 and 8.2.3. Due to size, uniqueness, low volume and the method of l supplier, identification of each package, ANO tagging of each package is not necessary. , Section 9 - Not applicable. We do not consider this subject as a "Special Process" in the context of 10CFR71, Appendix H Section'71.119 which is a restatement of 10CFR50, Appendix B Criterion 9. ANO
. Arkansoe Nuclear One SECTION:
QA MANUAL OPERATIONS APPENDIX A - QUALITY PROGRAM TRANSPORT PACKAGES REV. 10 DATE 8/31/88 PAGE AA-2
( l
'1 7a ATTACHMENT A (continued) j 10CFR71 Appendix H 1
I Section 10 - Applicable
.l Section 11 - Not applicable. ANO will not be testing the package-in the' l
context of 10CFR71', Appendix H, Section 71.123 which-is a i restatement of 10CFR50, Appendix B Criterion 11. 1
-Section 12 - Generally applicable except for paragraph 12.3.4. -This -l paragraph only applies to Health Physics measuring and- .
testing equipment that is used to calibrate other devices (used as a-standard'). Health Physics survey equipment is ~ response checked prior to each use. Section 13 - Generally applicable except for paragraph 13.5., ANO 'does
-l not " store"' package, therefore the' storage section does not apply.
ll L i 1 'Section 14 Not applicable. See Section 11 comments above.
- -j Section 15 - Generally applicable except for references to the various ll' types of dispositions in paragraphs 15.2.3 to 15.2.5. '
p : Nonconforming material or, equipment will be returned to the vendor or will be replaced. [ ; Section 16 - Applicable ' Section 17 - Applicable Section 18 Applicable 1 E ANO H Arkoneos Nuclear One ' SECTION: QA MANUAL OPERATIONS APPENDIX A - QUALITY PROGRAM TRANSPORT PACKAGES REV. 10 DATE 8/31/88 PAGE AA-3 l 1 !
_ - ._ .~ . _. . . _ _ _ - _ _ _ _ 7.- .y n , 1 t y i ATTACHMENT B i
,,,,,n,
- u.s. mucLean meoutATont coeseussion 't **0my"
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, QUALITY ASSURANCE PROGRAM APPROVAL-POR AADe0ACTfvt a4ATERIAL PACKActs
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l i- ! i l2 I~ I l ll *wevem ie v. Ana.c sas.,, act e issa.m en. ness one same,y nwomamoa Acr e ion. m emases as Tme io.cose et rewer a r noeu ne c v., t een rt-. . ea. e,e, essa.noa.no,sive,e . er m - as.ee -
; e. oueur Aseweae. eve, e.issannee nem s e e. ev ese Tne awe.W is moves e eeuwy v.reemes ea e anasa
[ 71.101 of 10 CPR vest Ft. The enerovW e sue.et to era soonese. ruses requieceas. ene eteers et ene Nuc.or Reguestory Conmusessa i; a e, neesene,in enact ens se say eeneineas sessenes on . ;
- l. .
(- a maass a smesmArion onTE l l ' l Arkaatat pnwer a tioht comoany January 31. 1990 Cl i siam aoonau l ll P.O. Box 551 . occasi muussa .i l i cnv- l st Ars i me cops It Little Rock' 1 AR I 7:203 71 0341 3
$ oWak TT AM8eC8 emo04aas aMaf oh oA7363) k August 27. 1979 and January 4. 1985 h,!
l lL , 1 Activities conducted under applicable criteria of Appendix B of 10 CFR h Part 50 to be executed in accordance with Attachment A to QA Manual I, ( AP&L-TOP 1 A) for Arkansas Power Station Nuclear One. Units 1 and 2 [ ll J0 octet hos. 50-313 and 50-358) with re9ard to transportation packages. ., I" ll l r l
. . , ?=. -. .
L, lL r ;r/c' ' : a. , ,; r .. . .. [' l 6, S. !d i ll ).I 1 ll li 1 I) ! i Il ', l! l r ...., . l lI , ,
/ L: l l .
- i 1 1 <
l l . l i II l li I , I; i t Ri I: I l' ' I l l' ,1 i- 1; . 1 i- li 31 q l li I- ! rom TNr u.s NucLaAm asautATony commission f p CharlesM E.!ac one d JAN 2 3 f!BS 11 CHIEF. TRANSPORT ATION CSRTIFICATION sRANCM DATE I: Divis ON OF FutL CYCLt ANO WATEmeAL SAFETY l l onics oF NUCLE AA MAT $ RIAL SA8CTv ANO SAFEouARDS __l a amurureras _ _ _ _ _ _ _ ______ ____________________ __ ____ ----- L ANO _ Arkansos Nuclear One SECTION: QA MANUAL OPERATIONS APPENDIX A - QUALITY PROGRAM TRANSPORT PACKAGES REV. DATE 8/31/88 PAGE AA-4 10
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t APPENDIX B p -!
. QUALITY PROGRAM FOR FIRE IPROTECTION' c
1.0 INTRODUCTION
l 1.1' The fire protection program was developed to define the i organizational. responsibilities, procedural controls,; fire 4
- brigade staffing and training and the quality assurance .
i provisions that have been established for'the nuclear plant. 4 The overall objective of-the fire protection program is to' i minimize both the probability and consequences of postulated- g fires and to maintain the capability to safely shut down the-plant if a fire should occur. j 1.2. The scope of the fire protection program includes-those fire i protection and detection systems,'and'thoseistructures'and. Et components (such as fire doors, fire-dampers,-and penetration q seals) which, as identified in the plant's fire hazards-. . analysis report, are rtccited to rostrIrt the damage caused by. , a single exposure tira to safety-re h ted equipment and equipment required to actif ave and maintain safe plant shutdown- ! to within those limits set furth in Section'1 of. Appendix R to'. 1 10CFR50.
. 1.3 The quality progra,a for fire protection is designed to comply 1 3 with the requirements of this manual and with the quality :
- k. l assurance guidelines. identified in BTP-APCSB 9.5-1, Rev.'2, July 1981, Guidelines for Fire Protection for Nuclear Power 1
', 1 o
Plants, subject to exceptions noted in this Appendix. i i i ANO QA MANUAL OPERATIONS REV. 10
+
DATE 8/31/88 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-1 Arkansas Nuclear On. FOR FIRE PROTECTION l fe -e . - _ _ _ _ _ _ __.m_ _ _ ______._____________._____m
R. ,
. ;1 +
)
+
.. l 1.4fWithrespecttoregulatorycommitments,ANOis;comrittedto. -j
~
i implementing.the requirements'of the following,. Wiject: tot g . excepti:::n'noted in.this Appendix:
^1
*y.
5[ 1. 10CFR50, Appendix A, General Design Criterion- Fire Protection. .
- 2. Specific sections of 10CFR50.48 Fire Protection and 10CFR50, Appendix R, Fire Protection for Nuclear Power.
,n Facilities-Operating Prior to January 1, 1979. These sections are as follows:
III.G. Fire Protection Safe. Shutdown Capability- ! i 1 III.J. Emergency Lighting ., 7 III.L. Alternative.and Dedicated Shutdown Capability. j i 111.0. Oil Collection System for. Reactor Coolant Pumps- j q 1.5 Other fire protection commitments are contained-in the following references and documents [ l 1.- Facility Operating' License (s) including Technical
-g h -Specification (s)~ .i
-t u
.l ~ 2. Safety Analysis Reports '(SAR)'
' [-.
l 3. Fire Protection Safety Evaluation Reports (SER) i
- 4. Regulatory correspondence to and from the NRC (includes applicable NRC generic letters and exemption letters for >
AN0), identified in Division 4.0 to the Fire Protection Program Manual'(FPPM). g h [ QA MANUAL OPERATIONS REV. 10 DATE 8/31/88 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-2 1, Arkoneos Nuclear one FOR FIRE PROTECTION f 1
g., 4 :. , >
- 1 :
- - ~
q ' f ,' I(O d
,, < .i 1.6 .The above requirements are implemented by controlling activities as described-in this manual and appendix and by-E" procedures referenced-in this manual and appendix.=
9 J* 2.0 ORGANIZATION . 2.1 lThe organizational structure and responsibilities of key-personnel associated with the administration, implementationi m and evaluation of the fire protection program are described:in
. Section 1.0 of this manual and as:follows:
. 1. The Vice President Nuclear is the off-site management i position which has the responsibility for the development, implementation and assessment of the effectiveness of the !
fire protection program. He reports.directly to the President and Chief Executive Officer. :;
-l 3 s
- 2. - The Executive Director Nuclear Operations is the on-site j.
manager responsible for the.overall administration and , implementation of plant operations in accordance with the fire protection program. He reports directly to:the Vice President Nuclear, j
~ 3. The Manager ANO Engineering 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. He is also 4 responsible for the fire protection aspects 'of the program
-at the plant, such as evaluation of fire detection and
. suppression' equipment, fire barriers and alternate e shutdown equipment protection. He reports directly to the Executiva Director Nuclear Operations. Reporting to the ANO Arkonses Nuclear one -
SECTION: QA MANUAL OPERATIONS APPENDIX B - QUALITY PROGRAM FOR FIRE PROTECTION REV. 10 DATE 8/31/88 PAGE AB-3 4 9 -r- .-r---,
q., --
'l t a. I a
- 7.. %
ManagerANOEngineeringis-theSuperiktendentEngineering Y[, Services.- Underibis direction is the Supervisor-Fire j Prevention / Protection. The Supervisor Fire Prevention / s Y
= Protection is responsible for: l
.J (1):-Implementing. maintaining and' assess'ing the fire J
prevention aspects of the program as defined in plant-procedures (2)' Performing fire protection evaluations (3) Developing inspection and surveillance criteria ~ 1 (4) Coordinating ANI fire protection inspections at the: j l: plant
). (5) Providingguidanceandtechnicalsupporttolhe nuclear plant in the area of-fire protection -;
i m. p (6) Assuring that applicable regulatory requirements;are included in the fire protection program (7). Assuring commitments.regarding fire protection are E identified and tracked-j (8) Assuring safety evaluations (10CFR50.59) and design reviews for' fire protection modifications are performed 4 1 < (9) Assuring that evaluations / assessments of the fire "
, protection program are performed and results reported to Management
'1 j
I QA MANUAL OPERATIONS 10 AN<O REV. l DATE 8/31/88 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-4 l-Arkonsos Nuclear One FOR FIRE PROTECTION 1 t
. . . . . _ _ , . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - - - - ~ ~ ^ - - - -
C4 1:. r'
.(10) Maintenance and revision of.the Fire Protection
. Program Manual.
y.
'(11) Classification of F-list components for the
]
- f <
i component level F-list ( 4. 'The General Manager Nuclear Quality is responsible for j
+ '
assuring that the fire protection program is implemented
=l in accordance with.the QA Manual. Operations, Technical !
; Specifications and applicable procedures. This is, i accomplished by the performance of audits and other a
. provisions of'the QA Manual Operations.' He.shall assure that corrective. action, when necessary,.is taken.- He- .I a
reports directly to the Vice President Nuclear. .;
, l 5. The Manager Licensing is responsible for providing other j responsible organizations with regulatory information and' j interpretations on regulatory issues related to fire. '
protection. He is also responsible for providing. interface with the NRC on fire protection matters,' i g engineering evaluations and analysis of fire protection'. I systems, as related to regulatory commitments and control l; of license-based documents relating to fire protection.
, .He reports directly.to<the Executive Director Nuclear - !
1 Operatio'ns. " E < 4
.l 6. The General Manager Design Engineering'is' responsible for q L
- assuring that the technical. requirements specified in the j
}' l Operating License, Technical Specifications and ; other design basis documents, with respect to fire -. 7
, protection, have been satisfied in design modifications L
and design documents affecting ANO. He reports directly-j to the Vice President Nuclear.
- j I
g -l f, -! , t ANO
- Arkoneos Nucleor-one SECTION:
QA MANUAL OPERATIONS APPENDIX B - QUALITY PROGRAM FOR FIRE PROTECTION REV. DATE 8/31/88 PAGE AB-5 10 l
1 4 t l;h *
,. 3.0 . QUALITY ASSURANCE PROGRAMI 4 3.1 This: quality program is to ensure that_the fire protection. r systems for. safety-related areas-(as defined in paragraph'l.2 of this Appendix) are controlled in accordance'with applicable-l NRC regulations,. industrial standards and codes, policies, ;
i rules, procedures and licensing documents.- The quality program '!
'l is! implemented through approved procedures. 'The' effectiveness of the fire protection program is verified <
q K
-l through surveillances'and scheduled audits' conducted by the-NQ organization, under the cognizance of the'SRC. General l requirements.for.this program are also-described in subsections 2.4 through 2.7 of this manual, except'that personnel -l performing inspections need'not be certified to ANSI N45.2.6 L
'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 er in support.of the nuclear plant are to participate in appropriate. training programs to assure J
,that suitable proficiency is achieved and maintained in the I work-they are performing.-
1 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 . 0
=l safety in accordance with approved procedures. Personnel i r
assigned to the plant Fire Brigade are to receive additional
~
indoctrination and training to assure their capability to fight
~
7 fires is established and-maintained. The Supervisor Fire , Prevention / Protection has the overall responsibility for these.
.1 training programs.
7 1 1 ANO Arkonses Nuclear One' SECTION:
' QA MANUAL OPERATIONS APPENDIX B - QUALITY PROGRAM FOR FIRE PROTECTION REV. 10 DATE 8/31/88 PAGE AB-6 I
u ! . s W .
, -{
p 4.0 LDESIGN CONTROL. , 1 L 4.1 Section'3.0 of this manual is applicable for design control ! activities ~ pertaining to the fire protection system.- i
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q 5.0l PROCUREMENT-DOCUMENT CONTROL 5.1 The control of ~ procurement documents for fire protection .j related materials, parts.and components is described 17 Section 4.0 of this manual with the.exc'eption of. paragraph 4.2.3,.when ! these items.are not associated with the Q-list. T'ie procurement document is to include the requirement that items be U.L.-l listed or F.M. approved for fire protection use, where q I applicable, in accordance with approved procedures. ' 6.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS # 6.1 Inspections,' tests, administrative controls, fire drills and' , j
~ training that govern the fire protection program are prescribed- ,
by documented. instructions,, procedures and drawings:and are j accomplished in accordance with these documents. A listing and brief description of procedures relating to fire protection
- l. activities are provided-in the ANO Fire Protection; Program Manual. Instructions, procedures and drawings are prepared,- -
l reviewed, approved and revised in accordance-with approved procedures, t 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. q 9 l ANO Arkonoce Nuclear On. QA MANUAL OPERATIONS SECTION: APPENDIX B - QUALITY PROGRAM FOR FIRE PROTECTION REV. DATE 8/31/88 PAGE AB-7 10 4 i ( l 1
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. 8; 0 CONTROL'0F PURCHASED' MATERIAL. EQUIPMENT AND SERVICES w;v 1 Q 'l 4
8.li The' control'of purchased fire protection related materials, i equipment and services is described in Section 7.0'of this c manual, with the following exception related to subsections p , 7.2, 7.3 and 7.5.- For;the procurement of fire protection j related items or servkes nv associated with the Q-list, the vendor / contractor qualification criteria (including periodic j 4 reassessment of their. program) is not required. t Nonconformances.dispositioned repair or use-as-is by the-vendor are to be submitted-to and accepted by ANO only T when so designated on the procurement document. 9.0 IDENTIFICATION AND' CONTROL OF MATERIALS. PARTS AND COMPONENTS tia i
- 9.1 Section 8.0 of this manual is not' applicable for the identification and control of materials, parts and components- i related to the' fire protection system. No particular. I 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-
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procurement and materials management procedures and practices. ,
~10.0 CONTROL0F SPECIAL PROCESSES i
; 10.1 Section 9.0 of-this manual is not applicable for the control of special processes, as applicable to fire protection systems.
No particular special process controls have been identified by i BTP-APCSB 9.5-1, Rev. 2. The control of special processes for-
-the. maintenance of the fire protection system.is performed-inc ,
, accordance with applicable approved procedures and practices, a
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t 111.0 INSPECTION 11.1Inspectionactivities'applicableto'thefireprotection_' system; fare described in Section 10.0 of this manual with the exception -! l 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 th'e fire protection system. Individuals outside the NQ' organization who perform inspections only need to meet' f paragraphs 10.3.2 and 10.3.2.1.-- t
.i In addition to the provisions of this manual, inspections and .;
l L surveillancesiare addressed for in applicable portions of the # I i Fire Protection Program Manual and the Technical Specifications ! for each nuclear unit. - N . 5 12.0 TEST CONTROL- ! L t . 1
.12.1 A test program is to be established and implemented to ensure i that testing is performed and verified on applicable systems 'l
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3 and. components'to demonstrate conformance with' design and i 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. ' 4 p l-12.2 The control of. testing activities is described in'Section 11.0 1.: '- of this manual. Surveilla7ce testing requirements.are t
.s identified'in the Technical Specifications for each nuclear unit.
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ANO QA MANUAL OPERATIONS REV. Ib DATE 8/31/88 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-9 Arkoneos Nuclear On. FOR FIRE PROTECTION
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R< 13.0 CONTROL OF MEASURING AND TEST EQUIPMENT j a. g 4 13.1 Section 12.0'of this' manual is not applicable f W the control i
-of measuring and-test. equipment. Noparticularmeasurlingand.
1 test equipment controls' have b'een identified in BTP-APCSB 9.5-1, 1 Rev. 2. Measuring and test equipment is controlled in. l accordance with applicable approved procedures and practices. L 14.0 HANDLING STORAGE AND SHIPPING i { 1 14.1 Section 13.0 of this manual is not applicable for the" handling, storage and. shipping'of. fire protection-related materials and '
- equipment. . No particular requirements for this section have- !
been identified in BTP-APCSB 9.5-1, Rev. 2. Handling, storage [ and shipping activities are controlled'in-accordance with
! applicable approved procedures and practices. !
15.0 INSPECTION, TEST AND OPERATING STATUS i 1 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.
. i A ~15.2 Section 14.0 of this manual is applicable for identifying the inspection, test and operating status of the fire prot'ection 1 system.
l 16.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l 16.1 The control of nonconforming materials, parts and components I related to the fire protection system is described in-Section~ 15.0 of this manual, with the exception of subsection 15.3, U
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i I when the item is not associated with the Q-list. Vendor ,
;l 'nonconformances are to be submitted to ANO only when so '
designated on the procurement. document.
-17;0 CORRECTIVE ACTIONS .
;l 17.'1'A corrective action system is established to' ensure that conditions adverse to fire protection, such as' failures, I malfunctions, deficiencies,' deviations, defective components, a uncontrolled combustible materials and nonconformances, are !
promptly identified, reported and corrected, t 17.2 Corrective action activities are controlled as described.in i 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 QUALITY ASSURANCE RECORDS < j 18.1 Records which furnish evidence that the-criteria enumerated in' i 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 i documents and records-(including-calculations, test reports, -t code reports and design change packages). relating to fire
-l protection is; included within the ANO Fire Protection Program ; Manual.
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- 19.0 AUDITS j 19.1 Audits:are to be conducted and documented to verify compliance) !
with.the fire protection program, including design and.
~ procurement documentspinstructions, procedures'and' drawings and inspection and test activities.: Section 1;B.0 of this manual is applicable for the control of' audits related to the
. fire protection program.-
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- l 19.2 As a minimum, audits of the fire protection program are to be l
, , scheduled at specified frequencies in accordance with the- '
Technical Specifications applicable to each' nuclear unit.
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