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{{#Wiki_filter:k'LROCHESTERGASANDELECTRICCORPORATIONROBERTChtECREDYVi<ehetidentCinnet4uclee<Ptoduction/'.tone>t*te~89EASTAVENUE,ROCHESTERN.Y.14649-0001TELEPHONEAREACODE71B5462700September11,1990Mr.ThomasT.MartinRegionalAdministratorU.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406'ubject:120-dayResponsetoInspectionReport50-244/89-81SafetySystemFunctionalInspectionontheRHRSystemR.E.GinnaNuclearPowerPlantDocketNo.50-244Reference:(a)NRCInspectionReport50-244/89-81,datedMay9,1990(b)RG&EletterfromR.C.Mecredy-toNRC,T.T.Martin,datedJune8,1990DearMr.Martin:Reference(a)requestedaresponsetotwoNoticesofViolationandseveralunresolveditemswithin30daysandawrittenevaluationofthedeficienciesidentifiedinSection2.1oftheInspectionReportwithin120days.Inour30-dayresponsetotwoNoticesofViolation,Ref.(b),wesummarizedourproposedresolutionorscheduleforresolutionfortheunresolveditems89-81-01through10.TheNRCunresolveditemdescriptionandourproposedresolutionofeachofthesewasdiscussedinenclosuresCandEofRef.(b).AnupdateoftheappropriateunresolveditemsisprovidedasAttachmentAtothisresponse.SpecificactionsregardingallNRCunresolveditemsarebeingtrackedtocompletionbyRG&E.~U~cIQet\Aoo1'Q~C3oPo+TheidentifiedweaknessesinSection2.1oftheInspectionReportcollectivelyraisedanNRCconcernastotheeffectivenessofRG&E'scurrentpracticestoestablishengineeringassurance.Thiswasidentifiedasunresolveditem89-81-11andisthefocusofthisresponse.RG&Erecognizesthatunresolveditem89-81-11,engineeringassurance,ischaracterizedbybroadprogrammaticissues.RG&EhascompletedanevaluationofthedeficienciesandconcernsraisedintheInspectionReportbyperforminganinternalassessmentoftheunderlyingissuesidentifiedinSection2.1andtheexamplesdiscussedinSection2.2.OurassessmenthasbeendocumentedinangQ~o//(]  
{{#Wiki_filter:k'LROCHESTER
GASANDELECTRICCORPORATION
ROBERTChtECREDYVi<ehetidentCinnet4uclee<Ptoduction
/'.tone>t*te~89EASTAVENUE,ROCHESTER
N.Y.14649-0001
TELEPHONE
AREACODE71B5462700September
11,1990Mr.ThomasT.MartinRegionalAdministrator
U.S.NuclearRegulatory
Commission
RegionI475Allendale
RoadKingofPrussia,PA19406'ubject:
120-dayResponsetoInspection
Report50-244/89-81
SafetySystemFunctional
Inspection
ontheRHRSystemR.E.GinnaNuclearPowerPlantDocketNo.50-244Reference:
(a)NRCInspection
Report50-244/89-81,
datedMay9,1990(b)RG&EletterfromR.C.Mecredy-toNRC,T.T.Martin,datedJune8,1990DearMr.Martin:Reference
(a)requested
aresponsetotwoNoticesofViolation
andseveralunresolved
itemswithin30daysandawrittenevaluation
ofthedeficiencies
identified
inSection2.1oftheInspection
Reportwithin120days.Inour30-dayresponsetotwoNoticesofViolation,
Ref.(b),wesummarized
ourproposedresolution
orscheduleforresolution
fortheunresolved
items89-81-01through10.TheNRCunresolved
itemdescription
andourproposedresolution
ofeachofthesewasdiscussed
inenclosures
CandEofRef.(b).Anupdateoftheappropriate
unresolved
itemsisprovidedasAttachment
Atothisresponse.
Specificactionsregarding
allNRCunresolved
itemsarebeingtrackedtocompletion
byRG&E.~U~cIQet\Aoo1'Q~C3oPo+Theidentified
weaknesses
inSection2.1oftheInspection
Reportcollectively
raisedanNRCconcernastotheeffectiveness
ofRG&E'scurrentpractices
toestablish
engineering
assurance.
Thiswasidentified
asunresolved
item89-81-11andisthefocusofthisresponse.
RG&Erecognizes
thatunresolved
item89-81-11,
engineering
assurance,
ischaracterized
bybroadprogrammatic
issues.RG&Ehascompleted
anevaluation
ofthedeficiencies
andconcernsraisedintheInspection
Reportbyperforming
aninternalassessment
oftheunderlying
issuesidentified
inSection2.1andtheexamplesdiscussed
inSection2.2.Ourassessment
hasbeendocumented
inangQ~o//(]  
Cl  
Cl  
internalreportentitled"SystematicAssessmentsofEngineeringAssuranceIssues'andRHRSSFIConcerns"dated9/11/90.RG&Ebelievesthattheunderlyingconcernsnecessitatebothinterim.andlongtermactivitiestoresolve.Ourapproachinperformingthe-internalassessmentandasummaryofthehighpriorityactionsarepresentedinAttachmentB.ThisattachmentisasummaryoftheconsiderableeffortsofanRG&ESSFIAssessmentTeamcomposedofagroupofexperiencedRG&Estaffandmanagementpersonnel.Theprimarytaskof'theRG&ESSFIAssessmentTeamwastoprepareareporttoRG&E'smanagementwhichrecommendedthemosteffectiveinterimactionsneededtobegintheprocessofstrengtheningtheengineeringprocessesand.controls.TheRG&ESSFIAssessmentTeamwascomposedofnineseniorengineersandstaff.Theteammettore-examinetheinspectionreportandcategorizethedeficienciesbytopicalareas.TheteamalsoevaluatedareportpreparedbyanRG&Econsultantwhoindependentlyidentifiedtheprogrammaticconcerns.Theassessmentconsistedofindividualevaluationsbyteammembersaswellasworkingsessionsasagroup.TheRG&EAssessmentTeamgroupedtheNRCidentifieddeficienciesintothefollowingtopicalareas:~Improved~Improved~Improved~Improved~Improved~ImprovedMethodofIdentifyingand.AssessingSafetyConcernsDesignControlandReviewsDesignInterfaceControlDocumentationAssociatedwithDesignBasesDocumentationAssociatedwithModificationsEngineering/PlantCommunicationsTheteamthenestablishedinterimactionsandlongtermcorrectiveactionsforeachtopicalarea.Theteamprioritizedtheinterimactionsandestablishedaproposedschedule.Theinterimactionswererecommendedbaseduponachievingafundamentalimprovementontheengineeringprocess.Interimactionsarethoseactionswhichcanbeimplementedimmediatelyorwithinaperiod.ofuptoayear.Long-termcorrectiveactionswerealsorecommended,.Manyofthelongertermrecommendationsarealreadyembodiedintwomajorprograms:ConfigurationManagement(CM)andtheEngineeringProceduresUpgradeProgram.AreportontheConfigurationManagementprogramdescriptionsandschedulewaspresentedtomembersofRegionIandNRRonMarch6andMarch27,1990,respectively.(IndividualprojectswithintheCMprogrammaybeexaminedwithintheenclosuretoInspectionReport90-03,datedApril18,1990).TheEngineeringProceduresUpgradeprogramhasbeeninitiatedandwillincludeanexternalassessmentofourcurrentproceduresbyanindependentconsultant.Itisexpectedthatthisassessmentwillbecompletebyyear-end.TheresultsofRG&E'sinternalSSFIAssessmentwillbecomeaninputtotheEngineeringProceduresUpgradeandtheConfigurationManagementPrograms.AttachmentBisasummaryreportoftheAssessmentTeamactivitiesandrecommendations.  
internalreportentitled"Systematic
Assessments
ofEngineering
Assurance
Issues'andRHRSSFIConcerns"
dated9/11/90.RG&Ebelievesthattheunderlying
concernsnecessitate
bothinterim.and
longtermactivities
toresolve.Ourapproachinperforming
the-internal
assessment
andasummaryofthehighpriorityactionsarepresented
inAttachment
B.Thisattachment
isasummaryoftheconsiderable
effortsofanRG&ESSFIAssessment
Teamcomposedofagroupofexperienced
RG&Estaffandmanagement
personnel.
Theprimarytaskof'theRG&ESSFIAssessment
TeamwastoprepareareporttoRG&E'smanagement
whichrecommended
themosteffective
interimactionsneededtobegintheprocessofstrengthening
theengineering
processes
and.controls.
TheRG&ESSFIAssessment
Teamwascomposedofnineseniorengineers
andstaff.Theteammettore-examine
theinspection
reportandcategorize
thedeficiencies
bytopicalareas.Theteamalsoevaluated
areportpreparedbyanRG&Econsultant
whoindependently
identified
theprogrammatic
concerns.
Theassessment
consisted
ofindividual
evaluations
byteammembersaswellasworkingsessionsasagroup.TheRG&EAssessment
TeamgroupedtheNRCidentified
deficiencies
intothefollowing
topicalareas:~Improved~Improved~Improved~Improved~Improved~ImprovedMethodofIdentifying
and.Assessing
SafetyConcernsDesignControlandReviewsDesignInterface
ControlDocumentation
Associated
withDesignBasesDocumentation
Associated
withModifications
Engineering/Plant
Communications
Theteamthenestablished
interimactionsandlongtermcorrective
actionsforeachtopicalarea.Theteamprioritized
theinterimactionsandestablished
aproposedschedule.
Theinterimactionswererecommended
baseduponachieving
afundamental
improvement
ontheengineering
process.Interimactionsarethoseactionswhichcanbeimplemented
immediately
orwithinaperiod.ofuptoayear.Long-term
corrective
actionswerealsorecommended,.
Manyofthelongertermrecommendations
arealreadyembodiedintwomajorprograms:
Configuration
Management
(CM)andtheEngineering
Procedures
UpgradeProgram.AreportontheConfiguration
Management
programdescriptions
andschedulewaspresented
tomembersofRegionIandNRRonMarch6andMarch27,1990,respectively.
(Individual
projectswithintheCMprogrammaybeexaminedwithintheenclosure
toInspection
Report90-03,datedApril18,1990).TheEngineering
Procedures
Upgradeprogramhasbeeninitiated
andwillincludeanexternalassessment
ofourcurrentprocedures
byanindependent
consultant.
Itisexpectedthatthisassessment
willbecompletebyyear-end.
TheresultsofRG&E'sinternalSSFIAssessment
willbecomeaninputtotheEngineering
Procedures
UpgradeandtheConfiguration
Management
Programs.
Attachment
BisasummaryreportoftheAssessment
Teamactivities
andrecommendations.  
   
   
RG&Ebelievesthatmanyofthedeficienciesnotedundertheengineeringassuranceunresolveditem89-81-11hadbeenrecognizedpriortotheRHRSSFIandhavebeenenvelopedunderthevariousConfigurationManagementProjects,suchastheSetpointVerificationProgramandDesignBasisDocumentationProjects.Wehaverecognizedthatinterimactionsarenecessarytosufficientlystrengthentheengineeringprocesses,proceduresanddocumentationofinformationtobridgethegaptotheselongertermprograms.Wehavebeguntheprocesstoimplementtheseactionsandplantoexaminetheireffectiveness,during1991.WebelievethattheinterimactionsplannedarethemosteffectivemeasuresforRG&EtoprovideadequateresolutionoftheidentifieddeficiencieswhileweareimplementingthelongtermConfigurationManagementPrograms.TheNRCInspectionReportidentifiedtheEngineeringA'ssurancedeficienciesinsections2.2.1.1,2.2.1.2,2.2.3.2,and2.2.3.3.TheRG&Eassessmentconcentratedontherootcausesofthesedeficienciesandnotjusttheexamplesthemselves.Nevertheless,thespecificanalyses,reports,anddrawingsthatrequirerevisionsorcorrectionsasdescribedinthesesectionsarebeingrevisedorupdatedasnecessary,includingforexample,thecalculationsdiscussedinsection2.2.1.2andthedrawingsidentifiedinsection2.2.3.3(B).,OurspecificevaluationsrelativetotheexamplesfoundinthesefoursectionsarecontainedintheAssessmentTeamreport.WebelievethatthesystematicassessmentdiscussedinAttachmentBisathoroughandappropriateresponsetounresolveditem89-81-11.PleasenotifyusifyoubelievewehavenotinterpretedtheNRCreportcorrectly.Verytrulyyours,GAHK118Atta'chmentRobertC.Mecredyxc:U.S.NuclearRegulatoryCommission(original)DocumentControlDeskWashington,D.C.20555AllenR.Johnson(MailStop14Dl)ProjectDirectorateI-3Washington,D.C.20555GinnaSeniorResidentInspector  
RG&Ebelievesthatmanyofthedeficiencies
notedundertheengineering
assurance
unresolved
item89-81-11hadbeenrecognized
priortotheRHRSSFIandhavebeenenveloped
underthevariousConfiguration
Management
Projects,
suchastheSetpointVerification
ProgramandDesignBasisDocumentation
Projects.
Wehaverecognized
thatinterimactionsarenecessary
tosufficiently
strengthen
theengineering
processes,
procedures
anddocumentation
ofinformation
tobridgethegaptotheselongertermprograms.
Wehavebeguntheprocesstoimplement
theseactionsandplantoexaminetheireffectiveness,
during1991.Webelievethattheinterimactionsplannedarethemosteffective
measuresforRG&Etoprovideadequateresolution
oftheidentified
deficiencies
whileweareimplementing
thelongtermConfiguration
Management
Programs.
TheNRCInspection
Reportidentified
theEngineering
A'ssurance
deficiencies
insections2.2.1.1,2.2.1.2,2.2.3.2,and2.2.3.3.TheRG&Eassessment
concentrated
ontherootcausesofthesedeficiencies
andnotjusttheexamplesthemselves.
Nevertheless,
thespecificanalyses,
reports,anddrawingsthatrequirerevisions
orcorrections
asdescribed
inthesesectionsarebeingrevisedorupdatedasnecessary,
including
forexample,thecalculations
discussed
insection2.2.1.2andthedrawingsidentified
insection2.2.3.3(B).
,Ourspecificevaluations
relativetotheexamplesfoundinthesefoursectionsarecontained
intheAssessment
Teamreport.Webelievethatthesystematic
assessment
discussed
inAttachment
Bisathoroughandappropriate
responsetounresolved
item89-81-11.Pleasenotifyusifyoubelievewehavenotinterpreted
theNRCreportcorrectly.
Verytrulyyours,GAHK118Atta'chment
RobertC.Mecredyxc:U.S.NuclearRegulatory
Commission
(original)
DocumentControlDeskWashington,
D.C.20555AllenR.Johnson(MailStop14Dl)ProjectDirectorate
I-3Washington,
D.C.20555GinnaSeniorResidentInspector  
   
   
AttachmentAUPDATEOFUNRESOLVEDITEMSFROMRG&E'sENCLOSUREEOF,JUNE8,1990URI89-81-02(Section2.2.1.4)ResolutionofSafetyConcernsJune8,1990:Aninterimprocessforhandlingsafetyconcernsisunderdevelopmentandwillbediscussedinour120dayresponse.Update:RG&EhasdevelopedaformalprocessinProcedureQE-1603,DocumentingandReportingofConditionsAdversetoQuality,forhandlingpotentialsafetyconcernsidentifiedbyNuclearEngineeringServicespersonnel.Theseamongtheconditions-whichwouldbereported,are:nonconformances,deviations,deficiencies,failures,malfunctions,defectivematerialandequipment,vendortechnicalreports,designbasisdocumentation,andthematerialconditionoftheplantstructures,systemsorcomponents.TheprocedurerequiresthatpotentialsafetyconcernsbedocumentedandtrackedbyNuclearEngineeringServicespersonnel.Theprocessprovidesfor:ensuringthatapreliminarysafetyevaluationisperformedbyNuclearSafetyandLicensing;transmittinginformationconcerningconditionsthatinvolveasafetyconcerntotheTechnicalManager,GinnaStation;dispositionofsafetyconcernsthroughtheappropriateprocesssuchasanonconformancereport(NCR),and.identifieddeficiencyreport(IDR);reviewingtheconditionandpreliminarysafetyevaluationbyGinnaStationTechnicalSectionagainstthecriteriaforreportingevents(A-25.1);dispositioningtheconditionthroughtheappropriateprocesssuchascorrectiveactionreports(CAR),procedurechangenotice(PCN)andworkrequest/troublerequest(WR/TR);providingtheinitiatorwiththefeedbackonthedisposition.PotentialconditionsadversetoqualitythatarediscoveredbyGinnaStationpersonnelaredispositionedbyoneofthecurrentprocessesundertheMaintenanceWorkRequestandTroubleReport(A-1603),CorrectiveActionReport(A-1601),andReportingofUnusualPlantConditions(A-25).InterimandlongtermcorrectiveactionsrecommendedaspartoftheRG&ESSFIAssessmentaredescribedinAttachmentBunderthegeneraltopicalareaImprovedProcessforReportingandAssessingSafetyConcerns.A-1  
Attachment
AUPDATEOFUNRESOLVED
ITEMSFROMRG&E'sENCLOSURE
EOF,JUNE8,1990URI89-81-02(Section2.2.1.4)Resolution
ofSafetyConcernsJune8,1990:Aninterimprocessforhandlingsafetyconcernsisunderdevelopment
andwillbediscussed
inour120dayresponse.
Update:RG&Ehasdeveloped
aformalprocessinProcedure
QE-1603,Documenting
andReporting
ofConditions
AdversetoQuality,forhandlingpotential
safetyconcernsidentified
byNuclearEngineering
Servicespersonnel.
Theseamongtheconditions
-whichwouldbereported,
are:nonconformances,
deviations,
deficiencies,
failures,
malfunctions,
defective
materialandequipment,
vendortechnical
reports,designbasisdocumentation,
andthematerialcondition
oftheplantstructures,
systemsorcomponents.
Theprocedure
requiresthatpotential
safetyconcernsbedocumented
andtrackedbyNuclearEngineering
Servicespersonnel.
Theprocessprovidesfor:ensuringthatapreliminary
safetyevaluation
isperformed
byNuclearSafetyandLicensing;
transmitting
information
concerning
conditions
thatinvolveasafetyconcerntotheTechnical
Manager,GinnaStation;disposition
ofsafetyconcernsthroughtheappropriate
processsuchasanonconformance
report(NCR),and.identified
deficiency
report(IDR);reviewing
thecondition
andpreliminary
safetyevaluation
byGinnaStationTechnical
Sectionagainstthecriteriaforreporting
events(A-25.1);
dispositioning
thecondition
throughtheappropriate
processsuchascorrective
actionreports(CAR),procedure
changenotice(PCN)andworkrequest/trouble
request(WR/TR);providing
theinitiator
withthefeedbackonthedisposition.
Potential
conditions
adversetoqualitythatarediscovered
byGinnaStationpersonnel
aredispositioned
byoneofthecurrentprocesses
undertheMaintenance
WorkRequestandTroubleReport(A-1603),
Corrective
ActionReport(A-1601),
andReporting
ofUnusualPlantConditions
(A-25).Interimandlongtermcorrective
actionsrecommended
aspartoftheRG&ESSFIAssessment
aredescribed
inAttachment
BunderthegeneraltopicalareaImprovedProcessforReporting
andAssessing
SafetyConcerns.
A-1  
   
   
URI,89-81-05(Section2.2.2.2)ElectricalLoadGrowthProgramJune8,1990:WearetakingactionstointegratethisprocessintotheappropriateEngineering(QE)procedures.,Weanticipatecompletionoftheseactionsbythedateofour120dayresponse.Update:RG&EissuedachangetoengineeringprocedureQE-301Rev.11withissuanceofPDR0609dated7/9/90.Thischangerequiresthatourdesignprocessensurethattheeffectsofallloadchangesonthestationbatteriesordiesel-generatorsshallbeaddressed,includingtherequirementthatthesebeevaluatedandshowntobewithinthemarginallowedbythecurrentloadinganalysis.DuringtheRG&ESSFIReviewTeamAssessmentitwasnotedthatotherexampleswereidentifiedwhichcouldbeplacedwithintheissueofestablishingamechanismtoevaluatethecumulativeeffectsofmodifications.InterimandlongtermcorrectiveactionsaredescribedwithinAttachmentBunderthegeneraltopicalareaImprovedDocumentationAssociatedwithModifications.URI89-81-07(Section2.2.4.4.a.,b.,andd.)ControlRoomP&ID'sJune8,1990:Aninterimprocessforenhancingtheupdateprocessforcontrolroominformation.iscurrentlyunderreviewandwillbediscussedinthe120dayresponse.Update:Thisconcernwasmanifestedintwoareas,drawingchangerequests(DCRs)andtrainingmaterial.DCRProcess:ThetimelinessofprocessingdrawingchangeshasbeenenhancedthroughimplementationofRevision3ofA-606,DrawingChangeRequestsprocedure.ThisupgradedirectsthetimelyupgradingofdrawingsusedintheControlRoomandTechnicalSupportCenter.Postingofdrawingchangesisrequiredwithin2workingdaysfromtheirreceiptbyCentralRecords.(Generalpracticehasbeensamedayposting).TheapprovalandtrackingoftheDCRprocessiscurrentlyassignedtotheTechnicalSectionatGinnaStation.Plansarebeingmadetotransferdataentry,controlofthedatabaseanddistributiontotheDocumentControldepartment.AnotherenhancementincludesamonthlyDCRstatusreportthatisdistributedtomanagement.TheDCRprocesshasbeengivenincreasedemphasisthroughproceduralcontr'ols.Withitspresentmethod,RG&EbelievesthattimelypostingandeffectivetrackingandtrendingoftheDCRsystemwillbeachieved..A-2  
URI,89-81-05(Section2.2.2.2)Electrical
LoadGrowthProgramJune8,1990:Wearetakingactionstointegrate
thisprocessintotheappropriate
Engineering
(QE)procedures.,
Weanticipate
completion
oftheseactionsbythedateofour120dayresponse.
Update:RG&Eissuedachangetoengineering
procedure
QE-301Rev.11withissuanceofPDR0609dated7/9/90.Thischangerequiresthatourdesignprocessensurethattheeffectsofallloadchangesonthestationbatteries
ordiesel-generators
shallbeaddressed,
including
therequirement
thatthesebeevaluated
andshowntobewithinthemarginallowedbythecurrentloadinganalysis.
DuringtheRG&ESSFIReviewTeamAssessment
itwasnotedthatotherexampleswereidentified
whichcouldbeplacedwithintheissueofestablishing
amechanism
toevaluatethecumulative
effectsofmodifications.
Interimandlongtermcorrective
actionsaredescribed
withinAttachment
BunderthegeneraltopicalareaImprovedDocumentation
Associated
withModifications.
URI89-81-07(Section2.2.4.4.a.,
b.,andd.)ControlRoomP&ID'sJune8,1990:Aninterimprocessforenhancing
theupdateprocessforcontrolroominformation
.iscurrently
underreviewandwillbediscussed
inthe120dayresponse.
Update:Thisconcernwasmanifested
intwoareas,drawingchangerequests(DCRs)andtrainingmaterial.
DCRProcess:Thetimeliness
ofprocessing
drawingchangeshasbeenenhancedthroughimplementation
ofRevision3ofA-606,DrawingChangeRequestsprocedure.
Thisupgradedirectsthetimelyupgrading
ofdrawingsusedintheControlRoomandTechnical
SupportCenter.Postingofdrawingchangesisrequiredwithin2workingdaysfromtheirreceiptbyCentralRecords.(Generalpracticehasbeensamedayposting).
TheapprovalandtrackingoftheDCRprocessiscurrently
assignedtotheTechnical
SectionatGinnaStation.Plansarebeingmadetotransferdataentry,controlofthedatabaseanddistribution
totheDocumentControldepartment.
Anotherenhancement
includesamonthlyDCRstatusreportthatisdistributed
tomanagement.
TheDCRprocesshasbeengivenincreased
emphasisthroughprocedural
contr'ols.
Withitspresentmethod,RG&Ebelievesthattimelypostingandeffective
trackingandtrendingoftheDCRsystemwillbeachieved..
A-2  
4  
4  
TraininMaterial:RG&EiscommittedtoensuringthatalltrainingmaterialavailabletoLicensedoperatorsisascorrectandcurrentaspossible.DuringtheinspectionweagreedthattheLessonTextRG&E-25containedaninvalidvalueforthetimeavailabletoisolatea50gpmsealleaktopreventRHRpumpmotorflooding.Otherinformationrelativetoplantmodificationsonvalve:numbers(EWR4761)andpipingmodification(EWR4675)alsohadnotyetbeenincorporatedintotheLessonTextbecausetheTrainingChangeRequesthadnotyetbeenimplemented.AfterthediscrepancyontheisolationtimewasidentifiedtoRG&E,theLessonTextwasimmediatelycorrected.Forclarity,theLessonTextshavebeenrenamedTRAININGSYSTEMSDESCRIPTIONS.However,thesearenotdefinedasControlledConfigurationmaterial.Thesedocumentsarenotmeanttotaketheplaceofapprovedplantprocedures,engineeringdesigndocuments,plantdrawingsorvendortechnicalmanuals.Theyareusedasreferencematerial,arrangedbysystem,thatcontainaconceptualoverviewof.thatsystemdesignedtobeused.asajoband.trainingaid.WeunderstandtheNRC'sconcernoverthefactthatthismaterialisavailableforuseinthecontrolroom,maybefrequentlyused,andisnotdesignatedasbeingpotentiallyoutofdate.Webelievetheprimaryconcernisthetimelinessofupdatingthismaterialtoreflecttheplantconfiguration,notoverthecontroloverthesedocuments.Therefore,strictcontrolhasbeenplacedoverthesedocuments.Thereisamastercopycontrolledb'ytheTrainingDepartmentandallchangesarecontrolledbyprocedureTR5.9(TrainingChangeRequest/Notice).Recordsarekeptofcontrolledcopyholdersofcontrolledcopies.PlacementofthismaterialinthecontrolroomiscontrolledbytheTrainingDepartment.Thisisthenorm,nottheexception,intheutilityindustry.Weunderstandandrecognizetheunderlyingconcernidentifiedoverthetimelinessofprovidingcurrentandcontrolledmaterialtothosewhomayuseit.ProceduresTR5.5.1(TrackingPlantChanges)iscurrentlytheprocessthathasbeendevelopedandimplementedtoidentifyandtrackplantchangesandincludethosechangesintrainingmaterialwhereappropriate.Wehavetakenadditionalstepsinordertoprovidetrainingmaterialthatisascurrentaspossibleandtobetterdefinethepurposeofthismaterial.1.Placeacopyofthe"InformationLetter"inallTrainingSystemDescriptionsthatareaffectedbyaplantmodification.ThisactionhasbeenimplementedandwillbecontrolledbyConfigurationA-3  
TraininMaterial:
2.ManagementTrainingGuidelines,CMTG-3.0,PreparationandUseofInformationLetters.Theinformationletterprovidescurrentinformationonamodification.Theletterwillremainpartofthesystemdescriptionuntilthesystemdescriptionhasbeenrevised.toincorporatethenewmodification.IThefirstpageofeachTrainingSystemDescriptionwillbestampedTRAININGINFORMATIONONLY.Thisactionhasbeeninitiated..3.IncludethedateofrevisionforeachpageoftheTrainingSystemDescription.Thisactionhasbeenimplemented.TherewerenoadditionalinterimremedialactionsrecommendedaspartoftheRG&ESSFIReviewTeamAssessmentotherthanthoseabove.LongtermcorrectiveactionsaredescribedinAttachmentBundergeneraltopicalareaPlantDesignInformation/DesignBases.URI89-81-06(Section2.2.2.3)MoldedCaseCircuitBreakerJune8,1990:Theindustryiscurrentlyexaminingtheneedfor,andbenefitsof,moldedcasecircuitbreakerstesting.RG&EwillcontinuetoworkcloselywiththeindustryandEPRItodeterminetheappropriatetestmethodsandrequirements.Update:DuringAugustRG&EpersonnelfromEngineeringandPlantMaintenancevisitedtheDiabloCanyonPowerPlanttoinspecttheequipmentandproceduresforperiodictestingofmoldedcasecircuitbreakersusedbyPG&E.ResultsofthefirstcycleoftestingbytheDiabloCanyonstaffwerealsodiscussed.AsimilarprogramforGinnaStationappearstobetechnicallyfeasible,subjecttoadditionalevaluationandprocurementoftestequipment,developmentofprocedures,andperformanceofatrialtestprogram.Itisanticipatedthatatrialprogramcanbeinitiatedwithinthenextyear.Itisestimatedthatthefirstcycleofatestprogramwouldrequirefourormoreyearstocompletefollowingthesuccessfulcompletionofatrialtest.A-4  
RG&Eiscommitted
AttachmentBSYSTEMATICASSESSMENTOFENGINEERINGASSURANCEISSUESANDRHRSSFICONCERNSThisattachmentisasummaryoftheSSFIAssessmentTeamapproachandrecommendedactionsextracted.fromtheRG&Ereportwiththesamename.  
toensuringthatalltrainingmaterialavailable
toLicensedoperators
isascorrectandcurrentaspossible.
Duringtheinspection
weagreedthattheLessonTextRG&E-25contained
aninvalidvalueforthetimeavailable
toisolatea50gpmsealleaktopreventRHRpumpmotorflooding.
Otherinformation
relativetoplantmodifications
onvalve:numbers
(EWR4761)andpipingmodification
(EWR4675)alsohadnotyetbeenincorporated
intotheLessonTextbecausetheTrainingChangeRequesthadnotyetbeenimplemented.
Afterthediscrepancy
ontheisolation
timewasidentified
toRG&E,theLessonTextwasimmediately
corrected.
Forclarity,theLessonTextshavebeenrenamedTRAININGSYSTEMSDESCRIPTIONS.
However,thesearenotdefinedasControlled
Configuration
material.
Thesedocuments
arenotmeanttotaketheplaceofapprovedplantprocedures,
engineering
designdocuments,
plantdrawingsorvendortechnical
manuals.Theyareusedasreference
material,
arrangedbysystem,thatcontainaconceptual
overviewof.thatsystemdesignedtobeused.asajoband.trainingaid.Weunderstand
theNRC'sconcernoverthefactthatthismaterialisavailable
foruseinthecontrolroom,maybefrequently
used,andisnotdesignated
asbeingpotentially
outofdate.Webelievetheprimaryconcernisthetimeliness
ofupdatingthismaterialtoreflecttheplantconfiguration,
notoverthecontroloverthesedocuments.
Therefore,
strictcontrolhasbeenplacedoverthesedocuments.
Thereisamastercopycontrolled
b'ytheTrainingDepartment
andallchangesarecontrolled
byprocedure
TR5.9(Training
ChangeRequest/Notice).
Recordsarekeptofcontrolled
copyholdersofcontrolled
copies.Placement
ofthismaterialinthecontrolroomiscontrolled
bytheTrainingDepartment.
Thisisthenorm,nottheexception,
intheutilityindustry.
Weunderstand
andrecognize
theunderlying
concernidentified
overthetimeliness
ofproviding
currentandcontrolled
materialtothosewhomayuseit.Procedures
TR5.5.1(Tracking
PlantChanges)iscurrently
theprocessthathasbeendeveloped
andimplemented
toidentifyandtrackplantchangesandincludethosechangesintrainingmaterialwhereappropriate.
Wehavetakenadditional
stepsinordertoprovidetrainingmaterialthatisascurrentaspossibleandtobetterdefinethepurposeofthismaterial.
1.Placeacopyofthe"Information
Letter"inallTrainingSystemDescriptions
thatareaffectedbyaplantmodification.
Thisactionhasbeenimplemented
andwillbecontrolled
byConfiguration
A-3  
2.Management
TrainingGuidelines,
CMTG-3.0,
Preparation
andUseofInformation
Letters.Theinformation
letterprovidescurrentinformation
onamodification.
Theletterwillremainpartofthesystemdescription
untilthesystemdescription
hasbeenrevised.toincorporate
thenewmodification.
IThefirstpageofeachTrainingSystemDescription
willbestampedTRAININGINFORMATION
ONLY.Thisactionhasbeeninitiated..
3.IncludethedateofrevisionforeachpageoftheTrainingSystemDescription.
Thisactionhasbeenimplemented.
Therewerenoadditional
interimremedialactionsrecommended
aspartoftheRG&ESSFIReviewTeamAssessment
otherthanthoseabove.Longtermcorrective
actionsaredescribed
inAttachment
BundergeneraltopicalareaPlantDesignInformation/Design
Bases.URI89-81-06(Section2.2.2.3)MoldedCaseCircuitBreakerJune8,1990:Theindustryiscurrently
examining
theneedfor,andbenefitsof,moldedcasecircuitbreakerstesting.RG&EwillcontinuetoworkcloselywiththeindustryandEPRItodetermine
theappropriate
testmethodsandrequirements.
Update:DuringAugustRG&Epersonnel
fromEngineering
andPlantMaintenance
visitedtheDiabloCanyonPowerPlanttoinspecttheequipment
andprocedures
forperiodictestingofmoldedcasecircuitbreakersusedbyPG&E.ResultsofthefirstcycleoftestingbytheDiabloCanyonstaffwerealsodiscussed.
AsimilarprogramforGinnaStationappearstobetechnically
feasible,
subjecttoadditional
evaluation
andprocurement
oftestequipment,
development
ofprocedures,
andperformance
ofatrialtestprogram.Itisanticipated
thatatrialprogramcanbeinitiated
withinthenextyear.Itisestimated
thatthefirstcycleofatestprogramwouldrequirefourormoreyearstocompletefollowing
thesuccessful
completion
ofatrialtest.A-4  
Attachment
BSYSTEMATIC
ASSESSMENT
OFENGINEERING
ASSURANCE
ISSUESANDRHRSSFICONCERNSThisattachment
isasummaryoftheSSFIAssessment
Teamapproachandrecommended
actionsextracted.
fromtheRG&Ereportwiththesamename.  
   
   
SystematicAssessmentofEngineeringAssuranceIssuesandRHRSSFIConcernsTABLEOFCONTENTS1.0INTRODUCTION1.1~purose1.3ScoeofReviewandRecommendations1.4ReviewTeam2.0SYSTEMATICASSESSMENT'I3.0ISSUESANDCONCERNSADDRESSED4.0SUMMARYOFRECOMMENDATIONSAPPENDICES:AppendixA,ProgrammaticConcernsListingPagei
Systematic
Assessment
ofEngineering
Assurance
IssuesandRHRSSFIConcernsTABLEOFCONTENTS1.0INTRODUCTION
1.1~purose1.3ScoeofReviewandRecommendations
1.4ReviewTeam2.0SYSTEMATIC
ASSESSMENT
'I3.0ISSUESANDCONCERNSADDRESSED
4.0SUMMARYOFRECOMMENDATIONS
APPENDICES:
AppendixA,Programmatic
ConcernsListingPagei
0  
0  
SystematicAssessmentofEngineeringAssuranceIssuesandRHRSSFIConcerns1.0INTRODUCTION1e2~PuroseThisdocumentprovidestheresultsofasystematicassessmentofissuesandconcernsraisedbytheNRC',sSafetySystemFunctionalInspection(SSFI)conductedduringNovemberandDecember,1989,whichfocusedontheGinnaStationResidualHeatRemoval(RHR)System.Thissummaryreportalsopresentsinterimremedialactionsandlong-termcorrectiveactions.Otherstepstowardimprovements,alreadyinprogress,arealsolisted..BackroundAsafetySystemFunctionalInspection(SSFI)wasperformedbyanNRCteamfromNovember6toDecember8,1989,atRG&Efacilities(GinnaStationandthecorporateoffices),andisdocumentedinaletterfromtheNRCdatedMay9,1990.TheobjectiveoftheSSFIwastoassessthecapabilityoftheGinnaResidualHeatRemoval(RHR)systemtoperformitsdesignbasissafetyfunctions.TheNRCinspectionteamevaluatedtheadequacyofoperationalprocedures,testpractices,,andmaintenancepoliciesastheycontributetoRHRsystemreliability.TheNRCteamalsoaddressedthequalityofengineeringsupportactivities.TheNRCteamdidnotidentifyanyconditionsthatwouldprohibittheRHRsystemfromperformingitsintendedfunctionsundernormalanddesignbasisaccidentconditions.However,itwasstatedbytheNRCthatcompleteverificationofsystemreliabilitywasnotpossiblesincethedesignbasiscalculationsfortheRHRsystemwerenotreadilyavailable.TheNRCSSFIteamdidhaveoneimmediateconcernand,asaresult,RG&EwasrequestedtopromptlyresolveadiscrepancyregardingthepotentialfloodingoftheRHRpumproom.OuractionstakentoresolvethisweredocumentedinEnclosureEtoourJune8,1990response(URI89-81-10).InadditionitappearedtotheNRCinspectionteamthattwoactivitieswerenotconductedinfullcompliancewithNRCrequirements,asdescribedintheNoticeofViolation(NOV)enclosedasAppendixAtotheNRCSSFIInspectionReport.B-1  
Systematic
TheRG&EresponsetotheNOVincludedascheduleforresolvingtheunresolveditems(exclusiveof89-81-11discussedabove)identifiedintheNRCSSFIreport.TheRHRSSFIInspectionReportalsocited,anumberofconcernswhichcouldbeassociatedwithbroaderprogrammaticissues.TheNRCinspectionteamconcludedthatweaknessesexistinengineeringsupportandplantmodificationactivities.TheseweaknesseswerelistedinSection2.1,andwerediscussedinSection2.2,oftheNRCSSFIInspectionReport,andhavebeenassignedunresolveditemnumber89-81-11.TheSSFIInspectionReportrequired'G&Eto"providetheirevaluationofthoseweaknesseswithin120days".Theidentifiedweaknesseswereplacedunderthebroadcategoryof"engineeringassurance"bytheNRC.RG&Ecommitted'ntheJune8,199030-dayresponsetoconductareviewofitsengineeringprocessusingasystematicapproach.RG&Eelectedtoperformitsevaluationofthe"engineeringassurance"issuesbyutilizingareviewteamapproach.Theresultsofthereviewteamapproachwasintendedtoprovidethebasistoward.resolutionofNRCSSFIInspectionunresolveditem89-81-11.1.3Scoe.oftheReviewand'RecommendationsThescopeoftheSSFIreviewwasestablishedbyRG&EManagementpriortotheinitiationofthereviewteameffort.RG&EManagementprovidedgeneralguidanceforconductofthereview'teameffortaswellasspecificguidanceonthescopeofpotentialrecommendations.Toensurethatathoroughevaluationwasconducted,thereviewteamexaminedthematerialfoundinthefollowingdocuments:a~NRCSSFIReportno.50-244/89-81,dated,May9,1990b.RG&E's30-dayresponselettertotheNRCdatedJune8,1990c~CommitmentandActionTrackingSystem(CATS)commitmentsestablishedbytheNRCinspectionreportandRG&E'sJune8,1990letter.d.e.INPOGoodPractices,"GuidancefortheConductofDesignEngineering"(INPO88-016)December,1988GroveEngineeringReviewReportdatedJuly10,1990ApplicablesectionsoftheRG&EConfigurationManagement(CM)Plan.B-2  
Assessment
ofEngineering
Assurance
IssuesandRHRSSFIConcerns1.0INTRODUCTION
1e2~PuroseThisdocumentprovidestheresultsofasystematic
assessment
ofissuesandconcernsraisedbytheNRC',sSafetySystemFunctional
Inspection
(SSFI)conducted
duringNovemberandDecember,
1989,whichfocusedontheGinnaStationResidualHeatRemoval(RHR)System.Thissummaryreportalsopresentsinterimremedialactionsandlong-term
corrective
actions.Otherstepstowardimprovements,
alreadyinprogress,
arealsolisted..BackroundAsafetySystemFunctional
Inspection
(SSFI)wasperformed
byanNRCteamfromNovember6toDecember8,1989,atRG&Efacilities
(GinnaStationandthecorporate
offices),
andisdocumented
inaletterfromtheNRCdatedMay9,1990.Theobjective
oftheSSFIwastoassessthecapability
oftheGinnaResidualHeatRemoval(RHR)systemtoperformitsdesignbasissafetyfunctions.
TheNRCinspection
teamevaluated
theadequacyofoperational
procedures,
testpractices,
,andmaintenance
policiesastheycontribute
toRHRsystemreliability.
TheNRCteamalsoaddressed
thequalityofengineering
supportactivities.
TheNRCteamdidnotidentifyanyconditions
thatwouldprohibittheRHRsystemfromperforming
itsintendedfunctions
undernormalanddesignbasisaccidentconditions.
However,itwasstatedbytheNRCthatcompleteverification
ofsystemreliability
wasnotpossiblesincethedesignbasiscalculations
fortheRHRsystemwerenotreadilyavailable.
TheNRCSSFIteamdidhaveoneimmediate
concernand,asaresult,RG&Ewasrequested
topromptlyresolveadiscrepancy
regarding
thepotential
floodingoftheRHRpumproom.Ouractionstakentoresolvethisweredocumented
inEnclosure
EtoourJune8,1990response(URI89-81-10).
InadditionitappearedtotheNRCinspection
teamthattwoactivities
werenotconducted
infullcompliance
withNRCrequirements,
asdescribed
intheNoticeofViolation
(NOV)enclosedasAppendixAtotheNRCSSFIInspection
Report.B-1  
TheRG&EresponsetotheNOVincludedascheduleforresolving
theunresolved
items(exclusive
of89-81-11discussed
above)identified
intheNRCSSFIreport.TheRHRSSFIInspection
Reportalsocited,anumberofconcernswhichcouldbeassociated
withbroaderprogrammatic
issues.TheNRCinspection
teamconcluded
thatweaknesses
existinengineering
supportandplantmodification
activities.
Theseweaknesses
werelistedinSection2.1,andwerediscussed
inSection2.2,oftheNRCSSFIInspection
Report,andhavebeenassignedunresolved
itemnumber89-81-11.
TheSSFIInspection
Reportrequired'G&E
to"providetheirevaluation
ofthoseweaknesses
within120days".Theidentified
weaknesses
wereplacedunderthebroadcategoryof"engineering
assurance"
bytheNRC.RG&Ecommitted'n
theJune8,199030-dayresponsetoconductareviewofitsengineering
processusingasystematic
approach.
RG&Eelectedtoperformitsevaluation
ofthe"engineering
assurance"
issuesbyutilizing
areviewteamapproach.
Theresultsofthereviewteamapproachwasintendedtoprovidethebasistoward.resolution
ofNRCSSFIInspection
unresolved
item89-81-11.
1.3Scoe.oftheReviewand'Recommendations
ThescopeoftheSSFIreviewwasestablished
byRG&EManagement
priortotheinitiation
ofthereviewteameffort.RG&EManagement
providedgeneralguidanceforconductofthereview'teameffortaswellasspecificguidanceonthescopeofpotential
recommendations.
Toensurethatathoroughevaluation
wasconducted,
thereviewteamexaminedthematerialfoundinthefollowing
documents:
a~NRCSSFIReportno.50-244/89-81,
dated,May9,1990b.RG&E's30-dayresponselettertotheNRCdatedJune8,1990c~Commitment
andActionTrackingSystem(CATS)commitments
established
bytheNRCinspection
reportandRG&E'sJune8,1990letter.d.e.INPOGoodPractices,
"Guidance
fortheConductofDesignEngineering"
(INPO88-016)December,
1988GroveEngineering
ReviewReportdatedJuly10,1990Applicable
sectionsoftheRG&EConfiguration
Management
(CM)Plan.B-2  
0  
0  
g,NRCSafetySystemFunctionalInspectionGuidelines,AppendixC(issued11/12/86).h.EPRI,NuclearSafetyAnalysisCenterDocument,NSAC/121,"GuidelinesforPerformingSafetySystemFunctionalInspections(November1988).NQA-1"QualityAssuranceProgramRequirementsforNuclearPowerPlants"(1979)j.ANSIN45.2.11,"QualityAssuranceRequirementsfortheDesignofNuclearPowerPlants"(1974)k.NRC'egulatoryGuide1.64,"QualityAssuranceRequirementsfortheDesignofNuclearPowerPlants"l.QE-seriesEngineeringProceduresm.A-seriesGinnaStationAdministrativeProceduresWiththisreferencematerialasbackgroundinformationthereviewteammembersproceededtoevaluatetheNRCconcernsandmakerecommendationsforcorrectiveactiontoRG&EManagementthroughtheDepartmentManager,NuclearEngineeringServices.Thefollowingis'summaryoftheguidanceprovidedbyRG&EManagement:a.Issuesaddressedweretofocuson,butnot,limitedto,thosecontainedintheNRCSSFIReport(IR89-81).b.c~ConcernscitedbytheNRCweretobeacceptedasvalid.NoeffortwastobeexpendedonquestioningeitherthecitedconcernsortheexamplesusedintheNRCSSFIReport.Recommendationsweretotaketheformofinterimactionsandlong-termcorrectiveactions.d.Recommendationsforinterimactionsweretobelimitedtothefollowingitems:i.Changesto~existinEngineeringandGinnaStationProcedures.ii.CreationofalimitednumberofnewEngineeringQEorAdministrativeProceduresand/orGinnaAdministrativeProcedures.iii.Issuanceofpolicystatements(atdiscipline,departmentorcorporatelevel.)B-3  
g,NRCSafetySystemFunctional
e.iv.Developmentofdiscipline-specificimplementingdocuments(suchasdesignguides,standards,etc.).v.Reassignmentofdutiestopersonnelwithinspecificdisciplines.Recommendationswere'obeachievableutilizingstafflevelsthatarecurrentlyauthorized.1.4ReviewTeamRG&EManagementselectedareviewteamtoactontheirbehalfconsistingofagroupofnineexperiencedpersonnelrepresentingthefollowingareas:MechanicalEngineering,ElectricalEngineering,StructuralandConstructionEngineering,NuclearSafetyandLicensing,ConfigurationManagement,DocumentControl/RecordsMan'agement,GinnaTechnicalSection,andNuclearEngineeringServicesDepartmentstaff.2.0SYSTEMATICASSESSMENTThemulti-disciplineRG&ESSPIReviewTeamperformedanassessmentoftheissuesandconcernsgeneratedbytheNRCRHRSSFI.Theteambeganbyestablishingthefollowingdefinitionof"EngineeringAssurance":EnineerinAssurance:Theplannedandsystematicactionsnecessarytoprovideadequateconfidencethatengineeringactivitiesareperformedinaconsistentmannerwithadherencetoplantlicensingbasis,applicableprocedures,regulationsandacceptedindustrystandards.Thereviewteammembersformed."focusgroups"whichwereassignedindividualdetailitemsfromtheprogrammaticconcernslistingestablishedintheinitialbreakdownofissues(appendixA).IndividualassessmentsweremadeandtheissuesgroupedanddocumentedaspartofRG&Es"SystematicAssessmentofEngineeringAssuranceandRHRSSPIConcernReport."Thereviewwasbasedonthereviewteam'sownassessmentaswellasondetailedinformationobtainedthroughdiscussionswithothercognizantengineeringand,plantpersonnel.3.0ISSUESANDCONCERNSADDRESSEDThereviewteamregroupedallissuesandprogrammaticconcernsintosixtopicalareas,aslistedbelow:s-4  
Inspection
3.1ToicalArea1:"ImprovedProcessforReportingandAssessingSafetyConcerns"a:"ProcessforHandlingSafetyConcernsOutsidetheEWRProcess"3.2ToicalArea2:."ImprovedDesignControlandReviews"a~b.cd.e.f."EngineeringManagement""EngineeringAssurance""TimelinessofDCRProcessing""DesignReviews""PAIDUpgradeProgram""DesignControl"3.3ToicalArea3:"ImprovedDesignInterfaceControl"a."ProceduralInconsistency"3.4ToicalArea4:"ImprovedDesignDocumentation/DesignBases"a~b.cd.e.f.g,"InterdisciplinaryReviewofNon-Mods""Calculations""DeletionofInformationfromPGIDs""ValveIdentificationDifferences""DesignBasisInformation"ControlledInstrumentListTrainingMaterial3.5ToicalArea5:Modifications"1"ImprovedDocumentationAssociatedwitha."InvalidInformationinUFSAR"b."AssessmentofCumulativeEffectsofModifications"c."IssuanceofDesignOutputs"d."ControlofEWRs"3.6ToicalArea6:"ImprovedEngineering/PlantCommunications"a."Engineering/PlantInterface"b."AcceptanceCriteria"c."AdequacyofSRVTestAcceptanceCriteria"4.0SummarofRecommendationsThefollowingisageneralsummaryofthemostsignificantinterimactionsandlongtermcorrectiveactions.4.1RG&E'smanagementhasensuredclosecontrolandqualityengineeringservicesthroughtheirinteractionandreviewofdesign,butwrittenproceduresdonotmakethatcontrolsufficiently-explicit.B-5  
Guidelines,
Asinterimactions,asingleprocedurewillbedevelopedthatoutlinestheentirescopeofthedesignprocess.Disciplinedesignguidesforgenerationofdesigncriteria,designanalysesanddesignverificationdocumentswillbeinitiated.Also,theintegrated.assessmentprocesswillbeseparately"proceduralized.Applicableprocedureswillberevisedtoestablishtherequirementsforreview,'a'pproval,andissuanceofvendordocuments.In,thelongerterm,weplantocompletetheupgradeofengineeringproceduresandprocessestoreflectindustrystandardsofgoodpractice,efficiencyandrapidresponse.4.24.34.4Engineeringprocedurescontainastrongbiastomodificationdesign.Thishasprovedtobewellsuitedtowardmajorstandalonedesignprojectsbutisnotaseffectivelyusedtoaggressivelysupportalloftheengineeringactivitiesassociatedwithawell-maintained.operatingplant.Close-outEWRdocumentationcanbeprotracted,becausethescopeofamodificationmaybein'creasedovertime,causingdesigndocumentstoremainopen.Asinterimactions,weplantolimitthepracticeofincreasingthescopeofadesignmodificationduringtheintervalbetweenturnoverofthemodificationintheplantandrecordsclose-out.WewillbegintotransmitEWRDesignPackagestoDocumentControlconcurrentwiththeissuanceoftheconstructionpackage.Inthisway,thelistofapplicabledesigndocumentswillalsobeestablishedforthemodificationtobeinstalled..TheUFSARchangeprocesswillbeproceduralizedandintegratedwiththeaboveturnoverprocess.Interimactivitiesareneededtobegintocapture,retain,provideaccessto,andorganizedesignbasisinformationaspartofthenormalongoingengineeringactivities.RG&EhasincorporatedadesignbasisdocumentationprojectundertheConfigurationManagementProgram.Thisprogramwillbeimplementedoverthenextseveralyearsfocusingonthesafetysystems.Effortswillbemadetoidentifythetypesofmateri'alanddocumentsthatcontaindesignbasisinformationandtobegintoindexandorganizeitinDocumentControl.Inthelongerterm,theDesignBasisDocumentationprojectwilldevelopDesignBasisDocumentsforthemajorplantsystemsandequipment.BecauseofthemajormodificationbiasusedinthedevelopmentofQEproceduresandthemajorupgradeprogramsthathavetakenplaceovertheyears,theengineeringdepartmentisnotformattedonasystembasis.B-6  
AppendixC(issued11/12/86).
h.EPRI,NuclearSafetyAnalysisCenterDocument,
NSAC/121,
"Guidelines
forPerforming
SafetySystemFunctional
Inspections
(November
1988).NQA-1"QualityAssurance
ProgramRequirements
forNuclearPowerPlants"(1979)j.ANSIN45.2.11,
"QualityAssurance
Requirements
fortheDesignofNuclearPowerPlants"(1974)k.NRC'egulatory
Guide1.64,"QualityAssurance
Requirements
fortheDesignofNuclearPowerPlants"l.QE-series
Engineering
Procedures
m.A-seriesGinnaStationAdministrative
Procedures
Withthisreference
materialasbackground
information
thereviewteammembersproceeded
toevaluatetheNRCconcernsandmakerecommendations
forcorrective
actiontoRG&EManagement
throughtheDepartment
Manager,NuclearEngineering
Services.
Thefollowing
is'summaryoftheguidanceprovidedbyRG&EManagement:
a.Issuesaddressed
weretofocuson,butnot,limitedto,thosecontained
intheNRCSSFIReport(IR89-81).b.c~ConcernscitedbytheNRCweretobeacceptedasvalid.Noeffortwastobeexpendedonquestioning
eitherthecitedconcernsortheexamplesusedintheNRCSSFIReport.Recommendations
weretotaketheformofinterimactionsandlong-term
corrective
actions.d.Recommendations
forinterimactionsweretobelimitedtothefollowing
items:i.Changesto~existinEngineering
andGinnaStationProcedures.
ii.CreationofalimitednumberofnewEngineering
QEorAdministrative
Procedures
and/orGinnaAdministrative
Procedures.
iii.Issuanceofpolicystatements
(atdiscipline,
department
orcorporate
level.)B-3  
e.iv.Development
ofdiscipline-specific
implementing
documents
(suchasdesignguides,standards,
etc.).v.Reassignment
ofdutiestopersonnel
withinspecificdisciplines.
Recommendations
were'obeachievable
utilizing
stafflevelsthatarecurrently
authorized.
1.4ReviewTeamRG&EManagement
selectedareviewteamtoactontheirbehalfconsisting
ofagroupofnineexperienced
personnel
representing
thefollowing
areas:Mechanical
Engineering,
Electrical
Engineering,
Structural
andConstruction
Engineering,
NuclearSafetyandLicensing,
Configuration
Management,
DocumentControl/Records
Man'agement,
GinnaTechnical
Section,andNuclearEngineering
ServicesDepartment
staff.2.0SYSTEMATIC
ASSESSMENT
Themulti-discipline
RG&ESSPIReviewTeamperformed
anassessment
oftheissuesandconcernsgenerated
bytheNRCRHRSSFI.Theteambeganbyestablishing
thefollowing
definition
of"Engineering
Assurance":
EnineerinAssurance:
Theplannedandsystematic
actionsnecessary
toprovideadequateconfidence
thatengineering
activities
areperformed
inaconsistent
mannerwithadherence
toplantlicensing
basis,applicable
procedures,
regulations
andacceptedindustrystandards.
Thereviewteammembersformed."focusgroups"whichwereassignedindividual
detailitemsfromtheprogrammatic
concernslistingestablished
intheinitialbreakdown
ofissues(appendix
A).Individual
assessments
weremadeandtheissuesgroupedanddocumented
aspartofRG&Es"Systematic
Assessment
ofEngineering
Assurance
andRHRSSPIConcernReport."Thereviewwasbasedonthereviewteam'sownassessment
aswellasondetailedinformation
obtainedthroughdiscussions
withothercognizant
engineering
and,plantpersonnel.
3.0ISSUESANDCONCERNSADDRESSED
Thereviewteamregrouped
allissuesandprogrammatic
concernsintosixtopicalareas,aslistedbelow:s-4  
3.1ToicalArea1:"Improved
ProcessforReporting
andAssessing
SafetyConcerns"
a:"ProcessforHandlingSafetyConcernsOutsidetheEWRProcess"3.2ToicalArea2:."Improved
DesignControlandReviews"a~b.cd.e.f."Engineering
Management"
"Engineering
Assurance"
"Timeliness
ofDCRProcessing"
"DesignReviews""PAIDUpgradeProgram""DesignControl"3.3ToicalArea3:"Improved
DesignInterface
Control"a."Procedural
Inconsistency"
3.4ToicalArea4:"Improved
DesignDocumentation/Design
Bases"a~b.cd.e.f.g,"Interdisciplinary
ReviewofNon-Mods"
"Calculations"
"Deletion
ofInformation
fromPGIDs""ValveIdentification
Differences"
"DesignBasisInformation"
Controlled
Instrument
ListTrainingMaterial3.5ToicalArea5:Modifications"
1"Improved
Documentation
Associated
witha."InvalidInformation
inUFSAR"b."Assessment
ofCumulative
EffectsofModifications"
c."Issuance
ofDesignOutputs"d."ControlofEWRs"3.6ToicalArea6:"Improved
Engineering/Plant
Communications"
a."Engineering/Plant
Interface"
b."Acceptance
Criteria"
c."Adequacy
ofSRVTestAcceptance
Criteria"
4.0SummarofRecommendations
Thefollowing
isageneralsummaryofthemostsignificant
interimactionsandlongtermcorrective
actions.4.1RG&E'smanagement
hasensuredclosecontrolandqualityengineering
servicesthroughtheirinteraction
andreviewofdesign,butwrittenprocedures
donotmakethatcontrolsufficiently-explicit.
B-5  
Asinterimactions,asingleprocedure
willbedeveloped
thatoutlinestheentirescopeofthedesignprocess.Discipline
designguidesforgeneration
ofdesigncriteria,
designanalysesanddesignverification
documents
willbeinitiated.
Also,theintegrated.
assessment
processwillbeseparately
"proceduralized.
Applicable
procedures
willberevisedtoestablish
therequirements
forreview,'a'pproval,
andissuanceofvendordocuments.
In,thelongerterm,weplantocompletetheupgradeofengineering
procedures
andprocesses
toreflectindustrystandards
ofgoodpractice,
efficiency
andrapidresponse.
4.24.34.4Engineering
procedures
containastrongbiastomodification
design.Thishasprovedtobewellsuitedtowardmajorstandalonedesignprojectsbutisnotaseffectively
usedtoaggressively
supportalloftheengineering
activities
associated
withawell-maintained.
operating
plant.Close-out
EWRdocumentation
canbeprotracted,
becausethescopeofamodification
maybein'creased
overtime,causingdesigndocuments
toremainopen.Asinterimactions,weplantolimitthepracticeofincreasing
thescopeofadesignmodification
duringtheintervalbetweenturnoverofthemodification
intheplantandrecordsclose-out.
WewillbegintotransmitEWRDesignPackagestoDocumentControlconcurrent
withtheissuanceoftheconstruction
package.Inthisway,thelistofapplicable
designdocuments
willalsobeestablished
forthemodification
tobeinstalled..
TheUFSARchangeprocesswillbeproceduralized
andintegrated
withtheaboveturnoverprocess.Interimactivities
areneededtobegintocapture,retain,provideaccessto,andorganizedesignbasisinformation
aspartofthenormalongoingengineering
activities.
RG&Ehasincorporated
adesignbasisdocumentation
projectundertheConfiguration
Management
Program.Thisprogramwillbeimplemented
overthenextseveralyearsfocusingonthesafetysystems.Effortswillbemadetoidentifythetypesofmateri'al
anddocuments
thatcontaindesignbasisinformation
andtobegintoindexandorganizeitinDocumentControl.Inthelongerterm,theDesignBasisDocumentation
projectwilldevelopDesignBasisDocuments
forthemajorplantsystemsandequipment.
Becauseofthemajormodification
biasusedinthedevelopment
ofQEprocedures
andthemajorupgradeprogramsthathavetakenplaceovertheyears,theengineering
department
isnotformatted
onasystembasis.B-6  
li1i  
li1i  
TheConfigurationManagementProgramisbeingdevelopedonasystemsbasis.TheQ-Listhasdefinedsystemboundariesthatwillbeusefulasweindexdesign.documentsinDocumentControlanddevelopDesignBasisDocuments.4.5Manyoftheunderlying'concernsandlongtermcorrectiveactionsarecurrentlypartoftheexistingorplannedprogramswithinConfiguration'anagementandEngineeringProceduresUpgradePrograms.TheDesignBasisDocumentation,SetpointVerification,Q-List,DocumentControlEnhancement,and.EngineeringControlledConfigurationDrawingUpgradeProgramsareindividualpartsofthisprogram.ThespecificactionsrecommendedbytheSSFIAssessmentteamwillbereviewedbytheRG&EpersonnelresponsiblefortheCMprojectstogetherwithmanagementtomakeanyneededrevisionstothescopeoftheseprojects.4.6EngineeringactivitiesareperformedbyNuclear,EngineeringServices(NES)andstationtechnicalstaff.Thedesignprocessmustensureconsistencybetweentheseactivities.Asinterimactions,weplantoincreasethecontrolsoversetpointchangesandreportingofsafetyconcerns.Aprocesswillbedevelopedtoensurethatproposedsetpointchangesaregiventheappropriatereviewpriortotheirissuance.ThePCAQprocess(PotentialConditionAdversetoQuality)hasbeenimplementedinQE-1603forNuclearEngineeringServicespersonneltoprovideidentificationanddispositionofpotentialsafetyconcernsandprovideavehicletoimprovetheinterfacewithtechnicalpersonnelattheplant.Wealsoplantodevelopastreamlinedapprovalprocessfortechnicalsupportprojectsnotinvolvingmodifications.InthelongtermwewillexamineestablishingasingleprocessforallNuclearDivisionpersonneltoreportspecificconcernswhichmayhavesafetysignificance.ProcesseswillbedevelopedtoensurecommonalityofproceduresbetweenNESandtheTechnicalSectionatGinna.B-7  
TheConfiguration
Management
Programisbeingdeveloped
onasystemsbasis.TheQ-Listhasdefinedsystemboundaries
thatwillbeusefulasweindexdesign.documents
inDocumentControlanddevelopDesignBasisDocuments.
4.5Manyoftheunderlying
'concerns
andlongtermcorrective
actionsarecurrently
partoftheexistingorplannedprogramswithinConfiguration'anagement
andEngineering
Procedures
UpgradePrograms.
TheDesignBasisDocumentation,
SetpointVerification,
Q-List,DocumentControlEnhancement,
and.Engineering
Controlled
Configuration
DrawingUpgradeProgramsareindividual
partsofthisprogram.Thespecificactionsrecommended
bytheSSFIAssessment
teamwillbereviewedbytheRG&Epersonnel
responsible
fortheCMprojectstogetherwithmanagement
tomakeanyneededrevisions
tothescopeoftheseprojects.
4.6Engineering
activities
areperformed
byNuclear,Engineering
Services(NES)andstationtechnical
staff.Thedesignprocessmustensureconsistency
betweentheseactivities.
Asinterimactions,weplantoincreasethecontrolsoversetpointchangesandreporting
ofsafetyconcerns.
Aprocesswillbedeveloped
toensurethatproposedsetpointchangesaregiventheappropriate
reviewpriortotheirissuance.
ThePCAQprocess(Potential
Condition
AdversetoQuality)hasbeenimplemented
inQE-1603forNuclearEngineering
Servicespersonnel
toprovideidentification
anddisposition
ofpotential
safetyconcernsandprovideavehicletoimprovetheinterface
withtechnical
personnel
attheplant.Wealsoplantodevelopastreamlined
approvalprocessfortechnical
supportprojectsnotinvolving
modifications.
Inthelongtermwewillexamineestablishing
asingleprocessforallNuclearDivisionpersonnel
toreportspecificconcernswhichmayhavesafetysignificance.
Processes
willbedeveloped
toensurecommonality
ofprocedures
betweenNESandtheTechnical
SectionatGinna.B-7  
000  
000  
SYSTEMATICASSESSMENTOFENGINEERINGASSURANCEISSUESANDRHRSSFICONCERNSAPPENDIXA
SYSTEMATIC
ASSESSMENT
OFENGINEERING
ASSURANCE
ISSUESANDRHRSSFICONCERNSAPPENDIXA
Cl0  
Cl0  
ProrammaticConcernsAreasInvolvinSiificantIdentifiedWeaknessesResonseScoeListinENGINEERINGMANAGEMENTWeaknessinmanagerialandadministrativecontrolsManagementreliesonengineer'sexperienceinsteadofformalcontrolsEngineeringmanagementhasnotprovidedclearguidanceandproceduralcontrolsoverdesignchangeprocessLackofEngineeringAssurancePracticesOrganizationalInterfacesw~Controlofdocumentation,engineeringdesigninterfaces,andengineeringcommunicationswithexternalorganizationsispoor.Lackofcriteriafor.determiningwhenengineeringconcurrenceisneededDCR'snotprocessedinatimelymannerDesignoutputnotproperlydistributedUFSARcontainsinvalidinformationNoprocessforhandlingsafetyconcernsidentifiedoutsidetheengineeringprocessP&IDchangedidnotresultinanUFSARchangeasappropriateEngineeringDisciplineInterfacesEachdisciplinehasitsowninterpretationofengineeringprocedurerequirements.EngineeringManagementhasadifferentperceptionthantheengineeringstaffP&IDchangesoccurredwithoutaninterdisciplinaryreviewCONFIGURATIONMANAGEMENTPlantBaselineConfigurationLackofcompleteandconsistentnomenclaturebetweenP&IDsandprocedures,UFSARandQAManualDeletionofinformationfromP&IDsDesignBasesr~DesignBasisCalculationnotavailableordonotexist~Lackofdocumenteddesignbasisisagenericweakness~UFSARcontainsinvalidinformationwithoutasupportingdesignbasis~Nocalculationlistorformalizedoveralllisting
ProrammaticConcernsAreasInvolvinSiificantIdentified
Weaknesses
ResonseScoeListinENGINEERING
MANAGEMENT
Weaknessinmanagerial
andadministrative
controlsManagement
reliesonengineer's
experience
insteadofformalcontrolsEngineering
management
hasnotprovidedclearguidanceandprocedural
controlsoverdesignchangeprocessLackofEngineering
Assurance
Practices
Organizational
Interfaces
w~Controlofdocumentation,
engineering
designinterfaces,
andengineering
communications
withexternalorganizations
ispoor.Lackofcriteriafor.determining
whenengineering
concurrence
isneededDCR'snotprocessed
inatimelymannerDesignoutputnotproperlydistributed
UFSARcontainsinvalidinformation
Noprocessforhandlingsafetyconcernsidentified
outsidetheengineering
processP&IDchangedidnotresultinanUFSARchangeasappropriate
Engineering
Discipline
Interfaces
Eachdiscipline
hasitsowninterpretation
ofengineering
procedure
requirements.
Engineering
Management
hasadifferent
perception
thantheengineering
staffP&IDchangesoccurredwithoutaninterdisciplinary
reviewCONFIGURATION
MANAGEMENT
PlantBaselineConfiguration
Lackofcompleteandconsistent
nomenclature
betweenP&IDsandprocedures,
UFSARandQAManualDeletionofinformation
fromP&IDsDesignBasesr~DesignBasisCalculation
notavailable
ordonotexist~Lackofdocumented
designbasisisagenericweakness~UFSARcontainsinvalidinformation
withoutasupporting
designbasis~Nocalculation
listorformalized
overalllisting
   
   
~Operatingprocedures,emergencyprocedures,andoperatortraining.,materialdonotreflectthelimitingdesignbasisofthesystemDesignModificationsRG&Edoesnothaveamechanismforaccountingforsynergisticeffectsofmodifications(electricalcalcs,pipestresscalcs)NumerousweaknessesexistinengineeringsupportandplantmodificationactivitiesDocumentControl,~UFSARcontainsinvalidinformationLackofcomprehensivecontrolledinstrumentlistWeaknessinmanagementcontrolsystemtoassurecompleteandconsistentdesignoutputisissuedanddistributedPSIDsissuedhaveremovedandrevisedinformation.TeamconcernedhowRG6EmaintainstraceabilityofthisinformationInformationalinconsistenciesexistbetweendocumentsDCRprocessingisnottimelyEWRsremaininpersonalcontrolofresponsibleengineerEWRslackindexCompletedEWRsarenotprocessedintothedocumentcontrolsysteminatimelymannerUncontrolledtrainingmaterialENGINEERINGPROCEDURESDesignReviewsReviewprocesslacksdepthReviewandverificationdoesnotstrictlyfollowANSIN45.F11InadequateReviewIndependentVerificationnotdoneinaccordancewithengineeringproceduresCalculations-GenericweaknessinreviewandapprovalofcalculationsCalculationalcontrolprogram(ANSIN45.2.11)isweakNolistofcalculations,nowaytotrackpastcalculationsSetpoints~Instrumentloopsetpointsmaynotaccountforloopinaccuracies
~Operating
procedures,
emergency
procedures,
andoperatortraining.,material
donotreflectthelimitingdesignbasisofthesystemDesignModifications
RG&Edoesnothaveamechanism
foraccounting
forsynergistic
effectsofmodifications
(electrical
calcs,pipestresscalcs)Numerousweaknesses
existinengineering
supportandplantmodification
activities
DocumentControl,~UFSARcontainsinvalidinformation
Lackofcomprehensive
controlled
instrument
listWeaknessinmanagement
controlsystemtoassurecompleteandconsistent
designoutputisissuedanddistributed
PSIDsissuedhaveremovedandrevisedinformation.
Teamconcerned
howRG6Emaintains
traceability
ofthisinformation
Informational
inconsistencies
existbetweendocuments
DCRprocessing
isnottimelyEWRsremaininpersonalcontrolofresponsible
engineerEWRslackindexCompleted
EWRsarenotprocessed
intothedocumentcontrolsysteminatimelymannerUncontrolled
trainingmaterialENGINEERING
PROCEDURES
DesignReviewsReviewprocesslacksdepthReviewandverification
doesnotstrictlyfollowANSIN45.F11Inadequate
ReviewIndependent
Verification
notdoneinaccordance
withengineering
procedures
Calculations-
Genericweaknessinreviewandapprovalofcalculations
Calculational
controlprogram(ANSIN45.2.11)
isweakNolistofcalculations,
nowaytotrackpastcalculations
Setpoints
~Instrument
loopsetpoints
maynotaccountforloopinaccuracies
   
   
~AcceptancecriterianotestablishedintestprocedureforsetpointofundervoltagealarmrelaysOtherLackofformalcontrolofengineeringanddesigndocumentsRG&EdesigncontrolmeasuresdonotcomparefavorablywithacceptedindustrypracticesUFSARcontainsinvalidinformationLackofinterfacecontrolwithinternalandexternalorganizationsSRVtestingprocedurescontaingeneralandminimalinformationSAFETYCONCERNSInabilitytoproperlyidentifysafetyconcerns(batteryloadprofiledeficienciesnotdiscovered)Inabilitytoassesssafetyconcerns(poorrootcauseanalysis)Nomechanismtodispositionsafetyconcernsidentifiedoutsideofthenormalengineeringprocess(PIC-629EWRdidnotreflectanyactiontakenonidentifiedconcernTESTINGDCundervoltagetestinadequateSRVtestinginadequateMCCBsnottestedperiodicallySPECIFICDESIGNCONCERNSSWSingleFailureInadequateRHRNPSHJumpercableexceededminimumallowedbendradiusBatteryrackdonothaveagroundingcableRHRpumpsealfailure(Eg)RHRpumpsealfailurecausinglossofbothRHRpumps(singlefailure)
~Acceptance
criterianotestablished
intestprocedure
forsetpointof
undervoltage
alarmrelaysOtherLackofformalcontrolofengineering
anddesigndocuments
RG&Edesigncontrolmeasuresdonotcomparefavorably
withacceptedindustrypractices
UFSARcontainsinvalidinformation
Lackofinterface
controlwithinternalandexternalorganizations
SRVtestingprocedures
containgeneralandminimalinformation
SAFETYCONCERNSInability
toproperlyidentifysafetyconcerns(batteryloadprofiledeficiencies
notdiscovered)
Inability
toassesssafetyconcerns(poorrootcauseanalysis)
Nomechanism
todisposition
safetyconcernsidentified
outsideofthenormalengineering
process(PIC-629EWRdidnotreflectanyactiontakenonidentified
concernTESTINGDCundervoltage
testinadequate
SRVtestinginadequate
MCCBsnottestedperiodically
SPECIFICDESIGNCONCERNSSWSingleFailureInadequate
RHRNPSHJumpercableexceededminimumallowedbendradiusBatteryrackdonothaveagrounding
cableRHRpumpsealfailure(Eg)RHRpumpsealfailurecausinglossofbothRHRpumps(singlefailure)
}}
}}

Revision as of 13:16, 29 June 2018

Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion
ML17262A133
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/11/1990
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To: MARTIN T T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 9009200182
Download: ML17262A133 (2)


See also: IR 05000244/1989081

Text

k'LROCHESTER

GASANDELECTRICCORPORATION

ROBERTChtECREDYVi<ehetidentCinnet4uclee<Ptoduction

/'.tone>t*te~89EASTAVENUE,ROCHESTER

N.Y.14649-0001

TELEPHONE

AREACODE71B5462700September

11,1990Mr.ThomasT.MartinRegionalAdministrator

U.S.NuclearRegulatory

Commission

RegionI475Allendale

RoadKingofPrussia,PA19406'ubject:

120-dayResponsetoInspection

Report50-244/89-81

SafetySystemFunctional

Inspection

ontheRHRSystemR.E.GinnaNuclearPowerPlantDocketNo.50-244Reference:

(a)NRCInspection

Report50-244/89-81,

datedMay9,1990(b)RG&EletterfromR.C.Mecredy-toNRC,T.T.Martin,datedJune8,1990DearMr.Martin:Reference

(a)requested

aresponsetotwoNoticesofViolation

andseveralunresolved

itemswithin30daysandawrittenevaluation

ofthedeficiencies

identified

inSection2.1oftheInspection

Reportwithin120days.Inour30-dayresponsetotwoNoticesofViolation,

Ref.(b),wesummarized

ourproposedresolution

orscheduleforresolution

fortheunresolved

items89-81-01through10.TheNRCunresolved

itemdescription

andourproposedresolution

ofeachofthesewasdiscussed

inenclosures

CandEofRef.(b).Anupdateoftheappropriate

unresolved

itemsisprovidedasAttachment

Atothisresponse.

Specificactionsregarding

allNRCunresolved

itemsarebeingtrackedtocompletion

byRG&E.~U~cIQet\Aoo1'Q~C3oPo+Theidentified

weaknesses

inSection2.1oftheInspection

Reportcollectively

raisedanNRCconcernastotheeffectiveness

ofRG&E'scurrentpractices

toestablish

engineering

assurance.

Thiswasidentified

asunresolved

item89-81-11andisthefocusofthisresponse.

RG&Erecognizes

thatunresolved

item89-81-11,

engineering

assurance,

ischaracterized

bybroadprogrammatic

issues.RG&Ehascompleted

anevaluation

ofthedeficiencies

andconcernsraisedintheInspection

Reportbyperforming

aninternalassessment

oftheunderlying

issuesidentified

inSection2.1andtheexamplesdiscussed

inSection2.2.Ourassessment

hasbeendocumented

inangQ~o//(]

Cl

internalreportentitled"Systematic

Assessments

ofEngineering

Assurance

Issues'andRHRSSFIConcerns"

dated9/11/90.RG&Ebelievesthattheunderlying

concernsnecessitate

bothinterim.and

longtermactivities

toresolve.Ourapproachinperforming

the-internal

assessment

andasummaryofthehighpriorityactionsarepresented

inAttachment

B.Thisattachment

isasummaryoftheconsiderable

effortsofanRG&ESSFIAssessment

Teamcomposedofagroupofexperienced

RG&Estaffandmanagement

personnel.

Theprimarytaskof'theRG&ESSFIAssessment

TeamwastoprepareareporttoRG&E'smanagement

whichrecommended

themosteffective

interimactionsneededtobegintheprocessofstrengthening

theengineering

processes

and.controls.

TheRG&ESSFIAssessment

Teamwascomposedofnineseniorengineers

andstaff.Theteammettore-examine

theinspection

reportandcategorize

thedeficiencies

bytopicalareas.Theteamalsoevaluated

areportpreparedbyanRG&Econsultant

whoindependently

identified

theprogrammatic

concerns.

Theassessment

consisted

ofindividual

evaluations

byteammembersaswellasworkingsessionsasagroup.TheRG&EAssessment

TeamgroupedtheNRCidentified

deficiencies

intothefollowing

topicalareas:~Improved~Improved~Improved~Improved~Improved~ImprovedMethodofIdentifying

and.Assessing

SafetyConcernsDesignControlandReviewsDesignInterface

ControlDocumentation

Associated

withDesignBasesDocumentation

Associated

withModifications

Engineering/Plant

Communications

Theteamthenestablished

interimactionsandlongtermcorrective

actionsforeachtopicalarea.Theteamprioritized

theinterimactionsandestablished

aproposedschedule.

Theinterimactionswererecommended

baseduponachieving

afundamental

improvement

ontheengineering

process.Interimactionsarethoseactionswhichcanbeimplemented

immediately

orwithinaperiod.ofuptoayear.Long-term

corrective

actionswerealsorecommended,.

Manyofthelongertermrecommendations

arealreadyembodiedintwomajorprograms:

Configuration

Management

(CM)andtheEngineering

Procedures

UpgradeProgram.AreportontheConfiguration

Management

programdescriptions

andschedulewaspresented

tomembersofRegionIandNRRonMarch6andMarch27,1990,respectively.

(Individual

projectswithintheCMprogrammaybeexaminedwithintheenclosure

toInspection

Report90-03,datedApril18,1990).TheEngineering

Procedures

Upgradeprogramhasbeeninitiated

andwillincludeanexternalassessment

ofourcurrentprocedures

byanindependent

consultant.

Itisexpectedthatthisassessment

willbecompletebyyear-end.

TheresultsofRG&E'sinternalSSFIAssessment

willbecomeaninputtotheEngineering

Procedures

UpgradeandtheConfiguration

Management

Programs.

Attachment

BisasummaryreportoftheAssessment

Teamactivities

andrecommendations.

RG&Ebelievesthatmanyofthedeficiencies

notedundertheengineering

assurance

unresolved

item89-81-11hadbeenrecognized

priortotheRHRSSFIandhavebeenenveloped

underthevariousConfiguration

Management

Projects,

suchastheSetpointVerification

ProgramandDesignBasisDocumentation

Projects.

Wehaverecognized

thatinterimactionsarenecessary

tosufficiently

strengthen

theengineering

processes,

procedures

anddocumentation

ofinformation

tobridgethegaptotheselongertermprograms.

Wehavebeguntheprocesstoimplement

theseactionsandplantoexaminetheireffectiveness,

during1991.Webelievethattheinterimactionsplannedarethemosteffective

measuresforRG&Etoprovideadequateresolution

oftheidentified

deficiencies

whileweareimplementing

thelongtermConfiguration

Management

Programs.

TheNRCInspection

Reportidentified

theEngineering

A'ssurance

deficiencies

insections2.2.1.1,2.2.1.2,2.2.3.2,and2.2.3.3.TheRG&Eassessment

concentrated

ontherootcausesofthesedeficiencies

andnotjusttheexamplesthemselves.

Nevertheless,

thespecificanalyses,

reports,anddrawingsthatrequirerevisions

orcorrections

asdescribed

inthesesectionsarebeingrevisedorupdatedasnecessary,

including

forexample,thecalculations

discussed

insection2.2.1.2andthedrawingsidentified

insection2.2.3.3(B).

,Ourspecificevaluations

relativetotheexamplesfoundinthesefoursectionsarecontained

intheAssessment

Teamreport.Webelievethatthesystematic

assessment

discussed

inAttachment

Bisathoroughandappropriate

responsetounresolved

item89-81-11.Pleasenotifyusifyoubelievewehavenotinterpreted

theNRCreportcorrectly.

Verytrulyyours,GAHK118Atta'chment

RobertC.Mecredyxc:U.S.NuclearRegulatory

Commission

(original)

DocumentControlDeskWashington,

D.C.20555AllenR.Johnson(MailStop14Dl)ProjectDirectorate

I-3Washington,

D.C.20555GinnaSeniorResidentInspector

Attachment

AUPDATEOFUNRESOLVED

ITEMSFROMRG&E'sENCLOSURE

EOF,JUNE8,1990URI89-81-02(Section2.2.1.4)Resolution

ofSafetyConcernsJune8,1990:Aninterimprocessforhandlingsafetyconcernsisunderdevelopment

andwillbediscussed

inour120dayresponse.

Update:RG&Ehasdeveloped

aformalprocessinProcedure

QE-1603,Documenting

andReporting

ofConditions

AdversetoQuality,forhandlingpotential

safetyconcernsidentified

byNuclearEngineering

Servicespersonnel.

Theseamongtheconditions

-whichwouldbereported,

are:nonconformances,

deviations,

deficiencies,

failures,

malfunctions,

defective

materialandequipment,

vendortechnical

reports,designbasisdocumentation,

andthematerialcondition

oftheplantstructures,

systemsorcomponents.

Theprocedure

requiresthatpotential

safetyconcernsbedocumented

andtrackedbyNuclearEngineering

Servicespersonnel.

Theprocessprovidesfor:ensuringthatapreliminary

safetyevaluation

isperformed

byNuclearSafetyandLicensing;

transmitting

information

concerning

conditions

thatinvolveasafetyconcerntotheTechnical

Manager,GinnaStation;disposition

ofsafetyconcernsthroughtheappropriate

processsuchasanonconformance

report(NCR),and.identified

deficiency

report(IDR);reviewing

thecondition

andpreliminary

safetyevaluation

byGinnaStationTechnical

Sectionagainstthecriteriaforreporting

events(A-25.1);

dispositioning

thecondition

throughtheappropriate

processsuchascorrective

actionreports(CAR),procedure

changenotice(PCN)andworkrequest/trouble

request(WR/TR);providing

theinitiator

withthefeedbackonthedisposition.

Potential

conditions

adversetoqualitythatarediscovered

byGinnaStationpersonnel

aredispositioned

byoneofthecurrentprocesses

undertheMaintenance

WorkRequestandTroubleReport(A-1603),

Corrective

ActionReport(A-1601),

andReporting

ofUnusualPlantConditions

(A-25).Interimandlongtermcorrective

actionsrecommended

aspartoftheRG&ESSFIAssessment

aredescribed

inAttachment

BunderthegeneraltopicalareaImprovedProcessforReporting

andAssessing

SafetyConcerns.

A-1

URI,89-81-05(Section2.2.2.2)Electrical

LoadGrowthProgramJune8,1990:Wearetakingactionstointegrate

thisprocessintotheappropriate

Engineering

(QE)procedures.,

Weanticipate

completion

oftheseactionsbythedateofour120dayresponse.

Update:RG&Eissuedachangetoengineering

procedure

QE-301Rev.11withissuanceofPDR0609dated7/9/90.Thischangerequiresthatourdesignprocessensurethattheeffectsofallloadchangesonthestationbatteries

ordiesel-generators

shallbeaddressed,

including

therequirement

thatthesebeevaluated

andshowntobewithinthemarginallowedbythecurrentloadinganalysis.

DuringtheRG&ESSFIReviewTeamAssessment

itwasnotedthatotherexampleswereidentified

whichcouldbeplacedwithintheissueofestablishing

amechanism

toevaluatethecumulative

effectsofmodifications.

Interimandlongtermcorrective

actionsaredescribed

withinAttachment

BunderthegeneraltopicalareaImprovedDocumentation

Associated

withModifications.

URI89-81-07(Section2.2.4.4.a.,

b.,andd.)ControlRoomP&ID'sJune8,1990:Aninterimprocessforenhancing

theupdateprocessforcontrolroominformation

.iscurrently

underreviewandwillbediscussed

inthe120dayresponse.

Update:Thisconcernwasmanifested

intwoareas,drawingchangerequests(DCRs)andtrainingmaterial.

DCRProcess:Thetimeliness

ofprocessing

drawingchangeshasbeenenhancedthroughimplementation

ofRevision3ofA-606,DrawingChangeRequestsprocedure.

Thisupgradedirectsthetimelyupgrading

ofdrawingsusedintheControlRoomandTechnical

SupportCenter.Postingofdrawingchangesisrequiredwithin2workingdaysfromtheirreceiptbyCentralRecords.(Generalpracticehasbeensamedayposting).

TheapprovalandtrackingoftheDCRprocessiscurrently

assignedtotheTechnical

SectionatGinnaStation.Plansarebeingmadetotransferdataentry,controlofthedatabaseanddistribution

totheDocumentControldepartment.

Anotherenhancement

includesamonthlyDCRstatusreportthatisdistributed

tomanagement.

TheDCRprocesshasbeengivenincreased

emphasisthroughprocedural

contr'ols.

Withitspresentmethod,RG&Ebelievesthattimelypostingandeffective

trackingandtrendingoftheDCRsystemwillbeachieved..

A-2

4

TraininMaterial:

RG&Eiscommitted

toensuringthatalltrainingmaterialavailable

toLicensedoperators

isascorrectandcurrentaspossible.

Duringtheinspection

weagreedthattheLessonTextRG&E-25contained

aninvalidvalueforthetimeavailable

toisolatea50gpmsealleaktopreventRHRpumpmotorflooding.

Otherinformation

relativetoplantmodifications

onvalve:numbers

(EWR4761)andpipingmodification

(EWR4675)alsohadnotyetbeenincorporated

intotheLessonTextbecausetheTrainingChangeRequesthadnotyetbeenimplemented.

Afterthediscrepancy

ontheisolation

timewasidentified

toRG&E,theLessonTextwasimmediately

corrected.

Forclarity,theLessonTextshavebeenrenamedTRAININGSYSTEMSDESCRIPTIONS.

However,thesearenotdefinedasControlled

Configuration

material.

Thesedocuments

arenotmeanttotaketheplaceofapprovedplantprocedures,

engineering

designdocuments,

plantdrawingsorvendortechnical

manuals.Theyareusedasreference

material,

arrangedbysystem,thatcontainaconceptual

overviewof.thatsystemdesignedtobeused.asajoband.trainingaid.Weunderstand

theNRC'sconcernoverthefactthatthismaterialisavailable

foruseinthecontrolroom,maybefrequently

used,andisnotdesignated

asbeingpotentially

outofdate.Webelievetheprimaryconcernisthetimeliness

ofupdatingthismaterialtoreflecttheplantconfiguration,

notoverthecontroloverthesedocuments.

Therefore,

strictcontrolhasbeenplacedoverthesedocuments.

Thereisamastercopycontrolled

b'ytheTrainingDepartment

andallchangesarecontrolled

byprocedure

TR5.9(Training

ChangeRequest/Notice).

Recordsarekeptofcontrolled

copyholdersofcontrolled

copies.Placement

ofthismaterialinthecontrolroomiscontrolled

bytheTrainingDepartment.

Thisisthenorm,nottheexception,

intheutilityindustry.

Weunderstand

andrecognize

theunderlying

concernidentified

overthetimeliness

ofproviding

currentandcontrolled

materialtothosewhomayuseit.Procedures

TR5.5.1(Tracking

PlantChanges)iscurrently

theprocessthathasbeendeveloped

andimplemented

toidentifyandtrackplantchangesandincludethosechangesintrainingmaterialwhereappropriate.

Wehavetakenadditional

stepsinordertoprovidetrainingmaterialthatisascurrentaspossibleandtobetterdefinethepurposeofthismaterial.

1.Placeacopyofthe"Information

Letter"inallTrainingSystemDescriptions

thatareaffectedbyaplantmodification.

Thisactionhasbeenimplemented

andwillbecontrolled

byConfiguration

A-3

2.Management

TrainingGuidelines,

CMTG-3.0,

Preparation

andUseofInformation

Letters.Theinformation

letterprovidescurrentinformation

onamodification.

Theletterwillremainpartofthesystemdescription

untilthesystemdescription

hasbeenrevised.toincorporate

thenewmodification.

IThefirstpageofeachTrainingSystemDescription

willbestampedTRAININGINFORMATION

ONLY.Thisactionhasbeeninitiated..

3.IncludethedateofrevisionforeachpageoftheTrainingSystemDescription.

Thisactionhasbeenimplemented.

Therewerenoadditional

interimremedialactionsrecommended

aspartoftheRG&ESSFIReviewTeamAssessment

otherthanthoseabove.Longtermcorrective

actionsaredescribed

inAttachment

BundergeneraltopicalareaPlantDesignInformation/Design

Bases.URI89-81-06(Section2.2.2.3)MoldedCaseCircuitBreakerJune8,1990:Theindustryiscurrently

examining

theneedfor,andbenefitsof,moldedcasecircuitbreakerstesting.RG&EwillcontinuetoworkcloselywiththeindustryandEPRItodetermine

theappropriate

testmethodsandrequirements.

Update:DuringAugustRG&Epersonnel

fromEngineering

andPlantMaintenance

visitedtheDiabloCanyonPowerPlanttoinspecttheequipment

andprocedures

forperiodictestingofmoldedcasecircuitbreakersusedbyPG&E.ResultsofthefirstcycleoftestingbytheDiabloCanyonstaffwerealsodiscussed.

AsimilarprogramforGinnaStationappearstobetechnically

feasible,

subjecttoadditional

evaluation

andprocurement

oftestequipment,

development

ofprocedures,

andperformance

ofatrialtestprogram.Itisanticipated

thatatrialprogramcanbeinitiated

withinthenextyear.Itisestimated

thatthefirstcycleofatestprogramwouldrequirefourormoreyearstocompletefollowing

thesuccessful

completion

ofatrialtest.A-4

Attachment

BSYSTEMATIC

ASSESSMENT

OFENGINEERING

ASSURANCE

ISSUESANDRHRSSFICONCERNSThisattachment

isasummaryoftheSSFIAssessment

Teamapproachandrecommended

actionsextracted.

fromtheRG&Ereportwiththesamename.

Systematic

Assessment

ofEngineering

Assurance

IssuesandRHRSSFIConcernsTABLEOFCONTENTS1.0INTRODUCTION

1.1~purose1.3ScoeofReviewandRecommendations

1.4ReviewTeam2.0SYSTEMATIC

ASSESSMENT

'I3.0ISSUESANDCONCERNSADDRESSED

4.0SUMMARYOFRECOMMENDATIONS

APPENDICES:

AppendixA,Programmatic

ConcernsListingPagei

0

Systematic

Assessment

ofEngineering

Assurance

IssuesandRHRSSFIConcerns1.0INTRODUCTION

1e2~PuroseThisdocumentprovidestheresultsofasystematic

assessment

ofissuesandconcernsraisedbytheNRC',sSafetySystemFunctional

Inspection

(SSFI)conducted

duringNovemberandDecember,

1989,whichfocusedontheGinnaStationResidualHeatRemoval(RHR)System.Thissummaryreportalsopresentsinterimremedialactionsandlong-term

corrective

actions.Otherstepstowardimprovements,

alreadyinprogress,

arealsolisted..BackroundAsafetySystemFunctional

Inspection

(SSFI)wasperformed

byanNRCteamfromNovember6toDecember8,1989,atRG&Efacilities

(GinnaStationandthecorporate

offices),

andisdocumented

inaletterfromtheNRCdatedMay9,1990.Theobjective

oftheSSFIwastoassessthecapability

oftheGinnaResidualHeatRemoval(RHR)systemtoperformitsdesignbasissafetyfunctions.

TheNRCinspection

teamevaluated

theadequacyofoperational

procedures,

testpractices,

,andmaintenance

policiesastheycontribute

toRHRsystemreliability.

TheNRCteamalsoaddressed

thequalityofengineering

supportactivities.

TheNRCteamdidnotidentifyanyconditions

thatwouldprohibittheRHRsystemfromperforming

itsintendedfunctions

undernormalanddesignbasisaccidentconditions.

However,itwasstatedbytheNRCthatcompleteverification

ofsystemreliability

wasnotpossiblesincethedesignbasiscalculations

fortheRHRsystemwerenotreadilyavailable.

TheNRCSSFIteamdidhaveoneimmediate

concernand,asaresult,RG&Ewasrequested

topromptlyresolveadiscrepancy

regarding

thepotential

floodingoftheRHRpumproom.Ouractionstakentoresolvethisweredocumented

inEnclosure

EtoourJune8,1990response(URI89-81-10).

InadditionitappearedtotheNRCinspection

teamthattwoactivities

werenotconducted

infullcompliance

withNRCrequirements,

asdescribed

intheNoticeofViolation

(NOV)enclosedasAppendixAtotheNRCSSFIInspection

Report.B-1

TheRG&EresponsetotheNOVincludedascheduleforresolving

theunresolved

items(exclusive

of89-81-11discussed

above)identified

intheNRCSSFIreport.TheRHRSSFIInspection

Reportalsocited,anumberofconcernswhichcouldbeassociated

withbroaderprogrammatic

issues.TheNRCinspection

teamconcluded

thatweaknesses

existinengineering

supportandplantmodification

activities.

Theseweaknesses

werelistedinSection2.1,andwerediscussed

inSection2.2,oftheNRCSSFIInspection

Report,andhavebeenassignedunresolved

itemnumber89-81-11.

TheSSFIInspection

Reportrequired'G&E

to"providetheirevaluation

ofthoseweaknesses

within120days".Theidentified

weaknesses

wereplacedunderthebroadcategoryof"engineering

assurance"

bytheNRC.RG&Ecommitted'n

theJune8,199030-dayresponsetoconductareviewofitsengineering

processusingasystematic

approach.

RG&Eelectedtoperformitsevaluation

ofthe"engineering

assurance"

issuesbyutilizing

areviewteamapproach.

Theresultsofthereviewteamapproachwasintendedtoprovidethebasistoward.resolution

ofNRCSSFIInspection

unresolved

item89-81-11.

1.3Scoe.oftheReviewand'Recommendations

ThescopeoftheSSFIreviewwasestablished

byRG&EManagement

priortotheinitiation

ofthereviewteameffort.RG&EManagement

providedgeneralguidanceforconductofthereview'teameffortaswellasspecificguidanceonthescopeofpotential

recommendations.

Toensurethatathoroughevaluation

wasconducted,

thereviewteamexaminedthematerialfoundinthefollowing

documents:

a~NRCSSFIReportno.50-244/89-81,

dated,May9,1990b.RG&E's30-dayresponselettertotheNRCdatedJune8,1990c~Commitment

andActionTrackingSystem(CATS)commitments

established

bytheNRCinspection

reportandRG&E'sJune8,1990letter.d.e.INPOGoodPractices,

"Guidance

fortheConductofDesignEngineering"

(INPO88-016)December,

1988GroveEngineering

ReviewReportdatedJuly10,1990Applicable

sectionsoftheRG&EConfiguration

Management

(CM)Plan.B-2

0

g,NRCSafetySystemFunctional

Inspection

Guidelines,

AppendixC(issued11/12/86).

h.EPRI,NuclearSafetyAnalysisCenterDocument,

NSAC/121,

"Guidelines

forPerforming

SafetySystemFunctional

Inspections

(November

1988).NQA-1"QualityAssurance

ProgramRequirements

forNuclearPowerPlants"(1979)j.ANSIN45.2.11,

"QualityAssurance

Requirements

fortheDesignofNuclearPowerPlants"(1974)k.NRC'egulatory

Guide1.64,"QualityAssurance

Requirements

fortheDesignofNuclearPowerPlants"l.QE-series

Engineering

Procedures

m.A-seriesGinnaStationAdministrative

Procedures

Withthisreference

materialasbackground

information

thereviewteammembersproceeded

toevaluatetheNRCconcernsandmakerecommendations

forcorrective

actiontoRG&EManagement

throughtheDepartment

Manager,NuclearEngineering

Services.

Thefollowing

is'summaryoftheguidanceprovidedbyRG&EManagement:

a.Issuesaddressed

weretofocuson,butnot,limitedto,thosecontained

intheNRCSSFIReport(IR89-81).b.c~ConcernscitedbytheNRCweretobeacceptedasvalid.Noeffortwastobeexpendedonquestioning

eitherthecitedconcernsortheexamplesusedintheNRCSSFIReport.Recommendations

weretotaketheformofinterimactionsandlong-term

corrective

actions.d.Recommendations

forinterimactionsweretobelimitedtothefollowing

items:i.Changesto~existinEngineering

andGinnaStationProcedures.

ii.CreationofalimitednumberofnewEngineering

QEorAdministrative

Procedures

and/orGinnaAdministrative

Procedures.

iii.Issuanceofpolicystatements

(atdiscipline,

department

orcorporate

level.)B-3

e.iv.Development

ofdiscipline-specific

implementing

documents

(suchasdesignguides,standards,

etc.).v.Reassignment

ofdutiestopersonnel

withinspecificdisciplines.

Recommendations

were'obeachievable

utilizing

stafflevelsthatarecurrently

authorized.

1.4ReviewTeamRG&EManagement

selectedareviewteamtoactontheirbehalfconsisting

ofagroupofnineexperienced

personnel

representing

thefollowing

areas:Mechanical

Engineering,

Electrical

Engineering,

Structural

andConstruction

Engineering,

NuclearSafetyandLicensing,

Configuration

Management,

DocumentControl/Records

Man'agement,

GinnaTechnical

Section,andNuclearEngineering

ServicesDepartment

staff.2.0SYSTEMATIC

ASSESSMENT

Themulti-discipline

RG&ESSPIReviewTeamperformed

anassessment

oftheissuesandconcernsgenerated

bytheNRCRHRSSFI.Theteambeganbyestablishing

thefollowing

definition

of"Engineering

Assurance":

EnineerinAssurance:

Theplannedandsystematic

actionsnecessary

toprovideadequateconfidence

thatengineering

activities

areperformed

inaconsistent

mannerwithadherence

toplantlicensing

basis,applicable

procedures,

regulations

andacceptedindustrystandards.

Thereviewteammembersformed."focusgroups"whichwereassignedindividual

detailitemsfromtheprogrammatic

concernslistingestablished

intheinitialbreakdown

ofissues(appendix

A).Individual

assessments

weremadeandtheissuesgroupedanddocumented

aspartofRG&Es"Systematic

Assessment

ofEngineering

Assurance

andRHRSSPIConcernReport."Thereviewwasbasedonthereviewteam'sownassessment

aswellasondetailedinformation

obtainedthroughdiscussions

withothercognizant

engineering

and,plantpersonnel.

3.0ISSUESANDCONCERNSADDRESSED

Thereviewteamregrouped

allissuesandprogrammatic

concernsintosixtopicalareas,aslistedbelow:s-4

3.1ToicalArea1:"Improved

ProcessforReporting

andAssessing

SafetyConcerns"

a:"ProcessforHandlingSafetyConcernsOutsidetheEWRProcess"3.2ToicalArea2:."Improved

DesignControlandReviews"a~b.cd.e.f."Engineering

Management"

"Engineering

Assurance"

"Timeliness

ofDCRProcessing"

"DesignReviews""PAIDUpgradeProgram""DesignControl"3.3ToicalArea3:"Improved

DesignInterface

Control"a."Procedural

Inconsistency"

3.4ToicalArea4:"Improved

DesignDocumentation/Design

Bases"a~b.cd.e.f.g,"Interdisciplinary

ReviewofNon-Mods"

"Calculations"

"Deletion

ofInformation

fromPGIDs""ValveIdentification

Differences"

"DesignBasisInformation"

Controlled

Instrument

ListTrainingMaterial3.5ToicalArea5:Modifications"

1"Improved

Documentation

Associated

witha."InvalidInformation

inUFSAR"b."Assessment

ofCumulative

EffectsofModifications"

c."Issuance

ofDesignOutputs"d."ControlofEWRs"3.6ToicalArea6:"Improved

Engineering/Plant

Communications"

a."Engineering/Plant

Interface"

b."Acceptance

Criteria"

c."Adequacy

ofSRVTestAcceptance

Criteria"

4.0SummarofRecommendations

Thefollowing

isageneralsummaryofthemostsignificant

interimactionsandlongtermcorrective

actions.4.1RG&E'smanagement

hasensuredclosecontrolandqualityengineering

servicesthroughtheirinteraction

andreviewofdesign,butwrittenprocedures

donotmakethatcontrolsufficiently-explicit.

B-5

Asinterimactions,asingleprocedure

willbedeveloped

thatoutlinestheentirescopeofthedesignprocess.Discipline

designguidesforgeneration

ofdesigncriteria,

designanalysesanddesignverification

documents

willbeinitiated.

Also,theintegrated.

assessment

processwillbeseparately

"proceduralized.

Applicable

procedures

willberevisedtoestablish

therequirements

forreview,'a'pproval,

andissuanceofvendordocuments.

In,thelongerterm,weplantocompletetheupgradeofengineering

procedures

andprocesses

toreflectindustrystandards

ofgoodpractice,

efficiency

andrapidresponse.

4.24.34.4Engineering

procedures

containastrongbiastomodification

design.Thishasprovedtobewellsuitedtowardmajorstandalonedesignprojectsbutisnotaseffectively

usedtoaggressively

supportalloftheengineering

activities

associated

withawell-maintained.

operating

plant.Close-out

EWRdocumentation

canbeprotracted,

becausethescopeofamodification

maybein'creased

overtime,causingdesigndocuments

toremainopen.Asinterimactions,weplantolimitthepracticeofincreasing

thescopeofadesignmodification

duringtheintervalbetweenturnoverofthemodification

intheplantandrecordsclose-out.

WewillbegintotransmitEWRDesignPackagestoDocumentControlconcurrent

withtheissuanceoftheconstruction

package.Inthisway,thelistofapplicable

designdocuments

willalsobeestablished

forthemodification

tobeinstalled..

TheUFSARchangeprocesswillbeproceduralized

andintegrated

withtheaboveturnoverprocess.Interimactivities

areneededtobegintocapture,retain,provideaccessto,andorganizedesignbasisinformation

aspartofthenormalongoingengineering

activities.

RG&Ehasincorporated

adesignbasisdocumentation

projectundertheConfiguration

Management

Program.Thisprogramwillbeimplemented

overthenextseveralyearsfocusingonthesafetysystems.Effortswillbemadetoidentifythetypesofmateri'al

anddocuments

thatcontaindesignbasisinformation

andtobegintoindexandorganizeitinDocumentControl.Inthelongerterm,theDesignBasisDocumentation

projectwilldevelopDesignBasisDocuments

forthemajorplantsystemsandequipment.

Becauseofthemajormodification

biasusedinthedevelopment

ofQEprocedures

andthemajorupgradeprogramsthathavetakenplaceovertheyears,theengineering

department

isnotformatted

onasystembasis.B-6

li1i

TheConfiguration

Management

Programisbeingdeveloped

onasystemsbasis.TheQ-Listhasdefinedsystemboundaries

thatwillbeusefulasweindexdesign.documents

inDocumentControlanddevelopDesignBasisDocuments.

4.5Manyoftheunderlying

'concerns

andlongtermcorrective

actionsarecurrently

partoftheexistingorplannedprogramswithinConfiguration'anagement

andEngineering

Procedures

UpgradePrograms.

TheDesignBasisDocumentation,

SetpointVerification,

Q-List,DocumentControlEnhancement,

and.Engineering

Controlled

Configuration

DrawingUpgradeProgramsareindividual

partsofthisprogram.Thespecificactionsrecommended

bytheSSFIAssessment

teamwillbereviewedbytheRG&Epersonnel

responsible

fortheCMprojectstogetherwithmanagement

tomakeanyneededrevisions

tothescopeoftheseprojects.

4.6Engineering

activities

areperformed

byNuclear,Engineering

Services(NES)andstationtechnical

staff.Thedesignprocessmustensureconsistency

betweentheseactivities.

Asinterimactions,weplantoincreasethecontrolsoversetpointchangesandreporting

ofsafetyconcerns.

Aprocesswillbedeveloped

toensurethatproposedsetpointchangesaregiventheappropriate

reviewpriortotheirissuance.

ThePCAQprocess(Potential

Condition

AdversetoQuality)hasbeenimplemented

inQE-1603forNuclearEngineering

Servicespersonnel

toprovideidentification

anddisposition

ofpotential

safetyconcernsandprovideavehicletoimprovetheinterface

withtechnical

personnel

attheplant.Wealsoplantodevelopastreamlined

approvalprocessfortechnical

supportprojectsnotinvolving

modifications.

Inthelongtermwewillexamineestablishing

asingleprocessforallNuclearDivisionpersonnel

toreportspecificconcernswhichmayhavesafetysignificance.

Processes

willbedeveloped

toensurecommonality

ofprocedures

betweenNESandtheTechnical

SectionatGinna.B-7

000

SYSTEMATIC

ASSESSMENT

OFENGINEERING

ASSURANCE

ISSUESANDRHRSSFICONCERNSAPPENDIXA

Cl0

ProrammaticConcernsAreasInvolvinSiificantIdentified

Weaknesses

ResonseScoeListinENGINEERING

MANAGEMENT

Weaknessinmanagerial

andadministrative

controlsManagement

reliesonengineer's

experience

insteadofformalcontrolsEngineering

management

hasnotprovidedclearguidanceandprocedural

controlsoverdesignchangeprocessLackofEngineering

Assurance

Practices

Organizational

Interfaces

w~Controlofdocumentation,

engineering

designinterfaces,

andengineering

communications

withexternalorganizations

ispoor.Lackofcriteriafor.determining

whenengineering

concurrence

isneededDCR'snotprocessed

inatimelymannerDesignoutputnotproperlydistributed

UFSARcontainsinvalidinformation

Noprocessforhandlingsafetyconcernsidentified

outsidetheengineering

processP&IDchangedidnotresultinanUFSARchangeasappropriate

Engineering

Discipline

Interfaces

Eachdiscipline

hasitsowninterpretation

ofengineering

procedure

requirements.

Engineering

Management

hasadifferent

perception

thantheengineering

staffP&IDchangesoccurredwithoutaninterdisciplinary

reviewCONFIGURATION

MANAGEMENT

PlantBaselineConfiguration

Lackofcompleteandconsistent

nomenclature

betweenP&IDsandprocedures,

UFSARandQAManualDeletionofinformation

fromP&IDsDesignBasesr~DesignBasisCalculation

notavailable

ordonotexist~Lackofdocumented

designbasisisagenericweakness~UFSARcontainsinvalidinformation

withoutasupporting

designbasis~Nocalculation

listorformalized

overalllisting

~Operating

procedures,

emergency

procedures,

andoperatortraining.,material

donotreflectthelimitingdesignbasisofthesystemDesignModifications

RG&Edoesnothaveamechanism

foraccounting

forsynergistic

effectsofmodifications

(electrical

calcs,pipestresscalcs)Numerousweaknesses

existinengineering

supportandplantmodification

activities

DocumentControl,~UFSARcontainsinvalidinformation

Lackofcomprehensive

controlled

instrument

listWeaknessinmanagement

controlsystemtoassurecompleteandconsistent

designoutputisissuedanddistributed

PSIDsissuedhaveremovedandrevisedinformation.

Teamconcerned

howRG6Emaintains

traceability

ofthisinformation

Informational

inconsistencies

existbetweendocuments

DCRprocessing

isnottimelyEWRsremaininpersonalcontrolofresponsible

engineerEWRslackindexCompleted

EWRsarenotprocessed

intothedocumentcontrolsysteminatimelymannerUncontrolled

trainingmaterialENGINEERING

PROCEDURES

DesignReviewsReviewprocesslacksdepthReviewandverification

doesnotstrictlyfollowANSIN45.F11Inadequate

ReviewIndependent

Verification

notdoneinaccordance

withengineering

procedures

Calculations-

Genericweaknessinreviewandapprovalofcalculations

Calculational

controlprogram(ANSIN45.2.11)

isweakNolistofcalculations,

nowaytotrackpastcalculations

Setpoints

~Instrument

loopsetpoints

maynotaccountforloopinaccuracies

~Acceptance

criterianotestablished

intestprocedure

forsetpointof

undervoltage

alarmrelaysOtherLackofformalcontrolofengineering

anddesigndocuments

RG&Edesigncontrolmeasuresdonotcomparefavorably

withacceptedindustrypractices

UFSARcontainsinvalidinformation

Lackofinterface

controlwithinternalandexternalorganizations

SRVtestingprocedures

containgeneralandminimalinformation

SAFETYCONCERNSInability

toproperlyidentifysafetyconcerns(batteryloadprofiledeficiencies

notdiscovered)

Inability

toassesssafetyconcerns(poorrootcauseanalysis)

Nomechanism

todisposition

safetyconcernsidentified

outsideofthenormalengineering

process(PIC-629EWRdidnotreflectanyactiontakenonidentified

concernTESTINGDCundervoltage

testinadequate

SRVtestinginadequate

MCCBsnottestedperiodically

SPECIFICDESIGNCONCERNSSWSingleFailureInadequate

RHRNPSHJumpercableexceededminimumallowedbendradiusBatteryrackdonothaveagrounding

cableRHRpumpsealfailure(Eg)RHRpumpsealfailurecausinglossofbothRHRpumps(singlefailure)