ML16267A400

Grand Gulf Nuclear Station, Unit 1 - Clarification of Grand Gulf Nuclear Station Containment Leak Rate Program Description

ML16267A400
Person / Time
Site:	Grand Gulf
Issue date:	09/23/2016
From:	Fallacara V Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2016/00052
Download: ML16267A400 (5)

Text

GNRO-2016/00052 September23,2016U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555-0001 EntergyOperations, Inc.P.O.Box756PortGibson,MS39150 VincentFallacaraVicePresident, OperationsGrandGulfNuclearStationTel.(601)437-7500

SUBJECT:

Clarification ofGrandGulfNuclearStationContainmentLeakRateProgramDescription GrandGulfNuclearStation,Unit1 DocketNo.50-416LicenseNo.NPF-29

REFERENCE:

1.NRCCorrespondence toEntergyGNRI2016/00088, "Question toGGNSRegarding LRAB1.1.15,"

datedSeptember21,2016

DearSirorMadam:

EntergyOperations,Inc.isproviding,in Attachment1,aclarificationtotheLicenseRenewalApplication(LRA)asrequestedinReference1.ThisdocumentisbeingprovidedtosupportreviewoftheGrandGulfNuclearStation(GGNS)LRASafetyEvaluationReport(SER).Thislettercontainsnonewcommitments.Ifyouhaveanyquestionsorrequireadditionalinformation,pleasecontactJamesNadeauat(601) 437-2103.Ideclareunderpenaltyofperjurythattheforegoingistrueandcorrect.Executedonthe23rddayofSeptember,2016.

VF/sas

Attachment:

1.Clarification ofGGNSContainmentLeakRateProgramDescriptioncc:(SeeNextPage)

GNRO-2016/00052Page2of2cc:U.S.NuclearRegulatory CommissionATTN:Mr.JimKim, NRR/DORL(w/2)MailStopOWFN8B1Rockville,MD 20852-2738 U.S.NuclearRegulatory CommissionATTN:Mr.KrissM.

Kennedy(w/2)RegionalAdministrator,RegionIV1600EastLamarBoulevardArlington,TX76011-4511Mr.B.J.Smith(w/2)Director,Divisionof Radiological HealthMississippiState DepartmentofHealthDivisionof Radiological Health3150LawsonStreet Jackson,MS39213NRCSeniorResidentInspectorGrandGulf NuclearStationPortGibson,MS39150 Attachment1toGNRO-2016/00052 ClarificationofGGNSContainmentLeakRateProgramDescription Attachment1toGNRO-2016/00052Page1of2OnFebruary17,2016,theNRCstaffapproved(ADAMSAccessionNo.ML16011A247) aGrandGulf licenseamendment request(ADAMSAccessionNo.ML15147A599) toadoptNEI94-01,Revision3-A, subjecttospecificconditionsandwithpartialimplementation ofANSI/ANS56.8-2002, "Containment SystemLeakageTestingRequirements,"astheimplementing documentforType8and TypeCleakrate testing(LRT).8asedupontheNRC acceptance oftheGrandGulf licenseamendment, changesarewarrantedtotheGrandGulfContainmentLeakRateProgramdescriptions inlicenserenewalapplication (LRA)sectionsA.1.15and8.1.15.Thelicenseamendment doesnotaltertheconclusionthattheContainmentLeakRateProgramelementsareconsistentwiththecorresponding programelementsdescribed inNUREG-1801 SectionXI.S4.However,achangetotheLRAis warranted toclarifythedocuments thatprovidetheguidelines forimplementing theGrandGulfContainmentLeakRateProgram.SeechangestoA.1.15and8.1.15shownbelow.

Additions areshownwithunderline anddeletions withstrikethrough.

A.1.15Containment LeakRateProgramTheContainment LeakRateProgramprovidesfordetectionoflossofmaterial,

cracking, andlossoffunctioninvarioussystemspenetrating containment.

Theprogramalsoprovidesfordetection ofage-related degradation inmaterialproperties ofgaskets,a-rings,andpackingmaterialsfortheprimarycontainment pressureboundaryaccesspoints.Containment leakageratetests(LRT)areperformed toassurethatleakagethroughthecontainment andsystemsandcomponents penetrating primarycontainment doesnotexceedallowable leakagelimitsspecifiedintheplanttechnical specifications.

TypesA,8andCleakageratetestingwillbeimplemented inaccordancewiththecriteriasetforthinRG1.163,NEI94-01,Revision3-A,and ANSI/ANS-56.8-2002,whichareguidelines foracceptable leakratetesting programs.

AnintegratedleakratetestA)isperformed duringaperiodof reactorshutdown.atthefrequency specified in10erRPart50,AppendixJ,OptionB,baseduponthecriteriainRegulatory Guide1.163,NEI9401,andANSI56.81994.Performance oftheintegratedleakratetestper10CFRPart50, AppendixJdemonstrates theleak-tightness andstructural integrityofthecontainment.Localleakratetests (hbR+Type8andC)are performed onisolation valvesandcontainment accesspenetrations.,

-atTestfrequencies tHatforTypesA,8andCleakageratetestingcomplywiththerequirementsof10CFRPart50, AppendixJ,Option8,baseduponthe criteriainNEI94-01,Revision3-A.

Attachment1toGNRO-2016/00052Page2of28.1.15Containment LeakRateProgramDescription TheContainment LeakRateProgramisanexistingprogramthatprovidesfordetectionoflossofmaterial, cracking,andlossof functioninvarioussystemspenetrating containment.

Theprogramalsoprovidesfordetection ofage-related degradation inmaterialproperties ofgaskets,o-rings,andpackingmaterialsfortheprimarycontainment pressureboundaryaccesspoints.Containment leakageratetests(LRT)areperformed toassurethatleakagethroughthecontainment andsystemsandcomponents penetrating primarycontainment doesnotexceedallowable leakagelimitsspecifiedintheplanttechnical specifications.

TypesA,BandCleakageratetestingwillbeimplemented inaccordancewiththecriteriasetforthinRG1.163,NEI94-01, Revision3-A,andANSI/ANS-56.8-2002, whichareguidelines foracceptable leakratetestingprograms.

Anintegratedleakratetest(.f.bR+TypeA)isperformed duringaperiodofreactorshutdown.atthefrequency specifiedin10CFRPart50,AppendixJ,OptionB,baseduponthecriteriainRegulatory Guide1.16d,NEIQ401,andANSI56.81QQ4.Performance oftheintegratedleakratetestper10CFRPart50, AppendixJdemonstrates theleak-tightness andstructural integrityofthecontainment.Localleakrate tests(hbR+TypeBandC)are performed onisolation valvesandcontainment accesspenetrations.

atTestfrequencies thatforTypesA,BandCleakageratetestingcomplywiththerequirementsof10CFRPart50, AppendixJ,OptionB,baseduponthecriteriainNEI94-01,Revision3-A../