ML16267A400: Difference between revisions

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{{Adams
#REDIRECT [[GNRO-2016/00052, Grand Gulf Nuclear Station, Unit 1 - Clarification of Grand Gulf Nuclear Station Containment Leak Rate Program Description]]
| number = ML16267A400
| issue date = 09/23/2016
| title = Grand Gulf Nuclear Station, Unit 1 - Clarification of Grand Gulf Nuclear Station Containment Leak Rate Program Description
| author name = Fallacara V
| author affiliation = Entergy Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000416
| license number = NPF-029
| contact person =
| case reference number = GNRO-2016/00052
| document type = Letter
| page count = 5
}}
 
=Text=
{{#Wiki_filter:GNRO-2016/00052 September23,2016 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150 Vincent FallacaraVicePresident, OperationsGrandGulfNuclearStationTel.(601)437-7500
 
==SUBJECT:==
Clarification of Grand Gulf Nuclear Station ContainmentLeakRate Program Description Grand Gulf NuclearStation,Unit1 Docket No.50-416 License No.NPF-29
 
==REFERENCE:==
1.NRC Correspondence to Entergy GNRI 2016/00088,"Question to GGNS Regarding LRA B1.1.15," dated September21,2016
 
==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 of GGNS ContainmentLeakRate Program Descriptioncc:(SeeNextPage)
GNRO-2016/00052Page2of2cc:U.S.Nuclear Regulatory CommissionATTN:Mr.JimKim, NRR/DORL (w/2)MailStopOWFN8B1Rockville,MD 20852-2738 U.S.Nuclear Regulatory CommissionATTN:Mr.KrissM.
Kennedy (w/2)Regional Administrator,RegionIV1600EastLamarBoulevardArlington,TX76011-4511Mr.B.J.Smith(w/2)Director,Divisionof Radiological HealthMississippiState DepartmentofHealthDivisionof Radiological Health3150LawsonStreet Jackson,MS39213 NRC Senior Resident InspectorGrandGulf Nuclear StationPortGibson,MS39150 Attachment1to GNRO-2016/00052 ClarificationofGGNS ContainmentLeakRateProgramDescription Attachment1to GNRO-2016/00052Page1of2 On February 17,2016,theNRC staff approved (ADAMS AccessionNo.ML 16011A247) aGrandGulf license amendment request (ADAMS AccessionNo.ML 15147A599) to adopt NEI94-01,Revision3-A, subject to specific conditionsandwith partial implementation of ANSI/ANS 56.8-2002,"Containment System Leakage Testing Requirements,"asthe implementing documentforType8and TypeCleakrate testing (LRT).8asedupontheNRC acceptance oftheGrandGulf license amendment, changes are warrantedtothe Grand Gulf ContainmentLeakRate Program descriptions in license renewal application (LRA)sections A.1.15 and 8.1.15.The license amendment does not alter the conclusionthatthe ContainmentLeakRate Program elements are consistentwiththe corresponding program elements described in NUREG-1801 Section XI.S4.However, a changetotheLRAis warranted to clarify the documents that provide the guidelines for implementing the Grand Gulf ContainmentLeakRate Program.See changes to A.1.15 and 8.1.15shownbelow.
Additions are shown with underline and deletions with strikethrough.
A.1.15 Containment Leak Rate Program The Containment Leak Rate Program provides for detectionoflossof material, cracking, andlossof function in various systems penetrating containment.
The program also provides for detection of age-related degradation in material properties of gaskets, a-rings, and packing materialsforthe primary containment pressure boundary access points.Containment leakage rate tests(LRT)are performed to assure that leakage through the containment and systems and components penetrating primary containment does not exceed allowable leakage limits specifiedinthe plant technical specifications.
TypesA,8andC leakage rate testingwillbe implemented in accordancewiththe criteriasetforthinRG1.163,NEI94-01,Revision3-A,and ANSI/ANS-56.8-2002,whichare guidelines for acceptable leakratetesting programs.An integratedleakratetestA)is performed duringaperiodof reactor shutdown.atthe frequency specified in 10 erR Part 50, Appendix J, Option B, baseduponthe criteria in Regulatory Guide 1.163, NEI 94 01, and ANSI 56.8 1994.Performance of the integratedleakratetestper10CFRPart50, Appendix J demonstrates the leak-tightness and structural integrityofthe containment.Localleakratetests (hbR+Type8andC)are performed on isolation valves and containment access penetrations.,-at Test frequencies tHat for TypesA,8andC leakage rate testing complywiththe requirementsof10CFRPart50, Appendix J, Option8,baseduponthe criteriainNEI94-01,Revision3-A.
Attachment1to GNRO-2016/00052Page2of2 8.1.15 Containment Leak Rate Program Description The Containment Leak Rate Programisan existing program that provides for detectionofloss of material, cracking,andlossof function in various systems penetrating containment.
The program also provides for detection of age-related degradation in material properties of gaskets, o-rings, and packing materialsforthe primary containment pressure boundary access points.Containment leakage rate tests(LRT)are performed to assure that leakage through the containment and systems and components penetrating primary containment does not exceed allowable leakage limits specifiedinthe plant technical specifications.
Types A, Band C leakage rate testingwillbe implemented in accordancewiththe criteriasetforthinRG1.163,NEI94-01, Revision3-A,and ANSI/ANS-56.8-2002, which are guidelines for acceptable leak rate testing programs.An integratedleakrate test (.f.bR+TypeA)is performed during a period of reactor shutdown.atthe frequency specifiedin10 CFRPart50, Appendix J, Option B, baseduponthe criteria in Regulatory Guide 1.16d, NEI Q401,and ANSI56.81 QQ4.Performance of the integratedleakratetestper10CFRPart50, Appendix J demonstrates the leak-tightness and structural integrityofthe containment.Localleakrate tests (hbR+TypeBandC)are performed on isolation valves and containment access penetrations.
at Test frequencies that for Types A, Band C leakage rate testing complywiththe requirementsof10CFRPart50, Appendix J, Option B, baseduponthe criteriainNEI 94-01, Revision 3-A../}}

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