ML20247E140
| ML20247E140 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/22/1989 |
| From: | Tison Campbell, Humphrey L ARKANSAS POWER & LIGHT CO. |
| To: | |
| References | |
| NQ-89-00942, NQ-89-942, NUDOCS 8907260094 | |
| Download: ML20247E140 (155) | |
Text
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t A Arkensas Power & Ught CompIny 4?S West Capet O P O Box 551
( .
Lee RocA AR 7P203 Tol 501377 4000 July 21, 1989 CDPY 010 DOCUMENT CONTROL DESK US NRC - nAll. STATION P1-137 WrSHINGTON, DC 20555
SUBJECT:
Arkansas Nuclear One Quality Assurance Manual Operation Revision 11 Please update your copy of the sub.fect manual and indicate receipt of this document by signing below and returning this memo to Sally Benson, Licensing Section. Attached is
. Revision'11 to the Arkansas Nuclear One, Qua.Lity Assurance Manual Operation.
Your prompt action is requested.
r tru' y yours, lt 17-1f. James Lice sing Supervisor Attachment j Arkansas Power & Light Co.
ATTN: Sally Benson, Licensing Section Post Office Box 551 Little Rock, AR 72203
.I have received and incorporated this copy of Arkansas Nuclear One, Quality Assurance Manual Operation, Revision 11.
Signed Date Copy Number .
@f 8907260094 890721 -
Id
{DR ADOCK 05000313 PDC l
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- q. ...
R,eplace the following- sections, figures or tables in their entirety with the j ~ Revision 11. sections, figures,- or tables:
SECTION' SUBJECT Approval Cover Sheet Record of Revisions Table of Contents Policy Statement Introduction 1.0 Organization
- 2. 0 Quality Assurance Program 3.0 Design Control 5.0 Instructions, Procedures and Drawings 6.0 Document Control 9.0 Control of Special Processes 10.0- Inspection 12.0 Contro1~of Measuring and Test Equipment 13.0 Handling, Storage and Shipping
.14.0 Inspection, Test and Operating Status-15.0 Non-Conforming Material, Parts or Components 16.0 Corrective Action 17.0- Quality Assurance Records 18.0 Audits Figure 1 Nuclear and Related Corporate Organizations Figure'2 Nuclear Operations Department Figure 3 Unit 1 & 2 Operations Organizations Figure 4 Nuclear Quality Department /
Figure 5 Engineering Department Figure 6 Technical Support and Assessment Department Figure 7 Nuclear Support Department Table 2 Quality Assurance Procedures Table 3 Quality Program Policies, Procedures and
}-
Instruction Manual List Appendix A Quality Program for Transport Packages Appendix B Quality Program for Fire Protection
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'l#1 ATTACHMENT TO QUALITY ASSURANCE MANUAL OPERATIONS, REVISION 11 FACILITY OPERATING LICENSE NOS. DPR-51 AND NPF-6 DOCKET N05. 50-313 AND 50-368 This attachment lists replacement sections for the subject Quality Assurance =
Manual' Operations which will remain in effect for subsequent versions and modifications, unless specifically altered.
A change is indicated by a bar in the left margin, placed next to the affected area.- The revision number is indicated at the bottom of the affected page in the.right-hand. side box.
i i
__.5-___-__m.____. _
FORM AR731291
, REV,31-70 C')
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ARKANSASINTRA POWER & LIGHT COMPANY COMPANY CORRESPONDENCE Arkansas Nuclear One July 19,1989 NQ-89-00942 MEMORANDUM TO: Holders of QA Manual Operations FROM: Larry W. Humphrey
SUBJECT:
Changes to Quality Assurance Manual Operations, Revision 11 An evaluation has been conducted by Nuclear Qvality.to determine the applicability of 10CFR50.59 in regard to the .-hanges identified as Revision 11 to the Quality Ascurance Manual Operatieis tQAMO). The requested changes do
/~'N not involve a char,qe to facilities or procedures described in the SAR, to tests /
V experiments not detcribed in the SAR ar that effects compliance with Technical Specifications. Although the QAMO is not classified as a procedure, it is 7
described in the SAh, and therefore, any changes are subject to 10CFR50.59 for a determination of unreviewed safety questions.
The results.of the unreviewed safety question determination are documented on Attachment 1 to this memo. The basis or justification for this determination d has previously been addressed and documented on memo NQ-89-00937 (Attachment 2}, which identifies the various sections / paragraphs of the QAM0 in which requested changes have been incorporated.
Based on this 10CFR50.59 evaluation, Nuclear Quality has determined that these changes do not constitute an unreviewed safety questi)on nor do they reduce our current quality program commitments. /
HTG DAG:s'kg , #
Attachments ,
cc: C. H. Turk
- 5. K. Hendrix (SRC Secretary)
L. W. Humphrey/NQ File ]
L. W. Wagner ANO-DCC (m l
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. I
A rrM His1E*N T * /
NQ Procedure No. CANANUAl-0MRAT/0^/.SRev. No. //
,y
. ,V STEP 1 DETERMINATION:
Will the proposed procedure change:
1.1 Require a change to the Technical Specifications: *Yes No /
1.2 Result in the information in the Licensing Basis Document *Yes / No (LBD) (including drawings and descriptions of facilities, systems, components, structures, and procedures) being no longer true or accurate or violate a requirement stated in the LBD?
Document portions of the Technical Specifications and LBD reviewed below. If the answer to question 1.1 is "Yes," NRC approval is required before the procedure change is implemented. If the answer to question 1.2 is "Yes," then a 10CFR50.59 Evaluation is required and Step 2 must be completed. If the answer to questions 1.1 and 1.2 is "No," then the requirements of 10CFR50.59 do not apply and an evaluation (Step 2) is not required. A written response providing a basis for the answer to each question in Step 1 must be provided below.
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References:
List LBDs and Technical Specification sections reviewed.
Document No. Applicable and/or Title Section to Questions (s)
(Jpir / f3 Nch 3PEc.S. 4./~f.2, d./O /. /, /. A
(),v/ r / SAR /. (> /, 2.
WNt 7.2 .5 AN' /7 /. 2 l
- When any block is checked "Yes" the change requires PSC approval prior to l implementation. )
I i
^
( " NUCLEAR QUALITY FORM
\ PAGE 1 0F.1 10CFR50.59 REVIEW NQA-3/5. REV. 0
-- - a
NQ Procedure No.t9A/t M;JuAb-[]pf,Ei4*77pg5 Rev. No. //
STEP 2 EVALUATION:
f] If the answer to any question in Step 2 is "Yes,* then an "unreviewed safety
(/ question" may be involved. If the answer to all questions is "No," then the proposed thange does not involve an "unreviewed safety question". A written response providing the basis for the answer of each question must be provided.
Attach additional pages as necessary. A simple statement of conclusion is not sufficient.
2.1 May the probability of an accident previously Yes No /
evajuatedintheLBDbeincreased?
~7% e.)Ea-cis fx.A CAMO le/dnelinna A/D-D ? -De937 x x 3JLu % 7AL nt% /M '/
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2.2 May the consequences of an accident previously Yes No V evaluated in the LBD be increased?
'7% ce><suwaexa / ae erccic/ndm&A wb8liw YS/f/?
w r/ /al/>e7/WAv74 cAa.~c1$%XAL '
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- 2. 3 May the probability of a malfunction of equipment Nog Yes important to safety be increasej?
bl m<wA /O-87-00937. ~tb C-.MM md5 $Y OAMO Av }l%~
c/1P&a! W mr1'Ae4 a x& &M #~< adub /Mersn cen< m<%sf M/Ak -ck Aa7~c/ % a A L es aLtMdJ.
2.4 May truf consequences of a malfunction of equipment Yes Nog important to safet TA 9 A d d A $ y b. incre c s d?df J 2<-uhu$ca c/nesi/edsw-D$
CA'Ws0 A<w d :r/A.ex ex./4/7W ~5 n . ^auff frAw & a f f --ed. cwr0. CAo.x a as cAdd o/A- sn<an A/6 - a ? - 00 '737
V 2.5 May the possibility of an accident of a different' type Yes No 7 than any previously evaluated in the LBD be created?
W 9?NO e;4<s mdf'acAh/4/]dpA zb A%rbiWM /n auia&& xfM me rum %L / c~c cieAsc=* ud/b UscJ~/a1
<- m M A d a e Ac. -ca f 'dats CA'M6 n/1.cf/Mie. maaur AJO-89 ~00 9 37 2.6 May ths possibility of a malfunction of equipment Yes Nog important to safety of a different type than any previouslyevaluatedintheLBDbecreateJ?
~7E? OYMae/w fe<Av$1a A max cH2h Mai/Alib </a sal /wc~'Sh A n.Ao m . f D ,i" b :Wf Aher thada mf--Aw<> nd 'dweJAfn72M UWA< c.aatiW/c~b e. AMAd%K+ /cLM T& Waft)flehdWNQ 29-9075/}
2.7 Will the margin of safety'as defined in'the ba' sis for' Ybs Nog the Technical S jf j
~7%f f/4//J6SJ/ specification be reduced?2HeA}DJcJ.,a6??zA! 04MO h meOal$&'
eAa // EffA Welw Q~::'exA2'TL, <Ah-vnNo<na4cJ%A.Th ew<ireb76.Je Am a A<w-<l/xbk do%.J%'WD(/P*A m om/& i
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Prephred By: E~b g <~fjaM a.r4 'W&wJ c -
Date 7[9/8,9
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Preparer's Certification Expires
- PSC Approval Date l
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NUCLEAR QUALITY FORM PAGE20FA f
. ... L 10CFR50.59 REVIEW NQA-3/5. REV. O
y ,
1 FORM AR781291 NEV, AII/O O ~"=
. ARKANSASINTRA POWER & LIGHT COMPANY COMPANY CORRESPONDENT,E Arkansas Nuclear One July 19, 1989 1
NQ-89-00937 MEMORANDUM TO: L. W. Hum;e rey FROM: H. T. Greene W*
SUBJECT:
Quality Assurance Manual Operations, Rev. 11 Since the issuance of revision 10 to the Quality Assurtince Manual Operations (QAM0), changes have been requested in order to clarify existing wording, to reflect the current organizational structure, and to reflect current practices.
( Per the requirement of 10CFR50.54(a), Nuclear Quality has evaluated these Q] requested changes to determine if they represent a degradation of the QA Program.
The results of our investigation are documented as follows:
- 1) Organizational changes: The QAM0 required changes in numerous sections to reflect the new organization..al structure which has been accepted by the NRC througt. recently submitted Tech Spec changes. The primary change involved j the Operations Department which created Plant Managers for each unit and a '
Plant Manager for central operations. Other changes involved re-assignment of responsibilities to other department heads and title changes to existing i positions. Also, the various engineering groups involved with the plant ;
modification process have now been placed under one department head who reports to the VP, Nuclear. ' Nuclear Quality has determined that these changer. do not ceuse a degradation of the quality program commitments.
- 2) Section 2.0, wragraph 2.6.6: This paragraph was revised to agree with the current wording of the Unit 1 and 2 Tech Specs pertaining to the membership of the PSC. Nuclear Quality has determined that these changes do not cause a degradation of the quality program commitments.
- 3) Section 5.0, Paragraph 5.3.2: This paragraph required changes to reflect alterations to the review / approval process for Little Rock nuclear procedures. As a result of the consolidation of the various engineering / support groups in LRGO and AND, t.hese LRGO procedures shall be reviewed / approved ir accordance with approved plant administrative
,.. procedures. Table J to the QAMO has been rev. sed to identify the approval 1 '
'( ) requirements for departmental procedures. Nuclear Quality has determined
\/ that these changes do not cause a degradation of the quality program commitments.
I
L.'W. Humphrey:
- LJuly 1E, 1989-NQ-89-00937 Page'2-7 IfV l4) Section 5.0, Paragraph 5.4.2:_ This paragraph required cnanges to' reflect the Q
current. requirements of both the Unit 1 and Unit 2 Tech Specs for_the processing of ' temporary changes. Nuclear Quality has determined that'these changes'do not cause a degradation of the' quality program commitments.
5)~ Section 6.0, Paragraph _6.2.4:
This paragraph has beer. deleted-in revision 11 of QAMO. The responsibility for; the control._ and issuance of Little Rock nuclear procedures has been_ reassigned to the Manager, Administrative Services in accordance with approved plant _ administrative procedures..-
g Nuclear Quality has determined that this change does not cause a degradation of the quality program commitments.
- 6) LSection 10.0, Paragraph 10.'.1: 4 This paragraph required a change to add
. guidance for the waiver of inspection holdpoints by'the Superintendent, Quality Control / Quality Engineering. Nuclear Quality has determined that this change does not cause.a degradation of the quality program commitments.
I'
- 7) Section 16.0, Paragraphs 16.5.1 through 16.5.3: These paragraphs' required changes in order to' simplify the process for documenting reportable events and transmitting them to the NRC. Nuclear Quality has determined that these-changes do not cause a degradation of the quality program commitments.
- 8) Figures F-1 through F-7: These figures were revised to reflect the current organization in support of ANO Units 1 and 2. These organization charts support:the contents contained in Section 1.0 of the'QAMO. Nuclear Quality has determined that these changes do not cause a degradation of the quality program commitment.
. L
- 9) Table 2: 'This table required changes in order to identify new procedures which have superceded the currently listed procedures. These newer procedures are an output from.the plant' modification process program and reorganizations within the Nuclear Organization. Nuclear Quality has determined that these changes do not cause a degradation of.the quality program commitments.
- 10) Table 3: This table required changes as a result of the changes made to Sections 5.0 end 6.0 relating to the review, approval and control of LR procedures in support of the quality program. The section on Little Rock E procedures has been deleted and incorporated into the section entitled Departmental Procedures. Note: ANO procedure 1000.06 is being revised to reflect that the applicable LR procedures are to be controlled per LRNP-100 until-the transition.to the ANO system is complete' Nuclear Quality has determined that these changes do not cause a degradation of the quality program commitments.
1
y;e m M W.1 Humphreyj
, TJuly119,-1989 ,
-NQ-89-00937. Page_3- ,
s
[V
- \ j sin' regard to those sections /pages not specifically addressed above, the requested.
' changes'were in-the form of title. changes.or errata. These' changes do not cause"
~
1 -' =a' degradation of the quality program commitments. Since'none of~these_ requested 1 changes reduce ~our' quality commitments, they were incorporated into the; annual m ; update to the manual.
HTG:DAG:skg
'cc: : T. G. Campbell' C..H.< Turk'
- J.- Li Taylor-Brown /NQ File L. W. Wagner-D.-A.. Graham ANO-DCC.
a 1
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ARKANSAS NUCLEAR ONE QUALITY ASSURANCE MANUAL OPERATIONS REVISION 11 i
APPROVED: ~
Er -
DATE: Z 9 '
9 l
/ '/
SUPERINTENDENT ( QUAll1Y ASSURANCE
)
APPROVED: amt )'h'. '
/nt/v/l L4'/_ DATE: 7#r>/J'7
/
~~~IiENERALyNAGER'NUCLEARQUfITY APPROVED: J DATE: f/#///Y VICE PRESIDENT N})CtEAR //
QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: APPROVAL SIGNATURES Arkansas Nuclear One
I RECORD OF REVISIONS REVISION 1
.h- NUMBER- DESCRIPTION DATE ij 0 Initial' Issue 6/11/74 1 Responso to AEC questions submitted 12/13/74 11/21/74. Revisions to Section 2, 4, and 7 as indicated.
2 Response to NRC questions submitted 3/4/75 2/7/75. Procedure numbers 1005.xx changes to 1004.xx (number change only).
3 General revision to change AEC to NRC, 9/8/76 update organization, reflect NSP revisions, minor program implementation changes.
4 Eliminate-Quality Assurance Committee 9/8/77 changes to Procurement Control -
Qualification of Vendors. Organizational changes._ Incorporate Technical Specification changes.
5 Incorporate organizational changes 10/10/80 and responses to subsequent NRC questions. Incorporate Regulatory
(~h Guides and retype document in its
() entirety in standardized format.
6 Incorporate organizational changes, 5/30/84 delete procedural references throughout manual, and accurately reflect current regulatory commitments and QA. practices related to the 'l safe operation of AP&L nuclear plants. { '
Manual has been reformatted and retyped in its entirety.
7 Changes given below are identified 5/31/85 ,
on the pages by a bar in the left margin, placed next to the affected ares.
Corrected by errata (includes misspelled words) on the following pages:
A-1 2-5 10-6 T1-9 A-2 3-2 11-5 T1-13 1-10 3-3 13-2 T3-1
,r w QA MANUAL OPERATIONS REV. 11 SECTION: RECORD OF REVISIONS :R Arkansos Nuclear One l
l
RECORD OF REVISIONS j REVISION
(~N NUMBER DESCRIPTION DATE d 7 (Cont.) 1-12 3-4 13-4 T3-2 1-18 4-2 15-2 T3-3 1-19 5-2 15-3 1-20 5-3 15-5 1-22 5-4 15-4 1-23 6-2 16-1 7-2 T1-6 9-1 Page C-7: revised definition Page C-8: revised definition Page 1-9: revised paragraph 1.4.2(1)
Page 1-10: revised paragraph 1.4.2.1 Page 1-11:added paragraph 1.4.2.1.1
- paragraph 1.4.2.2 redesignated 1.4.2.1.2
- added paragraph 1.4.2.1.3
- paragraph 1.4.2.3 redesignated 1.4.2.2 and revised Page 1-12: paragraph 1.4.2 3.1 redesig-nated 1.4.2.2.1 Page 1-13:added 7) to paragraph 1.5.1.3 Page 1-14 & 15: revised paragraph 1.5.3 to delete Planning / Scheduling Supervisor Page 1-21:added paragraph 1.5.8
(] Pays 1-1 to 1-23: paragraph locations l
'u changed '
Page 2-2: paragraph 2.2.2 redesignated 2.2.3 and revised Page 2-2: paragraph 2.2.3 redesignated 2 2.4 Page 2-2: paragraph 2.2.4 redesignated-2.2.5 Page 2-2: new paragraph 2.2.2 added Page 2-3: revised paragraph 2.2.5(2)
Page 2-7 and 2-8: revised paragraph 2.6.4 Pages 2-3 to 2-9: paragraph locations changes Page 7-3: revised paragraphs 7.2.3 and 7.2.4 Pages 7-3 to 7-7: paragraph locations changes Page 15-1: revised paragraph 15.2.1 Page 18-3: revised paragraph 18.3.2 Pages 18-3 to 18-6: paragraph locations changes Page F-1: revised Figure 1 A QA MANUAL OPERATIONS REV,: 11 i () SECTION: RECORD OF REVISIONS DATE: 07/22/89 PAGE: RR-2 i Arkansas Nuclecr One L___-__-_____-___
RECORD OF REVISIONS REVISION l NUMBER DESCRIPTION DATE l
0 7 (Cont'.) Page F-2: revised Figure 2-Page F-3: revised Figure 3 Page F-5: revised Figure 5 Page F-6: ret 1 sed Figure 6 Page T2-1: revised titles Page AA-1 to AA-3: new Appendix A added Page AB-1 to AB-8: new Appendix B added 8 Changer, given below are identified 6/10/86 on tha pages by a bar in the left marc .ro placed next to the affected
~
aN:
Cor?.d ed by errata (including misspelled words) on the following pages:
A-1 5-1 16-1 17-5 5
B-1 6-1 16-3 AB-2 2-1 7-5 17-1 AB-4 2-6 11-5 17-2 AB-10 3-5 15-1 17-4 AB-11 4-1 e Page A-1 : Revised 2nd, 3rd, and 4th ,
/q paragraphs ;
y/ Page A-2: : Revised 1st paragraph
- Changed signature Page B-5 :Added ANSI N3.1
- Added paragraph at end of section Page C-7 : Revised definition Page C-9 Revised definition Pages 1-1 : Rewritten to reflect to-1-23 new organization Page 2-1 : Revised paragraph 2.2.1
- Added paragraph 2.2.2 l Page 2-2 : Paragraphs 2.2.3 and 2.2.4 were 2.2.2 and 2.2.3
- Revised paragraphs 2.2.3 and 2.2.4 Page 2-3 : Title changes, paragraph 2.2.5 l 4
- Paragraph 2.2.5 was 2.2.4
- Old Paragraph 2.2.5 incorporated ,
into Paragraph 2.2.2 l
- Paragraph 2.3.1, title change l
QA MANUAL OPERATIONS REV.: 11
/cs\ DATE: 07/22/89 U SECTION: RECORD OF REVISIONS PAGE: RR-3 f Arkansas Nuclear One i,
RECORD OF REVISIONS REVISION NUMBER DESCRIPTION DATE O 8 (Cont.) Page 2-4 : Title changes, paragraphs 2.3.3 and 2.3.4
- Revised paragraph 2.4.1 Page 2-5 : Title changes, paragraphs 2.4.3, 2.5.1, 2.5.2 Page 2-6 : Revised paragraph 2.5.2 and 2.6.1
- Title change, paragraph 2.5.3 Page 2-8 :New paragraph 2.6.6 added
- Para. graph 2.6.7 was 2.6.6
- Revised paragraph 2.6.7 & 2.7.1 Page 2-9 : Title change, paragraph 2.7.2 Page 3-1 : Revised paragraph 3.2.1 Page 3-2 : Title changes, paragraph 3.4.1 Page 3-4 : Revised paragraphs 3.5.1 & 3.5.3 Page 3-5 : Title change, paragraph 3.5.4 Page 4-1 : Title change, paragraph 4.2.1 Page 4-2 : Revised paragraph 4.3 Page 4-3 : Revised paragraph 4.4 Page 5-2 : Revised paragraph 5.3.1
- Title changes, paragraph 5.2.2 and 5.3.2 Page 5-4 : Revised paragraph 5.4.2 Page 6-1 : Revised paragraphs 6.1 & 6.2.2 Page 6-2 : Title change, paragraph 6.2.3
- Added paragraph 6.2.4 O Page 7-1 : Title changes, paragraphs 7.2.1
& 7.2.2 Page 7-3 : Revised paragraph 7.2.3
- Title change, paragraph 7.3.1 Page 7-4 :litle changes, paragraphs 7.3.2
& 7.3.3 Page 7-5 : Revised paragraph 7.4.3 Page 10-4 : Title changes, paragraphs 10.3.2.3
& 10.4.1 Page 10-5 : Revised paragraph 10.4.2 Page 10-6 : Revised paragraph 10.5.3 Page 12-1 : Added paragraphs 12.1.2 & 12.1.3 Page 12-2 : Title change, paragraph 12.2.4
- Revised paragraph 12.3.1 Page 13-2 : Title changes, paragraph 13.3.2 Page 13-3 :Titla change, paragraph 13.5.3 Page 13-4 : Title change, paragraph 13.5.5 Page 15-1 : Revised paragraphs 15.1, 15.2.1
& 15.2.2 QA MANUAL OPERATIONS REV.: 11 DATE: 07/22/89 SECTION: RECORD OF RFVISIONS PAGE: RR-4 Arkans 2s Nuclear One
t 6
RECORD OF REVISIONS l REVISION-r~'s; NUMBER DESCRIPTION DATE t
~~'
8 (Cont.) Page 15-2 : Revised paragraphs 15.2.3 & 15.2.4 l Page 15-3 : Added paragraph 15.2.6
- Paragraph 15.2.7 was 15.2.6
- Moved old subsection 15.3 to Section 16
- Subsection 15.3 was 15.4
- Revised paragraph 15.3.1 & 15.3.2 Page 15-4 : Subsection 15.4 was 15.5
- Subsection 15.5 was 15.5.2 with revisions Page 16-1 : Revised paragraph 16.2.1
& 16.2.2 Page 16-2 : Deleted paragraphs 16.2.4
& 16.2.4.1
- Paragraphs 16.2.4 & 16.2.5 were 16.2.4.2 and 16.2.4.3
- Revised paragraphs 16.2.3, 16.2.4 & 16.2.5
- Subsection 16.3 was 16.2.5 with revisions Page 16-3 : Subsection 16.4 was 16.3
- Revised paragraph 16.4(1) & (3)
- Subsection 16.5 was 16.3.2 and and subsection 15.3
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\~ '
Page 16-4 : Subsection 16.6 was 16.4 Psoe 17-4 : Title change, paragraph 17.3.4
- Revised paragraph 17.4.1.2 Page 18-1 : Title change, paragraph 18.2.1 Page 18-2 : Title change, paragraph 18.2,.2
- Revised paragraph 18.3.1 Page 18-4 : Title change, paragraph 18.4.1 Page 18-5 : Revised paragraphs 18.4.4, 18.4.5 & 18.5
) Page 18-6 : Revised paragraph 18.6 Page F1 : Revised organization charts Thru F-8 Page T1-1 : Revised first paragraph, third j column Page T1-2 : Add ANSI N18.7 (Sections 5.2.7.1)
Page T1-3 : Add ANSI N18.7 (Section 5.2.17)
Page T2-1 : Revised Table 2 Page T3-1 : Revised all paragraphs Page T3-2 : Revised all paragraphs Page T3-3 : Deleted I
l 1
l r QA MANUAL OPERATIONS REV.: 11 l
(,), DATE: 07/22/89 i SECTION: RECORD'0F REVISIONS PAGE: RR-5 Arkonpos Nuclear One
RECORD OF REVISIONS e REVISION h 7x NUMBER DESCRIPTION DATE l ).
'/~
8 (Cont.) Page AA-1 : Revised paragraph 1.1 Page AA-2 : Revised introductory paragraph Page AA-3 : Revised Section 12 Page AA-4 :Added Page AB-3 : Title change, paragraph 2.1(1)
- Revised paragraph 2.1(2)-
Page 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 left margin, placed next to the affected area.
Corrected by errata (including misspelled words) on the following pages:
B-5 C-10 10-5 C-1 1-4 AA-2 C-2 5-4 AA-3 A C-6 7-5
! Page A-1: Title change in 2nd paragraph Page A-2: Resigned Policy Page B-5: Clarify ANO Unit 2 Code Commitments Page C-1: Added definition Page C-3: Revised definition and added new definition Page C-5: Added definition Page C-7: Eevised definition Page C-8: Revised definition Pege 1-1 thru l-3: Rewritten to reflect current organization i Page 1-9: Revised responsibilities Page 1-10: Changed name title Page 1-13: Revised responsibilities in paragraph 1.4.1.3.2.
Changed name title f
QA MANUAL OPERATIONS REV.: 11
/O DATE: 07/22/89 C# SECTION: RECORD OF REVISIONS PAGE: RR-6 Arkansos Nuclear One
_.._-.m_________ .--_s___
RECORD OF REVISIONS REVISION m NUMBER DESCRIPTION- DATE :
'~)' ' 9 (Cont.) Page 1-14: Revised responsibilities within paragraphs 1.4.1.3.2.1 and 1.4.1.3.2.3 Page 1-15: Changed name title !
Pagres 1-15 thru l-16: Revised responsibilities in paragraphs 1.4.1.3.2.3.3 and 1.4.1.3.2.4 Page 1-17: Added paragraph 1.4.1.3.2.5.
Changed name title Page 1-18: Delete 1.4.1.3.3.e and cisanged name title Page 1-19: Clarified paragraph Page 1-20: Revised responsibilities Page 1-21: Revised responsibilities in !
paragraph 1.4.2.2 j Pages 1-21 i thru l-23: Paragraph 1.5 deleted and i-paragraphs 1.6, 1.6.1, 1.6.2, 1.6.3, and 1.7 renumbered accordingly Page 1-22: Changed name title Page 2-1: Revised paragraph 2.2.1 Page 2-3: Revised paragraph 2.2.5 and (7 Addeo paragraph 2.2.6 s _/ Page 2-4: Change.d name title ';
Page 2-9: Revised paragraph 2.6.6.
Page 3-1: Revised paragraph 3.2.1 Page 3-4: Revised paragraphs 3.4.4, 3.5.1, and 3.5.2 Page 3-5: Changed name title Page 4-1: Changed titles Page 4-3: Revised paragraph 4.4 Page 5-2: Changed name title '
Page 5-3: . Changed organization titles Page 5-4: Changed name title Page 6-2: Revised paragraph 6.2.4 Page 7-2: Revised paragraphs 7.2.2(1) and 7.2.2(5). Deleted )
paragraph 7.2.2(6)
Page 7-S: 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 l Page 13-2: Revised paragraph 13.3.2 QA MANUAL OPERATIONS REV. 11 (q) DATE: 07/22/89 SECTION: RECORD OF REVISIONS PAGE: RR-7 Arkansos Nuclear One
n ;
4
)
)
RECORD OF REVISIONS
]
REVISION
,q
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\d 9 (Cont.) Page 13-4: Revised paragraph 13.5.3 Page 15-2: Changed name title l Page 16.1: Revised paragraph 16.2.2 J Page 16.2: Deleted paragraph 16.2.3 and j renumbered 16.2.4 and 16.2.5. j accordingly. Ravised new l paragraph 16.2.3 4 Page 16-3: Revised paragraph 16.5.2 Page 16-4: Changed name title Page 18-6: Title changes Pages F-1 thru F-7: Revised organization charts Page F-8: Deleted page Page T2-1: Revised Table 2 Page T3-1: Revised section 2 to Table 3 Page T3-2: Changed name title in section 4. ,
Revised section 5 to Table 3 i Page AB-3: Moved from page AB-4 Page AB-4: Changed name title in i paragraph 2.1.3 and i Revised paragraph 2.1.4 Page AB-5: Deleted paragraph 2.1.8 The following pages were revised due to r3 format changes:
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C-4 1-11 2-6 AB-8 1-5 1-12 2-7 AB-9 1-6 1-23 2-8 AB-10 1-7 2-2 AB-6 AB-11 1-8' 2-5 AB-7 AB-12 1
10 Retype manual in its entirety on new pages; 8/31/88 also made grammatical corrections (including misspelled words and punctuation throughout).
Changes given below are identified on the pages by a bar in the left margin, placed next to the affected area.
"AP&L" or " Plant" was deleted or replaced with "ANO" in the following sections:
Pege A-1: Paragraphs 1, 2 & 3 Paje 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.: 11 ;
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- i 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 Page 4-1: Section 4.2 1 Page 4-2: Section 4.2.3 Page 5-1: Section 5.1.1 Page 5-3: Sections 5.3.2, 5.3.3 & 5.4.1 Page 7-3: Sections 7.2.3 & 7.2.4 !
Page 7-4: Sections 7.3.3 & 7.4.1 Page 7-5: Sections 7.4.2 & 7.4.3 Page 7-6: Section-7.5.1 Page 12-3: Section 12.3.3 Page 13-2: Section 13.3.2 Page 15-3: Sections 15.3.1 & 15.3.2 Page 17-1: Section 17.2.1 Page 17-2: Section 17.2.2 Page 17-4: Sections 17.3.4 & 17.4.1 Page 18-2: Section 18.3.2 Page 18-5: Section 18.4.4 Page 18-6: Section 18.6 Page T1-1: Heading & General Page T1-?: ANSI N18.7 Page TI-9. R.G. 1.58
/m Page T3-3: #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 "ANO", " Plant", "LRG0" and " Departmental" was deleted or replaced with " Approved" in the following sections:
Page 2-3: Sections 2.2.4 & 2.2.6 Page 2-4: Section 2.3.2 Page 2-5: Section 2.3.3 Page 2-7: Section 2.5.2 Page 2-8: Section 2.6.3 Page 2-10: Section 2.6.7 Page 3-1: Section 3.2.1 Page 3-2: Section 3.3 QA MANUAL OPERATIONS REV.: 11 f] DATE: 07/22/89 U SECTION: RECORD OF REVISIONS PAGE: RR-9 Arkoneos Nuclear One
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10 (Cont.) Page 3-4: Sections 3.4.4, 3.5.1 & 3.5.2 Page 4-1: Section 4.1 Page 4-2: Section 4.3 Page 5-3: Section 5.3.3 ;
Page 6-1: Section 6.2.2 i Page 7-3: Sections 7.2.3 & 7.2.4 j Page 7-5: Sections 7.4.3 & 7.4.4 Page 7-6: Section 7.4.6 l; Page 7-7: Sections 7.5.2 & 7.7 i Page 8-1: Sections 8.1.1 & 8.1.2 l Page 8-2: Sections 8.2.2 & 8.2.3.1 Page 8-3: St-ti an 8.4.1 !
Page 9-1: S ans 9.1 & 9.2.2 Page 9-2: Secu .a 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 1 Page 12-3: Sections 12.3.4 & 12.3.5 Page 12-4: Sections 12.4.2 & 12.4.3 Page 13-2: Section 13.3.2 ,
Page 13-3: Sections 13.4.2 & 13.4.4 l Page 13-4: Sections 13.5.3 & 13.6.1 !
Page 14-1: Section 14.1.1 Page 14-2: Section 14.2.2 f^ 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 j 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.: l'_
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10 (Cont..) Changed " quality program" and " Quality Assurance Program" to "the QA Program" in the following sections:
Page A-1: Paragraphs 1, 2, 3 & 4 Page A-2: Paragraphs 2 & 3 Page B-1: Paragraphs 2, 3 & 4 Page B-3: Paragraph 1 Page B-5: Paragraphs 2 & 9 Page 2-1: Sections 2.1 & 2.2 Page 2-5: Section 2.4.1 Page 2-6: Section 2.4.3 Page 2-7: Sections 2.5.3 & 2.6.1 Page 2-8: Section 2.6.2 !
Page 2-9: Sections 2.6.5 & 2.7.1 Page 2-10: Section 2.7.2 Page 3-5: Section 3.6 Page 5-2: Section 5.3.2 Page 5-3: Section 5.3.2 Page 9-1: Section 9.2.2 Page 18-1: Sections 18.1.2 & 18.2,1 Page 18-4: Section 18.4.2 Page T1-1: Heading Page T3-2: #4 & #5 m
() Other specific changes as follows:
Page A-1: 1st Paragraph, Revised 1st sentence Pap A-1: 2nd Paragraph, Revised titles Pa9.' A-2: 1st Paragraph, Revised responsibility Page B-1: 1st Paragraph, Revised l 1st sentence Page B-5: ASME Section III, Updated code edition Page B-5: ASNT SNT-TC-1A-1980, Added Sentence Page B-5: Revised "*" Sentence Page C-4: Added "F-List" Definition Page C-7: Modified Definition Page C-8; Added "S-List" Definition Page C"9: Modified Definition Page C-10: Modified Definition ..
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'"' Page 1-1 10 (Cont.)
to 1-23: Rewritten to reflect current organization.
Page 2-1: Section 2.2, Revised responsibilities in last sentence Page 2-2: Section 2.2.3, Added " quality" Page 2-3: Section 2.2.5, Revised I responsibilities, 1st, 2nd
& last sentence Page 2-3: Section 2.2.6, Revised responsibilities, 2nd sentence Page 2-3: Added Section 2.2.7 Pace ?-4: Added Section 2.2.8 Page 2-4: Section 2.3.1, Changed title Page 2-5: Section 2.3.4, Revised section Page 2-7: Section 2.5.2, Revised first section Page 2-10: Section 2.7.2, Deleted " audit" Page 3-1: Section 3.2.1, Changed title and deleted " required" Page 3-2: Section 3.3, Revised 1st sentence Page 3-2: Section 3.4.1, Revised 1st sentence
-p Page 3-3: Section 3.4.2, Revised C/ Page 3-4:
responsibilities 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",
i revised responsibilities and revised last sentence Page 5-3: Section 5.3.3, Revised 1st sentence Page 5-4: Section 5.4.2, Revised responsibilities QA MANUAL OPERATIONS REV : 11
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19 (Cont.) Page 6-1: 6.2.2 Revised title Page 6-2: 6.2.3 Revised title Page 6-2: Section 6.2.4, Revised section Page 6-3: Section 6.7, Revised 1st sentence Page 7-2: .(1), Revised responsibilities Page 7-3: Section 7.2.3, Revised last sentence l Page 7-4: Section 7.3.2, Deleted
" Quality Control" Page 7-4: Section 7.4.1, Revised last sentence Page 7-5: Sections 7.4.2 & 7.4.3, Revised responsibilities Page 8-3. Section 8.3, Revised section Page 9-3: Section 9.5, Added " review" &
title change Page 10-4: Section 10.3.2.3, Revised section and title change Page 10-4: Section 10.4.1, Title change Page 10-4: Section 10.4.1, Revised section Page 11-5: Section 11.3.7, Revised section Page 12-2: Section 12.2.3, Revised 1st sentence Page 13-4: Section 13.5.5, Title change N Page 14-1: Section 14.2.1, Title change (b 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 L Page 15-2: Section 15.2.3, Revised 1st sentence Page 15-2: Section 15.2.4, Revised 2nd sentence Page 15-3: Section 15.3.2, Revised responsibilities !
Page 15-4: Section 15.5, Revised responsibilities Page 16-1: Section 16.1, Revised 1st sentence Page 16-1: Section 16.2.2, Deleted "and evaluate their safety significance" & revised 3rd sentence Page 16-2: Section 16.3, Revised responsibilities Page 16-3: Section 16.5, Revised heading Page 16-3: Section 16.5.1, Revised heading m QA MANUAL OPERATIONS REV.: 11
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10 (Cont.) Page 16-3: Section 16.5.2, Revised responsibilities Page 16-4: Section 16.5.4, Revised section Page 17-1: Section 17.1.1, Added " operation" 1st sentence Page 17-1: Section 17.1.2, Added
" maintenance" and " personnel exper'ience" Page 17-1: Section 17.1.2, Revised last sentence Page 17-2: Section 17.2.2, Revised responsibility Page 17-3: Section 17.3.1.2, Revised section Page 17-4: Section 17.3.4, Revised responsibilities Page 17-4. Section 17.4.1, Revised section Page 17-4: Section 17.4.2, Revised section il 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 Page 18-5: Section 18.5, Revised rm responsibility d Page F-1 to F-7: Updated Figures Page'T1-2: Added ANSI N18.7 (Section 5.2.7)
Page T1-5: Added ANSI N45.2.2 (Section 6.4.2)
Page T1-15
& T1-16: Added ANSI N45.2.9 (Section 4.3)
Page T1-17:Added ANSI N45.2.23 (Section 2.3.1.3)
Page T1-18:Added AWS D1.1 (Section 5.2.8.4)
Page T2-1: Updated matrix Page T3-1: Revised #2 & #3 Page T3-2: Revised responsibilities #4 & #5 '
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.: 11
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RECORD OF REVISIONS REVISION rT ftUMBER- DESCRIPTION DATE i
V Changes given below are identified on the 7/22/89 11 pages by a bar in the left margin, placed next to the affected area.
Made grammatical corrections, including misspelled word and punctuation on the following pages:
A-1 2-10 14-3 B-1 3-1 14-5 1-1 3-4 16-4 1-2 5-2 18-1 1-24 5-3 18-2 1-25 10-4 18-4 2-1 10-6 18-5 2-3 12-2 AA-3 2-4 13-1 AB-6 2-5 14-1 AB-9 2-6 Page A-1: Changed title 2nd paragraph l Page A-2: Changed title 1st paragraph l Page B-1: Corrected issue date on Reg. Guide
/ Page B-2: Corrected issue date of V] Page 1-1:
Reg. Guide Section 1.3 revised 1st sentence, replaced " President" with Chairman of the Board",
deleted "(see figure 1)",
added last sentence Page 1-2: Section 1.3 (1) changed titles Pages 1-3 to 1-22: Rewritten to reflect new Nuclear Organization structure Page 1-23: All Sections in 1.3.6 were numbered 1.3.5, 1.3.6.2 changed titles, two places Page 1-24: Section 1.4.1 changed titles, three places q Page 1-25: Section 1.4.1.1.1 changed title, i deleted "/ contractors" Page 2-1: Section 2.2.1 changed last sentence to reflect Engineering Consolidation under new organizati.on Page 2-3: Section 2.2.5 changed title I l
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11 (Cont.) Page 2-3: Sect. ion 2.2.6 changed 2nd sentence to reflect Engineering Consolidation under New Organization Section 2.2.2 changed title Page 2-4: Section 2.3.1 replaced
" President" with " Chairman of the Board" Page 2-5: Section 2.3.4 changed title Page 2-9: Section 2.6.6 revised last sentence Page 3-1: Section 3.2.1 changed 1st and 4th sentences to reflect Engineering Consolidation under New Organization Page 3-2: Section 3.3 changed 1st sentence to reflect Engineering Consolidation under New Organization Section 3.4.1 changed 1st sentence to reflect Engineering Consolidation under New Organization, replaced
" organization" with " engineering section" in 2nd sentence
[V] Page 3-3: Section 3.4.2 1st sentence replaced " organizations" with
" engineering section" Page 3-4: Section 3.5.1 changed 1st sentence to reflect Engineering Consolidation under New Organization, replace
" organization" with " engineering section" 2nd sentence Page 3-5: Section 3.5.3, 1st sentence
" organization" with "section" Section 3.7 changed title Page 5-1: Section 5.1.1 addcd "Rev 2" last sentence Page 5-2: Section 5.3.2 revised section Page 5-3: Section 5.4.2 revised section Page 6-1: Section 6.2.2 revised section Section 6.2.3 revised title, 1st and 2nd sentences, replaced " plant" with " approved" ist sentence, added "(excluding NQ procedures)"
ist sentence QA MANUAL OPERATIGNS REV.: 11 l
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11-(Cont.) Page 6-2: Section 6.2.3 revised title last sentence Section 6.2.4 deleted section Page 6-3: Section 6.7 revised section Page 9-3: Section 9.5 revised section Page 10-2: Section 10.2.2 corrected issue dates of two Reg. Guides Page 10-4: Section 10.4.1 changed 1st sentence to reflect Engineering Consolidation under New Organization Page 10-5: Section 10.4.1 added last sentence Page 12-3: Section 12.3.3 changed " National 8ureau of Standards" to new name Page 13-2: Section 13.3.2 changed titles 2nd and 3rd sentences Page 14-1: Section 14.2.1 6dded " appropriate" Ist sentence Page 14-4: Section 14.3.1 added " appropriate" ist and last sentences Section 14.3.2 added " appropriate" 2nd sentence, changed title 2nd sentence Page 15-2: Section 15.2.4 changed titles Il V
2nd sentence Page 15-3: Section 15.3.2 changed " Quality Assurance" to " Nuclear Quality" Page 15-4: Section 15.5 revised section Page 16-1: Section 16.2.2 replaced " station" with " Plant" Ist sentence Page 16-3: Section 16.5.1 revised section Section 16.5.2 revised section Page 16-4: Section 16.5.3 revised section Section 16.6 changed " Quality Assurance" to " Nuclear Quality" Page 17-1: Section 17.2.1 changed title 1st senter.ce Page 17-5: Section 17.5.2.1 changed title 1st sentence Section 17.6 changed title 1st sentence Page 18-4: Section 18.4.1 revised 2nd sentence Page 18-5: Section 18.4.4 revised 1st and 2nd sentences I
e QA MANUAL OPERATIONS REV.: 11 i DATE: 07/22/09
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11 (Cont.) Page 18-6: Section 18.6 revised section Pages F-1 to F-2: Revised organization charts Page T2-1: Revised table 2 Pages T3-1 to T3-2: Rewrote Table 3 to reflect new organization Page AA-3: Section 12 revised titles 1st and 2nd sentences Page AB-3: Section 2.1 #1 deleted "Off-site" added "Overall" and replaced
" President" with " Chairman of the Board", #2 changed title and deleted "on-site", #3 changed title Page AB-5: Section 2.1 #5 changed title,
- 6 changed title em N- ,
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SECTION SUBJECT PAGES REV APPROVAL COVERSHEET N/A 11 RECORD OF REVISIONS RR-1 to RR-18 11 Ti,BLE OF CONTENTS TC-1 to TC-4 11 POLICY STATEMENT A-1 to A-2 11 INTRODUCTION B-1 to B-5 11
' TERMS AND DEFINITIONS C-1 to C-11 10 1.0 ORGANIZATION 1-1 to 1-26 11 fT 2.0 QUALITY ASSURANCE PROGRAM 2-1 to 2-10 11
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3.0 DE5IGN CONTROL 3-1 to 3-6 11 4.0 PROCUREMENT DOCUMENT 4-1 to 4-3 10 CONTROL 5.0 INSTRUCTIONS, PROCEDURES 5-1 to 5-3 11 AND DRAWINGS 6.0 DOCUMENT CONTR01 6-1 to 6-3 11 7.0 CONTROL OF PURCHASED 7-1 to 7-7 10 MATERIAL, EQUIPMENT AND SERVICES a qu e num*
fg QA MANUAL OPERATIONS REV. 11 1
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SECTION SUBJECT PAGES REV I
l B.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 11 PROCESSES 10.0 INSPECTION 10-1 to 10-6 11 11.0 TEST CONTROL 11-1 to 11-5 10 12.0 CONTROL OF MEASURING AND 12-1 to 12-4 11 j TEST EQUIPMENT (j 13.0 HANDLING, STORAGE AND 13-1 to 13-5 11 SHIPPING 14.0 INSPECTION, TEST AND 14-1 to 14-5 11 OPERATING STATUS 15.0 NONCONFORMING MATERIAL, 15-1 to 15-4 11 PARTS OR COMPONENTS 16.0 CORRECTIVE ALTION 16-1 to 16-4 11 1
17.0 QUALITY ASSURANCE RECORDS 37-1 to J1-5 11 IT:. 0 AUDITS 18-1 to 18-6 11 1
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SECTION SUBJECT PAGES REV FIGURE 1 NUCLEAR & RELATED F-1 11 CORPORATE ORGANIZATIONS
,. FIGURE 2 NUCLEAR OPERATIONS DEPARTMENT F-2 11 FIGURE 3 UNIT 1 & 2 OPERATIONS F-3 11 ORGANIZATIONS J FIGURE 4 NUCLEAR QUALITY DEPARTMENT F-4 11 FIGURE 5 ENGINEERING DEPARTMENT F-S 11 FIGURE 6 TECHNICAL SUPPORT & F-6 11 ASSESSMENT DEPARTMENT
,o k FIGURE 7 NUCLEAR SUPPORT DEPARTMENT F-7 11 I
TABLE 1 AND EXCEPTIONS / INTERPRETATIONS T1-1 to T1-28 10 0F REGULATORY GUIDES AND ANSI STANDARDS TABLE 2 QUALITY ASSURANCE T2-1 11 PROCEDURES MATRIX TABLE 3 QUALITY PROGRAM PDLICIES, T3-1 to T3-2 11 PROCEDURES AND INSTRUCTION MANUALS LIST I
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I APPENDIX A QUALITY PROGRAM FOR AA-1 to AA-4 11 TRANSPORT PACKAGES APPENDIX B QUALITY PROGRAM FOR AB-1 to AB-12 11 FIRE PROTECTION O
- " QA MANUAL OPERATIONS REV. 11 h(N DATE 07/22/89 SECTION: TABLE OF CONTENTS PAGE TC-4 Arkansas Nuclear One ,
ARKANSAS NUCLEAR ONE POLICY STATEMENT QUALITY ASSURANCE PROGRAM FOR OPERATIONS -
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It is the policy at Arkansas Nuclear One, Units 1 & 2 (AN0) and its l supporting organizations that the Quality Assurance Program for Operations (QA Program) meets the requirements of the Code of Federal l Regulations, Title 10, Part 50, Appendix B, with respect to operation, I maintenance, refueling, repair and modifications, and inservice l e
I inspection. The QA Program shall also meet the requirements of the ASME l
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 authority responsible for assuring that this policy statement and the QA Program are implemented within AN0 and its supporting organizations. The !
Executive Director Human Resources, and Executive Director Administrative Services are responsible for the procedural implementation of the QA Program within their assigned areas. The Director Nuclear (t )) Operations is responsible for the daily implementation of the QA Program's procedural requirements at ANO.
The General Manager Nuclear Quality is responsible for establishing the 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 inspecting / monitoring activities required by the QA Program to assure l
compliance with its requirements. Disputes involving quality, arising from difference of opinions between Nuclear Quality personnel and other ,
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personnel, which cannot be settled interdepartmentally, shall be presented to the Vice President Nuclear for resolution. The General Manager Nuclear Quality has direct access to the Chairman of the Board and Chief Executive Officer on matters concerning nuclear quality.
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 either this policy or the QA Program that are revealed during the review are to be reported to appropriate levels of management together with appropriate recommendations.
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 imple,ented and enforced by all responsible ,
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organizations and individuals.
AW T. G. Campbellf M
Vice Presidenf Nuclear Date: $2//19
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: STATEMENT OF POLICY PAGE A-2 Arkansos Nuclear One
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INTRODUCTION
(] This manual describes the Qual *y Assurance Program for Operations (QA V Program) applied to Arkansas Nuciect One, Units 1&2 (ANO) and its supporting l organizations. This manual is intended to serve as a standard reference for j safety analysis reports to fulfill the requirements of the Standard Format I and Contents of Safety Analysis Reports for Nuclear Power Plants, Section 17, published by the Nuclear Regulatory Commission.
The objective of the QA Program is to control those phases, as applicable, for the design, procurement, manufacture and fabrication, installation, operation, testing, refueling, repair, maintenance or modification to existing safety related (Q-List) structures, systems and components that prevent or mitigate the consequences of a postulated accident which may cause undue risk to the health and safety of the public. The QA Program is an outgrowth of the principle that quality assurance emanates from each individual contributor and that management is responsible for creating an awareness of quality.
r) c U
m 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 Vessei Code,Section XI for repair, replacement, and inservice inspection of items covered by the Code and Licensing commitments.
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:
1.8, Rev. 1-R Personnel Selecticn and Training (9/75) 1.28, Rev. 1 QA Program Requirements-Design and Construction (3/78) f f j 1
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(, QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: INTRODUCTION PAGE B-1 Arkansos Nuclear One
l 1.30 QA Requirements for Installation. l g Inspection and Testing of Instrumentation (j and Electrical Equipment (8/72) 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 Plants (3/73) 3 l
1.38, Rev. 2 QA Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water Cooled Nuclear Power Plants (5/77) 1.39, Rev. 2 '3usekeeping P. requirements for Water Cooled Nuclear Power Plants (9/77) 1.58, Rev. 1 Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel (9/80) 1.64, Rev, 2 QA Requirements for the Design of Nuclear g Power Plants (6/76)
-() 1.74 1.88, Rev. 2 QA Terms and Definitions (2/74)
Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records (10/76) 1.94, Rev. 1 QA Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (4/76) 1.116, Rev. 0-R QA Requirements for Installation, Inspection and Testing of Mechanical Equipment and Services (6/76) h 1.123, Res, 1 QA Requirements for Control of Procurer.ent f of Items and Services For Nuclear Power Plants (7/77)
.g Q QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: INTRODUCTION PAGE B-2 Arkansas Nuclecr One I
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i 1.144, Rev. 1 Auditing of Quality Assurance Programs for h
the Nuclear Power Plant (9/80) t v) 1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (8/80)
Based upon compliance to these regulatory guides, the QA Program also complies with the following American National Standards Institute (ANSI) l standards subject to exceptions noted in Table 1 of this manual: !
N45.2-1977 Quality Assurance Program Requirements for Nuclear Facilities N45.2.1-1973 Cleaning of Fluid Systems and Associated Components During the Construction Phase of j Nuclear Power Plants N45.2.2-1972 Packaging, Shipping, Receiv:ng, Storage and Handling of Items for Nuclear Power Plants (During
(' the Construction Phase)
N45.2.3-1973 Housekeeping During the Construction Phase of Nuclear Power Plants N45.2.4-1972 Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations N45.2.5-1974 Supplementary Quality Assurance Requirements for Installation and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
[ QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: INTRODUCTION PAGE B-3 Arkonses Nuclear One
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- .f a N45.2.6-1978 Qualifications of Inspection, Examination and '
Testing Personnel for Nuclear Power Plants
/
)
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N45.2.8-1975 Supplementary Quality Assurance Requirements for l Installe"en Inspection and Testing of Mechanical Equipment anu System for the Construction Phase of Nuclear Power Plants N45.2.9-1974 Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants N45.2.10-1973 Quality Assurance Terms and Definitions N45.2.11-1974 Quality Assurance Requirements for the Design of Nuclear Power Plants N45.2.12-1977 Requirements for Auditir g of Quality Assurance P'. , grams for Nuclear Power Plants
> L G/
N45.2.13-19.*6 Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants N45.2.23-1978 Qualification of Quality Assurance Program Audit Personnel for Nuclear Facilities ]
N18.1-1971 Selection and Training of Nuclear Power Plant j 1
Personnel N18.7-1976 Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants !
l N3.1-1981 Selection, Qualification, and Training of Personnel for Nuclear Power Plants
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b QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: INTRODUCTION PAGE B-4 Arkonsos Nuclear One i
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The above requirements are implemented by controlling activities as
, , described in this manual and by procedures referenced in thic manual.
\
GI i The QA Program is also designed to comply with the following codes and l standards, as applicable to those activities to which they are referenced t
l within various sections of this manual:
ASME Section III, Division 1 - 1986 Edition, No Addenda
- ASME Boiler and Pressure Vessel Code - Nuclear Power Plant Components ASME 5ection XI - 1974 Edition, Summer 75 Addenda (ANO Unit 2)**
- 1980 Edition, Winter 81 Addenda (ANO Unit 1)
.ASME Boiler and Pressure Vessel Code - Rules for Inservice Inspection of Nuclear Power Plant Components ASNT SNT-TC-1A-1980 }
Recommended Practice for Nondestructive Testing Personnel Qualification and Certification (This edition shall be used in lieu
] of earlier editions that might be referenced in other codes or standards to which ANO is committed).
AWS D1.1-1985 American Welding Society Structural Steel Welding Code
- Earlier editions / addenda of the Code may be specified for repair or replacement (including system changes) of components or systems, within the rules of ASME Section XI.
- Repair / replacement activities shall be to the 1980 Edition, Winter 81 Addenda Definitions of terms applicable to the QA Program are found in the Terms and Definitions section of this manual.
f 3' !
() QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: INTRODUCTION PAGE B-5 Arkansos Nuclear One i
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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 Arkansas Nuclear One, Units 1 & 2 (AND) in complial:ce with 10CFR50, Appendix B and applicable licensing commitments identified in the Introduction. It also includes a description of the interfaces with j other organizations who may be delegated the work of establishing and f 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.
1.2 GENERAL RESPONSIBILITIES The ultimate responsibility for ANO, including quality assurance, lies with the Vice President Nuclear . He provides management assessment of
, .s the QA Progra:n through review of reports generated by the Nuclear Quality
) (NQ) Organization and reports of NRC activities.
1.3 NUCLEAR ORGANIZATION The Nuclear 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 Chairman of the Board and Chief Executive Officer, 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. The Nuclear Organization is shown in Figures 1 thru 7. The Vice Presioent Nuclear's duties include the following:
p h A QA MANUAL OPERATIONS REV. 11 DATE 7/22/89
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.(1) Providing technical direction and administrative guidance to the:
LJ
- a. Director Nuclear Operations
- b. General Manager Nuclear Quality
- c. General _ nager Engineering
- d. General Manager Technical Support and Assessment
- e. General Manager Nuclear-Support (2) Ensuring conformance to the QA Program by instituting the necessary procedures and instructions within the Nuclear Organization i
(3) Providing for review and approval of design as_ engineering performed for AND (4) Providing for review and approval of procurement documents for equipment, material and services
/
(T) (5) Providing for liaison between ANO and applicable regulatory agencies (6) Providing and maintaining a qualified and suitable staff to carry out required departmental functions (7) Providing for procurement and design review of nuclear fuel (8) Assuming overall responsibility for the fire protection, emergency planning and radiation protection programs implemented at ANO i
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L 1. 3.1_ Director Nuclear Operat;o_n_ss i
,, j The Director Nuclear Operations retarts to the Vice President Nuclear and (v) has direct responsibility for operating ANO in a safe, reliable and a
l efficient manner. He is responsible for operating ANO in accordance with the provisions of the operating licenses. The Nuclear Operations Depattment's organization is shown in Figures 2 and 3. The Director Nuclear Operations has the authority to shut down either unit if required. The Director Nuclear Operations provides technical direction and administrative guidance to the:
i (1) Plant Manager, ANO-1 (2) Plant Manager, ANO-2 i (3) Plant Manager, Central Operations (4) Manager Nuclear Operations Standards 1.3.1.1 Plant Managers, ANO-1 & 2 The Plant Managers, ANO-1 & 2 report to the Director Nuclear Operations and are responsible for the actual operation of their assigned nuclear unit, the maintenance of plant equipment and facilities and the planning /
scheduling of plant work activities. The Units Operations organizations are shown in Figure 3. The Plant Managers, ANO-1 & 2 provide technical direction and adininistrative guidance to their respective:
(1) Managers Operations, ANO-1 & 2 (2) Managers Maintenance, ANO-1 & 2 (3) Project Manager, Outages, ANO-1 & 2 1.3.1.1.1 The Managers Operations, AND-1 & 2 are responsible for directing the actual day-to day operations of their assigned unit. They supervise each unit's operating staff and in.rface with the respective Managers QA MANUAL OPERATIONS REV. 11
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Maintenance, ANO-1 & 2 to accomplish operation-related maintenance activities. They are responsible for coordination of the daily review of O operating surveillance tests and coordination of operation-related maintenance activities. The Managers Operations, ANO-1 & 2 are also responsible for supervision of core refueling, which includes advance planning for the outage, plant preparation, equipment checkout and the refueling operations. The Managers Operations each hold an active Senior Reactor Operators License. The Managers Operations, ANO-1 & 2 provide technical direction and administrative guidance to the Supervisor Shift Operations of their assigned unit.
1.3.1.1.1.1 The Supervisors Shift. Operations report to the applicable Manager Operations and are responsible for the actual operation of the unit during their assigned shifts. The Supervisor Shift Operations is cognizant of operation activities being performed while on duty. The Supervisor Shift Operations on duty has the authority to shut down the unit if, in his judgement, conditiens warrant such action. The (9 Supervisors Shift Operations each hold an active Senior Reactor Operator License. The Supervisors Shift Operations provide technical direction and administrative guidance to the:
(1) Control Room Supervisors (2) Shift Administrative Assistants 1.3.1.1.1.1.1 The Control Room Supervisors 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 Control Room Supervisors each hold an active Senior Reactor Operator License. The Control Room Supervisors provide technical direction and administrative guidance to the:
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l QA MANUAL OPERATIONS REV. Il lb OATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-4 Arkonsos Nuclear One 4
(1) Control Board Operators (Holders of active Reactor Op <ator
,_s License)
) (2) Waste Control Operators (3) Auxiliary Operators 1.3.1.1.1.1.2 The Shift Administrative Assistants report to the applicable Supervisor Shift Operations and are responsible for general operations administrative duties.
1.3.1.1.2 The Managers Maintenance, ANO-1 & 2 report to the applicable Plant Manager, ANO-1 & 2 and are responsible for the maintenance of plant equipment and facilities as defined by plant maintenance program implementing procedures and ensuring that maintenance of equipment is performed in compliance with applicable standards, codes, specifications and procedures. The Managers Maintenance, ANO-1 & 2 are also to
()
coordinate operation-related maintenance activities with the applicable Nanagers Operations, ANO-1 & 2 and are responsible to make repairs on any structure, system or component under their control. The fianagers Maintenance, ANO-1 & 2 provide technical direction and administrative guidance to the Maintenance Technical Staff.
- 1. 3.1.1. 3 The Project Managers, Outages ANO-1 & 2 report to the applicable Plant Manager, ANO-1 & 2 and are responsible for management and direction of activities to prepare for and control scheduled and non-scheduled unit outages. The responsibilities include detailed planning, preparation and scheduling of refueling outages and other scheduled or forced outages requiring cold shutdown, and directing activities during outages.
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1.3.1.2 Plant Manager, Central Operations
()
The Plant Manager, Central Operations reports to the Director Nuclear Operations and provides planning, direction, control and overall supervision to the Central Support Department, the Planning & Scheduling section, the Radiation Protection /Radwaste section, the Chemistry /
Radiochemistry section, and the Maintenance Engineering section in operating and maintaining ANO. Responsibilities involve the development and administration of programs which support the capability of ANO to meet or exceed all industry standards and regulatory requirements.
Responsibilities also involve the supervision of personnel and daily work activities involving the safe, efficient and reliable operation of ANO.
The Plant Manager, Central provides technical direction and administrative guidance to the:
(1) Manager Central Maintenance (2) Manager Planning and Scheduling ,
(3) Superintendent Chemistry and Radiochemistry (4) Superintendent Radiation Protection and Radwaste
(_)
1.3.1.2.1 The Manager Central Maintenance reports to the Plant Manager, Central Operations and provides planning, direction, control and overall supervision of the Central Support functions (e.g., Central Maintenance, Maintenance Engineering, Meteorology, Welding, Machine Shop, Plant Services, etc.) operating and maintaining ANO. Responsibilities involve the development and administration of programs which support the {
capability of ANO to meet or exceed all industry standards and regulatory 1 requirements. Responsibilities also involve the supervision of personnel and daily work activities involving the safe, efficient and reliable operation of ANO.
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1.3.1.2.2 lh The Manager Planning & Scheduling reports to the Plant Manager, Central Operations and is responsible for the planning / scheduling of plant work activities and the maintenance.of the equipment history and associated reports. He supervises the Planning & Scheduling staff and interfaces with the Managers Operations, ANO-1 & 2, Managers Maintenance, ANO-1 & 2 and Project Managers, Outages AND-1 & 2 to accomplish the scheduling of the outage /non-outage work activities. The Manager Planning & Scheduling provides technical direction and administrative guidance to the:
1 (1) Superintendent Planning (2) Superintendent Scheduling (3) Supervisor Maintenance History (4) Data Processing Specialist 1.3.1.2.3 I The Superintendent Chemistry and Radiochemistry reports to the Plant Manager, Central Operations and is responsible for implementing the (nv) Nuclear Organization chemistry policies, programs, and procedores. The Superintendent Chemistry and Radiochemistry is directly responsible for implementing controls as required to maintain chemistry and radiochemistry parameters in specification and establish chemistry and radiochemistry controls conducive to maximizing plant life.
1.3.1.2.4 The Superintendent Radiation Protection and Radwaste reports to the Plant Manager, Central Operations and is responsible for implementing the Nuclear Organization radiation protection and health physics policies, programs, and procedures. The Superintendent Radiation Protection and Radwaste is directly responsible for implementing controls which will 1
A) t QA MAdUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-7 Arkonnos Nuclear One 1
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minimize personnel radiation exposure (ALARA), minimize personnel
,, contamination, minimize radwaste volume, and establish uniform procedures
/
- h. ani methods for contamination control and radiation protection, s
2.3.1.3 Manager Nuclear Operations Standards The Manager Nuclear Operations Standards reports to the Director Nuclear Operations and provides planning, direction, coritrol and overall supervision to the Nuclear Operations ftandards Department in develuping and maintaining policies and procedures for the operation, maintenance, chemistry and radiation protection programs of ANO. Responsibilities involve the development and administration of programs which support the capability of ANO to meet or exceed all indust e standards and regulatory requirements. Responsibilities also involve the Chairmanship of the Plant Safety Committee which reviews all aspects of operation, maintenance, modification and support to assure the safety of ANO. The Manager Nuclear Operations Standards providas technical direction and administrative guidance to:
( (1) Superintendent Operations Standards (2) Supervisor Maintenance Standards (3) Supervisor RP Standards (4) Supervisor Chemistry Standards (5) PSC Administrative Assistant 1.3.2 General Manager Nuclear Qualip The Nuclear Quality (NQ) Department's organization shown in Figure 4 is under the direction of the General Manager Nuclear Quality who reports l to the Vice President Nuclear. The NQ Organization performs reviews, surveillance, inspection, nondestructive examination 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 (n) QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-8 Arkansas Nuclear One
i i
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 designated channels; and verify w.-)
implementation of solutions.
The qualification requirements of the General Manager Nuclear Quality are i established within his job description which include the following prerequisites: !
(1) Possess a degree from an accredited school in engineering or a related scientific discipline or equivalent (2) Possess a minimum of four years experience in the field of quality assurance / control with at least two years in the nuclear field or equivalent number of years of nuclear plant i experience in a supervisory position with at least one year experience in the implementation of the quality assurance program (3) Exhibit the ability to plan, schedule and direct the activities
(% )) of others assigned to or functioning within the NQ organization l
Duties and responsibilities of the General Manager Nuclear Quality include the following:
(1) Teunical direction, administrative guidance an.J supervision to the Stperintradent Quality Assurance and Superintendent Quality Control / Quality Engineering (2) Approving of the QA Manual Operations and revisions thereto (3) Approving of QA and QC/QE procedures and revisions thereto as established within NQA procedures REV. 11 O)
QA MANUAL OPERATIONS DATE 7/22/89 SECTION. 1.0 ORGANIZATION PAGE 1-9 j Arkansas Nuclear One
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g 1.3.2.1 Superintendent Quality Assurance
\
i ) The Superintendent Quality Assurance reports to the Eeneral Manager a
Nuclear Quality. Duties and responsibilities of the Superintendent Quality Assurance include the following:
(1) Developing the QA Program requirements for operation, maintenance, and modification activities related to safety-related (Q-listed) systems, structures and components (2) Auditing of the quality activities as described in Section 18.0 of this manual (3) Reviewing, approving and verifying of the quality assurance requirements placed uoon contractors or vendors that provide equipment, material or services for ANO (4) Authority to stop work where conditions exist that prohibit effective quality programs, or if faulty materials, incorrect
[D
~) workmanship or procedures are detected (5) Reviewing, approving, and controlling of vendor quality manuals and procedures and revisions thereto (6) Reviewing and approving of quality assurance programs for outside organizations participating in the QA Program )
(7) Providing and maintaining a qualified and suitably trained staf f to carry out required staff functions )
I (8) Formulating programs for maintaining the professional competence of personnel within the Quality Assurance section and providing assistance in Quality Assurance training and l
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/O QA MANUAL OPERATIONS REV. 11
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indoctrination programs for management, engineering and plant a personnel whose activities affect quality kj (9) Providing technical direction and guidance to the Supervisors Quality Assurance and their staff ;
(10). Inspecting, auditing or reviewing practices, records, files, instructions, directions or documents concerned with all areas affecting quality (11) Scheduling and coordinating audits or surveillance efforts in the areas assigned, documenting findings and reporting results to the General Manager Nuclear Quality and management of the audited area (12) Providing to the General Manager Nuclear Quality on an annual basis the results of a review of the QA Program to deter e the effectiveness and proper implementation of the QA Program n
) 1.3.2.2 Superintendent Quality Contro'</ Quality Engineering The Superintendent Quality Control / Quality Engineering reports to the General Manager Nuclear Quality and is responsible for verifying the impicentation of the Quality Control program at ANO. The duties and responsibilities of the Superintendent Quality Control / Quality Engineering include the fMlowing: ,
(1) Interface with plant staff in developing qu6lity control requirements and inspection points for operation, maintenance and modification activities related to safety-related (Q-listed) and fire protection-related (F-listed) systems, structures and components
(/ QA MANUAL OPERATIONS REV.
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1 (2) Interface with the Superintendent Quality Assurance or his
, . y representative for technical assistance in resolving ;
j
) 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 surveillance, inspections, examinations, and reviews of plant activities and documents are conducted in accordance ,
with approved procedures (5) Providing technical direction and guidance to the Supervisor Quality Engineering, Supervisor Nondestructive Examination, and Supervisors Quality Control and their staffs (6) Providing and maintaining a qualified and suitably trained staff to carry out required staff functions and formulate programs for maintaining the professional competence of
(]
personnel within the Quality Control / Quality Engineering section
-1.3.3 General Manager Engineering Tne General MEnrer Enginecting reports to'the Vice President Nuclear and provides direction, planning, support and overall supervision to Mechanical / Civil / Structural Design; Eler.trical/I&C Design; ANO Engineering (Systems Engineering, Reactor Engineering and Engineering Services); Nuclear Design Services (Nuclear Engineering, Design Documentathn, Drafting, Planning & Scheduling and Engineering Methods /
Training) and ANO Modifications functions. Responsibilities include the ;
development of programs, policies, procedures and providing engineering 3
O l
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-12 Arkonsor Nuclear One
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_j
l services in support of design, evaluation, analysis, installation,
- , testing, inspection, and operation of ANO. This position is also )
(.-) responsible to ensure effective design modifications to correct l8 deficiencies in plant systems and equipment, improve plant availability, j efficiency, safety or productivity and assure thorough and complete l design documentation to support effective configuration management for I ANO. The Engineering Department's organization is shown in Figure 5.
The General Manager Engineering provides technical direction and f administrative guidance to:
(1) Manager Mechanical, Civil, Structural Design (2) Manager Electrical, Instrumentation & Control Design (3) Manager Nuclear Design Services (4) Manager ANO Engineering (5) Manager Modifications 1.3.3.1 Manager Mechanical / Civil / Structural Design The Manager of Mechanical, Civil, & Structural Design reports to the in i ji General Manager Engineering and directs engineering activities in support of ANO, primarily in the areas of plant modifications, operability assessments and maintenance of the Mechanical Engineering, Civil Engineering & Structural Engineering design bases of ANO, the primary benefit of which is safe efficient operation of ANO in compliance with applicable regulatory requirements. This position proviaes technical assistante in the resolution of Operations & Maintenance concerns at the request of plant staff, and is directly related to power generatton !
l' operations. f l
l 1.3.3.2 Manager Electrical / Instrumentation and Control Design The Manager of Electrical, Instrumentation and Control Design reports to the General Manager Engineering and directs engineering activities in support of ANO, primarily in the areas of plant modifications, iO)
V QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 l SECTION: 1.0 ORGANIZATION PAGE 1-13 Arkansos Nuclear One ;
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operability assessments and maintenance of the Electrical Engineering and Instrumentation & Control Engineering design bases for AN0; the primary
) benefit of which is safe efficient operation of AND in compliance with applicable regulatory requirements. This position provides technical ;
assistance in the resolution of Operation & Maintenance concerns at the request of plant staff, and is directly related to power generation operations.
1,3.3.3 Manager Nuclear Design Services The Manager Nuclear Design Services reports to the General Manager Engineering and directs engineering, drafting and administrative activities in support of ANO, primarily in the areas of plant modifications, operability assessments and nuclear safety analyses, the primary benefit of which is safe efficient operation of ANO in compliance with applicable regulatory requirements. The position provides nuclear i engineering, core reload, and availability, reliability technical assistance in the resolution of Operation & Maintenance concerns at the request of plant staff, and is directly related to power generation
,j operations.
1.3.3.4 Manager ANO Engineering The Manager ANO Engineering reports to the General Manager Engineering 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 j guidance to the:
(1) Superintendent Reactor Engir.rering (2) Superintendent Plant Engineering i l
(3) Superintendent Engineering Services j
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1.3.3.4.1 The Superintendent Reactor Engineering reports to the Manager ANO Engineering and is responsible for monitoring reactor core and NSSS performance; 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 q the Supervisor Core Reload Design 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.
1.3.3.4.2 The Superintendent Plant Engineering reports to the Manager AND Engineering and is responsible for drawing control, engineering support of plant activities, evaluating equipment and system performance and I plant efficiency, and investigating and evaluating equipment malfunctions A
Q or failures.
1.3.3.4.3 The Superintendent Engineering Services reports to the Manager AN0 Engineering and is responsible for the implementation and coordination of j the Inservice Inspection program, on-sit & k'elding program, and the q Ir; service Testing program at ANO. He is also responsible for f coordination of the ANO fire protection and fire prevention program.
These prograas include conducting periodic checks to examine control of combustibles, housektepina and other fire prevention efforts. He is also responsible for the steam generator integrity program, check Mvc l inspection program, secondary piping erosion-ccrrosion monitoring, tan 1
i
('-). QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-15 Arkansos Nuclear One ,
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and filter performance testing, evaluation of possible consequences of l
7-boric acid corrosion on carbon steel, and for coordinating the technical C)' manual, component data base and preventive maintenance pro 0 rams at ANO.
1.3.3.5 Manager Modifications The Manager Modifications reports to the General Manager Engineering 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 assignments and providing cost and schedule controls for department activities. The Manager Modifications is also responsible for providing engineering support during the implementation and closeout of design modifications generated in support of ANO. The Manager Modifications provides technical direction and administrative guidance to the:
(1) Superintendent Installation (2) Superintendent Project Engineering g (3) Administrative Coordinator i
1.3.4 General Manacer Technical Support & Assessment The General Manager Technical Support & Assessment reports to the Vice President Nuclear and provides planning, direction, control and overall supervision to the Plant Assessment, Training, Licensing, Administrative Services, Adm %istrative Control Standards ar.d Security Departments in [
support of the contitiued operation of ANO. Responsibilities involve ensurin9 the development and administration of programs in the areas mentionco above that meet or exceed industry standards and regulatory requireu,ents in both varied technical and non-technical arns; ell of which impact the capability and performance of maintenance, operations j.
and support persor.nel and thus affecting plant availability, performance and e.fficiency. Responsibilities also involve the supervision of
,e . 11 QA MANUAL OPERATIONS REV.
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activities involving direct regulatory interfaces, station support, I
,y safety assessment and program oversight as well as development and )
i,j maintenance of the ANO administrative controls program. The Technical Support and Assessment Department's organization is shown in Figure 6. j The General Manager Technical Support & Assessment provides technical )
direction and administrative guidance to the: l (1) Manager Licensing )
(2) Manager Administrative Services I (3) Manager Plant Assessment (4) Manager Training ,
(5) Superintendent Security l (6) Supervisor Administrative Control Standards 1.3.4.1 Manager 8icensing The Manager Licensing reports to the General Mar,ager Technical Support &
Assessment and has overall responsibility for the management and cversight of NRC inspection activities and interactions with the NRC
() regional and Washington, DC offices. The Manager Licensing provides technical direction and administrative guidance to the:
(1) Supervisor Licensing / Compliance i (2) 5@ervisor Licensing 1.3.4.'. 1 The Supervisor Licensing / Compliance 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 Q
ty QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1- P Arkonsos Nuclear one
p (2) Providing evaluations and recommendations in meeting regulatory commitments k'
(3) Establishing and maintaining a system for monitoring License Event Reports and NRC Inspection Reports (4) Providing technical direction and administrative guidance to the Nuclear Safety and Licensing Specialists 1.3.4.1.2 The Supervisor Licersing reports to the Manager Licensing and is responsible for the 'ollowing duties:
(1) Interfacing with NRC, Washington, DC offices and the Aanager Licensing pertaining to Licensing and regulatory matters (2) Establishing and maintaining programs for the maintenance of Licensing Base Documents (License, SAR, Technical 3 ' Specification, Emergency Plan, QA Manual Operations) m (3) Reviewing NRC Correspondence (incoming and outgoing) and related industry documents to remain cognizant of activities that may affect ANO (4) Providing technical direction and administrative guidance to the Nuclear Safety and Licensing Specialists 1.3.4.2 Manager Administrative Services The Manager Administrative Services reports to the General Manager Technical Support & Assessment and is responsible for providing administratda services in support of plant activities. The duties and QA MANUAL OPERATIONS REV. 11
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_ _ _ _ _ _ _ _ _ J
I responsibilities of the Manager Administrative Services include the f,.
'tollowing:
w/
(1) Technical direction and administrative guidance to the:
- a. Superintendent Office Service:,
- b. Superintendent Materials Management
- c. Superintendent Computer Support
- d. Administrator Human Resources (2) Accumulation, storage and disposition of quality assurance records related to all phases of.ANO (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 l
1.3.4.3 Manager Plant Assessment The Manager Plant Assessment reports to the General Manager Technical Support & Assessment and is responsible for providing assessments of plant and industry operating experiences, oversight of plant and industry operation experiences, oversight of key station programs (including radiation protection, chemistry, operations, maintenance, modification, procurement, training, etc.) and on-shift technical advice to operations. '
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l The Manager Plant Assessment provides support and membership on the Plant )
Safety Committee and Safety Review Committee. The Manager Assessment
() also manages the plant operation experience review program in accordance with INP0 guidelines. The Manager Plant Assessment provides technical direction and administrative guidance to the: I l
(1) Superintendent Operations Assessment (2) Superintendent Oversight 1.3.4.3.1 The Superintendent Operations Assessment reports to Manager Plant Assessment and 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 help plant operations personnel in preventing or dealing with similar occurrences.
The Superintendent Operations Assessment is also responsible for the administration of the Corrective Action Program. He also provides r~s I,] technical direction and administrative guidance to the Shift Technical Advisers.
1.3.4.3.2 The Superintendent Oversight reports to the Menager Plant Assessment and is responsible for assisting functional management in monitoring ard evaluating ANO performance to ensure that effective management programs are developed, implemented and maintained to achieve the predeterrrined .
I goals and Standards of Excellence as prescribed by senior nuclear 1 management. Nuclear Oversight is accomplished through a continued interaction between the Oversight staff and the approntiate functional managers and technical personnel in the Oversight Funi.tional Areas. The Oversight group provides independent, objective assessments (outside the traditional auditing role) of the overall effectiveness of nuclear p)
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programs to help assur'e that performance expectations are accomplished.
,, The inputs to this process include the assessment of prior and current (j '
AND performance compared to the predetermined goals, comparable industry performance.for these goals, the Standards of Excellence identified by INP0, and the evaluation of industry strengths and good practices for appl,1cability to Ah0. The Superintendent Oversight also provides technical direction and administrative guidance to the Corporate Health Physicist.
1.3.4.4 Manager Training The Manager Training reports to the General Manager Technical Support and Assessment and is responsible for the training and retraining of plant personnel and general office personnel as established by approved procedures. The Manager Training is also responsible for the implementation and maintenance of the ANO Emergency Plaa. The Manager Training directs the activities of the ANO training staff and provides technical direction and administrative guidance to the:
! Q;r (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 1.3.4.5 Superintendent Security The Superintendent Security reports to the General Manager Technical Support and Assessment and is responsible for plant security including coordination of efforts of the security force and managing the operation of the security system.
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i 1.3.4.6 Supervisor Administrative Control Standards
,3 f The Supervisor Administrative Control Standards reports to the General Manager Technical Support and Assessment and is responsible for preparing and maintaining the administrative controls program for ANO. This involves preparing policies and procedures related to the administration of the various ANO nuclear programs, revising these documents as requirements and practices change. The Supervisor Administrative Control Standards is also responsible for providing input to lesson plans and training support related to communication of these policies and procedures to ANO employees. This position also provides oversight of the administrative controls program for ANO and advises senior nuclear management on solutions to administrative and management issues.
1.3.5 General Manager Nuclear Support The General Manager Nuclear Support reports to the Vice President Nuclear and is rr:ponsible for managing the nuclear five year business plan, including establishing the budget, and goals and objectives program for the Nuclear Organization. Payroll, accounting and contracts
!v) administration support is also provided by the General Manager Nuclear Support. He is also responsible fur the overall management of ANO participation in the B&W and CE Owners Groups, and other industry groups.
He additionally serves as a member and Secretary of the Safety Review Committee. The Nuclear Support Department's organization is shown in Figure 7. The General Manager Nuclear Support is responsible for providing direction and general supervision to the folicwing technical and administrative ir.dividuals in support of the Vice President Nuclear:
(1) Project Manager Nuclear Industry Support (2) Superintendent Nuclear .nlanning (3) Controller (4) Project Manager Nuclear Staff Support (5) SRC Administrative Assistant rm REV. 11 Q^ QA MANUAL OPERATIONS DATE 7/22/89 SECTION: 1.0 ORGANIZATION PAGE 1-22 Arkansas Nuclear One
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1.3.6- Independent Review Organizations p- ,
b In addition to the responsibilities of key individuals within the Nuclear Organization who are involved with the overall quality program, the f following committees have been established as management tools to j independently review activities occurring during the operational phase of J ANO.
1.3.6.1 Safety Review Committee (SRC)
The SRC is chaired by the Vice Presidant 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 op' ration 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 meeting minutes generated from the Plant Safety Committee.
g Q 1.3.6.2 Plant Saf. sty Committee (PSC)
The PSC repo-ts to the Director Nuclear Operations and is responsible for reviewing activities specified in the Technical Specifications for the i purpose of:
(1) Rendering determinations in writing with regard to whether or not an unreviewed safety question (defined by 10CFR50.59) is involved (2) Furnishing written recommendations to the Director Nuclear Operations for approval (n
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These activities include coa yes to plant procedures and Technical
. Specifications, proposed modifications to ple.rt systems, changes to plant security and emergency plans and review of facility operations (v) ,
to detect potenti11 nuclear safety hazards.
1.3.6.3 Committee Structure The organizational structure and administrative requirements specific to each committee are describe _d in the Technical Specifications for each operating unit and in internal procedures / documentation.
1.4 OUTSIDE SUPPORT ORGANIZATIONS 1.4.1 Senior Vice President & Chief Financial Officer Administrative Services and Human Resou-ces heac'ed by the Senior Vice President & Chief Financial Officer are involved in procurement and training activities requiring execution'of the QA Program. The organization is shown in F'gare 1. The Senior Vice President & Chief im Financial Officer provides technical direction and administrative (v) guidance to .he:
(1) . Executive Director Administrative Services (2) Executive Director Human Resources 1.4.1.1 Executive Director Administrative Services The Executive Director Administrative Services, who reports to the Senior Vice President & Chief Financial Officer, is responsible for the
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procurement of materials, parts and components requested by Nuclear personnel off-site and for supporting the procurement activities at ANO.
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(,) The General Manager Procurement & Materials Management reports to the .
l Executive Director Administrative Services and is responsible for the ;
following duties and activities: )
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(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 (3) Performing the commercial interface functions between ANO and vendors l
(4) Ensuring that quality documentation prepared by ANO personnel is included in appropriate procurement documents 1.4.1.2 Executive Director Human Resources I
v) The Executive Director Human Resources reports to the Senior Vice President & Chief Financial Officer and is responsible for 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 including action to assure that the plant is operated in accordance with sound engineering practices, licensing requirements and applicable codes, specifications and precedures.
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Each supplier of equipment, material or services and each maintenance or )
,s modification contractor is responsible for administering the applicable l
) l quality control functions as required by ANO. The NQ Organization is responsible for assuring by surveillance, inspection, audit or review of a objective evidence (e.g., review audit reports conducted by others, etc.)
that these functions are accomplished for systems, structures and
]
i services that affect the safety and integrity of the plant. j Visits to manufacturers' shops by Quality Assurance personnel are {
conducted, when deemed necessary, based upon safety significance, complexity, method of acceptance and past history of the vendor, to establish product quality and to assure that quality assurance and quality control programs function in accordance with ANO requirements.
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l l 2.0 QUALITY ASSURANCE PROGRAM j 2.1 SCOPE l
t 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 i
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 j undue risk to the health and safety of the public or to mitigate the ry consequences of such accidents if they were to occur. These structures, i
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 l
(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 assreiated with a loss of safety function as determined by Engineering are to be considered Non-Q, unless otherwise dispositioned by Engineering.
- Expendable and/or consumable items are to include, as a minimum:
auclear fuel, weld rods, boric acid, and diesel fuel.
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2.2.2' 1 f Expendable and/or consumable items where quality is necessary for the performance of Q-listed structures, systems and components are identified and controlled in accordance with Technical Specifications and/or procedures.
The following expendable and/or consumable items are to be controlled in the followina 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 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
,\,
i ) (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 ef 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. j j
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. ) The quality program for fire protection is addressed in Appendix B of l' this manual and in the applicable section of the SAR and Technical Specifications for each operating nuclear unit and implemented through appropriate approved procedures. The effectiveness of the fire protection program is verified through scheduled audits conducted by'the NQ Organization, under the cognizance of the SRC.
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 peisonnel 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 review / approval by the applicable Manager 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. Engineering is responsible for the technical adequacy of the CLQL and the administrative controls of the CLOL within SIMS. Evaluations, reviews and approvals to changes to the CLQL are performed in accordance with applicable procedures.
2.2.7 l
The Component Level F-list (CLFL) is maintained on the SIMS component data base by Engineering. Components classified as "F" on this list fall under the requirements of Appendix B of this manual. The controls for this list are similar to the controls utilized for the Q-list.
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2.2.8 i Components that are not Q-listed or F-listed and which are subject to ASME code requirements or similar design stcndards, regulatory requirements or licensing commitments or other ANO commitments are classified as "S" in the SIMS corponent data base. The controls for this list are similar to controls for the Q-list. This list is also l
referred to as the Component Level S-list (CLSL).
- 2. 3 RESPONSIBILITIES 2.3.1 AND recognizes that quality assurance is an interdisciplinary function involving many organizational groups, encompasses many functions and activities and extends to various levels in all participating
] organizations (from the Chairman of the Board and Chief Executive Officer to all workers whose activities may influence quality). The QA Program
' designates responsibilities and duties of specific indiv1 duals, which may
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be performed by their appointed des'gnees.
2.3.2 a
The QA Program assigns the responsibility for quality to the departments performing the work and includes as a basic requirement that individuals j responsible for verification of conformance are qualified and do not perform or directly supervise the work. Additionally, independent j reviews, audits and surveillance are provided by individuals not reporting to the groups responsible for performing the work.
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2.3.3 g3 C) The QA Propam 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 surveillance by the NQ Organization provide assurance of compliance with applicable procedures.
2.3.4 l The Supervisor 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, manuf actured 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).
Individuals who perform receipt inspections are qualified in accordance V with paragraph 2.6.3 of this manual. The Quality Control / Quality Engineering Superintendent maintains a listing of those individuals qualified to perform receipt inspection on nuclear fuel.
2.4 PROCEDURES 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 the QA Program. Procedures provide for standard forms, lis,ts, end checkoffs used in documenting the inspections, certifications, reviews, 1
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surveillance and audits. Programs and procedures are modified or supplemented from time-to-time as the need for change arises during the life of the plant. Quality program policies, procedures and instructions
}] are contained in the documents listed in' Table 3.
I 2.4.2 l
I Procedures assure that activities affecting quality are performed under- j suitably controlled conditions. Controlled conditions include the use of l appropriate equipment, suitable environmental conditions for performing i the activity such as adequate cleanness and assurance that required prerequisites for the given activity have been satisfied. Administrative procedures also assure that the need for special controls, processes, tests and equipment to attain the required quality and the need for.
verification of quality by inspections, evaluations or tests is taken into account.
2.4.3 l Other organizations outside of the Nuclear Organization may establish written procedures to control support activities affected by the requirements of the QA Program. Procedures developed by such organizations are prepared and reviewed for technical adequacy within the cognizant organization, reviewed by the Superintendent Quality Assurance and approved uy the cognizant organization's Department Head.
l 2.5 PROGRAM REVISION AND CONTROL 2.5.1 Program revision and control shall be the responsibility of the General Manager Nuclear Quality.
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2.5.2
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) Proposed changes to this manual are to be submitted by the Superintendent Quality Assurance to affected management personnel for review and comment prior to approval and transmittal to the Nuclear Regulatory Commission.
After resolution of comments, changes are to be approved by the 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 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 the commitments are to be submitted and approved.by the Nuclear Regulatory Commission prior to implementation. The General Manager Nuclear Quality is to determine if changes do or do not reduce the commitments of the QA Program.
L) 2.6 PERSONNEL 2.6.1 Employees whose duties and responsibilities are related to the QA Program activities at or in support of ANO are to participate in appropriate indoctrination and training programs to assure that suitable proficiency ,
is achieved and maintained in the work they are performing. Such I training shall include, as a minimum: plant security (badged personnel only), discussion of the overall Company policies, procedures and instructions which establish the QA Program, an explanation of the i quality organization and a discussion of those procedures which implement the QA Program related to the employee's specific job-related activity.
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2.6.2 ,
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v The education, experience and responsibility requirements of individuals involved in the QA Program are documented in job descriptions which are approved and periodically ' reviewed by management. Requirements for <
education, experience and proficiency levels are commensurate with the degree of importance of the job assignment. Experience and training I requirements for plant staff personnel are to meet the requirements of ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted in Table 1. Personnel whose qualifications do not meet those specified in ANSI N18.1-1971, and who are performing inspection, examination and testing activities during the operational phase of the plant, are to meet the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. -
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, specifications, regulatory requirements and approved procedures.
Personnel performing inspections on those activities occurring during the operational phase that are comparable in nature and extent to related activities occurring during initial plant design and construction are to meet the provisions of Regulatory Guide 1.58, Rev. 1 (9/80) and ANSI N45.2.6-1978, in lieu of ANSI N18.1-1971.
1 2.6.4 Personnel involved with welding of materials, systems or components are to meet the appropriate qualification requirements of the ASME Boiler and Pressure Vessel Code, Sections III and XI, or for structural welds, the American Welding Society (AWS) Structural Steel Code D1.1. Personnel I)
V QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 2.0 QUALITY ASSURANCE PROGRAM PAGE 2-8 l Arkansos Nuclear One l
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t involved with nondestructive examination of materials, components or systems are to meet the qualification requirements of the American ,l
) Society Nondestructive Testing Recommended Practice SNT-TC-1A or ASME- [
Section III and XI for ASME Code materials, components or systems.
f Personnel are to be certified to perform these tasks in accordance with these codes and standards. j l
2.6.5 ;
l Personnel performing audits of the QA Program are to meet the experience, training and qualification / certification requirements of ANSI N45.2.23-1978, and Regulatory Guide 1.146 (8/80), unless otherwise noted in Table 1.
2.6.6 l
Personnel appointed to the SRC shall collectively have the experience and l competence required by ANSI /ANS N3.1-1981. Personnel appointed to the !
PSC shall be composed of those individual positions identified in the
( ) Technical Specifications applicable to each nuclear unit.
2.6.7 Training records are to be maintained in accordance with approved procedures. For formal training programs, documentation is to include the objective, content of the program, attendees and date of attendance.
I I QA MANUAL. OPERATIONS REV. 11 DATE 7/22/89 SECTION: 2.0 QUALITY ASSURANCE PROGRAM PAGE 2-9 Arkansos Nuclear One
2.7 PROGRAM REVIEW (y
t_~.,J ' 2.7.1 ,
l The General Manager Nuclear Quality through the Superintendent Quality )
Assurance is responsible for a review of the QA Program on an annual l basis to determine the effectiveness and proper implementation of the QA !
1 Program. l i
I 2.7.2 l I
Management reviews of the status and adequacy of the QA Program are j accomplished through regular reports and presentations by the NQ l
Organization and through reviews of quality assurance reports. - Quality assurance reports supply data on the status of outstanding audit and corrective action items and may identify the status of other significant QA Program activities as requested by management.
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3.0 DESIGN CONTROL
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3,1 SCOPE
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1 Design activities are to be controlled to assure that irsposed plant changes to the structure <, systems, equipment and components conform to applicable regulatory requirements and that design bases are correctly translated into appropriate design documents. Design control activities are to be in accordance with the requirements of Regulatory Guide 1.64, Rev. 2 (6/76), unless otherwise noted in Table 1.
i 3.2 GENERAL 3.2.1 l
Engineering is responsible for the continued upgrading and modification of plant design. Design documents (drawings, specifications, procedures ,
and instructions) originating or released through these departments are to be based upon the regulatory requirements, licensing based documents, 7s
( ) functional requirements, quality standards and design bases in accordance v
with NRC 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 within Engineering are controlled by the use of Plant Modification Process (PMP) control procedures and by applicable administrative and departmental procedures. These procedures include controls to assure that verified computer codes are certified for use and j that their use is specified.
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) Design standards and requirements are to be at least equivalent to those employed during the construction of the plant and are to be consistent with the Technical Specifications and License requirements. ..
3.3' DESIGN INTERFACE i
1 Design control activities include measures for the identification and
]
control of design interfaces between the various engineering sections within Engineering, between Engineering and other Nuclear Organizations, and between Engineering and firms / suppliers outside the Nuclear ]
Organization. These measures include the development of procedures among -
the participating organizations for the review, approval, release, j i
distribution and revision of docurr.ents involving design interf ace, j l
Coordination of the interface control is the responsibility of the j originating organization's management unless otherwise specified in a procedure applicable to the design activity. Design information between interfacing organizations is to be documented and retained for permanent records.
(v) 3.4 DESIGN VERIFICATION 3.4.1 lo assure the design is adequate and the above requirements and procedures are implemented, Engineering is to verify the adequacy of the design through the performance of design reviews, the use of alternate or simplified calculation methods, or the performance of a qualification testing program. The extent and depth of design verification performed l
by the responsible engineering section is determined by an assigned engineering reviewer based upon the importance and complexity of the p) i QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 3.0 DESIGN CONTROL PAGE 3-2 Arkonsos Nuclear One
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design, the degree of standardization and its similarity with proven i designs. In all cases, the design verification is to be complete prior to relying upon the component, system or structure to perform its (a)-
function. j i
I 3.4.2 l The verification process is to be performed by competent individuals or ;
groups other than those who performed'or supervised the design but who l may be from the same engineering section. This verification, however, may be performed by the originator's supervisor in accordance with departmental procedures if he is the only individual in the organization competent to perform the verification and provided the need is individually documented and approved in advance by the responsible Manager or Superintendent. The frequency and effectiveness of the use of !
Supervisors as design verifiers is to be verified by 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 r
( changes on the overall design. l K
3.4.3 When a test program is used to verify the adequacy of a design, it is to include suitable qualification testing of a prototype or initial production unit under the most adverse 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.
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3.4.4 7
i ) Design work performed by organizations outside of the Nuclear l Organization is to receive a documented review and approval by engineering personnel in accordance with PMP control procedures and applicable departmental procedures.
3.5 DESIGN CHANGE
- 3. 5.1 Methods for the preparation, review, approval and implementation of design changes, including field changes, are documented in PMP control procedures and departmental procedures for Engineering. Design changes are subject to review and verification by the same engineering section which reviewed and verified the original design unless otherwise specified in departmental procedures for design control. If changes to an approved design are required to meet plant requirements or conditions, Field Change Requests (FCR) may be issued or otherwise documented by a ;
) cognizant engineer and transmitted with the changes for review and approval in accordance with PMP control procedures and applicable departmental procedures.
3.5.2 Changes from specified design inputs, such as design bases, regulatory requirements, codes and standards (including quality standards) are to be identified, approved, documented and controlled through PMP control procedures and applicable departmental procedures.
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() During preparation o' a design change, the responsible engineering l
l section is to' perform a review per'10CFR50.59 to verify compliance with the SAR and to determine if NRC approval of the design change is required. The review is to be document <:d, reviewed and approved by the PSC. In addition, any 10CFR50.59 evaluations shall also be reviewed and 1
approved by the SRC.
.3.5.4 1 i
Design changes are also to be submitted to the Superintendent Quality Control / Quality Engineering prior to plant implementation to verify the use of. appropriate quality codes, standards and inspection requirements in the design documents.
L 3.6 CORRECTIVE ACTIONS When design changes are made as a recult of design deficiencies or l
.(] errors, corrective actions (for significant conditions) are to be taken in accordance with Section 16.0 to determine the root cause and to l
I 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 at necessary. !
3.7 DESIGN RECORDS ,
The Manager Administrative Services is responsible for maintaining l
permanent records of the design documents for the construction and testing phases. In addition, he shall be responsible for maintaining ,
,k records of the upgrading or modification of these documents as described in this section. The controls for maintaining these records are j i
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established by specific procedures described in Section 17.0'of this manual. These records pro'vice the historic reference necessary for the ID: safe and reliable operation of Ad0, V
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5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS
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5.1 SCOPE 5.1.1 Instructions, procedures and drawings are provided for the control of those activities which affect quality and safety at ANO. Activities covered by written procedures include, as a minimum: administrative, general plant operations, start-up, shutdown, power operation and load changing, process monitoring, 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 l Regulatory Guide 1.33, Rev. 2 (2/78) unless otherwise noted in Table 1.
5.1.2 m
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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 l and/or qualitative criteria such as comparative workmanship samples to determine that important activities have been satisfactorily
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accomplished. Each procedura is to be sufficiently detailed so that a qualified individual may perform the required function (s) without direct l i ). supervision and is to include measures to document the activity being performed.
1 5.2.2 To assure the accomplishment of activities in accordance with approved instructions, procedures and drawings, each superviror 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 l
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 FSC prior to submittal of the procedures to designated department head for approval and subsequent issuance. Overall Administrative procedures (OP-1000.XXX & OP-60b0.XXX Series) are also reviewed by the NQ Organization to verify compliance to the QA Program requirements.
[ QA MANUAL OPERATIONS REV. 11 L DATE 7/22/89 SECTION: 5.0 INSTRUCTIONS, PROCEDURES PAGE 5-2 Arkansas Nuclear One AND DRAWINGS WNh-e-___.m_____m.m,
l 5.3.3 i Procedures and instructions are to be reviewed no less than every two
()
years, or prior to each use if utilized less frequently than once every j two years, to determine if changes are necessary to nieet NRC commitments and current ANO practices. \pplicable procedures (i.e those that relate to the incident cause) are to be reviewed follcwing an unusual incident such as an accident, unexpected transient, significant operator error or equipment malfunction. Applicable procedures are also to be reviewed following any modification to a plant system.
5.3.4 Drawings related to plant changes and modifications are controlled as described in Section 3.0 and 6.0 of this manual.
5.4 CHANGES TO PROCEDURES 5.4.1 O Changes or revisions to approved instructions, procedures and drawings are to be reviewed and approved by the same organizations or groups that performed the original review, unless otherwise noted in specific ANO procedures und controlled in the same manner as the original.
5.4.2 Temporary changes to approved procedures may be made in accordance with either the applicable Technical Specifications or approved procedures for those procedures w.ich are not Technical Specifications related. In the event of an emergency not covered by an approved procedure, operations personnel may take action, without obtaining approval 1, to minimize personnel injury and damage to the facility and to pr(tect health and s a f.ety, n
QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 i SECTION: 5.0 INSTRUCTIONS, PROCEDURES PAGE 5-3 Arkonsos Nuclear One AND DRAWINGS
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6.0 DOCUMENT CONTROL
,y
() 6.1 SCOPE The various quality program documents identified in Table 3 provide means to control the review, approval, issuance, use and retrievability of documents, such as calculations, computer codes, analyses, QA Manual Operations, SAR, instructions, procedures, specifications, manuals and drawings, including changes thereto, which prescribe activities affecting quality.
6.2 RESPONSIBILITIES 6.2.1 Each organization originating documents which prescribe activities affecting quality is responsible for the establishment of document control procedures which identify individuals or groups responsible for
. preparation, review, approval and maintenance of the document and for the
() issuance of these procedures to the affected individuals or groupr.
6.2.2 Review of these documents for concurrence with quality-related requirements is to be performed by the NQ Organization and/or by the appropriate reviewer as described in approved prncedures.
6.2.3 The Manager Administrative Services is responsible for the control and issuance of procedures (excluding NQ procedures), and revisions thereto, to assure distribution in accordance with approved procedures. The Manager Administrative Services is also responsible for the storage and ,
control of approved historical plant documents and the storage of
,m QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 6.0 DOCUMENT CONTROL PAGE 6-1 l Arkonsos Nuclear One l
E-_._______ _ _ _ _ _ _ i
l historical drawing records. The Generai Manager Engineering is responsible for the control and issuance of drawings and revisions
' vI} thereto to er dre that they reflect the as-built conditions of the plant.
6.3 IDENTIFICATION Documents are to be identified by a title descriptive of their purpose or applicability and marked or stamped as to their current status (Draft, For Information Only, Void, etc.) per departmental procedures. Revision status of a document is to be identified in document registers, distribution lists and/or within the revision record page/ block of the document.
- 6. 4 DISTRIBUTION Distribution lists and/or document registers are to be maintained by the i organization responsible for issuance of the document. These lists are to identify the revision status of the document and are to be reviewed
(}
and updated periodically by the responsible organization to maintain them These lists are available to individuals using the in a current status.
document to assure they are in receipt of the current document. These measures are to preclude the possibility of using outdated or inappropriate documents.
6.5 CHANGES 6.3.1 Changes to controlled documents are to be reviewed and approved by the same organizations which performed the original review and approval unless otherwise specified in departmental proceduras applicable to the affected activity.
(~ ' QA MANUAL OPERATIONS REV. 11
(_.-} DATE 7/22/89 SECTION: 6.0 DOCUMENT CONTROL PAGE 6-2 Arkansas Nuclear One
6.5.2'
?
/N .
("',) Obsolete or superceded documents are to be destroyed or marked to prevent I; inadvertent use in accordance with applicable document control procedures.
6.6 STORAGE Documents which affect quality are to be stored and maintained at the plant in permanent storage facilities and controlled as described in Section 17.0 of this manual.
6.7 VERIFICATION Nuclear Quality personnel, through their various levels of quality review, surveillance, audit, and inspection activities assure proper documents are being used and made available to those individuals performing the work.
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(' ) QA MANUAL OPERATIONS REV. 11 l
'- / DATE 7/22/89 SECTION: 6.0 DOCUMENT CONTROL PAGE 6-3 l
Arkonses Nuclear One
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- 9. 0 CONTROL OF SPECIAL PROCESSES 9.1 SCOPE lv) !
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I Suecial processes are to be controlled through the use of qualified personnel and approved procedures which meet the requirements of applicable codes, specifications, standards and other criteria stipulated in ANO licensing documents.
9.2 GENERAL 9.2.1 Special processes are those activities which require interim in process controls in addition to final inspection to ensure quality and include such activities as welding, nondestructive examination, heat treating, ;
coating, plating and chemical cleaning.
l 9.2.2 l \ b N.
Technically qualified personnel are to establish the prc,cedural and qualification requirements for those special processes not covered by existing codes or standards or where the QA Program requirements exceed the requirements of established codes or standards.
9.2.3 The requirements for welding and nondestructive examination are to comply with the applicable portions of the ASME Boiler and Pressure Vessel Code or for structural welds, the AWS Structural Steel Code 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.
O t ) QA MANUAL OPERATIONS REV. 11
'd DATE 7/22/89 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES PAGE 9-1 Arkansas Nuclear One l L-- __
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i 9.3 QUALIFICATION v
() 9.3.1 {
Special process procedures for welding and nondestructive examinations are to be qualified prior to use to ensure compliance with applicable codes, standards or specifications. These @ alifications are to be documented and also made available for review to the Code Inspector for activities on ASME items.
9.3.2 ersonnel responsible for the performance and verification of special processes are to be qualified and/or certified according to applicable codes, standards, specifications, regulatory guides and approved procedures. These qualifications and certifications are to be documented and made ava4m.le for review to the Code Inspector for activities on ASME items. Personnel qualification and/or certification records for a special process are to be regularly reviewed by the supervisor
( ) responsible for that special process to ensure that the appropriate docunents are up-to-date and personnel are periodically re qualified and/or re-certified in accordance with approved procedures.
9.4 RECORDS The results of special processes are to be documented, reviewed, approved and stored in accordance with appropriate approved procedures and as addressed in other sections of this manual.
QA MANUAL OPERATIONS REV. 11 lJ k DATE 7/22/89 SECTION: 9.0 CCNTROL OF SPECIAL PROCESSES PAGE 9-2 Arkonson fluclear Or;
9.5 VERIFICATION-Performance of special processes in accordance with applicable codes,
(
standards, specifications and approved procedures is verified by Nuclear Quality personnel through performance of their audit, review, surveillance and inspection activities.
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c) t QA MANUAL OPERATIONS REV.
DATE 7/22/89 PAGE 9-3 11 SECTION: 9.0 CONTROL OF SPECIAL PROCESSES Arkonses Nuclear One i
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l-i 10,0 INSPECTION L
v
) 10.1 SCOPE i Inspections relating to normal operating activities and inspections relating to operating activities comparable in nature and extent to those occurring during initial pint design and construction are to be controlled to assure that int,rections are performed in accordance with applicable design documents, codes, standards, specifications and i procedures. Inspection activities are to be in accordance with Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1, 10.2 GENERAL 10.2.1 Inspection activities relating to normal operating activities (Operational Inspections) include:
(1) Work functions associated with normal operation of the plant IV)
(2) Routine maintenance (3) Technical services routinely assigned to the on-site operating organization (4) Non-routine maintenance activities and minor modifications made by the on-site operating organization that are not comparable in nature and extent to related activities occurring during initial plant design and construction 10.2.2 Inspection activities relating to operating activities comparable in nature and extent to related activities occurring during design and construction (Construction Inspections) include:
/ QA MANUAL OPERATIONS REV. 11 C DATE 7/22/89 SECTION: 10.0 INSPECTION PAGE 10-1 Arkansas Nuclear One
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- 1) Non-routine maintenance, except as not d 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 (8/72); R.G. 1.37, (3/73); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77); R.G. 1.37, R.G. 1.94, Rev. 1 (4/76); and R.G. 1.116, l Rev. 0-R (6/76).
10.2.3 ,
Personnel performing inspection activities to verify quality are to be qualified as stated in Section 2.0 of this manual. When inspection I techniques require specialized qualifications or skills, personnel performing the inspect',on are to meet applicable licensing requirements, I codes and standards appropriate to the discipline involved.
10.3 CONTROL OF INSPECTIONS.
"T 10.3.1
[V 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 procedures are to contain, as a minimum, the following:
(1) Qualitative and/or quantitative acceptance criteria (2) Prerequisites for performing the inspection and any limiting conditions ]
(3) Identification of any special equipment and tools required to l l
perform the inspection (when accuracy requirements for inspections exceed the accuracy of normally available process ;
/~~N QA MANUAL OPERATIONS REV. 11
(_,) 0 ATE 7/22/89 SECTION: 10.0 INSPECTION PAGE 10-2 Arvonsos Nuclear One
l or measuring and test equipment, such additional accuracy requirements are to be specified within those inspection
( ; procedures) ,
v 1 (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 aid in documenting the inspection activity to assure quality ]
requirements have been met )i 10.3.2 Operational inspections are to be performed by qualified individuals other than.those who performed or directly cupervised 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.
^
( 10.3.2.1 L]'
I Operational inspections may be performed by second-line supervisory personnel or by other qualified personnel not assigned first-line supervisory responsibility for conduct of the work.
10.3.2.2 l
Construction inspections are to be conducted in a manner 5d...ilar to that associated with construction phase activities in accordance with applicable approved procedures.
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10.3.2.3 If individuals performing inspections are not part of the 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 Assurance or Quality Control / Quality Engineering prior to initiation of the activity.
10.3.3 If an inspectioc. determined to be required is isopossible 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 wt:.n control is inadequate without both.
10.4 INSPEC1 ION POINTS ls.s) 10.4.1 Inspection hold points are established for non routine maintenance procedures and design change packages (DCPs) by Engineering and reviewed by the Superintendent Quality 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 ,han 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.
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( " ) QA MANUAL OPERATIONS DATE 7/22/89 l SECTION: 10.0 INSPECTION PAGE 10-4 Arkansas Nuclear One
Work is not to proceed past-a designated in:rection hold point until signed by a qualified inspector or waived, in writing, by the
-_x
) Superintendent Quality Control / Quality Engineering.
v 10.4.2 Inspection hold points are inserted in procedures based upon safety significance, complexity of the item or activity, degree of standardization of the iteni or activity, past performance of the item or activity and the ability to verify quality by job-site testing.
10.4.3 Inspection responsibilities, requirements, information and acceptance criteria for the work activity are to be identified in appropriate, approved documents (e.g. procedures, checklists, etc. ).
10.4.4 m Fcr 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 waived by the Code Inspector.
[) ! QA MANUAL OPERATIONS REV. 11
A DATE 7/22/89 E
,,,,,,,, L SECTION: 10.0 INSPECTION PAGE 10-5
10.5 DOCUMENTATION 1 ) 10.5.1
~s 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 I procedures, instructions or drawings to verify design requirements; show compliance with acceptance criteria or identify the cause of rejected items; and identify the appropriate inspection personnel approving the l results.
10.5.2
] Records are to be maintained in accordance with approved procedures and Section 17.0 of this manual. Inspection results on ASME Code items are available to the Code Inspector for his review.
,m ;
10.5.3 (v) l 1
The results of inspection and monitoring activities are periodically evaluated per approved procedures and the results documented to determine whether the individual inspection programs demonstrate that the plant can be operated safely and as designed.
10.6 NONCONFORMANCES Nonconforming items found as a result of inspection and monitoring activities are identified, segregated and dispositioned in accordance with approved written procedures and Section 15.0 of this manual.
Rework, repair or replacement performed after completion of inspections requires re-inspection to the extent necessary to determine acceptability to established criteria.
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'h A QA MANUAL OPERATIONS REV. 11 DATE 7/22/89
... ._.. L sEC110N: 10.0 1NSeeCTION eacE 10-e !
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I L 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT m) 12.1 SCOPE i
l 12.1.1 j l
A program is established to assure that devices used for measurements, tests and calibrations are identified, controlled and calibrated against reference standards to assure that accuracy is maintained within the limits specified by the inspection or test requirements. Control of measuring and test equipment is to comply with the applicable provisions of Regulatory Guide 1.33, Rev. 2, pertaining to measuring and test equipment, unless otherwise noted in Table 1.
12.1.2 This section is generally applicable to' chemical and radiochemical equipment, except for paragraphs 12.3.3, 12.3.4 and 12.4.2. The controls for the calibration of chemical and radiochemical measuring equipment are
) to comply with the provisions of Regulatory Guide 1.33, Rev. 2, Appendix A, Section 10.0, and performed in accordance with chemical and radiochemical control procedures.
12.1.3 This section does not apply to rulers, tape measures, levels or other such devices where normal commercial practices provide adequate accuracy.
12.2 RESPONSIBILITIES 12.2.1 The cognizant superintendents / group supervisors are responsible for establishing and maintaining lists of measuring and test equipment under
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(Vl QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 12.0 CONTROL OF MEASURING PAGE 12-1 Arkansas Nuclear One AND TEST EQUIPMENT
their control that require periodic calibration and for the calibration of this equipment, as assigned within approved procedures.
~A 12.2.2 The cognizant supervisor is responsible for identifying measuring and test equipment required for the activity and assures that the devices are used only by qualified personnel.
12.2.3 Personnel perfoming the activity are responsible for utilizing only properly. identified and calibrated measuring and test' equipment when performing inspec.tions and tests for record.
12.2.4 The NQ Organization is responsible for monitoring test equipment control and use in order to verify compliance with the program.
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12.3 GENERAL 12.3.1 Calibration procedures are to be established for each type of measuring and test equipment. These proceaures are to conform to recognized codes and standards and to local, state and federal regulations and are to be i referenced on the calibration reports / logs.
12.3.2 Measuring and test equipment are to be properly controlled, calibrated and adjusted at specific intervals or prior to use to assure the t necessary accuracy of calibrated equipment. Calibration intervals are to 7 QA MANUAL OPERATIONS REV. 11
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DATE 7/22/89 SECTION: 12.0 CONTROL OF MEASURING PAGE 12-2 Arkonsos Nuclear One
be based upon the type of equipment, manufacturer's recommendations, stability and reliability characteristics, required accuracies, use and other conditions affecting calibration. f (a) 12.3.3 Reference standards used in the calibration of measuring and test {
equipment are to be traceable to '.he National Institute of Standards and )
Technology, or if nonexistent, to accepted industry or ANO standards.
Reference standards are to have an accuracy at least four times that of the measuring and test equipment. In any instance 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, b 12.3.4 When measuring and test equipment are found to be out of calibration, an !
evaluation of the validity of previous inspection or test results and the acceptability of items previously inspected or tested is to be made and documented by written report in accordance with approved procedures. If any piece of measuring or test equipment is consistently found to be out of calibration, it is to be repaired or replaced.
12.3.5 i
l Re-calibration per approved procedures is to be performed when the accuracy of either installed or calibrated equipment is questionable.
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- l. 12.4 EQUIPMENT IDENTIFICATION
(,,)
,a 12.4.1 Measuring and test equipment lists are to contain sufficient information to uniquely identify each item listed cod 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. t 12.4.2 Items listed on measuring and test equipment lists are to be tagged, labeled or otherwise identified per approved procedures in such a manner that clearly identifies the equipment and their calibration status and provides traceability to the calibration records.
12.4.3 Measuring and test equipment found to be out of calibration is to be
,-~
(% tagged and segregated from acceptable equipment in accordance with !
approved procedures until repaired and/or re-calibrated.
12.5 RECORDS Calibration documentation is to be maintained to verify calibration status, condition, accuracy and out-of-tolerance trends of the equipment. ;
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13.0 HANDLING STORAGE AND SHIPPING l ) 13.1 SCOPE v
I 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 l, prevent damage, deterioration or loss of the item. Activities are to comply with the provisions of Regulatory Guide 1.38, Rev. 2, unless otherwise noted in Table 1.
13.2 GENERAL
]
13.2.1 Instructions for preservation are to be provided for items subject to deterioration or dar.. age 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 special packaging instructions and maintenance procedures.
13.2.2 Procurement documents assure that any special cleaning, preserving, handling, packaging or shipping requirements for purchased material or equipment are taken into account.
13.2.3 l
For critical, sensitive, perishable or high value articles, recommendations for their handling, storage, packaging, shipping and preservation are to be requested from the supplier per the procurement REV. 11
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V A QA MANUAL OPERATIONS DATE 7/22/89 e^ce 13-1
- * *' L sec11o": 13.o "A"o'1"c. sioaace ^"o SHIPPING l
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documents and furnished to the plant prior to or upon receipt of the
, items at the plant.
O 13.3 SHIPPING CONTROLS 13.3.1 Shipping requirements are to be specified in the procurement documents.
Suppliers' compliance with these requirements are to include controls to assure that items are complete and assembled as required; items have been preserved and packaged in accordance with the procurement documents; items have been marked and identified in accordance with specifications and procurement documents; items have been loaded for shipment in such a manner as to prevent damage; and required documentation is complete and furnished in accordance with the procurement documents.
13.3.2
, Special nuclear material and sources are to be shipped and stored as
) specified in the operating licenses and other appropriate regulatory documents. The Superintendent Radiation Protection and Radwaste is responsible for assuring that radioactive sources and instruments containing radioactive sources are stored and handled per these requirements and approved procedures. The Superintendent Radiation Protection and Radwaste is also responsible for assuring that low-level waste 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 procedures, is shipped, stored and handled per these requirements and the appraved procedures.
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,, 1 ij QA MANUAL OPERATIONS REV. 11 l DATE 7/22/89 l SECTION: 13.0 HANDLING, STORAGE AND PAGE 13-2 l A/konsos Nuclear One SHIPPING l
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13.4 RECEIVING
/m j 13.4.1 Materials and equipment are to be received at the plant per approved procedures and subjected to a receipt inspection in accordance with Section 7.0 of this manual. As part of the inspection activity, received materials and equipment are to be inspected for damage, deterioration, j I
cleanliness and proper identification and markings per approved procedures for receipt inspection.
1 13.4 2 Results of the receiving inspection and disposition of the material or )
equipment are to be documented on receiving inspection records.
Nonconforming items are to be handled in accordance with approved j procedures and Section 15.0 of this manual.
13.5 STORAGE CONTROLS
,m
(.
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 i
l Storage control procedures are to be established which include, as a !
1 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 )
i snelf life.
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QA MANUAL OPERATIONS REV. 11 l tL2' DATE 7/22/89 SECTION: 13.0 HANDLING, STORAGE AND PAGE 13-3 Arkansas Nuclear One SHIPPING i l t__ - . _ _ _ . _ _ . _ _ - __________-__a
J 13.5.3
[] Only items which have completed the receiving process are to be placed in
~'
a controlled storage area. Records of the items' location (s) are to be provided by the Superintendent Materials Management (see paragraph 13.3.2 ,
for control of radioactive sources, low-level waste material and SNM) to )
identify those items currently in storage and to facilitate inspection and maintenance planning. Issuance of items from storage for installation or use is to be documented and controlled in accordance with 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 contrci 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 documents and approved procedures to protect the quality of items
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QA MANUAL OPERATIONS 13.0 HANDLING, STORAGE AND REV. 11 DATE 7/22/89 PAGE 13-4 SECTION:
Arkansos Nuclear One SHIPPING
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susceptible to handling damage. Special tools and equipment are to be provided to handle these items and are to be controlled and maintained
,s
'; i per written procedure to assure safe and adequate handling.
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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 j 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.
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14.0 INSPECTION, TEST AND OPERATING STATUS
,n 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, 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.
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14.2 EQUIPMENT CONTROL 14.2.1
- Prior to removal of equipment, components or systems from service for maintenance, modification, repair, test or inspection activities, permission is to be received and documented from the appropriate Supervisor Shift Operations. The Supervisors Shift Operods is are to assure that the item can be released without affecting plat,L safety.
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 Arkonses Nuclear One bER Tb5
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14.2.2 (j The status of equipment, components and systems during these activities is to be identified in accordance with approved procedures / instructions, which contain, as a minimum, the following:
(1) Methods for control of equipment to maintain personnel and reactor. safety and to avoid unauthorized operation of equipment or systems (2) The use of markings or other suitable means to indicate the status of activities being performed upon individual items.
Suitable means are to include identification numbers which are traceable to records or to the status of these activities (3) Provisions for the identification of items which have satisfactorily passed the r2 quired activities. In cases where required documentary evidence is not available, the associated equipment or system is to be considered nonconforming and fD V
handled in accordance with Section 15.0 of this manual i
(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 1
14.2.3 ,
1 J
When entry into a closed system is required, control measures are to be established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed.
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1 QA MANUAL OPERATIONS REV. 11 U DATE 7/22/89 SECTION: 14.0 INSPECTION, TEST AND PAGE 14-2 Arkonsos Nuclear One OPERATING STATUS
14.2,4 l [ -During maintenance or modification activities, certain portions of systems, as identified in approved procedures, may be subject to potential contamination with foreign materials. To prevent such contamination, control measures, including measures for access control, are to be established. Immediately prior to closure, an inspection is to j be conducted to assure cleanliness and the result of such inspection is j to be documented.
14,2.5 If temporary modifications (such as temporary bypass lines, electrical jumpers, lifted electrical leads and temporary trip point settings) are required for a system or piece of equipment, they are to be performed in accordance with approved procedures. A status log is to be maintained by the Supervisors Shift Operations, identifying the current status of such 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 returned to service, the appropriate Supervisor Shift Operations is )
notified and initiates the proper operation procedures. Testing of the j equipment or system for functional acceptability is to be in accordance with Section 11.0 of this manual and documented to verify current status -I of the item.
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14.2.7 l Equipment, structures and systems found to be nonconforming as a result
- of an activity are to be handled in accordance with approved procedures and Section 15.0 of this manual.
14.3 MAINTENANCE CONTROL 14.3.1 In addition to the requirements and controls identified in subsection 14.2 of this manual, a maintenance program is to be planned and scheduled throu0h the appropriate Manager Maintenance to assure that l
the safety of the plant is not compromised nor the Technical Specifications violated. Maintenance activities are to be performed per approved procedures and instructions and conducted in a manner to assure quality at least' equivalent to that specified in the design documents, material specifications and inspection requirements. As experience is gained in operation of the plant, routine maintenance may be altered to
,m
- ) improve equipment performance and procedures for repair of equipment are
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to be improved as directed by the appropriate Manager Maintenance.
l 14.3.2 A preventive maintenance program, including procedures and instructions for systems, structures and components, is to be established and 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 appropriate Plant Manager and is implemented by l
qualified maintenance personnel in accordance with approved procedures 1
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and instructions which specify the work activities, acceptance requirements and the control measures to assure adequate quality. When 4,
) equipment malfunctions occur, 'he cause is to be promptly determined, evaluated and recorded per apptaved procedures and Section 16.0 cf this manual.
14.4 OVERALL PLANT STATUS 14.4 1
! The Supervisors Shift Operations are provided sufficient knowledge of the overall plant status of equipment, structures and systems to control l operation of the plant in a safe manner. The shift operators are to mainta.in 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 en succeeding shif ts is conducted in I accordance with approved procedures. These procedures include documented s_-)
turnover action appropriate to the duty station acknowledging the status of the nuclear power plant, its structures, systems and components (including design changes / modifications which may affect the performance of their duties) and transfer of authority.
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15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS n
15.1 SCOPE s )
_(
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, riocumentation, segregation, technical review and disposition of a nonconforming item.
15.2 GENFRAL 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 identified within approved procedures. If the nonconformance is determined to be a Technical Specification violation and/or reportable to the NRC, see subsection 16.5.
15.2.2 Nonconforming items are to be identified by tagging, marking or as otherwise identified per approved procedures to control further processing ir, when physical segregation is not practical, to prevent inadvertent use or installation of the item. Nonconforming items are to be segregated from acceptable items unless they are currently installed l or their size, weight, configuration, etc., makes it impractical to move i to a segregated area. Tags and/or markings are to remain on the item l until the disposition is complete per approved procedures. i i
QA MANUAL OPERATIONS REV. 11 4
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SECTION: 15.0 NONCONFORMING MATERIAL, PAGE 15-1 :
Arkanscs Nuclear One PARTS AND COMPONENTS i w_ _--
L l r 15.2.3 w(7 ,) Reports cf nonconforming items are to identify the group responsible for dispositioning the nonconformance. The assigned individual within the responsible group is to evaluate the nonconformance and confer, as appropriate, with interfacing groups to determine a recommended
]
disposition. The disposition for materials, parts, components and as '
applicable, services (including computer codes), which may be reject, rework, repair or use-as-is, and any actions taken/ required to be taken I 1
- 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 in'dividual/ group identified within approved procedures. If the review group or individual cannot agree with the assigned individual on the disposition, either the Director Nuclear Operations or the appropriate General aanager, is to decide. For a repair or use-as-is disposition, a cognizant individual knowledgr.able in the design requirements for the
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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 cre !
to be documented and become part of the permanent records for the item.
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QA MANUAL OPERATIONS DATE 7/22/89 SECTION: 15.0 NONCONFORMING MATERIAL, PAGE 15-2 l Arkansos Nuclear One PARTS AND COMPONENTS i
1 i
- 15. f. 6 j l
.s l
- ') bpon completion of the disposition, the nonconformance report is to j receive an independent review in accordance with approved procedures, for concurrence or possible assignment of additional actions pertaining to the disposition. j 1
15.2.7 1
For ASME Code,Section III, Division 1 materials, parts and components dispositioned repair or use-as-is, the nonconformance report is to be subject to review and concurrence by the Code Inspector. ,
15.3 SUPPLIER NONCONFORMANCES 15.3.1 Procurement documents are to contain requirements for the vendor / contractor to identify to AND those items which violate a
(;t technical or material requirement of the procurement document and which.
results in a disposition of repair or use-as-is. All such nonconformances are to be reported to ANO for evaluation and acceptance.
The vendor / contractor is to document such nonconformances on its applicable nonconformance report which is to be included in the final documentation package submitted to ANO, in accordance with the procurement documents.
15.3.2 Upon receipt of items at the plant, Nuclear Quality personnel are to review any nonconformance reports in the documentation package to ensure the nonconforming items have been properly dispositioned and accepted by ANO.
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15.4 RECORDS l
'xj ' 15.4.1 Upon completion of disposition and verification activities, the completed nonconformance report, and related dc,cuments generated to ensure proper disposition and resolution of the nonconformance, are to be forwarded to and maintained by the Document Control Center.
15.5 DEFICIENCY TRENDING The Superintendent Operations Assessment is to maintain and issue a trending report . at least quarterly, of nonconformances to the Vice President Nuclear fo. review.
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(~ QA MANUAL OPERATIONS DATE 7/22/89 SECTION: 15.0 NONCONFORMING MATERIAL, PAGE 15-4 Arkansos Nuclear One PARTS AND COMPONENTS
, 16.0 CORRECTIVE ACTION 1
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(,)l 16.1 SCOPE 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 nonconformances are promptly identified arid corrected. In the case of significant conditions adverse to safety, this system is to assure that tF.e cause of the condition is determined and corrective action taken is i documented and reported to appropriate levels of management for i independent review.
16.2 GENERAL 16.2.1 When deviations, dei;c.encies, malfunctions, nonconformances or other abnormal occurrences or conditions are encountered, they are to be r~x
() reported to responsible authorities for review and disposition in accordance with apr.u , procedures.
16.2.2 Cognizant supervisors are to review discrepancies discovered during the l course of plant operations and take appropriate action to resolve the discrepancies. For conditions adverse to safety, they are to initiate corrective action to preclude recurrence. For significant conditions adverse to safety, they are to initiate action to identify their root causes and take necessary corrective action to preclude repetition.
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 16.0 CORRECTIVE ACTION PAGE 16-1 Arkansas Nuclear One
16.2.3 i
)- Evaluation of the corrective action is to be performed by the individual / group identified within approved procedures to determine its adequacy and completeness and to assure the need for additional corrective action. If the corrective action is acceptable, follow-up action to verify implementation, documentation and close-out of the corrective action commitments is to be performed per approved procedures.
16.2.4 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 pnrchase contract and, in the opinion of n
( j 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 action to be taken. Results of the reappraisal, together with a request for specific corrective actions, b.e to be transmitted to the vendor. If the vendor does not improve his quality assurance system and products as requested, the Superintendent Quality Assurance is to remove the vendor from the Qualified Vendor List (QVL) in accordance with approved procedures, t ^5 QA MANUAL OPERATIONS REV. 11
't) DATE 7/22/89 SECTION: 16.0 CORRECTIVE ACTION PAGE 16-2 Arkansas Nuclear One
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ . . _ _ _ _ _ _ _ _ _ _ __ _ _ _ __ J
16.4 SIGNIFICANT CONDITIONS
- ) Significant ccnditions adverse to safety are to include, as a minimum, the following
(1) Conditions that have a direct adverse effect on the safety of the plant per the plant Operating License and Technical Specifications (2) Conditions that have caused the uncontrolled release of radioactive materials (liquid, solid, gaseous or air particulate) to the environs (3) Adverse quality trends which could lead to unsafe plant operations 16.5 REPORTABLE EVENTS 16.5.1 When significant conditions adverse to safety are discovered, the lQ O
1 responsible Department Head and Licensing Department are to evaluate the condition and determine if it is an event reportable to the NRC.
16.5.2 Upon determination that an adverse condition is reportable, the Manager Licensing ensures that the appropriate report is initiated and subsequently transmitt d to the NRC.
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1' 16.5.3
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v Upon completing the final draft of the report, the Manager Licensing forwards the report to the General Manager Technical Support and Assessment for final approval. The PSC reviews Root Cause and Corrective Action plans for reportable events through its review of significant Condition Reports.
16.5.4 l The Licensing Department is responsible for transmitting approved reports to the NRC within the time period specified in the Technical Specifications and approved procedures.
16.6 VERIFICATION Verification by surveillance or audit of the effective implementation of corrective actions is to be periodically performed and documented by Nuclear Quality personnel. Audits are to be performed in accordance with
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Section 18.0 of this manual.
[\~ /) QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 16.0 CORRECTIVE ACTION PAGE 16-4 Arkansas Nuclear One
- l. 1 17.0 QUALITY ASSURANCE RECORDS j
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17.1 SCOPE 17.1.1 Documentation covering design, construction, procurement, fabrication, 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 reviews, inspections, tests, maintenance, audits, material analyses; monitoring of work performance; qualification of personnel, procedures, n
( i and equipment; historical drawings, specifications, personnel exposure,.
wJ engineering reports, calculations, procure;nent documents, calibration procedures and reports, nonconformance reports, corrective action reports, correspondence and related records pertinent to quality as defined in approved procedures.
17.2 RESPONSIBILITY 17.2.1 The Manager Administrative Services, is responsible for the establishment, <
implementation and maintenance of the records management program to be used throughout the operational life of ANO End for ensuring that documentation retention requirements comply with applicable Technical Specifications, codes and regulations.
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1 17.2.2
,ls_g) 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 subsequen't storage and retention by the Document Control Center.
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 outlired in Section 18.0 of this manual.
17.3 DOCUMENTATION RETENTION .
17.3.1 Lifetime Quality Assurance Records
,.m
(, ,) 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
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-2 Arkansas Nuclear One j
17.3.1.2
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- - Lifetime quality-related. records are to be maintained for the life of the i particular item while it is installed or' stored for future use as j prescribed in approved procedures.
I' 17.3.2 Non-Permanent Quality Assurance Records 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 ,
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17.3.2.2 Non permanent records are to provide evidence that an activity was performed in accordance with applicable requirements and be retained for specified periods as directed by the approved procedures for document I retention and disposition.
17.3.3 Categoties of permanent and non permanent records to be maintained and their appropriate retention periods are described in approved procedures.
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17.3.4
,,m The Superintendent Quality Assurance is responsible for receiving, (a) inspecting and authenticating such documents as directed by approved l 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.
17.4 STORAGE 17.4.1 Permanent records are to be microfilmed and the microfilm stored within a controlled area at AND 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 env bonment as
'~
recommended by the manufacturer and approved procedures.
17.4.1.2
)
A list is to be prepared in accordance with approved procedures designating those personnel who have access to the storage files.
17.4.2 Records storage systems are to provide for the accurate retrieval of information without undue delay and be sufficient to control and account for records removed from the storage facility, QA MANUAL OPERATIONS REV. 11
[ DATE 7/22/89
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17.5 RECORDS INDEXING aND RECEIPT CONTROL
, ) 17.5.1 t.s Indexing methods and systems for quality related records are delineated 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: i (1) Establishment of a records list designating the required quality-related records (2) Establishment of a system designating criteria for document inspection to assure that records are complete, legible and received in good condition (3) A file system to indicate which quality-related documents have been received f'
(
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17.5.2.1 Implementation of receipt control requirements for storage is the .
! responsibility of the Manager Administrative Services.
17.6 FINAL DISPOSITION The Manager Administrative Services is responsible for disposal of quality-related records in accordance with approved procedures for document retention and disposition, which permits periodic purging of I records retained past their required retention date.
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18.0 AUDITS y,
18.1 SCOPE (w .-)
18.1.1 A comprehensive system of planned and periodic audits is provided to ensure and verify compliance with all aspects of the administrative controls and quality assurance program. Audits are to be planned and l performed in accordance with written procedures, plans and checklists and are to conform tc 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 The audit program is to include provisions to determine the compliance with and effectiveness of the QA Program in controlling structures, systems, components and activities in accordance with the rules set forth in the codes, standards and regulations identified in the Introduction of
()
this manual.
18.2 AUDIT PERSONNEL .
18.2.1 l The Superintendent Quality Assurance is assigned auditing responsibility 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 the activity being audited.
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,m ij QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 18.0 AUDITS PAGE 18--1 Arkansas Nuclear One
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3
'18.2.2
( ) Auditors assigned auditing responsibilities are to have experience and f u/ I i training commensurate with the scope, complexity and/or special nature of the activities to be audited. When audit assignments are made, considerations are given to special abilities, specialized technical training, prior pertinent expertise, personal characteristics, education and capability. If r:0 one within the NQ Organization meets these 3 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.
19.2.3 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 (a
c
) (2) Review and study of codes, standards, procedures and I wJ 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 l beginning of each year by the NQ Organization and approved by the Superintendent Quality Assurance, General Manager Nuclear Quality and the SRC.
( p.) QA MANUAL OPERATIONS REV. 11 l V DATE 7/22/89 SECTION: 18.0 AUDITS PAGE 18-2 l
'- Arkansas Nuclear One I
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18.3.2 m
(J I 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 within ANO.
18.3.3 Audits of vendor / contractor activities are to be scheduled as identified in paragraph 7.3.3 of this manual. These audits are to evaluate and verify their quality assurance program, procedures and activities, to assure compliance with the procurement documents and to verify they periodically review and audit their suppliers' quality assurance programs.
18.3.4 Periodic reviews of the audit programs are to be performed by the SRC or e-w !
( ,s) their appointed management representative at least semiannually 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 oth6rwise noted in Table 1.
l 18.3.5 i Regularly scheduisd BJdit5 ) Day b0 typpl0mented, a5 required, to cover unforeseen events or r. hanged requirements, I
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18.4 AUDIT IMPLEMENTATION
,'l 18.4.1
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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 used to ensure depth _ and continuity of audits in order to verify that those procedures and instructions issued to control the audited activity are adequate.
18.4.2 Upon completion of an audit, a written report is to be prepared which includes at least the following items:
(1) Description of audit scope and date (2) Identif1 cation of the auditor (s)
(3) A summary of audit results (4) Details of nonconformances or programmatic deficiencies (5) Recommendations for correcting nonconformances. or improving the QA Program, as appropriate
.18.4.3 Deficiencies identified as a result of an internal audit are to be recorded on an Audit Finding Report (AFR) by the auditor and issued to the Department Head responsible for the area audited for corrective j action. The Department Head or the assigned designee is to provide
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prompt torrective 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
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l' conducted in the deficient areas to verify proper and timely implementation of corrective action commitments. Follow-up actions are
, s i uj to be documented on the AFR. J
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i 18.4.4 .)
l Internal audit reports pertaining to plant operations acthities are to be independently reviewed by the SRC to determine if additional corrective actions need to be initiated to assure continued safe operation of ANO. Internal audit reports pertaining to other than plant operations activities are to be independently reviewed by the SRC. In addition to this review, the audit reports are to be distributed, as a minimum, to the General Manager Nuclear Quality, Superintendent Quality I l
Assurance and appropriate levels of management having responsibility in j the area audited to assure their awareness of the findings. l l
1 18.4.5 Audit results and findings related to external audits conducted by QA (mg 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 organization 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 forwarded to the Document Control Center for storage in accordance with Section 17.0 of this manual.
b v QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: 18.0 AUDITS PAGE 18-5 Arkansas Nuclear One
18.6 NUCLEAR FUEL AUDITS
() ANO delegates to Entergy Services Inc. (ESI), a wholly-owned subsidiary of Entergy Corporation, 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 ESI Quality Assurance Services 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. ESI also conducts audits of component suppliers as deemed necessary by the ESI Manager, Quality Assurance Services to l ensure the quality of the fuel. Formal audit reports are issued by ESI to document their audit activities and to identify nonconformarces or ,
other . items requiring action by the fuel fabricator. Resolution of nonconformances or other items requiring action is verified by ESI and documented in follow-up reports. The AN0 Superintendent Quality Assurance is on distribution for all audit and follow-up reports. These audit reports are to be forwarded to AND and stored in accordance with Section 17.0 of this manual.
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( ) QA MANUAL OPERATIONS REV. 11 ,
\~' DATE 7/22/89 i
SECTION: 18.0 AUDITS PAGE 18-6 Arkonnos Nuclear One l
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TABLE 3 e s QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION v
) MANUALS LIST
- 1. Quality Assurance Manual Operations The Quality Assurance Manual Operations establishes the policies and guidelines of the QA Program for ANO. This program is to be followed by all organizations involved in safety related work I applicable to ANO.
- 2. Overall Administrative Procedures The Nuclear Organization employs a system of procedures designated as Overall Administrative Procedures (0P-1000.XXX or OP-6000.XXX series). These procedures implement the QA Program requirements and control safety-related activities. Overall Administrative Procedures and changes thereto are prepared by the responsible '
department, reviewed by the Plant Safety Committee and approved by
/ \
( ) the Vice President Nuclear. The procedures <and revisions are also x._ /
reviewed by the Superintendent Quality Assurance to assure that the QA Program commitments are met. Review and approval of NQ administrative procedures is described in paragraph 4 below.
- 3. Departmental Procedures Each department (excluding Nuclear Quality) within the Nuclear Organization has developed procedures in support of the Overall Administrative Procedures and the QA Program. These procedures provide technical and administrative instructions to the respective departments to aid in implementing their responsibilities within the QA Program. Each Department Head is responsible to perform a review ]
of their procedures to assure conformance with the QA Program.
l'
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p A QA MANUAL OeERA110NS REv. 11 DATE 7/22/89 l 1
I
. .. .,. . b. SECTION: TABLE 3 PAGE T3-1 l
>~
Procedures required by the Technical Specifications are reviewed by the Plant Safety Committee. Department procedures are approved by the appropriate Department Head.
- 4. Nuclear Qualitv Procedures The NQ Organization employs a system of procedures developed to assure proper implementation of the QA Program. These procedures provide technical and administrative instructions to the NQ staff to aid in implementing their responsibilities within the QA Program.
These procedures are reviewed / approved by the Superintendent Quality Assurance and/or Quality Control / Quality Engineering and the General Manager Nuclear Quality.
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i l
1 l
REV. 11 I QA MANUAL OPERATIONS (O / DATE 7/22/89 PAGE T3-2
)
SECTION: TABLE 3 j Arkansas Nuclear One l l
I l
APPcNDIX A
. ( ;
QUALITY PROGRAM FOR TRANSPORT PACKAGES LJ
1.0 INTRODUCTION
1.1 The quality program for transport packages containing radioactive material is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in 10CFR71, Subpart H - Quality Assurance, subject to exceptions noted in Attachment A to this Appendix.
1.2 Attac.. ment A to this Appendix identifies the applicability of each section of the Quality Assurance Manual Operations to the Quality Program for Transport Packages.
1.3 Attachment B to this Appendix contains the Quality Assurance Program Approval document which shows NRC approval of this program on January 23, 1985.
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1 QA MANUAL OPERATIONS REV. 11 DATE 7/22/89
! SECTION: APPENDIX A - QUALITY PROGRAM PAGE AA-1 !
f Arkonsos Nuclear One TRANSPORT PACKAGES l
l' l L l
$ ATTACHMENT A
' ~
The following sections of the most currently approved revision of the QA Manual Operations will be applied as stated below (Note specific paragraphs are to revision 10 paragraph numbers which could change during subsequent revisions).
Section 1 -
Applicable Section 2 -
Applicable Section 3 - Not applicable. ANO will use only licensed packaging which has been designed under a QA program which has been submitted to the NRC for approval.
Section 4 -
Applicable (m) s_-
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 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~10CFn71, Appendix H Section 71.119 which is a restatement of 10CFR50, Appendix B Criterion 9.
/ QA MANUAL OPERATIONS REV. 11 V DATE 7/22/89 SECTION: APPENDIX A - QUALITY PROGRAM PAGE AA-2 Arkoneos Nuclear One TRANSPORT PACKAGES
I i L ,
L ATTACHMENT A (continued) l 10CFR71 Appendix H )
: 7.. \
- l. G 1
i Section 10 - Applicable l Secticn 11 - Not applicable. ANO will not be testing the package in the context of 10CFR71, Appendix H, Section 71.123 which is a restatement of 10CFR50, Appendix B Criterion 11.
Section 12 - Generally applicable except for paragraph 12.3.4. This paragraph only applies to Radiation Protection and Radwaste measuring and testing equipment that is used to calibrate other devices (used as a standard). Radiation Protection and Radwaste survey equipment is response checked prior to each use.
Section 13 - Generally applicable except for paragraph 13.5. ANO does
.i l not " store" packages, therefore the storage section does not apply.
Section 14 - Not applicable. See Section 11 comments above.
Section 15 - Generally applicable except for references to the various types of dispositions in paragraphs 15.2.3 to 15.2.5.
Nonconforming material or equipment will be returned to the vendor or will be replaced.
Section 16 - Applicable Section 17 - Applicable Section 18 - Applicable
,m_
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QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: APPENDIX A - QUALITY PROGRAM PAGE AA-3 Arkansos Nuclear One TRANSPORT PACKAGES i
m___
ATTACHMENT B 73
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1 AMSOWAL SER I u.a. NUCLEAR REGULATORY COMMi$410N f une Fonu s,,
QUAUTY ASSURANCE PROGRAM APPROVAL Revision sEn i'g *m - .
FOR RADICACT!YE MATERIAL PLOKAGES l 4
R
( Pursuem to the Atomic Energy Act of19R as amended the $nergy Reorganiastion Act of1974.as emanced.and THie 10. Cooe of Feoeral Regulations Ch5Dief 1. Part 71, and m reliance on glatements and representations heretofore maOG in item a by the person namedin item l 2. ine ousiv Assursace Prog sm iaentified in nem a e nereo, soprovec. The approvai ns issued to satisty tne reevirements of section g-g 71.101 of 10 CFR Port 71 The approvsl e subiect to sh appiscaem rules regulations. anc oroers of the Nucieer Regumiory Commession g.
no. or herester in e*, ct and to any conainons spechwa besow. ,
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a sxpiRation oats 3 naus Arhem power & tioht temoany January 31, 1990 t g
(l g $fREtt ADDRESS a poc at avusea n A P.O. Box 551 i d: crry I stata u m coot H- Little Rock i AR I 72203 71-0341 1 E
% a cuaur, assuna~ca eaoonau apucation cattisi Auoust 27, 1979 and January 4, 1985 fg e cohomous ly i l,
< p t' Activities conducted under applicable criteria of Appendix B of 10 CFR i
- 4. Part 50 to be executed in accordance with Attachment A to QA Manuel )
(AP&L-TOP-1 A) for Arkansas Power Station Nuclear One, Units 1 and 2 R;
(Docket hos. 50-313 and 50-368) with regard to transportation packages, j
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CharlesE.[MacDonadd JAN 2 31995 DATE g
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il CMEF TRANSDORT ATION CERTIFICATION BRANCH il Dfv!SiON OF FUEL CYCLE AND MATERaAL SAFETY Of fiCE OF NUCLE AR MATE 81;AL 5as ETY ANO SAFEGUARDS- ... - ~ ,- - -,--. - - - ~ ~ - ---w-q,,n,-..
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'l f b l QA MANUAL OPERATIONS REV. 11
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DATE 7/22/89 SECTION: APPENDIX A - QUALITY PROGRAM PAGE AA-4 i TRANSPORT PACKAGES Arkonsos Nuclear One
I APPENDIX B' l
QUALITY PROGRAM FOR FIRE PROTECTION i
)
1.0 INTRODUCTION
j 1.1 The fire protection program was developed to define the organizational responsibilities, procedural controls, fire brigade staffing and training and the quality assurance ,
provisions that have been established for the nuclear plant.
The overall objective of the fire protection program is to minimize both the probability and consequences of postulated fires and to maintain the capability to safely shut down the plant if a fire should occur.
1.2 The scope of the fire protection program includes those fire
, protection and detection systems, and those structures and V components (such as fire doors, fire dampers, and penetration seals) which, as identified in the plant's fire hazards unalysis report, are required to restrict the damage caused by a single exposure fire to safety-related equipment and equipment required to achieve and maintain safe plant shutdown to within those limits set forth in Section 1 of Appendix R to 10CFR50.
1.3 The quality program for fire-protection is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in BTP-APCSB 9.5-1, Rev. 2, July 1981, Guidelines for Fire Protection for Nuclear Power Plants, subject to exceptions noted in this Appendix.
! ) QA MANUAL OPERATIONS REV. 11 DATE 7/22/89 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-1 Arkonson Nuclect una FOR FIRE PROTECTION
k 1.4 With respect to regulatory commitments, ANO is committed to implementing the requirements of the following, subject to
( ,) exceptions noted in this Appendix:
- 1. '10CFR50, Appendix A, General Design Criterion 3 - Fire Protection.
- 2. Specific sections of 10CFR50.48, Fire Protection and 10CFR50, Appendix R, Fire Protection for Nuclear Power Facilities Operating Prior to January 1,1979. These sections are as follows:
III.G. Fire Protection Safe Shutdown Capability III.J. Emergency Lighting III.L. Alternative and Dedicated Shutdown Capability III.O. Oil Collection System for Reactor Coolant Pumps (3) 1.5 Other fire protection commitments are contained in the following references and documents:
- 1. Facility Operating License (s) including Technical Specification (s) i
- 2. Safety Analysis Reports (SAR)
- 3. Fire Protection Safety Evaluation Reports (SER)
- 4. Regulatory correspondence to and from the NRC (includes applicable NRC generic letters and ' exemption letters for ANO), identified in Division 4.0 to the Fire Protection Program Manual (FPPM). l 1
l f3 QA MANUAL OPERATIONS REV. 11
(]' DATE 7/22/89 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-2 i '
Arkansos Nuclear One FOR FIRE PROTECTION I
1.6 The above requirements are implemented'by controllir::
,_ activities as described in this manual and appendix and by
( ) procedures referenced in this manual and appendix.
2.0 ORGANIZATION 2.1 The organizational structure and responsibilities of key personnel-associated with the administration, implementation and evaluation of the fire protection program are described in Section 1.0 of this manual and as follows:
- 1. The Vice President Nuclear is the management position which has the overall responsibility for the development, implementation and assessment of the effectiveness of the fire protection program. He reports directly to the Chairman of the Board and Chief Executive Officer.
- 2. The Director Nuclear Operations is the manager responsible for the overall administration and implementation of plant i
(~)j operations in accordance with the fire protection program.
He reports directly to the Vice President Nuclear.
- 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 responsible for the fire protection aspects of the program at the plant, such as evaluation of fire detection and suppression equipment, fire barriers and alternate shutdown equipment protection. He reports directly to the General Manager Engineering. Reporting to the l im.
) QA MANUAL OPERATIONS REV. 11
.'~' DATE 7/22/89 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-3 Arkansas Nuclear One FOR FIRE PROTECTION
Manager AND Engineering is the Superintendent Engineering Services. Under his direction is the Supervisor Fire
) Preventicn/ Protection. The Supervisor Fire Prevention /
- k. ,/ .
Protection is responsible for:
(1) Implementing, maintaining and assessing the fire prevention aspects of the program as defined in plant procedures (2) Performing fire protection evaluations (3) Developing inspection and surveillance criteria (4) Coordinating ANI fire protection inspections at the plant (5) Providing guidance and technical support to the nuclear plant in the area of fire protection
,m
( 1 (6) Assuring that applicable regulatory requirements are LJ included in the fire protection program (7) Assuring commitments regarding fire protection are identified and tracked (8) Assuring safety evaluations (10CFR50.59) and design reviews for fire protection modifications are performed (9) Assuring that evaluations / assessments of the fire protection program are performed and results reported to Management REV. 11
[)
QA MANUAL OPERATIONS DATE 7/22/89 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-4 Arkansas Nuclear One FOR FIRE PROTECTION 1
____.______._____o
(
(10) Maintenance and revision of the Fire Protection Program Manual t ) '
v (11) Classification of F-list components for the component level F-list
- 4. The General Manager Nuclear Quality is responsible for j assuring that the fire protection program is implemented [
in accordance with the QA Manual Operations, Technical Specification m and applicable procedures. This is accomplished by the performance of audits and other provisions of the QA Manual Operations. He shall assure that corrective action, when necessary, is taken. He reports directly to the Vice President Nuclear.
- 5. The Manager Licensing is responsible for providing other responsible organizations with regulatory information and interpretations on regulatory issues related to fire protection. He is also responsible for providing
,v) interface with the NRC on fire protection matters, j engineering evaluations and analysis of fire protection systems, as related to regulatory commitments and control of license-based documents relating to fire protection.
He reports directly to the General Manager Technical Support & Assessment.
- 6. The General Manager Engineering is responsible for assuring that the technical requirements specified in the Operating License, Technical Specifications and other design basis documents, with respect to fire protection, have been satisfied in design trodifications and design ,
documents affecting ANO. He report's directly to the Vice f President Nuclear. .i 1
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I L '3 0 0,UALITY ASSURANCE PROGRAM
/ 3.1 This quality program is to ensure that the fire protection 1
systems for safety-related areas (as defined in paragraph 1.2
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of this Appendix) v e controlled in accordance with applicable i NRC regulations, industrial standards and codes, policies, l rules, procedures and licensing documents. The quality program is' implemented through approved procedures. The j effectiveness of the fire protection program is serified through surveillance and scheduled audits conducted by the NQ ;
Organization, under the cognizance of the SRC. General requirements for this program are also described in subsections 2.4 through 2.7 of this manual, except that personnel
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performing inspections need not be certified to ANSI N45.2.6, i when inspections are performed on equipment not listed on the Q-list.
I 3.2 Employees whose duties and responsibilities are related to this fire protection program at or in support of the nuclear plant ;
) are to participate in appropriate training programs to assure-that suitable proficiency is achieved and mainta ued in the work they are performing.
3.3 Fire protection training for plant personnel is included as part of industrial safety in the General Employee Training Program. Personnel are periodically retrained in industrial safety in accordance with approved procedures. Personnel assigned to the plant Fire Brigade are to receive additional 3 indoctrination and training to assure their capability to fight fires is established and maintained. The Supervisor Fire Prevention / Protection has the overall responsibility for these training programs.
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L 4.0 DESIGN CONTROL
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[ 4.1 Section 3.0 of this manual is applicable for design' control activitier pertaining to the fire protection system.
l 5.0 PROCUREMENT DOCUMENT CONTROL l
5.1 The control of procurement documents for fire protection related materials, parts and components is described in Section 4.0 of this manual with the exception of paragraph 4.2.3, when these items are not associated with the Q-list. The procurement document is to include the requirement that items be U.L. listed or F.M. approveo for fire protection ase, where applicable, in accordance with approved procedures.
6.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS 6.1 Inspections, tests, administrative controls, fire drills and l training that govern the fire protection program are prescribed by documented instructions, procedures and drawings and are
-] accomplished in accordance with these documents. A listing and brief description of procedures relating to fire protection activities are provided in the ANO Fire Protection Program Manual. Instructions, procedures and drawings are prepared, reviewed, approved and revised in accordance with approved procedures.
7.0 DOCUMENT CONTROL 7.1 Section 6.0 of this manual is applicable for the control of quality program documents related to fire protection.
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8.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES )
I g i 8.1 The control of purchased fire protection related materials, (o) equipment and services is described in Section 7.0 of this manual, with the following exception related to subsections 7.2, 7.3 and 7.5. For the procurement of fire protection related items er services not associated with the Q-list, t.he vendor / contractor qualification criteria (including periodic reassessment of their program) is not required.
Nonconformances dispositioned repair or use-as-is by the vendor are to be submitted to and accepted by ANO only when so designated on the procurement document.
9.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS 9.1 Section 8.0 of this manual is not applicable.for the identification and control of materials, parts and components related to the fire protection system. No particular requirements for this section have been identified in BTP-APCSB
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) 9.5-1, Rev. 2. The identification and control of materials, (J parts and components are conducted in accordance with existing procurement and materials management procedures and practices.
10.0 CONTROL OF SPECIAL PROCESSES 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 procest controls have been identified by l BTP-APCSB 9.5-1, Rev. 2. The control of special processes for the maintenance of the fire protection system is performed in accordance with applicable approved procedures and practices.
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( ) QA MANUAL OFERATIONS REV. 11 L' DATE 7/22/89 SECTION: APPENDIX B - QUALITY PROGRAM PAGE AB-8 Arkonsos Nuclear one FOR FIRE PROTECTION
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11.0 INSPECTION l
11.1 Inspection activities applicable to the fire protection system (v) are described in Section 10.0 of this manual with the exception of paragraphs 10.2.2 and 10.3.2.3, when inspections are ,
performed on equipment not associated with the Q-list. The Regulatory Guides referenced in paragraph 10.2.2 are not applicable to tSe fire protection system. Individuals outside l the NQ Organization who perform inspections only need to meet paragraphs 10.3.2 and 10.3.2.1.
In addition to the provisions of this manual, inspections and surveillance are addressed in applicable portions of the Fire Protection Program Manual and the Technical Specifications for each nuclear unit.
12.0 TEST CONTROL 12.1 A test program is to be established and implemented to ensure
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) that testing is performed and verified on applicable systems and components to demonstrate conformance with design and system readiness requirements. The tests are to be performed in accordance with written test procedures and test results evaluated for conformance to the test objectives.
12.2 The control of testing activities is described in Section 11.0 of this manual. Surveillance testing requirements are identified in the Technical Specifications for each nuclear unit.
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13.0 CONTROL OF MEASURING AND TEST EQUIPMENT
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'i i 13.1 Section 12.0 of this manual is not applicable for the control v of measuring and test equipment. No particular measuring and test equipment controls have been identified in BTP-APCSB 9.5-1, Rev. 2. Measuring and test equipment is controlled in accordance with applicable approved pro:edures and practices.
14.0 HANDLING STORAGE AND SHIPPING 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
[] 15.1 Measures are established to provide for the identification of items that have satisfactorily passed required inspections and tests and are documented per approved instructions or procedures.
15.2 Section 14.0 of this manual is applicable for identifying the inspection, test and operating status of the fire protection system.
16.0 NONCONFORMING MATERIAL, PARTS AND CCMPONENTS 16.,1 The control of nonconforming materials, parts and components related to the fire protection system is described in Section 15.0 of this manual, with the exception of subsection 15.3, l
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i SECTION: APPENDIX 8 - QUALITY PROGRAM Arkansos Nuclear One FOR FIRE PROTECTION j
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-- j F i when the item is not associated with the Q-list. Vendor
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p, nonconformances are to be submitted to AND only when so designated on the procurement document.
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17.0 CORRECTIVE ACTIONS 17.1 A corrective action system is established to ensure that conditions adverse to fire protection, such as failures,
functions, deficiencies, deviations, defective components, uncontrolled combustible materials and nonconformances, are promptly identified, reported and corrected.
17.2 Corrective action activities are controlled as described in Section 16.0 of this manual, with the following exception related to subsection 16.3. Vendors furnishing fire protection items not associated with the Q-list are not required to be listed on the QVL, 18.0 QUALITY ASSURANCE RECORDS C) !
18.1 Records which furnish evidence that the criteria enumerated in this program are being met for activities affecting the fire protection program are to be prepared and maintained as described in Section 17.0 of this manual. A listing of documents and records (including calculations, test reports, code reports and design change packages) relating to fire protection is included within the AND Fire Protection Program Manual.
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l 19.0 AUDITS 1
l- . ,e j 19.1 Audits are to be conducted and documented to verify compliance with the fire protection program, including design and procurement documents, instructions, procedures and drawings and inspection and test activities. Section 18.0 of this manual is applicable for the control of audits related to the fire protection program.
19.2 As a minimum, audits of the fire protection program are to be scheduled at specified frequencies in accordance with the Technical Specifications applicable to each nuclear unit.
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