ML17329A049

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Dynarack Simulations to Demonstrate Ability to Predict Classical Nonlinear Phenomena.
ML17329A049
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Issue date: 06/07/1991
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.855M%HOLTEC9106i40043 9i0607PDRADGCK050003i5PPDRDYNARACKSlhKJLATIONS TODEMONSTRATE THEABILITYTOPREDICTCLASSICAL NONLINEAR PHENOMENA byA.I.SolerHoltecReportHI-91614HoltecProject10290ReportCategory:

I;f SUKQvfARY OFREVISIONS HoltecReportHI-91614Revision0containsthefollowinaes:TitlePageReview8cCertification LogSummaryofRevisions PageExecutive SummarySection1Section2AppendixAAppendixBAppendixC1111120294 ect EXECUTIVE SUMMARYThisreportcontainsresultsofadditional verification studiesonHolteccomputercodeDYNARACKperformed todemonstrate DYNARACK's capability tosimulatecertainunusualandarcanecharacteristics exhibited bysomenonlinear systems.ThisreportisasecpxeltotheoriginalDYNARACKQ.A.validation report,anditwasundertaken toestablish DYNARACK's abilitytosimulatetheso-called "jump"andsubharmonic responsephenomena associated withcertainnonlinear systems.Towardsthisend,sampledynamicproblemswereselectedfromtheliterature andwereanalyzedonDYNARACK.

Theseproblemsdemonstrate DYNARACK's abilitytocapturebothstandardandspecialcharacterizations ofnonlinear systems.

1.0INTRODUCTION

Thisreportprovidesverification thattheHoltecdynamicsimulation codeDYNARACKisabletopredictcertainclassical nonlinear phenomena thathavebeenfoundtoexistincertaindynamicsystems.Inparticular, weaddressherethesimulation ofCoulombfrictionbypiecewise linearsprings,thedevelopment ofsubharmonic resonance, theestablishment oflimitcycles,andtheprediction ofnonlinear "jumps"inthesolutiondepending onthedirection ofloading.Fourproblemsareaddressed inthisreportwhichshowthatthecomputercodeiscapableofpredicting theclassical phenomena.

HoltecProprietary Reports:User'sManual(HI-89343, Revision0);Theory,(HI-87162, Revision1andHI-90439, Revision0),andVerification (HI-87161, Revision2.)1-1 2.02.1NONLINEAR DYNAMICANALYSISPROBLEMSSubharmonic Resonance Considerthegenericsingledegree-of-freedom systemshowninFigure2.1.Amassmissubjected toadrivingexcitation F(t)orabaseexcitation y(t).Themassisattachedtothesurrounding environment byafrictioninterface, byagapelementF(t)withspringrateK<,andbyanelasticspring-damper systemthatcanexhibitatmostnonlinear cubicbehavior(inFigure2.1,6'zistheextension oftheelasticspring).Figure2.2showsthebehaviorofthedifferent elementscpxalitatively.

Allofthese"spring>>elementsarecodedinDYNARACK; theuserneedonlyinputtheinformation regarding thedegrees-of-freedom thatcausethespringextension, andtheinformation concerning springratemagnitude, etc.Zntheinitialproblem,weassumeF(t)=0,andthecoefficient offrictionp=0(notethat)P~)=pF~whereF~isaninputvalueortheloadfromanadjacentcompression onlystopelementthatrepresents thecontact).

Wealsoassumeinthisproblemthatx,islargesothatthegapelementneveracts.Thenonlinear springisassumedas(Kz0)F,=-[K~6~++S~]andtheinputexcitation isy(t)=10gsin(2n'ft).Weassumem=.1036lb.sec./in.,C~=0.,K~=90lb./in.,Kz=10lb./in.,f=9.4HZ,andg=386.4in./sec.Foralowamplitude linearexcitation, thelinearnaturalfrecpxency is2-1 t'10 f04.69HZ2rmIfweintegrate g(t),andrequirethattherebenorigidbodybasemotion,then10g=-65.4228in./sec.y(0)=0Toensurethatthespringisinitially unstretched, weassumethesameinitialconditions onthemassm.Figure2.3showstheacceleration ofthemassversustime.Thesubharmonic resonance isclearlyvisibleinthatthereisastrongresponseat4.7HZ(halfthefrequency oftheimposeddrivingexcitation).

AppendixAcontainsnumerical resultsforthesameproblemdoneinReference 6.6.2.2SlidinFrictionandDeadBandsConsiderFigure2.1forthecasex,~ao,F>=0,Cz=0,F(t)=Bsinrt.That.is,weconsideramassrestingonafrictional surfacewhichgenerates africtional resisting force+Randisdrivenbyanexternalsinusoidal force.TouandSchutheiss havegivensolutions forthissituation.

Theinteresting featuresofthemotionarethatifR/B<.536,themotionisroughlysinusoidal, buthasdiscontinuities inacceleration.

IfR/B.536,thenthemotionissporadic, therebeingso-called deadbands"StaticandSlidingFrictioninFeedbackSystems,J.TouandP.M.Schultheiss, Jour.Appl.Physics,Vol.24,9,September 1953'p1210-1217

'-2

~pC withinwhichnomotionoccurs.WhenR/8>1,nomotionispossibleexceptforaninitialtransient.

AppendixBcontainsacopyofthereference.

Here,weuseDYNARACKtomodelthephenomena.

Thegoverning equationisdxmdt=8sinwt+RWesimulatetheeventform=8=1,andR/8=A=.3,.7,and1.01.Thefrictionspringconstant(Figure2.2)issetatQ=1x10lb./in.tosimulatean"infinite" slope.Figures2.4-2.6showtheresultsforthethreevaluesofA.ZtisclearlyevidentthatDYNARACKiscapableofreproducing theexpectedphenomena.

XnFigure2.6,thesmallnon-zerovelocitycomponents subsequent totheinitialtransient areduetothepresenceofthefiniteQ.2'JumPhenomena Considerthedifferential equationmx+bx+cx+dx=EsinvtWeletxz=(d/c)x;tz=(c/m)tThenthedifferential equationbecomesdxy2dx1+6dt)dt's+xg+x~=Egsinugt3wherexz,tgEgvga8aredimensionless and6=b/c(c/m)E>=E/C(d/c)v~=e(m/c)2-3

Anapproximate firstorderasymptotic solutionisobtainedanalytically byBogliubov andMitropolsky.

Foranassumedoscillatory solutionxgacos(y>t+8)a=a(t)(8=8(t)theapproximate solutionforthev-aresonance curveis3w,=(1+-a)8E2vl(w(a)+[8~)I'21',Fortheparameters 8=.2,E>=1,theresonance curvecanbeconstructed usingusingtheaboveapproximate analytical solution.

AtypicalresultisshowninAppendixC,andtabularresults,sufficient toplottheresonance curve,arealsogiveninthatappendix.

Notethatthesolutiontothelinearnon-dimensional equation(neglectthexzterm)predictsthepeakamplitude

)x>)~=5.0atafrequ'ency of.99rad/sec.Ithasbeenshownthatasystemwithahardening springhasaresonance curvewhosecentralspineistiltedtotherightasshowninFigure,C-1 inAppendixC.Theresonance curveisobtainedforagivenamplitude ofexcitation.

Inpractice, theresonance curveshowsareasofinstability.

Iftheexcitation frequency rises,theresponsefollowstheresonance curvetoacertainpoint,andthendropsabruptlytoasmalleramplitude.

Similarly, iftheexcitation frequency isdecreased throughtheresonance region,theresponsewillpassalongtheAsymptotic MethodsintheTheoryofNonLinearOscillations",

byN.N.Bogolinbov andY.A.Mitropolsky (Translation byHindustan Publishing Corp.,1961),pp244-245.2-4 rg,4fi lowercurve,totheinflection point,andthenabruptlyincreasetothehigherbranch.Itisfoundinactualshakerteststhattheonsetoftheinstability issensitive tothesweeprateoftheshaker.Weattemptheretodemonstrate theabilityofDYNARACKtopredictajumpphenomena.

Wesimulatetheresonance curvebydoingatimehistoryanalysiswithE>='1,b'.2,andv<slowlyincreased fromavaluelessthan1.0rad/sec.Thesweeprateissetlowenoughtobeabletoascertain themaximumresponseamplitude.

Figures2.7and2.8showtheresultoftheDYNARACKsimulation.

Figure2.8alsocontainsthetwobranchesoftheresonance curveplottedfromTableC-1inAppendixC.Bothfiguresshowthatthesimulation codeisabletomodelthejumpinstability; however,theresultsshowthattheonsetofinstability isverysensitive tothetimestepsize.Figure2.7represents arunfor5000secondswithstepsize.004sec.whileFigure2.8showsthecurveobtainedwithastepsizeof.0001sec.Weseethattheamplitude attheonsetofinstability isrelatively insensitive tothestepsizebutthefrequency atwhichtheinstability occursissensitive tothestepsize.Itisapparentthattoexactlyfollowtheresonance curve(itselfanapproximate solution),

anextremely finestepsizeiscalledfor.Wedidnotattemptanymodelingoftheresonance withadecreasing forcingfrequency.

2.4LIMITCYCLES0WeconsidertheproblemstudiedinShawandHolmes.toinvestigate theabilityofDYNARACKtopredicttheexistence ofstablelimitcycles.IntheShawandHolmespaper,themodelS.W.ShawandP.Z.Holmes,"APeriodically ForcedPiecewise LinearOscillator",

Journ.ofSoundandVibration, Vol.90,1983,pp129-155.2-5 0A' described inFigure2.1isinvestigated undertheassumptions that'frictionisabsent,thespringF>islinear,andtheexcitation isbyaharmonicforce.Thenon-dimensionalized equationcanbewrittenasx+2ax+H(x)=8coswtwhereH(x)x<xowx+(1-w)x,x>xoandw=(Kz+K4>/K~2Figure2.9,reproduced fromShawandHolmesshowsdifferent casesoftheaboveequation.

Thecasex,=0isconsidered sotheproblemisessentially thatofapiecewise linearspringhavingadifferent springconstantintensionandincompression.

TheresultsfromDYNARACK, forthesameproblemsofFigure2.9,areshowninFigures2.10-2.14.Thecomputersimulation startedfromaspecified initialcondition andcoveredasufficient numberofcyclessothatalimitcyclecouldbeestablished.

Figures2.10and2.11showthematchwithtwoproblemsshowninFigure2.9.Thesimulation predictstheoneortwostablelimitcycles.Figures2.12-:2.14showresultsofthesimilaranalysisforthethirdcaseconsidered.

Figures2.12and2.13showtheeffectofdifferent startingconditions.

Itisclearthatonlythestableperiodoneorbitisbeingtrackedbythenumerical solution.

Figure2.14isaplotofonlythelastfewhundredtimestepsandconfirmsthetendencytowardthestableperiodoneorbit.Theperiodthreeorbitappearsunstablewhichseemstocontradict theconclusion in.ShawandHolmes.However,ifonereadsthetextinFigure2.9,ShawandHolmesappeartoconcludethatanunstableperiodthreealsoexistsatthesameparameter values.Wecanonlyconcludethatitisextremely fortuitous ifthenumerical solutioncansimulateastable'orbit whenanunstableorbitwiththesameperiodexistsconcurrently.

2-6 Fgcllos,'IN1Bkg,4CIQ,/(gg4ICIPily')JyI~FIGURE2.ll-DOFMODEL

'%'Olkt1 FIGURE2.2SPRINGCHARACTERISTICS

)Gory~iNEkEcAS7]c'S--+5.CoKP..88ssI.0U.....0AJ6Y,Flicv]giN7ERFcg,gLD~g~~F~x2-8 Cp,"i,'}

7.5Acceleration ofMussvs1imeLevyProblem,Sec.2.14,Subharmonic Resonance) 5.02.50.025-5.0C75)-:0.025-'I5.0-17.5-2oo0.0D.l0.2D.3D.l0.5D.6time(sec.)FIGURE2.30.70.80.91.0 J'is~'l~.(I 0.20Oscillating masswithfrictionR/F=.3liloDeadBandsVelocityofmassvstime(initialvelocity=0.)0.150.100.05~--0.00U01-0.0:,-0.100L-0.20-8.008.258.508.759.009.259.509.7510.00time(sec.)FIGURE2.4

0.0 8Oscillating

masswithfrictionR/F=.7DeadBandsPresentVelocityofmassvstime(initialvelocity=O.)0.050.030.00U0(D)-0.0=528.0000Q28.2528.5028.7529.002.9.2529.5029.7530.00time(sec.)FIGURE2.5 Pl 0.20Oscillating masswithtriction8/F=-1.01 n-inssevel1lllally sl.opsVelocityofmassvstime(initialvelocity=-1.)0.00-0.20~--G.40U003-0.60-0.80-1.000001.002003.004.005.006.007.008.00tilTie(SBc.)FIGORE2.69.0010.00

JumpPhenomena

--frequency increasing from.9r2.00C0y)1.00Q0.000.901.001.101.201.301.401.501.601.701.80I.902.00FIGUR2.7Iyeq.ygiso

~ht44 2.50JumpPhenomena (increasing frequency withtime)2.252.001.7501.50c1.25o1.000.750.500.250.000FIGURE2.8fieq.fcitio5016017018019020021022023024025 literij-lt!

FIG.2.9(REPRODUCED TEXT)~4Qe~4.04S.W.SHAWANDP.J.HOLMES(4)(b)0oa04-0-4004-04-na004r4Figure8.(4)Siableperiodoncoibitai4>240,a012$,re0,III~and>24,fromdigiialsimulaiioa; (b)stableperiodiwooibiiaicu<<242,a<<0l2$,llI,ro<<0,and>><<4,(romdigitalsimulation.

Boih)aprojected phaseplane(r,y).Byusingdigitalsimulations, othersubharmonic orbitsarealsofoundtoexist.Figures9(a)and(b)showthecoexistence ofsingleimpactstableperiodoneandstableperiodthreeorbitsforx0~0,cs~0026,ns=42andm~35.Wcconjecture thatthcperiodthreeorbitappearedinasaddle-node bifurcation

[21]andthatanunstableperiodthreeorbitalsoexistsattheseparameter values.Analysisofthisbifurcation ismuchmoredifficult sincenoreasonable assumption regarding thctimesofflightcanbemadeandhigheriteratesofthemapping(multiple impacts)appeartobeinvolved.

oalo)440~<<>~004Figurc9.Cocrisiencc olstableperiodihseeandstableperiodoneatci<<P2,a<<0OM,i)<<l,re<<0and4><<3$.(4)Period3;(b)pcriodI.Bothinprojecied phaseplane(r,y).4.3.THEIMPACPLIMlT>ANAI.YSIS Inthcimpactlimitanimportant simplification occurs,sincethetimeof()ightduringtheimpactistakentobezero.Thisallowsmoreanalysistabedoneonperiodicolbils.Wealsorcscale:x~Px,andtakeunitforcingamplitude.

Thcreturnmapfortheimpactoscillator isverysimilartothconcforthegeneralsystem.Frompoints0to1inFigure4aneusestheimpactlimit,i.e.,ri~roandyi~-ryo.(49)FrompointsIto2oneusesthesamemappingasdescribed inthegcncralcase.'IllusthemappingPstillcannotbewrittendownexplicitly.

Asbefore,howcvcr,onecancomputeDPanalytically.

Moreover, inthislimitingcaseonccancomputeperiodicpointscorresponding tosingleimpact,periodnorbitsdirectly.

Suchorbitscorrespond tothosemotionswhichstrikethewall(theverystitfspringki)andthenremaininx<xoforPIECEWISE LINEAROSCILLATIONS

+141exactly2sln/osmtimeandthenstrikethewallagamwiththesamevelomtyasthepreviousimpact.Thcconditions fortheexistencc ofsuchanorbitarera-ro~2srn/ns,yz~yo~-ys/r,withyo>0-(50>51)Thesetwocanditions allowanetocomputetheperiodnpoint(I,y).Firstoncwritesequation(7),usingequations (5),(50)and(51),toobtain0~-xof+Ays+sl(8f

+Ayn>)+cs(yf

-Amos),(52)wherewehavedrogpedthcminussubscripts ony,8,andOandwheref~1-EcacrA,A><<Es/O,Ec",seisin(2>rnO/cu),

andccos(2srlsO/0>).

Nextoncwritesequation(51)usingequation(50)andthctimederivative ofequation(5)toobtain0=y(-I-r+rf,)+Arxo+s r(yosf-IB)-c,r(beef

+Ay).(53).Sinceyiappearsinalinearmannerinbothequations (52)and(53),itmaybeeliminated Ioobtainasingleequationinvolving onlyriasanunknown(inthctermscsicos(o>rs)andsisin(mrs)):0=-(../A)[r 1'-rP]+5[ryrul-Aar+g/A)(ar

+Ay~)]i+c,[-amr.-.fyr+

g/A)(yr-Arm)].(54)Iwhere((>=I+r-rf.Straightforward association oftermsallowsthisequationtobcwrittenas0=X+stY+ciZ,(55)whichhasasolutionI(1/m}[arctan (Y/Z)+arccos(-X/W)],(56)~+~.si>>*>>ioo>i~heiiitheperiodnorbit.Thevclomtylustafterimpactyiistheneasdycomputedbyusmgeitherequation(52)orequation(53).Itisimportant tonotethatasolutionobtainedasdescribed aboveonlysatisfies x(rs)xoandx(ls)=-rx(ra).

Ifthevalueofyl~x(rs)ispositive, thenthesolutioncorresponds toanon-physical, or"penetrating" orbit[13].Theorbitsforyinegativemustabobecheckedsincenowherehasonebeenassuredthatthcdesiredxocrossingigthefirstontheorbit.Infact,theaboveconditions canbesatisfied afterseveralxo~crossings, forsomeparameter values.Caremustbetakentodetermine whichofthesealbitsarephysically possible.

Knowingthcperiodicpoint,onecannowcomputeitsstability.

Asbefore,oncbreakstbecalculation ofDPintotwoparts,frompoint0toIandfrompointItopoint2.Herc<<herc[>)(ra,yz)/i)(ls, yi)]wasderivedaboveintheanalysisofthefinitestilfncss case.Framthiscalculation onefindsthatDPhasdeterminant D(ryl/yz)c~gadtraceT[e'~</Oy,l(N,

+rNa)sin(O(r,-ro))+O(y i-ry,)cos(O(ra-ro))].

(60)Evaluating onaperiodnorbitgivesiD=rEandT=(E/Oyo)[(l

+r)(4+xo)s-2ry Oc],(61,62) 1"I4't g5LimitCycleBehavior(xO=v0=0.)

'.000.750.500.25~-0.003(Qr.-025-1/yI((-0.50-0.75-1.00I-1.2~I0CIISPICICel AeiltFIGURE2.lo.2-1.1-1.-0.9-0.8-0.7-0.6-0.5-0.4-0.3-0.2-0.1-0.00.10.2 IC4sI 1.00LimitCycleBehavior(x0=.1,vO=O...Fig.

BbofshawandI-lolmesShowsprediction oftwostablelimitcycles0.750.500.250.003(D-0.25U050-0.75-1.001.25-0.8-0.7-0.6-0.5-0.4-0.3-0.2-0.10.00.1FIGURE2.11CIISPICICeITlen t~~l-1.0-0.9

'I(x,O.

0.800.600.20~000IL~;-G.2GE~-0.40//II/j),s/ij,,~;yl-0.60-0.80-1.00-0.5-0.5-0.4-0.4-0.3-0.3-0.2-0.2-0.1-0.00.00.10.10.20.20.30.3displacemen t

1.00LimitCycleBehaviorofaBi-LinearSpring.x0=.2,v0=0Fig.9ashawandholmes..cycles oforder1and30.75H0.500.25~0.00o-0.25(D+-o.5o/Ql.j-0.75-1.00I-1.25-0.7-0.6-0.5-0.4-0.3-0.2-0.1-0.0displacemen t0.10.2

)jA<nIiW 0.40LimitCycleBehaviorofaBi-LinearSpring.x0=.2,vo=oFig.9ashawandholmes..cycles oforder1and30.300.200.10~0.00U0-0.1003-0.20-0.30I-0.40C)0.50-0.50.10-0.40-0.30-0.20-0.100.0000.200.300.50FIGURE2.14displcjcernent APPENDIXASEC.2.14FromTextbook"Component ElementMethod",McGrawHill(1976)byS.LevyandJ.Wilkinson (Subharmonic Resonance)

'IS-Ci~

82YIIF.nislleNSNr Fg.saicigr aiaggg.IIYIIAKIIE>>

oFslislol.L AIAsssYsilais83inthethird,and60Hzto120Ilzinthefourth.Lctiheg-levelbe0.3lgatI~0,I25gatI=14),50gatI=20,54)gatI~30,and00gaiI=44).Thisdescription corrcspon<ls toconstantdisplacement amplitude excitation below30llz,andaroll-oilioOgbetwccn60Ilzand120Ilz.'.46Insomecasesatresonance, ihcforcesarcscvcrcenoughiocauseabolltoli%olfiisseal.Insuchacase,theclfcctive springstiffness dropsmarkedlyatlift-off.

Rerunthcexampleproblemwithc=015Ibscc/in.andaddk~-800Ib/in,,y=0.222in.,corresponding toIifi-olfai50g(900x0.222/450g).Thctotalstilfncss afterlift-olfis900-800=100lb/in.IlowdocsIhcpeakamplitude comparewiththevalueinFig.2.3872.47Repeatproblem2.46fordecreasing frequency.

(IlinrrLctfrequency bc100,60,30,5andg-levelbcI,5,5,Ifortimes00,14),25,and30,respectively.)

Noteihcditfcrencc inrcsponscforincreasing anddecreasing frcqucncy forthisnonlinear system.248Repeatproblems2.46and247withc~020.Docsihcincreased dampingcauseamarkeddccrcascinamplitude I'orthisnonlinear problcm72.I4SVIIIIARMONIC RESONANCE Subharmonic resonance canoccurinmechanical systemsifthespringI'orceisnon-linear.Asanexample,wewillconsiderasystemforwhichspringlorce=90(y-x)+IO(y-x)zWetakethemassas01036lbsec/in.,sothatthelowamplitude naturalfrequency is47Ilz.Thesystemisexcitedbyasupportmovementat94Ilz.TheresponseisshowninFig.2.39.Theresponseisquitenonlinear withoo(hc=00nndc=03;however,itisevidentIhatIhc47Ilzcomponent ismuchlargerthanthe94Hzcomponent.

Anintcrestino featureoftheresponsecurvesistheirlemlcncvIotrratthe+50levelasabarrier.Inthespringforcesketc)t,wenotethatthemaximumcompressive.

forcedevelopeii hvinc.nonlinear springissue>Ibal45in.comnrrssion.

)!ereinrepresents aweightnf40lb.soIhespringcanalmostapply2025/4~'=506a ofupwardacrrlcr:ilion Thedaoip.miglitmodifythisvalueslighlly.

I.orinespringelongatio>>,

linwever, Iherestoring I'orcebccoinesquilehighandresultsindownwardaccelerations ashighasI5(/.10IiIIIIIIIIIIIiiilIIIIIIIgIIIiIIIIIiIIII~IIIIIIiIIIIIIIIIIIIIIiIIIIIIIIIIIIg,010IIIIIIIIIIIIIIIIgI'I02IIIIIIIIlIIIIIIIIgIIIIgggII0'6IIIIIIIIIIIIii]IllII~IIIIIII1II0IIIIIIIIIIIIIIIII-I-15------suppoumoglon

--dampednlass,rIHIbsec/in-undampedngassm-01036Ibscc/ingl/g~10sin(2II9'4g) 1000IbSPglilgforceforce90(F-z)+10(y-)z-5imrIIIIIIIIIIgIIIIglI~IIIIIIIII1071imc(sec' IIIIIIIIIIgIgIIlSnflllgelongation

-10001b.Problcnis

?49Repeatihccxamplcproblemwithihcsupportg-levelincreased from10gio15g.2.50Rcpcaitheexampleproblemwithibcexcitingfrequency atthreetimesibelowamplitude naturalfrequency.

2.51Rcpcatproblems2.49and2.50withkz=5Ib/in.insteadof10lb/in.2.15SVMMARYThischapterhasconcerned itselfwithIhesinglemasssystem.Ingeneral,restoring forcesofthesystemwerenonlinear, consisting ofnonlinearly linrdcning orsoftening

'springs,

friction, orslops.Numerousexaioples ofsuchsystcioswereslutliedhymeansofocomputerprogramgivenioIORTRANinsection24ofthiscliapler.

Thcnumerical examplesweredesigiicd toilluslrileeichfeatureofthecoioputerprograin:

FIGURE2.39Rcsponscornonlinear systemwithspringforce~90(displacement)

+IO(dicptaccmcnu excitation at9AIlz.LowamPligudc naturalfrcqueigcy Iua~47Itz.RcgPongcshows'b.bagg'ilcllllc lcsollallcc cffccgnamely,eachelement(springsofvarioustypes,stops,friction),

andeachtypeo'xcitation (I'orcesonthemass,acceleralion ofthesupport,aodtime-varying exi0-tionsolonekindoranother).

Inaddition, wemadecomparisons behvecn'.cnumerical resultsofthecomputerprogramandsomeoftheknownsolutions exisu'.I"in(lielilci'illiife forlloilllllcilf systcllls.

Wehavereacliedupointwherewecaninquireintothebcliavior ol'asysiclohavingmorethanonemass,eachmassinteracting wilhothersbyme;insofsprii~s,ilampers,

friction,

<<ndstops.Suchniulti-inass systemswillbediscussed iothcI'stchapter,wherecooiputer prograios suitablefortheirstudywillalsobcgiven.

APPENDIXB(SLIDINGFRICTIONANDDEADBANDS) r.Fg tJ0t.'tNAi0PAPPI.I80P!IvSIesVs)00uxtL' i.)0<'htnl<X 0)StaticandSlidingFrictioninFeedbackSystemsJ.TDUh'.0<DP.1c>IUI.T'IE>ss Dcparln<ml o/E(w~)real Entimcrixg Ya(cUniecrsily,

.YreHaeex,Cs>xscdic<s)

(Rccciv<January16,1953)sgprv.stu>'.g,"'<<r.,'sf;.1

.n~,rOneoithemostcommonnonlinearities encountered inservsirnechanisms designistrefrictionphenomenon inelectron>echanical systems.Conventional lineartheoryfailstopredictits<<ifcctuponsyslemperformance.

Thispape.extendsfamiliartechni<tucs tnthetreatment oifrictionnonlinearity insar:nays><ms.

Frequency.

<esponscmethodsareemployedthroughout an<Ithethcireiiralreiul<saicvcri<sesl liy<nvansnfananalogcomputer.

Sliding(<ictinnanilstaticfriclir>n nrerq)renenicsl Iiyslesc<il>ing functissns

.ihichlnrm:hecriticalfactorsindetermining systemstal>ility.

Thcanalysisin<(ical<a thatcertainserirsequalizers

<lcsi<<nest fromlineartheorymayfailInachicvcc>7celivc cs>mpcnsatinn inihaPr<~enrcofslidingan<1static(riction.

Ontheotherhand,asuhsi<liary losspmayavsii<ithestaliility p

    lcmivhilestillrealiring answscnlially eluivaten< loopgainf<<nctinnI.II('iRODUCTIVil HKEbasicanalysisnn<tsyntliesis i>r<i<Lcturcsfor~~rlinearfeedbacksystemsl>avc1><<imeivctiss-tablished duringthelast,<t<.<<;><le, thereisnos:s)rresl><)>><t-inglybroadapproacht<)n<>>>linear pr<blem..Ex<0cptinverysimplecases,nogeneralsolutions arc,)ossihtc, anilthedesignermustrelyeitheronmachinecomputation oronvariouslinearorquasi-linear ariproximations. Avarietyotsuchapproximat.ions hasbeentievctopc<t 'tot>tnumeroustypesofsystemsandsue<<cssiul <le=i',n procedures havebeendiscovered foragrcat,manypra-ticaiproblems. Itisthepurposeoithispapertoex(en<ioneofthesetechniques soastomakeitat)pticabte Iotheanalysisoffeedbacksystemsinvolving slidinga;idstaticfriction. Particular attention willbcpai<ltore.-tainloopgainfunctions >vhichappeartoiiequitesatilt-factoryonthebasisoflinearanalysisb>>tnrcfos)n<ttrbeunstableinpracticeasaresultuffrictis>n i>t>errn'cna. Methodsofpredicting, anilhence1:rcsunal;iy prcvert-'ng, sucnt)ehavior willbe<.uttine<l. 11.REVIBKOPBASICPROCEDURE ssI!<nwsnnJs,~isaniiiJf<<<<0>'snnnsss<00s5< Ass}~I'a<A<<sn<ii<0f0i>i>>niyii,afundame>>tal corrlx)nent >>itnc>>>>>ts;;.s I!iinrcItic)amplitude an<Ipnascoftnefun<!".ni)nial <nmix)n<n)I. variesirishthcnmplitu<)e nf'.!>ear!>!isxi sinus<>i<t, lheapproximate chamctcristics nf!h:as>>i~linear<tnVi<<CarerepreSCntCd iiy'>n"a>nt>tituslo (.-scribingfunction" Fl,>'a.)=I'(4e<'<" (sceFi<i.1}.ti'cpreentsthcamplitude i)tasinuMittat inp>>tsigna!,f(")isthcratiooithcf>>n<(a<>cntntoutputtoI!)ci::,"n:.amptit>i<le and>(z)>stl>cpl>0~.:i))iioftile<liltss~'un<(.>mc>>rn) .e.'a!ivc 'to:licinpu:siPnal.%<tc'::.';::s,;")ixfrC<tuen<~ inVariant, itrtepen<tS nniysin:::~~inputarnnlitu<!c. ()n<'e<'fn(Z)Ivgn>>W>><:I>tat)st'ty an<it'S(S<<ant)rnC'."I essct>tinily;is int.i>clinear<':isi:.<".<>>>sist<)r I.l>esimple!.i!sir sl>mvninl'i<1.2.System.:;>i>>tity isgovcrnc<i hy.l:.~roots<>fthceruatis)n '00000Thetechnique tobeemploye<i wasfirstievise<tbyKochenburgeri fortheanalysisofcontractor serv>>-mechanisms andsubsequently adaptc<lforusewithothernonlinear devices.".'t>c basicprorc<t>>re has))cendes<Tibed extensively. iittheliterature' andwillthereforbeoutline<i onlyhriIly.Itisuniqueinthatitpermit"useoftheir~uency<tomainina<<apl:rs>a<
  1. g certaintypesofnol>linear etc<.ants.Ifasinusoidal voltageisappliedtoan>>niincar dcvicc,theoutputisgenerally notsinusoi<lal. II>>>vcver, uliderrathergeneralconditions thcfun<tamcntat corn()onent oftheoutputwitthegreaterthannnyharmonic, adifference whichwittbefurtherempt>assize,l byeffective low-passfilterssuchasservomotr~. Adequateaccuracycantherefore beobtainedinmanycasesbyconsidering F<s:.!.Des<rihh:gfu:iciisni ss<anonlinear slevie<<.0<>r(i(s)=-I!Ea(.z).l>>thelinearcaseFl<<{z)=-1'>n<ltt>cstol)itity pron!emre<luccslothc<.>>nvcntionat one,sntvctl'easily bymensofaNyr>>l<<..plot.iŽneonlyInodifi<n'i"n r!<<ir.dfcrtn>>onlili<';ir <'aseun!tertliuassumptions statedIsachangeinttecriti<<atpointwhichnowbecomes-I//la(x) instca<lof~l.Thusthecriticalpointchangeswiththesignalamplitude, anilitbecomesnecessary toplotanamptitutte locus-I/Ela(s)ina<!di-'iontothefrequency 'usFE(s),Iftheamplitude locusliescompletely outsidethefrequency locus,thesystemisstable>>niter allo>ndition ofoperations.'igure 3sl>owsintcrsccti<>g!o<<i. I%etcthrsystemeunabi.". forsmall<list>>rt>aiiccs, butstahteforlargedLsturt>anccs s>><e>us;oily thein'elsekxi,till(s).>nil-H~(x),arot>lo<t~t. Thuhoicol~goveriiesl:imlily!i" ron>putat(onat cnnvenie. ~'>>pa<lieut:<r <nuts>no< s.0No<vivithPhileoCorporation, Phila<lcil>hia, 1'e<insylvania. IR.J.Kochenhurgers Fdee.Fng.69,<'s><7(li).=,>>>. SeealsoT<ans.Am.Inst.Floe;Eng<s.69,270(1950).sEC.Johnson,dissertation, 5fasi~chuse<ts [us<i:<<<x o(T<cli-nohgy,1951;Trans.Am.Inst.Elec.Fngrs.71>I,16i')(!952).>E.S.Sherrard, Trans.Am.Inst.Flee.Engrs.71><.312(195).121J0hi~0,000<jr0>00<i',00 wtg%jPIW'4~p,ysJ./+II'g~r STA'l'ICANDSllDlNCFRlCTIONlNFEEDBA(KSVSTE!}iS 12llbt."satoscil!ations willtendtostabilize neartheintersec-tionpointPwhichthusspeci6esthesteady-state condi-tions,atleasttoaGrstapproximation.'n summary,analysisofthestability problemv:illrequirethefollowing steps.(a)Determination ofthewaveformattheoutput.ofthenonlinear deviceresulting fromasinusoidal input.(b)Calculation ofthedescribing functionfin(a;)fromthc~aveshapeobtainedin(a).(cjPlotandinterpretation oithcamplitutle andfrequency lociforthesystemunderconsideration. Forthecasesofparticular interesthercthissteprequiresrearrangement oftheccnventinnal bloc!trliagcmminordertosecureeffective scp;Iratior. oi:iiilrci>>ster iun<<-tionsintotaro<<lassc:Theciasofalllinc"".!)utl:c-quencysensitive components anilthatofallnonlinear butfrequency insensitive cleincnts. Thefollowing definitions willbeuse(Ithroughnut thispaper.Staticfrictionisthetnrnucrequiredtoinitiaterotation. Slidingfrictionisthcv"locity-in(lcl)et)dent component ofthetorquenecessar.'o inainlain suchmotiononcestarted.Yis<<ousfrictionisthtcomlanentofthetorquewhicnislinearlyprolx)rtional totheangu-larvelocityoftherotatinmember. }n0}cI~tc)}}0n}CIS0C K}t}}}tntHts)nu}0}}IE}ccncn}Fto.2.Feedbackloops<<ithnonlinear eletncnt. IILSLIDINGPRlCTIONINSERVOSYSTZ.'tstS A.VivePormResulting fromaSinusoia~l'it)put TorquetoaSystemwithSlidingFrictionIfonlyslidingfrictionisconsidered theentirefrictionphenomenon canberepresented bythccharactcristi curveofFig.4.~Considerarotatingtnemberwithmomentofinertia'.Jandangularacceleration 8.Becausenfslirlingirictiontheeffective accelerating ordece!erati.)g torquer.is'}related totheap,"!iedtorquer,throughthecquatit)n r,~rn~T(3).'whereT,isdefinedbyFig:4.FromNewton'slawnf..motion,,r~T,+J8forangularvelocity8)l)(4)r0=-T,+J8for8(0.(3)=FromEqs.(3)I(4),and(5),theangularacceleration ,oftherotatingmemberisgivenby8(i)-..(i)P. (e)Hence8(l)hasthesamewaveforn)asr,A).Iftheappliedtorquerissinusoirlal, r,(t)=Tsino}t.}nc00}nnc'/ ..lS~'S~}0c'IIIIIIII'4}cI}talIIIII,c4c}/////rrr~rk!s}I'}I;.t.An}l}lit}}I!<<a}} Jfr<<In}<<nc: )I}<<i.whileo)I=>>~-a, )}=tiel,g,3Iitltc)l=/r.rccccc}nrncnncrcercFto.4.chili}ling irictinncharacteristi<<.. IThe(orres!>>ntlingstc"tiv-statewaveiorinsaresketchedinl'igs.5".;u).Thceffe(tivetorqut:)<<ave(lcrivcrl fromiq.I.<)isshownin}h)ttcdiincs.Tlicdiscnnttnuitics oithercw:ivccorrcs!xsnd tozcrnsoithc8(vavcbe<<ausethcirict,io>>al torqueT,.<<i)ant.cs signatthoseinstanis. <)nthc0curve,lx)intPisthep})intofinHcctinn, ct)rrc-s!x)n(lit)lc lomaximum:i<<cc.cratinn. Sine"thestra<<'tate isu.primaryittr:r:st, th'(:reference timeiscl)o~:)<<i:<rthcoscc!lation hasrc;t<<hc(l itssteady-state value.8(llII);tr<<cs thmughzc~)a:. JyCAj,4 1212J.TOUANDP.M.SCHULTHF;lSS5pII~rand<eareaNo.2~T(sided-sina)r.'(o>t) =T,Lcosa-(~-a)sinu~cnQ+tfsir~j.f13>IfEqs.(12)and(13)areseiequalandsimplified, theresultiscosd~ssina/2OI'9~cos)(xA/2)l'<)rt'<rcx'r<)m<<asr,8~a.l'<l.(11)l>e<~raus,n."\Frc.S.Sies<lystatewavefonnawiih<>ui<leo<ie<>n<<~.Itfollowsthatwherea=sin5,X~Tj'T,.Onlytheang!estcorresponding tothefirstdi:cr>ntinuity pointremainsunknown.Onceithasbeencrnluatcdin"termsofX,thewaveformiscompletely rlctrrmincd. Therearetwopossibilities: Ifa<8,thereisnorlearlneinther,wave(Fig..5). Ifa)P,thcrcarcdearlesasindicated inFig.6.Thesetwocases:vill besideredseparately.'e+ fn,)<,'2le =l3wiutir>>)f<)r.Eyic!dsX~h<.~l).53l).X,isthecritic;il valueofthcquartityT,/To.ThereisnodeadzonefnrX<'A,,nnrltherearedeadzonesforCasei~i-lurt<<den<izones.n>d.Ir.likemannrr,oneobtainsfromFig.6:sharlcrlarea.'4v.1sharlcrlareaNo.2~shadcrlareaNo.3=sharlcdareaNo.4,et<<./P.l.'wwja2~<'4~.rMathematical Rcprcsc))talion uflireSlcadylate 5'areFo<~sCase(1).-Nodeadzone.a<g.Refertotig.5.Intheabsenceofviscousfrictio>>, th.following steady-state conditions exist.ShadedareaNo.1~shadedareaNo.2~shadedareaNo.3~shadedareaNo.4,ctr.":Butbetweenaand6,r,=Tsino>t+T. ~T,(sino>l+s)na) =T,(sin<A+A); il0)antibetween6andc,r,~2,sine>t-T, ~T(sino>t-sina) =T(sino>l-X). (11)ThenP>iareaNo.1~T,(sincA+sina)d(rdt) T(-cos8+Pshe'+cosa+a sine:),(12)totethatadeadxoneorregionofseroellectlve torqueand'tysuchasbconFirr.6occurswhenevertheapplie<ltorquessmallerlnmagnitude thanT<<attheinstantwhentheve..ryreacheszero.~yelocftylsproportional tothelntegrr!oftorqueintheahsenceofviscousfifcdca). H<)t,l)ct)vren uanrl6,r.~Tfsi)wl-;-Al,l)etwe<:<) 6all<i<~a)i<ibet<veen<.':irl(l rl,r,~7'(sin~i-V.Ile)ice,5:ireaNo.1=-T,(sino)t+A)r>! fr>t)~'I;(-cni8; PP+<<osa+aX), !19)pg~RaraaAo.2=JT,<sin~<Md(el>-a(21)Fortheestrc)necasea~P~s<<r'A,Xsin-'X-(1V)I~(1X-)i(>rsin-<X)g)~X,~0.53f) asbefore.T,ccosa-(~-a)A+cosa+a@. (20)I:quating (19);tnd(20)anrisimplifying 'P-.coStl~ (I-V)l-(x-sin9,)X.0'I~pa.-~sQ. ~ICty1' ',B.Cil~tionoftheDescribing Puactioncer.(l)isaperiodicfunctionoftime,itcanbeintermsofaFourier'series: ber,(l)~-+g(asirusa}l+bcosncA). (22)aIrOP}PPI~}I't&l}tII~S~ )}~reIthasbeenpointedoutthat,toaGrstapproximation, ,(t)canberepresented bythefundamental component ofstdZo~m~es.Fromsymmetryconsiderations,
    be~0.Thisimpliesoscillation abouttherestposition'whichisacondition ofprimaryinterestinstability analyses.r Then~~}<<<<~~IIIwhereandr<(l)~atstr}IA+bt cosCP}l}(2316t~-r,(l)cns(os)d(cA).
    ]sr+0r.(l)sin(col)d(<ul) (24))'!G,6}teI.I)"stale '%atnnmsO'Ilhne'}lz}IAM.eiTectivc torqueisr.(l)~T,1-41--WPPQ~.V~I}EerJlualiors ofIhcFosrricrCocgcicnls Case(1).-isodeadmne,X<A.ora<j).lnacro.~.",}<< ..iththedeltnition ofSec.II,thede.scr'.bint; functionforthe3liding-friction elementisSimilarly T,(sincrl+ X)sin(cA)rl(orl) ~~+-T,(since-X) sin(N)rl(o}l) =-T(1-2'Ls). (2())llnr))f(QZSQ,)}%[(2s)s-Vjt)'-41--A'tan'-Case().~~it)ideadmont~,X>.'},ora)d~where(35)(sina+sinP)'P.) tan-'-(a-P)-sina(cosa+ cog)-cosP(si'na+sing)sExtensions tononseromeansarepossiblebutcomp)icate theanalysisappreciably. Srereference I.16t~2TQP(2/a)s-X'1). !27)1IS$Tg(<<nlldl ih]'.>>nlr<<}l!>etc;l) Equation. (23)mayalsobewrittenintheformnsitsr.(l)Ctsin(tel+6), (8)~T(~~)()l(tyoCt(ats+6t')> T,1-41--'t.'29)-!Tj~)Lr(rrg).in(co~geo.y) srand-coal'.-.inn+ "itt")j.(33!2gI(2y~)syj)Similarly tan-t-tan-ttgl)).~6,~7ga)("ittaq sire)s.(tq)at1-2XsHenceincompleteanalogywithcase(1)thefriction-sHence,withanappliedtorquer,(l)~Tsino}i,thed"scribing functionisgivenbytheeq)ression I".~~eP)f(>)Z~(').;where'1"fP)~-(Ls-(a-P)-sina(cosa+cag3)-cog(sina+sinP) J'+$(sina+sinP)'P} l'IPP.~I'~IP,IIs'~~t(C~.t:e'.p"'I't<<~It.}<<},'III~}PI,' W',.(,%r12i4//*'.I:in.7.The6hen>>.C.CI.ousI/I-sCase(>).-WithilcailrAinaw,ora~=sin-'P,/ s'tl.()nFig.10,shaileilareaNn.1rail,(sinI-.inn)((ttrt1~T<Icosai-(x-ai)sinai+ciwrs+a. sinai].sh:wlcdareaXio.2+e~s~I~(s>nial>>lai'talt'lwg~MQPgi~Ci'QIf>siI~TheClocuswillbedclinelasapolarplotofthcquantity(-I//Ia). I'nranygivensystemT,iscon-stantandlloisafunctionniT(because T,=T,/i). I'oralixedvalueofTB'aisacomplexquantitywhichmayberepresented byavectorini.heromplexplane.Thecurveof(-I/IIa),theClocus,formsthc"critical locus"forsystemstability considerations, witl>the"critical point"(-1,0)asaspecialraseforlinearsystems.TheClocusisplotteilinI'iII.7.=lfcn~d-(F+tt)slilai-cosai+fK-ai)<inniI.I~eel~egr.i~@IV.SLIDINGANDSTATICFRICTIONIN~~SERVOSYSTEMSA.ViveFormResulting fromaSinusoidal InputTorquetoaSystemwithSlidingandStaticFrier!onIfbothsliilinganilstaticfrictionarccnnsi<Icrc<I. lliefrictionphenomenon canhcreI)rcse>>tccsatisfactory iiirmostpurpnsetoassumeinsta.ntaneous transitinn fromthestatictotheslidingfrictionvaluealthnughthisprocedure docsimplvailc"rccniiilcalizatin>>. Waveformsofr,(t)corrcspnniling toanalipli<<il torquer,(t)~T,sinai areeasily'skctchcil byapro-cedureidentical withthatusei}inScc.III(I'igs.0and10).Asbefore,therearetwomnilcsofoscillation, withandwithoutdeadzones.Thelatterisin'istinguisl> ~ablefromthecorresp.ndingcasediscussnI inScc.[IIbecausethesystemiscontinually inmi~ti<in.Thusiuilytheformerrrquiresde'!..dtlisucsinn.~hfathcmatfcal Rcprcscntation ofihcSkadyS(atc IYaccFormsh>>Case(I).-~So"cadzone,h,<Xora~~j8.FromSec.III,Eqs.(10)anil(11),nncimmisliitcly 'obtainstheequations forr,(l),~~r,(t)~T,(sire+A) for-ai<c.t)r,(t)~T(s~t-X)forP<(ut(x-ai, (37)whereX~TJ7',.ai~sin-9,and4~cns'(nA/2),Pin,L.'itiiling anilatn(h:!iictinncharacienriir,. V.'ithpureinertiaInadanilunilcrsteiily-stat< cnnrii~tionthcshailcilareasarecqu:il.Equating(38)ainii.-'.anilsimplifying,, u-en<=(I-0 T,/T,V]<-L=-sin'(XT/T,)iit.(40>Equation(l0)9cQncsPintermsofknownpar.".mc!".rs. ItiscleartiiatthesystemwillnotmoveatulliiX>T,/Tforth.nT,>T,.B..Calculation oftheDescribing FunctionApproximate expressions foreffective torqueareob-tainedbyreasoning sim.wrtothatinSec.III.r,(t)~aisin"t+bicomet,('3';whereaianiloiarcgivenIiyLqs.(24)'aniI (2>>,respectively. Case(1),-Xo(leadzone.X<Aag<p. Sincetheequations f<irr,(l)areiilentica! wit!i:."ai.~ <<'ng~s,Scq4~. 'lRII At/\I\ivN./IF<c.9.Steady-state waveformswithoutileadcones.T,/T,f(A,)I2.46+(T,/T,)s<I(41>incase(1)ofSec..zil, thedescribing func<.i<in .Yn(A)~f(X)Zb(A)isgivenbyEe;.(32'an<i j<X)an<Ib4)havethefollowing limiti;;g values:F<c.II.S<<<<icfric<innI<xi..'il<<us.('<<.(2'KVith<lea<l!ones. A)~,<ze)d.'o<Jl~(s...',>> -5<s<nf<i<iiiz<<i<f) T~fT.'rIgv-(as-i9,'+en~<(sinus -2siniz<I-coat(2sine<+sinu) jinlikemannerb(X,)~tan '4/~)(T,/T,)(r/2)+(T./T,)s-2I (a/2)e+(T,/T,)zjI (42)bi~(T,/s)Isindf2sine<+sin<3) -;sine:(2.sinai-sma:) j.I44)Hencethe<lcscribing functionforthestaticfrictirin elementiswhere8o(X)-fP,)ZS(X),1f(>)--{b-(ez-P)-co~s(2 sinai-sinaz) -co4(2vina<+sing)p- +!:<e".(2'inu<+sinp)+ vin<z-..'ine<-vin<z )+~}I(2r'<<a<+sin/i, suiz:(2vi<<<z<-s<n<zzjo(A,)~tan i>-(as-0)-coszz(2 sin<z<-sin<ze)-cosp(2 si<<a<~sin<j) I<45IC.StaticFriction-Loci andSLocusThestaticfrictionlociarcpolarplots<ifthequan(ity(-I/Ho)forvariousrati<isofstaticfrictiontosiidingfriction. TheSlocusisthelocusofthet.'rminioflliestaticfrictionloci.Thestaticfrictionlocian<ithe5locu"areplottedinFig.11.fiof)F<c.10.Steady<ate wavefnrmswith<trailzones.V.PLOT.4YDIÃVBRPRBTATIOK OFTEfEr.hMPLITUDBhkfDFllZQUEIICY LOCLZXAMPUIZ()ncc<liefriction-<le. bribingfunctionhashnncal<a.-latel,th<i<lcsircdstability i<lfofnlation canbeobtaine<l easil;bythemethodoutlinedincm.II.TheliroceJurewillbeesplaine<l witlitheaidolaspecificexamplewhiciihasb.cn's<icliosc<itliatacommontyzofeorr~ti"networkwillpro<luceinstability whereasanother.typenfequalizer, apparently equivalent onalinearbasis,willleadtoastablepcrformanc .(onsiderthepositioning loopshoivninFig.12.Iiitheabsenceof'riction thelo<ipgainfunction3(s)'a>>lhcformh<if.(s)g,(s).(47)s(1+Ts)AblockdiagramforthisloopisshowninFig.13.Tli<.'.II<iicilc!inc<I as<hef<rga<ive nftheIonf<gsf<<. ~,C'jAk'n%f 'rI12i6s~'10t)Af'1)P.M.BC'HULTffE1SSsetofunits,K'7~hy~O1~R~lbI0$31~Kia')002Z,-SO,r-O.1.(.,n;Equation(47)nowbecomesp>frictfoqdescribing functionrelatesappliedtorquetn2effective torque,neitherofwhichappe,".rs asanexplicity~antityinFig.13.Thisrliagramtherefore doesnotlendtselfreadilytotheanalysisaffriction. However,itiseasytoconstruct theequivalent blockdiagramofFig.14byrearranging thcbasicequations iiescribing motorperformance. Torquenowappearse~licitly, anditisasimplemattertowritetheloopgainequationintermsofthefriction-describing functionandthesystemparameters definedinFig.12.Theequation59)e,fs).s(1+0.1s)(c0)Inthcabsencenfanequalizer fl.(s)theloopwnuldber3os.toinstability. LetSE,(s)heatwnstagelagnetworknrintegralequalizer i('1+0.3s fI.(s)~(;"li'1-'..sWi>aaitfrictionthusystem2"2>>i!<.'xlno:t i>>tusema-inoi26'an'firly~r'--a<<)c~i tr.2,.cremns...'heNyquistdiagramnfFig.I-<nnfirmsthatdedur.'.ir <2.Note,however,thatthcsliilingfriction(C)locusinl.cr.sectstheNyquistplotattwnpnirts.Thesystemisevidently stablefnrexcce(iingly small(listurnancw; iibecomesunstableassoonasasignificant inputsignalisappliedandthensustainsnscillations atananplitur'.e 222<222~sio24)y40222L<<<2<r,2<<'y<<yap,.~="'('~ir 4py~~(Oi4<4<040-,--1TFm.12.Simplepoaitionin<f system.T<<JR/K.Ks<<motortimeconstant; 8,(s)<<equalizer tranderfunctio(L; .Vr<<motortorquepcrunitarmaturecurrent;K,<<motorcounterernfperunitspeed;J<<motor<edloadinertia;Ea<<<tainofamphfierandselsyn<<E<ER<<armature looprcsisu<nce. isr<br<<~I.aiey'sy~('e~rb2'<a41hastheformKrKpE'sA(s)-ZoP,) -~-Z.(s).Js'R(48)otethatviscousdampingiiuetocountercmfisrepresented bytheadditional feedbackpathratherthantheconventional velocityAcpendent loadontheoutputmember.Thisstepisnece~rybeca'usethfrictinn-describing functionwasderivedforthecasenfapur-inertiaload.Theprocedure isobviously basednntheassumption thatasinusoidapplieiitnthenonlinear Fin.'l4.Filubalcntblack&gnm.andfrequui);1 deiermineii hythcnterscction pointclosertothenrigin.Anca:perime:ital cb".ekbyanal~;ycomputerresultedinoscillation'at 1.orad/secascnin-paredtoatheoretical valuenfabout2rad/sec.Ifamino.loopisusedinporcnftheseriesequalizer (F:g,16),thcresultisquitedilIcrent. Dyaprocessen-tirelyequivalent tothatusedinrearran<p<nlr thc~iM'iagramofFig.13theloopgainfunctinnmaybewritteninthcequivalent formZrK,-,'4(sj E.s.<(stlie(L)-+JsRPUsingthecquulizer transferfunction'" (5s)'(1-t-0. 1s)Els(s)~(53)10(1+0.Ss)-'a(1+0,0(bls) ~AmareeLeberereeqaaltser reletprebebtrbesemiiapmerirr.Thisprin)itive formwaschosenbe".auacitillustrates clearly!he difliculties encouniered becauseoffrictioneffects.'4Ef>f<)hasH.nchosensoastoyieldasystemwithtransfr<fran:<n;ut'!<L<Lu!put..scloseaspractical to(hrcriese;~"'Ucltructurc. i'Vithout thelastdcnominaia; tenn(requir~l itprcalizal>ility) theubowouldbeal<LLostidentical inthealtsenceoffricii<m. Asitis,thestepfore(i(rL 0:spanses at'evirtually in<listinguishahle. 2e0<istttesp2<42<<2)Fin.13.Convn<innal blrckdiagram.deviceyieldsanoutputsignalofwhichonlythe.'unda-mentalissignificant intransmission aroundcadiloop,sothatonlysinusoids ofthemmefrequency needbeconsidered. This'ssumption becomesprogressively poorerasdamping,andhencetheinteriorloopgain,increases. However,itwillbeseenthatthemc'hodstilleadstoacceptable firstal)proximatinns inrascsofnsiderable practical interest. ConsiderthesystemofFig.12withthefollowing arbi-crarynumerical parameters, allgiveninn,consistent ~%&-'e2~',toepe'h~'mes-m,wgsmm'2'1h:l:,<<C~,shb+WJe,;X."h.~:".e,(i2~~a2e5e~h2ra 'fA'IaQg14'I'l ~~STATICANDSLIDINGFRICTlONlNFEEDOACKSYSTE.'S'analthesamenumerical valuesasinr>epreviouscaseConeobtainsthcNyquistdiagramshownalongwiththeseriesequalizer caseinFig.'l5.Theplotdoesnot'tersecttheClocussothatthesystemremainsstab!cintheptaenceoffriction. Measuredresultsfromananalogcomputerbearoutthisconclusion. Theequahzerusedintheaboveexampleintroduced '".attenuation withthethirdpovreroffrequency oilera10:ifrequency range,sothattheresultant frictionless systemisconditionally stable.Itmaytherefore notapr.~surprising thatoscillations shoulddevelopwhenan~earelementisintroduced intotheloop.5imihrresultscan,however,beobtainedwithasing!L-stage hgnetworkandaresultant loopofabsolutestability. Considerthcseriescqua!rzer thestatic-to-sliding frictionrat!)>isal;oittequallyclosesothatthemethotimaybesaidtoyieldaream)ruble firstapproximation. VLCQHCi.USiOS85 Thetlescribing functiontechnique hasbeenextendedtocoverproblemsofstaticandslidingfrictioninfeed-backsystems.Underocr(amassumptions thestability problemcanbehanrlledadequately, andthefrequency 8eutrrtr.~w,h)i.B(.l~(1+0.25s)/1! ~:N:j.(541ThegainfactorEsischosenas100,allotherpammeters remainunchanged fromthepreviousexample.Figure17lt)o.16.Gloclctlinxratn suih...!nrtrlt).(tfpnrnlle) ~)t)n!i.".'Locus2.0ro)ISeerofanysustained oscillations canbupredicted (oafitslapproximation. Inparticular ithasbeensnown<hatthcuwofintegralcquaiir~tion inesericsiviththeloopmayeasilyleadtoinstability whenfrictionphcnomcna arehnp-2-nst.E~~)itiallyequivalent minorloopequal-izersmayyieldanentirelysatisfactory system.ttoJf'Oto~C~see)ca411>4\~w'i,~/q2i+Ii~Ctlttocteo ScottCLocus'H(si<<)hsttkstquosttrH(slwithrtoroae<equoaset-.Fto.IS.Roughsketchofamplitude andfrequency loci.Intersec-tionatPiaactuallyatafargreaterdistancefromtheorigin.showsthc'Nyquist plotaswellasthecurveforacom-spondingminorloopstructure. Thelatteris'clearlystable.TheNyquistplotforthcseriesequalizer case~-'showsnointersection withtheClocusandmeasure-mcntsinthepresenceofslidingfrict'"naloneindicate~.,stability. However,theVayquistdiagramdoescromthe"';"Slocustwice,i-.dicating thatosci!Iationa rsrayoccur'.',;.when"taticas.wellasslidingfrictioniscot;s(dered. ':"Sincetkc'Slocustracestheterminiofthedescribing functions forvariousstatic-to-sliding-friction r*tios,"'itisevidentthatstability dependscritically onthat~-.ratio:onlyforvaluesbetweenthosecorresponding to'hetwointersection pointscanoscilla:!ons exist.Itisalsoevidentthatthefrequet:cy ofoscillations shouldrisefromatheoretical minimumofC.7rad/smtcamaximumof2,>rad/sec. Thecorrespon(ling rangefron.computermeasurement is0.8rad/secto2.0rad/scc.Theexperimenta corrchtion atintermc(liatc vahresnfwo't)())lltsootiOSO ~'coitOiiOC~tv+~VILACK'fOWLKDGMEif 7'heauthorswishtoacl(nowledge thea.'dofvariousmembersoftheFlcctrical Engineering Department ofYaleUniversity, espcc!ally thar.ofProfessor F.I3.Tuteurof[hcsrvnrnrthanismslaboratory. Tl'ccon-tcn(snithispaperatc()eninessencefroma(lisser(a-tionbyJ)iliesToupresented tnthehculrvoftheYaleSchoolofEngincerinc; in;rrti~ifullilmcnt oit(icr"-qu)rc))rents iorthet!c"rrcniDnctornfEi)r',irieeringr. 1)~(,.r%r'jl~Cs~ocusi)CurrtrI)h,tri~Stqjo))ter HCurutcnhyctelt~IequohttrF)Q.l7Al,plitude tsndlrtqt)rncy 4iior-"t'mr'n!criral sytrein,'(>") APPENDIXCJUMPPHENOMENA (MATHCADSOLUTION) p CALCULATION OFHARDEiVING SPRINGRESPONSECURVERef.Asymptotic MethodsintheTheoryofNonLinearOscillations byN.NBogoliubov andY.A.Mitropolsky, (U.of.pa. Math/Physics) Hindustan Publishing, 1961.Theory....For assumedamplitudes, findfrequencies a:=1.5E1'+.375'aNN=1.6621N-"2.0092 TableC-1NONLINEAR RESONANCE CURVE1.05.4.3.7.8.75.704015078 1.21.0291.52.32.52.85.01.6941.7321.7111.7851.7151.9012.0971.6781.6651.6691.6771.7031.7042.0092.593.0483.3953.97710.375~9541.1011.033IMAGINARY IMAGINARY IMAGINARY IMAGINARY IMAGINARY .551,305.0021.251.01.6622.4072.9183,2923.90210.375 4S'.li FIGUREC-j.RESONANCE CURVESHOWINGJUMPPHENOMENA l' ~>030gjpq5 DONALDC.COOKNUCLEARPLANT1990ANNUALOPERATING REPORTFebruary28,1991COMPILEDBYu</."H.B.ugger.F.KurganREVIEWEDBY:APPROVEDBY:B.A.SvenssonLicensing Activities Coordinator ~4/M.P.Al'erichVicePresident-Nuclear Operations TABLEOFCONTENTSSFCTIONSECTION-TITLE PAGENUMBER1.0Introduction 1.11.2,PlantDescription ReportPreparation ',0Personnel Radiation ExposureSummary".0SteamGenerator In-Service Inspection 3.13.2Unit1Inspection SummaryLni"2Inspection Summary554.0ChangestoProcedures 4.14.24.34.4Maintenance Procedures Operating Procedures Chemistry Procedures Environmental Monitoring Procedures 78995.0Challenges toPressurizer PowerOperatedReliefValvesandSafetyVa;es6.0.0ReactorCoolantSpecificAc"ivityIrradiated FuelExaminations 1213'7.1VisualExaminations Ultrasonic Examinations 13138.0ChangestoFacility148.28.38.48.58.68.78.88.98.108.118.12ColdtoHotLaboratory Conversion NuclearInstrumentation SystemUpgradeContainment Atmosphere Temperature Detectors PlantRadioCommunications UpgradeFuelTransferSystemUpgradeAdditional Auxiliary BuildingRadiation MonitorsMonitoring ReducedRCSInventory Conditions ControlRoomVentilation Modification Containment AirlockDoorSealModifications ControlAirDryerFilterModification ChlorineInjection MethodModification Temporary Jumpering ofBatteryCells14141515161617171818'919AppendixA:SteamGenerator Inspection Details

    1.0INTRODUCTION

    1.1PLANTDESCRIPTION TheDonaldC."CookNuclearPlantisownedbyIndianaMichiganPowercompanyandislocatedfivemilesnorthofBridgman, Michigan. ThePlantconsistsoftwonuclearpowerunits,eachemploying aWestinghouse pressurized waterreactornuclearsteamsupplysystem.Eachreactorunitemploysanicecondenser reactorcontainment system.TheAmericanElectricPowerServiceCorporation wasthearchitect-engineer andconstructor. Unit1and2reactordesignpoweroutput(andlicensedrating)are3250MWtand3411MWt,respectively. Unit1approximate grossandnetelectrical outputsare1056MWeand1020MWe,respectively. Unit2approximate grossandnetelectrical outputsare1100MWeand1060MWe,respectively. Themaincondenser coolingmethodisopencycleusingLakeMichiganwaterasthecoolingsourceforeachunit.l.2REPORTPREPARATION ThisreportwascompiledbyH.B.Brugger/J. F.Kurganwiththefollowing individuals contributing information asfollows:D.C.LoopeC.A.FreerB.A.SvenssonB.A.SvenssonPersonnel ExposureSummarySteamGenerator ISISummaryChangestoProcedures Challenges toPressurizer PORVsandSafetyValvesB.A.SvenssonD.H.MalinJ.B.KingseedB.A.SvenssonResultsofIrradiated ChangestoFacility-FuelInspections RFCs,MMs,PMsChangestoFacility-Temporary Modifications toUnit2ReactorCoolantSpecificActivity

    2.0 PERSONNEL

    RADIATION EXPOSURESUMMARYTable2,below,providesasummaryoftheradiation dosetostation,utility,contractor (andother)personnel receiving exposures greaterthan100mRemin1990.Allofthedosesshowninthetableweremeasuredbythermoluminescent dosimetry (TLD)~Thegrandtotalperson-Rem doseshowninTable2is484.537Rem,andwasdetermined inaccordance withNRCRegulatory Guide1.16.(ThetotalrecorddoseforCookNuclearPlantin1990was579.589Rem.)

    TABLE2PERSONNEL RADIATION EXPOSURESUMMARYREG.GUIDEl.16Rx0erationsandSurveillance ofPersonnel Stat.Util.>100mRTotalPerson-Rem Cont.StationUtilitContractMaintenance Personnel Operations Personnel llealthPhysicsPersonnel Supervisory Personnel Engineering Personnel 9167.122,01070561493011.16913.6005.1020.1672.0600.0980.4010.0000.0000.0009.8333.46036.0470.0000.086RoutineMaintenance Maintenance Personnel Operations Personnel llealthPhysicsPersonnel Supervisory Personnel Engineering Personnel In-Service Insection831090512.00036220340224.6002.3001.4050.0000.9360.3460.5960.0000.0000.000142.9767.8208.4270.0000.300Maintenance Personnel Operations Personnel llealthPhysicsPersonnel Supervisory Personnel Engineering Personnel SecialMaintenance 931000100-014612001~1640.5440.2260.0000.0000.0000.1170.0000.0000.00051.4255.440,2.2530.0000.000Mainenance Personnel Operations Personnel llealthPhysicsPersonnel Supervisory Personnel Engineering Personnel 82204000030712419l.4100.7280.2420.0000.6040.0000.0000.0000.0000.63590.0012.3130.4530.0971.545

    TABLE2'd)gofPersonnel >100mRStat.Util.Cont.TotalPerson-Rem StationUtilitContractHasteProcessin Maintenance Personnel Operations Personnel flealthPhysicsPersonnel Supervisory Personnel Engineering Personnel Refuelin'Maintenance Personnel Operations Personnel HealthPhysicsPersonnel Supervisory Personnel Engineering Personnel 01,4017721173101600505723020.0000.1360.4270.0000.1940.8522.6870.2120.0980.2230.0000.0000.0000.0000.0000.0000.0000.0000.0000.00020.6353.0593.8560.0000.0009.66814.8815.2690.0000.261TOTALSMaintenance Personnel Operations Personnel HealthPhysicsPersonnel Supervisory Personnel Engineering Personnel 938125177001051261329.28320.0777.6930.2654.0260.4431.1150.000324.61936.98157.1060.6342.1990.000'.097GRANDTOTALS21894561.3432.192421.001 '

    3.0 STEANGENERATOR

    IN-SERVICE INSPECTION 3.1UNIT1INSPECTION SUMHARYOnehundredpercentofthetubesinallfoursteamgenerators ofUnit1werebobbincoileddycurrentinspected. Alltubesweretestedutilizing a0.720inchdiameterprobewiththeexceptions ofrows1through4U-bendsthatwouldnotallowa0.720inchprobetopass.A0.700or0.680inchprobewasusedfortheU-bendinspections only.hThebobbincoiltestfrequencies usedwereasfollows:400kHzastheprimetestfrequency. 200kHzandthe100kHzassupplemental frequencies. 10kHzasthelocatorfrequency Atotalof70tubeswereremovedfromservicefollowing thisinspection duetotheeddycurrentresults.AppendixAprovidesinspection detailsconcerning theindications foundineachtubeandwhetherornotthetubewasplugged.3.2UNIT2INSPECTION SUtf~BRYSixandone-halEpercentofthetubesinUnit2steamgenerators wereinspected usingthesamemethodandtestfrequencies described forUnit1inspections. Alltestswereconducted witha0.720inchdiameterprobewiththeexception ofthreetubes'insteamgenerator 23,locatedinRows1and'2.Thesethreetubesweretestedwitha0.700inchprobe.Nodegradation orpluggable indications werefound. TABLE1STEAMGENERATOR INSPECTIONS UNIT1UNIT2SteamGenerator 11'SteamGenerator 21Alltubestestedfromtheinlet(HL)624fulllength(TE-CLTOTE-HL)2,584U-bend(7TSP-CLtoTE-HL)NoneSteamGenerator 12SteamGenerator 22Alltubestestedfromtheinlet(HL)615fulllength(TE-CLtoTE-HL)2,625U-bend(7TSP-CLtoTE-HL)Alltubestestedfromtheinlet(HL)67fulllength(TE-CLtoTE-HL)169U-bend(7TSP-CLtoTE-HL)SteamGenerator 13SteamGenerator 23Alltubestestedfromtheinlet(HL)634fulllength(TE-CLtoTE-HL)2,612U-bend(7TSP-CLtoTE-HL)Alltubestestedfromtheinlet'HL) 68fulllength(TE-CltoTE-HL)167U-bend(7TSP-CLtoTE-HL)SteamGenerator 14SteamGenerator 24Alltubestestedfromtheinlet(HL)619fulllength(TE-CLtoTE-HL)2,602U-bend(7TSP-CLtoTE-HL)None

    4.0 CHANGESTOPROCEDURES

    Thissectioncontainsabriefdescription oftheprocedure changesimplemented undertheprovisions of10CFR50.59andtheassociated safetyevaluations. 4.1MAINTENANCE PROCEDURES '.1.1Procedure NO12MHP502.010001Revision2Description ofChange:Duringpreparations forthecompletereplacement oftheicecondenser containment dividerbarrierseal,itwasdiscovered thattheactualsealinstallation didnotagreewiththedescription inthesubjectmaintenance procedure entitled"RemovalandReplacement ofSectionsoftheIceCondenser DividerBarrierSeal".Furtherengineering reviewdetermined thatthedividerbarriersealwasproperlyinstalled pertheplantdesigndrawings. Itwasalsodiscovered thatthedescription ofthesealinstallation detailsintheUFSARwasthesameasthemaintenance procedure butdifferent thantheactualdesign.Specifically, page5.2.-80oftheUFSARstatesthatthespacingbetweenboltsholdingthesealisthreeinches,andthatthesealislaidwithone-halfinchextralengthbetweenboltholes.Plantdesigndrawingsshowthestudsbeingthreetofiveinchesapartinvariouslocations, andthesealhavingbetweenzeroandone-quarter inchextralengthbetweenboltholes.Theprocedure wasrevisedtorequireinstallationof thesealasshownonthedesigndrawings. SafetyEvaluation Summary:Thereviewofthisissueindicated thatduringalossofcoolantaccident, steamfromthebreakisdirectedthroughtheicecondenser. andcondensed, thuspreventing containment pressurefromexceeding designvalues.Toensurethemaximumamountofsteamiscondensed, theflowareafromlowertouppercontainment whichbypassestheicecondenser mustbelimited.Theicecondenser issupported from'hecranewallinsidecontainment. Duringaseismicevent,therelativemovementbetweenthecranewallandthecontainment wallis1.3inches.Toaccommodate thismovement, agapwasleftbetweenthecranewallandthecontainment wall.Thisgapissealedwitha,barrier designedtowithstand thedifferential pressurebetweenloweranduppercompartments duringpostulated lossofcoolantaccidents andseismicevents. Thestatements onpage5.2-80oftheUFSARregarding holespacingandlengthimplythattheextraone-halfinchlengthisnecessary topreventfailureofthesealduetoelongation duringaseismicevent.Areviewbyourdesignengineers determined thatthereis-sufficient resiliency inthematerialtopreventfailureduringthemaximumelongation providedthesealisinstalled perthedesigndrawings. Thesafetyevaluation concluded thatchangingthedividerbarriersealinstallation procedure torequireinstallation ofthesealperthedesigndrawingsdoesnotinvolveanunreviewed safetyquestionasdefinedin10CFR50.59. TheUFSARwillberevisedtoreflecttheactualsealinstallation inthenextannualupdate.4.1.2Procedure Numbers:12NHP5021,001.016 12HHP5021.005.003 Description. ofChange:Thesemaintenance procedures wereimplemented topermittheuseof"Chesterton" valvepackingonsafetyrelatedvalvesinsystemsdescribed intheUFSAR.TheChesterton valvepackingdiffersfromthevalvepackingconfigurations described intheUFSARforcertainsafetyrelatedvalves.SafetyEvaluation Summary:Atechnical evaluation determined thatthepackingsystemdescribed intheUFSARhasbeenrenderedobsoletebyadvancesintechnology. TheChesterton systemofpackingcurren"ly beinginstalled inthemajorityofthesafetyrelatedvalvesisadirectdevelopment ofanEPRIstudyandistechnically superiortothatdescribed intheUFSAR.Thesafetyevaluation determined thatthechangesdonotinvolveandunreviewed safetyquestionasdefinedin10CFR50.59. ChangestotheUFSARwillbeincorporated inthenextannualupdate.4.2OPERATING PROCEDURES 4.2.1Procedure Numbers:'-and2-OHP4021.008.002 1-and2-OHP4020.STP.053A 1-and2-OHP4030.STP.053B 1-and2-OHP4030.STPi055 Description ofChanges:Theaboveprocedures werechangedtorequiretheRHRpumpdischarge cross-tie valvestobeclosedduringnormalplantoperations. Thechangeswereimplemented ascorrective actioninresponsetoNRCBulletin88-04,"Potential SafetyRelatedPumpLoss".ClosingtheRHRpumpdischarge cross-tie valvesmakestheminiflowcircuitsforeachRHRpumpindependent, therebyremovingthepotential fordeadheadingtheweakerpump.When'theRHRcross-tie valvesareclosedthesafetyinjection pumpdischarge cross-tie valvesmustremainopen.SafetyEvaluation Summary:Thechangeswereimplemented afterreceiving NRCapprovalviaa"ChangetotheLicensing BasisforSIandRHRCross-ties (TACSNos.64962and64963)",datedJanuary30,1989.4.3CHEMISTRY PROCEDURES 4.3.1Procedure Number:1'-and2-THP6020.LAB.200 Description ofChange:Theaboveprocedures wereimplemented forthepurposeofchlorinating theUnit1andUnit2mainturbinecondenser circulating watersystems.TheUFSAR,Section10.6.2,describes chlorination ofcirculating waterusingchlorinegas.Theseprocedures willaccomplish theclorination usingasodiumhypochlorite solutionratherthanchlorinegas.SafetyEvaluation Summary:Theuseofsodiumhypochlorite resultsinthesamechemicalcompoundinthewateraswouldbethecaseifchlorinegaswereused.Theuseofsodiumhypochlorite ispreferred becauseitisinaliquidformatroomtemperature and,therefore, doesnotpresentatoxicgasconcern.Thesafetyevaluation concluded thatthechangedoesnotinvolveanunreviewed safetyquestionasdefinedin10CFR50.59. ChangestotheUFSARwillbeincorporated inthenextannualupdate.,4.4IIRONMENTAL MO0INGPOCDURESProcedure Number:12THP6010ENV.051,Revision3

    Description ofChange:Revision3tothe,aboveprocedure includedchangestothesamplelocationmaptoreflecttheupdatedsamplestationlocations forallsamplemedia.SafetyEvaluation Summary:Thechangeshavenoeffectontheenvironmental samplingrequirements ofTechnical Specification 3.12.Thesafetyevaluation concluded thatthechangedoesnotrepresent anunreviewed safetyquestion. TheUFSARwillberevisedtoreflecttheadditional samplestationlocationinthenext'annualupdate.10

    5.0 CHALLENGES

    TOPRESSURIZER POWEROPERATEDRELIEFVALVESANDSAFETYVALVESTherewerenochallenges on,eitherUnit1orUnit2tothepressurizer poweroperatedreliefvalves(PORV's)orthepressurizer safetyvalvesasaresultofthevalvesbeingcalledupontomitigateanactualoverpressure condition. OneeventoccurredonUnit2,onOctober6,1990,theinadvertent openingofpressurizer PORV,2-NRV-153. Theeventoccurredwhileperforming asurveillance testontheresidualheatremovalpumpssuctionvalvesisolation actuation bistables. Whentheeventoccurred, thereactorcoolantsystem(RCS)wasinMode4.RCSaveragetemperature wasapproximately 250FandtheRCSpressurewasapproximately 350psig.Thecoldoverpressure protection systemwasnot.requiredtobeoperablesincetheRCStemperature wasgreaterthan152~F.However,thecoldoverpressure protection blockswitchwasinthe"unblocked" positiontoprovideaddedprotection fortheRHRsystem.Duringthetest,whenthebistablewasmadeuptoverifytheautomatic isolation oftheRHRsystemfromtheRCS,asignalwasalsodirectedtotheactuation bistableforPORV,2-NRV-153, causingittoopen.Topreventrecurrence, thesurveillance testprocedure hasbeenrevised,to requirethe"coldoverpressure block"switchtobeplacedinthepositiontoblocktheRCSpressuresignalpriortoperforming thistest. 6.0REACTORCOOLANTSPECIFICACTIVITYTherewerenoinstances oneitherUnit1orUnit2inwhichthereactorcoolantI-131specificactivityexceededthelimitsofTechnical Specification 3.4.8.12

    7.0 IRRADIATED

    FUELEXAMINATIONS During1990twoseparateexaminations wereperformed ontheirradiated fueldischarge fromUnit2,Cycle7.Theseexaminations wereconducted inparallelwith,orshortlyafter,thecorewasunloaded. Theintentwastodetermine fuelpinfailuresandgrossstructural defectsinthefuelassemblies. Also,during1990anexamination wasperformed ontheirradiated fueldischarged fromUnit1Cyclell.Thisexamination wasconducted inthesamemannerandforthesamepurposeastheexaminations ofUnit2discharged fuel.7.1VISUALEXAMINATIONS Thefirstexamination ofUnit2fuel,(andtheonly"examination ofUnit1fuel)wasbyroutinebinocular inspections ofthefuelassemblies perprocedure numbers:>*12THP6040PER.353and12SHP4050QC.002.Aseachassemblyisdownloaded tothespentfuelpool,itisvisuallyexaminedonallfoursides.Theexaminerislookingspecifically fortomormissinggridstraps, missingordamagedfuelpins,excessive cladhydriding, orrodbowtogapclosure.Thisinspection isprimarily intendedtodetectfueldamagecausedbymechanical interaction betweenassembl'ies orbafflejetting,andisdoneduringeachrefueling. Therewasnoindication ofanyfueldamage.7.2ULTRASONIC EXAMINATIONS BecausetheUnit2steamgenerators werereplaced, andbecauseallpreviousplantsthatreplacedsteamgenerators experienced subsequent cyclefuelfailures, acontractwaslettoAdvancedNuclearFuels(ANF)toprovideultrasonic (UT)examination ofthe116irradiated assemblies outof193assemblies makingupthe'nit2,Cycle8core.Theultrasonic systemworksbyaprobetransceiver sendingahighfrequency soundwaveintoafuelpinandmeasuring thestrengthofthereturning signal,or"',ringback".'fuelpincanbedetermined tohavewaterini.tbymonitoring therelativestrengthofthisringback.Inthisway,notonlycananassemblybedetermined tohaveleakingpins,butthenumbersandlocations ofthebadpinscanbeidentified. Noneofthe116fuelassemblies werefoundtocontainleakingpins.Inaddition, a117thUnit2assembly, T24,wasalsoexamined. ItwasknowntohaveleakingfuelpinsafterCycle6butwasreusedinCycle7.Theexamination providedacheckofthetestingmethodology. FuelassemblyT24wasagaindetermined tobeleaking. i'

    8.0 CHANGESTOFACILITYBriefdescriptions

    andsummarysafetyevalu'ations fordesignchangesmadetothefacilityasdescribed intheUFSARarepresented inthissection.Thesechanges"erecompleted pursuanttotheprovisions of10CFR50.598.1COLDTOHOTLABORATORY CONVERSION Description ofChange:RFC01-1959involvedtheconversi"n ofthecoldlaboratory toprovideadditional hotlaboratory space.Thechangedidnotaffectsystemsrequiredforsafeplantshutdownnordiditaffectsystemswhosefailurecouldimpairsafetyrelatedsystems.Thechangeincreased theamountofspaceavailable forperforming analysesofradioactive materials andwillreducecongestion inthehotlab.Safet'valuation Summary:ThechangesmadeinthisRFCdidnotaffectsafetyrelatedsystemsorcomponents; however,changesweremadetosystemswhichhandleradioactive materials. Thischangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50;59.8.2NUCLEARINSTRUMENTATION SYSTEMUPGRADEDescription ofChange:Thepurposeofthissubtask(RFC12-2900,SubtaskB.01,Unit2only)wastoupgradethenuclearinstrumentation system(NIS)tomeettheguidance.provided byR.G~l.'97,Revision3.Theneutronfluxinstrumentation wasinstalled sothattheperformance ofthereactorprotection system(RPS)isnotdegraded. Thescopeofworkforthissubtaskincludedproviding twoGamma-Metrics environmentally andseismically qualified detectors insidecontainment, installing apre-amplifier justoutsidecontainment, modifying theNIScabinets, andrunningcableforsignalsandpowersupplies. SafetyEvaluation SummaryThissubtaskhasbeenclassified assafetyrelated.Theinstrumentation installed bythissubtaskwillnotprovideanyreactortripsignalstothereactorprotection system(RPS).However,theneutronfluxindicators willbemountedinChannelsIandIIIofthesafetyrelatedNIScabinet.Furthermore, R.G.1.97,Revision3,classifies neutronfluxasacategory14

    1v'ariable whosepurposeistoverifyaccidentmiti.gation. Category1classification isintendedforkeyvariables important tosafety.Conse-quently,theinstallation requirements forCategory1variables includefullequipment qualification, classlEpowersupplies, redundancy, andaqualityassurance program.Thischangewasreviewedanditwasconcluded thatitdidnotinvolveachangeintheT/S,didnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," anddidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.3CONTAINMENT ATMOSPHERE TEMPERATURE DETECTORS Description ofChange:ThepurposeofRFC12-1900D.22,(Unit2only)wastoupgradesixoftheseventeen containment atmosphere temperature RTDstomeetR.G.1.97,Rev.3,requirements. Commitment forthischangewasmadeinAEP:NRC:07790, "June12,1984Confirmatory Order-FinalStatusReportonRegulatory Guide1.97Compliance," datedOctober15,1985.Specifically, weagreedtoreplacesixcontainment atmosphere temperature RTDs(ETR-121,18,20,21,and22)withenvironmentally qualified equipment havingaltemperature rangeof0to400'F.Inaddition, thisRFCexpandedtherangeofallseventeen containment atmosphere temperature RTDsbyreplacing themwithwiderrangeinstruments. SafetyEvaluation Summary:ThisRFCwasclassified assafety-interface inaccordance withR.G.1.97,Rev.3.Containment atmosphere temperature servesnofunctionassociated withreactortriporECCSactuation, andfailureoftheRTDswillnotresultinanincreaseinthe'severity ofanaccidentorpreventproperfunctioning ofsafetysystems.Thischangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," anddidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.4PLANTRADIOCOMMUNICATIONS UPGRADEDescription ofChange:RFC12-2950upgradedtheCookNuclearPlantcommunication systemradiotofacilitate requiredoperatoractionsduringnormalandemergency operations. Thenewradioincorporates twoexistingsecurityemergency andfireprotection radiofrequencies aswellastworecentlyobtainedfrequencies. 15 SafetyEvaluation Summary:Thischangeupgradedexistingequipment anditdoesnotadversely impactanysafetyrelatedequipment. Thechangeprovidesamorereliablecommunications radiosystemtoassistinnormaloperation anditprovidesamoreefficient meansofcoordinating thesafeshutdownofthereactor'. Thischangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," andthatthechangedidnotcreate,,a substantial hazardtothehealthandsafetyofthepublic.8.5FUELTRANSFERSYSTEMUPGRADEDescription ofChange:RFC12-3024replacedtheexistingairmotor-driven fueltransfersystemwithawinchcable-driven fueltransfersystem.Theprevioussystemwasanunderwater airmotor-driven conveyorcarthatranontracksextending fromtherefueling canalthroughthetransfertubeandintothetransfercanal.Criticalcomponents wereunderwater, thusmakingrepairsandmaintenance difficult. Thecable-driven systemeliminates underwater operation forcriticalcomponents makingthesystemmorereliable. SafetyEvaluation Summary:RFC12-3024didnotalterthefunctionofthefueltransfersystem.Itchangedthedrivemechanism andmovedmajorcomponents toamoreaccessible area,makingrepairsandmaintenance easierandquicker.Nosafety-related actionsareassociated withthefueltransfermechanism. Thischangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," andthatthechangedidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.6ADDITIONAL AUXILIARY BUILDINGRADIATION MONITORSDescription ofChange:RFC12-4036involvedtheinstallation ofninearearadiation monitors. Themonitors, whicharelocatedintheauxiliary

    building, measureradiation fromtherefueling waterpurification filter,northandsouthsealwaterinjection filters,sealwaterfiltersandreactorcoolantfilters.Themonitorswereinstalled tomeasuredoseratesinthefiltercubicles, therebypreventing overexposure toworkerschangingthefilters.16 SafetyEvaluation Summary:ThechangesmadeviathisRFCdonotimpactsafetyrelatedequipment.

    Thechangesweremadetoaidinminimizing theexposureofpersonnel workingintheareaswherethemonitorsareinstalled. Noaccidentanalysesareimpactedbytheadditionoftheseradiation monitors. Thischangewasreviewedand'itwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestandExperiments," andthatthechangedidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.7MONITORING REDUCEDRCSINVENTORY CONDITIONS Description ofChange:ThepurposeofRFC12-4058istocomplywithcommitments totheNRCregarding GenericLetter88-17.ThisRFCaddedanew,independent systemformonitoring halfloopandreducedinventory intheRCS,aswellas'otherindications toenhanc'etheabilityofthecontrolroomoperatortomonitorandmaintainRCSwaterlevelduringreducedinventory conditions. Twoinstrument cartsweresetupinthecontrolroomtomonitorwideandnarrowrangelevels,incoretemperatures andRHRflowsduringhalf-loop orreducedRCSinventory conditions. SafetyEvaluation Summary:ThisRFCaddedinstrumentation tomeasureRCSlevelaswellasotherparameters ofimportance duringhalf-loop. Thischangewasreviewedandit'asconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59andthatitdidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.8CONTROLROOMVENTILATION MODIFICATION Description ofChange:MinorModification 12-094adjustedthecontrolroomventilation systemsuchthatflowthroughthenormalintakeductworkfromtheoutsideatmosphere islimitedto150cfm.Theadjustment wasaccomplished bymodulating theexistingmanualbalancing damperHV-ACRDV-l. (Nohardwarechangeswererequired.) Themodification wasperformed onbothunits.Thechangewasnecessary tofulfillacommitment madetotheNRCtosatisfyconcernsregarding theanalysesfoundinChapter14.3.5ofthepresentUnit1UFSAR.Therevisedanalysesassumedthatflowthroughthenormalintakedamperwaslimitedto200cfmforcasesthatassumedfailure17

    ofthenormalintakeisolation damper(HV-ACRDA-1) to,isolate whenrequired. Theflowwaslimitedto150cfmtoprovidemargintothe200cfmanalysislimit.SafetyEvaluation Summary:Thechangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," anddidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.9CONTAINMENT AIRLOCKDOORSEALMODIFICATION Description ofChange:MM12-098involvedthereplacement ofthepackingglandfromtheinterlock andhandwheel hubsonthecontainment upperandlowerairlockdoors.AmodifiedpackingglandthatusedEPDM0-ringsealswasinstalled inlieuofgrafoilpacking.Themodification wasmadetoavoidpastdifficulties inadjusting thehandwheel 'packingglandcovertoadequately compressthepackingaroundthehandwheel shaftwhileretaining rotational freedomoftheshaft.Thecontainment airlocksareSeismicClassIstructures. Further,themodification totheairlockdoorshadthepotential toadversely increasetheconsequences ofaloss-of-coolant accident. Asaresult,thesealmodification wasconsidered asafetyrelateddesignchange.SafetyEvaluation SummaryThischangewasreviewedanditwasconcluded thatitdidnotrepresent anunreviewed safetyquestion. Thisconclusion wasbased,inpart,ontheperformance ofapost-installation testoftheairlockdoorstoverifytheirfunctionality. 8.10CONTROLAIRDRYERFILTERMODIFICATION Description ofChange:PM12-805consisted ofreplacing thecontrolairdryerafter-filters withafilterincorporating apressureguagewhichmeasuresdifferential-pressureacrossthefilter.Thechangerequiredpipingmodifications tothecontrolairsystem,a'non-safety relatedsystem,butdidnotalterthesystem'sfunctionnordidthechangeimpactanysafetyrelatedsystemorequipment. 18

    SafetyEvaluation SummaryThechangewasmadetoanon-safety relatedsystem."Thefiltersarelocatedintheturbinebuilding, and'there isnosafetyrelatedequipment inthevicinity. Thechangedidnotalterthefunctionofthesystemandtheinclusion ofthedifferential pressureguageisconsidered tobea"systemenhancement. Thischangewasreviewedanditwasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59, "Changes, TestsandExperiments," andthatthechangedidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.11CHLORINEINJECTION METHODMODIFICATION Description ofChange:Thepurposeofmodification PM12-810wastochangethemethodofinjecting chlorineintotheessential servicewatersystem.Thechangeconsisted ofmodifying non-safety-related pipingtoallowtheuseofliquidsodiumhypochlorite .ratherthanchlorinegas.SafetyEvaluation Chlorination oftheessential servicewatersystemisnotasafetyrelatedfunction, andthechangeinthechemicals usedtoperformthechlorination doesnotadversely impactthecapability oftheessential servicewatersystem.Thephysicalchangesrequiredweremadetonon-safety gradepipingwhichdoesnotinterface withanysafetyrelatedsystems.Thischangewasreviewedandit,wasconcluded thatitdidnotconstitute anunreviewed safetyquestionasdefinedin10CFR50'9,"Changes, TestsandExperiments," andthatthechangedidnotcreateasubstantial hazardtothehealthandsafetyofthepublic.8.12TEMPORARY JUMPERING OFBATTERYCELLSDescription ofChange:TheUFSARdescribes theplant250voltDCbatterysystemsastothenumberofcellsineachbattery.The"TrainAB"andTrainCD"batteries consistof116cellsconnected inseriesandthe"TrainN"batterysystem(turbinedrivenauxiliary feedpumpDCpowersupply)consistsof117cells.Temporary Modification No.164providedforjumpering threecellsinUnit2TrainNbatteryandTemporary Modification No.171providedforthejumpering oftwocellsinUnit2TrainABbattery.Ineachcasethe19 , batteries hadbeendeclaredinoperable perTechnical Specification 4.8.2.3.2.6.1 duetotheindividual cellvoltageshavingdroppedmorethan0.05voltsfromthevalueobservedduringtheoriginalacceptance test.SafetyEvaluation Summary:Atechnical evaluation andasafetyevaluation wasperformed anditwasconcluded thatjumpering ofthecellsdidnotsignificantly degradethebatteries capacitytoperformtheirintendedsafetyfunctionandthatthechangesdidnotinvolveanunreviewed safetyquestionasdefinedin10CFR50.59. 20

    APPENDIXASteamGenerator Inspection Details APPENDZXASTEAMGENERATOR NUMBER1181013153DI2SPH+0INNO337+o'SPC+0INNO347+o1SPC+0INYES315'SPC+0INNO3224TSC+14.2INNO4DITEH+19.9INYES414'DI1SPC+0INNOl2SPH+0INNO:.1615181718204DI1SPH+0INNO5324TEH+20.3INYES518'SPC+0INNO5DITEH+20.6INYES61441SPC+0INNO7DITEH+20.3INYES72941SPC+0INNO8DI1SPH+0INNO8DI1SPH+0INNO,2317834>o9DI1SPC+0INNOTEH+20.5INYES22169DITEH+20.5INYES10DITEH-+20.5INYES1910DITEH+20.2INYES2210DITEH+20.5INYES510DITEH+20.8INYES311DITEH+20.6INYESRONCOLINDICLOCATIONPLUGGED811'ITEH+20.6INYES18112111261129ll24125143114101511618162316917251732173517171831183518361836203720DITEH+20.4IN,YESDI1SPH+0INNODITEH+20.4INYESDITEH+20.7INYESDI1SPH+0INNODI3SPH+0INNODITEH+20.4INYESDITEH+20.4INYES35+o2SPH+0INNODITEH+20.9INYESDITEH+20.8INYESDI,TEH+21.0INYES57+oTEH+20~7INYES11+o2SPC+0INNODITEH+20.0INYESDITEH+20.7INYESDI1SPH+033+o2SPC+0INNOINNO28%2SPC+0INNO47%2SPC+0INYES18%1SPC+0INNO1821DITEH+21.2INYES20213721DI2SPH+0IN31%2SPC+0INNONO'ROWCOLINDICLOCATIONPLUGGED JJ STEAMGENERATOR NUMBER1138213223822384'SPC+0INNODI2SPH+0INNO2642SPC+0INNO40253842SPC+0INNO22730'7332736291030DIDI2SPH+0INNOTEH+20.3INYES96+oTEH+20~3INYESDITEH+20.4INYESDI1SPH+0INNO1230DI1SPH+0INNOROWCOLINDICLOCATIONPLUGGED3639'ITEH+20.6INYES3939DITEH+,20.3INYES3340DI1SPH+0IN4040DI2SPH+0IN44403341SPC+0INNONONO4341DITEH+20.5INYES3442DITEH+20.5INYES2243DITEH+20.5INYES3843DITEH+20.7INYES3943DITEH+20.5INYESROWCOLINDICLOCATIONPLUGGED27303131393142314331163223542354236737DITEH+20.1INYESDITEH+20.2INYESDITEH+20.2INYESDITEH+20.5INYES27~o37%2SPC+0INNO1SPC+0INNODITEH+20.7INYESDI1SPH+0INNO'ITEH+20.6INYESDITEH+20.8INYESDRITEH+2.3INYES4243DI3SPH+0INNO2244DI2SPH+0INNO1445DITEH+15.6INYES3347DI1SPH+0INNO548DI2SPH+0INNO4148254AV4+0INNO1249954'EH+14.9INYES3149DI1SPH+0INNO4649DI1SPH+0INNO3351DI1SPH+0INNO2752DI1SPH+0INNO4137DITEH+20.2INYES43'725+o2SPC+0INNO45373042SPC+0INNO138DI2SPH+0INNO4552185316542554255432%2SPC+0INNODI1SPH+0INDI.2SPH+0INNONODITSH+.8,INYESDITSH+1.8INYES STEAMGENERATOR NUMBER11ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED1055DITEH+20.9INYES1355DITEH+13.2INYES2155DI1SPH+0INNO36'6325+o366318%'063DIAV3+0INNOAV4+0INNOTEH+20.8INYES45553356DI1SPC+0INNODI1SPH+0IN-NO1564DI2SPH+0INNO265DI1SPH+0INNO1365DRITEH+2.7INYES43435656DI32~o,1SPH+0IN2SPC+0INNONO4545565626~o3743SPC+0IN2SPC+0INNONO4557158.58584595594459455934~o3SPC+0INDI2SPH+0IN3742SPC+0INNONONO254DI1SPC+0TEH+20NOIN.6INYESDI1SPH+0IN29~o2SPC+0IN33~o2SPC+0INNONONO560DI1SPH+0INNO42296061DI1SPH+0INDI1SPH+0INNONONO3962DITEH+20.3INYES6363363DI27~o23~o2141SPH+0IN2SPH+0INAV2+0INAV3+0INNONONONO3961DI2SPH+0IN1862'I3SPH+0INA-32665DI'SPH+0IN43'53541SPC+0IN2566DI1SPH+0IN2666DI1SPH+0IN2766DI1SPH+0INNONONOPNONO3367DI1SPH+0IN3668-DI2SPH+0INNONO4070DITEH+20.7INYES171DI1SPH+0IN871DI1SPH+0IN2771DI1SPH+0IN172DI1SPH+0IN172DI2SPH+0IN2573DITEH+20.7IN174DRITEH+2.3IN1174DI1SPH+0IN1474DI1SPH+0INNONONONONOYESYESNONO1974'ITEH+20.7INYES2775DITEH+20.7INYES3666DITEH+20.8INYES

    ,STEAMGENERATOR NUMBER11ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED3276DI,1SPH+0INNO87DITEH+20.6IN,YESNO307732773179580DI2SPH+0INNO16%2SPC+0INNO16%1SPC+0INDI1SPH+0INNONO36762741SPC+0IN2121987878814871987DIDI1SPH+0IN4SPH+0INNONODI1SPH+0INNODI1SPH+0INNODITEH+20.9IN'YES3030808010I28191982828283832481308119418%2SPC+0IN1SPC+0INNONO25~o1SPC+0INDI1SPH+0INDI1SPH+0INDI1SPH+0INNONO,NONODIDI1SPH+0IN2SPH+0INNONODITEH+20.7INYES8989789109015911092DI'IDI1SPH+0INNO2SPH+0INNO1SPH+0IN,NO2441SPC+0INDI2SPH+0INNONO993"29+o1SPC+0IN'O119330%'SPC+0INNODI1SPH+0INNO28832684DI1SPH+0IN2241SPC+0INNONO272726268484858518%24%31%1843SPC+0IN2SPC+0IN2SPC+0IN1SPC+0INNONONONO10862386DI,1SPH+0INNO3842SPC+0IN'O.87872486258630+o1SPC+0INDI2SPH+0INDI1SPH+0INDI1SPH+0INNONONONOA-4 STEAMGENERATOR NUMBER12ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED2DI4SPH+0INNO2-52~o1SPC+0INYES343~o1SPC+0INYES3DI2SPH+0INNO9'28~o1SPC+0INNO1313335~o429'o1SPC+1SPC+0INNO0INNO"14425~o1SPC+0IN,NO15450~oE1SPC+0IN"YES5~DI1SPH+0INNO522+o2SPC+0INNO6DI2SPH+0INNO6,DI3SPH+0INNO7DI2SPH+0INNO7DI7DI1SPH+0INNO2SPH+0INNO417189DI2SPH+0INNO9DI1SPH+0INNO9DI1SPH+0INNO9DITEH+20.8INYES8213DI1SPH+0INNO13DI1SPH+0INNO14DI1SPH+0INNO1810-DI1SPH+0INNO412Dl1SPH+0INNO812DI1SPH+0INNO2315DI1SPH+0INNO3015231715188202120182118228238241624202417'SPC+0INNODI1SPH+0INNODRITEH+2.4INYESDI2SPH+0INNODI1SPH+0INDI1SPH+0INDI1SPH+0INDI1SPH+0INDI2SPH+0INNONONONONODI1SPH+0INNODI1SPH+0INNODITSH+.6INYES1631353145~oAV3+0INYESDI1SPH+0INNODI2SPH+0INNO53~o2SPC+0INYES'14'SPC+0IN.NO113212374437443843414341434214433843NONO38~o.AV3+0IN35~oAV4+0INDITEH+20.8INYESoDITSH+1.6INYES1SPH+0INNOTSH+1.8INYESDI1544'I1214'I1SPH+0INNO815DI1SPH+0INNOA-5 . STEAMGENERATOR NUMBER12ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED3535444432~25~AVl+0INAV2+0INNONO2771DITEH+20.6INYES4545444414~o2SPC+0INNO14'SPC+0INNO387224%387228<AV3+0INAV4+0INNONO375435536551957436023614361446242426363426418E65'51246234738474347114814481351525427~o344AV3+0INAV4+0INNONO14~1SPC+0INNODI1SPH+0INNO17'V1+0INNODITEH+17.8INYESDI1SPH+0INNODI2SPH+0INNO19'V1+0'INNODI2SPH+0INNODRITEH+2.5INYESDITEH+21.1INYESDI,1SPH+0INNO26~oAV4+0INNO39~oAV4+0INNODI1SPH+0IN8041+oAV1+0INYESDI1SPH+0INNO2l~o1SPC+0INNODI1SPH+0INNODI2SPH+0INNO23~o2SPC+0INNO367437743774217637763776,357715'SPC+0INYESDIDI4SPH+0IN1SPC+0INNO'NODI1SPH+0IN.NO15'I2SPC+0IN1SPC+0INNONO27~o1SPC+0IN3677377733~o33~o2SPC+0IN1SPC+0INNONO28783378DI.1SPH+0IN22~o1SPC+0INNO347815'SPC+0INNO317928%317911~2SPC+0IN1SPC+0INNONO298227~o2SPC+,,0INNO308225~o2SPC+0INNO1586DITEH+20.6INYES238635~o238614>o2SPC+0IN1SPC+0INNONO248645~o789DI2SPC+02SPH+0INYESINNO139010'SPC+0IN69130<1SPC+0INNONO1689DI2SPH+0INNO1989DI1SPC+0INNO414*66.DI2SPC+0INNOA-6 STEANGENERATOR NUMBER12ROWCOLIND1CLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED10913341SPC+0INNO79322<1SPC+0INNOA-7 II0l,0 STEAMGENERATOR NUMBER13RONCOLINDICLOCATIONPLUGGED3722,27~o2SPC+0INNO1023DRITEH+2.3INYES14~o1SPC+0INDI2SPH+0INDI3SPH+,0INDI'SPC+0IN18'SPC+0IN26~o2SPC+0INNO4'NO2424827DRITEH+2.4INYESDRITEH+2.5INYESDI2SPH+0INNODITEH+20.8INYESDRITEH+2.4INYESNONO123527328312838283828NO10NO13DI2SPC+0INNO28~o2SPC'+0INNODI3SPH+0INNO1428~30~oAV2+0INNOAV3+0INNOITEH+2.5INYES16"429DRI6DITEH+20.3INYESDI1SPH+0INNO1522292929266DITEH.+20.3INYESDRITEH+2.5INYES29~o2SPC+0INNODI1SPH+0INNO102331DRITEH+2.6INYES2531DRITEH+2.6INYES'533DRITEH+2.7INYES2933DRITEH+2.7INYES1236~o2SPC+0IN.NODITEH+20.1INYES28.12413101428,1635,189191019=34193519DI1SPH+0INNO634DRITEH+2.9INYES1434DRITEH+2.9INYESDITEH+19.9INYES14'SPC+0INNODRITEH+2.4INYESDI2SPH+0INNO52+o1SPC+0INYES24~o1SPC+0INNO443431+o2SPC+0INNO2435DRITEH+2.4INYES2535DRITEH+,3.0INYES436DRITEH+2.8INYES2836DRITEH+2.4INYES1920DRITEH+2.2INYES32+o2SPC+'0INNODRITEH+2.6INYES44362837352148<2SPC+0INYES822DRITEH+2.5INYESA-8ROWCOLINDICLOCATIONPLUGGED. 0 STEAMGENERATOR NUMBER13ROW4141COLUNDIDLOCAT10NPLUGGED3816%AV3+0INNO3830~oAV4+0INNO1252~DRITEH+2.3INYES'ROWCOLINDICLOCATIONPLUGGED'1952DITSH+.9INYES640DITEH+20.4INYES364145~oAV2+0INYES414119'V1+0INNO1142DRITEH+2.3INYES33524l~o'V3+0INYES453DRITEH+2.3INYES2852DRITEH+2.4INYES38384228~oAV3+0INNO4229~oAV4+0INNO363653531853DITSHv30~oAV318'V4+0IN+0INNONO+1~1INYES645DITEH+19.9INYES1546DITSH+.1INYES3046DRITEH+2.7INYES375518'V2+0INNO754DRITEH+2.6INYES:3842424823~oAV3+0IN4832<AV4+0IN484818~AV1+0IN16~AV2'+0IN4726~oAV3+0IN4723~oAV4+0INNONONONONONO40405529%AV3+0IN5518'V4'0INNONO556DRITEH+2.8INYES656DRITEH+2.5INYES365638~oAV1+0INNO3656374AV2+0INNO40405050334916'V3+0INNO28~oAV3+0INNO17'V4+0IN'O375632~oAV1+0INNO375637~oAV2+0INNO375630~oAV3+0INNO4141505034~oAV3+0INNO25+oAV4+0INNO251651DRITEH+2.4INYESDRITEH+2.4INYES38~3851'18'V3+0INNO5117'V4+0INNO.51DI2SPH+0INNO51DI1SPH+0INNO2251DITSH+.3INYESA-924573657365765885839583958415826595'0DI1SPH+0INNO35~oAV3+0INNO28+oAV4+0INNODI1SPH+0INNODI1SPH+0INNO17'V3+0INNO23~oiAV4+0INNO45~o,AV3+0INYESDRITEH+2.5INYESDI1SPH+0INNO STEAMGENERATOR NUMBER13ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED2330344460DRI60DRI601846016'EH+2.4INYESTEH+2.5INYESAV4+0INNO1SPC+0INNO567DI1SPH+0INNO1167DI1SPH+0INNO368DRITEH+2.4INYES1069DRITEH+2.4INYES343436366118'125<6130o6135'oAV3+0INAV4+0INAV3+0INAV4+0INNONONONO396926+o3SPC+0IN387033%'SPC+0IN397038~o3SPC+0INNO41326123~o6225~oAV3+0INNOAV3+0INNO471DRITEH+2.4INi'71DRITEH+2.2INYES4040'3106215'231~o6228~o6227~o62DI64DIAV1+0INNOAV2+0INNOAV3+0INNOAV4+0INNO1SPC+0INNO1SPH+0INNO3971DI2SPH+0INNO2473DI2SPH+0IN37732941SPC+0INNONO474DRITEH+2.4INYES473DRITEH+2.5INYES333336366425~o6417~o6425%6423~oAV1+0INNOAV2+0INNOAV3+0INNOAV4+0INNO347628+o2SPC+0IN367629~oAV3+0INNONO40436430%6432~oAV1+0INNO1SPC+0INNO877DRITEH+2.3INYES327814'SPC+0IN~NO2465DI1SPH+0INNO680DI1SPH+0INNO36363939.6524>o6526<6518'526+o6519~o6527+o66DIAV3+0INNOAV4+0INNOAV3+01NNOAV4+0INNOAV2+0INNOAV3+0INNOTEH+20.6INYES318016'SPC+0IN'O30813743SPC+0INNO308133~o1SPC+0INNO1083DI2SPH+0INNO2883DI1SPC+0INNO2984DI1SPH+0INNO686'I2SPH+0INNO 'STEAMGENERATOR NUMBER13RONCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED1086218778999110921093DI1SPH+0IN11+o1SPC+0INDI2SPH+0INDI2SPH+0INNONONONO28+o'SPC+0INNO17'SPC+0INNO494DI1SPH+0INNO5941941SPC+0INNO794'5~o1SPC+0IN'O

    'STEAMGENERATOR NUMBER14639155DITEH+20.8INYES28~o1SPC+0INNODITEH+20.8INYESDI1SPC+01NNO19202122jj<1SPC+0INDI1SPH+0INDI1SPC+01N30~o1SPC+0IN12'SPC+0INNONONONONO1610251027102212DI3SPH+0INNODI1SPH+0IN"NO24+o1SPC+0INNODI2SPH+0INNODI1SPH+0INNO1641SPC+0INNODITEH+20.6INYES2612'6'SPC+0INNO281228133013DI5SPH+0INNODI1SPH+0INNODI1SPH+0INNO18,,14DITEH+21.1INYESROWCOLINDICLOCATIONPLUGGED2815DITEH+20.5INYES31158'7341721982092015203720282128213021372138211122'12228222822112415263827628192817~1SPC+0INNODI2SPH+0INNO38+o1SPC+0INNODI2SPH+0IN'I1SPH+0INDI1SPH+0IN'NO,NONODITEH+20.7INYESDI1SPH+0INNODI1SPH+0INNODI2SPH+0INNODI1SPH+0INNODITEH+20.6INYESDI1SPH+0INNODI1SPH+0INNOD13SPH+0INNODI1SPH+0INNODI2SPH+0INNODI3SPH+0INNODRITEH+2.5INYESDI1SPH+0INNODRITEH+2.6INYESDRITEH+2.3INYESROWCOLINDICLOCATIONPLUGGED311481518DI1SPC+01SPH+0INNOINNO4029'I1SPH+0INNO15DITEH+20.1INYES4229DI1SPC+0INNO15DI1SPH+0INNO530530530DI1SPH+0INDI2SPH+0INDI.3SPH+0INNONONO STEAMGENERATOR NUMBER14'ITEH+20.9INYESDI1SPH+0INNODITEH+20.7INYESDITEH+20.5INYES23~o1SPC+0INNODI2SPH+0INNO13'SPC+0INNODI1SPH+0INNO38+o1SPC+0INNO29%2SPH+0INNODITEH+20.4INYES8303230343037303042531413132324232331233NO34DI1SPH+0IN443427%1SPC+0INNO1733444445353535363632+oTSH+5INYESDI1SPH+0INNO19'1SPC+0INYES26<1SPC+0INNO1641SPC+0INNOROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED4439'7+o4SPC+0INNO4240DI2SPH+0INNO2941DI1SPH+0INNO3841DI1SPH+0INNO4241DI1SPH+0INNO454119'SPC+0INNO464116<2SPC+0INNO2143D11SPH+0INNO4443DI'SPC+0INNO4643244'SPC+0INNO1045DI1SPH+0INNO1745DITSH+.5INYES4145234AV3+0INNO414518%AV4+0INNO'646DI'TSH+1.1INYES2246DITEH+21.2INYES334624~oAV2+0INNO3346344AV3+0INNO334626~oAV4+0ZNNO4545383714%2SPC+0IN371641SPC+0IN39DI1SPH+0IN39DI1SPH+0IN1737DI1SPH+0IN2937DI1SPH+0IN3837DI2SPH+0IN4437392SPC+0INNONONONONONONONO4246DITEH+20.8INYES464619'SPH+0INNO384818'SH+42'INNO3249DI2SPH+0INNO4649DI1SPH+0INNO850DRITEH+2.4INYES1250'I1SPH+0INNO4650DI1SPH+0INNO

    STEAMGENERATOR NUMBER14ROWCOLZNDZCLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED2351DI1SPH+0INNO303057DI1SPH+0IN57DI3SPH+0INNONO2260DI1SPH+0IN446014<3SPC+0IN1261DI1SPH+0INNONONO17o3061DI1SPH+0INNO61DI1SPH+0INNO61DI1SPH+0INNO43613141SPC+0INYES1362DI1SPH+0INNO3562DI'SPH+0INNO455113'SPC+0INNO1852DRITEH+2.1INYES1854DRITEH+2.2INYES4455DI2SPH+0INNO2669266918703170307333733973474574187433743374137533753575367547615'6'Vl+0INAV2+0INNONODI1SPH+0INNODI1SPH+0INNODI1SPH+0INNODI1SPH+0INNO16~2SPC+0INNODI2SPH+.0INNODI1SPH+0INNODITEH+20.6INYESDIDI1SPH+0INNO2SPH+0INNODI2SPH+0INNODI1SPH+0INNODI2SPH+0INNO24~o2SPC+0INNO38>o2SPC+0INNO1919196322~oAV2+0IN6319<AV3+0IN6311%AV4+0INNONONO665DI1SPH+0IN1765DI1SPH+0IN416534+o2SPC+0IN-.NONONO19191925,66DI1SPH+0INNO67DITEH+20.7INYES6615'Vl+0INNO6622~oAV2+0INNO66244AV3+0INNOA-141776DITEH+20.9INYES1876DITEH+20.9INYES1976"DITEH+20.6INYES3176DI3SPH+0INNO3376DI1SPH+0INNO367621'SPC+0INNO2377DITEH+20.8INYES337754~o2SPC+0INYES2378DI3SPH+0INNO

    'STEAMGENERATOR NUMBER14ROWCOLINDICLOCATIONPLUGGEDROWCOLINDICLOCATIONPLUGGED2678'I2SPH+0INNO30'82298328842680248129813081182118222<AV3+0INNODI2SPH+0INNO10'SPC+0INNO28+o2SPC+0INNODI2SPH+0INNODI2SPH+0INNO31+o2SPC+0INNODI1SPC+0INNO10'SPC+0INNO'686DI38>o2SPH+0INNO2SPC+0INNO2387'28816911292312SPC+0INNODITEH+21.1INYES28~o1SPC+0INNO25%1SPC+0INNO12'12939324'3~o2SPC+0INNO1SPC+0INNO59411%1SPC+0INNOA-15 ls' .9104220022 c.CoomcUNIRSANDDOCKETNOS~50315AND50-316LICENSENOS.DR-58ANDDPR7iUPDATEDQUALITYASSURANCS PROGRAMDESCRIPTION 'IFORTHECOOKNUCLEARPLANTJULY'991Concurred by:AEPSCVicePresident -NuclearOperations CChice'orVxePresident andngineDate:Approvedby:AEPSCDirector-QualityAssurance Date:4il EQUALITYASSURANCE PROGRANDESCRIPTION FORTHECOOKNUCLEARPLANTTABLEOFCONTENTSSectionTableofContentsTitle~PaeNo.1.7Statement ofPolicyfortheDonaldC.Cook1.7.11.7.2,1.7.31.7.41.7.51.7.61.7.71.7.81.7.91.7.101.7.111.-7.121.7.131.7.141.7.151.7.161.7.171.7.181.7.19NuclearPlantgualityAssurance Program.....Organization. gualityAssurance Program...........DesignControl.Procurement DocumentControl.Instructions, Procedures, andDrawings. DocumentControl.ControlofPurchased ItemsandServices.Identification andControlofItems.ControlofSpecialProcesses. Inspection. TestControl.ControlofHeasuring andTestEquipment .Handling, StorageandShipping. Inspection, TestandOperating Status.Nonconforming Items...Corrective Action.gualityAssurance Records.udits.AFireProtection gAProgram.Figure1.7-1.Figure1.7-2...................Figure1.7-3.Flgu're1o7'4o~~~~~~~~~~o~~~~~~~Figure1.7-5.AppendixARegulatory andSafetyGuide/ANSI Standards. ...AppendixBAEPSC/IKH Exceptions toOperating PhaseStandards andRegulatory Guides..............1.7-11.7-41.7-331.7-411.7-471.7-501.7-531.7-551.7-601.7-611.7-641.7-681.7-701.7-721.7-741.7-761.7-781.7-801.7-821.7-861.7-921.7-931.7-941.7-951.7-961.7-971.7-102 AmericanElectricPowerServiceCorporation tRi~'>>Ge'ac3Colo.'Boos OHA32l56t~223l000ANERICANELECTRiCPCWVERSTATEk69IT OFPOLICYFORTHEDONALDCoCOOKNUCLEARPLANTQUALITYASSURANCE PROGRAMPOLICYAmericanElectricPowerCompany,Inc.,recognizes thefundamental importance ofcontrolling thedesign,modification, andoperation ofIndianaMichiganPowerCompany's DonaldC.CookNuclearPlant(CookNuclearPlant)byimplementing aplannedanddocumented QualityAssurance Program,including QualityControl,thatcomplieswithapplicable regulations, codes,andstandards. TheQualityAssurance Programhasbeenestablished tocontrolactivities affecting safety-related functions ofstructures, systems,andcomponents intheCookNuclearPlant.TheQualityAssurance Programsupportsthegoalofmaintaining thesafetyandreliability oftheCookNuclearPlantatthehighestlevelthroughasystematic programdesignedtoassurethatsafety-related itemsareconducted incompliance withtheapplicable regulations, codes,standards, andestablished corporate policiesandpractices. AsPresident andChiefExecutive OfficerofAmericanElectricPowerCompany,Inc.,Imaintaintheultimateresponsibility fortheQualityAssurance Programassociated withtheCookNuclearPlant.Ihavedelegated functional responsibility fortheQualityAssurance ProgramtotheAmericanElectricPowerServiceCorporation (AEPSC)SeniorExecutive VicePresident-Engineering andConstruction. Hehas,withmyapproval, delegated furtherresponsibilities asoutlinedinthisstatement. IMPLEMENTATION TheAEPSCDirector-Quality Assurance, underthedirection oftheAEPSCSeniorExecutive VicePresident-Engineering andConstruction, hasbeenassignedtheoverallresponsibility forspecifying theQualityAssurance programrequirements fortheCookRevisedaFebruary25,1991July,1991

    Statement ofPolicyfortheDonaldC.CookNuclearPlantQualityAssurance ProgramPage2NuclearPlantandverifying theirimplementation. TheAEPSCSeniorExecutive VicePresident-Engineering andConstruction hasgiventheAEPSCDixector-Quality Assurance authority tostopworkonanyactivityaffecting safety-related itemsthatdoesnotmeetapplicable administrative, technical, and/orregulatory requirements. TheAEPSCDirector-Quality Assurance doesnothavetheauthority tostopunitoperations, butshallnotifyappropxiate plantand/orcoxporate management ofconditions notmeetingtheaforementioned criteriaandrecommend that.unitoperations beterminated. TheAEPSCVicePresident-Nuclear Operations, underthedirection oftheAEPSCSeniorExecutive VicePxesident-Engineering andConstruction, hasbeendelegated responsibility foreffectively implementing theQualityAssurance Program.TheAEPSCVicePresident-Nuclear Operations istheManagerofNuclearOperations. AllotherAEPSCdivisions anddepartments, except'ualityAssurance, havingasupporting rolefortheCookNuclearPlantarefunctionally responsible totheManagerofNuclearOperations. ThePlantManager,underthedirection oftheAEPSCVicePresident-Nuclear Operations, isdelegated theresponsibility forestablishing theCookNuclearPlantQualityControlProgramandimplementing theQualityAssurance ProgramattheCookNuclearPlant.TheAEPSCDirector-Quality Assurance isresponsible forproviding technical direction tothePlantManagerformattersrelatingtotheQualityAssurance ProgramattheCookNuclearPlant.TheAEPSCDirector-Quality Assurance isalsoresponsible formaintaining aQualityAssurance SectionattheCookNuclearPlanttoperformrequiredreviews,audits,andsurveillances, andtoprovidetechnical liaisonservicestothePlantManager.fTheimplementation oftheQualityAssurance Programisdescribed intheAEPSCGeneralProcedures (GPs)andsubtierdepartment/ divisionprocedures, PlantManager's Instructions (PMIs),andsubtierDepartment HeadInstructions andProcedures, whichintotaldocumenttherequirements forimplementation oftheProgram.Revised:February25,1991July,1991 0 St'atement ofPolicyfortheDonaldC.CookNuclearPlantQualityAssurance ProgramPage3EachAEpSCandCookNuclearPlantorganization involvedinactivities .affecting safety-related functions ofstructures, systems,andcomponents intheCookNuclearPlanthastheresponsibility toimplement theapplicable policiesandrequirements oftheQualityAssurance Program.Thisresponsibility includesbeingfamili'ar with,andcomplying with,therequirements oftheapplicable QualityAssurance Programrequirements. ~COMPLIANCE TheAEPSCDirector<<Quality Assurance shallmonitorcompliance withtheestablished QualityAssurance Program.Auditprogramsshallbeestablished toensurethatAEPSCandCookNuclearPlantactivities complywithestablished programrequirements, identifydeficiencies ornoncompliances andobtaineffective andtimelycorrective actions.Employees engagedinactivities affecting safety-related functions ofstructures, systems,andcomponents intheCookNuclearPlantwhobelievethattheQualityAssurance Programisnotbeingcompliedwith,orthatadeficiency inqualityexists,shouldnotifytheirsupervisor, theAEPSCDirector-Quality Assurance, and/orthePlantManager.Ifthenotification doesnotintheemployee's opinionreceivepromptorappropriate attention, theemployeeshouldcontactsuccessively higherlevelsofmanagement. Employees reporting suchconditions shallnotbediscriminated againstbycompanies oftheAmericanElectricPowerSystem.Discrimination includesdischarge orotheractionsrelativetocompsation,terms,conditions, orprivileges ofemployment. R.E.DisbrowPresident andChiefExecutive OfficerAmericanElectricPowerCompany,Inc.Revised:February25,1991July,1991 1.7.1.ORGANIZATION 1.7.1.1SCOPEAmericanElectricPowerServiceCorporation (AEPSC)isresponsible forestablishing andimplementing theQualityAssurance (QA)Programfortheoperational phaseoftheDonaldC.CookNuclearPlant(CookNuclearPlant).Althoughauthority fordevelopment andexecution ofvariousportionsoftheprogrammaybedelegated toothers,suchascontractors, agentsorconsultants, AEPSCretainsoverallresponsibility. AEPSCshallevaluateworkdelegated tosuchorganizations. Evaluations shallbebasedonthestatusofsafetyimportance oftheactivitybeingperformed andshallbeinitiated earlyenoughtoassureeffective qualityassurance duringtheperformance ofthedelegated activity. ThissectionoftheQualityAssurance ProgramDescription (QAPD)identifies theAEPSCorganizational responsibilities foractivities affecting thequalityofsafety-related nuclearpowerplantstructures, systems,andcomponents, anddescribes theauthority anddutiesassignedtothem.Itaddresses responsibilities forbothattaining qualityobjectives and,forthefunctions ofestablishing theQAProgram,andverifying thatactivities affecting thequalityofsafety-.related itemsareperformed effectively inaccordance withQAProgramrequirements. 1.7.1.2INPLEHENTATION 1.7.1.2.1SourceofAuthoritThePresident andChiefExecutive OfficerofAmericanElectricPowerCompany,Inc.(AEP)andAEPSCisresponsible forsafeoperation oftheCookNuclearPlant.Authority andresponsibility foreffectively implementing theQAProgramforplantmodifications, operations andmaintenance aredelegated throughtheAEPSCSeniorExecutive VicePresident -Engineering andConstruction, totheAEPSCVicePresident NuclearOperations (ManagerofNuclearOperations). 1.7-4July,1991 Inthe.operation ofanuclearpowerplant,thelicenseeisrequiredtoestablish clearanddirectlinesofresponsibility, authority andaccountability. Thisrequirement isapplicable totheorganization providing supporttotheplant,aswellastotheplantstaff.TheAEPSCcorporate supportoftheCookNuclearPlantistheresponsibility oftheentireorganization underthedirection oftheHanagerofNuclearOperations whomaintains primaryresponsibility fortheCookNuclearPlantwithinthecorporate organization. TheAEPSCVicePresident -NuclearOperations istheManagerofNuclearOperations. AllotherAEPSCdivisions anddepartments, otherthanthegualityAssurance

    Division, havingasupporting rolefortheCookNuclearPlantarefunctionally responsible totheManagerofNuclearOperations (reference Figure1.7-1).Inordertofacilitate amorethoroughunderstanding ofthesupportfunctions, someoftheresponsibilities, authorities, andaccountabilities withintheorganization areasfollows:1)Theresponsibilities oftheManagerofNuclearOperations shallbededicated totheareaofCookNuclearPlantoperations andsupport.2)TheManagerofNuclearOperations shallberesponsible for,andhastheauthority todirect,allCookNuclearPlantoperational andsupportmatterswithinthecorporation andshallmake,or4concur,inallfinaldecisions regarding significant nuclearsafetymatters.3)AEPSCorganization managersresponsible forCookNuclearPlantmattersshallbefamiliarwithactivities withintheirscopeofresponsibility thataffectplantsafetyandreliability.

    Theyshallbecognizant of,andsensitive to,internalandexternalfactorsthatmightaffecttheoperations ofCookNuclearPlant.1.7-5July,1991 Ji 4)AEPSCorganization managersresponsible forCookNuclearPlantmattershaveacommitment toseekandidentifyproblemareasandtakecorrective actiontoeliminate unsafeconditions, ortoimprovetrendsthatwillupgradeplantsafetyandreliability. 5)TheManagerofNuclearOperations shallensurethatCookNuclearPlantpersonnel arenotrequested toperforminappropriate workortasksbycorporate personnel, andshallcontrolassignments andrequeststhathavethepotential fordiverting theattention ofthePlantManagerfromtheprimaryresponsibility forsafeandreliableplantoperation. 6)AEPSCdivisionanddepartment managershavingCookNuclearPlantsupportresponsibilities, aswellasthePlantManagerandplantorganization

    managers, shallbefamiliarwiththepolicystatements fromhigher'anagement concerning nuclearsafetyandoperational priorities.

    Theyshallberesponsible forensuringthatactivities undertheirdirection areperformed inaccordance withthesepolicies. 1.7.1.2.2Resonsibilit forAttaininualitOb'ectives inAEPSCNuclear~0erations TheAEPPresident andChiefExecutive Officerhasdelegated thefunctional responsibility ofthegualityAssurance ProgramtotheAEPSCSeniorExecutive VicePresident -Engineering andConstruction. TheAEPSCDirector-gualityAssurance, underthedirection oftheAEPSCSenior'xecutive VicePresident -Engineering andConstruction, isresponsible forspecifying gAProgramrequirements andverifying theirimplementation. July,1991 TheAEPSCVicePresident -NuclearOperations, underthedirection oftheAEPSCSeniorExecutive VicePresident -Engineering andConstruction, isresponsible foreffectively implementing theQAProgram.ThePlantManager,underthedirection oftheAEPSCVicePresident-NuclearOperations, isresponsible forestablishing theCookNuclearPlantQualityControlProgramandimplementing theQAProgramattheCookNuclearPlant.Management/supervisory personnel receivefunctional trainingtothelevelnecessary toplan,coordinate, andadministrate thoseday-to-day verification activities oftheQAProgramforwhichtheyareresponsible. AEPSChasanindependent off-siteNuclearSafetyandDesignReviewCommittee (NSDRC)whichhasbeenestablished pursuanttotherequirements oftheTechnical Specifications fortheCookNuclearPlant.ThefunctionoftheNSDRCistooverseetheengineering, design,operation, andmaintenance oftheCookNuclearPlantbyperforming auditsandindependent reviewsofactivities whicharespecified intheFacilityOperating Licenses. TheCookNuclearPlanton-sitereviewgroupistheIndianaMichiganPowerCompany(I&M)PlantNuclearSafetyReviewCommittee (PNSRC).Thiscommittee hasalsobeenestablished pursuanttotherequirements oftheCookNuclearPlantTechnical Specifications. ThefunctionofthePNSRCistoreviewplantoperations onacontinuing basisandadvisethePlantManageronmattersrelatedtonuclearsafety.July,1991 1.7.1.2.3CororateOranization ~~~~AmericanElectricPowerComanAEP,theparentholdingcompany,whollyownsthecommon,stockofallAEPSystemsubsidiary (operating) companies. Themajoroperating companies andgeneration subsidiaries areshowninFigure1.7-2.ThePresident andChiefExecutive OfficerofAEPistheChiefExecutive OfficerofAEPSCandalloperating companies. Theresponsibility forthefunctional management ofthemajoroperating companies isvestedinthePresident ofeachoperating companyreporting totheAEPSCPresident andChiefOperating OfficerwhoreportstotheAEPSCChairmanoftheBoard.AmericanElectricPowerServiceCororationTheresponsibility foradministrative andtechnical direction oftheAEPSystemanditsfacilities isdelegated toAEPSC.AEPSCprovidesmanagement andtechnological servicestothevariousAEPSystemcompanies. 0eratinComaniesTheoperating facilities oftheAEPSystemareownedandoperatedbytherespective operating companies. Theresponsibility forexecuting theengineering, design,construction, specialized technical

    training, andcertainoperations'upervision isvestedinAEPSC,whileall,orpart,oftheadministrative functional responsibility isassignedtotheoper-atingcompanies.

    InthecaseofCookNuclearPlant,I&Mgeneralofficestaff(headquarters) providespublicaffairs,accounting, industrial safetydirection andprocurement support.TheCookNuclearPlantisownedandoperatedbyI&NwhichispartoftheAEPSystem.1.7-8July,1991 1.7.1.2.4 ualitAssurance Resonsibilit ofAEPSC~~~~~1}AEPSCprovidesthetechnical direction fortheCookNuclearPlant,andassuchmakesthefinaldecisions pertinent tosafety-related changesinplantdesign.Further,AEPSCreviewsNuclearRegulatory Commission (NRC)letters,bulletins, notices,etc.,forimpactonplantdesign,andtheneedfordesignchangesormodifications. 2)AEPSCfurnishes qualityassurance, engineering, design,construction, licensing, NRCcorrespondence, fuelmanagement andradiological supportactivities. 3)AEPSCprovidesadditional serviceinmatterssuchassupplierqualification, procurement oforiginalequipment andreplacement parts,andtheprocessofdedicating commercial gradeitemsorservicestosafety-related applications. 4)TheAEPSCgADivisionprovidestechnical direction inqualityassurancematterstoAEPSCandtheCookNuclearPlant,andoverseestheadequacy, effectiveness andimplementation ofthegAProgramthroughreviewandauditactivities. 5}Cognizant Engineer-(e.g.,SystemEngineer, Equipment

    Engineer, LeadEngineer, Responsible
    Engineer, etc.)-Thecognizant
    engineer, and/orengineerwiththeothertitlesnoted,isthatAEPSCindividual whoprovidestheengineering/design expertise foraparticular areaofresponsibility.

    Thisresponsibility includestheimplementation ofthequalityassurance andqualitycontrolmeasuresforsystems,equipment, structures, orfunctional areasincludedinthatindividual's responsibility. Thevarioustitlesusedfortheidentification ofanindividual's responsibility andassignment shallbeunderstood tomeanthesameascognizant engineerintherespective areasofresponsibility. 1.7-9July,1991

    ualitAssurance Resonsibilit of18M-CookNuclearPlant18M'sCookNuclearPlantstaffoperatestheCookNuclearPlantinaccordance withlicensing requirements, including theTechnical Specifications andsuchothercommitments asestablished bytheoperating licenses. ThePlantManagerInstruction (PMI)systemandsubtierinstructions andprocedures describethemeansbywhichcompliance isachievedandresponsibilities areassigned, including interfaces withAEPSC.Figure1.7-3indicates theorganizational relationships withintheAEPSystempertaining totheoperation andsupportoftheCookNuclearPlant.1.7.1.2.5 Oranization AEPSCThePresident andChiefExecutive Officerisultimately responsible fortheQAProgramassociated withtheCookNuclearPlant.Thisresponsibility hasbeenfunctionally delegated totheAEPSCSeniorExecutive VicePresident -Engineering andConstruction. TheAEPSCSeniorExecutive VicePresident -Engineering andConstruction hasfurtherdelegated responsibilities whichareadministered throughthefollowing divisionanddepartment management personnel: AEPSCDirector-QualityAssurance AEPSCVicePresident -NuclearOperations AEPSCSeniorVicePresident andChiefEngineerAEPSCVicePresident -ProjectManagement andConstruction ualitAssurance DivisionTheAEPSCDirector-QualityAssurance, reporting totheAEPSCSeniorExecutive VicePresident -Engineering andConstruction, isresponsible fortheQualityAssurance Division(QAD).TheQADconsistsofthe,following sections(Figure1.7-4):QualityAssurance Engineering SectionNuclearSoftwareQualityAssurance SectionAuditsandProcurement SectionJuly,1991

    gualityAssurance SupportSectionequalityAssurance Section(Site)'he gADisorganizationally independent andisresponsible toperformthefollowing: SpecifygAProgramrequirements. Identifyqualityproblems.

    Initiate, recommend, orprovidesolutions throughdesignated channels.

    Verifyimplementation ofsolutions, asappropriate. Prepare,issueandmaintaingAProgramdocuments, asrequired. Verifytheimplementation ofthegAProgramthroughscheduled auditsandsurveillances. Verifytheimplementation ofcomputersoftwarequalityassurance throughreviews,surveillances andaudits.Auditengineering, design,procurement, construction andoperational documents forincorporation of,andcompliance with,applicable qualityassurance requirements totheextentspecified bytheAEPSCmanagement-approved gAProgram.OrganizeandconductthegAauditororientation,

    training, certification andqualification ofAEPSCauditpersonnel.

    Providedirection forthecollection, storage,maintenance, andretention ofqualityassurance records.Haintain, ondatabase,alistofsuppliers ofnuclear(N)itemsandservices, plusotherselectedcategories ofsuppliers. Identifynoncompliances oftheestablished gAProgramtotheresponsible organizations forcorrective actions,andreportsignificant occurrences thatjeopardize qualitytoseniorAEPSCmanagement. Followuponcorrective actionsidentified bygAduringandafterdisposition implementation. Reviewthedisposition ofconditions adversetoqualitytoassurethatactiontakenwillprecluderecurrence. Conductin-process gAauditsorsurveillances atsupplier's facilities, asrequired. July,1991 t AssistandadviseotherAEP/AEPSC groupsinmattersrelatedtothegAProgram.ConductauditsasdirectedbytheNSDRC.ReviewAEPSCinvestigated ProblemReportsandassociated corrective andpreventive actionrecommendations. Naintaincognizance ofindustryandgovernmental qualityassurance requirements 'suchthatthegAProgramiscompatible withrequirements, asnecessary. Recommend forrevisionto,orimprovements in,theestablished gAProgramtoseniorAEPSCmanagement. Auditdedication plansforcommercial gradeitemsandservices. Issue"StopWork"orderswhensignificant conditions adversetosafety-related itemsareidentified topreventunsafeconditions fromoccurring and/orcontinuing. ProvideAEPSCmanagement withperiodicreportsconcerning thestatus,adequacyandimplementation ofthegAProgram.Prepareandconductspecialverification and/orsurveillance programsonin-houseactivities, asrequiredorrequested. Routinely attend,andparticipate in,dailyplantworkscheduleandstatusmeetings. ProvideadequategAcoveragerelativetoprocedural andinspection

    controls, acceptance
    criteria, andgAstaffingandqualification ofpersonnel tocarryoutgAassignments.

    Establish andmaintainacentralfileforequipment environmental qualification documentation. (*(*Amlification ofSecificResonsibilities uglification oftheAEPSCDirector-ualitAssurance TheAEPSCDirector-gualityAssurance shallpossessthefollowing positionrequirements: Hachelor's degreeinengineering, scientific, orrelateddiscipline. Ten(10)yearsexperience inoneof,oracombination of,thefollowing areas:engineering, design,July,1991(*(*(* construction, operations, maintenance offossilornuclearpowergeneration facilities'r utilityfacilities'A, ofwhichatleastfour(4)yearsmustbeexperience innuclearqualityassurance relatedactivities. Knowledge ofgAregulations,

    policies, practices andstandards.

    Thesame,orhigher,organization reporting levelasthehighestlinemanagerdirectlyresponsible forperforming activities affecting thequalityofsafety-relateditems,suchasengineering, procurement, construction andoperation, andissufficiently independent fromcostandschedule. Effective communication channelswithotherseniormanagement positions. Responsibility forapprovalofgAHanual(s). Performance ofnootherdutiesorresponsibilities unrelated togAthatwouldpreventfullattention togAmatters.StoWorkOrdersTheAEPSCgADisresponsible forensuringthatactivities affecting thequalityofsafety-related itemsareperformed inamannerthatmeetsapplicable administrative, technical, 'ndregulatory requirements. Inordertocarryoutthisresponsibility, theAEPSCSeniorExecutive VicePresident-Engineering andConstruction hasgiventheAEPSCDirector-gualityAssurance theauthority tostopworkonanyactivityaffecting thequalityofsafety-related itemsthatdoesnotmeettheaforementioned requirements. Stopworkauthority hasbeenfurtherdelegated bytheAEPSCDirector-gualityAssurance totheAEPSCgualityAssurance Superintendent (site).1.7-13July,1991

    TheAEPSCDirector-QualityAssurance andtheAEPSCQualityAssurance Superintendent donothavetheauthority tostopunitoperations, butwillnotifyappropriate CookNuclearPlantand/orcorporate management ofconditions whichdonotmeettheaforementioned

    criteria, andrecommend thatunitoperations beterminated.

    AAuditoruglification andCertification ProramAEPSChasestablished andmaintains aQAauditortrainingandcertification programforallAEPSCQAauditors. ProblemIdentification ReortinandEscalation AEPSChasestablished mechanis'ms fortheidentification, reporting andescalation ofproblemsaffecting thequalityofsafety-related itemstoalevelofmanagement wherebysatisfactory resolutions canbeobtained. Nuclear0erationsDivisionTheAEPSCVicePresident -NuclearOperations (ManagerofNuclearOper-.ations),reporting totheAEPSCSeniorExecutive VicePresident-Engineering andConstruction, isresponsible fortheNuclearOperations Division(NOD).Theorganization and'responsibilities ofthePlantNanageraredefinedfhihitliti41.7.1.E.S ~iCookNuclearPlant.NODisresponsible forthefollowing: Formulate policiesandpractices relativetosafety,licensing, operation, maintenance, fuelmanagement, andradiological support.1.7-14July,1991 ProvidethePlantHanagerwiththetechnical andmanagerial

    guidance, direction andsupporttoensurethesafeoperation oftheplant.Providedirection toallotherAEPSCengineering anddesignorganizations onengineering anddesignmatterspertaining totheCookNuclear'Plant.

    HaintainliaisonwiththeAEPSCDirector-gualityAssurance. Implement therequirements oftheAEPSCgAProgram.Haintainknowledge ofthelatestsafety,licensing, andregulatory requirements, codes,standards, andfederalregulations applicable totheoperation ofCookNuclearPlant.Accomplish theprocurement,

    economic, technical, licensing andqualityassurance activities dealingwiththereactorcoreanditsrelatedfuelassemblies andcomponents.

    Preparebidspecifications, evaluatebids,andnegotiate andadminister contracts fortheprocurement ofallnuclearfuelandrelatedcomponents andservices. Haintainaspecialnuclearmaterialaccountability system.Provideanalysestosupportnuclearsteamsupplysystemoperation, including reactorphysics,fueleconomics, fuelmechanical

    behavior, corethermalhydraulic andLOCAandnon-LOCAtransient safetyanalysisandotheranalysisactivities asrequested, furnishplantTechnical Specification changesandotherlicensing work,andparticipate inNRCandNSDRCmeetingsasrequiredbytheseanalyses.

    Performreactorcoreoperation follow-up activities andotherreactorcoretechnical supportactivities asrequested, andarrangeforsupportfromthefuelfabricator, whenneeded.Contractfor,andprovidetechnical supportfor,disposalofbothhighlevelandlowlevelradioactive waste.Coordinate thedevelopment ofneutronics andthermalhydraulic safetycodesandconductsafetyanalyses. ConductstudiesoftheCookNuclearPlantlicensing basestodetermine theoptimalchangestosupportunitoperations atalowerprimarypressureandtemperature. July,1991

    Coordinate NODcomputercodedevelopment, andprovidetheinterface controlforNODwiththeAEPSCInformation SystemDepartment andCookNuclearPlant.ObtainandmaintaintheNRCOperating LicenseandTechnical Specifications fortheCookNuclearPlant.Actasthecommunication linkbetweentheNRC,AEPSC,andtheplantstaff.Performandcoordinate effortsinvolvedingathering information, performing calculations andgenericstudies;preparing

    criteria, reports,andresponses; reviewing itemsaffecting safety;andinterpreting regulations.

    Review,coordinate, andresolveallmatterspertaining tonuclearsafetybetweenCookNuclearPlantandAEPSC.Thisincludes, butisnotlimitedto:thereviewofcertainplantdesignchangestoensurethattherequirements ofIOCFR50.59 aremet;thepreparation ofsafetyevaluations, orreviews,foranydesignated subject;thepreparation ofchangesto,andappropriate interpretation of,theplantTechnical Specification submittals oflicenseamendments; andtheanalysisofplantcompliance withregulatory requirements. Primarycorporate contactformostoralandwrittencommunication withtheNRC.Providesupportinkeyareasofexpertise, suchasnuclearengineering, probabilistic

    analysis, thermohydr aulicanalysis, chemicalengineering, mechanical engineering, electrical engineering, andtechnical writing.Interface withvendorsandotheroutsideorganizations onmattersconnected withthenuclearsteamsupplysystemandotherareasaffecting thesafedesignandoperation ofnuclearplants.Participate, asappropriate, inthereviewofnuclearplantoperating experiences, andrelatethoseexperiences tothedesignandsafeoperation ofCookNuclearPlant.1.7-16July,1991

    'l Review,evaluate, andrespondtoNRCrequestsforinformation andNRCnotifications ofregulatory changesresulting inplantmodifications ornewfacilities. Suchresponses aregenerated inaccordance withappropriate AEPSCAdministrative Procedures. Develop,specify,and/orreviewconceptual nuclearsafetycriteriaforCookNuclearPlantinaccordance withestablished regulations. Thisincludesallinformation contained intheFSAR,aswellasspecialized information suchasenvironmental qualification andseismiccriteria. Reviewandevaluateperformance requirements forsystems,equipment andmaterials forcompliance withspecified safetycriteria. Review,onaconceptual basis,plantreportsandproposedplantsafety-related designchanges,totheextentthattheyarerelatedtotheultimatesafeoperation oftheplant,forcompliance withsafetyregulations, plantTechnical Specifications, theUpdatedFSARdesignbasis,andwithanyotherrequirements underthe'perating License,todetermine ifthereareanyunreviewed safetyquestions asdefinedin10CFR50.59. PerformreviewsofProblemReportsand10CFR21reviewsinaccordance withcorporate requirements. OperatetheActionItemTrackingSystem(AIT)forAEPSCinternalcommitment tracking. Coordinate designchangesfortheCook'uclear Plant,actingasafocalpointwithinAEPSC.Thisprogramprimarily involvesprojectmanagement responsibilities forscheduling andimplementing RequestforChanges(RFCs),andincludesextensive interfacing withengineering, design,construction, andCookNuclearPlant.Provideworking-level coordination withtheInstitute ofNuclearPowerOperations (INPO).Thiseffortincludesproviding AEPSCaccesstoINPOresources, suchasNUCLEARNETWORKandNuclearPlantReliability DataSystem(NPRDS),andeffectively integrating AEPSCandCookNuclearPlanteffortstowardsutilizing INPOrecommendations contained inoperating experience reportstoimproveCookNuclearPlantperformance. 1.7-17July,1991

    Coordinate dailycommunication withtheCookNuclearPlant,provideAEPSCmanagement withadailyplantstatusreport,andmakepresentations toseniormanagement atregularly scheduled construction staffmeetings. Processincomingvendorinformation. Coordinate operations withinAEPSCthatsupporttheCookNuclearPlantFacilityDataBase(FDB).Contribute totheannualFSARupdatesthroughreviewsofLicenseeEventReports,designchangesandtheAnnualOperating Report.Radiological, emergency andsecurityplanning. Corporate supportoftheCookNuclearPlant'sradiation protection andhealthphysicsprogram,technical serviceandadviceontheradiological aspectsofdesignchanges,modifications orcapitalimprovements, theALARAprogram,theradiation monitoring system,theenvironmental radiological monitoring andsamplingprogram,doseandshielding

    analysis, radiochemistry review,andmeteorological monitoring.

    CookNuclearPlantandcorporate emergency

    planning, including procedure development, exercisescheduling, facilityprocurement andmaintenance, andtheliaisonwithoff-siteemergency planninggroups,suchasFEHAandtheMichiganStatePolice.Reviewfederal,codesandregulations astheyrelatetothedevelopment, implementation, revisionanddistribution oftheHodifiedAmendedSecurityPlan(HASP).Interface withtheplant'ssecuritydepartment providing supportforthesecurityplan,reviewing securityfacilities, maintaining securitydocumentfiles,anddeveloping theemployeefitnessforduty/background screening program.ProvideNuclearGeneralEmployeeTraining(NGET)forAEPSCpersonnel.

    Coordinate thedevelopment oftrainingforAEPSCpersonnel whosupporttheoperation andmaintenance ofCookNuclearPlant,ensuringaunifiedtrainingprogrammeetingannualgoalsandobjectives. Participate onALARAsubcommittees. 1.7-18July,1991

    Prepareresponses totheNRConradiological, emergency planningandsecurityissues.Serveastechnical advisorsonplantaudits.Remaincognizant ofcurrentdecommissioning practices anddevelopments. AEPSCEnineerinandDesinTheAEPSCSeniorVicePresident andChiefEngineer, reporting totheAEPSCSeniorExecutive VicePresident -Engineering andConstruction, isresponsible forcertainengineering anddesignfunctions throughtheAEPSCAssistant VicePresident -CivilEngineering, theAEPSCAssi'stant VicePresident -DesignandtheAEPSCAssistant VicePresident -NuclearEngineering. TheAEPSCElectrical Engineering, andSystemPlanningDepartments provideperiodic, technical assistance fortheCookNuclearPlant.Theadministrative andqualityassurance controlsforthisassistance, alongwiththatprovidedbytheCivilEngineering Department, arecontrolled throughdocumented interface agreements withtheAEPSCNuclearEngineering Department. CivilEnineerinDeartmentTheAEPSCAssistant VicePresident -CivilEngineering, reporting totheAEPSCSeniorVicePresident andChiefEngineer, isresponsible fortheCivilEngineering Department. TheCivilEngineering Department (CED)isresponsible forthetechnical aspectsforthefollowing: Nakerecommendations andassistintheformulation ofpoliciesandpractices relatingtothedesignandengineering ofofficeandservicebuildings, miscellaneous structures andmaterialhandlingequipment, andprovidethegeneralsupervision oftheengineering ofsuchfacilities, structures andequipment. 1.7-19July,1991 Reviewtheactivities ofequipment, facilities, buildings andotherstructures attheCookNuclearPlantandapprove,asrequired, alldesignchangesandmodifications, including thepreparation ofspecifications; andprocurement of,andmodifications to,equipment. Providetraininganddevelopment programsnecessary forpersonnel ofthedepartment, (including thecompany's safetyandhealthprogram), whichareconsistent withthewrittenpoliciesofAEPSC.Preparedesigncriteria, engineering standards, conceptual layouts,studiesandprocedures inconjunction withequipment, facilities, buildings andotherstructures attheCookNuclearPlant.Identifycriticalengineering anddesigninput,andensurethatappropriate analysisandreviewsareconducted. Prepare,reviewandapprovespecifications,

    sketches, drawings, designverifications andcalculations, asrequired.

    Provideinputforspecialstudiesandreportswhichmayberequested byotherorganizations orgovernmental agenciessuchastheNRC.Initiateand/orreview,approveandcontrollaboratory andfieldinvestigations andfeasibility studies.Prepareandreviewimprovement requisitions forcapitalandleaseexpenditures. Reviewandevaluateproposals andmakerecommendations fortheawardofpurchaseordersandcontracts. Prepareandadminister equipment, laborandservicecontracts. Providetechnical

    guidance, whenrequested, insupportofactivities attheCookNuclearPlantunderthedepartment's responsibilities.

    Prepareandapprovedesignchangespertaining toCookNuclearPlantinaccordance withtheGPs.Arrangeforoutsideengineering andconsulting assistance, asrequired. 1.7-20July,1991 0 Arbitrate disputeswhicharisebetweenconstruction forcesandoutsidesuppliers ofmaterials andservices. Coordinate consultant's reportswithotherinterfacing engineering organizations. Performshopandfieldinspections onequipment beingfabricated, orinstalled; whichiswithinthescopeofthedepartment's responsibility. Approveinvoicesforoutsideservices. ProvidefieldservicestotheCookNuclearPlant,including theassigning ofpersonnel, asarerequired, duringconstruction, normaloremergency outages,orasrequested. Assistintheplanningandexecution ofmaintenance workonequipment, facilities, buildings andotherstructures. Supervise maintenance andrepairsofallmasonryandconcreteworkatCookNuclearPlant,including supplying trainedinspection personnel. 'irecttestingofmaterials usedinconcreteandtestingofsoilstobeusedinworkattheCookNuclearPlant.Reviewandrecommend concretemixformulations forallnewconstruction. Preparesitestudies.Implement acorrective actionsystem,withregardtoallactivities ofthedepartment affecting qualityofsafety-related .items,thatwillcontrolanddocumentallitems,servicesoractivities whichdonotconformtorequirements. Oirectthereviewof,andresponseto,assignedcorrective actions.Assistinthepreparation ofapplications forfederal,stateandlocalpermitsrelativetoinstallations beingmadewhi'chrequiresuchpermits.1.7-21July,1991 0 Conductperiodicmanagement reviewsoftheactivities of.thedepartment toensurecompliance withtheobjectives ofthegAProgram,andexternaltechnical surveillance, asnecessary, ofconsultants, outsideorganizations andvendorsoverwhichthedepartment iscognizant. Establish andmaintainapermanent fileforgArecords.DesinDeartmentTheAEPSCAssistant VicePresident -Design,reporting totheAEPSCSeniorVicePresident andChiefEngineer, isresponsible fortheDesignDepartment. TheDesignDepartment isresponsible forthefollowing: Develop,reviewandapprovedesignsanddrawingsformechanical, electrical andstructural systems,equipment andfacilities oftheCookNuclearPlant.Initiate, develop,approveandmaintaindesignprocedures, specifications, standards, criteriaandguidelines. Performrequiredcalculations andanalyses, including pipestress,pipesupportdesign,cablesizing,conduitandcabletraysupportandstructural steelandconcrete. Initiateanddevelopdesignchangesintheareasofresponsibility oftheDesignDepartment. ProvideNRCresponses, asrequired. Assistfieldpersonnel intheresolution ofproblemsstemmingfromtheinstallation ofdesignchanges,orfromas-foundplantconditions, including assigning designpersonnel tothefield.Participate, asassigned, ontheNSDRCandNSORCsubcommittees, andparticipate inmatterscoveredinthecommittee's charter.Participate intheevaluation andremedyofanysituation requiring activation oftheemergency responseorganization, including resourceallocation. Formulate, administer, andimplement policiesandpractices relatingtothedesignoftheCookNuclearPlant.1.7-22July,1991

    Directthedevelopment, maintenance, procedural reviewandimplementation bywhichtheDesignDepartment adherestothegAProgramelementsasestablished byAEPSCGeneralProcedures. Conductfunctions ofthedepartment soastobeinconformance withtheoperating licensesoftheCookNuclearPlant.Investigate andevaluateproblems. Coordinate specialprojectsandstudies,asrequired. Establish andmaintainfilesofdesigndocuments forrecordpurposes. Coordinate thedevelopment andmaintenance ofthecomputerized DesignDrawingControl(DDC)andtheVendorDrawingControl(VDC)programswhichincludecoordinating theprogramswithinterfacing divisions/departments. Controltheissuanceanddistribution ofdrawingsfortheCookNuclearPlant,including monitoring oftheApertureCardMicrofilm Program.Supervise andcontroltheworkofconsultants, architect/engineers andoutsidedesignagenciessupplying servicestoAEPSCintheirdiscipline andprocessnotification ofdefectsinaccordance withcompanyrequirements. Alsoperformdetailedreviewsofdesignworksubmitted byoutsideagencies. Provideinputtothelistofmajorapprovedmaterials, andmaintaincurrentspecifications usedwithinthegroup'sscopeofresponsibility. Provideengineering anddesignsupporttoNOD.Reviewandupdateapplicable sectionsofCookNuclearPlantUpdatedFSARasassigned. Participate oncommittees thatreviewnuclearactivities asmembers,whenassigned. Coordinate andresolvedesigncommentsmadebyinterfacing departments/divisions. Prepare,review,approveandadminister designspecifications andpurchasedocuments fordesignservicesand/ormaterials. 1.7-23July,1991

    NuclearnineerinDeartmentTheAEPSCAssistant VicePresident -NuclearEngineering, reporting totheAEPSCSeniorVicePresident andChiefEngineer, isresponsible fortheNuclearEngineering Department. TheNuclearEngineering Department (NED)isresponsible forthefollowing: Provideplanningandengineering, inconjunction withotherspecialists,

    sections, anddivisions, oftheelectrical facilities insideCookNuclearPlantuptothehighvoltage(HV)bushingsofthemaingenerator transformers andmechanical facilities insideCookNuclearPlantincluding:

    determination ofgenerallayoutanddesign;selection ofequipment; preparation ofone-lineandflowdiagrams; and,coordination ofinsideandoutsideplantfacilities. Provideengineering anddesignofallcontrolsforoperation andprotection ofnuclearsteamsupply,steamgenerator, turbinegenerator, auxiliary equipment andgeneralplantprotection, including checkingandapproving elementary, one-line, andflowdrawings. Interface withotherorganizations toensurethatallpurchased equipment conformstoacceptedstandards andfulfillsthedesiredfunction. Closelyfollowmanufacturer's engineering anddesignprocesses toassureprovision ofadequateandreliableequipment uponwhichdependthesafety,reliability, economy,andperformance oftheunitandplant.Preparecostestimates andimprovement requisitions forplantfacilities, including reviewofimprovement requisitions andcostestimates preparedbyothers.1.7-24July,1991 h Prepareand/orapprovespecifications andpurchaserequisitions, andperformdrawingreviewofequipment, asappropriate. Reviewandapproveprocedures, correspondence, RequestsforDesignChangesormodifications, asappropriate. Obtain,reviewandperformengineering evaluations, including environmental equipment qualification (Eg).Performcalculations forproperapplication ofequipment. Performandevaluateeconomicstudies,investigations, analysesandreportsforfacilities pertaining tothedesign,operation andmaintenance oftheCookNuclearPlant.Assistfieldpersonnel ininstallation, start-up, andsubsequent locatingofproblemsinequipment, andindetermining properoperation ofequipment duringnormal,orafter,emergency operations. Haintainaconstantawareness forimprovements andmorereliabledesignofequipment andfacilities, maintenance andoperating methodsorprocedures. Haintainaconstantawareness ofactivities toensurecompliance withallapplicable policiesandprocedures, initiating, whenrequired, trainingorretraining programs. Participate, asassigned, ontheNSDRCandNSDRCsubcommittees, andparticipate inmatterscoveredinthecommittee's charter.Provideresponses toNRCcorrespondence, asrequired. Participate intheevaluation andremedyofanysituation requiring activation oftheemergency responseorganization. Providetechnical engineering supportinareasofoperation andmaintenance, including: theInservice Inspection (ISI)Program;thegAProgram;theFireProtection gAProgram;theAEPALARAProgramcoveringradiation protection; and,thecorporate andplantIndustrial Safetyprogram:Provideengineering supporttotheAEPSCNOD.Providetechnical direction andassistance totheAEPSCDesignDivisioninthelayoutandarrangement ofequipment piping,systems,controls, etc.,forthedevelopment ofdrawings. 1.7-25July,1991 Initiateanddevelopdesignchangesinareasofresponsibility oftheNED.DevelopSystemDescriptions. Providesupportpersonnel fortheemergency responseorganization. Provideanalytical supportinengineering disciplines (e.g.,heattransfer, thermodynamics, fluiddynamics). Provideengineering evaluations forPRs,LERs,INPOSOERs,andNRCBulletins. Participate, asassigned, ontheAEPSCProblemAssessment Group(PAG).Pro'ectManaementandConstruction DeartmentTheAEPSCVicePresident -ProjectManagement andConstruction, reporting totheAEPSCSeniorExecutive VicePresident -Engineering andConstruction, isresponsible fortheProjectManagement andConstruction Department. Reporting totheAEPSCVicePresident -ProjectManagement andConstruction arethefollowing: SiteConstruction Manager,reporting administratively totheAEPSCVicePresident -ProjectManagement andConstruction, andfunctionally totheCookNuclearPlant,PlantManager.TheProjectHanagement andConstruction Department isresponsible forthefollowing: Administer andimplement construction jobordersissuedbytheCookNuclearPlantorganization formajormodifications, replacement andmaintenance workwithoutsidecontractors. Administer andmonitorcontractor's industrial safetyVprogramsandperformance. Administer humanresources'unctions forsiteconstruction organization. 1.7-26July,1991

    Manageconstruction laborrelations withtheInternational BuildingandConstruction Trades'nions. Scope,bid,recommend awardsandadminister construction laborandservicescontracts. Plan,organizeandcontrolmajorconstruction

    projects, asassignedbytheAEPSCSeniorExecutive VicePresident-Engineering andConstruction.

    Maintaincognizance onmatterspertaining totheCookNuclearPlantandcorporate emergency responseorganization. Prepareofconstruction laborestimates. Provideconstructability guidancewhenrequested insupportofengineering anddesignchanges.Participate ontheNuclearSafetyDesignReviewCommittee. Purchasin andStoresDeartment(notcharted)TheAEPSCExecutive VicePresident -Operations, reporting totheAEPSCt~President andChiefExecutive Officer,isresponsible forthePurchasing andStoresDepartment throughtheAEPSCVicePresident -Purchasing andMaterials Management. ThePurchasing andStoresDepartment isresponsible forthefollowing: Procurement of"N"itemsfromonlyqualified andapprovedsuppliers. Providesupervision toCookNuclearPlantPurchasing Section.Provideorderingandstockingdescriptions of"N"itemsandincludethesedescriptions intheCookNuclearPlantinventory catalog,including necessary communications withsuppliers, cognizant engineers, theCookNuclearPlantStoresSupervisor andotherappropriate personnel. 1.7-27July,1991 Coordinate procurement activities withAEPSCNuclearOperations, AEPSCengineering anddesigndivisions/departments, CookPlantSitePurchasing Section,theAEPSCgADandCookNuclearPlantpersonnel. Prepareandissuerequestsforquotations, contracts, serviceordersandpurchaseordersfor"N"items.Establish asystemtoimplement corrective actionasdescribed in'theAEPSCGeneralProcedures fortheCookNuclearPlant.Establish asystemofdocumentkeepingandtransmittal. Establish asystemofdocumentcontrolforcontrolled procedures, instructions, andpurchasing documents for"N"items.Themaintenance andcontrolofselectedstandardprocurement documentphrasesasidentified bytheDirector-gualityAssurance, ordesignee. Conducttrainingsessionsinvolving purchasing personnel andothersonanannualbasis,ormorefrequently, asrequired, andascertain thattrainingsessionsincludecompleteresponsibilities associated withthepurchaseofsafety-related items.1.7.1.2.6OraniationCookNuclearPlantThePlantManagerreportsfunctionally andadministratively totheAEPSCVicePresident -NuclearOperations (ManagerofNuclearOperations) andisresponsible fortheCookNuclearPlantactivities. Reporting tothePlantManagerarethefollowing (Figure1.7-5):Assistant PlantManager-Production Assistant PlantManager-Technical SupportAssistant PlantManager-ProjectsLicensing ActivityCoordinator SafetyandAssessment Superintendent 1.7-28July,1991 Radiation Protection Manager(reportsfunctionally tothePlantManager)NuclearSecurityManager(reportsfunctionally tothePlantHanager)TheCookNuclearPlantorganization, underthePlantManager,isresponsible forthefollowing: Ensurethesafetyofallfacilityemployees andthegeneralpublicrelativetogeneralplantsafety,aswellasradiological safety,bymaintaining strictcompliance withplantTechnical Specifications, procedures andinstructions. Recommend facilityengineering modification andinitiateandapproveplantimprovement requisitions. Ensurethatworkpractices inallplantdepartments areconsistent withregulatory standards, safety,approvedprocedures, andplantTechnical Specifications. Providemembership, asrequired, onthePNSRC.Maintaincloseworkingrelationships withtheNRC,aswellaslocal,state,andfederalgovernment regulatory officials regarding conditions whichcouldaffect,orareaffected, byCookNuclearPlantactivities. Setupplantloadschedules andarrangeforequipment outages.Developandefficiently implement allsitecentralized trainingactivities. Administer the-centralized facilitytrainingcomplex,simulator, andprogramsensuringthatprogramdevelopment isconsistent withthesystematic approachtotraining, maintainINPOaccreditations, regulatory andcorporate requirements. Ensurethathumanresourceactivities includeemployeesupportprograms(i.e.,fitnessforduty)consistent withINPO/NUHARC guidelines, companypolicies, andregulatory requirements andstandards. Administer theNRCapprovedphysicalSecurityProgramincompliance withregulatory standards, ModifiedAmendedSecurityPlan(HASP),andcompanypolicy.1.7-29July,1991

    Supervise, plan,anddirecttheactivities relatedtothemaintenance andinstallation ofallCookNuclearPlantequipment, structures, grounds,andyards.Prepareandmaintainrecordsandreportspertinent toequipment maintenance andregulatory agencyrequirements. Administer. contracts andscheduleoutsidecontractors'ork forces.Enforceandcoordinate CookNuclearPlantregulations, procedures,

    policies, andobjectives toassuresafety,efficiency, andcontinuity intheoperation oftheCookNuclearPlantwithinthelimitsoftheoperating licenseandtheTechnical Specifications andformulation ofrelatedpoliciesandprocedures.

    Plan,schedule, anddirectactivities relatingtotheoperation oftheCookNuclearPlantandassociated switchyards; cooperate inplanningandscheduling ofworkandprocedures forrefueling andmaintenance oftheCookNuclearPlant;anddirectandcoordinate fuelloadingoperations. Reviewreportsandrecords,directgeneralinspection ofoperating conditions ofplantequipment, andinvestigate anyabnormalconditions, makingrecommendations forrepairs.Establish andadminister equipment clearance procedures consistent withcompany,plant,andradiation protection standards; authorize andarrangeforequipment outagestomeetnormaloremergency conditions. Providetheshiftoperating'rews withappropriate procedures andinstructions toassisttheminoperating theCookNuclearPlantsafelyandefficiently. Approveoperatortrainingprogramsadministered bytheCookNuclearPlantTrainingDepartment designedtoprovideoperating personnel withtheknowledge andskillrequiredforsafeoperation ofthefacility, andforobtaining andholdingNRCoperator.licenses. Coordinate trainingprogramsinplantsafetyandemergency procedures forCookNuclearPlantOperating Department personnel toensurethateachshiftgroupwillfunctionproperlyintheeventofinjuryofpersonnel, fire,nuclearincident, orcivildisorder. 1.7-30July,1991 Advanceplanningandoverallconductofscheduled andforcedoutages,including thescheduling andcoordination ofallplantactivities associated withrefueling, preventive maintenance, corrective maintenance, equipment

    overhaul, Technical Specification surveillance, anddesignchangeinstallations.

    Coordinate al.lCookNuclearPlantactivities associated withtheinitiation, review,approval, engineering, design,production, examination, inspection, test,turnover, andcloseoutofdesignchanges.Developandimplement aneffective QualityControl(QC)Program.Thisencompasses, butisnotlimitedto,theplanninganddirecting ofqualitycontrolactivities toassurethatindustrycodes,NRCregulations, andcompanyinstructions andpoliciesregarding qualitycontrolforCookNuclear'lant areimplemented, qualified personnel performthework,andthattheseactivities are(*properlydocumented. Preparereportsofreportable eventswhicharemandatedbytheNRCandtheTechnical Specifications. Directtheactivities ofcontractor QC/nondestructive examination (NDE)personnel assignedtotheSafetyandAssessment Department andprovideinspections ofworkperformed. Preparestatistical reportsutilizedinNRCAppraisal HeetingsandEnforcement Conference. Coordinate theeffortsofoutsideagencies, suchasAmerican,(*NuclearInsurers(ANI),INPO,andthird-party inspector programs. (*Haintainknowledge ofdevelopments andchangesinNRCrequirements, industrystandards andcodes,regulatory compliance activities, andqualitycontroldisciplines andtechniques. Stopplantoperationintheeventthatconditions arefoundwhichareinviolation oftheTechnical Specifications oradversetoquality.Haintainandrenewaccreditation oftrainingprograms. 1.7-31July,1991 'l gualification andcertification ofI&Hpersonnel performing inspections ortestsofmajormodifications andnon-routine maintenance totherequirements ofRegulatory Guide1.58andANSIN45.2.6,exceptasnotedinAppendixBhereto,item9.gualification andcertification ofI&HNDEpersonnel totherequirements .oftheAEPNDEManual.gualification ofI&Hpersonnel performing inspection ofnormaloperating activities to'NSIN18.1.Propercertification ofcontractor inspection, testandexamination personnel inaccordance withRegulatory Guide'.58, ANSIN45.2.6,ASHEB&PVCodeand/orSNT-TC-IA, asapplicable. Performpeerinspections ofworkcompleted byI&Hpersonnel byindependent personsqualified toANSIN18.7.ConductoftheInservice Inspection (ISI)Program.Procurement, receiving, qualitycontrolreceiptinspection, storage,handling, issue,stocklevelmaintenance, andoverallcontrolofstoresitems.Providematerialserviceandsupportinaccordance withpoliciesandprocedures requiredbyAEPPurchasing andStores,AEPSCgA,andtheNRC,whichareadministered andenforcedinatotalefforttoensuresafetyandplantreliability. Plananddirectengineering andtechnical studies,nuclearfuelmanagement, equipment performance, instrument andcontrolmainte-nance,on-sitecomputersystems,Shift'Technical

    Advisors, andemergency planningfortheCookNuclearPlant.Theseactivities supportdailyon-siteoperations inasafe,reliable, andefficient mannerinaccordance withallcorporate
    policies, applicable laws,regulations,
    licenses, andTechnical Specification requirements.

    Implement stationperformance testingandmonitorprogramstoensureoptimumplantefficiency. Directprogramsrelatedtoon-sitefuelmanagement andreactorcorephysicstesting,andensuresatisfactory completion. Establish testingandpreventive maintenance programsrelatedtostationinstrumentation, electrical systems,andcomputers. 1.7-32July,1991

    Recommend alternatives toCookNuclearPlantoperation, .technical oremergency procedures, anddesignofequipment toimprovesafetyofoperations andoverallplantefficiency. Implement thecorporate Emergency PlanasitpertainstotheCookNuclearPlantsite.Providetechnical andengineering servicesinthefieldsofchemistry; radiation protection, ALARA,andenvironmental insupportofthesafeoperation oftheplantandthehealthandsafetyoftheemployees andthepublic.Planandscheduletheactivities oftheTechnical PhysicalScienceSectionsoftheCookNuclearPlantinsupportofoperations andmaintenance. Establish chemistry, radiochemistry, andhealthphysicscriteriawhichensuremaximumequipment life,andtheprotection ofthehealthandsafetyoftheworkersandthepublic.Establish samplingandanalysisprograms'hich ensurethechemistry, radiochemistry, andhealthphysicscriteriaarewithintheestablished criteria. Establish anddirectinvestigations, responses, andcorrective actionswhenoutsidetheestablished criteria. Administer anddirecttheCookNuclearPlant'sradioactive waste.programs, including volumereduction, packaging andshipping. Administration oftheQARecordsProgram.MaintaintheCookNuclearPlantFacilityDataBase.1.7.2QUALITYASSURANCE PROGRAM1.7.2.1SCOPEPoliciesthatdefineandestablish theCookNuclearPlantQAProgramaresummarized intheindividual sectionsofthisdocument. Theprogramisimplemented throughprocedures andinstructions responsive toprovisions oftheQAPD,andwillbecarriedoutforthelifeoftheCookNuclearPlant.1.7-33July,1991 Qualityassurance controlsapplytoactivities affecting thequalityofsafety-related structures, systemsandcomponents toanextentbasedontheimportanceof thosestructures, systems,components, etc.,(items)tosafety.Suchactivities areperformed undercontrolled conditions, including theuseofappropriate equipment, environmental conditions, assignment ofqualified personnel, andassurance thatallapplicable prerequisites havebeenmet.Safety-related itemsaredefinedasitems:Whichareassociated withthesafeshutdown(hot)ofthereactor;orisolation ofthereactor;ormaintenance oftheintegrity ofthereactorcoolantsystempressureboundary. ORWhosefailuremightcauseorincreasetheseverityofadesignbasisaccidentasdescribed intheUpdatedFSAR;orleadtoareleaseofradioactivity inexcessof10CFR100guidelines. Ingeneral,itemsareclassified assafety-related iftheyare:SeismicClassI,orElectrical ClasslE;orassociated withtheEngineered SafetyFeaturesActuation System(ESFAS);orassociated withtheReactorProtection System(RPS).AspecialQAProgramhasbeenimplemented forFireProtection items(Section1.7.19herein).TheQAProgramalsoincludesprovision forRadwasteQAinaccordance withtherequirements of10CFR71,partH.QAProgramstatus,scope,adequacy, andcompliance withlOCFR50,AppendixB,areregularly reviewedbyAEPSCmanagement throughreports,meetings, andreviewofauditresults.1.7-34July,1991

    Theimplementation ofthegAProgrammaybeaccomplished byAEPSCand/orIndianaHichiganPowerCompanyordelegated inwholeorinparttootherAEPSystemcompanies oroutsideparties.However,AEPSCand/orIndianaHichiganPowerCompanyretainfullresponsibility forallactivities affecting safety-related items.Theperformance ofthedelegated organization isevaluated byauditorsurveillances onafrequency commensurate withtheirscopeandimportance ofassignedwork.1.7.2.2IHPLEHENTATION 1.7.2.2.1 The'Chief Executive OfficerofAEPSChasstatedinasigned,formal"Statement ofPolicy",thatitisthecorporate pol,icytocomplywiththeprovisions ofapplicable codes,standards andregulations pertaining toqualityassurance fornuclearpowerplantsasrequiredbytheCookNuclearPlantoperating licenses. Thestatement makesthisgAPDandtheassociated implementing procedures andinstructions mandatory, andrequirescompliance byallresponsible organizations andindividuals. Thestatement alsoidentifies themanagement positions withinthecompanies vestedwithresponsibility andauthority forimplementing theprogramandassuringitseffectiveness. 1.7.2.2.2 ThegAProgramatAEPSCandtheCookNuclearPlantconsistofcontrolsexercised byorganizations responsible forattaining qualityobjectives, andbyorganizations responsible forassurance functions. ThegAProgrameffectiveness iscontinually assessedthroughmanagement reviewofvariousreports,NSDRCreviewofthegAauditprogram,andshallalsobeperiodically reviewedbyindependent outsidepartiesasdeemednecessary bymanagement. ThegAProgramdescribed inthisgAPDisintendedtoapplyforthelifeoftheCookNuclearPlant.1.7-35July,1991

    ThegAProgramappliestoactivities affecting thequalityofsafety-relatedstructures, components, andrelatedconsumables duringplantoperation, maintenance, testing,andalldesignchanges.Safety-related structures, systemsandcomponents areidentified intheFacilityDataBaseandotherdocuments whicharedeveloped andmaintained fortheplant.Asdeemednecessary bytheAEPSCDirector-gualityAssurance, orthePlantManager,'pplicable portionsofthegAProgramcontrolswillbeappliedtononsafety-related activities associated withtheimplementa-tionofthegAProgramtoensurethatcommitments aremet(e.g.,off-siterecordsstorage,trainingservices, etc.).1.7.2.2.3 ThisgAPD,organized topresentthegAProgramfortheCookNuclearPlantintheorderofthe18criteriaof10CFR50,Appendix8,statesAEPSCpolicyforeachofthecriteria, anddescribes howthecontrolspertinent toeacharecarriedout.AnychangesmadetothisgAPDthatdonotreducethecommitments previously acceptedbytheNRCmustbesubmitted totheNRCatleastannually. AnychangesmadetothisgAPDthatdoreducethecommitments previously acceptedbytheNRCmustbesubmitted totheNRCandreceiveNRCapprovalpriortoimplementation. Thesubmittal ofthechangesdescribed aboveshallbemadeinaccordance withtherequirements of10CFR50.54. Theprogramdescribed inthisgAPDwillnotbeintentionally changedinanywaythatwouldpreventitfrommeetingthecriteriaof10CFR50,AppendixB,andotherapplicable operating licenserequirements. 1.7.2.2.4 Documents usedforimplementing theprovisions ofthisgAPDincludethefollowing: 1.7-36July,1991 PlantManagerInstructions (PMIs)establish thepolicyattheplantforcompliance withspecified

    criteria, andassignresponsibility tothevariousdepartments, asrequired, forimplementation.

    Whennecessary, Department HeadProcedures (OHPs),andinsomecasesDepartment HeadInstructions (DHIs),havebeenpreparedtodescribethedetailedactivities requiredtosupportsafeandeffective plantoperation asperthePMIs.ThePMIsarereviewedbyAEPSCgAforconcurrence thattheywillsatisfactorily implement regulatory requirements andcommitments. TheyarethenreviewedbythePNSRCpriortoapprovalbythePlantManager.Safety-related DHPsandDHIsarereviewedbythedepartment headoforigination, PNSRCandPlantManagerpriortouse.AEPSCGeneralProcedures (GPs)areutilizedtodefinecorporate policiesandrequirements forqualityassurance, andtoimplement certaincorporate gAProgramrequirements. AEPSCdivision/department and/orsectionprocedures arealsousedtoimplement gAProgramrequirements. GPsmayalsobeusedtodefinepolicieswhicharenonprocedural innature.NuclearEngineering Procedures (NEPs)establish thepolicyinAEPSCNuclearEngineering Department forcompliance withtheAEPSCGPsandassignresponsibility toNEDpersonnel, asrequired, forimplementation. NuclearEngineering SectionProcedures (NESPs)areissuedtosatisfyaspecialized GPrequirement. TheNEPsincludeaprocedure forthedevelopment andmaintenance ofprocedures. Thisprocedure containthereviewsand'approvals necessary tosatisfactorily implement regulatory requirements andcommitments. 1.7-37July,1991

    Otherprocedures usedatAEPSCtoimplement QAProgramrequirements includeNuclearDesignProcedures (NDPs),NuclearOperations Department Procedures (NODs),andtheCivilEngineering Organization andProcedures Hanual.Whencontractors performworkon-siteundertheirownqualityassurance

    programs, theprogramsareauditedforcompliance andconsistency withtheapplicable requirements oftheCookNuclearPlant'sQAProgramandthecontract, andareapprovedbyAEPSCQApriortothestartofwork.Implementation ofon-sitecontractor's QAprograms, willbeauditedtoassurethatthecontractor's programsareeffective.

    1.7.2.2.5 Provisions oftheQAProgramfortheCookNuclearPlantapplytoactivities affecting thequalityofsafety'-related items.AppendixAtothisQAPDliststheRegulatory/Safety GuidesandANSIStandards thatidentifyAEPSC'scommitment. AppendixBdescribes necessary exceptions andclarifications totherequirements ofthosedocuments. Thescopeoftheprogram,andtheextenttowhichitscontrolsareapplied,areestablished asfollows:a)AEPSCusesthecriteriaspecified intheCookNuclearPlantUpdatedFSARforidentifying structures, systemsandcomponents towhichtheQAProgramapplies.b)Thisidentification processresultsintheFacilityDataBasefortheCookNuclearPlant.ThisFacilityDataBaseiscontrolled byauthorized personnel. FacilityDataBaseitemsaredetermined byengineering analysisofthefunction(s) ofplantitemsinrelationtosafeoperation andshutdown. 1.7-38July,1991

    c)Theext'enttowhichcontrolsspecified inthegAProgramareappliedtoFacilityOataBaseitemsisdetermined foreachitemconsidering itsrelativeimportance tosafety.Suchdeterminations arebasedondatainsuchdocuments astheCookNuclearPlantTechnical Specifications andtheUpdatedFSAR.1.7.2.2.6 Activities affecting safety-related itemsareaccomplished undercontrolled conditions. Preparations forsuchactivities includeconsideration ofthefollowing: a)b)c)d)e)f)g)h)Assignedpersonnel arequalified. Workhasbeenplannedtoapplicable engineering and/orTechnical Specifications. Specified equipment and/ortoolsareavailable. Itemsareinanacceptable status.Itemsonwhichworkistobeperformed areinthepropercondition forthetask.Properinstructions/procedures fortheworkareavailable foruse.Itemsandfacilities thatcouldbedamagedbytheworkhavebeenprotected, asrequired. Provisions havebeenmadeforspecialcontrols, processes, testsandverification methods.1.7.2.2.7 Responsibility andauthority forplanningandimplementing indoctrination andtrainingofAEPSCandCookNuclearPlantstaffpersonnel arespecifically designated, asfollows:a)Thetrainingandindoctrination programprovidesforon-goingtrainingandperiodicfamiliarization withthegAProgramfortheCookNuclearPlant.1.7-39July,1991 b)Personnel whoperforminspection andexamination functions arequalified inaccordance withrequirements ofRegulatory Guide1.8,ANSIN18.1,Regulatory Guide1.58,ANSIN45.2.6,theASNEBKPVCode,orSNT-TC-IA, asapplicable, andwithexceptions asnotedinAppendixBhereto.c)AEPSCgADauditorsarequalified inaccordance withRegulatory Guide1.146andANSIN45.2.23. d)Personnel assigneddutiessuchasspecialcleaningprocesses, welding,etc.,arequalified inaccordance withapplicable codes,standards, regulatory guidesand/orplantprocedures. e)Thetraining, qualification andcertification programincludes, asapplicable, provisions forretraining, reexamination andrecertification toensurethatproficiency ismaintained. f)Training, qualification, andcertification recordsincluding documentation ofobjectives, waivers/exceptions, attendees anddatesofattendance, aremaintained atleastaslongasthepersonnel involvedareperforming activities towhichthetraining, qualification andcertification isrelevant. g)Personnel responsible forperforming activities thataffectsafety-related itemsareinstructed astothepurpose,scopeandimplementation oftheapplicable manuals,instructions andprocedures. Management/supervisory personnel receivefunctional trainingtothelevelnecessary toplan,coordinate andadminister theday-to-day verification activities ofthegAProgramforwhichtheyareresponsible. TrainingofAEPSCandCookNuclearPlantpersonnel isperformed employing thefollowing techniques, asapplicable: 1)onthejoband1.7-40July,1991

    ,formaltrainingadministered bythedepartment orsectionthe.individual worksfor;2)formaltrainingconducted byqualified instructors fromtheCookNuclearPlantTrainingDepartment orotherentities(internal andexternaltotheAEPSystem);and3)formal,INPOaccredited trainingconducted bytheCookNuclearPlantTrainingDepartment. Recordsoftrainingsessionsforsuchtrainingaremaintained. Wherepersonnel qualifications orcertifications arerequired, thesecertifications areperformed onascheduled basis(consistent withtheappropriate codeorstandard). CookNuclearPlantemployees receiveintroductory traininginqualityassurance usuallywithinthefirsttwoweeksofemployment. Inaddition, AEPSCpersonnel receivetrain'ing priortobeingallowedunescorted accesstotheplant.Thistrainingincludesmanagement's policyforimplementation ofthegAProgramthroughPlantManagerandDepartment HeadInstructions andProcedures. Theseinstructions alsoincludeadescription ofthegAProgram,theuseofinstructions andprocedures, personnel requirements forprocedure compliance andthesystemsandcomponents controlled bythegAProgram.1.7.31.7.3.1DESIGNCONTROLSCOPEDesignchangesareaccomplished inaccordance withapproveddesign.Activities todevelopsuchdesignsarecontrolled. Depending onthetypeofdesignchange,theseactivities includedesignandfieldengineering; theperformance ofphysics,seismic,stress,thermal,hydraulic andradiation evaluations; updateoftheFSAR;reviewofaccidentanalyses; thedevelopment andcontrolofassociated computerprograms; studiesofmaterialcompatibility; accessibility forinservice inspection andmaintenance; determination ofqualitystandards; andrequirement forequipment qualification. Thecontrolsapplytopreparation andreviewofdesigndocuments, including thecorrecttranslation ofapplicable regulatory requirements anddesignbasesintodesign,procurement andprocedural documents. 1.7-41July,1991

    1.7.3.2IMPLEMENTATION 1.7.3.2.1 Designchangesarecontrolled byprocedures andinstructions andarereviewedasrequiredby10CFR50.59. Safety-related designchangesareaccomplished byoneoftwoseparateprocesses: MinorModification (HH),orRequestforChange(RFC).Thosethatdonotaltertheintendedfunctionoftheitemandcanbedetermined, byjudgement tohaveaminimaloverallimpactontheitembeingmodifiedmaybeimplemented viatheHMprocess.Allothersafety-relateddesignchanges,thatarenotappropriate forHHprocessing, areimplemented viatheRFCprocess.IncaseswheredesignchangescouldbedeemedtobewithinthescopeofRFCsorMMssolelyduetopossibleinsignificant adverseseismiceffects,thechangemaybeimplemented viathePlantModification (PH)process.1.7.3.2.2 ~~~~RFCs(exceptthoserequiring emergency processing), HHsandPHs(havingonlyinsignificant seismiceffectonsafetyitems)arereviewedandapprovedpriortoimplementation, asaminimum,bythecognizant AEPSCengineering section,PNSRC,andPlantManager.RFCsandMHsarereviewedtodetermine theirimpactonnuclearsafetyandtodetermine iftheproposedchangesinvolveanunreviewed safetyquestionasdefinedby10CFR50.59. Ifadesignchangeweretoinvolveanunreviewed safetyquestion, itwouldnotbeapprovedforimplementation untiltherequiredNRC'approval wasreceived. 1.7-42July,1991 0 1.7.3.2.3 ~~~~ForRFCs,theChangeControlBoardestablished withinAEPSCprovidesanadditional reviewandapprovallevel.TheChangeControlBoardiscomprised ofmembersoftheEngineering, Design,NuclearOperations andgAorganizations withinAEPSC,andissupplemented byotherAEPSCorganizations orindividuals, asrequired. Thecognizant memberoftheChangeControlBoardassignsaleadengineerforeachRFC.Theleadengineerisresponsible forcoordinating theRFCactivities withinAEPSCandmaintaining closeinterface withtheCookNuclearPlantProjectEngineers. 1.7.3.2.4 ProposedRFCswhichrequireemergency processing areoriginated attheplant,reviewedbythePNSRC,andapprovedbythePlantHanager.CookNuclearPlantmanagement thencontactstheAEPSCNOD,andother,AEPSC management, asrequired, describes thechangerequested, andimplements thechangeonlyafterreceiving verbalAEPSCmanagement authorization toproceed.Thesereviewsandapprovals aredocumented andbecomeapartoftheRFCPacket.1.7.3.2.5 WhenRFCsorHHsinvolvedesigninterfaces betweeninternalorexternaldesignorganizations, oracrosstechnical disciplines, theseinterfaces arecontrolled. Procedures areusedforthereview,approval, release,distribution andrevisionofdocuments involving designinterfaces toensurethatstructures, systemsandcomponents arecompatible geometri-callyandfunctionally withprocesses andtheenvironment. Linesofcommunication areestablished forcontrolling theflowofneededdesigninformation acrossdesigninterfaces, including changestothe1.7-43July,1991 information asworkprogresses. Decisions andproblemresolutions involving designinterfaces aremadebytheAEPSCorganization havingresponsibility forengineering direction ofthedesigneffort.1.7.3.2.6 Checksareperformed anddocumented toverifythedimensional accuracyandcompleteness ofdesigndrawingsandspecifications. 1.7.3.2.7 RFCdesigndocumentpackagesareauditedbyAEPSCgAtoassurethatthedocuments havebeenprepared,

    verified, reviewedandapprovedinaccor-dancewithcompanyprocedures.

    1.7.3.2.8 Theextentof,andmethodsfor,designverification aredocumented. Theextentofdesignverification performed isaFunctionoftheimportance oftheitemtosafety,designcomplexity, degreeofstandardization, thestate-of-the-art, andsimilarity withpreviously provendesigns.Hethodsfordesignverification includeevaluation oftheapplicability ofstandardized orpreviously provendesigns,alternate calculations, qualification testinganddesignreviews.Thesemethodsmaybeusedsinglyorincombination, depending ontheneedsforthedesignunderconsideration. Whendesignverification isdonebyevaluating standardized orpreviously provendesigns,theapplicability ofsuchdesignsisconfirmed. Anydifferences fromtheprovendesignaredocumented andevaluated fortheintendedapplication. 1.7-44July,1991 gualification testingofprototypes, components, orfeaturesisusedwhentheabilityofanitemtoperformanessential safetyfunctioncannototherwise beadequately substantiated. Thistestingisperformed beforeplantequipment installation, wherepossible, butalwaysbeforerelianceupontheitemtoperformasafety-related function. gualification testingisperformed underconditions thatsimulatethemostadversedesignconditions, considering allrelevantoperating modes.Testrequirements, procedures andresultsaredocumented. Resultsareevaluated toassurethattestrequirements havebeensatisfied. Designchangesshowntobenecessary throughtestingaremade,andanynecessary retesting orotherverification isperformed. Testconfigurations areclearlydocumented. Designreviewsareperformed bymulti-organizational orinterdisciplinary groups,orbysingleindividuals. Criteriaareestablished todetermine whenaformalgroupreviewisrequired, andwhenreviewbyanindividual issufficient. Procedures requirethatminordesignchangesaccomplished bytheHHprocessalsoreceiveformaldesignverification. Applicable designverification activi'ties shallbecompleted priortodeclaring thedesignchange,orportionthereof,operational. 1.7.3.2.9 Personsrepresenting applicable technical disciplines areassignedtoperformdesignverifications. Thesepersonsarequalified byappropriate education orexperience, butarenotdirectlyresponsible forthedesign.Thedesigner's immediate supervisor mayperformtheverification, providedthat:1.7-45July,1991 4 1)Thesupervisor istheonlytechnically qualified individual. or2)Thesupervisor hasnotspecified asingulardesignapproach, ruledoutdesignconsiderations, norestablished thedesigninputs.and3)Theneedisindividually documented andapprovedinadvancebythesupervisor's management. and4)Regularly scheduled QAauditsverifyconformance topreviousitems1through3.Designverification onsafety-related designchangesshallbecompleted priortodeclaring adesignchange,orportionsthereof,operational. 1.7.3.2.10 CookNuclearPlantimplementation ofdesignchangesisaccomplished bytheCookNuclearPlantProjectEngineering Department. Materialtoperformthedesignchangemustmeetthespecifications established fortheoriginalsystem,orasspecified bytheleadengineer. Forthosedesignchangeswheretestingaftercompletion isrequired, thetestingdocumentation isreviewedbytheorganization performing thetestand,whenspecified, bytheAEPSCleadengineerorothercognizant engineer(s). Further,completed designchangesareauditedbyAEPSCQAfollowing installation andtesting.1.7-46July,1991

    1.7.3.2.11 ~~~~Changestodesigndocuments, including fieldchanges,arereviewed, approvedandcontrolled inamannercommensurate withthatusedfortheoriginaldesign.Suchchangesareevaluated forimpact.Information onapprovedchangesistransmitted toallaffectedorganizations. 1.7.3.2.12 Erroranddeficiencies in,anddeviations from,approveddesigndocuments areidentified anddispositioned inaccordance withestablished designcontroland/orcorrective actionprocedures. 1.7.3.2.13 Established 1)2)3)4)5)6)7)designcontrolprocedures providefor:controlled submission ofdesignchanges,engineering evaluation, reviewforimpactonnuclearsafety,auditbyAEPSCgA,designmodification, AEPSCmanagerial review,andapprovalandrecordkeepingfortheimplemented designchange.1.7.41.7.4.1PROCUREMENT DOCUMENTCONTROLSCOPEProcurement documents definethecharacteristics ofitem(s)tobeprocured, identifyapplicable regulatory andindustrycodes/standards requirements, andspecifysuppliergAProgramrequirements totheextentnecessary toassureadequatequality.1.7-47July,1991 1.7.4.21.7.4.2.1 IHPLEHENTAT IONProcurement controlisestablished byinstructions andprocedures. Thesedocuments requirethatpurchasedocuments besufficiently detailedtoensurethatpurchased materials, components andservicesassociated withsafety-related structures orsystemsare:1)purchased tospecification andcoderequirements equivalent tothoseoftheoriginalequipment orservice(exceptwhentheCodeofFederalRegulations requiresupgrading), 2)properlydocumented toshowcompliance withtheapplicable specifications, codesandstandards, and3)purchased fromvendorsorcontractors whohavebeenevaluated anddeemedqualified, orbythededication planprocess.Procedures establish thereviewofprocurement documents todetermine that:qualityrequirements arecorrectly 'stated,inspectable andcontrollable; thereareadequateacceptance criteria; andprocurement documents havebeenprepared, reviewedandapprovedinaccordance withestablished requirements. Themanageroftheoriginating group,withsupportofthe'ognizant AEPSCengineering group,isresponsible forassuringthatapplicable requirements aresetforthinprocurement documents. TheCookNuclearPlantmayrequestassistance ofAEPSCcognizant engineers inanyprocurement activity. 1.7.4.2.2 TheFacilityDataBase,inconjunction withothersources,isusedforequipment safetyclassification andprocurement grade.AEPSCspecifications areusedtodetermine requirements, codesorstandards thatitemsmustfulfill,anddefinethedocumentation thatmustaccompany theitemtotheplant.1.7-48July,1991

    Procurement documents forsafetyrelateditemsandservicesarereviewedtoensurethat:correctclassification ismade;therequirements areproperlystated;andthatmeasureshavebeen,orwillbe,implemented toassuretherequirements aremetandadequately providedfor.Purchaserequisitions fornewsafetyrelateditemsareinitiated bythecognizant engineering groupwhichestablishes initialrequirements. Replacement/spares arepurchased torequirements equivalent totheoriginalunlessupgrading isrequiredbyFederalRegulations, ordeemednecessary bythecognizant engineering group.I1.7.4.2.3 Thecontentsofprocurement documents varyaccording totheitem(s)beingpurchased anditsfunction(s) intheCookNuclearPlant.Provisions ofthisgAPDareconsidered forapplication toservicecontractors also.Asapplicable, procurement documents include:a)Scopeofworktobeperformed. b)Technical requirements, withapplicable

    drawings, specifications, codesandstandards identified" bytitle,documentnumber,revisionanddate,withanyrequiredprocedures suchasspecialprocessinstructions identified insuchawayastoindicatesourceandneed.Imposition ofguides/standards onAEPSC/I&M suppliers andsubtiersuppliers willbeonacase-by-case basisdepending upon'heitemorservicetobesuppliedanduponthedegreethatAEPSC/IMreliesonsuppliers toinvokeguides/standards.

    AEPSC/I&M recognizes thatcertainsuppliers haveacceptable lOCFR50,AppendixBgAprograms, eventhough,thesuppliers arenotcommitted toRegulatory Guidesorindustrystandards (e.g.ANSIN45.2.6). Inthosecases,inwhichsuppliers arenotcommitted tothesameguides/standards asAEPSC/IQf, AEPSC/INwillassurethat(I)thesupplier's gAprogramprovidesadequategAcontrols, regardless ofthelackofspecificcommitment, or(2)controlswillbeinvokeddirectlybyAEPSC/IEN toassureadequatequalityofproducts/services receivedbysuppliers. 1.7-49July,1991

    c)d)e)g)h)Regulatory, administrative andreporting requirements. gualityrequirements appropriate tothecomplexity andscopeofthework,including necessary testsandinspections. /Arequirement foradocumented gAProgram,subjecttogAreviewandwrittenconcurrence priortothestartofwork.Arequirement forthesuppliertoinvokeapplicable qualityrequirements onsubtiersuppliers. Provisions foraccesstosupplierandsubtiersuppliers'acilities andrecordsforinspections, surveillances andaudits.Identification ofdocumentation tobeprovidedbythesupplier, thescheduleofsubmittals anddocuments requiring AEPSCapproval. 1.7.4.2.4 TheAEPSCgADivisionperformsauditsofprocurement documents toassure,thatgAProgramrequirements havebeenmet.Theseauditsareconducted inaccordance withAEPSCgADivisionprocedures. 1.7.4.2.5 ~~~~Changes,to procurement documents arecontrolled inamannercommensurate withthatusedfortheoriginaldocuments. 1.7.51.7.5.1INSTRUCTIONS, PROCEDURES, ANDDRAWINGSSCOPEActivities affecting thequalityofsafety-related structures, systemsandcomponents areaccomplished usinginstructions, procedures anddrawingsappropriate tothecircumstances, including acceptance criteriafordetermining ifanactivityhasbeensatisfactorily completed. 1.7.5.21.7.5.2.1 IHPLEHENTATION Instructions andprocedures incorporate: 1)adescription ofthe1.7-50July,1991 activitytobeaccomplished, and2)appropriate quantitative (suchastolerances andoperating limits)andqualitative (suchasworkmanship andstandards) acceptance criteriasufficient todetermine thattheactivityhasbeensatisfactorily accomplished. Holdpointsforinspection areestablished whenrequired. Instructions andprocedures pertaining tothespecification of,and/orimplementation of,thegAProgramreceivemultiplereviewsfortechnical adequacyandinclusion ofappropriate qualityrequirements. Toptierinstructions andprocedures arereviewedand/orapprovedbyAEPSCgA.Lowertierdocuments arereviewedandapproved, asaminimum,bymanagement/supervisory personnel trainedtothelevelnecessary toplan,coordinate andadminister thoseday-to-day verification, activities ofthegAProgramforwhichtheyareresponsible. Specialprocedures maybeissuedforactivities whichhaveshort-term applicability. 1.7.5.2.2 ~~~~AEPSCactivities relativetotheCookNuclearPlantareoutlinedbyprocedures whichprovidethecontrolsfortheimplementation oftheseactivities. AEPSChastwocategories ofgAProgramimplementation procedures: 1)GeneralProcedures (GPs)whichareapplicable toallAEPSCdivisions anddepartments involvedwithCookNuclearPlant.2)Division/department/section procedures whichapplytothespecificdivision, department orsectioninvolved. 1.7.5.2.3 Activities attheCookNuclearPlantarecontrolled usingplantprocedures. July,1991 ThePHIshavebeenclassified intothefollowing series:1000Organization andResponsibilities 2000Administration -DocumentControl,Security,

    Training, Records,Radiation Protection andFireProtection 3000Procurement,,Receiving, ShippingandStorage4000Operations, FuelHandling, Surveillance Testing5000Haintenance, Repair,Hodification, SpecialProcesses, EQandISI6000Technical

    -Chemistry, Radiological

    Controls, Performance/Engineering Testing,andInstrument andControlHaintenance andCalibration 7000QualityAssurance, QualityControlProgramandCondition/Problem Reporting Instructions andprocedures identifytheregulatory requirements andcommitments whichpertaintothesubjectthatitwillcontrolandestab-lishresponsibilities forimplementation.

    Instructions andprocedures mayeitherprovidetheguidancenecessary forthedevelopment ofsupplementalinstructions and/orprocedures toimplement theirrequirements, orprovidecomprehensive guidancebasedonthesubjectmatter.1.7,5.2.4 CookNuclearPlantdrawingsareproduced, controlled anddistributed underthecontrolofAEPSCandtheCookNuclearPlant.AEPSCdesigndrawingsareproducedby,orunderthecontrolof,theAEPSCNuclearDe'signGroupunderasetofprocedures whichdirecttheirdevelopment andreview.Theseprocedures specifyrequirements forinclusion ofquantitative andqualitative acceptance criteria. Specificdrawingsarereviewedandapprovedbythecognizant engineering divisions/department. AEPSChasstationed anon-sitedesignstafftoprovidefortherevisionofcertaintypesofdesigndrawingstoreflectas-builtconditions. 1.7-52July,1991 1.7.5.2.5 ~~~~ComplexCookNuclearPlantprocedures aredesignated as"InHand"procedures. Examplesof"InHand"procedures arethosedeveloped forextensive orcomplexjobswhererelianceonmemorycannotbetrusted.Further,thoseprocedures whichdescribeasequencewhichcannotbealtered,orrequirethedocumentation ofdataduringthecourseoftheprocedure, areconsidered. "InHand"procedures aredesignated assuchbydoubleasterisks (**)whichprecedetheprocedure numberonthecoversheet,allpagesandattachments ofaprocedure andthecorresponding index.1.7.6DOCUMENTCONTROL1.7.6.1SCOPEDocuments controlling activities withinthescopedefinedin1.7.2hereinareissuedandchangedaccording toestablished procedures. Documents suchasinstructions, procedures anddrawings, including changesthereto,arereviewedforadequacy, approvedforreleasebyauthorized personnel, andaredistributed andusedatthelocationwhereaprescribed activityisperformed. Changestocontrolled documents arereviewedandapprovedbythesameorganizations thatperformed theoriginalreviewandapproval, orbyotherqualified, responsible organizations specifically designated inaccordance withtheprocedures governing thesedocuments. Obsoleteorsuperseded documents arecontrolled topreventinadvertent use.1.7.6.2INPLENENTAT ION1.7.6.2.1 Controlsareestablished forapproval, issueandchangeofdocuments inthefollowing categories: a)Designdocuments (e.g.,calculations, specifications, analyses) 1.7-53July,1991 b)c)d)e)f)g)Drawingsandrelateddocuments Procurement documents Instructions andprocedures UpdatedFinalSafetyAnalysisReport(UFSAR)PlantTechnical Specifications Safeguards documents 1.7.6.2.2 Thereview,approval, issuanceandchangeofdocuments arecontrolled by:a)Establishment ofcriteriatoensurethatadequatetechnical andqualityrequirements areincorporated. b)Identification oftheorganization responsible forreview,approval, issueandmaintenance. c)Reviewofchangestodocuments bytheorganization thatperformed theinitialreviewandapproval, orbytheorganization designated inaccordance 'withtheprocedure governing thereviewandapprovalofspecifictypesofdocuments. Maintenance, modification andinspection pro'cedures areauditedbyAEPSCgAforcompliance withestablished inspection requirements. 1.7.6.2.3 Documents areissuedandcontrolled sothat:a)Thedocuments areavailable priortocommencing work.b)Obsoletedocuments arereplacedbycurrentdocuments inatimelymanner.1.7-54July,1991 1.7.6.2.4 ~~~~Nasterlists,orequivalent

    controls, areusedtoidentifythecurrentrevisionofinstructions, procedures, specifications anddrawings.

    Thesecontroldocuments areupdatedanddistributed todesignated personnel whoareresponsible formaintaining currentcopiesoftheapplicable documents. Thedistribution ofcontrolled documents isperformed underprocedures requiring receiptacknowledgement andinaccordance withestablished distribution lists.1.7.6.2.5 Intheeventadrawingisdeveloped on-sitetoreflectanas-builtconfiguration, themarked-up drawingismaintained intheHasterPlantFileandallholdersofthedrawingareissuedappropriate notification toinformthemtherevisiontheyholdisnotcurrent,cannotbeusedand,ifrequired, reference mustbemadetotheMasterPlantFiledrawing.1.7.6.2.6 Documents preparedforuseintrainingorforinterested partiesareappropriately markedtoindicatethattheyareforinformational useonlyandcannotbeusedtooperateormaintainthefacility, ortoconductactivities affecting thequalityofsafety-related items.AtCookNuclearPlant,unlessadocumentisidentified as"controlled," itisautomatically assumedthedocumentisforinformational useonly.1.7.71.7.7.1CONTROLOFPURCHASED ITEMSANDSERVICESSCOPE'ctivities thatimplement approvedprocurement requestsforitemsandservicesarecontrolled toassureconformance withprocurement documentrequirements. Controlsincludeasystemofsupplierevaluation andselection audits,acceptance ofitemsanddocumentation upon1.7-55July,1991

    delivery, andperiodicassessment ofsupplierperformance.

    Objective .evidence ofqualitythatdemo'nstrates conformance withspecified procurement documentrequirements isavailable totheCookNuclearPlantsitepriortouseofequipment,

    material, orservices.

    1.7.7.2IHPLEHENTATION 1.7.7.2.1 AEPSCqualifies suppliers anddistributors byperforming adocumented evaluation oftheircapability toprovideitemsorservicesspecified byprocurement documents. Itemsandservicesdesignated assafety-related arepurchased fromsuppliers whoseQAprogramshavebeenaccepted'inaccordance withAEPSCrequirements, orfromcommercial gradesuppliers throughtheAEPSCdedication program.Suppliers ofotheritems/services, suchasfireprotection, recordsstorage,etc.,arealsoevaluated usingdifferent criteriaforacceptance. Qualification ofsuchsuppliers isdetermined bytheAEPSCQADivision. Inthedischarge ofthisresponsibility, theAEPSCQADivisionmayuseinformation generated byotherutilities. Thesupplier, ordistributor, mustbeapprovedbeforeprocurement canbecompleted. AEPSCisamemberoftheNuclearProcurement IssuesCouncil(NUPIC),participates injointsupplieraudits,andsharesauditinformation consistent withNUPICrequirements. Thesupplier, ordistributor, mustbeacceptable, oracceptable subjecttofollow-up, beforeaprocurement canbeapprovedandprocessed. Additional auditswillbeconducted, asnecessary, tomeetrequirements. Acceptance isnotcompleteuntilithasbeendetermined thatthesuppliers'A programcanmeettherequirements fortheitem(s)/service(s) offered.1.7.7.2.2 Foritemsthatarenotuniquetoanuclearpowerplant("Commercial Grade")whererequirements cannotbeimposedinapractical manneratthetimeofprocurement, programsfor'dedication tosafety-related, 1.7-56July,1991

    standards areestablished andaccomplished bytheAEPSCcognizant engineerpriortotheitembeingacceptedforsafety-related use.1.7.7.2.3 In-process auditsofsuppliers'ctivities duringfabrication, inspection, testingandshipmentofitemsareperformed whendeemednecessary, depending uponsupplierqualification status,complexity oftheitem(s)beingfurnished, theitems'mportance tosafety,and/orprevioussupplierhistory.Theseauditsareperformed byAEPSCgA.Thecognizant engineerand/orresponsible CookNuclearPlantpersonnel mayalsoparticipate, ifdeemednecessary. 1.7.7.2.4 Spareandreplacement partsareprocuredinsuchamannerthattheirperformance andqualityareatleastequivalent tothoseofthepartsthatwillbereplaced. a)Specifications andcodesreferenced inprocurement documents forspareorreplacement itemsareatleastequivalent tothosefortheoriginalitemsortoproperlyreviewedandapprovedrevisions. b)Partsintendedassparesorreplacement for"off-the-shelf" items,orotheritemsforwhichqualityrequirements werenotoriginally specified, areevaluated forperformance atleastequivalent totheoriginal. c)Wherequalityrequirements fortheoriginalitemscannotbedeter-mined,requirements andcontrolsareestablished byengineering evaluation performed byqualified individuals. Theevaluation assuresthereisnoadverseeffectoninterfaces, safety,interchangeability, fit,form,function, orcompliance withapplicable regulatory orcoderequirements. Evaluation resultsaredocumented. 1.7-57July,1991

    d)Anyadditional ormodifieddesigncriteria, imposedafter.previous'procurement oftheitem(s),areidentified andincorporated. 1.7.7.2.5 Instructions andprocedures addressrequirements forsupplierselection andcontrol,aswellasprocurement documentcontrol.ThePHIonreceiptinspection ofsafety-related itemsaddresses theprogramforinspection ofincomingitems,including areviewofthedocumentation requiredundertheprocurement. Receiptinspection personnel arequali-fiedandcertified inaccordance withtherequirements ofANSIN45.2.6.Provisions forreceiptinspection applyregardless ofwheretheprocurement originates. Additional inspections mayapplyifrequiredbytheprocurement document. Whereitemsand/orservicesaresafety-related andprocurement isaccomplished withoutassistance ofAEPSC,supplierselection islimitedtothosecompanies identified asbeingqualified. 1.7.7.2.6 Itemsreceivedatthesitearetaggedwitha"HOLD"tagandplacedinadesignated, controlled areauntilreceiptinspected. Duringreceiptinspection, designated materialcharacteristics andattributes arechecked,anddocumentation ischeckedagainsttheprocurement documents. Iffoundacceptable, the"HOLD"tagisremovedandreplacedwithan"ACCEPTED" tagandtheitemisplacedinadesignated areaofthestoreroom. Itemtraceability toprocurement documents andtoenduseismaintained throughrecording of"HOLD"and"ACCEPTED" tagnumbersonapplicable documents. 1.7-58July,1991

    Nonconforming items,ormissingorquestionable documentation resultsinitemsbeingplacedon"HOLD"andmaintained inadesignated, controlled areaofthestoreroom. Ifthenonconformance cannotbecleared,theitemiseitherscrapped, returnedtomanufacturer, ordispositioned throughengineering analysis. F7.7.2.7Contractors providing services(on-site) forsafety-related components arerequiredtohaveeitheraformalqualityassurance programandprocedures, ortheymustabidebytheCookNuclearPlantgAProgramandprocedures. PriortotheirworkingattheCookNuclearPlant,contractor qualityassurance programsmustbeauditedandapprovedbyAEPSCgA.Contractor procedures mustbereviewedandapprovedbytheoriginating/sponsoring department supervisor, PNSRCandthePlantHanager.Further,periodicauditsofsitecontractor activities areconducted underthedirection oftheAEPSCgualityAssurance Superintendent. 1.7.7.2.8 Totheextentprescribed inspecificprocurement documents, suppliers furnish(qualityrecords;documentary evidencethatmaterialandequipment eitherconformstorequirements oridentifies anyrequirements thath'avenotIbeenmet;anddescriptions ofthosenonconformances fromtheprocurement requirements, whichhavebeendispositioned "Use-as-is" or"repair." IThisevidenceisretainedatthePlant,orattheServiceCorporation. Totheextentprescribed inspecificprocurement agreements, suppliers arerequiredtomaintainadditional (backup)documents intheirrecordsystem.1.7-59July,1991 ~I Insomecases,suchaswithNSSS,suppliers aredesignated primaryrecordretention responsibility. 1.7.7.2.9 Thecapability ofsuppliers tofurnishvalidcertificates isevaluated duringprocurement documentreviews,annualsupplierevaluations, andduringaudits.1.7.8IDENTIFICATION ANDCONTROLOFITEMS-1.7.8.1SCOPEItemsareidentified andcontrolled topreventtheirinadvertent use.Identification ofitemsismaintained either'ntheitems,theirstorageareasorcontainers, 'oronrecordstraceable totheitems.1.7.8.21.7.8.2.1 ~~~~IMPLEMENTATION Controlsareestablished thatprovidefortheidentification andcontrolofitems(including partially fabricated assemblies). 1.7.8.2.2 Itemsareidentified byphysically markingtheitemoritscontainer, andbymaintaining recordstraceable totheitem.Themethodofidenti-ficationissuchthatthequalityoftheitemisnotdegraded. 1.7-60,July,1991

    1.7.8.2.3 ~~~~Itemsaretraceable toapplicable

    drawings, specifications, orotherpertinent documents toensurethatonlycorrectandacceptable itemsareused.Verification oftraceability isperformed anddocumented priortoreleaseforfabrication,
    assembly, orinstallation.

    1.7.8.2.4Requirements fortheidentification byuseofheatnumber,partnumber,serialnumber,etc.,areincludedinAEPSCSpecifications (DCCs)and/ortheprocurement document. 1.7.8.2.5 Separatestorageisprovidedforincorrect ordefective itemsthatareonholdandmaterialwhichhasbeenacceptedforuse.Allsafety-relateditemsareappropriately taggedoridentified (stamping, etc.)toprovideeasyidentification astotheitems'sage status.Recordsaremaintained fortheissueofitemstoprovidetraceability fromstoragetoenduseintheCookNuclearPlant.1.7.8.2.6 Whenmaterials aresubdivided, appropriate identification numbersaretransferred toeachsectionofthematerial, ortraceability ismain-tainedthroughdocumentation. 1.7.9CONTROLOFSPECIALPROCESSES 1.7.9.1SCOPE1.7-61July,1991Specialprocesses arecontrolled andaccomplished byqualified personnel usingapprovedprocedures andequipment inaccordance withapplicable codes,standards, specifications, criteriaandotherspecialrequirements. L 1.7.9.21.7.9.2.1 IHPLEHENTATION Processes subjecttospecialprocesscontrolsarethoseforwhichfullverification orcharacterization bydirectinspection isimpossible orimpractical. Suchprocesses includewelding,heattreating, chemicalcleaning, application ofprotective

    coatings, concreteplacement andNDE.1.7.9.2.2 Specialprocessrequirements forchemicalcleaning, application ofprotective coatingsandconcreteplacement aresetforthinAEPSCSpeci-fications (DCCs)and/ordirectives preparedbytheresponsible AEPSCcognizant engineer.

    Thesedocuments arereviewedandapprovedbyotherpersonnel withthenecessary technical competence. AEPSCSpecifications areauditedbytheAEPSCgADivision. Specialprocessrequirements forwelding,heattreatingandNDEaresetforthinAEPSCSpecifications, theAEPWeldingandNDEHanualsandplantprocedures. Thesespecifications andmanualsarepreparedby,orarereviewedandapprovedby,theAEPSCCognizant Engineer-WeldingandNDEAdministrator. Theadministrative controlsportionoftheNDEHanualisauditedbyAEPSCgA.Specialprocessprocedures, withtheexception ofweldingandheattreating, arepreparedbyCookNuclearPlantpersonnel withtechnical knowledge inthediscipline involved. Theseprocedures, whicharealsoreviewedbyotherpersonnel withthenecessary technical competence, arequalified bytesting.1.7-62July,1991Weldingisperformed inaccordance withprocedures contained intheAEPMeldingHanual,orintheapprovedcontractor's manual.Theseprocedures arequalified inaccordance withapplicable codes,andProcedure gualification Recordsareprepared. WeldProcedure gualifi cation.RecordsarereviewedandapprovedbytheAEPSCCognizant Engineer-Welding.Weldqualification documentation isretainedintheAEPWeldingManual,ortheapprovedcontractor's manual.Contractor weldingprocedures arequalified bythecontractor. Theseprocedures andthequalification documentation arereviewedandapprovedbytheAEPSCCognizant Engineer-Welding.Thisdocumentation isretainedbythecontractor. 1.7.9.2.3 NDEpersonnel arequalified andcertified byaCookNuclearPlantNDELevelIIIwhohasbeenqualified andcertified bythedesignated NDEAdministrator. Certification isbyexamination. Personnel qualifi-cationiskeptcurrentbyre-examination attimeintervals specified bytheAEPNDEManual,andinaccordance with'heASHECode.CookNuclearPlantweldersarequalified bytheMaintenance Department utilizing theprocedures intheAEPWeldingManual.Supervision ofCookNuclearPlantwelderqualifications isperformed bytheMaintenance Department. Examination ofspecimens isperformed underthesupervision oftheSafetyandAssessment Department inaccordance withtheAEPWeldingManualcoveringwelderqualification. CookNuclearPlantwelderqualification recordsaremaintained foreachwelderbytheMaintenance Department. Contractor andcraftweldersarequalified bythecontractor usingprocedures approvedbytheAEPSCCognizant Engineer-Weldinginaccordance withAEPSCprocedures. Contractor andcraftwelderqualification recordsaremaintained bythecontractor. 1.7.9.2.4 gC/NDETechnicians assignedtotheSafetyandAssessment Department performnondestructive testingforworkperformed byCookNuclearPlant1.7-63July,1991 0 andcontractor personnel. Theseindividuals arequalified toeitherSNT-TC-IA, orANSIN45.2.6,andrecordsofthequalifications/ certifications aremaintained atCookNuclearPlant.1.7.9.2.5 Forspecialprocesses thatrequirequalified equipment, suchequipment isqualified inaccordance withapplicable codes,standards andspecifications. 1.7.9.2.6 Specialprocessqualifications arereviewedduringregularly scheduled QAaudits.Qualification recordsaremaintained inaccordance with1.7.17herein.1.7.9.2.7 Thedocumentation resulting fromweldingandnondestructive testingisreviewedbyappropriate personnel. 1.7.10INSPECTION 1.7.10.1SCOPEActivities affecting thequalityofsafety-related structures, systemsandcomponents areinspected toverifytheirconformance withrequire-ments.Theseinspections areperformed bypersonnel otherthanthosewhoperformtheactivity. Inspections areperformed byqualified personnel utilizing writtenprocedures whichestablish prerequisites andprovidedocumentation forevaluating testandinspection results.Oirectinspection, processmonitoring, orboth,areusedasnecessary. Whenapplicable, holdpointsareusedtoensurethatinspections areaccomplished atthecorrectpointsinthesequenceofactivities. 1.7-64July,1991 1.7.10,2IMPLEMENTATION 1,7.10.2.1 Inspections areappliedtoappropriate activities toassureconformance tospecified requirements. Holdpointsareprovidedinthesequenceofprocedures toallowfortheinspection, witnessing, examination, measurement, orreviewnecessary toassurethatthecritical, orirreversible, elementsofanactivityarebeingperformed asrequired. Notethatholdpointsmaynotapplytoallprocedures, buteachmustbereviewedforthisattribute. Holdpointsspecifyexactlywhatistobedone(e.g.,typeofinspection orexamination, etc.),acceptance

    criteria, orreference toanotherprocedure, etc.,forthesatisfactory completion oftheholdpoint.Whenincludedinthesequenceofaprocedure, theactivities requiredbyholdpointsarecompleted priortocontinuing workbeyondthatpoint.Processmonitoring isusedinwhole,orinpart,wheredirectinspection aloneisimpractical orinadequate.

    1.7.10.2.2

    Training, qualification andcertification programsforpersonnel whoperforminspections areestablished, implemented anddocumented inaccordance with1.7.2hereinandasdescribed inAppendix8hereto,item9b,withexceptions asnotedtherein.1.7.10.2.3 Inspection requirements arespecified inprocedures, instructions,
    drawings, orchecklists asapplicable.

    Theyprovideforthefollowing, asappropriate: 1.7-65July,1991

    a)Identification ofapplicable revisions ofrequiredinstructions, E.drawingsandspecifications. b)Identification ofcharacteristics andactivities tobeinspected. c)Inspection methods.-d)Specification ofmeasuring andtestequipment havingthenecessary accuracy. e)Identification ofpersonnel responsible forperforming theinspection. f)Acceptance andrejection criteria. g)Recording oftheinspection results'nd theidentification oftheinspector. 1.7.10.2.4 ~~~~Inspections areconducted usingthefollowing programs: a)WorkActivities Performed b18MPersonnel. Workfunctions associated withnormaloperation ofthe'lant, routinemaintenance, calibrations, etc.,areroutinely assignedtoplantpersonnel. IKHpersonnel whoinspectthisworkarequalified inaccordance withRegulatory Guide1.8andANSIN18.1,andareperiodically trainedintheirskillareausingINPO"accredited" training. Asaresultofthequalifications andtrainingwhichIMpersonnel receive,apeerinspection systemisused.Peerinspection personnel areindependent inthattheydonotperform,ordirectlysupervise, theworkbeinginspected, butmaybefromthesameworkgroup.CookNuclearPlantSafetyandAssessment Department personnel qualified inaccordance withRegulatory Guide1.8andANSIN18.1willensure(throughsurveillance) that1.7-66July,1991 inspections havebeencorrectly implemented andmakeroutinereportstomanagement. b)WorkActivities Performed bContractors. Hajormodifications, non-routine maintenance, and/orotherservicesonsafety-related itemsaregenerally performed bycontractors whoarerequiredtocomplywiththeapplicable requirements ofRegulatory Guide1.33andANSIN45.2.Inspections oftheseworkactivities areperformed byinspectors qualified andcertified inaccordance withRegulatory Guide1.58andANSIN45.2.6.Apeerinspection programisnotusedforworkactivities performed bythesepersonnel. Contractor inspection personnel arerequiredtobequalified andcertified inaccordance withRegulatory Guide1.58andANSIN45.2.6.18MCookNuclearPlantgualityControlpersonnel whoarealsoqualified andcertified inaccordance withRegulatory Guide1.58andANSIN45.2.6mayperforminspections and/orsurveillance oftheseactivities. 1.7.10.2.5 ~~~~Inspections associated withthepackaging andshipmentofradioactive wasteandmaterials areconducted usingthefollowing program:a)NRCLicensedPackains-Inspections ofNRClicensedradioactive materialpackagings shallbeperformed byindividuals independent fromtheworkbeingperformed. Theindependent-inspectors shallbeIndianaMichiganPowerpersonnel, qualified inaccordance withRegulatory Guide1.8andANSIN18.1,asaminimum.Additionally, Etheinspector shallbefamiliarwiththeactivities beingperfor'med. b)Non-NRCicensedPackainsandContainers -Inspections ofnon-NRClicensedradioactive materialpackagings andcontainers (shipping and/orburial)shallbeperformed byIndianaMichigan1.7-67July,1991 Powerpersonnel, qualified inaccordance withRegulatory. Guide1.8andANSIN18.1,asaminimum.c)TransortationVehicles-Inspection oftransportation vehiclesbeingshippedas"exclusive use",shallbeperformed byIndianaMichiganPowerpersonnel, qualified inaccordance withRegulatory Guide1.8andANSIN18.1,asaminimum.d)OtherinsectionsandVerification -Inspections andverifications ofotheractivities associated withthepackaging andshipmentofradioactive materials andwasteshallbeperformed byIndianaandMichigan.Powerpersonnel, qualified inaccordance withRegulatory Guide1.8andANSIN18.1,asaminimum.1.7.10.2.6 Inspections areperformed, documented, andtheresultsevaluated bydesignated personnel inordertoensurethattheresultssubstantiate theacceptability oftheitemorwork.Evaluation andreviewresultsaredocumented. 1.7.11TESTCONTROL1.7.11.1SCOPETestingisperformed inaccordance withestablished programstodemon-stratethatstructures, systemsandcomponents willperformsatis-factorily inservice.Thetestingisperformed byqualified personnel inaccordance withwrittenprocedures thatincorporate specified requirements andacceptance criteria. Typesoftestsare:1.7-68July,1991 Scheduled Surveillance, preventive maintenance, post-design, qualification. Unscheduled Pre-andpost-maintenance. Testparameters (including anyprerequisites), instrumentation requirements,andenvironmental conditions arespecified intestprocedures. Testresultsaredocumented andevaluated. '.7.11.2INPLEHENTATI ON1.7.11.2.1 Testsareperformed inaccordance withprograms, procedures andcriteriathatdesignate whentestsarerequiredandhowtheyaretobeperformed. Suchtestingincludesthefollowing: a)gualification tests,asapplicable, toverifydesignadequacy. b)Acceptance testsofequipment andcomponents toassuretheiroperation priortodeliveryorinstallation. c)Post-design teststoassureproperandsafeoperation ofsystemsandequipment priortounrestricted operation. d)Surveillance teststoassurecontinuing properandsafeoperation ofsystemsandequipment. ThePHIonsurveillance testingcontrolstheperiodictestingofequipment andsystemstofulfillthesurveillance requirements established bytheTechnical Specifications. Controlshavebeenestablished toidentifyuncompleted surveillance testingtoassureitisrescheduled forcompletion tomeetTechnical Specification frequency requirements. 1.7-69July,1991 Datatakenduringsurveillance testingisreviewedbyappropriate management personnel toassurethatacceptance criteriaisfulfilled, orcorrective actionistakentocorrectdeficiencies. e)Maintenance testsafterpreventive orcorrective maintenance. 1.7.11.2.2 Testprocedures, asrequired, providemandatory holdpointsforwitnessorreview.I1.7.11.2.3 Testingisaccomplished afterinstallation, maintenance, orrepair,bysurveillance testprocedures, orperformance tests,whichmustbesatisfactorily completed priortodetermining theequipment isinan,operablestatus.Alldataresulting fromthesetestsisretainedattheCookNuclearPlantafterreviewbyappropriate management personnel. 1.7.12CONTROLOFMEASURING ANDTESTEQUIPHENT1.7.12.1SCOPEMeasuring andtestingequipment usedinactivities affecting thequalityofsafety-related systems,components,and structures areproperlyiden-tified,controlled, calibrated andadjustedatspecified intervals tomaintainaccuracywithinnecessary limits.1.7.12.2IMPLEMENTATION 1.7.12.2.1 Established procedures andinstructions areusedforcalibration andcontrolofmeasuring andtestequipment utilizedinthemeasurement, inspection andmonitoring ofstructures, systemsandcomponents. Theseprocedures andinstructions describecalibration techniques andfrequencies, andmaintenance andcontroloftheequipment. 1.7-70July,1991 AEPSCgAperiodically assessestheeffectiveness ofthecalibration programviathegAauditprogram.1.7.12.2.2 Heasuring andtestequipment isuniquelyidentified andistraceable toitscalibration source.1.7.12.2.3 Asystemhasbeenestablished forattaching, oraffixinglabels,tomeasuring andtestequipment todisplaythedatecalibrated andthenextcalibration duedate,oracontrolsystemisusedthatidentifies topotential usersanyequipment beyondthecalibration duedate.1.7.12.2.4 Heasuring andtestequipment iscalibrated atspecified intervals. Theseintervals arebasedonthefrequency ofuse,stability cha'racteristics andotherconditions thatcouldadversely affecttherequiredmeasurement accuracy. Calibration standards aretraceable tonationally recognized standards; orwheresuchstandards donotexist,provisions areestablished todocumentthebasisforcalibration. Theprimarystandards usedtocalibrate secondary standards have,exceptincertaininstances, anaccuracyofatleastfour(4)timestherequiredaccuracyofthesecondary standard. Inthosecaseswherethe'four(4)timesaccuracycannotbeachieved, thebasisforacceptance isdocumented andisauthorized bytheresponsible manager.Thesecondary standards haveanaccuracythatassuresequipment beingcalibrated willbewithinrequiredtolerances. Thebasisforacceptance isdocumented andauthorized bytheresponsible manager.1.7-71July,1991 1.7.12..2.5 CookNuclearPlantprocedures definetherequirements forthecontrolofstandards, testequipment andprocessequipment. 1.7.12.2.6 Whenmeasuring andtestingequipment usedforinspection andtestingisfoundtobeoutsideofrequiredaccuracylimitsatthetimeofcalibration, evaluations areconducted todetermine thevalidityoftheresultsobtainedsincethemostrecentcalibration.'etests, orreinspections, areperformed onsuspectitems.Theresultsof~evaluations aredocumented. 1.7.13HANDLING, STORAGE,ANDSHIPPING1.7.13.1SCOPEActivities withthepotential forcausingcontamination ordeterioration, byenvironmental conditions suchastemperature orhumiditythatcouldadversely affecttheabilityofanitemtoperformitssafety-related functions andactivities necessary topreventdamageorloss,areidentified andcontrolled. Theseactivities arecleaning, packaging, preserving,

    handling, shippingandstoring.Controlsareeffectedthroughtheuseofappropriate procedures andinstructions.

    1.7.13.2INPLENENTAT ION1.7.13.2.1 Procedures areusedtocontrolthecleaning,

    handling, storing,packaging, preserving andshippingofmaterials, components andsystemsinaccordance withdesignated procurement requirements.

    Theseprocedures include,butarenotlimitedto,thefollowing functions: a)Cleaning-toassurethatrequiredcleanliness levelsareachievedandmaintained. 1.7-72July,1991 I. b)Packaging andpreservation -toprovideadequateprotection againstdamageordeterioration. Whennecessary, theseprocedures provideforspecialenvironments, suchasinertgasatmosphere, specificmoisturecontentlevelsandtemperature levels.c)Handling-toprecludedamageorsafetyhazards.d)Storing-tominimizethepossibility ofloss,damageordeterio-rationofitemsinstorage,including consumables suchaschemicals, reagentsandlubricants. 1.7.13.2.2 Controlshavebeenestablished forlimitedshelflifeitemssuchas"0"rings,epoxy,lubricants, solventsandchemicals toassuretheyarecorrectly identified, storedandcontrolled topreventshelflifeexpiredmaterials frombeingusedintheCookNuclearPlant.Controlsareestablished inplantprocedures. 1.7.13.2.3 Packaging andshippingrequirements areprovidedtovendorswiththeAEPSCSpecifications (OCCs)whichareapartofthepurchaseorder,orareotherwise specified ontheprocurement order.Controlsforreceiptinspection, damageditemsandspecialhandlingrequirements attheCookNuclearPlantareestablished byplantprocedures. Specialcontrolsareprovidedtoassurethat,stainless steelcomponents andmaterials arehandledwithapprovedliftingslings.1.7.13.2.4 Storageandsurveillance requirements havebeenestablished toassuresegregation ofstorage.Specialcontrolshavebeenimplemented forcritical, highvalue,orperishable items.Routinesurveillance isconducted onstoredmaterialtoprovideinspection fordamage,rotation1.7-73July,1991

    ofstoredpumpsandmotors,inspection forprotection ofexposedsurfacesandcleanliness ofthestoragearea.1.7.13.2.5 Specialhandlingprocedures havebeenimplemented fortheprocessing ofnuclearfuelduringrefueling outages.Theseprocedures minimize'he riskofdamagetothenewandspentfuelandthepossiblereleaseofradioactive materialwhenplacingthespentfuelintothespentfuelpool.1.7.14INSPECTION, TEST,ANDOPERATING STATUS1.7.14.1SCOPEOperating statusofstructures, systemsandcomponents isindicated bytaggingofvalvesandswitches, orbyotherspecified means,insuchamannerastopreventinadvertent operation. Thestatusofinspections andtestsperformed onindividual itemsisclearlyindicated bymarkingsand/orloggingunderstrictprocedural controlstopreventinadvertent bypassing ofsuchinspections andtests.1.7.14.2IMPLEMENTATION 1.7,14.2.1 Fordesignchangeactivities, including itemfabrication, installation andtest,aprogramexistswhichspecifies thedegreeofcontrolrequired'for theidentification ofinspection andteststatusofstruc-tures,systemsandcomponents. Physicalidentification isusedtotheextentpractical toindicatethestatusofitemsrequiring inspections, tests,.or examinations. Proce-duresexistwhichprovidefortheuseofcalibration andrejection

    stickers, tags,stampsandotherformsofidentification toindicatetestandinspection status.TheClearance PermitSystemusesvarioustagstoidentifyequipment andsystemoperability status.Another1.7-74July,1991 programestablishes ataggingsystemforliftedleads,etc.Forthoseitemsrequiring calibration, theprogramprovidesforphysicalindica-tionofcalibration statusbycalibration
    stickers, oracontrolsystemisused.1.7.14.2.2 Application andremovalofinspection andweldingstamps,andofsuchstatusindicators astags,markings, labels,etc.,iscontrolled byplantprocedures.

    Theinspection statusofmaterials receivedattheCookNuclearPlantisidentified inaccordance withestablished instructions. Thestatusisidentified asHold,HoldforgualityControlClearance, Reject,orAccept.Theinspection statusofworkinprogressiscontrolled bytheuseofholdpointsinprocedures. PlantgualityControl,ordepartmental ANSIN18.1qualified personnel (reference 1.7.10.2.4herein),inspectanactivityatvariousstagesandsignofftheprocedural inspection steps.Thestatusofweldingiscontrolled throughtheuseofawelddatablockwhichidentifies theinspection andNDEstatusofeachweld.1.7.14.2.3 Requiredsurveillance testprocedures aredefinedinPHIs.Theseinstructions providefordocumenting bypassedtestsandrescheduling ofthetest.Thestatusoftestingafterminormaintenance isrecordedaspartoftheJobOrder.Thestatusoftestingaftermajormaintenance isincludedaspartoftheprocedure, andincludestheperformance offunctional testingandapprovalofdatabysupervisory personnel. 1.7-75July,1991 Testing,inspection andotheroperations important tosafetyareconducted inaccordance withproperlyreviewedandapprovedprocedures. ThePHIforplantprocedures requiresthatprocedures befollowedaswritten.Alteration tothesequenceofaprocedure canonlybeaccomplished byaprocedure changewhichissubjecttothesamecontrolsastheoriginalreviewandapproval. Whenanimmediate procedure changeisrequiredtocontinuein-process workortestingandtherequiredcompletereviewandapprovalprocesscannotbeaccomplished, an"OnTheSpot"changeisprocessed inaccordahce withthePHIonplantprocedures. 1.7.14.2.4 Nonconforming, inoperable, ormalfunctioning structures, systemsandcomponents areclearlyidentified bytags,stickers, stamps,etc.,anddocumented topreventinadvertent use.1.7.15NONCONFORHING ITEHS1.7.15.1SCOPEHaterials, parts,orcomponents thatdonotconformtorequirements arecontrolled inordertopreventtheirinadvertent use.Nonconforming itemsareidentified, documented, segregated whenpractical anddisposi-tioned.Affectedorganizations arenotifiedofnonconformances. 1.7.15.2IHPLEHENTAT ION1.7.15.2.1 Items,services, oractivities thataredeficient incharacteristic, documentation, orprocedure, whichrenderthequalityunacceptable orindeterminate, areidentified asnonconforming andanyfurtheruseis1.7-76July,1991 controlled. Nonconformances aredocumented anddispositioned, andnotification ismadetoaffectedorganizations. Personnel authorized todisposition, conditionally releaseandcloseoutnonconformances aredesignated. TheJobOrderSystemand/ortheCondition/Problem Reports(referto1.7.16herein)areusedatCookNuclearPlanttoidentifynonconforming itemsandinitiatecorrective actionforitemswhichareinstalled orhavebeenreleasedtotheCookNuclearPlant.Systems,components, ormaterials whichrequirerepairorinspection arecontrolled undertheJobOrderSystem.Inaddition, thevariousprocedures identified in1.7.14hereinprovideforidentification, segregation'nd documentation ofnonconforming items.1.7.15.2.2 Nonconforming itemsareidentified bymarking,tagging,segregating, orbydocumented administrative controls. Documentation describes thenonconformance, thedisposition ofthenonconformance andtheinspection requirements. Italsoincludessignature approvalofthedisposition. Completed JobOrdersarereviewedbythesupervisor responsible foraccomplishing thework,andthesupervisor ofthedepartment/section thatoriginated theJobOrder.ThegADivisionperiodically auditstheJobOrderSystem,andonasamplebasis,JobOrders.1.7.15.2.3 Itemsthathavebeenrepairedorreworkedareinspected andtestedinaccordance withtheoriginalinspection andtestrequirements, oralternatives, thathavebeendocumented. 1.7-77July,1991

    Itemsthathavethedisposition of"repair"or"use-as-is" requiredocumentation justifying acceptability. Thechangesarerecordedtodenotetheas-builtcondition. Whenrequiredbyestablished procedures, surveillance oroperability testsareconducted onanitemafterrework,repairorreplacement. 1.7.15.2.4 Disposition ofconditionally releaseditemsareclosedoutbeforetheitemsarereliedupontoperformsafety-related functions. 1.7.16CORRECTIVE ACTION1.7.16.1SCOPEConditions adversetoquality,suchasfailures, malfunctions, deficien-cies,deviations, defective materialandequipment, andnonconformances areidentified promptlyandcorrected assoonaspractical. Forsignificant conditions adversetoquality,thecauseofthe"condition isdetermined, corrective actionistakentocorrecttheimmediate problem,andpreventive actionisimplemented topreventrecurrence. Inthesecases,thecondition, causeand'corrective actiontakenisdocumented andreportedtoappropriate levelsofmanagement. 1.7.16.2IHPLEHENTATION 1.7.16.2.1 Procedures areestablished thatdescribetheplantandAEPSCcorrective actionprograms. Theseprocedures arereviewedandconcurred withbytheAEPSCgADivision. 1.7-78July,1991 1.7.16.2.2 ~~~Condition/Problem Reportsprovidethemechanism forplantandAEPSCpersonnel. tonotifymanagement ofconditions adversetoquality.Condition/Problem Reportsarealsousedtoreportviolations tocodes,regulations andtheTechnical Specifications. Investigations ofreportedconditions adversetoqualityareassignedbymanagement. TheCondition/Problem Reportisusedtodocumenttheinvestigation ofaproblem;andtoidentifytheneedforadesignchangetocorrectsystemorequipment deficiencies, ortoidentifytheneedfortheinitiation ofJobOrderstocorrectminordeficiencies. Further,Condition/Problem Reportsareusedtoidentifythoseactionsnecessary topreventrecurrence ofthereportedcondition. Significant

    problems, whicharesodesignated onCondition/Problem Reports,arereviewedbythePNSRCforevaluation ofactionstaken,orbeingtaken,tocorrectthedeficiency andpreventrecurrence.

    TheAEPSCNSDRCisresponsible forassuringthatindependent reviewsofviolations (asspecified intheTechnical Specifications) areperformed. Theseviolations areconsidered significant problemswhicharedocumented onCondition/Problem Reports.Thereviewswillprovideanindependent evaluation ofthereportedproblemsandcorrective actions., TheAEPSCgADivisionperiodically auditsthecorrective actionsystemsforcompliance andeffectiveness. 1.7-79July,1991

    1.7.17.EQUALITYASSURANCE RECORDS1.7.17.1SCOPERecordsthatfurnishevidenceofactivities affecting thequalityofsafety-related structures, systemsandcomponents aremaintained. Theyareaccurate,

    complete, legibleandareprotected againstdamage,deterioration, orloss.Theyareidentifiable andretrievable.

    1.7.17.2INPLENENTAT ION1.7.17.2.1 Documents thatfurnishevidenceofactivities affecting thequalityofsafety-related itemsaregenerated andcontrolled inaccordance withtheprocedure thatgovernsthoseactivities. Uponcompletion, thesedocuments areconsidered records.Theserecordsinclude:a)b)c)d)e)f)g)h)Resultsofreviews,inspections, surveillances, tests,auditsandmaterialanalyses. gualification ofpersonnel, procedures andequipment. Operation logs.Haintenance andmodification procedures andrelatedinspection results.Reportable occurrences. RecordsrequiredbytheplantTechnical Specifications. ProblemReports.Otherdocumentation suchasdrawings, specifications, dedication plans,procurement documents, calibration procedures andreports.Radiographs.1.7.17.2.2 Instructions andprocedures establish therequirements fortheidenti-ficationandpreparation ofrecordsforsystemsandequipment underthegAProgram,andprovidethecontrolsforretention oftheserecords.1.7-80July,1991

    Criteriaforthestoragelocationofqualityrelatedrecords,andaretention schedulefortheserecords,hasbeenestablished. FileIndexeshavebeenestablished toprovidedirection forfiling,andtoprovidefortheretrievability oftherecords.Controlshavebeenestablished forlimitingaccesstothePlantHasterFiletopreventunauthorized entry,unauthorized removal,andforuseoftherecordsunderemergency conditions. TheAccounting Supervisor isresponsible forthecontrolandoperation ofthePlantHasterFileRoom.1.7.17.2.3 WithinAEPSC,eachdepartment/division managerisresponsible fortheidentification, collection, maintenance,and storageofrecordsgenerated bytheirdepartment/division. Procedures ensurethemaintenance ofrecordssufficient tofurnishobjective evidencethatactivities affecting qualityareincompliance withtheestablished gAProgram.1.7.17.2.4 Whenadocumentbecomesarecord,itisdesignated aspermanent, ornonpermanent, andthentransmitted tofile.Nonpermanent recordshavespecified retention times.Permanent recordsaremaintained forthelifeoftheplantorequipment, asapplicable. 1.7.17.2.5 Onlyauthorized personnel mayissuecorrections orsupplements torecords.1.7-81July,1991 1.7.17..2.6 ~~Traceability betweentherecordandtheitemoractivitytowhichitappliesisprovided. 1.7.17.2.7 Exceptforrecordsthatcanonlybestoredasoriginals, suchasradio-graphsandsomestripcharts,ormicrographs thereof,recordsarestoredinremote,dualfacilities topreventdamage,deterioration, orlossduetonaturalorunnatural causes.Whenonlythesingleoriginalcanberetained, specialfire-rated facilities areused.1.7.18AUDITS1.7.18.1SCOPEAcomprehensive systemofauditsiscarriedouttoprovideindependent evaluation ofcompliance with,andtheeffectiveness of,theQAProgram,including thoseelementsoftheprogramimplemented bysuppliers andcontractors. Auditsareperformed inaccordance withwrittenprocedures orchecklists byqualified personnel nothavingdirectresponsibility intheareasaudited.Auditresultsaredocumented andreviewedbymanagement. Follow-up actionistakenwhereindicated. 1.7.18.2INPLEHENTAT ION1.7.18.2.1AEPSCADivisionResonsibilitiesThebasicresponsibility fortheassessment oftheQAProgramisvestedintheAEPSCQAD.TheAEPSCQADisprimarily responsible forensuringthatproperQAprogramsareestablished andforverification oftheirimplementation. Theseresponsibilities aredischarged incooperation withtheAEPSCandCookNuclearPlantmanagement andtheirstaffs.1.7-82July,1991 Internalauditsareperformed inaccordance withestablished schedules thatreflectthestatusandimportance ofsafety,to theactivities beingperformed. Allareaswheretherequirements of10CFR50,AppendixBapplyareauditedwithinaperiodofonetotwoyears.1.7.18.2.3 TheAEPSCgADconductsauditstoverifytheadequacyandimplementation ofthegAProgramattheCookNuclearPlantandwithintheAEPSystem.gAauditreportsaredistributed toappropriate CookNuclearPlantmanagement andtheNSORC(allaudits).1,7.18.2.4 Theindependent off-sitereviewandauditorganization istheAEPSCNSORC.Thiscommittee iscomposedofAEPSC,I&MandCookNuclearPlantmanagement members.AnNSDRCManualhasbeendeveloped forthiscommittee whichcontainstheNSDRCCharterandprocedures. TheNSDRCconductsperiodicauditsofCookNuclearPlantoperations pursuanttoestablished criteria(Technical Specifications, etc.).NSDRCauditreportsaresubmitted forreviewtotheNSORCmembership, theChairmanoftheNSDRC,andtheAEPSCSeniorExecutive VicePresident -Engineering andConstruction. ProblemReportsprovidefortherecording ofactionstakentocorrectdeficiencies foundduringtheseaudits.1.7.18.2.5 TheCookNuclearPlanton-sitereviewgroupisthePNSRC.Thiscommittee reviewsplantoperations asaroutineevaluation andservestoadvisethePlantManageronmattersrelatedtonuclearsafety.Thecomposition ofthecommittee isdefinedintheTechnical Specifications. 1.7-83July,1991

    ThePNSRCalsoreviewsinstructions, procedures, anddesignchangesforsafety-related systemspriortoapprovalbythePlantHanager.Inaddition, thiscommittee servestoconductinvestigations ofviolations toTechnical Specifications, andreviewssignificant ProblemReportstodetermine ifappropriate actionhasbeentaken.1.7.18.2.6 Auditsofsuppliers andcontractors arescheduled basedonthestatusofsafetyimportance oftheactivities beingperformed, andareinitiated earlyenoughtoassureeffective qualityassurance duringdesign,pro-curement, manufacturing, construction, installation, inspection andtesting.Principal contractors arerequiredtoaudittheirsuppliers systematically inaccordance withthecriteriaestablished withintheirqualityassurance programs. 1.7.18.2.7 ~~~~Regularly scheduled auditsaresupplemented by"specialaudits"whensignificant changesaremadeinthegAProgram,whenitissuspected thatqualityisinjeopardy, orwhenanindependent assessment ofprogrameffectiveness isconsidered necessary. 1.7.18.2.8 Auditsincludeanobjective evaluation ofpractices, procedures, instructions, activities anditemsrelatedtoquality;andareviewofdocuments andrecordstoconfirmthatthegAProgramiseffective andproperlyimplemented. 1.7-84July,1991 Auditprocedures andthescope,plans,checklists andresultsofindivi-dualauditsaredocumented. 1.7.18.2.10 Personnel selectedforauditingassignments haveexperience, oraregiventrainingcommensurate withtheneedsoftheaudit,andhavenodirectresponsibilities intheareasaudited.1.7.18.2.11 Hanagement oftheauditedorganization identifies andtakesappropriate actiontocorrectobserveddeficiencies andtopreventrecurrence. Follow-up isperformed bytheauditingorganization toensurethattheappropriate actionsweretaken.Suchfollow-up includesreaudits, whennecessary. 1.7.18.2.12 TheadequacyofthegAProgramisregularly assessedbyAEPSCmanagement. Thefollowing activities constitute formalelementsofthatassessment: a)Auditreports,including follow-up oncorrective actionaccomplishment andeffectiveness, aredistributed toappropriate levelsofmanagement. b)Individuals independent fromthegAorganization, butknowledgeable inauditingandqualityassurance, periodically reviewtheeffectiveness ofthegAPrograms. Conclusions andrecommendations arereportedtotheAEPSCVicePresident -NuclearOperations. 1.7-85July,1991 1.7.19~~FIREPROTECTION gAPROGRN1.7.19.1Introduction TheCookNuclearPlantFireProtection gAProgramhasbeendeveloped usingtheguidanceofNRCBranchTechnical Position(APCSB)9.5-1,AppendixA,SectionC,"gualityAssurance Program," andNRCclarification "NuclearPlantFireProtection Functional Responsibilities, Administrative

    Controls, andgualityAssurance,"

    datedJune14,1977.Assuch,theFireProtection gAProgramispartoftheoverallgAProgramfortheplant.TheFireProtection gAProgramencompasses design,procurement, fabrication, construction, surveillance, inspection, operation, maintenance, modification, andaudits.Implementation andassessment oftheFireProtection gAProgramistheresponsibility ofeachinvolvedAEPSCandIndianaMichiganPowerCompanyorganization. .2TheFireProtection gAProgramisunderthemanagement controlofAEPSC.Thiscontrolconsistsof:1)Verifying theeffectiveness oftheFireProtection gAProgramthroughreview,surveillance, andaudits.2)Directing formulation, implementation, andassessment oftheFireProtection gAProgrambyprocedural controls. 3)AssuringthegAprogramisacceptable tothemanagement responsible forfireprotection. 1.7-86July,1991 ThePlantManagerhasdelegated responsibility tovariousCookNuclearPlantdepartments forthefollowing fireprotection activities: a)b)c)d)e)f)g)Haintenance offireprotection systems.Testingoffireprotection equipment. Firesafetyinspections. Firefightingprocedures. Firedrills.Emergency remoteshutdownprocedures. Emergency repairprocedures (lOCFR50, AppendixR).TheFireProtection gAProgramattheCookNuclearPlantalsoprovidesforinspection offirehazards,explosion hazards,andtrainingoffirebrigadeandresponding firedepartments. TheAssistant ShiftSupervisor onduty,ordesignee, isdesignated astheFireBrigadeLeaderandcoordinates thefirefightingeffortsofshiftpersonnel andtheFireBrigade.1.7.19.3DesinControlandProcurement DocumentControlgualitystandards arespecified inthedesigndocuments suchasappropriate fireprotection codesandstandards, and,asnecessary, deviations andchangesfromthesequalitystandards arecontrolled. TheCookNuclearPlantdesignwasreviewedbyqualified personnel toensureinclusion ofappropriate fireprotection requirements. Thesereviewsincludeitemssuchas:1)Verification astotheadequacyofelectrical isolation andcableseparation criteria. 2)Verification ofappropriate requirements forroomisolation (sealingpenetrations, floorsandotherfirebarriers). 1.7-87July,1991 3)Determination forincreaseinfireloadings. 44)Determination fortheneedofadditional firedetection andsuppression equipment. Procurement offireprotection equipment andrelateditemsaresubjecttotherequirements ofthefireprotection procurement documents. Areviewofthesedocuments isperformed toassurefireprotection requirements andqualityrequirements arecorrectly stated,verifiable, andcontrollable, andthatthereisadequateacceptance andrejection criteria. Procurement documents mustbeprepared,

    reviewed, andapprovedaccording togAProgramrequirements.

    Designandprocurement documentchanges,including fieldchangesanddesigndeviations, arecontrolled byprocedure. 1.7.19.4Instructions Procedures andDrawinsInspections, tests,administrative

    controls, firedrillsandtrainingthatassistinimplementing thefireprotection programareprescribed byapprovedinstructions orprocedures.

    Indoctrination andtrainingprogramsforfireprevention andfirefightingareimplemented inaccordance withapprovedprocedures. Activities associated withthefireprotection systemsandfireprotection relatedsystemsareprescribed andaccomplished inaccordance withdocumented instructions', procedures, anddrawings. Instructions andprocedures fordesign,installation, inspection, tests,maintenance, modification andadministrative controlsarereviewedthroughauditstoassurethatthefireprotection programismaintained. Operation andmaintenance information hasbeenprovidedtotheplantintheformofSystemDescriptions andequipment supplierinformation. 1.7-88July,1991 1.7.19e5ControlofPurchased ItemsandServices~~Heasuresareestablished toassurethatpurchased itemsandservicesconformtoprocurement documents. Thesemeasuresincludeprovisions, assappropriate, forsourceevaluation andselection, objective evidenceofqualityfurnished bythecontractor, inspections atsuppliers, orreceiptinspection. Sourceorreceiptinspection isprovided, asaminimum,forthoseitemswherequalitycannotbeverifiedafterinstallation. 1.7.19.6~lesectioAprogramforindependent inspection ofthefireprotection activities hasbeenestablished andimplemented. Theseinspections areperformed bypersonnel otherthanthoseresponsible forimplementation oftheactivity. Theinspections include:a)Inspection ofinstallation, maintenance andmodification offireprotection systemsandequipment. b)Inspections ofpenetration sealsandfireretardant coatinginstallations toverifytheactivityissatisfactorily completed inaccordance withinstallation specifications. c)Inspections ofcableroutingtoverifyconformance withdesignrequirements asspecified inAEPSCSpecifications and/orplantprocedures. d)Inspections toverifythatappropriate requirements forfirebarriersaresatisfied following installation, modification, repairorreplacement activities. 1.7-89July,1991 e)Measurestoassurethatinspection personnel areindependent fromtheindividuals performing theactivitybeinginspected andareknowledgeable inthedesignandinstallation requirements forfireprotection. f)Inspection procedures, instructions orchecklists forrequiredinspections. g)Periodicinspections offireprotection systems,emergency breathing andauxiliary equipment. h)Periodicinspections ofmaterials subjecttodegradation, suchasfirestops,sealsandfireretardant coatingasrequiredbyTechnical Specifications ormanufacturer's recommendations. 1.7.19.7TestandTestControla)Installation testing-Following installation, modification, repair,orreplacement, sufficient testingisperformed todemonstrate thatthefireprotection systemsandequipment willperformsatisfactorily. Writtentestprocedures forinstallation testsincorporate therequirements andacceptance limitscontained inapplicable designdocuments. b)Periodictesting-Periodictestingoccurstodocumentthatfireprotection equipment functions inaccordance withitsdesign.c)Programshavebeenestablished toverifythetestingoffireprotection systems,andtoverifythattestpersonnel areeffectively trained.d)Testresultsaredocumented, evaluated, andtheiracceptability determined byaqualified responsible individual orgroup.1.7-90July,1991

    1.7.19.,8 sectionTestad0eratintatusTheinspection, testandoperating statusforplantTechnical Specification fireprotection systemsareperformed asdescribed in1.7.14herein.1.7.19.9Nonconformin ItemsTechnical Specification fireprotection equipment nonconformances areidentified anddispositioned asdescribed in1.7.15herein.1.7.19.10Corrective ActionThecorrective actionmechanism described in1.7.16hereinappliestotheTechnical Specification fireprotection equipment. 1.7.19.11 RecordsRecordsgenerated tosupportthefireprotection programarecontrolled asdescribed in1.7.17herein.1.7.19.12AuditsAuditsareconducted anddocu'mented toverifycompliance withtheFireProtection gAProgramasdescribed in1.7.18herein.Auditsareperiodically performed toverifycompliance withtheadminis-trativecontrolsandimplementation offireprotection qualityassurance criteria. Theauditsareperformed inaccordance withpre-established writtenprocedures orchecklists. Auditresultsaredocumented andreviewedbymanagement havingresponsibility intheareaaudited.Follow-up actionistakenbyresponsible management tocorrectthedeficiencies revealedbytheaudit.1.7-91July,1991 AMERICANELECTRICPOWERSERVICECORPORATION SLI%%ltTOtOANZZAYZOD5 FQtACCOOLIQCLEAlt~TMCSloc>>IuuCettfCXCCNIIVC OffICCD51>>toeCACCUIeCvtCLtetLc>>OI>>tttoec uOCo>>5IIUCIICN DlfttcIfft/V>>LITTASSISIANCC vtctMCSIOC>>ftuCLIAOOPQIATICNS St>>IONvlccONCSIOC>>f uuCNIcfc>>41>>CCOvlCCMCSIOCNIMOICCINNIAOC>>C>>I utlCO>>SI4>>STIONttttLITfASSINNNCDtettto>>TLA>>INANACu~COOLtuCLCADOLA>>lASSISTANT VlctMtttof>>TD15IONA5515Tutf vtCCMtttoctff CIVCLQtottttftf NOA551STulf vlotMttfot>>IICXLCADt>>SIN1ttt>>OMOJCCINA>>ACC>>t>>f IN)CONS'Ie>>CIION DlPAAftCNI tuCLCANcvuATICNS Dtvltto>>NetONtefAtttoN'4IOI>>etlttv Ne>>nfN'>>IN>>etlNl NltteeuhletttNIee Nl4NtNtleeel OITNltlet TNtvlfaIIIe>>et+NltlNNINuwtleheIN'ee>>eeeferfleetatl~ItteeIIIIINJCLCAOOSSICNCt>>tclCIVILCICIICCOINO OtttffftNNI CLtCTOICAL STSICNSDIVISIINtucLCAOOLA>>Ic>>ot>>cuc>>o [DttlSIONSlitCO>>STCOOTION IN>>ACtoIN+ftfIIIIOAOCOTALL 104

    AmericanElePowerCompanyAmericanElectricPowerCompanyAmericanElectricPowerServiceCorporation Appalachian PowerCompanyOhioPowerCompanyInsaneMichiganPowerCompanyColumbusSouthernPoworCompanyK>ngspatPowerCompanyKentuckyPowerCompanyMrchganPoworCompanyWheetrngPowerCompanyCentalOdelsting ICookNuctoa<Plantadministrative. technical. andlunctional direction ValleyPowerIcarsnatIOpratingCompanyIIgenerating subrudiary iointtyownedwithBuckeyePower.Inc. !4FjguzeNo.F7-3PRGANj:ZPTIONALRELATIONSHIPS THEAMERICANELECTRICPOWERSYSTEMPERTAINING TOQUALITYASSURANCE 1IiQUALXTY CONTROLSUPPORTPFTHECOOKNUCLEARPLANTPRESIDEuT AVDCHIEFExECUTvE"FFCERAEPSC.NDAVAMICHGANPOWER"MPANYANDOTpRAE?SUBS---AR-=S OR-.("uT'v=.SAu"4=NGuE-=R:SGhCOLSRL'CT:ON. AEPSCANDVICEPRESZDEVT, INDANA4IZCHZ~AN POAERCOMPAiVYICEPRESIDENT NUCLEAROPERATONS,AEPSCAiVDVICEPRESIDENT. INDIANAMICHGAN(MANAGEROFNUCLEAROPERATIONS) DIRECTORQUALITYASSURANCE AEPSC0~~~~~~~~IMANAGERSENGINEFRING%CONSTRUCTION ORGANIZATION, AEPSC~,~~~~~~s~~~o~~~~~s~~~o~~~~I~~~~~o~~PLANTMANAGERCOOKNUCLEARPLANTII*IISAFETYLASSESSMENT SUPERINTENDENT IIIII~~0IQUALITYASSURANCE SUPERINTENDENT (ONSITE)AEPSCACmlnlstrative 11functfonal dlrectlnTechnical direction Technical liasonFunctional dlrectionforCookNuclearPIantact1v1tles1'"94July,1991

    OarOIZAEPSCQUALITYASSURANCE DIVISIONORGANIZATION ALVSCDJHLCIOH(.JUAI.I'I'YA'l.'>IJI(AN('I:. SL'CIIONMANAGERQUALITYASSURANCE SUPPORTSLCIlONMANAGEIPAUDIISANI)PIIDCUI<LME.NI SLCIEONMANAUtl(QUAIIIYA~bl)IIANCL LNOINELBlWI'>LC IlONMANA4tI<NUClLAB501IWAI<LQUAL11YASSUIlANCI QJJAIIIYA'.~UI<ANCL'.IJI'IIIIIIII.HI)ENI('.JIII) . IndianaMichiganPowerCompanvOrganization fortheCookNuclearPlantPlslllM<<llsgolACPSCSect<<<<<M<<<<ago< NucloaiSstslyIIIce<<a<<gIIC<<nSlngA<t<v<lyCo<<<*<I<<lu<Assistant PlantManage<P<odu<:tt<<<I Assistant PlantManage<Technical Suppu<IAs'sist<<ill IhllllM<<lingo<Pl<<lliitsAla<<<n<st<alk<nSupenntendenl Ope<atlons Supe<Into<<~it Technical Sup<<<lilt<<<<dont PhysicalScienceVielectEngulee<lngSupe<<<<lo<<<tent S<<l<<ly<<<<<IAss<<ssmo<<l Sl<plilllllon<lo<<t StoicsSupetstsc< To<<tin<col Sup<<I<I<till<<I<mt Fi<glllooiiii<l SiloConshuctlun Manage<OushlyCo<it<el/NI)l Sect<unMaintenance Sup<<lint<<nlhiill Compute<SciencesSupe<mte<<<ts<<t hEPSCSileDeslg<<S<11<<IIISIISIIYO IOSPOnsasaty I<<et<<<<cslhslson luncliunal IesponsMity

    APPENDIX'AREGULATORY ANDSAFETYGUIDESANSISTANDARDS 1.Reg.Guide1.8(9/75)ANSIN18.1(1971)Personnel Selection andTrainingSelection andTrainingofNuclearPowerPlantPersonnel 2.Reg.Guide1.14(8/75)ReactorCoolantPumpFlywheelIntegrity 3.Reg.Guide1.16(8/75)Reporting ofOperating Information, AppendixA-Technical Specifications 4.SafetyGuide30(8/72)ANSIN45.2.4(1972)gualityAssurance Requirements for.theInstallation, Inspection, andTestingofInstrumentation andElectricEquipment Installation, Inspection, andTestingRequirements forInstrumentation andElectricEquipment DuringtheConstruction ofNuclearPowerGenerating Stations5.Reg.Guide1.33(02/78)ANSIN18.7(1976)(ANS3.21976)ANSIN45.2(1977)gualityAssurance ProgramRequirements (Operation) Administrative ControlsandgualityAssurance fortheOperational PhaseofNuclearPowerPlantsgualityAssurance ProgramRequirements forNuclearFacilities 1.7-97July,1991 6.Reg.Guide1.37(3/73)ANSIN45.2.1(1973)gualityAssurance Requirements forCleaningofFluidSystemsandAssociated Components ofWater-CooledNuclearPowerPlantsCleaningofFluidSystemsandAssociated Components DuringConstruction PhaseofNuclearPowerPlants7.Reg.Guide1.38(10/76)ANSIN45.2.2(1972)gualityAssurance Requirements forPackaging,

    Shipping, Receiving, StorageandHandlingofItemsforWater-Cooled NuclearPowerPlantsPackaging,
    Shipping, Receiving, StorageandHandlingofItemsforNuclearPowerPlants(DuringtheConstruction Phase)8.Reg.Guide1.39(10/76)~~~ANSIN45.2.3(1973)Housekeeping Requirements forWater-CooledNuclearPowerPlantsHousekeeping DuringtheConstruction PhaseofNuclearPowerPlants9.Reg.Guide1.54(6/73)ANSIN101.4(1972)gualityAssurance Requirements forProtective CoatingsAppliedtoWater-Cooled NuclearPowerPlantsgualityAssurance forProtective CoatingsAppliedtoNuclearFacilities 10.Reg.Guide1.58(9/80)gualification ofNuclearPowerPlantInspection, Examination andTestingPersonnel 1.7-98July,1991 ANSIN45.2.6(1978)gualifications ofInspection, Exami-nation,andTestingPersonnel forNuclearPowerPlants11.Reg.Guide1.63(7/78)ElectricPenetration Assemblies inContainment Structures forLight-Water-Cooled NuclearPowerPlants12.Reg.Guide1.64(10/73)ANSIN45.2.11(1974)gualityAssurance Requirements fortheDesignofNuclearPowerPlantsgualityAssurance Requirements fortheDesignofNuclearPowerPlants13.Reg.Guide1.74(2/74)ANSIN45.2.10(1973)gualityAssurance TermsandDefinitions gualityAssurance TermsandDefinitions 14.Reg.Guide1.88(10/76)~~~ANSIN45.2.9(1974)Collection, Storage,andHaintenance ofNuclearPowerPlantgualityAssurance RecordsRequirements forCollection, Storage,andHaintenance ofguality.Assurance RecordsforNuclearPowerPlants15.Reg.Guide1.94(4/76)gualityAssurance Requirements forInstallation, Inspection, andTestingofStructural ConcreteandStructural SteelDuringtheConstruction PhaseofNuclearPowerPlants1.7-99July,1991 ANSIN45.2.5(1974)Supplementary gualityAssurance Requirements forInstallation, Inspection, andTestingofStructural ConcreteandStructural SteelDuringtheConstruction PhaseofNuclearPowerPlants16.Reg.Guide1.108(8/77)PeriodicTestingofDieselGenerator UnitsusedasOnsiteElectricPowerSystemsatNuclearPowerPlants17.Reg.Guide1.123(7/77)ANSIN45.2.13(1976)gualityAssurance Requirements forControlofProcurement ofItemsandServicesforNuclearPowerPlantsgualityAssurance Requirements forControlofProcurement ofItemsandServicesforNuclearPowerPlants18.Reg.Guide1.144(1/79)~~~~ANSIN45.2.12(1977)AuditingofgualityAssurance ProgramsforNuclearPowerPlantsRequirements forAuditingofgualityAssurance ProgramsforNuclearPowerPlants19.Reg.Guide1.146(8/80)ANSIN45.2.23(1978)gualification ofgualityAssurance ProgramAuditPersonnel forNuclearPowerPlantsgualification ofgualityAssurance ProgramAuditPersonnel forNuclearPowerPlants1.7-100July,1991 0

    20.ANSIN45.2.8(1975)~~~Supplementary equalityAssurance Requirements forInstallation, Inspection andTestingofHechanical Equipment andSystemsfortheConstruction PhaseofNuclearPowerPlants21.ANSIN45.4(1972)Leakage-Rate TestingofContainment Structures forNuclearReactors1.7-101July,1991 APPENDIXBAEPSC/I&M EXCEPTIONS TOOPERATING PHASESTANDARDS ANDREGULATORY GUIDES1.GENERALCertainRegulatory Guidesinvoke,orimply,Regulatory Guidesandstandards inadditiontothestandardeachprimarily endorses. CertainANSIStandards invoke,orimply,additional standards. ExcetionInterretationTheAEPSC/I&M commitment referstotheRegulatory GuidesandANSIStandards specifically identified inAppendixA.Additional Regulatory Guides,ANSIStandards andsimilardocuments implied,orreferenced, inthosespecifically identified arenotpartofthiscommitment. 2.N18.7GeneralExcetionInterretationAEPSCandI&Mhaveestablished bothanon-siteandoff-sitestandingcommittee forindependent reviewactivities; togethertheyformtheindependent reviewbody.Thestandardnumericandqualification requirement maynotbemetbyeachgroupindividually. Procedures willbeestablished tospecifyhoweachgroupwillbeinvolvedinreviewactivities. Thisexception/interpretation isconsistent withtheplant'sTechnical Specifications. 1.7-102July,1991 z...Sec.4.3.1"Personnel assignedresponsibility forindependent reviewsshallbespecified inbothnumberandtechnical disciplines, andshallcollectively havetheexperience andcompetence requiredtoreviewproblemsinthefollowing areas:ExcetionInterretationAEPSCNuclearSafetyandDesignReviewCommittee (NSORC)andPlantNuclearSafetyReviewCommittee (PNSRC)willnothavemembersspecified bynumber,norbytechnical disciplines, anditsmembersmaynothavetheexperience andcompetence requiredtoreviewproblemsinallareaslistedinthissection.Thisexception/interpretation isconsistent withtheplant'sTechnical Specifications. TheNSDRCandPNSRCwillnotspecifically includeamemberqualified innondestructive testing,butwillusequalified technical consultants toperformthisandotherfunctions asdetermined necessary bytherespective committee chairman. 2b.Sec.4.3.2.1II"Whenastandingcommittee isresponsible fortheindependent review.program,itshallbecomposedofnolessthanfivepersonsofwhomnomorethanaminorityaremembersoftheon-siteoperating organization. Competent alternates arepermitted ifdesignated inadvance.Theuseofalternates shallberestricted tolegitimate absencesofprincipals." ExcetionInterretationSeeItem2a.1.7-103July,1991

    Sec.4.3.3.1"...recommendations ...shallbedisseminated promptlytoappropriate membersofmanagement havingresponsibility intheareareviewed." IExcetionInterretationRecommendations madeasaresultofreviewwillgenerally beconveyedtotheon-site,oroff-site, standingcommittee. Procedures willbemaintained specifying howrecommendations aretobeconsidered. 2d.Sec.4.3.4Reuirement"Thefollowing subjectsshallbereviewedbytheindependent reviewbody'~~~"ExcetionInterretationSubjectsrequiring reviewwillbeasspecified intheplantTechnical Specifications. 2e~Sec.4.3.4(3)"ChangesintheTechnical Specifications orLicenseAmendments relatingtonuclearsafetyaretobereviewedbytheindependent reviewbodypriortoimplementation, exceptinthosecaseswherethechangeisidentical toapreviously reviewedproposedchange."ExcetionInterretationAlthoughtheusualpracticeistomeetthisrequirement, exceptions aremadetoNSDRCreviewandapprovalpriortoimplementation inrarecaseswiththepermission oftheNSDRCChairmanandSecretary. PNSRCreviewandapprovalisalwaysdonepriortoimplementation ofTechnical Specification changes.1.7-104July,1991

    2f..Sec.4.4"Theon-siteoperating organization shallprovide,aspartofthenormaldutiesofplantsupervisory personnel ExcetionInterretationSomeoftheresponsibilities oftheon-siteoperating organization described inSection4.4maybecarriedoutbythePNSRCand/orNSORCasdescribed inplantTechnical Specifications. 2g.Sec.5.2.2"Temporary changes,whichclearlydonotchangetheintentoftheapprovedprocedure, shallasaminimumbeapprovedbytwomembersoftheplantstaffknowledgeable intheareasaffectedbytheprocedures. Atleastoneoftheseindividuals shallbethesupervisor inchargeoftheshiftandholdasenioroperator's licenseontheunitaffected." fxcetionInterretationIKHconsiders thatthisrequirement appliesonlytoprocedures identi-4fiedinplantTechnical Specifications. Temporary changestotheseprocedures shallbeapprovedasdescribed inplantTechnical Specifications. 2h.Sec.5.2.6"Incaseswhererequireddocumentary evidenceisnotavailable, theassociated equipment ormaterials mustbeconsidered nonconforming inaccordance withSection5.2.14.Untilsuitabledocumentary evidenceisavailable toshowtheequipment ormaterialisinconformance, affectedsystemsshallbeconsidered tobeinoperable andrelianceshallnotbeplacedonsuchsystemstofulfilltheirintendedsafetyfunctions." 1.7-105July,1991 ExcetionInterretationIEMinitiates appropriate corrective actionwhenitisdiscovered thatdocumentary evidencedoesnotexistforatestorinspection whichisarequirement toverifyequipment acceptability. Thisactionincludesatechnical evaluation oftheequipment's operability status.2i.Sec.5.2.8lt"Asurveillance testingandinspection program...shallincludetheestablishment ofamastersurveillance schedulereflecting thestatusofallplannedin-plantsurveillance testsandinspections." ExcetionInterretationSeparatemasterschedules mayexistfordifferent

    programs, suchasISI,pumpandvalvetesting,andTechnical Specification surveillance testing.Sec..5.2.13.1"Totheextentnecessary, procurement documents shallrequiresuppliers toprovideagualityAssurance Programconsistent withthepertinent requirements ofANSIN45.2-1977."ExcetionInterretatioTotheextentnecessary, procurement documents requirethatthesupplierhasadocumented gualityAssurance Programconsistent withthepertinent requirements ofIOCFR50,AppendixB;ANSIN45.2;orothernationally recognized codesandstandards.

    2k.Sec.5.2.13.2ANSIN18.7andN45.2.13specifythatwhererequiredbycode,regulation, orcontract, documentary evidencethatitemsconformtoprocurement requirements shallbeavailable atthenuclearpowerplantsitepriortoinstallation oruseofsuchitems.1.7-106July,1991 ExcetionInterretatioTherequireddocumentary evidenceisavailable atthesitepriortouse,butnotnecessarily priortoinstallation. Thisallowsinstallation toproceedwhileanymissingdocuments arebeingobtained, butprecludes dependence ontheitemforsafetypurposes. 21.Sec.5.2.15lt"Plantprocedures shallbereviewedbyanindividual knowledgeable intheareaaffectedbytheprocedure nolessfrequently thaneverytwoyearstodetermine ifchangesarenecessary ordesirable." ExcetionInterretationBiennialreviewsarenotperformed inthatIKNhasprogrammatic controlrequirements inplacethatmakethebiennialreviewprocessredundant fromaregulatory perspective. Theseprogrammatic controlswereeffectedinanefforttoensurethatplantinstructions andprocedures arereviewedforpossiblerevisionwhenpertinent sourcematerialisrevised,therefore maintaining theprocedures current.Webelievethatthisapproach, inadditiontoanannualrandomsamplingofprocedures, betteraddresses theintentofthebiennialreviewprocessandismoreacceptable frombothatechnical andpractical perspective thanastatictwo-yearreviewprocess.2m.Sec.5.2.16~RRecordsshallbemade,andequipment suitablymarked,toindicatecalibration status.ExcetionInterretationSeeItem6b.1.7-107July,1991 2n.Sec.5.3.5(4)Thissectionrequiresthatwheresectionsofdocuments suchasvendormanuals,operating andmaintenance instructions, ordrawingsareincorporated

    directly, orbyreference intoamaintenance procedure, theyshallreceivethesamelevelofreviewandapprovalasoperating procedures.

    ExcetionInterretationSuchdocuments arereviewedbyappropriately qualified personnel priortousetoensurethat,whenusedasinstructions, theyprovideproperandadequateinformation toensuretherequiredqualityofwork.Maintenance procedures whichreference thesedocuments receivethesamelevelofreviewandapprovalasoperating procedures. 3.3a.N45.2.1,Sec.3~RN45.2.1establishes criteriaforclassifying itemsinto"cleanliness levels,"andrequiresthatitemsbesoclassified. ExcetionInterretationInsteadofusingthecleanliness levelclassification systemofN45.2.1,therequiredcleanliness forspecificitemsandactivities isaddressed onacase-by-case basis.Cleanliness ismaintained, consistent withtheworkbeingperformed, soastopreventtheintroduction offoreignmaterial. Asaminimum,cleanliness inspections areperformed priortoclosureof"nuclear" systemsandequipment. Suchinspections aredocumented. 1.7-108July,1991 Sec.5~ll"Fittingandtack-welded joints(whichwillnotbeimmediately sealedbywelding)shallbewrappedwithpolyethylene orothernonhalogenated plasticfilmuntiltheweldscanbecompleted." EcetionInterretationIKHsometimes usesothernonhalogenated

    material, compatible withtheparentmaterial, sinceplasticfilmissubjecttodamageanddoesnotalwaysprovideadequateprotection.

    4.N45.2.2,GeneralN45.2.2establishes requirements andcriteriaforclassifying safetyrelateditemsintoprotection levels.ExcetionInterretationInsteadofclassifying safetyrelateditemsintoprotection levels,controlsoverthepackaging,

    shipping, handlingandstorageofsuchitemsareestablished onacase-by-case basiswithdueregardfortheitem'scomplexity, useandsensitivity todamage.Priortoinstallation oruse,theitemsareinspected andserviced, asnecessary, toassurethatnodamageordeterioration existswhichcouldaffecttheirfunction.

    4a.Sec.3.9andAppendixA3.9"Theitemandtheoutsideofcontainers shallbemarked."(FurthercriteriaformarkingandtaggingaregivenintheAppendix.) ExcetionInterretationTheserequirements wereoriginally writtenforitemspackagedandshippedtoconstruction projects. Fullcompliance isnotalways1.7-109July,1991

    necessary inthecaseofitemsshippedtooperating plantsandmay,insomecases,increasetheprobability ofdamagetotheitem.Therequirements areimplemented totheextentnecessary toassuretraceability andintegrity oftheitem.4b.Sec.5.2.2~llP"Receiving inspections shallbeperformed inanareaequivalent tothelevelofstorage." xcetionInterretationReceiving inspection areaenvironmental controlsmaybelessstringent thanstorageenvironmental requirements foranitem.However,suchinspections areperformed inamannerandinanenvironment whichdonotendangertherequiredqualityoftheitem.4c.Sec.6.2.4"Theuseorstorageoffood,drinksandsalttabletdispensers inanystorageareashall'otbepermitted." ExcetionInterretationPackagedfoodforemergency orextendedovertimeusemaybestoredinmaterialstockrooms.Thepackaging assuresthatmaterials arenotcontaminated. Foodwillnotbe"used"intheseareas.4d.Sec.6.3.4II"Allitemsandtheircontainers shallbeplainlymarkedsothattheyareeasilyidentified withoutexcessive handlingorunnecessary openingofcratesandboxes."ExcetionInterretationSeeN45.2.2,Section3.9(Exception 4b.).1.7-110July,1991 4,.Sec.6.4.1"Inspections andexaminations shallbeperformed anddocumented onaperiodicbasistoassurethattheintegrity oftheitemanditscontainer ...isbeingmaintained." ExcetionInterretationTherequirement impliesthatallinspections andexaminations of'temsinstoragearetobeperformed onthesameschedule. Instead,theinspections andexaminations areperformed inaccordance withmaterialstorageprocedures whichidentifythecharacteristics tobeinspected andincludetherequiredfrequencies. Theseprocedures arebasedontechnical considerations 'whichrecognize thatinspections andfrequencies neededvaryfromitemtoitem.5.5a.N45.2.3,Sec.2.1Cleanliness requirements forhousekeeping activities shallbeestablished onthebasisoffivezonedesignations. ExcetionInterretationInsteadofthefive-level zonedesignation systemreferenced inANSIN45.2.3,INbasesitscontrolsoverhousekeeping activities onaconsideration ofwhatisnecessary andappropriate fortheactivityinvolved. Thecontrolsareeffectedthroughprocedures orinstructions. Factorsconsidered indev'eloping theprocedures andinstructions includecleanliness control,personnel safety,fireprevention andprotection, radiation controlandsecurity. Theprocedures andinstructions makeuseofstandardjanitorial andworkpractices totheextentpossible. However,inpreparing theseprocedures, consideration isalsogiventotherecommendations ofSection2.1ofANSIN45.2.3.1.7-111July,1991 6.N45.2.46a.Sec.2.2Section2.2establishes prerequisites whichmustbemetbeforetheinstallation, inspections andtestingofinstrumentation andelectrical equipment mayproceed.Theseprerequisites includepersonnel qualification, controlofdesign,conforming andprotected materials andavailability ofspecified documents. ExcetionInterretationDuringtheoperations phase,thisrequirement isconsidered tobeapplicable tomodifications andinitialstart-upofelectrical equipment. Forroutineorperiodicinspection andtesting,the,prerequisite conditions willbeachieved, asnecessary. 6b.Sec.6.2.1"Itemsrequiring calibration shallbetaggedorlabeledoncompletion, indicating dateofcalibration andidentityofpersonthatperformed calibration." ExcetionInterretationFrequently, physicalsizeand/orlocationofinstalled plantinstrumentation precludes attachment ofcalibration labelsortags.Instead,eachinstrument isuniquelyidentified andistraceable toitscalibration record.Ascheduled calibration programassuresthateachinstrument's calibration iscurrent.47.7a.N45.2.5,Sec.2.5.2Reuirement"Whendiscrepancies, malfunctions orinaccuracies ininspection andtestingequipment arefoundduringcalibration, allitemsinspected July,1991 withthatequipment sincethelastpreviouscalibration shallbeconsidered unacceptable untilanevaluation hasbeenmadebytheresponsible authority andappropriate actiontaken."xcetionInterretationILHusestherequirements ofN18.7,Section5.2.16,ratherthanN45.2.5,Section2.5.2.TheN18.7requirements aremoreapplicable toanoperating plant.7b.Sec.5.4~ll"Handtorquewrenchesusedforinspection shallbecontrolled andmustbecalibrated atleastweeklyandmoreoftenifdeemednecessary. Impacttorquewrenchesusedforinspection mustbecalibrated atleasttwicedaily."ExcetionInterretationTorquewrenchesarecontrolled asmeasuring andtestequipment inaccordance withANSIN18.7,Section5.2.16.Calibration intervals arebasedonuseandcalibration historyratherthanasperN45.2.5.8.N45.2.6,Sec.1.2~ll"Therequirements ofthisstandardapplytopersonnel whoperforminspections, examinations andtestsduringfabrication priortoorduringreceiptofitemsattheconstruction site,duringconstruction, duringpreoperational andstart-uptestingandduringoperational phasesofnuclearpowerplants."cetionInterretationPersonnel participating intestingwhotakedataormakeobservations, wherespecialtrainingisnotrequiredtoperformthisfunction, neednotbequalified inaccordance withANSIN45.2.6,butneedonlybetrainedtotheextentnecessary toperformtheassignedfunction. 1.7-113July,1991 0 gRe.Guide1.58-GeneralIIgualification ofnuclearpowerplantinspection, examination andtestingpersonnel. 9a.C.2.a(7)RRRi"Regulatory Guide1.58endorsestheguidelines ofSNT-TC-1A asanacceptable methodoftrainingandcertifying personnel conducting leaktests.ExcetionInterretationI&Htakesthepositionthatthe"Level"designation guidelines asrecommended inSNT-TC-IA, paragraph 4donotnecessarily assureadequateleaktestcapability. I&Hmaintains thatdepartmental supervisors arebestabletojudgewhetherengineers andotherpersonnel arequalified todirectand/orperformleaktests.Therefore, I&Hdoesnotimplement therecommended "Level"designation guidelines. ItisI&H'sopinionthatthetrainingguidelines ofSNT-TC-lA, TableI-G,paragraph 5.2specifically areorientedtowardsthebasicphysicsinvolvedinleaktesting,andfurther,towardsindividuals whoarenotgraduateengineers. I&Hmaintains thatitmeetstheessenceofthesetrainingguidelines. Thepreparation ofleaktestprocedures andtheconductofleaktestsatCookNuclearPlantisunderthedirectsupervision ofPerformance Engineers whoholdengineering degreesfromaccredited engineering schools.. Thebasicphysicsofleaktestinghavebeenincorporated intotheapplicable testprocedures. Thereviewandapprovalofthedataobtainedfromleaktestsisperformed bydepartment supervisors whoarealsograduateengineers. I&Hdoesrecognize theneedtoassurethatindividuals involvedinleaktestsarefullycognizant ofleaktestprocedural requirements andthoroughly familiarwiththetestequipment involved. Plant1.7-114July,1991 performance engineers receiveroutine,informalorientation ontestingprogramstoensurethattheseindividuals fullyunderstand therequirements ofperforming aleaktest.gb.C5,C6,C7,C8,C10ExcetionInterretationI&Htakesthepositionthattheclassification ofinspection, exami-nationandtestpersonnel (inspection personnel) into"Levels"basedontherequirements statedinSection3.0ofANSIN45.2.6doesnotnecessarily assureadequateinspection capability. I&Hmaintains thatdepartmental andfirstlinesupervisors arebestabletojudgetheinspection capability ofthepersonnel undertheirsupervision, andthat"Level"classification wouldrequireanoverlyburdensome administrative workload,couldinhibitinspection activities, andprovidesnoassurance ofinspection capabilities. Therefore, I&Hdoesnotimplement the"Level"classification conceptforinspection, examination andtestpersonnel. Themethodology underwhichinspections, examinations andtestsareconducted attheCookNuclearPlantrequirestheinvolvement offirstlinesupervisors, engineering personnel, departmental supervisors andplantmanagement. Inessence,thelastseven(7)projectfunctions showninTable1toANSIN45.2.6areassignedtosupervisory andengineering personnel, andnottopersonnel oftheinspector category. Thesemanagement supervisory andengineering personnel, asaminimum,meettheeducational andexperience requirements of"LevelIIandLevelIII"personnel, asrequired, tomeetthecriteriaofANSI18.1whichexceedsthoseofANSIN45.2.6.InI&H'sopinion,nousefulpurposeisservedbyclassification ofmanagement, supervisory andengineering personnel into"Levels." Therefore, I&Htakesthefollowing positions relativetoregulatory positions C5,6,7,8and10ofRegulatory Guide1.58.1.7-115July,1991 C-5Basedonthediscussion in9b,thispositionisnotapplicable totheCookNuclearPlant.C-6Replacement personnel forCookNuclearPlantmanagement, supervisory andengineering positions subjecttoANSI18.1willmeettheeducational andexperience requirements ofANSI18.1andtherefore, thoseofANSIN45.2.6.Replacement inspection personnel will,asaminimum,meettheeducational andexperience requirements ofANSIN45.2.6,Section3.5.I-"LevelI."C-7ISN,asageneralpractice, complieswiththetrainingrecommendations assetforthinthisregulatory position. C-8AllI&Hinspection, examination andtestpersonnel areinstructed inthenormalcourseofemployeetraininginradiation protection andthemeanstominimizeradiation doseexposure. C-10I&Mmaintains documentation toshowthatinspection personnel meettheminimumrequirements of"LevelI,"andthatmanagement, supervisory andengineering personnel meettheminimumrequirements ofANSI18.1.10.N45.2.8,10a.Sec.2.9eSection2.9eofN45.2.8listsdocuments relatingtothespecificstageofinstallation activitywhicharetobeavailable attheconstruction site.1.7-116July,1991 ExcetionInterretationAllofthedocuments listedarenotnecessarily requiredattheconstruction sitefor'installation and-testing.AEPSCandI&Nassurethattheyareavailable ~tthesite,asnecessary. 10b.Sec.2.9eEvidencethatengineering ordesignchangesaredocumented andapprovedshallbeavailable attheconstruction sitepriortoinstallation. ExcetionInterretationEquipment maybeinstalled beforefinalapprovalofengineering ordesignchanges.However,thesystemisnotplacedintoserviceuntilsuchchangesaredocumented andapproved. 10c.Sec.4.5.1Reuirement"Installed systemsandcomponents shallbecleaned,flushedandcondi-tionedaccording totherequirements ofANSIN45.2.1.Specialconsideration shallbegiventothefollowing requirements: (Requirements aregivenforchemicalconditioning, flushingand"processcontrols.) ExcetionInterretationSystemsandcomponents arecleaned,flushedandconditioned asdetermined onacase-by-case basis.Measuresaretakentohelpprecludetheneedforcleaning, flushingandconditioning throughgoodpractices duringmaintenance ormodification activities. July,1991 I11.lla.N45.2.9Sec.5.4,Item2Recordsshallnotbestoredloosely."Theyshallbefirmlyattachedinbindersorplacedinfoldersorenvelopes forstorageonshelvingincontainers." 'Steelfilecabinetsarepreferred. ExcetionInterretatioRecordsaresuitablystoredinsteelfilecabinets, oronshelvingincontainer s.Hethodsotherthanbinders,folders,orenvelopes (forexample,dividers) maybeusedtoorganizetherecordsforstorage.lib.Sec.6.2"Alistshallbemaintained designating thosepersonnel whoshallhaveaccesstothefiles".IExcetionInterretationRulesareestablished governing accesstoandcontroloffilesaspro-videdforinANSIN45.2.9,Section5.3,Item5.Theserulesdonotalwaysincludearequirement foralistofpersonnel whoareauthorized access.Itshouldbenotedthatduplicate filesand/ormicroforms mayexistforgeneraluse.llc.Sec.5.6Whenasinglerecordsstoragefacilityismaintained, atleastthefollowing featuresshouldbeconsidered initsconstruction: etc.xcetionInterretationTheCookNuclearPlantHasterFileRoomandotheroff-siterecordstoragefacilities complywiththerequirements ofNUREG-0800 (7/81),Section17.1.17.4. 1.7-118.July,1991 12.ReG'd.44ANSIN45.~~~~12a.Sec.C3a22.1()~ltApplicable elementsofanorganization's gualityAssurance Programfor"designandconstruction phaseactivities shouldbeauditedatleastannuallyoratleastoncewithinthelifeoftheactivity', whichever isshorter." ExcetionInterretationSincemostmodifications arestraightforward,theyarenotauditedindividually. Instead,selectedcontrolsovermodifications areauditedperiodically. 12b.Sec.C3b(1)Thissectionidentifies procurement contracts whichareexemptedfrombeingaudited.ExcetionInterretatioInadditiontotheexemptions ofReg.Guide1.144,AEPSC/I&M considers thattheNationalInstitute ofStandards andTechnology, orotherStateandfederalAgencieswhichmayprovideservicestoAEPSC/I&M, arenotrequiredtobeaudited.12c.Sec.4.5.1Responses toadverseauditfindings, givingresultsofthereviewandinvestigation, shallclearlystatethecorrective actiontakenorplannedtopreventrecurrence. "Intheeventthatcorrective actioncannotbecompleted withinthirtydays,theauditedorganization's responseshallincludeascheduled dateforthecorrective action."1.7-119July,1991 ExcetionnterretationAEPSC/I&M takethepositionthatcertaincircumstances warrantmorethanthirty(30)daystocompletely investigate thecauseand/ortotalimpactofanadversefinding.Forthesecircumstances, aninitialthirty(30)dayresponsewillbeprovidedwhichaddresses ascheduleforknowncorrective actions,thereasonwhyadditional investigation timeisneeded,andascheduleforcompletion oftheinvestigation. Theseinitialresponses requiretheapprovaloftheDirector-gualityAssurance. 13.N45.2.13, 13a.Sec.3.2.2~llN45.2.13requiresthattechnical requirements bespecified inprocurement documents b.reference totechnical requirement documents. Technical requirement documents aretobeprepared, reviewedandreleasedundertherequirements established byANSIN45.2.11.ExcetionInterretationForreplacement partsandmaterials, AEPSC/I&N followANSIN18.7,Section5.2.13,Subitem1,whichstates:"Wheretheoriginalitemorpartisfoundtobecommercially 'offtheshelf'rwithoutspecifically identified gArequirements, spareandreplacement partsmaybesimilarly

    procured, butcareshallbeexercised toensureatleastequivalent performance."

    13b.Sec.3.2.3"Procurement documents shallrequirethatthesupplierhaveadocumented gualityAssurance Programthatimplements partsorallofANSIN45.2aswellasapplicable gualityAssurance Programrequirements ofothernationally recognized codesandstandards." 1.7-120July,1991 nnterretationRefertoItem2j.13c.Sec.3.3(a)~llReviewsofprocurement documents shallbeperformed priortoreleaseforbidandcontractaward.ExcetionInterretationDocuments maybereleasedforbidorcontractawardbeforecompleting thenecessary reviews.However,thesereviewsarecompleted beforetheitemorserviceisputintoservice,orbeforeworkhasprogressed beyondthepointwhereitwouldbeimpractical toreversetheactiontaken.13d.Sec.3.3(b)Reviewofchangestoprocurement documents shallbeperformed priortoreleaseforbidandcontractaward.xcetionInterretationThisrequirement appliesonlytoqualityrelatedchanges(i.e.,changestotheprocurement documentprovisions identified inANSIN18.7,Section5.2.13.1,Subitems1through5).Thetimingofreviewswillbethesameasforreviewoftheoriginalprocurement documents. 13e.Sec.10.1~lt"Whererequiredbycode,regulation, orcontractrequirement, documentary evidencethatitemsconformtoprocurement documents shallbeavailable atthenuclearpowerplantsitepriortoinstallation oruseofsuchitems,regardless ofacceptance methods." 1.7-121July,1991 ,ttretioRefertoItem2j."Post-installation testrequirements andacceptance documentation shallbemutuallyestablished bythepurchaser andsupplier." ExcetionInterretationInexercising itsultimateresponsibility foritsgualityAssurance Program,AEPSC/IMestablishes post-installation testrequirements givingdueconsideration tosupplierrecommendations. 14.14a.14b.eGud146ANSN45..3andANSIN45...1~ANEII5..3,I.I.IThisstandardprovidesrequirements andguidanceforthequalification ofauditteamleaders,henceforth identified as"leadauditors." ANSIN45.2.12,Sec.4.2.2~RAleadauditorshallbeappointed teamleader.EcetonterretatioTheAEPSCauditprogramisdirectedbytheAEPSCDirector-gualityAssuranceandisadministered bydesignated gADivisionsectionmanagers/supervisor whoarecertified leadauditors. Auditsare,inmostcases,conducted byindividual

    auditors, notby"auditteams."Theseauditorsarecertified inaccordance withestablished procedures andareassignedbytheresponsible gAsectionmanager/supervisor basedontheirdemonstrated auditcapability andgeneralknowledge oftheauditsubject.Incertaincases,thisresultsinanindividual otherthana"leadauditor"conducting theactualauditfunction.

    1.7-122July,1991

    .9104220022 Attachment 1toAEP:NRC:0847V SpecificChangestotheQAPD Attachment 1.toAEP:NRC:0847V Page1SectionsProosedChanessPolicyStatement 1.7.1.2.1 1.7.1.2.2 1.7.1.2.3 1.7.1.2.5 1.7.2.2.1 FigureNo.1.7-1FigureNo.1.7-3Titlechangedtoreflectnewcorporate management structure; i.e.,from"Chairman oftheBoardandChiefExecutive Officer"to"President andChiefExecutive Officer." 1.7.1.2.5 1.7.2.11.7.2.2.5 1.7.6.2.1 Clarification: Addedtheword"Updated"; i.e.,"UpdatedFSAR..."1.7.1.2.2 Fourthparagraph clarification: Addedtheword"Program"; i.e.,"CookNuclearPlantequalityControlProgram..." 1.7.1.2.5 ~~~~gualityAssurance DivisionSecondparagraph, fifteenth itemclarification: Includedthewords"auditsor";i.e.,"Conductin-process gAauditsorsurveillances..." 1.7.1.2.5 gAAuditorgualification andCertification ProgramDeletedthewords"Orientation, Training" fromthesubheading; addedtheword"Auditor." Alsodeletedreference togAproviding ageneraltrainingprogramtoAEPSCpersonnel engagedinactivities affecting thequalityofsafety-related item.Thisresponsibility hasbeenreassigned totheNuclearOperations Divisionandisnowaddressed underthoseresponsibilities (page1.7-18)1.7.1.2.5 NuclearOperations DivisionDeletedreference toNuclearOperations Divisionmiddlemanagement. Thisallowsforlowerlevelreorganization, butmaintains delineated divisional responsibilities. 00 Attachment 1.toAEP:NRC:0847V Page2SectionsProosedChaness1.7.1.2.5 (cont.)NuclearOperations DivisionIncludedadditional item(¹42)toreflectcurrentNuclearOperations Divisionresponsibilities regarding development andimplementation oftrainingforAEPSCpersonnel engagedinactivities affecting thequalityofsafety-related items.1.7.1.2.5 AEPSCEngineering andDesignIncludedadditional paragraph regarding AEPSCElectrical Engineering andSystemPlanningDepartments'esponsibilities withregardtoCookNuclearplant.1.7.1.2.5 CivilEngineering Department Deletedreference toCivilEngineering Department middlemanagement. Delineated Department responsibilities aremaintained. Alsoaddedthewords"technical aspectsforthe"tofurtherclarifyCivilEngineering Department's responsibilities withregardtoCookNuclearPlant.1.7.1.2.5 DesignDepartment Deletedreference toDesignDepartment middlemanagement. Inaddition, Item,(¹7)wasrewritten toclarifytheDesignDepartment's responsibilities withregardtotheNSDRCandtheNSDRCsubcommittees. 1.7.1.2.5 NuclearEngineering Department Deletedreference toNuclearEngineering Department middlemanagement. Inaddition, included"nuclearsteamsupply"inItem(¹2)tofurtherclarifytheNuclearEngineering Department's responsibilities withregardtoCookNuclearPlant.~~ Attachment 1toAEP:NRC:0847V Page3Sections1.7.1.2.5 ProjectManagement andConstruction Department ProosedChanessaDeletedreference toProjectManagement andConstruction Department middlemanagement. Alsoaddeditemregarding NSDRCparticipation. 1.7.1.2.5 Purchasing andStoresDepartment Includedadditional items(i.e.,82and89)toreflectthePurchasing andStoresDepartment's currentresponsibilities withregardtotheCookNuclearPlant.Inaddition, forclarification inItem84,deletedreference to"I&HPurchasing Department" andreplaceditwith"CookPlantSitePurchasing Section". Alsodeletedreference tonotification ofsuppliers, I&HPurchasing Department and/orCookNuclearPlantStoresSupervisor withregardtosupplieracceptability status.1.7.2.2.4 ~~~~Includedadditional paragraphs forfurtherclarification ofNuclearEngineering Procedures (NEPs)1.7.2.2.5 Firstparagraph: Deletedthirdsentence, "Imposition oftheseguides/standard..." toeliminate confusion ormisinterpretation bythereader/reviewer. Thisstatement nowexpandedandappearsinSection1.7.4.2.3. 1.7.3.2.1 1.7.3.2.2 Changestotheseareincludedtoaccommodate moreefficient handlingofdesignchangesthatwouldhaveaninsignificant seismiceffectonsafetyrelateditems.Specifically, changesthatwouldintroduce onlyinsignificant seismiceffects(e.g.,placinganon-safety relatedinstrument onasafetyrelatedcontrolpanel)wouldbeprocessed viathatPlantModification (PH)process.ThePMprocesshasadequatecontrolstoassurethatthechangesarelimitedto Attachment 1.toAEP:NRC:0847V ~~Page4SectionsProosedChaness1.7.3.2.1 (cont.)1.7.3.2.2 insignificant effects.ThePHprocessalsoprovidesformoreexpedient andefficient processing, thusallowingourengineers moretimetofocustheirattention onmoresignificant safetyissues.1.7.3.2.13 Editorial change;clarified thepreviously usedword"mechanism." 1.7.4.2.1 Firstparagraph: 3)Includedthephrase"...orbythededication planprocess"tofurtherdefinetheimplementation ofprocurement controlinstructions andprocedures. Inaddition, thethirdparagraph wasrewritten tofurtherclarifyresponsibilities. 1.7.4.2.2 Firstparagraph: Deleted"asthesourcedocument..." inthefirstsentenceand"...fortheCookNuclearPlant(DCCSpecifications)" inthesecondsentence, forgrammatical clarification. Inaddition, thesecondparagraph wasrewritten tofurtherclarifyprocurement ofsafetyrelateditemsorservices. 1.7.4.2.3 Itemb):Statement addedtoaccurately depicthowimposition isimplemented. 1.7.7.2.1 Secondparagraph (lastsentence): rewritten forgrammatical clarification. 1.7.7.2.2 Deletedthewords"andupgrading" Attachment 1.toAEP:NRG:0847V Page5SectionsProosedChaness1.7.7.2.8 Rewritten tofurtherclarifysupplierrecordretention responsibility. 1.7.7.2.9 Rewritten toclarifyevaluation ofsupplier's capability tofurnishvalidcertificates. 1.7.9.2.2 1.7.9.2.3 Deletedreference to"AEPSCStaffEngineer-ChiefMetallurgist (NDEAdministrator)"; replacedwith"AEPSCCognizant Engineer-WeldingandNDEAdministrator" toreflectcurrentpositiontitle.1.7.9.2.2 Fourthparagraph, firstsentence: Forfurtherclarification, addedthephrase"orintheapprovedcontractor's manual."1.7.9.2.3 Secondparagraph: Replaced"AEPSCWeldingSpecification" with"AEPWeldingManual."Inaddition, includedthephrase"inaccordance withAEPSCprocedures." 1.7.13.2.3 Forfurtherclarification, includedthephrase,"orareotherwise specified ontheprocurement order."1.7.17.2.1 Itemh:Included"dedication plans."Itemi:Deletedthephrase"(whicharealsoclassified assafetyrelateditem)."1.7,18.2.4 Secondparagraph: Included"NSDRCmembership." FigureNo.1.7-4~~~Deletedreference togualityAssurance Divisionsupportpersonnel ontheorganization flowchart. Attachment l,toAEP:NRC:0847V Page6SectionsProosedChanessAppendixBItem12:Includedreference to"ANSIN45.2.12." AppendixBItem12b:Editorial change;corrected nameofagency.AppendixBItem12c:AddedSection4.5.1regarding responses toadverseauditfinding.Thisissuewaspreviously deemedacceptable bytheNRCwhensubmitted inAEPsubmittal letterAEP:NRC:0847T datedOctober30,1990.TheentiregAPDwasrepaginated. Proposedchangesincontentarereflected bymarginbarsinthemargintotherightofthetext.Pleasenote:Amarginbarfollowedbyaasterisk(i.e.,/*)reflectsaneditorial change,(e.g.,grammar;punctuation) only.}}