ML20058F338

QA Program Description for Operational Nuclear Power Plants

ML20058F338
Person / Time
Site:	Palisades, Big Rock Point  File:Consumers Energy icon.png
Issue date:	10/15/1990
From:	Fryling V, Heins G, Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20058F337	List: ML20058F332 ML20058F338
References
CPC-2A, NUDOCS 9011080220
Download: ML20058F338 (87)

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{{#Wiki_filter:.;, l Consumers 8RY CPC 2A lI l, QUALITY ASSURANCE I PROGRAM DESCRIPTION I FOR I DPERATIONAL NUCLEAR POWER PLANTS lI E A LI seEl l -Appa g ( I 1 ,I 'I 'I I i8A"8ss:::8ag;gs

s I Consumers Power "****'ak * *aak=*a i President and m CMel Operertne ODker - MKRMAN'E M i l I o.n.r.i otoc..: 21: we t uichio.n Av.nu., Jack.on, ul 49201 * (617) 788-0550 i' I SUBJECTi STATEMENT OF RESPONSIBILITY AND AUTHORITY REGARDING THE CONSUMERS POWER COMPANY QUALITY ASSURANCE PROGRAM FOR OPERATIONAL' NUCLEAR POWER PLANTS gl As Chief Operating Officer.of. Consumers Power Company, I have.the ultimate- _ g; management authority.for the establishment of Corporate Quality Assurance Policy. -This Policy is provided in the Consumers Power Company Quality Assurance: Program Description-for Nuclear Power Plants. The Quality Assurance ,I Program Description complies with the quality assurance requirements contained 4 in Appendix B ofJ10CFR50, " Quality Assurance Criteria for Nuclear Power Plants and-Fuel Reprocessing Plants" and responds to the additional guidance con- ' l tained!in' ANSI N18.7, and'to the ANSI N45.2 Series of Standards and corre-e ,spondingLRegulatory Guides within the context of' applicability imposed by i

N18 1 The, Quality l Assurance: Program Description l for Operational Nuclear.

I ' Power Plants outlines the actione that are' implemented during the operational < s phase' including fueling,L testing, operation, refueling, procurement, mainte-- nance',l repair,.and. inodification ~ design = and construction of the safety-related, f

portions of

the nuclear power plants.:

r 1 shave delegated the: authority for the establishment and maintenance of the = QualityjAssurance Program-Description through the Senior Vice President.. I +. Energy Supply to'the Vice. President, Nuclear Operations for operational phase activities.and plant modifications, and in turn'to.the Director,. Quality. M A 1 ssurance. ;The Director Quality Assurance 18:also authorized to verify the l effective implementation of the Quality: Assurance Program Description. i The Quality AssurancelProgram Description contains mandatory requirements which must be implemented and enforced by all responsible ~ organizations'and: .' individuals.. a y, <6 3 h I ,1 5 ' I' lA C4G GVERGYCOMPANY a ( g n

I w "Jl-w CPC-2A 11 i q QU N TY ASSURANCE PROGRAM DESCRIPTION 4' FOR i ,4 -i. OPERATIONAL NUCLEAR POWER PLANTS .I m REVISION 11 ' APPROVED BY* g 'i /N / O-P 90- - j y s

Senior Vice-President. Energy > Supply Date Y

, G L Heina I g N( /D-DN i Vice. President. cl a Operations Date D P Hoffman f fe // fO M eu ice Pr t and Chief F ancial.0fficer Date E - g,s 2 hW lo/S~f90 s .Vice resi ent. Energy. Supply.-. Services ' Da't e. ~ D ;W "oos / O ~* h - & .Vi% President. ElectriVTransmission.and Distribution-Date -D VLVoigt' 58 ] Ah^W_L I /O- + 90 Date-W: JVi'cePresd/j6f;InformationServices& Technology-K C'Bottonari I /0$he LVicF?resTdent(Foss1T 6 Hydro Operations 'Date; 'R J Nicholson-a l I .E l

f i. Page 111 Rev 11 Date: 10/15/90 p QUALITY ASSURANCE PROGRAM DESCRIPTION FOR OPERATIONAL NUCLEAR POWER Pl. ANTS a. CONTENTS- "kb Title Page Section Statement of Responsibility and Authority.... i . Approval Page........... 11 + Contents.. iii 1.0: Organization....... 1 l* 12.0' LQualityl Assurance Program. 19 . 7,.; 3.0

Design Control.................. -

25 ,' nl 74.0 ' Procurement Document Control. 29 ^ 5.0i 31 - InstructionsF Pro,cedures and Drawings.... 6' 0 - . Document Control.<......~............ 35 o 7.0- -Contro1~of: Purchased Material. Equipment '37 ,and Services... '. '.........-........ -. C 41- ' 8 '. 0 c ' Identification and Control of Items. y. 1, 4: ~43-9.0 . Control of'Special Processes. l1b 0 . Inspection..................-.'..-.. c46 E 11.0 .Te s t C on t r ol..... :.. ;.. :.... '. '. -........ - 47 j 49 a g 112.0' Control-of Measuring and Test' Equipment... [1l3.0h Handling Storege and Shipping..-. ~' 51 i m is .,\\.. 3 9,".. -,y --14.0) T Inspection, Test'and Operating Status.......... 53 y ?' 15.0L

Nonconforming Materials. Parts or. Components.....

.55 I

16.0}

Corrective Action- ..1. 57' s 117.0;

Quality'_ Assurance Records..

59 61 m 18.0. . Audits...-....-. ~ l l . PD108'l-0535A-QA04-QA06

y.if. Il P:gs iv j .c j Rev 11 Date: 10/15/90 1 J; 4 Section Title Page Appendix A Regulatory Guide and ANSI Standard Commitments... 6') (2pp) Part 2 'CP Co Exceptions to Operating Phase Standards and Regulatory Guides...... 65 (22 pp). I,1 FIGURES ) ~1 Consumers Power Company Corporate gI li' 3 '.] Organization.. j (2 Energy Supply Organization. 12 a s g (p 3 . Nuclear Operations Department Organization..... 13-4' Quality Assurance' Organization...-'......... 14 Q' 5s Energy' Distribution and . Information Services-& Technology.. 15. ,lm, o g: '6- ' Energy Supply Services' Organization 16-ly

7; rinance Organization........

17 n. .]t '~,f. I t a t b 4 9 S, [ t '.3 b Yi) 'l E_ i s s. j f ,. h,.t. i .? E G ,f-Q)[ '

lf _g W , M' E Pago 1 Rev 11 4 = ~M Date: 10/15/90 s ' l '. 0 ORGANIZATION-4

1.1 -

POLICY Consumers Power Company (CP Co) is responsible for establish'ag and g implementing the Quality Assurance Program, as described hereni, for the operational phase of its nuclear power plants. Although authority = for development and execution of some parts of the program is delegat- .ed to others, such as contractors and consultants, CP Co retains overall responsibility. 1, This section of the Quality Assurance Program ?>escription (QAPD) identifies the CP Co organizations responsible for activities affect-a?' ,m 9' ing the quality of. safety-related nuclear power plant structures, systems and components and describes the authority and duties assigned , f .to them. It addresses responsibilities for both attaining quality objectives and for the assurance functions of establishing and main- .0 taining the Quality Assurance Program and verifying that activities affecting the quality of safety-related items are performed in accor-l'" dance Nith QA program requirements. =,

1. q J '

J, Qu'ality assurance functions (audits, surveillance, certain reviews and- _J', controliof'this QAPD)iare performed by personnel within formally designated Quality Assurance (QA) organizational units that report to a w --j V the Director,. Quality Assurance. Specific-areas of responsibility and' authority are delegated to these units by the individual assigned a overall responsibility and authority for the QA Program.. The report-m ting level of'the' Quality Assurance organization affords sufficient authority andJorganizational freedom ' including suf ficient indepen-L'.. dence from the' cost,and schedule, impacts of QA organization actions,. f" ~ " to enabic people;in:that organization.to. identify quality problems; to initiate, recommend. or provide solutions; and to; verify implementa-

j, tjonfof solutions.

IMPLEMENTATION ,,' (1.2: e 4 w 'MY

1;2.1 Source of' Authority p'

. V The. President and Chief Operating Officer'(see Figure 1 of Company Organization Charts). of CP.Co is responsible.for safe operation of~ CP Co nuclear power plants. ' Authority and responsibility for'estab-l' 'lishing and implementing the QA Program for plant operations :mainte-i nance and modifications,is delegated through'the Senior Vice f . President Energy Supply to theLVice-President'- Nuclear Operations ~ F .l(see Figure 2). This delegation 1stformalized in a STATEMENT OFl ,m' RESPONSIBILITY AND AUTHORITY eigned by the President and ChiefLOperat- ... f 5 -ing Officer. Other quality-related functions are provided by other-organizations as described herein. J. ~PD1081-0535A-QA06

.. ~. x Il Pcgs 2 .j Rev 11 I Date: 10/15/90 1.2.2 Responsibility for Attaining Quality Objectives in the Nuclear gi Operations Organization g The Vice President - Nuclear Operations is responsible to the Senior ) Vice President, Energy Supply for operation and maintenance of CP Co q 'I l nuclear power plants. Directors and Managers who report to him are responsible for directing the performance of activities that affect safe plant operation and/or safety-related functions of structures, I systems and components of the operating nuclear power plants in W ; s accordance with QA Program requirements. a.- The Plant General Manager / Plant Manager (see Figure 3) are respon- ^ sible to the Vice President, Nuclear Operations for operation and maintenance of the nuclear power plants in such a manner.as to -l achieve compliance with Plant licenses, applicable regulations and the QA Program.. Each Plant General Manager or Manager delegates 4 to appropriate managers and staff personnel.in his organization 'l responsibility for carrying.out applicable controls required by l; =the' Quality Assurance Program.; QA Program activities performed on 31 the authority.of the' Plant General Manager / Manager.includet c Qualification of plant operating and maintenance personnel. . Control'of preparation, review and approval of Q-List updates. Control of preparation, review and approval of plant procedures um j and instructions. A F Control of plant initiated procurement, including preparation.- . reviews:and approva1L of purchas'e requests, for spares : replacement - a t items,'.consumables, and materials',. items and services.- Control aj i .also includes' submittal'of~ purchase requests ~to Purchasing, vendor gH surveys'for urgent procurements, planning ~and execution.of source j surveillance.or. inspection., receiving inspection ~, and review of Jy.. yM pplier' quality;-related' documentation. - 4 ' Accomplishing plant licensing activities including maintaining g licensingEdocuments up-to-date,Jinterfacing with the NRC, accom-g-( ~ E plishing;and/or tracking' licensing commitments.and coordinating' gy internal' action on;NRC. bulletins, generic letters, etc. .y i q EProviding necessary corrective' action processing and status l w reporting for assigned corrective action documents, including. ~ 'T . determination of'NRC reportability. + 3 Functioning as'.the. Company design'and configuration control s w + -' authority for compliance'of. plant 2 modifications and design changes t to. existing plant design criteria. h 1 E Project responsibility.for modifications, including design, procurement, construction and testing-activities as assigned by 4 the Plant' General Manager / Manager. a PD1081-0535A-QA06 .g, -W, ) - \\x. [ a

f Pass 3

, Rev 11 Date: 10/15/90 8-Safety assessments operating experience reviews including NRC Information Notices, administrative and technical support for Plant Review Committee (Palisades) activities and technical support for onsite review organizations. Developing and maintaining Plant Security Plans and administering the contract (s) for the security force. Authorizing use of secondary calibration standards whose accuracy is equal to that of equipment being calibrated, and assuring that such use cannot result in operation outside Technical Specifica-I, tions limite. Maintaining Echelon III calibration facilities for Portable and I Laboratory Measuring and Test Equipment (PL-M&TE),and Health . Physics PL-M&TE (HPPL-M&TE). Calibration / maintenance,of installed plant instrumentation. Ix _v: s Controlling a calibration recall system, Maintaining a Master List for plant-owned PL-M&TE. 5s v Operating onsite Document Control Centers.- 'Onsite. evaluation of corrective action documents,. including initial determination of reportability to the NRC. I 1 i Providing for' storage and protection.of purchased materials and items'andl items awaiting disposition implementation after removal-from service, assuring' preservation of identification. N Developing-and maintaining Plant FireLProtection Plans. (-Implementing security, fire. protection, health. physics and emer-- gency plans. Performing. start-up and operational testing, such as precritical' B >* and/ criticality. tests.. low-power, power ascension and plant tests. iand; 'rveillance testing. t Mat..ining equipment atatus. control.' I-Maintaining: required controls over.cheEical standards and-3 t yreagents.) - Conducting the inservice inspection program in'accordance with technical-specifications and State of Michigan rules.

Conducting'a water chemistry program in accordance with technical specifications.

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y Date: 10/15/90

') W 4; W W,. w i y.cf. Mg E. 3J Qjf f(f Performing reactor engineering functions.,such as fuel calcula-y y a# tions and: specification, fuel movement calculations, reactor 5l $ ~ ',. %, ,. thermal profileistudies. safety analysis, etc.' l $g a ? bc ~b.3 1The-Directot, Nuclear Safety Services Department-(see Figure 3), [ Cistresponsible for:- $Q y, y. @. Y ' spy Performance of the_offaite safety review functions for the nuclear ~- pi Q+ ' power plants as-described in plant technical specifications. i m 4-p4 N i 1 .. s f p< < Development:and maintenance-of nuclear plant probabilistic rit' gj ,, : assessment models and application of PRA technology to severe 31 y%g-3 D. F ! accident' management,and plant reliability improvement. m c r 6 'h .{ k m' ConductL,of,the biennial. assessment of QA Program effectiveness. J vme 'a .4_.- 2} MU%i L Procurement of nuclear fuel and associated services. Q7,' 0;/ 7, .g j Q$ 4 3 - "Assessingithe effectivenessLoftthe' corporate Health' Physics. !5:1 %Mf , program"and(maintaining standards for}controlLoffRadiological _j g$ 3 LMaterials'and' personnel _ exposure and recommending program improve-g(J r y

ments.to reducejon-site:and-offsite: radiation. exposure-caused-by-

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%M rplantEoperations,topefating the dosimetry laboratory and main-- , j h"$<> ' $ taining;recordslof personnel _ radiation exposure.- j aymq m. ,-m. w n e eLThetEmergency Plannin'g Administrator-(see Figure 3):is responsible O s* W c m pi < y, .'for(coordinating Corporate-Nuclear. Emergency Planning. q T m w yg n n ,1 1 _t- . + - ,v k,Qlf..

"di ?.,The; Director,1 Nuclear Training, Dis responsible for! establishing,l ll!

g L:. M. iiinplementingiandidocumenting the training of nuclear ' operations; 3 h;gp @M @M M ;M 4t!1ok andStraining.- i ' f Sand ^technicalcaupp rt-p'ersonnel,'includingcQA Program indoctrina-i $M f' ~ L'dj s; by M 2.3 b Responsib111tytfor. Attaining Quality Obh 2tives in the Energy Supply., d g g, m,m m-r c 4 y- @ @lW, ]ServicesOrganization.. -h &N Y 1 Y

qu RJ g he.;Vice President,yEnergyrSupply:. Services (see Figure 16)=is responsi -

d M [$ %9 M(blelto.theSenior>Vice~ President,' Energy'Supplyfor;certainservices; gg hD g4 W y{if M 'includingf standards ?for calibrationjof M&TE,1 and performing assigned! n" ymodifications, to1CPzCo. nuclear' power: plants. Directo_rs and Managersi d [ k. lj p ;activitieskinLaccordance.with;QA-Program requirements'.- g x, ji J' Meportingstothim areiresponsible for directing th'eiperformance of;

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e pup gn ,e o-QW NG a. :' The Manager : Energy. Supply 1 Technical' Services '(ESTS) Jis :responsi-' ll ca@:w 74. lble,;through personnel.reportingito-him; for: ( U j g ,8 <: ~ w . _ y. ~ t G 8 kg P' < Maintaining /tesl ting'el'ectricalprotective-l devices. W w; / \\ T ~ 4 (Performingfdesign verificationstest1ng associated with, electrical + i protective. devices, except when such testing is procured from A W i,f p.@R.w approvedoutside' contractors. J y

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, y m. [ $r.i u i 9 ,,,, s Rev 11 Date: 10/15/90~ , g m. .. Maintaining the Company's Echelon 11 calibration facility for i ^ g* calibrating reference and secondary standards and genere.1 usage 4 portable and, laboratory measuring and test equipment. Controlling the calibration recall system for Portable and Labora-

tory M&TE owned by ESTS, and other departments, as requested..

g Maintaining a Master PL-M&TE List for ESTS PL-M&TE and for other ? E o' departments, as requested. .) l Maintaining a Company PL-M&TE Inventory List.. i

Providing chemistry support to Nuclear Operations, as requested, l

I'*' a

Preparing,Lreviewing,. approving and obtaining additional reviews

andLapprovals if! required.of purchase requests.for services.-

y;E chasing for' procurement action.= -equipmentfahd consumables.and submitting such requests to pur-o3 x e fi m Conducting performance tests-on materials, equipment-and systems.7 j Performing nondestructive examination, and controlling / maintaining: MNDE" equipment.- J y ;f 4 , x, , l' ; ~ iProviding7qualifie'd NDE procedures.and equipmentfand NDE ,7 '4 -personnel, q g %.h

iMS, Providingachemical a'ndl metallurgical analytical services?

j

Providirig nece'esary; corrective, action processing andsstatus Mit m

m !LO treporting.for:assignedicorrective action'. documents. l Ty s y. 4 ? a ,fb.1;Th'e. Manager;Projectsf(ConstructionlandiEquipmentc(PC&E)-is-i ih. U

r'esponsible.,

through personnellreporting to him;for:

.j f-M' O

t W LPerforming the construction. preoperational' testing and overall=' j / . project; management-of' assigned generating plant modification' r; o A 1 s sprojectsu s 'i 0.Providing necessary corrective; action process'ing;and status- / i p reporting for assigned 1 corrective actioncdocuments.- A V [ ',' b m = ~ ' f" iProvidingVelectrical' equipment anditurbine-generator.expertiseJand:

q 5 developing:and qualifying:special process procedures for weldingi-4

,1 1 .and: heat ltre'ating oper'tions. (( a d.z @

c. - The ; Manager,; Field MainEenance. Services provides' Field Maintenance -

f,s . Services for assigned modifications and plant outages. a -l c... PD.1081-0535 A-QA06 ." 5... l o

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y o. I 3 I 4, 'I f Page 6 g y .Rev 11 i Date: 10/15/90 y, f ?d..The Manager Engineering is responsible -through_pers<Tnel report-g ing;to him.for: g F' Performing the engineering associated with generating plant ff modification projects as assigned by the Plant General N

Manager / Manager.

g, 7m Providing, as requested, technical expertise and review capability 3j to Nuclear Operations in thel areas of metallurgy, special process-B' Jes, coatings,"~ electrical, mechanical and civil-structural engi-l af ~ neering and application of codes and standards. Maintaining:the Records Management System including required retention, protection and retrievability,-operating the General. i W, Office-(offsite) Document: Control Center and Engineering Records l W %i4 Center, and for maintaining the Uniform File Index., This includes y Ecollecting.. storing, maintaining, distributing and controlling P ant engineering / design documents. (( ' l <Providing necessary }cctective: action processing;and status ~ go., reporting for: assigned corrective action documents. ~ c m "_ " 1 ~ JPer'fLrming analytical ' studies to appraise the adequacy ;of electri- - + ,.s g"J L 1 ncal. supply to; safety-related e'uipmentLintnuclear power plants. q A

from

the? principal power; supply. facilities;of the; transmission:

l 1 W Lnetwork;and; onsite power ' supply. W M_.y_ y

e.-)TheDirector, Management 1andBudget.is; responsible,;through!

ig 'ds n d >( q

pers'onnel reporting tofhim,.for:'

'g; -n 93, -;4ProvidingLnecessary: corrective action processing and status? a H ~y,, creporting:for-assigned corrective actionidocuments" 8 lf'o y [f . n _. 1 g, f it'.2.4J 1Responsib111ty for: Attaining-Quality Objectives Outside Nuclear-I' Operations andrEnergy Supply-Services: LCertainL fdnctior.s ? that' constitute!.part of; the' Nuclear.0perations QA [( s Program;are performed by;CP Co1 organizational: units outside the gl a, Nuclea'r Operations Departmentior Energy Supply' Services. Engineering? y' M Land. des'ign tasks executed in support of.-plant activitiesLare subject s i

NPW, M to. review. add' acceptance by the associated plant-organizatior'respon-

'70gG. ysiblelforthatiactivity;(astheldesignauthority). ' ' N: MlM ir L G,7~ h The, Director,LAdministrative _ Services a(see Figure 5);is _responsi- )

a.

gJ %Fy* ~ ble through theLVice President, Information? Services and'Technolo- ~ gy to the President'and Chief operating Officer for microfilming L3: ,[,, of specified'QA' records and plant engineering / design documents.' l> 1-g JPD1081-0535A-QA06. _{ s s e, r'- _-__A__.

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W 'Ey. Page 7. 'y'[, i Rev 11 7;, W Date:.10/15/90 y n t ,e t b. The Manager, Purchasing, Land and Materials (see Figure 7) is j j _.J .,F responsible. through the Executive :Vice President and Chief Finan-a g, W _ e' ' cial Officer for initiating procurement action : based on approved -d !!g, ( ci- . purchase-requests received from organizations performing or 1 g ~ supporting plant operation,-maintenance or modification, and for.. 7 _ preparing-and obtaining required' reviews and approval of contracts. l' ] j' ,,W c. The Manager. Transmission Engineering (see Figure.5) is responsi-t 3 xbleythrough the Vice President, Electric Transm1ssion-and Distri-y abution t'o the Senior Vice President, Energy Distribution for { t T

determining settings for electrical: protective, systems and relay.

[ W, . control; systems, and for design. review and recommending changes to electrical protective schemes and associated' settings. s W .d. Thel Director, Corporate Performance and Quality improvement (see 1 Figure ll), is responsible'to the President and Chief Operating. 1 Officer for operating the: Skill 1 Centers and training and qualify. d .ingjpersonnelandequipmentforveldingoperations., d M', n en 1. 2. 54 { Resp'onsibility-for-Quality Assurance Functions j A c w W' O jTheLDirector, Quality [AssuranceDepartment.(seeFigure4),isrespon-': L Esibleito7the Vice President, Nuclear Operations"for the' definition,.. 4 P J jdirectionsand effectiveness measurement of theLNucl' ear =0perations-QAL j s ,S

Program, including' modifications.; and' for verifying that. activities?

^ , n

h. f f>y taffecting:the' quality,of,s'afety-related items are performe'drin accor -:

G adance with QA Program requirements.- He is:also responsible lfor-4 .providing'm'nagement1 direction;to.departmentLheads reporting to him asL M W a 11ndicatedjbelow for corporate' environmental auditing..The Director's' y W]: s iauthority; includes the. following major. functions f or work under -his - o

1. '

s : j urisdiction:" ,d .c ,..,a,, 4 4+ s. Q f Est'ablishing;thejQA'Programforloperating.nuclearplants.. ]yn ' ')1 s*y iContinuing evaluation-of QA-Program' status;andladequacy, reporting his f- ,"conclusionsJ o CP Co Management..- a t p f? ] I49 m s m fAssuring;that verification activities are accomplished by personnel" J Pi ' ' not directlytresponsible>for the work'being performed.L

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. for installationiof. nonconforming materials..orcitems. j ao < A 9 Stopping unsatisfactory; work.to control.further processing,zdelivery 5' o x 3p.. + ]3 M , Recommending that:a plantJbe shut down if such action appears nece's " .f I gM ' ',

sary (the orderLis issued by.the<Vice President. Nuclear: Operations'or.

.i 7 j' Lthe-PlantLGeneral; Manager / Manager). cg -:g ' _ f Reviesing' and = concurring with organizational administrative ~ procedures j "s and procedure ~ changes for compliance with QA Program requirements. 'f r~ l y 1PD1081-0535A-QA06 ly ?- & j

~' - ~ $g % .? ^ y 'l J. Pcgs 8 4 Rev 11-mi y[ *1 W ;u.' 4 Date: 10/15/90 s,%

w.'

N:p ggf. Assuring _that nonconforming items are properly identified, segregated gj; bj

• fW and?dispositioned =

3} i; W^ W i Administering'an. Enhanced Performance Incentive Program'according to We' 'Section 2.3.- d. e o 1 iw .a "w ' lj -QA' engineering associated with modification design, procurement,. M, construction and testing,' including verification that quality-related q test prerequisites =have been accomplished, identification and partici-W-j t 7pation in resolution of installation inspection ~and test problems and

(

W .nonconformances, and maintenance and reporting of status of-hardware 3, hpi and'testfquality and corrective action. -(This function will be El pig t q; carried'out by. plant and/or genera 1' office QA 'taff, as assigned by' 17 s W "J, the; Director, QA'.')~ =1 mLy .g n i, ,3 d' = f Jgg .The iDirector's; job ' description includes' the following prerequisites: y &W !. Previous? management' experience;" knowledge of quality assurance regula-l U ' h %g ..tions. : policies, practices' and standards; ' and experience working in4

g4 equality assurance or:related activities'in reactor design, construc-El s

Ltion;or) operations Lor.in a similar high technologyfindustry. -The i 1 g ,-4 ' cquality managementhoffice.. consisting'of.thel Director and:hisLimmedi-ad y g[, 4

ate staff,umeet-or, exceed the qualifications established in Paragraph

= {/ I I', b4~.4.5.of;ANS1/ANS'3.1, 12/79' Draft-as; endorsed by'. Regulatory' Guide' q, 71.8. i' ' f %, I S ? g Rf TheLDirector. -Quality ; Assurance :has-no other duties or responsibili-M 2 Lties unrelated 1to QALthat would prevent;his; full attention tolQA 5' 7 matters,'is.sufficiently free from schedule.and cost pressures to give Lg~' +Lappropriate' weight tolquality considerationsninthis, decisions.and

33 <

(recommendationsRandihas' direct access;to:hightenough11evels ofc j ,gManagement;to;obta'in resolution of quality problems.i As Director, he' u ~ {g _,"1' sdelegatesl authority and holds his' organization responsible?for accom - ' ' i, T, J p11 shin'g QALfunctionsifor operational nuclearLpbwer;plantsi as Lj. Y H 5

followst lQ

/ E ilf [a.SThePalisades' Plant-QA.Directorandthe'BigRockPointPlantQA' q [Q, *f o SuperintendentLare required,to possessithe e'ducationali and experi-8 d ' '. j ence qualificationsfspecified in-Regulatory Guideu1.~8'. Each:is _ gy a2, % responsible'to the' Director - Quality'Assurancelfor the,following. jgpp < c (operating phase activities Lfor work under ?his jurisdiction:! ga .c j . j/ -d R' [ Plant;si.teLqualityassurancesurveillanceaofsafety-related; d n H 7NJ' 3 activities,1 including operationsJmaintenance, modifications, j DS V, procurement, testing fetc. M 'J'l l Mb ' m ; Tf, ' Review of. Land. concurrence.with plant administrative procedure's';for Wy >VW -compliance with Nuclear--Operations QA Program re'quirements. 2

3

3u LVerification of.onsite corrective action implementation and the. g , ^ effectiveness lof corrective action for significant safety-related-problems,' including, for modifications, that nonconformances are= incorporated inco the' appropriate corrective system. i q ', ' .,[ y'PD1081-0535A-QA06 E,' . {I p we 'i 'f k. i t

3 ~... h r .v l n' Page 9 Rev 11' Date: 10/15/90 l 1 I" = nuclear fuel, source audit / surveillance / inspection at fuel suppli-1 y c er facilities, fuel inspection upon delivery, and review of fuel: i supplier quality-related documentation, t 5 . Plant _ site quality control ir nection program, including inspec-l ~ . tion of' maintenance, modificatio n,' testing and fuel handling. v. l 7 . Participation in daily work schedule and status meetings to remain . abreast of day-to-day work assignments throughout the plant and to [ 1 assure adequate-QA. coverage relative to procedural and, inspection controls,' acceptance criteria and staffing and qualification of- 'y

site-QA personnel to carry out their assignments.

J ReviewLof maintenance, modification, test, and fuel handling: { procedures and instructions, and work-authorizing' documents for QA ~ i

aspects,. inapection planning,- and inclusion of necessary Hold and 4

Notification; points. '} Nj ' Review:and concurrence 'with acIministrative procedures that control. 3 methods.for~ indicating inspection, test land operating status and a ezg, * . attachment / removal of; inspection. status indicators. ~ ~ I{ W Q-List-changes..to assure; j - Reviewf and concurrence ;with.Q-Lir,te and: I,,l ' 1 compliance with;QA Program commitments and to assure'that the-- J 4 fs extent'that+QA' controls'are to be applied to specific structures, f .g .-systemsland' components Lis apr,ropriate.: >gz. w 3 (51* f Lb. Quality 1 Assurance'Section Heads;(Corporate Office)-are' responsible; j M 'to.the" Director,1 Quality Assurance forLthe Nuclear Operations-QA'- i fi

audit program ;QA' program development,tand speciall studies

includ-d g%

e sing the following:- s .g <h 7Q",' /QA, Security and Environmental audit. programs l(plant sites andL S e r Corporate' Office), including follow-up on corrective action.for-q 1j audit' findings.'- J w 'l 'f + } g i '", . Verification:of the implementation and cffectiveness of Corporate' j 63;' Officeicorrective actionifor significant' problems, h ~ 3[' c Supplier'surveysiand evaluation including' review / approval of' .gp' 1 ip$, ,^ 1 L j . supplier'QA programs, and maintenance.tof thefNOD Approved Suppli-1 ers List. j [ ,o ~ f, 'Reviev'of anc concurrence with' quality' requirements of procure'm'ent: 4 Te requ'est packages generated in:the Corporate' Office, as required, L yg t ( TEL_. . Corrective? action program trend analysis'and reporting. ' p" ' I '

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ENERGY DISTRIBUTION-CHIEF OPERATING' (! OFFICER' 'l IV > n 1 o j g 7. g. - tl-ci; 4 t 4 v % :. -. Ig ) ,t-1 " j:jf& VICE PRESIDENT- .VICE PRESIDENT '[ ELECTRIC 3:' " ^ INFORMATION 4 ? TRANSMISSION' SERVICES oi[ i y,. ' AND. DISTRIBUTION & TECHNOLOGY'. .K c ^ s ,}.. y x i kip < !. 3 .a i e ,,3m.. a b : < r. : ). i 'a-ip, n ' [ i x 2 e u ..f' -.c M i l .q.; m ' MANAGER .. DIRECTOR " 'N,!U -TRANSMISSION. ADMINISTRATIVE 9 ^ ' ENGINEERING: SERVICES: W,.j!- o o p(GRAPHIC;0PERATIONS), 4. ( w,.w s a 4 -t i [ ,1 I IDIVISIONcHEAD? O - SYSTEM: PROTECTION d L ENGINEERING: 1 ,? ',' pf p i Jf ui. d1s. ' ' '- y{ a [ M -0 ;; o [- h t if i v. <M e Q;] ?,, l \\; ' $$ ]3( r u d, [iW: g s-}. wy' '{'J .-;): y ) }\\ q 0 ) ., =. l ;. 6 'j f}-l1 f :. - ^ s M f Figure)S_-LEnergy Distribution and Corporate Services Organizations i;. .l > : o a I

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%g ~ ^ j} ,f.. 4 s u' Y ,M' Pags 19-g .Rev 11 ~ I,Y W '4. Date: 10/15/90 t z l s 2'.0s fQdALITY2ASSNRANCEl PROGRAM. l [ 02.1- ) POLICY l .Policiesithat define-and establish the Consumers Power Company (CP.Co) [ LQuality. Assurance Program for. Operational Nuclear Power Plants are 4", G I yf",

stated in'the in'dividual sections of this document; lThe program is i

implemented through proc'edures and instructions responsive, to provi- [. sions of.theTQAPD and will be carried out for,the life of each plant. l gh l Quality. assurance' controls apply to activities affecting the quality ^ Egh >ofisafety-related.. structures,- systemssand components, to an' extent ~ , Dy based'on'the importance of those structures, systems, or components to ' ]', %g l safety;=?Such; activities:are performedrunder' suitably controlled conditions, including;theiuse-of. appropriate. equipment,, maintenance'of ~, y proper environmental conditions, assignment of qualified personnel and y< assuranecLthat?all applicable = prerequisites have been met. . ualityLAssurance Program statun, scope,, adequacy'and' compliance with ( Q 7E t10CFR50.AppendixcBiare; regularly-reviewed by CP Co Management.through. j J reports,PmoetingsTandl review of-audit results... Biennially,:a. pre ' i j%. f,,

planned andFdocumented; assessment of the Nuclear' Operations _QA Program-l e

> g#[f ' is[perfarmedbyl'amanagementteam:independentoftheQualityAssurance >{ ~ 3 F s ' Department. m ji 12'.2 l IMP 1.EMENTATION? ,,9 o s 't

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i iThe: President 6fConeumersPowerJCompanyi'asChiefOperat'ing10fficer, } 0 1211' J V 2 4 (WQ #;, shas statedtin;a;formalSSTATEMENT.'0Fl RESPONSIBILITY AND AUTHORITY, q 1 " s ' ! signed: by 'him, thathitl'is corporate (policy: to comply with the provi-' h ,4 'g$o cf1sions1of[applicablellsgis1'ation?and:regulationsIpertainingftofquality: 'l W < HM assuran' eifor: nucleart powert plants as defined. byc10CFR50 l Appendix LB. ' ,J g" c LThe statement makesethis: QAPD and the associatedtimplementingiproce. , s ]l@,. % f, "durestandlinstructions'mandasory;and; requires compliance'.by all( J J ns pc,2 1 ment positions initheicompany vested with responsib111tycandeauthority }Q lresponsiblelorganizations and? individuals. cItDidentifies:the: Manage > t kN q i : ~ e 3, Py lfor/ implementing thelProgram'and. assuring /its effectiveness.. e , =.... i f . 2.'2'.20'sThe;QualityEAssuranceiProgram at;CP Co consists'of;controistexercis'ed'. ~ ^f iby1organizationojresponsible:forLatta'ining quality objectives.and by:

<J e

py forganizations: responsible for.assuranc'e functionse(see Sectio'n'1;0'," y,

0RGANIZATION).s J

9 i ' g 3 ' 3.g - c n' t

2.2.3h JThefeffectivity,and applicability;of this'QAPD;are as followst 4.

,y ? c 1

a. g s

s Q;"p > ,a.: For; Big (Rock 1PointJand Palisades,2heJQAPDibecame' effective on-1 j , Aprili l',71982,iwith fullfimplementation'onl January'1,f1983.. W i.;TThe7QA Programldescribed in this QAPD is intended to apply for.the 3 lifesof;CP Co's nuclear. power plants. / w, i I t l '"[. p[ j o 4 L 3. 1 .. ; jPD1081-0535A-QA06' ~ j e ~... a

gg;y ) Page 20 Rev 11 Date: 10/15/90 c. The QA Program applies to activities affecting the quality of g, safety-related structures, systems, components and related g consumables during plant operation, maintenance, testing and all modifications. These activities having a direct impact on Q-listed items shall be procedurally controlled. Safety-related structures, system, components and related consumables are identi-fied in Q-Lists, which are developed and maintained for each plant in accordance with the criteria of Regulatory Guide 1.29 as clarified by Items No. 20a and No. 20b in Part 2 of Appendix A to this QAPD. 2.2.4 This QAPD, organized to present the CP Co Quality Assurance Program for Operational Nuclear Power Plants in the order of the 18 criteria of 10CFR50 Appendix B, states CP Co policy for each of the criteria and describes how the controls pertinent to each are carried out. Any changes made to this QAPD that do not reduce the commitments previous-ly accepted by the NRC must be submitted to the NRC at least annually. Any changes made to this QAPD that do reduce the commitments previous-g ly accepted by the NRC must be submitted to the NRC and receive NRC 3 approval prior to implementation. The submittal of the changes described above shall be made in accordance with the requirements of a 10CFR50.54. g The program described in this QAPD will not be changed in any way that would prevent it from meeting the criteria of 10CFR50 Appendix B. 2.2.5 Documents used for implementing the provisions of the QAPD include the following: a. Nuclear Operat1ons Department Standards (N0DS) and/or administra-tive procedures specify the standard methods of accomplishing operational phase activities. Because the Quality Assurance Program is an integral part of the operational phase activities, the methods for implementing Quality Assurance Program controls l are integrated into these documents. The Quality Assurance .l Department reviews the NODS and administrative procedures for compliance with QA Program requirements and Corporate QA policy. b. When Contractors perform work under their own quality assurance programs, these programs are reviewed for compliance with the applicable requirements of 10CFR50 Appendix B and the contract and are approved by CP Co prior to the start of work. c. Applicable elements of the operations Quality Assurance Program are applied to emergency plans, security plans, radiation and fire g protection plans for CP Co nuclear power plants. These plans 5 describe QA controls applicable to associated equipment and activities. 2.2.6 Provisions of the Quality Assurance Program for Operational Nuclear Power Plants apply to activities affecting the quality of safety-related structures, systems, components and related consumables. PD1081-0535A-QA06 g

e } }h, (' l .l 4,' j a! 7 1 Pags 211 U Rev 11 + Date ~10/15/90 'I Appendix A'to this QAPD lists the ANSI Standards and Regulatory' Guides 3 to'which CP.Co commits., Appendix.A also d;.k ribes necessary excep-T tions'and clarifications to the requirements of.those documents. The Y

scope of the program and the extent to which its controls are-applied

[ ' I *, w * " ~ are established as.follows: [ M., s" Te a. CPLCo uses'the criteria specified in1 Regulatory Guides 1.26.and i I. 1.29 in engineering analysis of an. item's function in relation.to safe' operation and-shutdown to identify structures, systems and-y components.to which the Quality Assurance Program applies (See i .' oW '~ b.: - This -identification process 'results in. the classification of l equipment'as either Q or non-Q, and-the inclusion of this classi- ,g (g'*s. .fication'in an equipment data base.- This data base is available .for inquiry by. individuals' involved in' plant operation.- The t 4 -}, classification of structures, systems:and consumables is also identified,! documented, and, controlled. [ 2

+

j; c..:The e'xtent to'which controls specified in the QualitymAssuranceL b[lW j

Programare applied:to!Q-listed items':11s determined for each item

'j cons deringtits relative.importance to safety. Such determina-~ i (gf' , p %;. tions}are based /on data in-such documents as the plant' risk S p;g " '

• analysis, plant 5 Technical ~ Specifications and the FSAR/FHSR,(See.

1 i Appendix' A)-.1 3g; 7 7 fivg M.' ' 2in ".ActivitiestaffectingLthe quality of. safety-related; items are accom-plished under, controlled conditions.. Preparations for'such' activities 3 ,i ? 'l include:confirmationethat prerequisites.have been met, such as:' j su ) fa.t JAssignedjpersonne1Lare' qualified.. 1 pI4p 4

}

m.[ ' ,, R Work ltias,been3pla'nned to the proper (revisions of applicable. g i Vengineering'and/or technicalispecifications., d g; N '; W / V s e.j , c. jSpecified equipment and/or' tools,.if any,' are;on hand to beJused. 4 W g,n _.dk Materials and items.are.inL an: acceptable status., y b L Le.L JSystems:oristructuresLon which'workLis to be!performedfarejin the' j g

g' e 4 rproper

condition forfthe task.

j V sQ[.M'< 'f. > Authorized current'lustructions/ procedures for the work are l a X Lavailab'le'. for: use.1 9 ? x ,: t T i g. Items and' facilities that.could be damaged by the'workJhave:been-m ?+ , i o i y. protected, as,requ' ired.' 4 y y .i (y ch. Provisions have:been made for special controls, processes,. tests and verification methods. -l i .1 D 1 'PD1081-0535A-QA06 Y

m ? h .a' y.>b Page 22-W' Rev 11 4:f Date: 10/15/90 ? g m s 3 4"' 12.2.;8 Development, control'and-use of computer programs affecting nuclear Ap' power-plant design and-operation at.CP Co are subject to QA_ Program Edesign controls-(see Section 3.0,. DESIGN CONTROL). b Tv 2.2 9 1 Responsibility: and authority for planning and implementing indoctrina- , Em Ltion-and training are specif1cally designated in the CP Co organiza-tion'(see Section 1.0, ORGANIZATION).

1. g

'a.- The training and indoctrination program provides for ongoing ( c, . training-and, periodic-refamiliarization with the Quality Assurance Program for;0perational Nuclear Power Plants. 7' b.s Personnel who perform inspection and examination functions are._ M , qualified in'accordance with requirements.of Regulatory Guide

n k J.58, SNT TC-1A,

or the:ASME Code,=or Section.10.2.7'of this QAPD,.

, S,y ' as' applicable'. - a d 's t,

Personnel who; participate in quality assurance audits are quali-1 DC c.

i 's' 9, fiedO1n?accordance with Regulatory Guide1.146.; Rf M t d.:, Personnel assignediduties such as_special cleaning-processes, . welding.: etek.are qualified in ace'ordance with applicable codes, i (, fstandards'and: regulatory guides. ~ 1 ,,w /h ' e.t.The: training / qualification program for personne17 performing QA-K -functions' includes provisions)for retraining.. reevaluation and 4 recertification ton nsure that proficiency 11s maintained. e g,, my y w g ? s ;f'.1 ; Certificates :of qualification; for-personnelJperforming QA func-- 5 l i tiions. designate specific functions;that' the named personnel' are N> qualified-to perform.and indicateithe; performance criteria onL 3m; ' jwhich the qualification;was: based.' g 4, x

g. : Training ' and S qualification' records, including ' documentation 'ofo M

m;c i, 4 <oobjectives,< content'ofl program,4attendeesiand'date's of attendance l 79 Tl ' Lareimaintained'at leasttas'long as the personnelLinvolved are 1 7.,

performing activities to which the' training /qualificationlis.

W.+ , relevant; i y l_" { shU! Personnel responsible for performing.activ.ities_that affect q" [,, g@s l'uality are-instructed;as to the requirements identified'in W 7 q 36 Y, ; % > applicable' quality related manuals; instructionslan'd procedures. / j k[ [* "i.. The:QualityLAbsuranceIDepartment'providesLtraininginquality nd fassurance;principlesrelated_toprocurementforthosepersonnel-v W~ _"l performing procurement; quality-assurance actions,. including. review y i 4 a7 of procurement documents, source' verification;and. receipt y a inspection.. 7 m_ [ $2.101 sSt'atus atid iadeqtiacy of. the quality assurance program are regularly d}"

assessed.by CP Co Management. The following activities constitute Ck formal elements of!that assessments q

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?' )4 M Page 23 ,' q 1 Rev 11 l, i Y Date: 10/15/90 'i w f _n f 1 ? 'a. Audit reports, including follow-up on corrective action accom-5 /plishmentLand effectiveness ore distributed to appropriate levels of' Management.(see'Section 18.0,' AUDIT). l I b,- Semi-annual lQA Program Status Meetings are held, involving the 4 i Vice; President ' Nuclear Operations, the' Director,-Quality b . Assurance and.the Managers of the organizations responsible for l impicmenting elements,of the QA Program for' Operational-. Nuclear l c 1 Power Plants. 1

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-c. LManagement teams. independent from the Quality Assurance organiza- . ~ ion,' but knowledgeable in; auditing and quality's. assurance, bienni-i

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ally ~ review the' effectiveness offthe Quality'As urance Program for R e' J . Operational. Nuclear Power Plants. :This review may be performed as yI& 'part of.the Independent audit of the Quality Assurance organi- .t, zation, ' Conclusions and recommendations are reported to the h ilN iSenior-Vice President Energy Supply. 1i r ~yh zCorrective actions.in response to recommendations are trac ek d in- ,t . "1-7 CORRECTIVE ACTION). j y fthe regular' corrective action' tracking' system.(see Section'16.0,. H q i g, I 2' 3--

E101ANCED PERFORMANCE INCENTIVE PROGRAM -

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+ . ?TheLDiiector,,QualityfAssurance; evaluates performance..of'Lorganization-d s G 1al. units to.~ determine 1which,Eif any,' may.have the level of,QA over '. y[.s ' sight ofLin-process" activities reduced.E' Consideration is given toLthe-3' J ggply . sfo11owing'in making th' determination:' regulatory performance;: e NW?@MJ igualification 7 knowledge ~and performance'of personnel; internal- ~ l audit / surveillance / inspection results; results!of asaessments by(other. o9 ~J"g M. s N, in' dependent' organizations;; overall' conformanceLto established require-4 E A sj Lments;(and corrective action performance. w t i.y g g,, <12.3.2f mThose:organizationalfunits selected may receive. reduced;QA/QC atten-j 7 : tion 1n: areas?such as direct: reviews'(for; example,' maintenance / work l 9 1

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?orderLoriprocedure review), inspection coverage, or surveillance,'as d s da awarranted.:iAudit frequency is not subject"to reduction. l[J mggm ( j < 3 % [/f 2.3.3! (AnlEnhan'ced:PerformancefIncentivelProgram Plan is developed!f'or each 'q,' = sorganizational'u' nit? entering the. Program'tofdefine:the performance'- (, j ,criterialto'be' maintained, the areas:where'QA/QC will be reduced,<and: 'O llp' ' ; the11ntervals'at which performance _'will be' assess'ed ands reported.. '.) ] m) c,'e >4 + 't r ] ..uu ph-Q, X6 3f.4l !Performancefofl organizational units in the Program is monitored and _ _ ( 2 4 Jreported;to'the: Director,{ Quality' Assurance Jattintervals establishedL 9 s Jas part of1theLentry conditions. _ Declining performancegresults in; d i j hs y 1 return tornormal'or increased QA/QC attention. t I '1p O '( t! y2 Y i )PD1081-053'5A-QA06 ( s ' [ '. a. i .;,~

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g- ,g m 3 '\\. m s y;sf Page 25 Rev 11 Date: 10/15/90 j .\\ y. ya [ 13.01 1 DESIGN CONTROL: ~ I-

3. l' p0LICY-

. Modifications 1 to safety-related structures, systems and components'are accomplished,in accordance with approved designs. Activities-to 'I.- 'dev'elop'such designs'are~ controlled. Depending.on the type of modifi- ~ . cation.-these' activities include design and' field engineering; the; h " performance lof physics. seismic, stress, thermal, hydraulic,Lradia' tion. i ', ? and Safety, Analysis Report (SAR) accident analyses; the development jEj and'controllof' associated computer-programs; studies of material

5?

. compatibility; accessibility for inservice inspection and maintenance; .)' and determination of quality standards.. The controls apply to prepa- $1 ration"and. review-of design documents, including the correct transla-tion-ofl applicable regulatory requirements and design, bases into design.iprocurement:and procedural documents. , M. .( 3~ 2 . IMPLEMENT'ATION. P NE '%

3i2k1 Authority. and(responsibility.for modification activities :is under the-

[ 4 [g? '; cognizance lofJthe Nuclear Operations Department as described in g, -Sectionl1.0,cORGANIZATION ~ This authority andEresponsibility includes?

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' WNU ' .the1 preparation, review',: approval and verification of;the'following" Ldesignsdocuments:1 a) System descriptions; b) Design < input ;and' crite-J- ,yp h, ^f. s

ria;}c)lDrawingsandspecifications;and:d) Engineering'analysesand t

7 < associated: computer programs.

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r [. : /' '3 I.27 ;Errorsiandjdeficiencies.in approved design' documents, or in design ) imethodsL(suchias.c'omputer codes) that'couldia'dversely affectistruc ' f' f ures,7 systems;and components,are. documented. Action =18Ltaken to- ~j jQ* g t .-assureithatiche errors.and~ deficiencies are corrected.7 g," ' 4 e s '13.U3)1Matehials, parts.andhrocessesthat<are.essentialito' safety-related

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~ ~ 'functionsfareiselected and specified, basedfon the requirements ofL 3 L 4 4 0applicableScodes;and standards'or on-known, successful.use under-i:n f *; G M : similar conditions.: This includes standard commercial' materials,, l ~ lpW , parts and processes. :. Alternatively.cmaterials,; parts: and ? process'es, 4 j cmsyLbe1 qualified:for use'through qualification ^ testing:(s'e' Item e i W -3.2.8). :The: adequacy'of the selected materials,; parts and proc' esses-d. in assured--through the required' design verifications:orsapprovals.: l q w a r s < _j t' ? i ..)i ? 3 J3. 2 '.'4, JExceptions and waivers to:or deviations from the engineeringf(quality)L j yg standards (ie',1the required. dimensions,' material! properties,pfeatures; j g land other^ characteristics specified for modifications):are requiredL.by? H

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procedure and by. contract,;when applicable, - to 'be documented and-i

? N c'ontrolled. : d(See',,also, Section 15Lconcerning the approval.of;"re-V; [ i ' pair" or "useLas'is" dispositiuns %f nonconformances.) { ps o .g I. ? . ji ,f } .^ {pp PD1081-0535A-QA06 } w;,3n i d '

. '.,, _ -,,..,...:,,--,,,,,,,~,, -.,, - y Page 26 Rev 11 Date: 10/15/90 e 5.e.5 WS n modifications involve design interfaces between internal or g external design organizations or across technical disciplines, these g interfaces are controlled. Procedures are used for the review, approval, release, distribution and revision of documents involving design interfaces to ensure that structures, systems and components are compatible geometrically, functionally and with processes and environment. Lines of communication are established for controlling the flow of needed design information across design interfaces, including changes to the information as work progresses. Decisions and problem resolutions involving design interfaces are made by the CP Co organization having responsibility for engineering direction of g the design effort. g 3.2.6 Checks are performed and documented to verify the dimensional accuracy and completeness of design drawings and specifications (ie, the products of a design process). 3.2.7 Modification design document packages are revieved by the Quality l Assurance Department to assure that the documents that they contain 3 have been prepared, verified, reviewed and approved in accordance with Company procedures and that they contain the necessary quality assur-ance requirements. These requirements include the inspection and test requirements, quantitative and/or qualitative acceptance criteria and the requirements for documenting inspection and test results. 3.2.8 The extent of and methods for design verification are documented. The extent of design verification performed is a function of the impor-tance of the item to safety, design complexity, degree of standardiza-g tion, the state-of-the-art and similarity with previously proven g designs. Methods for design verification include evaluation of the applicability of standardized or previously proven designs, alternate calculations, qualification testing and design reviews. These methods may be used singly or in combination, depending on the needs for the design under consideration. When design verification is done by evaluating standardized or previ-ous'.y prover designs the applicability of su::h designs is confirmed. An di G rences from the proven design are documented and evaluated g fot ene intended application. g Qualification testing of prototypes, components or features is used when the ability of an item to perform an essential safety function cannot otherwise be adequately substantiated. This testing is per-formed before plant equipment installation where possible, but always before reliance upon the item to perform a safety-related function. Qualification testing is performed under conditions that simulate the most adverse design conditions, considering all relevant operating modes. Test requirements, procedures and results are documented. Results are evaluated to assure that test requirements have been satisfied. Modifications shown to be necessary through testing are made, and any necessary retesting or other verification is performed. Scaling laws are established and verified, when applicable. Test configurations are clearly documented. PD1081-0535A-QA06

w_ in & 9 y h. .( y, , t a 3: ; _ '., y t qs.. u3 WDn Page 27 ^ q. ' %YS Rev 11 N, Date: 10/15/90 l i Design reviews are performed by multi-organizational or inter-disciplinary l groups-or'by single individuals.- Criteria are estab- . j g' lished to determine-whenia formal' group review is required and when %'~ creview by an individual is sufficient. k k~~ Unless'othervike stated, the verification-'of design addresses all-information conveyed by the design document. When the verification is -: n -limited to certain areas or features, the scope or extent and any. 'W limitations on:the verification are documented. ,,g g a 3.2;9! Persons l representing applicable technical disciplines are assignedt to ' perform design verifications. :These persons.are qualified by appro-If. (priate education or-experience but.are not'directly responsible for 'the-design.: The designer's immediate supervisor.may' perform the [ UL" Everification_,,provided-that: [ b em, D)lHejistheonlytechnicallyqualifiedindividualavailable,and e y +,. J 4t, i t.n i l(2)!Helhas'not:specified atsingular design approach, ruled out certain iggA> design: considerations or established the design inputs for thef Sgt YD particular design aspect being verified. and-s s a1 j' z(3):His review is,Leither:5 s a.: TApprov'ed(int advan'ce' byi h'e supervisor's management; with. _ WM J t ydocumentation of the approval includedLin'the' design package,- [I [' (, 4Q s cor:

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Contro11sd by;a) procedure reviewed andl approved-by the; Quality: ~ t g 'AssuranceaDepartment.-lSuch procedure shall provide? specific'~ 4 2I gm ' <T l limitations <regaruing,the.typesJof' design work that may or-mayo not'be1 verified byla designer's supervisor, andeshall: provide 1 4 3 X; design?ve rification.. ' ~ ~ forfclear documentation-that-thereupervisor performid the 7 g b\\' (QS 'atidits-coverithe frequency, ef fectiveness, sand."teclknical+adequacyL S f nthe.use"of Laupervisorsjas design ' verifiers tohguard against abuse. - o ,.m c N lr0 ) {' O- % 3.2;10' When designs must be released for use before:they;.have been fully. tgy +

completed sor before they have. been: verified, the: incomplete or unv'eri '

N /gN lg %fied parts-of;the design and theLhold point toiwhich work may proceedJ q [j-g y' . irreversible: or 3before the' item is-reliedsonLtofperform a.Lsafety-- ^ Jare. identified.-JThis hold,, point ' occurs beforesthe xork "becomes s Pc a w related function.n aJustification'for;such early release is documented; ~ (w ^ ~ j J' q,

3.2.'1'1/ Computer codes ~ used in design are appropriately (documented, ' verified.

np certified for use'andrcontrolled.' Their use is'specified.' r 1 '{ . y '.q s i Y k ?. e i hPD1081-0535A-QA06 -k-

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yn' y e' n , -. der ii P- ^ Page 28 Rev 11 Date: 10/15/90 e s' ') ' E3.2.12 [. ( I.Cli' nges-i to design' output documents,--including field changes, are a Leontrolled.-in'~a manner commensurate with that used for the original' idesign.: Such changes.are evaluated for impact. Those that affect 'f fit 7 form or function are reviewed and approved.by-the same, or J y equivalent.l organizations that approved the original-design.- Informa-

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Ltionon. approved changes is transmitted to all.affected organizations. Ok pl;, i :a.. e>,;~ c .;i M,, s.': [(e ' k.- e p.1,... u+ <+ 3 L I ' m-Ci. ~ ^ c .m, + E' i 5 c + h h' ) i,3 g f. s f'k,, i, - 1 i s t 'g t' , ~;f,1 t i ? - e.I \\ g .t1 sc ';.x w+ ',' (,. 7 +- s -u, ) -.t'- % 9 9' y; x. . v.. g-; - 3.. I i ,-)., !) l', 's p h , O{' r llb. w ( 3 v I 'I. s v g.e,Nf. t3 i* J ( 3 m@jni", Q,; s 1 Ni y' .M,' I I (,.i_.s k .,g Hw, [ h".'i , ~f}.'. ' ' H I;.- }; : w, 'I N * % ~ i ~ i. i i 3 3 s

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I n Page 29 Rev 11 E' Date: 10/15/90: c3-3 = = 14.0-PROCUREMENT' DOCUMENT CONTROL 4.11 POLICY .j 1 Procurement documents for safety-related structures, systems, compo-nents and services _ define the characteristics of item (s) to be-pro-tcured, identify applicable regulatory and industry codes / standards- - I requirements and specify supplier quality assurance program require-Lments'to the extent'necessary to assure adequate quality. n- ! 1Er 4.2 IMPLEMENTATION (g g 4.2.1 -Responsibilities and authorities for procurement planning and for l gl preparation, review'and approval of procurement documents are delin-eated in/Section'~1.0, ORCANIZAT10N. gll y

f1

Procurement request packages are reviewed and approved prior to l

submittalsto:the Purchasing,' Land.and Materials Department. Review l includes: verification that the necessary quality requirements 'are (specifiedJ . m ' l The responsible project 1 engineer performs bid evaluations. ^ 4.2.2 ,SupplierLeelection' is described lin Section 7.0, CONTROL OF PURCHASED g 'MATERIALSkEQUIPMENTlAND' SERVICES. {n,, - 4 22.3 :' ;The(contients'.of procurement ~ documents vary a'ccording to the item (s) being purchase _d and it's function (s) in the plant.. Provisions.of this 'QAPD are considered?for.-. application-to: suppliers. As applicable,- 3' s 7 procurement documents includet; La6 Scope of' work.toibe performedL b { ), 1b. T'echnical; equirements,: with l applicable drawings,1 cpecifications, 7 3 . codes andsstandards identifiedLby' title, document number andi e t revision and date,;with any required procedures-suchias. special ~ %[ s. ;",. process instructionsJidentified in such n-way as to indicateL ~ 1 y n source'and need... y 3 c. Regulatory, administrative :and reporting requirements. ,EL_ g; 'd.-lQuality requirements appropriatefto:the complexity [and scope of. yM 'theywork,jincluding necessary testa andtinspections. Ib cc. - A requirement : for'a documented QA' Program Lsubject to CP Co review - M 'and written concurrence prior:to'the start of work. -lm

f. : A' re'quirement' f or the supplier to invoke. applicable quality' E

5) requirements on subtier supp.11ers. ^ l eg. Provisions for access to supplier.and subtier suppliers' facili-i tiestand records for inspections, surveillances and audits. v i 'm E' "PD1081-0535B-QA06 "93 = ;g_ b, I

y n;, j 3 Page 30- - i Rev 11 t 5 1' fi Date: 10/15/90- -l. s E^. (;; w s LIdentificationqof' documentation to.be provided by the supplier, - g 4 'h.. fidentification of; documents be compatible with the Engineering- {g m, o' 1 Records; Center System,'the schedule of submittals and identifica-. l[ tion ofgdocuments requiring CP Co approval. 0i -A 5 n Q, , 4.' 2. 41 Trained,7 qualified and certified personnel-perform and de-cument s p[ c' 4. reviewstof. procurement request packages to assure.that:- 4 y a Quality.; requirements (see 4.2.3-of this Section) are correctly . 5j ~, g a. stated,7 nspectable, and; controllable. j 1 ~; "S ' Adequate a'ceptance.andcrejection criteria are' included.- b.1 e 6 .4 T' h' e procurement : documents; have been pt epared, reviewed'. and I; ft c., k,, y;m 5}-{ ' approved perfthefQA Program requirements. y g , i4.2;54. Changes.co the: technical or quality requirements in procurement Edocumentanare(controlled inLa manner commensurate:withithat used for g, i u.UW the>origina1' requirements.. Those that couldLaffeetsfit,. form.;func-g:# D -?tioniorLthelnecessary assurance'of quality are. reviewed.and ' approved. @g ], by? theisams, lor equivalent, 'orgarazations!.that approved the ' original.~ j N"; s

procurementirequest;p.ackages.

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,2 w /4 lI y f" Page 31 Rev 11 m 8; o l Date: 10/15/90 4 r Wi f,b5M INSTRUCTIONS; PROCEDURES AND DRAVINGS yL, ,s H.W c5.1; POLICY + Activities:affecting the quality of_ safety-related structures, systems i >t, andicomponents are accomplished using instructions, procedures and. t JM~ idrawings appropriate to=the circumstances which include acceptance t criteria for-determining:1f an activity har been satisfactorily-(, completed.- J 512'

IMPLEMENTATION' Q4 The' authority and responsibility for performing activities affecting the' quality;of safety-related' structures, eystems and components are I '

y., yassigned-as' described;in Section'1.0, ORGANIZATION. Management-ipersonnel assigned these responsibilities assure that the instruc-

>q'W tions,1 procedures =andidrawings necessary totaccomplish the-activity

'm

are) prepared and-implemented'.

2, f Instructions,( procedures-and drawings-incorporate (1)i a' der cription of ,thepactivity, to.belaccomplished and_ '(2)-' appropriate; quantitative (such I,,I J Eas5 tolerances and[ operating' limits)'and qualitativeL(such as-workman-y o,[. 'W ship standards)Lacceptance criteriarsufficientito determine that>the . f cactivity has been~ satisfactorily accomplished. Iy,.# W Temp'oraryJprocedures may be issueditoiprovide management instructions -which have'short-term l applicability.., Temporary procsdures include-a. /.M h' # / de'signationfof?the timeLperiod:during which they may be used.. t L, Y Thdiprocedures used by CP Co+to contro Eits activities include th'e D s 5 g+

followin6:

I'&m a ..... iv bi, +1db41ministrativeiProcedures'i, including! Quality Assurance Department-f ; j.g 9P rocedures ~.- ~ \\ y 2.'Systemproceduresithatl describe:theLoperationofItheplant. L M -S. tart-up procedures:that prov'ide for' starting the reactor from hot-g Ig '3. t or cold condition and recovering from reactor trips.: .e. + r .y : 4. - LShutdownuprocedures that provid,e lf ori controlled, reactor ' shutdown 1 A 4 .or shutdown following reactor trips, - [ m f. f5. Power' operation-andloadchang1Ngproceduresthatprovidefor- , JsM. steadyM tateLpower> operation and load-changingh including responsel ~ x to una'nticipatedlloadLehanges.- ~' 7 m i SN y .6. LProc'ess monitoring procedures that provide for monitoring' plant .I! c ,1 system

• performance and-which, as.~ appropriate,. identify limits for.

L significant process" parameters. ~ fr PD1085-0535B-QA061 j ~ 14 p a

I L% Page 32 Rev 11 Date: 10/15/90 .s.

7. Fuel-handling procedures that provide for activities such ast a.

Core alterations ^ b., Refuel ng

c.

Tuel accountability s t. d. ' Receipt and shipment of fuel e. Nuclear-Saiety measures

8. Maintenance = procedures that provide fort n

a.- Preparation for maintenance . b.. Performance of maintenance 'q

c. : Post-maintenance and operability. checks and tests

e d. Use of support 1ng maintenance documents gg 1 I 9'.' Radiation control procedures that provide fort 'a. Implementation of the radiation control prog am inclu' ding the >p acquisition of radiation data o D.' b..- Identification of equipment for performing radiation surveys

c. ' Measurement, evaluation-and' assessment of radiation hazards.

j ' 100 Calibration and test procedures that provide for $r* f a., ! Periodic calilitation and testing of. safety-related instrumen-N tation and ent. trol systems"

b.'. Calibration of portable measuring and toot equipment used in n

activities'affecting' safety '11. Chemical-radiochemical control procedures that provide for activi-ties including t a..' Sampling and analyses l [ b'. -haintenance of coolant quality T c. Control of deleterious agents w d. Control.. treatment and management of radioactive wastes e. The control of radioactive calibrat on sources .F PD1081-0535B-QA06 ' 3 W

i Pags 33 Rev 11 Date: 10/1$/90 i

12. Emergency procedures that provide guidance for:

Operations during potential emergencies so that a trained a. operator vill know in advance the expected course of events I that will identify an emergency and the immediate action he should take b. Identifying symptoms of emergency conditions I c. Monitoring automatic action d. Immediate operator action i c. Subsequent operator action i

13. Emergency Plan Implementing Procedures i

I

14. Inspection, test and examination procedures that identify:

l a.

Objectives ) I .b. Acceptance criteria l c.. Pretcquisite and special conditions ^I d. 1.imiting conditions ) e. Test or inspection instructions f. Any required special equipment or calibration 4 t g.. Hold and Witness points, as appropriate

15. Modification procedures that provide fort-I l

a. Administrative cor.t";1 and technical support luring plant [ modifications-

b. ~The basis for a consistent method of performing recurring engineering, construction and quality assurance activities c.

Control of the interfaces between CP Co and its suppliers 11 L'

d. 'Offsite management control and visib uity-I l

Control of onsite quality-related modifJcation activities that e. y E< assure the QA Program is implemented and its effectiveness is annessed and reported I ~ PD1081-0535B-QA06

Page 34 Rev 11 Date: 10/Is/90 ~ I L I I L g I TilIS PAGI' INTENTIONALLY LEFT BLANK I I I I I I I I = I I I g reiee1.es3ss.oA.

l Pego 35 Rev 11 I Datet 10/1$/90 i 6.0 DOCUMENT CONTROL 6.1 POLICY Documents controlling safety-related activities within the scope defined in Section 2.0, QUALITY ASSURANCE PROGRAM are issued and changed according to estabitsbed procedures-Documents such as instructions, procedures and drawings.' including changes thereto, are i 1 reviewed for adequacy, approved for release by authorir.ed personnel and are distributed and used at the location where a preacribed activity is performed. Changes to controlled documents are reviewed and approved by the same t organizations that performed the original review and approval or by I other qualified,. responsible organir.ations specifically designated in accordance with the: procedures goverr.in these docunients. I,,. 6.2 IMptEMENTAT10N. l l6.2.1; Th'e authority and responsibility for the control of documents are described.in Section 1.0, ORGANIZATION. .,6. 2 '.2 . Coritrols are established for approval, issue and change of documents du the.following categoriest t 'a. Design. documents (eg, eniculations, drawings, specifications. analyses) including. documents related to computer codes t a b.. As-built drawings (record drawings) and related documents

c.

Procurement documents ? ^ . d.1 ' Instructions.and procedures for activities such as fabrication. c construction, modification, installation, inspection. test and plant maintenance and operation -v' e. . Procedures that implement the' Quality Assurance Program I f. ~ Final Safety Analysis Report. g. . Reports of nonconformanceo

h.. Plant Technical' Specifications 6.2.3

.The review, approval, 1ssue and change of the above documents are E5 c controlled by: l r I* a. Establishment of criteria to ensure that adequate technical and quality requirements are incorporated b. Identification;of the organizations responsible for review, i I? approval, issue'and revision PD1081-0535B-QA06 i .m t e + +,. s +. .b

o

\\ ,e, peg 2 36 ~ Rev 11 i Date: 10/15/90 c. performance and documentation of a review for concurrence with Quality Assurance related aspects of items 6.2.2 a, c, d (except l for operating procedures), e and g. I d. Review of changes to documents by the organization that performed i the initial review and approval or by the organization designated in accordance with the procedure governing the review and approval of specific types of documents 6.2.4 controlled documents are iesued and distributed so thats a. The documents are available at the work location prior to commenc-ing work i 6 b.- Obsolete or superseded documents are removed from work areas and . replaced by applicable. revisions in a timely manner 1 6.2.5 Master lists.or equivalent controls are used to identify the current g revision of instructions, procedures, specifications, drawings and g f I' procurement documents. When master lists are used they are updated and distributed to designated personnel who are responsible for maintaining current copies of the lists. 6.2.6 Accurate as-built drawings (racord drawings) and.related documentation s are prepared.in'a timely manner. l T t I I Ia 1 I; ' L r' 13 L pD1081-0535B--QA06 g'

page 37 Rev 11 Date: 10/15/90 q 7.0 CONTR0h 0F PURCHASED MATERIAL EQUIPMENT AND SERVICES 7.1 p0LICY Activities that implement approved procurement requests for safety-related material, equipment and services are controlled to assure confermance with procurement document requirements. Controls include I. a system of supplier evaluation and selection, source inspection, examination and acceptance of items and documents upon delivery. and periodic assessment of supplier performance. Objective evidence of , I quality that demonstrates conformance with specified procurement document-requirements is available to the nuclear power plant site prior to use est equipment, material or services. 7.2 IMPLEMENTATION 7.2.1 Authority and responsibility for implementing the controls outlined herein are described in Section 1.0. ORGANIZATION. 7.2.2 Cp Co qualifies suppliers by performing a documented evaluation of their capability to provide items or services specified by procurement I documents. To remain qualifted. suppliers involved in active procure-ments are reevaluated annually and are audited triennially. If the a Coordinating Agency for Supplier Evaluation Register is used to I establish the qualifications of the Supplier, the documentation identifies the audit used. Evaluation of suppliers holding applicable ASME Certificates of Authoritation is done'by reference to the current ASME listing of certificate holdera. Supplier evaluation and triennial audits are not necessary when the items or services supplied ato all of the followingt I< a...Relatively simple and standard in design, manufacture and, test, and a b. Adaptable to standard or automated' inspections or tests of the end om product to verify quality characteristics af ter delivery, and -c.: Such that: receiving inspection does not require operations that ~ -could' adversely affect the integrity, function or cleannens of the item. c In the'above' cases, source and/or receipt inspection provides the necessary assurance of an acceptabic item or' service. 7.2.3 Supplier activities that affect quality are verified in accordance with written procedures. These procedures provide the method of verifying (such as audit, surveillance or~ inspection) and documenting I that the characteristics or processes meet the requirements of the procurement document.' For commercial "off-the-shelf" items where the ' requirements for a specific quality assurance program appropriate for I nuclear applications cannot be imposed in a practical manner, source l pD1081-0535B-QA06

pegs 38 L Rev 11 Date: 10/15/90 verification is used=to provide adequate assurance of acceptability unless the quality of the item can be adequately verified upon receipt. 7.2;4 . Spare and replacement parts are procured in such a manner that their performance and quality are at least equivalent to those of the parts that will be replaced.

a. -Specifications and codes referenced in procurement documents for spare or replacement items are at least equivalent to those for

'the original items or to properly reviewed and approved revisions, b. parts intended as spares or replacements for "off-the-shelf" items, or other items for which quality requirements were not originally specified, are evaluated for performance at least equivalent to the original. i' c. Where quality requirements for the original-items cannot be E determined, requirements-and controls are established by engineer-B ing evaluation performed by qualified individuals. The evaluation assures there is no adverse effect on interfaces, interchangeabil-ity, safety, fit form, function or compliance with' applicable regulatory or code requirements. Evaluation results are documented.- 4 w d. Any additional or modified design criteria imposed after previous ' procurement of the item (e), are identified and incorporated. = 7.2.5' Receipt inspections are performed to verify that items are undamaged and properly identified, that they conform with safety-related pro-curement requirements not previously verified by source surveillance or inspection and that required supplier furnished documentation is available. Items inspected are identified as,to their acceptance- ~ 1 status prior to their storage or release for-installation. 7 2.6 Suppliers are required to furnish'the fc11owing records: a. Applicable drawings and related engineering documentation that ' identify the purchased item and'the specific procurement require ' ments (eg codes, standards and specifications)' met by the item. b. Socumentation identifying any procurement: requirements that have not been met. .c. LA description of those nonconformances from the procurement requirements dispositioned " accept as is" or." repair." 'd.- Quality' records as specified in the procurement requirements. The acceptability of these documents is evaluated during source and/or receipt inspection. I pD1081-0535B-QA06

E o Pago 39 Rev 11 Date: 10/15/90 I 7.2.7 Supplier's certificates of conformance are periodically evaluated by audits, independent inspections or tests to assure that they are valid. The results of these evaluations are documented. I g ) k 3 hl Si g

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I i Pcg2 41 Rev 11 I Date: 10/15/90 8.0 IDENTIFICATION AND CONTROL OF ITEMS 8.1 POLICY Safety-related materials, parts and components (items) are identified i and controlled to prevent their inadvertent use. Identification of items is maintained either on the items, their storage areas or containers or on records traceable to the items. 8.2 IMPLEMENTATION 8. 2.' l Controls are established that provide for the identification and control of materials (including consumables), parts and components. (including partially fabricated assemblies). Responsibility for the ,I identification and control of items is described in Section 1.0, i ORGANIZATION. I

8.2.2-Itemn:are identified by physically marking the item, its storage area or its container or by maintaining records traceable to the item.

The [ method of identification is such that the quality of the item is not degraded. 8.2.3-Items are traceable to applicable drawings, specifications or other y pertinent documents to. ensure that only correct and acceptable items are used. Verification of traceability is performed and documented i . prior to release for' fabrication, assembly or installation. l t i f i .Il i l l 11 PD1081-0535B.QA06 l

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n Tcas 43 Rev 11 Date: 10/15/90 ^ .f 9.0 CONTR01. OF SPECIA1. PROCESSES 9.1 POLICY Special processes affecting safety-related structures, systems and components are controlled and are accomplished by qualified personnel using qualified procedures and et.uipment in accordance with applicable j I codes, standards, specifications, criteria and other special require- .4 ments. 9.2 IMPLEMENTATION 9.2.1 processes subject to special process controls at CP Co are those for h which full verification-or characterization by direct inspection is g impossible or impractical. Such processes include welding, heat-treating, chemical cleaning, application of protective coatings,. concrete placement and> nondestructive examination. Ig 9.2.2" Organizational responsibility for implementation of special processes, and!for qualification of proceduren, personnel, and' equipment used to perform special? processes-is indicated in Section 1.0, ORGANIZATION. [ 9.2.3' Special process procedures are prepared by personnel with expertise in the discipline involved. The procedures are reviewed for technical , adequacy by other personnel with the necessary technical competence.. i and are. qualified by testing, as necessary. l 9.2.4 Special process perconnel qualification is determined by individuals c AM authorized to administer the pertinent examinations. ' Certification is 9 '[ based on: examination results, personnel qualification is kept current ~ lby-performance'of the special process (es).and/or reexamination at time e s . intervals,specified by. applicable codes, specifications and standards. i Unsatisfactory performance or, where applicable, failure to perform' [ ~ within the designated time intervals requires recertification. 9.2.5 .For special processes that require qualified equipment, such equipment. i"

is; qualified in accordance.with applicable codes, standards and i

specifications. ~ '9.2.6 Qualification records are maintained in accordance with QApD Section s + 17. 9 '. 2. 7 .The Quality Assurance Department audits special process qualification y activities.and performs-insp'ection and surveillance of special pro-cesses to assure they are satisf actorily performed when specified by n-applicable inspection planning and/or site procedures. Such inspection l and surveillance includes verification that process data' are recorded - [ as required, are within specified limits and are performed in accor-

m; dance with applicable requirements.

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Pago 45 Rev 11 l I> i Date: 10/15/90 10.0 INSPECTION 10.1 POLICY Activities affecting the quality of safety-related structures, systems and components are inspected to verify their conformance with require-7 ments. These inspections are performed by people other than those who I perform the activity being inspected. Direct inspection, process monitoring, or both, are used as necessary. Ilold points are used as necessary to ensure that inspections are accomplished at the correct points in the sequence of work activities.- 10.2 IMPLEMENTATION j 10.2.1 Organizational responsibilities are as described in Section 1.0, ORGANIZATION. 10.2.2 Inspections are applied to procurement, maintenance, modification, 1

testing, fuel handling and inservice. inspection to verify that-items and activities conform to specified requirements. Work authorizing

documents (eg; procedures, instructions, maintenance work orders) are

,I' reviewed.in accordance with established criteria to do the following j 't as-necessary:-

a. : Determine'the need for inspection (s).

b. Identify theLinspection organization. 5 c. Identify lloid and Notification points. d. Determine how and when the inspections are to be performed. Specify measuring 'and test equipment of,the necessary accuracy for j ~ e.- lg performing inspection. y[ f. ' Provide for documentation of inspection results to provide ade-q quate: objective evidence. of acceptability.

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t Inspection is performed at each operation where.it is necessary to - f verify quality.' [ L Process monitoring is used in whole or in part where direct inspection alone is impractical or-inadequate. an -j: 'i 10.2.3. Training and qualification programs for personnel who perform inspec-tions, including nondestructive. examination, are established. imple-- mented and documented in accordance-with Section'2.0, QUALITY. ASSURANCE PROGRAM. These programs meet the requirements of applicable I-codes and' standards..The Quality Assurance Department reviews!and concurs with any such programs that are not under its direct responsi-I .bility. Qualifications and certifications of inspection and NDE personnel are maintained. PD1081-0535B-QA06

k 11 Paga 46 Rev 11 Date: 10/15/90 J J 10 2.4 Inspection requirements are specified in procedures, instructions, l drawings or checklists and are either provided or concurred with by a' the authorized inspection planning organization. They (procedures, etc) provide for the following as appropriate: a. . Identification-of applicable revisions of required instructions, drawings and specifications. ll b. Identification of characteristics and activities to be inspected. W c. Inspection methods. L d.- Specification of measuring and test equipment having the necessary ,o accuracy. e. Identification of personnel responsible for performinr. the inspec-tion. y

f.. Acceptance and rejection criteria.

1 Recording of the inspection results and the. identification of the g g.1 s inspector, g o, 10.2.5 Inspection' points are; designated as mandatory hold points by desdgnat-s ed inspection personnel when confirmation is needed that the work 'l. accomplished.up to that point is acceptable before the work can be. "l ' allowed to proceed further, liold point inspections are. performed, and work is ' released for further processing or use, by designated inspec- ,g. . tion' personnel.. ~ lloid points may be waived only by; the designated _ g' inspection planning organization. g --10.2.6,: Inspections are performed and documented in accordance with'the. +: ' written' instructions providea.. The results are. evaluated by-designat-ed personnel in order to ensure that the results-substantiate the acceptability of the item or work. Evaluation and review results are documented. I 10'2;7 zinspection.of work associated.only with normal operation of the plant. EI such as surveillance tests,and verifications of routine maintenance 3.! may be performed.by individuals in the same group as. that which

performed the work, but.not by personnel who directly performed or gl supervised the work. Peer inspection is acceptable.provided:

g, j i La. The quality of'the work can be demonstrated through a functional test when the work involves breaching a pressure retaining item. l b. The qualification criteria for the inspection personnel have been l reviewed and found acceptable by the Quality. Assurance Department.- Minimum criteria are that individuals performing inspection must p possess qualifications at least equal to those of the persons i authorized.to perform the task (s) that will be inspected. PD1081-0535B-QA06-

I h pass 47 Rev 11 ~ Datet 10/15/90 11.0 TEST CONTROL-11.1 POLICY Testing is performed in accordance with established programs to 'demonstratt that cafety-related structures, systems and components will perform satisfactorily in service. The testing is perf ormed in I accordance with written procedures that incorporate specified require-ments and acceptance criteria. The test program includes qualifica-tion (as applicable), acceptance, pre-operational, start-up, .g surveillance and maintenance tests. Test parameters, including any 3 . prerequisites, instrumentation requirements and environmental condi-tiona are specified and met. Test resulta are documented and evaluated. 11.2 ' IMPLEMENTATION 11.2.1-Organizational responsibilities for testing are described in Section 1.0, ORGANIZATION. B 11 2.2 Tests are performed in accordance.with programs, procedures and 'g criteria.that designate when tests are required and how they are to be L T performed. Such; testing includes the followingt l'

n. - Qualification tests, as applicable, to verify design adequacy in accordance with Section 3.0, DESIGN CONTROL.

b. Acceptance tests of equipment and components to assure their I1 proper operation prior.to delivery or to pre-operationni tests. pre-operational tests to assure proper,and safe operation of gg c. ,g systems and~ equipment prior'to start-up tests or operations. d.'- Start-up tests, including precritical. criticality, low-power and I< power' ascension tests, performed after refueling to assure proper and. safe operation;of systems and equipment. Surve.111ance tests to. assure continuing proper and saf e operation I, e. of systems and equipment.' f.: Maintenance tests after preventive or corrective maintenance.- I, 11.2.3. Test proc 6dures and; instructions' include provisions for the following, as applicablet;. a. The requirements and acceptance limite contained in applicable design and procurement. documents.

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i; ; Cf, l $.7 p" ^ pag 2 48 .O o Rev 11 Date: 10/15/90 b. Teet prerequisites auch as calibrated instrumentation, adequate g test equipment and instrumentation including accuracy require-g ments, completeness of the item to be tested, suitable and con-trolled environmental conditions and provisions for data j collection and storage. c. Instructions for performing the test. I.i -T 'd. Mandatory inspection hold points for witness by the appropriate authority. .c 4 e. Acceptance and rejection criteria. r f. Methods of' documenting or recording test data and results. s g... Assuring that-test prerequisites have been met. i I h. QA verification of completion of modification activities. Test' procedures and instructions'are reviewed by the engineering organizations for technical content and by the Quality Assurance g Department for QA aspects. g - 11.2.4 iThe. Quality Assurance Department verifies, through audits. inspection. H and surveillances,'that test.results~are documented, evaluated and their acceptability is: determined by responsible personnel.- y 3 1 g [ t I I L E: i 1 5 j

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-;._=_. S Page 49 Rev 11 Date: 10/15/90 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 POLICY Measuring and testing equipment used in activities affecting the quality of safety-related systees, components and structures are properly identified, controlled, calibrated and adjusted at specified intervals to maintain accuracy within necessary limits. 12.2 1MPLEMENTAT10N _AJ 12.2.) The authority and responsibility of personnel establishing, imple-menting and assuring effectiveness of calibration programs is de-scribed in Section 1.0, ORGANIZATION. '12.2.2 Procedures are established for measuring and test equipment utilir.ed in the measurement, inspection and monitoring of structures, systems l and components.. These procedures describe calibration technique and m; , frequency and maintenance,and control of the equipment. Measuring-and test equipment is uniquely identified and is traceable .12.2.3 to its calibration source. 12.2.4 CP Co uses'a system of labels to be attached to measuring and test equipment to display the next calibration due date. Where labels cannot be attached, a control system is used that identifies to potentia 1' users any equipment beyond the calibration due date. 12.2.5 Measuring >and test equipment (M&TE).and installed plant instrumenta ' tion is calibrated at'specified intervals based on the required accuracy, purpose, degree of usage, stability characteristics, and -I, other conditions affecting the measurement. Calibration of M&TE is against standards that have an accuracy of at least'four times the required accuracy of the equipment being cali- .brated,or, when this is not possible, have an accuracy that assures 1 the equipment being calibrated will be within required tolerance and -g the basis of acceptance is. documented and authorized by responsible 3 management. Calibration. standards used for installed plant instrumentation shall 'a s j normally have' greater accuracy than the instrumentation being cali : brated.. Standards with the same accuracy may be used when shown to be The basis for this' adequate:for specific calibration requirements. acceptance is documented and is approved by responsible management. ~ 12.2.6 -Calibrating standards have' greater accuracy than standards being calibrated. Calibrating standards with the same accuracy may be used 8 if it can be shown to be adequate for the requirements and the basis 'of' acceptance is documented and authorized by responsible management. e -PD1081-0535B-QA06

i I! Pcgs 50 j Rev 11 Date: 10/15/90 - 12.2.7 Reference and transfer standards are traceable to nationally recog-Ei nized standards; where national standards do not exist, provisions are 3l established to document the basis for calibration. ] ' 12.2.8 When measuring and testing equipment used for inspection and test is found to be outside of required accuracy limits at the time of cali-bration, evaluations are conducted to determine the validity of the .results obtained since the most recent calibration. The results of evaluations are documented. Retests or reinspections are performed on y suspect items. Yi > E: 4 (<' q i ) IJ I. I L Il 1. Io.q t,.

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x f i Pagc $1 Rev 11 Date: 10/15/90 13.0 ' ilANDLING, STORAGE AND SHipp1NG 13.1-p0LICY Activities with the potential for caus.ing contamination or deteriora-tion that could adversely affect the ability of a safety-related item to perform its intended safety functions, and activities necessary to I prevent undetected or uncorrectable damage are identified and con-trolled. These activities include. cleaning, packaging, preserving, handling, shipping and storing. Controls are effected through the use I of. appropriate procedures and instructions implemented by suitably trained personnel. 13.2 IMPLEMENTATION Il f 13.2.1 The authority and responsibility of personnel implementing and assur-ing the effectiveness of material cleaning, handling, storing, packag-I. ing, preserving and shipping activities is described in Section 1.0, ORGANIZATION. '13.2.2' procedures are used to control the cleaning, handling, storing, B packaging, preservinE and shipping of materials, components and systems in accordance with design and procurement requirements. These 3. procedures include, but are not limited to, the following functions : c a.- Cleaning, to assure that required cican11 ness levels are achieved .and. maintained. b. Packaging and prerervation, to provide adequate protection against -damage er deterioration. When necessary, these procedures provide for:special environments such as inert gas atmospheres, specific-I moisture content levels and temperature' levels. c. llandling', to preclude damage or. safety hazards. E, d. Storingi to minimize the' possibility of loss., damage to or deteri-oration of items in storage including consumables such as chemi-8. .cals, reagents and lubricants. Storage procedures also provide methods to assure that specified shelf lives.are not exceeded. I' I I l !Bi " " " ' - " " " ^ "

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Pega 53 ^ Rev 11 Date 10/15/90 14.0 INSPECTION, TEST AND OPERATING STATUS l14.1 POLICY ' Operating status.of safety-related structures, systems and components is indicated by tagging of valves and switches, or by other specified i med is, in such a manner as to prevent inadvertent operation. The I status of inspections and tests performed on individual items is clearly indicated by markings and/or logging under strict procedural controls to prevent inadvertent bypassing of such inspections and tests. 14.2 IMPLEMENTATION . I'4. 2.1 Organir.ational responsibilities are as described in Section 1.0, ORGANIZATION.. I-14.2.2 For modification activities, including item fabrication, installation and ~ test, procurement documents, service contracts and procedures 'i specify the degree of control required for the indication of inspec-tion and' test status of structures, systems and components. 7 t, 14.2.3-Application and removal of: inspection and welding stamps and of such status indicators as tags, markings, labels, etc. are controlled by I ' procedures. i. 14.2.4 The' sequence of inspections, tests and other operations important to ,I safety are-controlled by procedures. Changes in the ' approved sequence are subject'to the same review and approval as the. original. (14.2.5 The status of nonconforming, inoperable or malfunctioning structures, I systems and components is' clearly identified and documented to prevent inadvertent'use. i y I I I I 'PD1081-0535B-QA06

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A Page 55 Rev 11 Datet 10/15/90 15.0 NONCONFORMING MATERIALS, PARTS OR COMPONENTS 15.1 p0LICY Safety-related materials, parts or components that do not conform to requirement' are controlled in order to prevent their inadvertent use. Nonconform g items'are identified, documented, segregated when d dispositioned. Affected organizations are notified of practical .i nonconfor mees. 15.2 IMPLEMENTATION 15.2.1 Items,. services or activities that are deficient in characteristic, -documentation or procedure, which render the quality unacceptable or indeterminate, are identified as nonconforming and any further use is controlled. Nonconformances are documented and dispositioned, and- . notification'is made to affected organizations. Personnel authorized I< to disposition, conditionally release and close out nonconformances are designated.. The authority and responsibility for the implementa-- tion of activities related to the processing and control _of noncon-forming materials, parts or components are described in Section 1.0, g . ORGANIZATION.

n a.

Nonconforming items.are identified by marking, tagging or.segre-- J gating or by documented administrative controls. Documentation-describes.the nonconformance,' the disposition of the nonconfor-mance'and the-inspection requirements.- It also includes signature ' approval of the disposition.

b. _The original' inspection planning' authority reviews the disposition of nonconformances, and' documents concurrence with the acceptance..

"[ conditional' release or repair.of a nonconforming item.

c. ' Items that have been repaired or reworked are inspected and tested-in accordance with the original inspection and test requirements or alternatives that have-been documented'as acceptable and concurred with by the original inspection planning authority.

d.. Items that'have the disposition of " repair" or "use as is" require documentation justifying acceptability. The changes are recorded to denote the-as-built condition.

e. !The' Quality Assvrance Department reviews'"use as.is" or " repair" dispositions wh.ch result in deviation from original design or specification' requirements.

7 15.2.2 Dispositions of etnditionally released items are closed out before the _ items are relied spon to perform safety-related functions. j k = 4 3

O '; I. Page 56 o Rev 11 , 1 g, 'J Date: 10/15/90 .r ..\\ - 15.2.3 Prior to the initiation of preoperational testing on an item, all lj nonconformances are corrected or dispositioned and evaluated for 3; s impact upon the item or the testing program. 15.2.4 Nonconformance reports are analyzed to identify quality trends. Trend reports, which highlight significant results, are issued periodically . to upper management for review and assessment. I o t 4 I 'd L. jh i r s I t 4 ' ), l, Ij .(' l;.. -l 1 h ( I.'.; I L! . ]'Il , Polo 81-0535B-QA06 W

i Pcg2 57 Rev 11 I3 Date: 10/15/90 16.0 CORRECTIVE ACTION l 16.1 p01,1 CY Conditions adverse to quality of safety-related structures, systems, components or activities, such as failures, malfunctions, deficien-cies, deviations, defective material and enuipment and nonconformances pg are identified promptly and corrected na soon as practical. For significant conditions adverse to quality, the cause of the ll condition is determined and corrective action is.taken to preclude W repetition. In these cases, the condition, cause and corrective action taken is documented and reported to appropriate levels of management for review and assessment. L 16.2 IMP 1.D4ENTATION F i 16.2'.1.The responsibility and authority for the control of corrective action J are described in.Section 1.0, ORGANIZATION. l.le, N' 16.2.2-Controls are established to assure that conditions adverse to quality. 3 are identified and documented and that appropriate remedial action is-l taken. ' 16.2'.3 For significant conditions adverse to quality, necessary corrective-action =to promptly determined and recorded. Corrective action in l cludes determining the cause and extent of the condition, and taking -i appropriate. action to preclude similar problems in the future. The controls also' assure that corrective action is implemented in a timely manner. The Quality. Assurance Department.' reviews and-documents concurrence with-actions.taken to prevent recurrence of significant I ~ conditions adversc to quality, performs follow-up to verify proper j . implementation and. determines if additional' action (such as audit or j i-surveillance) is necessary to verify the: ef fectiveness of action (s). -t I+' taken. I I %p 4 g e m el-05 m.. e i - + ,s .-,4

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g> Pags 59 Rev 11 Dates'10/15/90 l 17.0 QUALITY ASSURANCE RECORDS 17.1' POLICY-Records that furnish evidence of activities affecting the quality of safety-related structures, systems and components are maintained. They are accurate, complete and legible and are protected against damage, deterioration or loss. They are identifiable and retrievabic. . 17.2 IMPLEMENTATION i 4 17.2.1. Respcnsibilities-for the identification and control of QA records are described in'Section'1.0, ORGANIZATION. ~ 17.2.2 Documents that' furnish evidence of activities affecting quality are generated and' controlled in accordance with the procedures that govern - those activities.: Upon completion, these documents are considered v ~ records. These records includes. E ^ a'.; Results = of reviews, inspections, surveillances, tests, audits and ' material analyses b.' Qualifiestion of personnel, procedures and equipment + ' c '. ' Operating logs- .y 1 \\ d. MaintenanceLand modification procedures and related inspection 3 E ' results tei:-Reportabic occurrences <i y )

f.

Records. required by1the plant' technical specifications y 1 g.- Nonconformance reports .I4 I y .h. Corrective. action reports'

1. - 10ther documentation -such: aa drawings, specifications, procurement

[

M{: u" documents, calibration procedures and reports. i 4 4 I (17.2.3' Inspection and test. records contain the following where applicablet. IL f

a.: - A descrintion of the type ' of observation i

' b.. ' The date and results of the inspection or test c. Information,related'to conditions adverse-to quality (d.. Inspector or data recorder identification e. Evidence es to the acceptability of the results gj g. i PD 081-0535B-QA06 ~D

-,9, d pH V ; phi n] t Yk [M < ... f Page 60 69, Rev 11 Date: 10/15/90 22 y t il .f. . Action'taken-to resolve-any discrepancies noted L17!2.4 When.a document ~becomes a record, it is designated as permanent or 1, . nonpermanent and then transmitted to file. Nonpermanent records have e9 'specified ' retention -times. Permanent records are maintained for the-lll% f lifeiof the item.. i j-17.2.5 Temporary' storage of completed documents.during processing to become-E fl,

records is in special fire-resistant file cabinets.

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4 "17.2.6:.Only'. authorized personnel may issue corrections or supplements to

' records 3, ft '1N2^.7:- TraceabilityLbetween the' record and the item or activity to which it 4 -applies 1s;provided. A: ,s g!;p + { f'(17.'218hRecords'.arestoredinremote, dual =facilitiestopreventdamage, deterioration or loss due to natural or: unnatural causes. Fecords' that can?onlyLbe: stored -as originals.. such as radiographs and some ll 4 strip: charts are retain'ed in a four-hour fire-rated f acility. ,u_ = s,, '=' 3; s D y i

g

.,i P M .m s 3 f i W .i X .<.i 4 f f: r \\ '.-4. f 7 y b, ,q 4 y '3; N s. +1 3 h 5 i 4 .t i 1 ' j) ....f. - f.i PD1 Bi 0535B-QA06j 6 J a e n. i i.. l g 'a 4,

- m ( Page 61 Rev 11 m Date: 10/15/90 18.0c AUDITS-18.1: P'OLICY. . A comprehensive' system of audits is carried out to provide independent evaluation of compliance with and the effectiveness of the Quality ? Assurance Program, including those elements of-the program. implemented I by suppliers and contractors. Audits are performed in accordance with. written procedures or checklists by' qualified. personnel not having j N-direct responsibility in the areas audited. Audit results are docu-( mented'and are reviewed by management. Follow-up action is taken m-where indicated. 18.2-IMPLEMENTATION 18.2.1 Responsibility and authority for the audit program is described in ~ Section 1.0'. ORGANIZATION. ~18.2.'2 -Internal audits are performed in accordance with established schedules 1 that. reflect-the status and importance to safety of the-activities 'T 7 eing performed..All' areas where the' requirements of 10 CFR 50 b A lAppendixiBjapply are audited within a period of two years. The .following are audited at 1 east once every 12 months: ~ 1 a ~ Conformance of. facility operations with applicable conditions of:- a. 7 the: technical specifications and license b.1 The performance,; training and qualifications of the' facility. staff -J 'c.t Controls'over plant modifications. including the frequency, 1t effectiveness anditechnical adequacy.of the use of supervisors as -d design verifiers. 18.2.3 gAudits of suppliers and contractors are' scheduled' based'on the status - s ~ and safety importanceof the activities.being performed and'are - initiated early enough to assure effectiveLquality assurance during- ' design, procurement, :manuf acturing, construction, installa:1rm, . inspection and~ testing. J18.'2.4 Principal contractors are required to audit'their, suppliers systemat-lically in accordance with the foregoing scheduling criteria. ( L1'8.2.5T Regularly scheduled: audits are supplemented by special audits when .significant; changes.are made in the-Quality Assurance Program, when it. A .) ' fia-suspected-that quality is in jeopardy or-.when an independent s assessment'of program effectiveness is considered'necessary; r E* L18'2;6) Au'its include an objective evaluation of quality-related practices, d l procedures, instructions, activities and items emd review of document; 'and records to confirm that the QA Program is effective and properly ~ implemented. y Pm 0ei-e535s. ee

Page 62 Rev 11 Date: 10/15/90 18.2.7 Audit procedures and the scope, plans, checklists and results of g individual audits are documented. g 18.2.8 Personnel fielected for auditing assignments have experience or are given training commensurate with the needs of the audit and have no direct responsibilities in the areas audited. g 18.2.9 Audit data are analyzed by the Quality Assurance Department. The resulting audit reports identify any quality deficiencies and assess gr the effcctiveness of the QA Program in the area audited. The reports are distributed to the responsible management of both the audited and 3 auditing organizations, g 18.2.10 Management of the. audited organization identifies and takes appropri-ate corrective action to correct observed deficiencies and to prevent recurrence of any significant conditions adverse to quality. Follow-up is performed by the Quality Assurance Department to ensure that the appropriate corrective action is taken and is effective. Such fol-g Icw-up includes reaudits when necessary. 3 18.2.11 Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of Nuclear Safety Services Depart-ment. I I I I I I I I I g PDlo8i-os m -Qios

m o Page 63 Rev 11 Date: 10/15/90 i .h ~ QAPD MANUAL - g(' . APPENDIX A, PART 1 REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS + I, .The Consumers Power Company Quality Assurance Program complies with the regulatory: position-of.the Regulatory Guides rcierenced in this appendix as modified by the exceptions stated.in'Part 2. 1. Appendix B to-10.CFR, Part 50, Quality Assurance Criteria for Nuclear i . Power Plants and Fuel Reprocessing Plants. 2.- 10 CFR, Part 50.55a - Codes and Standards. y s

13. ; Regulatory Guide 1.8 - (9/80.Draf t) '- Personnel Qualification and Train-

? 1 'ingT-Endorses ANSI /ANS-3.1 - (12/79 Draft). 2 p ((

4. ~ Regulatory Guide.l.'26 - (2/76 Rev 13); - Quality-Group Classification, and aB'

.StandardsJfor' Water, Steam, and Radioactive-Waste-Containing Components < p of. Nuclear Power Plants, g) ' kg

5. ' : Regulatory Guide.l.29 - (9/78, Rev. 3)'- Seismic-Design Classification.

e p ). l6) 1 Regulatory-Guide 1.30-(Safety Guide ;30) - (8/11/72) - Qualitf Assurance. / j. Requirements;for.the Installation Inspection, and Testing of Instrumen-tation and'ElectricalfEquipment - Endorses ANSI N45.2.4 - 1972. d! g'W L7 '.Regdlat!ory Guide 1.73 -j(2/.78,: Rev 2) - Quality Assurance Program ~Re- -4 ~ quirementsf(Operation) --l Endorses ANSI N18.7 - 1976. 4 .8: URegulatory Guidell.37. ;(3/16/73) . Quality' Assurance Requirements for. By

Cleaning of~ Fluid l Systems and-Associated Components-of; Water-Cooled ~

Nuclear Powerg Plantsi-- Endorses ANSI N45'.2.1;- 1973.'

s ,4 I '9. DRegulatory Guide 11~.38 -1(5/77, Rev~2) - QualityLAssurance Requirements for Packaging,EShipping, Receiving Storage, and HandlingLof Items:for: ' ts. qWater-Cooled Nuclear. Power Plants - Endorses' ANSI N45.2.2 - 1972.. 4 M iO.a Regulatory Guide"l'.39J (9/77 Rev 2) - Housekeeping Requirements for

Water-Cooled' Nuclear Power. Plants.- Endorses ANSI N45.2.3'- 1973.

4 < 113,I egulatory Guide.' 1.58 --(9/80, Rev.1);- Qualification of. Nuclear Power R 1J 1-Plant Inspection," Examination, and Testing Personnel - Endorses N45.'2.6 'W 51978.: s y' ~ ',-~12. ' Regulatory Guide 1.64 (6/76,-Rev 2) = Quality Assurance Requirements : 7 or the Design Of Nuclear Power Plants '- Endorses N45.2.11 - 1974. f g '13. ; Regulatory Guide 1.74 '.. (2/74) - Quality Assurance Requirements Terms and Definitions - Endorses ANSI N45.2.10 -'1973. PD1081-0535C-QA06-

.f I Pags 64 j m Rev 11 7 i p' Date: 10/15/90

14.-

Regulatory Guide 1.88 - (10/76, Rev 2) - Collection, Storage, and Mainte-

-g j . nance of Nuclear Power Plant Quality Assurance Records - Endorses N45.2.9 3J 3'

1974, V

. '15.y Regulatory Guide 1.94 - (4/76, Rev 1) - Quality Aseurance Requirements i for' Installation, inspection, and Testing of Structural Concrete and i qO Structural ~ Steel During the Construction Phase-of Nuclear. Power Plants - t Endorses. ANSI N45.2.5 - 1974. t 'I6. - Regulatory. Guide 1.I'16 -(5/77) - Quality Assurance Requirements for " :;g l Installation, Inspection, and Testing of Mechanical Equipment-and 3 ? M Systems;- Endorses ANSI N45.2.8 - 1975. .I e V 17. - Regulatory Guide 11.123 .-(7/77. Rev 1) - Quality Assurance Requirements for Control of Procurement ~of Items.and Services-for Nuclear Power. 1 1 Plants - Endorses N45.2.13 1976. I wA .gi

18. - Regulatory Guide-l'.144 - (9/80,;Rev 1).- Auditing:of Quality Assurance L31

, Programs _for. Nuclear Power Plants - Endorses'N45.2.12 '1977. ? ' 19. Regulatory' Guide 11.146'- (8/80).- Qualification of Quality Assurance' g! m -. t l Program Audit Personnel for-Nuclear Power. Plants - Endorses N45.2.23 - fg 4 1978. j $ ?ll y. '9 ^ -N ~ ( J' 20.U. Branch" Technical Position ASB9.5.ll(Rev 1) Guidelines for Fire' Protection. Mg for Nuclear Power Plants.' N ~ M.? ... l . - t o gW

21. 110CFR50,(Appendix.R,' Fire Protection Program for Nuclear' Power Facilities.

lgg g . Operating' Prior:to January l',(1979, Sections III G., III.J. and III 0. 'g, + 7 n 11 .) I g9p ,n, si ,a> ' -l p ; w!d 2. s [3 l, % ;q ta p i.f a + .;. { lfi' ' u s 'l \\llf.-J ' '3; L ?" y. ~.3 / j (7 iq 7 q e ([ 'j-yj; y 3L

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5 Page 65 Rev 11 u-Date: 10/15/90 1 i( -QAPD MANUAL APPENDIX A, PART 2 'W' CP'C0 EXCEPTIONS TO OPERATING PHASE STANDARDS -AND REGULATORY GUIDES =gi

g 7

.l. cGeneral-Requirement-Certa'in. Regulatory Guides invoke or imply Regulatory Guides and stan-I dards in addition to the standard each primarily endorses. 7 Certain ANSI Standards invoke or imply additional standards. s ~ f . Exception / Interpretation .The CP'Co commitment refers to the. Regulatory Guides and ANSI Standards

specifically -identified in Appendix A,- Part 1.. Additional Regulatory

' Guides, ANSILStandards-andisimilar documents' implied or referenced in 1 those specificallyLidentified are not part of this commitment. Imposition of these Regulatory Guides on CP Co suppliers and subtier

c ; '

suppliers

will be on.a~ case-by-case basis depending upon the item or tservice to be~ procured.

n ?2. N18.7 General-l Exception / Interpretation' i

Consumers Power-Company has. established an organizational unit,9 uclear N

Safety Services. Department (NSSD), for independent review activities.'. U LThe standard' numeric and' qualification requirements may not.be met by, y the' ' N S SD.; Procedures will~be established to specify how NSSD will' u . acquire necessary expertise to carry out.its review responsibilities in- .accordance<with Plant Technical Specifications. 1> + ..3 ./2a. , N18.7., 'Se c - 3.4.2 Requirement y I ' +. "ThecPlant. Manager shall?have~overall responsibility for,the execution-ofothe administrative ~ controls and quality assurance program at the . plant to' assure safety."- a ,,m j t k r ) 1

PD1081-0535C-QA06

'?

q >p Page 66 Rev 11 Datet 10/15/90 Exception / Interpretation Since CP Co has more than one nuclear unit and more than.one organiza-tion providing services to these units, overall responsibility cannot g-be centralized in a single on-site position. Instead, responsibilities g: are as designated within the QA Program Description. ~ 12b. Sec'4.3.1 Requirement-i " Personnel assigned responsibility for independent reviews shall be specified in both number and technienl-disciplir.es and shall collec-(3 tively have the. experience and competence required to review problems g in'the following areas:...'" _g1 p, Exception / Interpretation _II-i fin Nuclear Safety. Services Department will not have members specified by number or by. technical disciplines and its members may not have the - experience and competence required ~to review problems-in all areas. g ,.Q 'y _ listed'in this section;-however..the NSSD will function as. described in 3g ~ ' Plant Technical Specifications and will acquire the' services of person- .nel?having'such experience:and competence as necessary. I .2c. DSec_4.3.4: ^ c.- .Requirementz m" s "The following subjects shall be reviewed by:the independent review' 3:: W i-1b'ody's.- J Except' ion / Interpretation jSubjects requiring review will-be as specified-in the Plant LTechnical- ? Spe cific'ations'. < -2d._

Sec 4.3.4(3) sw E,

iRequirement g '.' Changes 'in the Technical Specifications or license amendments relating J h[, '

to, nuclear; safety-are to-be reviewed by the independent review body prior;to implementation', except in those cases where the change is E_

j W identical.to-aspreviously_ reviewed proposed change. W. PD1081-0535C-QA06' g

n I }[- Page 67. 6 Rev 11 Date: 10/15/90 Exception / Interpretation The Nuclear' Safety Services Department will not review Technical Specification Changes after NRC approval prior to implementation. The I,'i ' basis forithis position is that NSSD reviews all Technical Specification changes prior to submittal to the NRC. 2e. - Sec'4.5 Requireme'nt - 8 ' i; " Written reports of-audits specified in ANSI N18.7 shall be reviewed by. g the independent review body and by appropriate members of Management' .g including those having; responsibility in the area audited." Exception / Interpretation The in' dependent' review body reviews or arranges for reviews of those >i l' 2 audits?over!which-.it has cognizance, in accordance with the individual-4 h., plant: Technical Specifications. L J' 'gE Some'ofLthe: QA' audits required during'the-operational phase are in ~

areas other than those.3 requiring independent. review.in accordance with' e

ANSI N18.7.'Section 4.3.4.. ,.4 = .a '2f. L S e'c' : 4. 5 < B ' y.

Requirement:

w ~ / T CP Co considers that this requirementfapplies only to procedures , 9[y - j ^ identified in plant technical specifications'.- Temporary changes to Lthese' procedures:shall-be approved asl described in. plant technical g

specifications.-

gL < 2 i'. ; 'Sec 5.2.6: u L-Requirement- - + 1-l 1 d. f"t ("In(cases w'here required documentary evidence.is not available.the b ,1 ,Lassociated! equipment'or materials must be considered nonconforming-in. ~ !accordance with Section 5.2.141-:Until suitable documentary) evidence is 4, .availablettol.show-the equipment ortmaterialsis:in conformance,Jaffected. ' ' ~ ? enystems shall(b.e considered,to be.-inoperable and> reliance shall'not be- 'placed onnauch-systems-to fulfill their intended safety: functions."' ~ u; ~ Exception / Interpretation 1 i it@ ' jCP Co initiates appropriate corrective' action when itLis discovered ?thathdocumentary, evidence does not exist for a; test or inspection which. [ Q" ~~ is required'to: verify l equipment: acceptability. 'This~ action _ includes a @g ] s p Leechnical~evalua'tiontof the' equipment's operability-status. h;,7, [2j. LSee 5.2.8' L

3 LR'quirement.

To e 3l ,7"AL'urveillance testing'and inspection program....shall include the s q m s' establishment'of'a master surveillance schedule.refleeting the status 4< of all planned inplant surveillance tests and inspections." g W) t fieuwegs3sC40e y +w ,w

g ". Page 69 Rev 11 lg; Date: 10/15/90 .g Exception / Interpretation [ Separate master schedules may exist for different programs such as IS1, L Pump.and-Valve Testing and Technical Specification Surveillance Testing.4 3 2k. 4 Sec 5.2'.13.1 l . Requirement [ "To the extent necessary.-procurement documents shall require suppliers, r5 to provide a quality assurance program consistent with the pertinent L

requirements of ANS1 N45.2 - 1971."

'ExcepEion/ Interpretation 'To'the extent'necessary, procurement documents, require that the suppli-er have a documented quality assurance program consistent.with the pertinent requirements of ANSI N45.2 or other nationally recognized = . codes and standards.. c - 21.' Sec 3.2.13.2

gi+

1 Requirement g.

q

' ANSI ~N18.7!and N45.2.13 specify that where required by: code, regulation. + toricontract. documentary' evidence that. items conform to procurement 4 B requirements'shall-be available at.the nuclear power plant site prior s , to : installation or use' of. such items. Exception / Interpretation iThe: required documentary evidence is 'available at. the site prior to i use,'but noc necessarily prior:to installation.- This allows.installa-tion to proceed whilelany missing' documents are being obtained, but = l J i . precludes dependence on the item for-' safety purposes. t ^ Y 1 m. =See 5.2.15-2 g ~ Requirement Plant procedures shall be reviewed by 'an individual-knowledgeable in-

the area 1affected by the procedure no less frequently than every two sy 3;

years;to determine if changes are necessary-or desirable.

.f[' i fPD1081-05350-QA06- -_.__.~2.

5 p}'. Page 70 y' 4 Rev 11 [ g Date: 10/15/90 ?: Exception / Interpretation { ' Based onhamplification provided in ANSI /ANS 3.2-1982, section 5.2.15, Consumers' Power Company interprets that'this requirement for routine g followup. review can be. accomplished in several ways, including (but not g limited to):-documented step-by-step use of the procedure (such as occurs when the procedure has a' step-by-step checkoff associated with 11t)for detailed scrutiny of the procedure as part of-a documented ll l training program, drill, simulator exercise, or other such activity. IB 12n. LSec=5.2.16 j Requirement- ' Records shall be made".and equipment suitably marked to indicate cali-bration status. Exception / Interpretation i n f 1-r, See Item 9c;.

i; g:

' 2o.:

Sec 5.3.5(3) gj

1. Requirement:

I: Instructions shall be included.,or referenced..[in maintenance proce - ~.,* -dures), for; returning >the' equipment.to-its normal-operating status. , Exception / Interpretation 9o At-CP Co,Lequipment is returned to:.its normalpoperating; status 1e,; 3 t ' declared operable,.by licensed Operations Department' personnel, not' tg Maintenance.pernonnel. 0perationsi personnel verify and document i ' equipment operability:through second leveliline-up verification'orL 1 ~ .li . appropriate. functional testing..Thus " maintenance procedures" do not-contain;or directly referencensuch1. instructions.1 m q u 2p '. / Sec'5.3.5(4) j Requirement: t This section requires that where sections of documenti such as vendor c manuals. operating and maintenance instructions : or drawings are incor-- porated directly or by reference into a maintenance procedure, they shall receive;the:same level of review and. approval.-as operating,

procedures.

t.,

t .i ~ I; .jpD1081-0535C-QA06

( . y"[ r i 1 1 t 5, Page 71 Rev 11 i + Date: 10/15/90

l 4

Exception / Interpretation

Such documents are reviewed by appropriately qualified personnel prior

'g to;use.to ensure that,'when used as instructions, they provide proper and'adequateLinformation to ensure the required quality of work. g 4 Maintenance procedures lwhich reference these'documen;s receive the same ilevel ofireview and approval as operating procedures. s

^

j C 3a.. lRG l'.33','Sec C4a .i 1 Req uiremen_t ' t 'TheLresults'of. actions.taken to correct deficiencies that affeet j nuclear safety and occur,in facility equipment,ostructures, systems or 1 .gy ~ Y lg, ' method of operation are to be audited at least once per six months. p,E

Exception / Interpretation' j

4 .] Theicorrect ive-action system trend reports are : reviewed by the indepen-W 'dentaeview body. ;In addition, the corrective action systemLis audited j mj, p W. least once every?two years-with additional, audits land: investigations- 'i j(gk

performedias. indicated necessary by the trend report reviews.

. ~

w

.'S 1 3 b '.' 'RG"1433,cSec C4bL ~; ' Requirement i j .[ .'heFconformance of. facility operations =to provisions contained within T s, W u f ;c; itheitechnical; specifications and: applicable' license conditions - at

• '5

!1 east'once per :12 months. lex' option /Interpretatilon' n c [fi% ? Consistent with guidance presented in:NRC: letters dated. March.29, 1983~ .(RLSp'essard to JMTaylor) and January.30,l1984-(JGPartlow;to RLSpessard), j ? 'if m p 1 Consumers. Power Company interprets the commitment'to audit technical d pym xspecification/ license conditions contained in 18.2.2(a)'of this'QAPD,; 1 T and..in section 6.5.2.8(a) ofKboth' Palisades;andJBig. Rock Point techni - fl5% cal specifications,.as follows: q -ConsumersEPower Company: maintains a matrix that identifies allDapplica'-'- .} ~ I;;';p'L, Eupdatodiannually.to; conform.to approved Technical' Specification chang ~ ble'Technica1LSpecification linefitems.to.be audited. The matrix.isi ]' - s** .esk 2.During each'_'12' month periot aTselected sample of line items inn e'ach of?the following clements:is audited:L j ~ l.'. Limiting Conditions for Operation Eg; 2~.. Limiting Safety Syste d er. tings .Resetivity Control Systems. ] 3. .g i 4.;. Power: Distribution' Limits lS., instrumentation' i In i I !r o , [%: PD1081-0535C-Q406. m l ',, ', !' lX ,j if t*

l Page'72 4 Rev 11' ,;p Date: 10/15/90-I N 6;- Reactor-Coolant System .lj '7. _ Emergency Core Cooling System W! l '8 1 Containment Systems U 9 1 Plant Systems-g! .10.- Electrical _ Power. Systems gV[

11. jRefueling Operations O,<

12.: Special Tests-l 4 - 13. : Onsite Committee ~ 14.-10ffsite Committee j m

15. - Administrative Controls k

Audits are scheduled so that all line items,are covered within a ' maximum period of 5 years. The audit period for any of the above '1 elements may be reduced depending on Technical Specification-compliance . history._ ~ 4 m; ~ 4a.; ' ANS 3.1, General LException/ Interpretation-Ll ~ 'g 7g ' ~ The CP:Co commitment in this:QA Program Description to ANS'3.1'is-g1l -limited'tb'those. requirements which' apply.toLthe training and qualifi-g]:) ][f - cation:of personnel" performing'QA/QC functions. ffs"... L 1

l5a, RG - 1.-8. ac. 3.1,1 General ;

,' ' y .V .1 \\ Ex'ceptiori/ Interpretation t -p ,-i 5' .i: .iThe'CP':Co' commitment'inithis QA; Program Description'is limited to-those 1 t k.s >$Y.- -requirement's'which apply toLtheftraining:andlqualificationlof personnel. l siiE ", - performing'QA/QC functions, a ,A . C1. 2 ; 2:, C 5b.; ~gq. 1 s 1

• gg

" Requirement' .a W' .When an-in'dividEAli1's hired tol temporarily fun'etionias a plantiemploy- ,.iee;feuch;as'for'contractedservices. evidence:of' previous: education.D ' -ge l >cexperience:and)trainingish'ould'be provided'and reviewed:by:the appro- _g( priatel professional--technical group f1' aders. The; appropriate group. e 1 leaders shouldithen determine the content for that individual's train-g f, ing kincluding plant-specific training. Assa minimum,4each individual g. C Eshould receive. General Employee' Training." .4 l /jg "Exceptibn/ Interpretation' g,1,b*q CP!Co; understands that:this requirement applies'both to CP Co employees .3 ~ 1from'another site land~to contract 1 personnel.who are temporarily as- ~ ~ ~ feigned!to a nuclear power plant either as replacements for: regular ~ 5 ',I 'Lemployees-or to-augment the staff'during outages. CP Co employees so

D.081-0535C-QA06

, s 4

Page 73-Rev 11 Date: 10/15/90 m B - assigned possess the required qualifications as a prerequisite to the assignment'and.the review is waived. The qualifications of contract personnel:are reviewed and arrangements made for any necessary train-ing. LTemporarily assigned personnel < requiring unescorted access B receive the-site general orientation as embodied in General Employee Training. .6a.. ' N45.2.1, Sec'3.1 2 . Requirement-N45.2.1 establishes criteria for classifying items into " cleanness ' levels," and requires that items be so classified. _ B Exception / Interpretation-Instead of using the cleanness level classification system of'N45.2.1, B._, - 4 the required cleanness for specific items and-activities 18-addressed { ~ on a case-by-case' basis, = M. -go Cleanness-is maintained, consistent with the work being performed, so dj

• as to preventithe introduction of foreign material. As a minimum, s

'e' cleanness; inspections.are performed prior to-system. closure.c Such ' nspections are documented..

i

ps s

6ti.1 -Sec 5' lR'equirement = lL " Fitted and t'ack-welded -joints t (which will not' be immediately ; seal'ed by:- , g,; . welding) shall" be wrapped with polyettiylene :or other nonhalogenated .plasticffilm until the welds'canibe completed." g? s, 4< 2 L Exceution/ Interpretation-4 o [.' CP Co sometimes uses other.nonhalogenated material, compatible.with the. s -JM parent material..lsince plastic film is subject to-damage and does not 3 .always provide ~adeq' ate. protection.- u fV ' 7 a'. - 'N45.2.2,J eneral-G ~ Requirc- - tf + .. g[ 'N45.2.'2 establishes' requirements and criteria for classifying safetya = i related items into-protection levels.- t . Exception / Interpretation Instead of classifying-safety-related items into protection levels, .y controls"over the packaging, shipping, handling and storage of such items are established on a case-by-case basis with due regard for the t iPD1081-0535C-QA06-b f E

k 4 I J,

• Page *i4 g

M..

f, Rev 11 e Date: 10/15/90 ~ m 11 tem's' complexity, use and sensitivity to' damage. Prior to. g 1,

installation or use, the items are inspected and serviced as necessary 3i

.co, assure that no' damage.or deterioration exists which could affect their; function.: 7b. _ Sec'2.4~ Requirement ij "..~.0ffsite-inspection, examination or testing shall be audited and monitored'by personnel who are qualified in accordance with N45.2.6." in., g' 1 e E N ~ Exception / Interpret'ation i Offsite inspection, examination-or testing activities are. audited or [ inspected by' persons qualified'and certified in accordance with ANSI 09 .N45.2.23-1978, as endorsed by, Reg Guide 1.146,~.or. ANSI N45.2.6, as 4 i,' endorsed by Reg Guide?1.58, respectively.- Monitoring activities not' gi E-n/ involving audit:or inspection may be conducted by persons: trained and -Wr E', ~ qualified to ;ef fectively{ carry out-such tasks, but not necessarily s "f ". certified,toleither' ANSI..N45.2.23 or N45.2.6. gi ,u, ,, <, ~. 3~). y, y7c. iSec'3.4~.1.andLAppendix!A, 3.4.1(4) and (5)' Requirement ~ h.tc, a., A1 ' 7- - '"(4)T....) However,: preservatives for inace'essible inside surfaces containing reactor. coolant water.shall!be indicated to facilitate.' touch .gLj ' y. up. y3, -(5)jThe, name Tof the preservative-us' d ?shall be 4 the watergflushable. 3: e Ytype'." , g' r + x ['

g, s

[ Exception / Interpretation g ,x i ( l Based (onl.comparisonof1 these statements ti ANSI /ASME NQA-2E1983,'CP Co. I L lbelieves the intent ns to establish the' following;as requirements: a# L M)j...: However, preservatives for inaccessible inside surfaces:of gL[ ,n. 37 apumps,fvalves and pipe-for systems containing" reactor.. coolant' water dl Fy - ~ /shalljbe the' water: flushable type.~. A,, N j k !(5) The nam'e'of the' preservative used shall be'providedLto: facilitate j %'4 f - t ouch-up.'.- j m" 77 d,T n . l Ji a. 3 d ': . sec.3.9 andtAppendix A 3.9'

W h!

z ia 'i -' Requirement- .At 6 hg/ - The item and' the outside of containers shall be ma'rked." ~ ~ g (Further criteria for' marking and tagging are given in the appendix.) 1 2 ,y' jPD1081-0535C-QA06.. E, 7 e*I '{q

,'s ^ ~ - ~ ~ , f 3y, 4 9" ,1 Pags 75 Rev 11 l 4 Dates.10/15/90 j i .' Exception / Interpretation' i 7 73 These requirements were originally written for items packaged and ' g shipped to construction projects. Full compliance-fn not always -necessary in,the cese of items shipped.to operating plants and may, in + some' cases. increase the probability.of damage to the item. The

l I

requirements are implemented to the extent necessary to assure trace-ability and-integrity of the item. 'i i

7e..

Sec'S 2.2: i Requirement j 4 m "The inspections stiall.be. performed in an aren equivalent to the level l (' (/', 'of ; s torage.?! ' 4 w; Ij K E-l . Exception / Interpretation L 1

gc %,

1 TRe.ceiving inspectionlarea' environmental controls.may be'less~ stringent j

g'.,4 ithan; storage.. environmental requirements:for an item.

However,.such

inspections are' performed in a manner and'in an environment which do j

43/2 ~ ' ~not endanger the, required quality of the item.>:- 4 n f L7f h SeM62."4'- ] q ~' ' Requirement wg V I,,y , S, g j N t t"Theluseior;storagelof(food,: drinks ~and salt. tablet: dispensers in any EstorageinrenJshall not,b'e f permittedd': f W

• Exception /Interptetation i

~ :n.. x ~ w + E p

g Packaged

food'.for emergency or: extended: overtime <use may~.be storediin y"

material ~ stock. rooms. Thelpackeging" assures.that materials are not % W '4 d h '

contaminat'ed.

Foodivill not be "used" in these areas.

i o }

jgW, 7g.

Sec. 6~.3.4 - g s.g: -l [ 4. Requirement-y 4 '"A1101temsknditheircontainersshall'beplainly. marked-so-thatthey. ) h b 'are easily?identifiedtwithout-excessive: handling or unnecessary opening-' i ~ .4 S T.Q. J ~ "of crates and boxes."' g,- y 3 L? Exception / Interpretation. sdn r, t i.; + eSee :N45.2.2iiSection :3.9 -(Exception ;7d.). ,[ }g); e g + 1. r .~ iPD1081 05350-QA06-

.; h. '. _

t' r Df[ l O ' i

a ,f, 'f 'lf .) f 4 Page;76 J M 1 )e - Rev 11 1 7, 4 a. - Date: 10/15/90 s $7h; Sec 6.4.1 m Requirement- ? Inspections)and examinations shall be performed and docum nted-on a [ 7 l 't 1 periodic. basis-to assure that the integrity of the item a.d its con- .tainer...is being maintained." i .,g Exception / Interpretation ] W. The requirement implies that all inspections and examinations of items ~ g. h in' storage'are to be. performed on the same schedule. Instead, t.he ' g' e s inspections:and-examinations are performed and documented in accordance l! .with~ material storage procedures which identify the characteristics to .l j be: inspected and inclu.de.the required frequencies. These procedures are based on technical-considerations which recognize that.. inspections =- J / and frequencies needed vary from item to item.- m hda." n L N45 ; 2'i3 4 i Sec - 2.1~

4.,

= q fRequirement. .- i l I 1 C1'nnness requirements ~for housekeeping activitiestshallibe established 'A l e ' on; the' basis of five zone designations. "3-4 ,e, tException/ Interpretation j e .w j m a p: 4~' ?Instead of:theffive-levelizone designation system referenced in, ANSI' J g:, ' N45.2.3F CP Co bases,its controls over housekeeping activities on' a consideration lof what-is necessary.and~ appropriate for the activity .gl j

• 4

[ involved. The controls are: effected.through procedures or instructions g s, Lwhich Tin the case of maintenance 1.or modifications: work, aresdeveloped' 1 ?E h 4 y, Jon/aLcase-by-case l basis.z.. Factors considered;in developing the proce- 'l + ,;duresfandLinstruc'tions includeicleanliness1 control, personnel safety,; i '; 1 c f firejpreventioniand; protection, radiation control.and security.LThe j; f 'q.4% ' - y I procedures 'and' instructions make use of-standard, janitorial,and ' work g spractices;tolthe"extenthpossible.1 However, sin preparing these proce- { '.M '2.19of ANSI N45.2.3.- ~ g W Ldures,. consideration'is also given to the recommendations of-Section-gD i Y9 a'.H ~ N4'5?2 ;4, -$Se c i 2.2D a d m x -~ l Ws

Requirement gg s f

LSection 2.2z establishes prerequisites:which must:be. net before'the f

installation,Einspection'and' testing of.. instrumentation and electrical

) F Lequipment may proceed. These. prerequisites: include personnel;.qualifi-f', cation', control of design. conforming and protected materials.-and' i availability ; of.specified. document s. 3 45 t7 I ..q s ,c .,i,?7_; 2, PD1081-0535C-QA06 . '[g.$ni 1

!\\ 4 Page 77 Rev 11 lI Datet 10/15/90 l Exception / Interpretation o ~

During the operations phase, this requirement is considered to be applicable.to modifications and initial start-up_of electrical equip-I ment. 'For routine or-periodic inspection and testing, the prerequisite conditions will be achieved as necessary..

9b.; See 2.2(5) Requirement ~ Section 2.2(5) of. ANSI N45.2.4 lists documents which are to be avail-able;at the construction site. 13 4 Exception / Clarification l{ .All ofrthe: documents listed are not necessarily required at the plant y i site for installation and testing. CP Co assures that they are avail-able to the site _'as necessary. I' 9c. -

Sec:6.2.1 s

, Requirementi q . Iltemsirequiring, calibration shall be tagged or labeled on completion, T (indicatingidate of calibration and identity of person that. performed J t < y fthe' calibration." N ) Exception / Interpretation o n. Frequently,: physical size and/or location of. Installed Plant Instru-I . mentation-(IPI) mandates that calibration ~1abels:or tags not be-aff1xed- -tocIPI. Instead, each instrument ~18 uniquely 1dentified and is trace abl~e to its-calibration record. l. =3 tA_ scheduled calibration program assures that each. instrument's.calibra ; = tion is current.1 '10a.- N45.'2.5,L Sec 2.'4 m l l# Requirement " Persons charged with, engineering managerial responsibility of the i

inspection and. testing organization at the site in either a resident or -

Y non-resident capacity :shall be certified for Level,III capability." I

gy PD1081-0535C-QA06 s

y 7( il 4 o f, ' ' Pago 78 Rev 11 l f' Date: 10/15/90 ~

i.

Exception / Interpretation 4 !This standard (N45.2.5) was written for the construction phase of. nuclear; power plants; as such,'it presumes significant activity in the areas'of concrete and-structural steel which do not generally occur at - t -an operating plant.- At Consumers Power, persons having engineering managerial-responsibility for inspections and tests

• may be certified m

- to.' Level III or-may. meet other qualificatiot. criteria established for 0, 'the position, including, but not limited to, nuclear power and manage-ment experience.. For major modifications involving significant con- .} K .cretelor structural steel work, the services of a properly qualified 3H ' : Level:III' individual'will be obtained in at least an advisory capacity.. _g '*within:the' scope of N45.2.5-Il qp 7. < 10 b. :-.N45.2.5,:Sec 2.5.2 ~ N, Requirement. + "When discrepancies malfunctions or inaccuracies in inspection and j f~1 ? testing equipment"are found during calibration, all items inspected 1; ~ (!IW with'that equipment (since.the last previous calibration shall be l ' considered unacceptable.until'an-. evaluation has been made by'the. responsible l authority andfappropriate action taken." 7 m ~ Exception / Interpretation- 'CP Co uses'.the requirements of N18.7,.SectionIS.2.16, rather than ig., ~

N45.2.5, Section'2.512.1 JThe N18.7 requirements are.more'. applicable to' 4g.]

y: tan;operatingLplant. y' 3 L10c.] LSec 5.4L 1 4 Requirement l s'sM y

" Hand torque, wrenches used for inspection'shall be controlled'and must:

[ ~~ ~ l .be calibrated:at least weekly.and more often'if' deemed.necessary. j i; Impact. torque wrenches'used for' inspection must beLcalibrated at least j ~ .twice daily " l 1\\ 1 iException/ Interpretation' m ~ E n Torque wrenchesfare controlled as measuring and test equipment in >f ' M 'I 2 - - accordance with ANSI N18.7,2Section 5.2.16. ' Calibration intervalscarej at, . based on use and calibration history rather than as per N45.2.5 b ps ] r i li ~ \\,u ,y-s l 1 1PD1081-0535C-QA06 -3) 5 I 31 3 w L

a ny;. w Page 79 Rev 11 [" Date: 10/15/90 'lla.' N45.2.6. Sec 1.2 i RegtAirementi li, C j "Thefrequirements of this standard-apply to personnel who perform 6" . inspections, examinations, and tests during fabrication prior to and S

during/ receipt of items at the construction site, during construction, yl?

during-preoperational and start-up testing and during operational L "m phases of nuclearipower plants." .f Excep' tion / Interpretation ' [gi g! .A RD

Qualification of plant. personnel-who are 'involv' d with testing associ-e

!g[ l$ a: ated-with plant-operation is provided in specific plant specifications. In addition,Lpersonnel participating-in inspection or-testing who take = "V, Ldata or make observations, where special training is not required to s Ngn ? perform this function, need not be qualified in1accordance with ANSI g,,

N45.2.6 but need only be. trained to the extent necessary to perform the assigned-function.

q 0"_ '3?i c 1s '12a. TRG 1.58.'Sec.C.1'- 1 x l(( WL LRequirement' u; 1 ,3 i 1 '"However cforfqualification of personnel.(1) who' approve preoperation-

J ?

c p

-a1.: start-up and operational testLprocedures and testiresults and"(2) ~ twho; direct'or supervise the conduct-of individual preoperational,. Wg!. . start-up'and operational te'sts.1the-guidelines containedrinlRegulatory. Yg _k 1 Guide 1.8,gPersonne1~ Selection-and; Training..should-be followed:in lieu- 'of?the Guidelines of1 ANSI N45.2.6 --1978." 4cli

q.

Exception / Interpretation

-y M~ L kCPfCo.:endorsesthisposition,asalso:statediblla.above,exceptthat- ~ 5 J' fc Lof f siteisupport organizations. involved in;te' ting maylapply ANSI s z ? '!NAS.2.6h Some of these departments have aiready developed;their s lg; 7.ggualification programs based onuANSI N45.2;6T and provide services 3 y3 'Lthroughout the' operations phasefof CP1Co Nuclear-Plants. '112b2 Sec C.5

• Wu 4"

. \\;( ' Requirement 4' nlXt ?EU,*

• t"F J "In addition,;the: individual should be cap'able of' reviewing.and approv-a tB singyinspection, examination.and1 testing procedures and of evalu'ating-1 Lthef adequacy' of such procedures tolaccomplish' the inspection, examina-

[ l ition and test objectives." 1 1 .L so ' ; ; %. 4 ' PD1081'-05350-QA06 . g ';( l m f

,m, af O. y y Page 80 ^ Rev 11 Date: 10/15/90 s Exception / Interpretation V i O

While a Level III-individual should be capable of reviewing and approv-ing' inspection,-examination'and testing procedures and of evaluating

-the-adequacy'of such procedures to accomplish the inspection, examina-tionLandl test-objectives, this is not construed by CP Co a6 requiring -personnel whoireview, approve or evaluate such procedures to be certi-fied as Level:III personnel'. x. 12c.- See C.6: w"'y . Requirement' k"V ' ,y "Since,only one: set;of recommendations is provided for the education and experience.ofl personnel,Ka commitment to comply with.the regulatory = position of'this' guide' in: lieu of providing an-alternative to the ' recommendations of--the standard means that the specified education and [7 . experience recommendations. of,the standard will be followed.'.' -3 [,s -g; m ' Exception / Interpretation -Theeducationiandexperience.recommendationsgivenin,ANSIN45[2.6, [ ,4 7 t. e 'Section'.3.5 will'be> treated'as such, since our qualification and Mf:! , ecertification;; program is based upon;these recommendations,=and more ?Qj 1significantly,'-upon satisf actory completion of capability. testing prior,

• . a E Ltoncertification.-

It.is_our position that.a-candidate should not be irequire'djholbe'a higheschbol; graduate orlhave earned the GED: equivalent ~ m

7., m Y, "3for,the ab'ovetreasons.

x i ,8 t j >>i. ,( -.12.d; cSec;C.10 5, 4 < s [ A i f 3 y y. 4 Requirementi gj > " l' t

• of the measures outlinedLin:these actions t{ establish that an ?

T ind.tvidual,has the-required'qualificationsLin lieu;of required educa- ,Ei s <R' %.' tion an'd experience 1should; result in documented evidencee(ie,: procedure LE' ~ s N.andl record'of written) test)jdemonstrating'~that'the individual indeed-7 a @dbes(have-comparable {orequivalentcompetence4to.that:whichwouldbe g_ E 'igninedVfrom1having the required education and expefience."- ' g: ~ W 3, m + e e o Exception / Interpretation j . 7 1 ',g 4We 'will maintain documented (objective evidencecthatL demonstrates' that si af. _ g an tindividual' does i ave '! comparable" or " equivalent"gcompetenceL to that_ h c a" " which would be; gained from.having,the:requiredleducation and:experi > _g t ence.. However, this may;takeithe form of documentation-other.than:'

3J i,

'( proce' dure'sLand records _'of written test"'such as documentation.of ora 1K tests and on-the-job performance demonstrations. .g

y[.%

'7 g, fy' 10

.fl...

s W i.. _. JPD1081-0535C -QA06 y ..w = w s i Y g g,

4 s Pcgs 81 _."M' Rev 11 3 r*

• Date: 10/15/90 l'3 a. '

-N45.2.8, Sec 2.7' j 4..' Requirement 1 1 i L Section 2.7 requires that personnel performing inspection and test j activities'be qualified according to ANSI N45.2.6. Exception / Interpretation 'See' Exception / Interpretation lla and 12a. -Test personnel who are part $l ~ applicable qualification criteria of plant Technical Specifications. j

of'the plant staff need not be certified to N45.2.6 provided they meet-j

^ g 13b;' Sec 2.9 1 M Re_quirement - s , x(* )j Section.2.9. establishes prerequisites which must-be. met before the iu, . installation. inspection and testing ofimechanical equipment may

proceed. : These. prerequisites include personnel and' procedure qualif1-4 f

L, cation : control ~of; design, material' selection and fabrication, and ?. -availability ~of spe.cified. documents.- t ..u, 4 - Excep tion / Int erpre ta tion' j s [ ~ '.i i

DuringLthe operations phase,'this requirement is considered 1 to'be j?

applicable to modifications of mechanical-equipment... For routine or. <{;. iperiodic. inspection and testing,'the prerequisites'will be achieved as-A t M: -, <necessary.- 1 .y M"n ll c 213c.:.N45.2.8,TSec'2.9e-M m' x. n g O ' Requirement' f c-N %

Se'etion:2.9e'of;N45.2.8 lists. documents relating to the specific stage;

,j ? W i ! k: 2 ofjinstallation' activity.which are to-be available at the construction [.' f 3 . site'. ; sg m .j 43;, ' Exception / Interpretation jq A11;ofLthe documents listed are.not necessarily required aj the plant j

e. g ;

y< g- . site for installation and testing. : CP Co Lassures that they are avail- } .i able to the site =as necessary. ? .t IEV U< l13ddi Sec'2'9A og J w LE ' l Requirement j 'T 0 Evidence'that' engineering or design changes are documented and approved 'shall be.available at the. construction site prior to installation. ) j i .g ,PD1081-0535C-QA06: 1 ,f g

i Page 82 J"~ Rev 11 i [ Date: 10/15/90

)!

Exception / Interpretation' 4 ,\\ Equipment may be installed before final approval of engineering or 'j

design changes. However, the system is not declared operable until

'such changes are-documented and approved. ~ 13e. -Sec'4.5.1

j g

' Requirement 3j h ,F, '" Installed' systems and components shall be cleaned. flushed and condi-

tioned according to the requirements Jof ANSI N45.2.1.

Special consid- 'eration shall be given to the following requirements:...." l ,s,, _(Requirements are given-for chemical conditioning, flushing and process H . c ontrols.') . Exception / Interpretation 1 a LSystems:and components-are-cleaned, flushed and conditioned as1 deter- ' l mined on,a; case-by-case basis. Measures are taken to help preclude the y ineed for cleaning, flushing and' conditioning-through' good practices j f4

duringymaintenance

or modification activities.

i r

'14 a~. - -

N45.2'.'9, Seci5.4 Llt'm'2l d

e A Requirement 7 q i n fRecords(shall not be stored loosely.,/They;shall be firmly attached'in

gf I

Jbinders or placed'in folders or1 envelopes for storage.on shelving in-fi G 1 containers 6:lSteeljcabinets are preferred. lf ' Exception / Interpretation- 'l E 2 m ~ .Dj ' Records < areisuitablyLetored in : steel, file cabinets or on ' shelving-in ' containers. Methods'other than binders, folders or' envelopes ~(fori 'l L - ;n,

's example, dividers) may!be,used to organizeTthe records for storage.

.l 1

J;14b'. w Sec 6.2- ,a. Q l 4,.jj Requirement' m T.h u I"A' list shall'b'e maintained designating those personnel who shall have ~ ^ T inecess to the files."~ 7.y Exception / Interpretation? E! SUS $ _ i gis " 't f. [ [ Rules are estab'lished! governing accessuto and control of files as l provided for in ANSI N45.2.9,-Section 5.3, Item 5.. These-rules do not ^ lalways include a requirement for~a list of personnel who are authorized-i g jaccess.- It should be noted that duplicate files and/or microforms exist for general'uce and backup. + 1

PD1081-0535C-QA06 g

mJ '. :l{p,

i :

I .Page 83 y Rev 11 Date: 10/15/90 14 c. -

RG'l.88', C2-Requirement "Twoimethods of pr'otection of quality assurance records from the

. hazards--of-fire are described in Subdivision 5.6 of; ANSI N45.2'9-1974.- y NFPA No;232-1975... also contains provisions for records protection-I equipment and. records handling techniques that provide protection from the' hazards of. fire. This standard, within its scopefof coverage, is ' considered by the-NRC staff to provide an acceptable alternative'to the' g,' fire protection provisions listed-in Subdivision 5.6... When'NFPA g 1232-19751is used, quality assurance records should be classified.'as NFPA Class 1l records..-." Excepcion/ Interpretation g f CP Co adheres to ANSI N45.2.9-1974, Subdivision 5.6~for the facility Ii J' Efor_ permanent. storage of non-duplicated records; Temporary storage.of-documents.-after completion and:during processing as records is_in file. .. [' i cabinets' selectedlin accordance with provisions of NFPA 232-1975 for AG, ,ClassJ1 records.(usually NFPA Class C, 1-hour or UL-Class 350), h -15a.-

RG 1.64~,'.C2 Requirement

j. ' "Rigard'less of theirJtitle; individuals' performing design' verification @}'f Lahould not?(1) have.immediate' supervisory responsibility for the: 3B l individual performing the design... ~. l; E Exc'ep tion / Int o rpre tation - CP Co 9ollows:the requirements;of ANSI N45.2.11-1974, Section G.1, and' L --the0 guidance:ofcSection-3E4(a))o'fLtheiStandard Review Plani.with:thec ^ "'L I" et1"*" vi

818" r***r

>6 14 ib'y a' procedure insteadofLindividually.; approved'in advance {in each case f ^ b "(see-:Section 3.2;9, herein).> This approach'is necessarysto allow small 'j -l 4 jf* , organizational'-unitsL(having limited numbers of technically qualifiedi EP m A staff. orlhaving the only; technically qualified staff available in thec -Company);the flexibility:needed to most effectively accomplish their: gl f Jassigned; tasks.- U g/,S J16a.1 RG 1.144 Sec103a(1). 9* iR'equOement 7 W ( This.: section, requires that for operationaD phase activities,- RG 1.33-g '"QualityAssurance Program' Requirements (Operations)" are to be fol- - g {.- . lowed; One of the.RG 1^.33 requirements is that the results--of-actions .taken to correct deficiencies that' affect nuclear safety and occur in facility' equipment, structures, systems, or. method of operation.are to I* be. audited at least once per six months. n I & k,. 5 PD1081 05350-QA06-o ag n ^! y s i

5

g MM Pags 84 VE 1Rev 11 6-

-Date: 10/15/90-- n -Exception / Interpretation- ' 'See; Item-3a for-the' exception to this requirement. i .16b. Sec.C3a(2)'e g m V a7 = Requirement' E (' !!?W 2 Applicable ~ elements oflan. organization's quality assurance program (for " design 'and construction phase. activities") should be audited at least l annually or at least once within the life of the activity, whichever is gg M 4 , shorter. .g3 n 3 ] i fException/ Interpretation-y ' rr # + r .Since.most modific'ations are straightforward, they are not audited II 4 ( i iindividually. 'Instead, selected controls.over modifications are q f4 f '~ audit.ed periodically. E.. ~ 5j Wy m s s" i16c.:, Se.c C3b(1) 37 o 3 .:I ? L. "Requirementi ( . L ' v., n U 4: [:<Thissectionlidentifiesprocurementcontractswhich.areexempted1.from; = being' audite'd.; a ~ Exception / Interpretation eX i i ss

1..

>c "p' 1,.m yin;additionLto;the. exemptions 1of RG 1.144,.CP Co' considers;thatJAuthor-r / ~ izednInsp'ection. Agencies,' National Bureau of Standards.or other' State'.- y g c .and FederaliAgencies;which mayiprovide serviceszto CP Co;are noti .gp 'V req'uiredj $ beIaudited'.'.

g}i o,

1 .o.. 1 L17a N iN45.2.13,;Sec 3.2.2:

w. w +

n, f,' i( > g"re<> s Q ' }y' d :.. Requirement 1 l iN45.2.13jrequiresi hat 1 technical' requirements be;specified!in procure-gf ' ? ment documents by reference"to technical requirementidocuments.c .. g. t ? M 'Techn1lcalsrequirementdocumentsaretolbe: prepared,-reviewedand. [ w%2releasedLunder the~ requirements established by ANSI N45.2.11.. a 3[ f; Exception / Interpretation j s .t o-TFoiireplacement;partsland materials",1CP Co follow's ANSI N18'.7,_-Section'. .li 15.2.13,l Subitem 1. which;statest, ~ "Where the. ' original itemTor part;is g l.} ~ jfounditoLbeicommercia11yL'off the shelf'f.or without specifically J 4 e ,,g g fidentified1QALrequirements, spare and, replacement parts may be.similar- ~ ?ly procured, but care'shall be exercised to ensure at.least equivalent C ' performance."1 j 'u,a - ;{:: ' f kPD1081 0535C-QA06, 'E 5, ; 1

l;

't I [.? h ; Y' . '.,, ;;, [ n

?~ .I' .y Page 85 Rev 11 Date: 10/15/90 = .17 b. - :Sec 3.2.3- ~" Requirement o " Procurement documents--shall require that the supplier have a document- ~

ed' quality; assurance program that implements parts or all of ANSI N45.2

.g m tas:well as applicable quality-assurance program requirements of other ~

nationally recognized codes and standards."

Exception / Interpretation . Refer to' Item 21. 17c. Sec'3.3(a) 4 Requirement ~ w Q Reviews of procurement documents shall be performed prior to release B_ for; bid and/ contract award. y. , 1 LException/ Interpretation: . Documents may bel: released for bid.'or contract award before completing < the.necessary reviews.= However :these reviews are ' completed; before t'te

item or-service is put into' service,or=before

work hasJprogressed

'beyond-the point where it=would<be-impractical to-reverse'the action it aken'.1 il7d. SecL3.3(b) ^ Requirement -0 M ~ " Changes ~made'in-the procurement documents asTa. result of the bid _ evaluations or-precontract'negotiationsLshall be incorporated-into the ~ procurement documents.:lThe review oflsuch changes and their. effects-- shall be completed. prior to contract award."' 3 . Exception /Ititerpretation j ~

This

requirement' applies only.to quality rel'a'ed changes (ie, changes-t to'the: procurement document provisions identified in ANSI N18.7,-

r 'Section.5.2.13.1,l Subitems l'through 5.) The timing of reviews will be- 'g the:Laame;as for review'of.the original procurement document.~ t ik7e. SecL7.'5-jW Requirement - "Personne11 responsible for-performing verification activities shall be . qualified'.in'.accordance with. ANSI N45.2.6 as applicable." -_ k,- iPD1081- 0535C-QA06 : 3

5. F b m r .) Page 86 Rev 11 i Date: 10/15/90 ] s Exception /Ihterpretation N i ,e .. Consumers Power qualifies audit personnel according'to N45.2.23.

Thus,

' personnel performing source verification audits may not be certified g1 according to N45.2.6. Personnel performing inspection as part of g. source verification will'be certified to N45.2.6. !,17 f Sec 10.1; ( 4 Requirement! .i / "Where required.by code, regulation or contract requirement, documen-

t x-

, tary evidence that. items conform to procurement documents shall be j lavailable.at'the n'uclear power plant site prior to installation or use g! r 'of such items, regardless-of acceptance methods." gH Exception / Interpretation m .-{ 5 Refer t'o Item 21'.1 \\ .Sec 10.3.4 --(as modified' by RG11.123, C6e)

17

.1 8 jequirement ': } " Post-insta11'ation(test < requirements.and acceptance documentation shall j ~ L Lbe' mutually established-by the'purchaserLandLsupplier." H .u -il Exception / Interpretation. l i) i, ,p Q,1 -In,exercisingbits ultimate' responsibility for fits QA program,' CP tCo' f l>j^ Lestablishes' post-installation test requirements,,giving due considera-e3-s e tion,to; supplier recommendations. -J j a ,w n 118a." ?RG:1.26, General? j iRequirement s --) ( ,1 1

l1'

.s h X RG 1.26Lestablishesia. system for classifying pressure boundary items l{ f, Land?ANSICStandards requirements.' '(However,~RGil.26 does not indicate < Linto 'four quality; groups,' which 'are then correlated with ASME B&PV Code;

g E

t, twhich of the.fourfquality groups are safety-related, and which ares n no t. ) _- i, u ,E' ~' ld ,-Exception / Interpretation 1 lRG:1.26 was used~as a reference;to establish piping system boundaries, Y

but.not for. defining, specific-quality groups o'r making safety-related f

. determinations.'.-:RegulatoryfGuide'l.29i subject to Exception /Interpreta ' gs ition:20a' 'is,us'ed ito determine what systems 'and.' quipment are .g,;l e y safety-related. 7 [< PD1081-05350-QA06' m ~ s i 1

. i. 4 };. l. ~ Page 87 + ,m .Rev 11 i Date: 10/15/90 l gy '19a.: Branch' Technical-Position ASB9.5.1 and 10CFR50 Appendix R, j .C 3 Sections III G., III-J. and III O., General J Exception / Interpretation yg g<, Fire.protecti.on measures,. equipment and the individual plant Fire o 'a d Protection Plans are in compliance with the NRC Safety Evaluation Reports and the required sections.of 10CFR50' Appendix R except for the t' z specific exemptions approved by the NRC. ,20a., RG'1.29,.Sec C. Regulatory Position j ~ i Requirement i lThe1 Regulatory Positions states that the identified structures, systems, y and. components are to be? designated Seismic Category I and should be H p ' designedito' withstand the SSE, a Exception / Interpretation l J -l 4 ! oth'CP Co nuclear' plants 1(Big Rock Point-and Palisades):were designed,' j 1 3 B i g, constructed: and licensed : based on criteria available prior' to Revision- ,1 3 oflthis ~ Regulatory Guide being issued. The-specific design criteria q s ' and seismic: designations are f reflected in the FHSR and FSAR, respec-3 r tively,('and insother; docketed analysis.- Thus, the design; bases and j jj seismic designations!do not correspond to those of Regulatory Guide- .j '1.29.J ( e s The criteria.of:this~RegulatoryLGuide are used'at CP Co-primarily in.- y /the11dentification of systems,-structures, and somponents.to:which the-J y QA Program-is applied-(see'20bi below) c20b.. ERG ~1.29,lGeneralf t.4 1 ...s 9 w I

Requirement -

M m LA'pplylpertinentQuality; Assurance requirements of 10CFR50;. Appendix'B.- j M, JE ception/ Interpretation o .i 't 3: .Thi pertinent QA requirements'for these(systems,. structures and compo-j G.. ^ nents willibeldetermined in a graded. manner using: tools-lsuch as the ' s g plant specificI Probabilistic. Risk Assessment and the; Technical Specifi- ,} ~ cations,cand{other docketed' analyses to; determine the degree'which; E s Appendix B'of;10CFR50 applies. G y o q + 'i l t $)ii ?c; a J PD1081-0535C.QA06 I g _,y.,, ..m.._

1 F I I EL I E b I I K W T e I k I. I.- .? .ii-}}