ML15259A042

Grand Gulf, Unit 1 - Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing

ML15259A042
Person / Time
Site:	Grand Gulf
Issue date:	09/15/2015
From:	Kevin Mulligan Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2015/00037
Download: ML15259A042 (49)

Text

{{#Wiki_filter:GNRO-2015/00037 September 15,2015 U.S.Nuclear Regulatory Commission Attn: DocumentControlDesk Washington,DC20555-0001EntergyOperations,inc.P.O.Box756 Port Gibson,MS39150KevinMulliganSiteVice PresidentTel.(601)437-7500

DearSirorMadam:

ApplicationtoRevisetheGrand Gulf NuclearStationUnit1 Technical Specifications to Remove the Inservice TestingProgramandtoClarifySR Usage Rule ApplicationtoSection5.5 Testing Grand Gulf NuclearStation,Unit1DocketNo.50-416LicenseNo. NPF-29 In accordancewiththe provisionsof10CFR50.90,the Entergy Operations Inc.(Entergy)issubmittinga requestforan amendmenttotheGrand Gulf NuclearStationUnit1 Technical Specifications (TS).Theproposed changerevisesthe Grand Gulf NuclearStationUnit1 Technical Specifications(TS)to eliminateSection5.5,"Inservice Test Program,"whichis supersededbyOMN-20.A new defined term,"Inservice TestingProgram,"is addedtotheTS.This request is consistent with TSTF-545, Revision1,"TS Inservice Testing ProgramRemoval&ClarifySRUsageRule ApplicationtoSection5.5 Testing," which under Nuclear Regulatory Commission (NRC)approvalreviewatthistime.The proposed change also proposes an alternativetothetestingperiodsinthe American Society of Mechanical Engineers (ASME)Operation and Maintenance(OM)Code,byadoptionofCodeCaseOMN-20,"Inservice Test Frequency." Attachment1providesa description and assessmentofthe proposedTSchanges. Attachment2providestherequestforan alternativetotheASMECode. Attachment 3 providestheexistingTSpagesmarkedupto show the proposed changes.Attachment 4 providesrevised(clean)TS pages.Approvaloftheproposed amendmentisrequested.Once approved, the amendmentshallbe implementedwithin90days. In accordancewith10CFR50.91,acopyofthis application, with attachments,isbeingprovidedtothe designated Mississippi Official./ GNRO-2015/00037Page2of3 This letter containsnonew commitments.Ifyouhaveany questions or require additional information, please contact James Nadeau at 601-437-2103. I declare under penalty of perjury that the foregoing is true and correct.Executedonthe is"dayof September, 2015.Sincerely,.----1-.....------KJM/ram Attachment(s): 1.2.3.4.Description and Assessment of Technical Specifications Changes Description and Assessment of Proposed Alternativetothe ASME Code Proposed Technical Specification Changes (Marked-Up) Revised Technical Specification Pages (Clean)cc:with Attachment(s)Mr.JohnP.Boska, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555 GNRO-2015/00037Page3of3 cc: without Attachment(s)Mr.MarkDapas Regional Administrator,RegionIV U.S.Nuclear Regulatory Commission1600East Lamar BoulevardArlington,TX76011-4511 U.S.Nuclear Regulatory CommissionATTN:Mr.M.Orenak, NRR/DORLMailStop OWFN/8 G1411555RockvillePikeRockville,MD 20852-2378NRCSenior Resident InspectorGrandGulf Nuclear StationPortGibson,MS39150Dr.MaryCurrier,M.D.,M.P.HStateHealth Officer Mississippi DepartmentofHealthP.O.Box1700 Jackson, MS 39215-1700 Email: marv.currier@msdh.ms.gov Attachment 1 to GNRO-2015/00037 Description and Assessment of Technical Specifications Changes GNRO-2015/00037 Attachment 1 DESCRIPTION AND ASSESSMENT OF TECHNICAL SPECIFICATIONS CHANGES DESCRIPTION AND ASSESSMENT OF TECHNICAL SPECIFICATIONS CHANGES

1.0 DESCRIPTION

The proposed change eliminates the Technical Specifications (TS), Section 5.5,"Inservice Test (1ST)Program," to removerequirements duplicated in American Society of Mechanical Engineers(ASME)Codefor Operations and Maintenance of Nuclear Power Plants(OMCode), Case OMN-20,"Inservice Test Frequency."Anew defined term,"Inservice Testing Program," isaddedtoTS Section 1.1,"Definitions." The Surveillance Requirement (SR)Section3.0,"SR Applicability, II Bases are revised to explain the applicationofthe usagerulesto the Section 5.5 testing requirements. The proposed changetotheTSis consistent with TSTF545,Revision1,"TS Inservice Testing Program Removal&Clarify SR Usage Rule Application to Section 5.5 Testing,"whichis under NRC approval reviewatthistime. 2.0

SUMMARY

DESCRIPTION On August 23,2012,theNRC issued Regulatory Issue Summary (RIS)2012-10,"NRCStaff Position on Applying Surveillance Requirement3.0.2and 3.0.3 to Administrative Controls Program Tests:'TheRIS statedthattheNRC staff had determined that restructuring Technical Specifications (TS)chapters during the developmentofthe Improved Standard Technical Specifications (ISTS)resulted in unintended consequences when Section3.0,"Surv eillance Requirement Applicability," provisions were made applicable to Section5.0TS.TheNRCstaff concluded that Surveillance Requirement (SR)3.0.2andSR 3.0.3 cannot be appliedtoTS5.5forteststhatarenot associatedwithaTSSR. In order to providetimefor licensees to addresstheNRC position,theNRC issued Enforcement Guidance Memorandum (EGM)2012-001,"Dispositioning Noncompliance with Administrative ControlsTechnicalSpecifications Programmatic Requirements that Extend Test FrequenciesandAllow Performance of Missed Tests," on February 24,2012.TheEGM statestheNRCstaff positionthatSR 3.0.2andSR 3.0.3 cannot be applied to Inservice Tests.The Inservice Testing (1ST)Program requirements, including the associated testing intervals, are providedinthe American Society of Mechanical Engineers (ASME)Codefor Operations and Maintenance of Nuclear Power Plants (OM Code), which licensees are required to followby10CFR 50.55a(f),"Inservice testing requirements:' The staff evaluation of inservice testing requirements under 10 CFR 50.55a determinedthat,ifa licensee findsthatthe requirementsoftheTS conflictwiththe requirementsof10CFR 50.55a,thenthe licensee must amend theirTSto complywith10CFR50.55a.Also,withregardtothe ASME OM Codeand10CFR 50.55a,theOMCode,atthetime,didnotmake available test allowances similar to eitherSR3.0.2orSR3.0.3 underTitle10oftheCodeof Federal Regulations(10CFR),Part50, paragraph 50.55a(f). Therefore, these allowances couldnotbe applied to Inservice Tests.TheEGM provided enforcement discretion to licensees to apply SR 3.0.2 to Inservice Tests and guidance on addressing missed Inservice Tests, pending revisiontothe ASMEOMCodeandtheTS. GNRO-2015/00037 Attachment 1 The proposed change requests a revisiontotheTSto eliminate the Chapter 5.0,"Administrative Controls," specification,"Inservice Testing Program." The ASME has made available a Code Case, OMN-20,"Inservice Test Frequency," which provides similar definitions and allowancesasinthe current TS inservice testing program.Anew defined term,"Inservice Testing Program," is addedtoTS Section 1.1,"Definitions." Existingusesoftheterm"Inservice Testing Program"intheTSandTS Bases are capitalized to indicateitisnowa defined term.TheSR3.0.2andSR 3.0.3 Bases are revised to clarify the application of these usagerulesto testing requiredbyTS Section 5.5,"Programs and Manuals, II specifications.TheSR3.0.2 Basesarealso revised to clarify the applicationofSR3.0.2to inservice tests.This application is modelled after TSTF-545, Revision2,"TS Inservice Testing Program Removal&Clarify SR Usage Rule Application to Section 5.5 Testing," which is under NRC evaluationatthistimeanditis anticipated thatitwillbe availableforuseasaModel Safety Evaluation and Model Applicationonor after September 10, 2015.The conservative position outlinedinthe TSTF that changestotheSR3.0 Baseshavebeen adoptedinthis license amendment application.

Background

Title10ofthe Code of Federal Regulations,Part50, Section 50.55a, paragraph (b),"Standards approved for incorporation by reference," references the approved standards requiredtobe followed for systems and components of nuclear power reactors.10CFR 50.55a, paragraph (b)(3), references the ASME OM Code.10CFR 50.55a, paragraph (b)(6),"0perationand Maintenance of Nuclear Power Plants Code Cases, II allows licensees to apply the ASME Code Caseslistedin Regulatory Guide 1.192,"0perationand Maintenance Code Case Acceptability, ASME OM Code," without prior NRC approval subjecttothe conditions listedin10CFR 50.55a(b)(6), paragraphs (i)through(iii).10CFR 50.55a, paragraph (a)(3)(i)allows licensees to requesttheuseof ASME Code Cases thatarenot referencedinthe current version of Regulatory Guide 1.192.TheOM Code was developedandis maintainedbythe ASME OM Committee. The ASME publishesanew editionoftheOM Code every three yearsandanew addendum every year.The latest editions and addendaoftheOM Code thathavebeen approvedforusebytheNRC are referencedin10CFR 50.55a(b). The ASME also publishes OM Code Cases yearly.Code Cases provide alternatives developed and approved by ASME or explain the intent of existing Code requirements.TheTS1ST Program in Section 5.5,"Programs and Manuals," provides a table defining some ofthe1ST frequencies and describes the relationship betweentheTSandthe Inservice Testing requirements. The program states: Technical Specification 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1,2,and3 components. The program shall include the following: a.Testing frequencies specified in SectionXIofthe ASME Boiler and Pressure Vessel Code and applicable Addenda as follows: GNRO-2015/00037 Attachment 1ASMEBoilerand PressureVesselCodeandapplicableAddenda terminology for inservice testing activities Weekly MonthlyQuarterlyorevery3months Semiannually orevery6monthsEvery9monthYearlyor annuallyBienniallyorevery2years Required Frequencies for performing inservice testing activitiesAtleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper276daysAtleastonceper366daysAtleastonceper731daysb.TheprovisionsofSR3.0.2are applicabletotheaboverequired frequencies for performinginservicetestingactivities;c.TheprovisionsofSR3.0.3are applicabletoinservicetestingactivities;andd.NothingintheASMEBoilerandPressureVesselCodeshallbeconstruedto supersede the requirementsofanyTS.SR3.0.2statesthatanSRis consideredmetwithinitsspecifiedFrequencyiftheSurveillanceisperformedwithin1.25timestheintervalspecified.SR3.0.3statesthatifaSurveillancewasnotperformedwithinitsspecifiedFrequency,then compliancewiththe requirementtodeclaretheLCOnotmetmaybedelayed,fromthetimeofdiscovery,upto24hoursoruptothelimitofthespecifiedFrequency, whicheverisgreater.InJanuary2013,theASME announced the availabilityofCodeCaseOMN-20,"InserviceTestFrequency."TheCodeCasestates: Inquiry: What alternative(s)maybeappliedtothetest frequenciesforpumpsandvalvesspecifiedinASMEOMDivision:1Section 1ST2009EditionthroughOMa-2011Addendaandallearliereditionsand addendaofASMEOMCode? Reply.Itistheopinionofthe[ASMEOM] Committeethatforthetest frequencies forpumpsandvalvesspecifiedinASMEOMDivision:1Section 1ST2009EditionthroughOMa-2011AddendaandallearliereditionsandaddendaofASMEOMCode,thebelow requirementsmaybeapplied.ASMEOMDivision:1Section 1STandearliereditionsand addendaofASMEOMCode specify component test frequenciesbasedeitheronelapsedtimeperiods(e.g.,quarterly,2years,etc.)orbasedonthe occurrenceofplant conditionsorevents(e.g.,coldshutdown,refuelingoutage,upondetectionofasamplefailure,following maintenance, etc.). GNRO-2015/00037 Attachment 1 a)Componentswhosetest frequenciesarebasedonelapsedtimeperiodsshallbetestedatthe frequencies specifiedinSection 1STwithaspecifiedtimeperiodbetweentestsasshowninthetablebelow.Thespecifiedtimeperiodbetweentestsmaybereducedorextendedasfollows:1)Forperiodsspecifiedaslessthan2years,theperiodmaybeextendedbyupto 25%foranygiventest.2)Forperiodsspecifiedas greaterthanorequalto2years,theperiodmaybeextendedbyupto6monthsforanygiventest.3)Allperiodsspecifiedmaybereducedatthediscretionoftheowner(Le.,thereisnominimumperiod requirement).Periodextensionistofacilitatetest scheduling and considersplantoperating conditions thatmaynotbesuitablefor performanceoftherequiredtesting(e.g., performanceofthetestwouldcausean unacceptableincreaseintheplantriskprofiledueto transientconditionsorotherongoingsurveillance,testor maintenanceactivities).Period extensionsarenotintendedtobeusedrepeatedlymerelyasan operational conveniencetoextendtestintervalsbeyondthose specified. Period extensionsmayalsobeappliedto accelerated test frequencies(e.g.,pumpsinAlertRange)andotherlessthantwoyeartest frequenciesnotspecifiedinthetablebelow. Period extensionsmaynotbeappliedtothetest frequency requirementsspecifiedinSubsectionISTD, Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-water Reactor Nuclear Power Plants,asSubsectionISTDcontainsitsownrulesforperiodextensions. Frequencv SpecifiedTimePeriod Between Tests Quarterly (or92daysevery3months) Semiannually (or184daysevery6months)Annually(or366dayseveryyear)xYears x calendaryearswhere'x'isawhole numberofyears2 b)Componentswhosetest frequenciesarebasedonthe occurrenceofplant conditionsoreventsmaynothavetheirperiodbetweentestsextendedexceptasallowedbyASMEOMDivision:1Section 1ST2009EditionthroughOMa-2011Addendaandearliereditionsand addendaofASMEOMCode. GNRO-2015/00037 Attachment 1TheCode Case differsfromthe current TS requirementsinthe following aspects: The Code Case does not define the periods IIWeekly,1I"Monthly,"orIIEvery9 months." The Code Case allows tests requiredtobe performed at periods greaterthan2 years to be extendedupto6 months.The ISTS does not allow test periods greaterthan2 yearstobe extended.The Code Case does not address failure to perform an Inservice Test within its required period.The Code Case does not include the statementintheTSthatthe ASME OM Code may not supersede the requirementsofanyTS.The proposed change eliminatestheTS Inservice Testing Program.TheTS contain Surveillances that require testing or test intervals in accordancewiththe Inservice Testing Program.The eliminationoftheTS Inservice Testing Program from Section5.5oftheTScould result in uncertainty regarding the correct application of these Surveillance Requirements. Therefore,anew defined term,"Inservice Testing Proqrarn," is added to Section 1.1,"Definitions,"inthe Technical Specifications..Itis definedas,"The INSERVICE TESTING PROGRAMisthe licensee program that fUlfii'ls the requirementsof10CFR 50.55a(f).11 FollowingtheNotein Section1.1oftheTS,the existing usesoftheterm"lnservice Testing Proqrarn" are capitalized throughouttheTSandTS Bases to indicateitisa definedterm.TheSR3.0.2 Bases are revised to expand the existing discussion of frequencies specified in regulations to include inservice tests.Atthe November 21, 2013 TSTF/NRC public meeting, the TSTFandNRC agreed that revisingtheTS Section 5.5 specificationstono longer refertoSR 3.0.2orSR 3.0.3isnot sufficiently beneficial to warrant the expenditure of industryandNRC resources, and shouldnotbe pursued.This decision was based on agreement that: The presentationhasbeenusedfor20 yearswithno significant misinterpretation (with the exceptionofthe1ST program requirements, which are addressedinthis Traveler);TheNRCand industry agree that the allowances are appropriate; and Any change would simply restate the existing allowancesina different way.TheNRCis currently pursing publication of OMN-20inthe regulationssothatitmaybeused without plant-specific approval.ShouldtheNRC approve this Traveleranda licensee desire to adopt the Traveler priortoNRC incorporation of OMN-20intothe regulations, the model application in Enclosure 1 contains an optional requestfora plant-specific alternativetothe ASME O&M Code to utilize OMN-20.Proposed Change The proposed change eliminates the Inservice Testing ProgramfromTS Section 5.5.Subsequent programs are renumbered to reflect eliminationofthe program and references to the renumbered programs are revisedintheTSandTSBases.Itis anticipated that plant-GNRO-2015/00037 Attachment 1 specific requests to adopt this Traveler will marktheSection5.5 program deletedandwillnot renumber the subsequent programs.Anew defined term,"Inservice Testing Program," is addedtoTSSection1.1,"Definitions." Itstates,"The INSERVICE TESTING PROGRAMisthe licensee programthatfulfillsthe requirementsof10CFR 50.55a(f)."Theexistingusesoftheterm"Inservice Testing Program" are capitalized throughouttheTSandTSBasesto indicateitisa definedterm.Thephrase"InserviceTesting Program" may appear in differentTSandTSBases locations in plant-specificTS.Revisingthisphrasetobe capitalized, whereveritmay appearina plant'sTSandTSBases,iswithinthe scopeofthis proposed change.TheSR3.0.2Bases discussion of frequencies specifiedinthe regulation is expanded to discuss inservice tests.Wordsinitalicsareadded. Wordsthatare struck-through are deleted.The 25%extensiondoesnot significantly degrade the reliabilitythatresultsfrom performing the Surveillanceatits specified Frequency.Thisisbasedonthe recognitionthatthe most probableresultofany particular Surveillance being performedisthe verification of conformancewiththeSRs.The exceptionstoSR3.0.2arethose Surveillancesforwhichthe 250/0 extensionoftheinterval specifiedinthe Frequencydoesnotapply. These exceptionsarestatedinthe individual Specifications. The requirements of regulations take precedenceovertheTS. An oxamploExamples ofwhereSA3.0.2doesnot apply areisinthe[Primary]Containment Leakage Aate Testing Program requiredby10 CFR 50, Appendix J, and the American Society of Mechanical Engineers(ASME)Code inservice testing required by 10 CFR50.55a.These+I=Hs programs establishes testing requirements.and Frequencies in accordancewiththe requirements of regulations.TheTScannot,inandof themselves,extendatest interval specifiedinthe regulations directly or by reference.TheSA3.0Basesare modified to discuss the applicationofSA3.0.2andSA3.0.3toSection5.5testing requirements. SR3.0.1 throughSR3.0.4 establish the general requirements applicabletoall Specificationsandapplyatalltimes, unless otherwise stated.SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when invoked by a Chapter 5 Specification.TheSA3.0.2Basesare modified to discuss the applicationofSA3.0.2to Section5.5testing requirements. When a Section 5.5,"Programs and Manuals," specification statesthatthe provisions of SR 3.0.2 are applicable, a 25%extension of the testing interval, whether statedinthe specification or incorporated byreference,is permitted.TheSA3.0.3Basesare modified to discuss the applicationofSA3.0.3to Section5.5testing requirements. When a Section 5.5,"Programs and Manuals," specification statesthatthe provisions of SR 3.O.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordancewithSR 3.0.3whenthe testing has not been completedwithinthe GNRO-2015/00037 Attachment 1 testing interval (including the allowance of SR 3.0.2 if invoked bytheSection5.5 specifica tion).

3.0 TECHNICAL EVALUATION

3.1 Technical Evaluationofthe Proposed Changetothe Technical Specifications The proposed change eliminates TS Section 5.5,"Proqrarns and Manuals,""lnservice Testing Proqrarn." This removes TS requirements relatedto1ST frequencies, the applicationofSR3.0.2andSR3.0.3,andthe relationship betweentheTSandthe ASME Code.The existing referencestothe1ST Program are revised to referenceanewTS Section 1.1 defined term,"lnservice Testing Proqrarn," which states: "The INSERVICE TESTING PROGRAMisthe licensee program that fulfills the requirementsof10CFR 50.55a(f).11 Plant operation under the proposed alternative in OMN-20andthe proposedTSwill differ from the current TS requirementsinthe following aspects: The Code Case does not define the periods IIWeekly,1I IIMonthly,1IorIIEvery9 months.1I Unlike the existingTS1ST Program;the OMN-20 Code Case does not define the periods"weekly,""monthly,"orlIevery9 months.IIAsthe ASME OM Committee specifies the pump and valve testing frequenciesintheOM Code, we defer to that Committee regardingtheneedto define these testing periodsinthe Code CaseorintheTS. The Code Case allows tests requiredtobe performed at periods greaterthan2 yearstobe extendedupto6 months.TheISTS does not allow test periods greaterthan2 yearstobe extended.The ASME OM Committee determined that allowing a 6-month extension to testing periods greaterthan2 years is appropriate. The 6-month extensionwillhave minimal impact on component reliability consideringthatthe most probable result of performing any inservice test is satisfactory verificationofthetest acceptance criteria.Assuch, pumps and valves will continuetobe adequately assessed for operational readiness when tested in accordance with the requirements specifiedin10 CFR 50.55a(f)withthe frequency extensions allowed by Code Case OMN-20.The Code Case does not address failure to perform an lnservice Test within its required period.The current TS allow SR 3.0.3tobeusedwhenan Inservice Testisnot performedwithinits required testing period.SR 3.0.3 statesthatifa Surveillancewasnot performedwithinits specified Frequency, then compliancewiththe requirement to declaretheLCOnotmet may be delayed,fromthetimeof discovery,upto24 hoursoruptothelimitofthe specified Frequency, whichever is greater.RIS 2012-10 stated licensees cannotuseTS 5.5.6 to apply SR 3.0.3toan inservice test under10CFR 50.55a(f)thatisnot associatedwithaTS surveillance.InEGM 2012-001,theNRC stated that failure to either perform or meet an inservicetestfor tests required onlyby10CFR50.55a(f)resultsina nonconformancewiththeOM Code requirements and should be resolved as discussedinRIS 2005-20, Revision1.RIS 2005-20, Revision 1, announced the availability of NRC Inspection ManualPart9900, Technical Guidance,"Operabillty Determinations &Functionality Assessments for Resolution of Degraded GNRO-2015/00037 Attachment 1 and Nonconforming Conditions Adverse to QualityorSafety"(hereinreferredtoasthe "00Process").Inotherwords,ifitis discoveredthatan inservicetestwasnot performedwithinthe specifiedperiod,theeffecton equipment Operabilitymustbe assessed.The guidanceinEGM2012-001is consistentwithSection6.2ofthe 00Process,whichstates,"Insomecasesalicenseemay discover a noncompliancewitharegulation.The noncompliancewiththeregulationshouldbe treatedasa degraded or nonconforming condition,andthe operability or functionality of affected SSCs assessed.IITherefore,following adoptionofthe proposedCodeCaseandthe proposed changetotheTS,failuretoperforman inservice testwithintheperiod specifiedintheOMCodeas modifiedbyCodeCase OMN-20willbe treatedasa degraded or nonconforming conditionandthe effectonthe Operabilityofthe affected componentswillbe assessed.Shoulditbe determinedthatthe affected components are inoperable, the appropriate TS Actionswillbetaken. The proposedchangeto deletetheSR3.0.3 allowance is consideredmorerestrictivesincetheOMCode, applicable addenda, and RegulatoryGuide1.192 incorporated by referencein10CFR50.55a(b)donotprovidean equivalent allowance to generically delay performanceofaninservicetestdueto discoveryofamissedtest. AlthoughSR3.0.3will continuetoapplytoTSLCOsand associated surveillance requirements that reference the 1STProgram,theSR3.0.3 allowancewillnotapplytonon-TS inservice testing requirements.TheCodeCasedoesnotincludethe statementintheTSthattheASMEOMCodemaynot supersede the requirementsofanyTS.The current TS 1ST Program, Paragraphd,states,"NothingintheASMEOMCodeshallbe construed to supersede the requirementsofanyTS."This statementhasbeenintheISTSsinceRevision0wasissuedin1992,andinthe pre-ISTS equivalent requirement(4.0.5)since1978,orearlier.EGM2012-001stated,lithestaff evaluation of inservice testing requirementsunder10CFR determinedthat,ifa licenseefindsthatthe requirementsofTS conflictwiththe requirementsof10CFR50.55a,thenthe licenseemustamendtheirTSto complywith10CFR50.55a."AstheNRCpositionisthatthe statement in Paragraphdisincorrect,itisremovedin the proposed change.SR3.0.2willno longerapplyto frequencies specifiedinthe Inservice Testing ProgramInservicetesting frequencies are specifiedintheASMEOMCode,as modifiedbyOMN-20,and10CFR50.55a(f)requires licensees to implementtheASMEOMCode.The Technical Specifications cannot supersede regulations and, therefore,SR3.0.2maynotbeusedtoextendthetesting frequencies specifiedintheASMEOMCode.TheexistingSR3.0.2Bases discussionregardingthe inabilityofSR3.0.2toalter frequencies specified in regulations isexpandedto discuss inservice testing.OMN-20addsthistest scheduling flexibilitytotheASMEOMCode,soitisnotneededintheTS.Plantoperationunderthe proposed alternative(OMN-20)andthe proposed changestotheTSwillhaveno significanteffecton component reliability. GNRO-2015/00037 Attachment 1 3.2 TechnicalEvaluationofthe ProposedChangetothe Technical Specifications BasesTheSR3.0 Applicability specificationsapplyto Chapter3oftheTSandapplytotesting requirements in Chapter 5,"Administrative Controls, IISection5.5,"ProgramsandManuals,"onlywhen explicitlystatedintheSection5.5 Specification. The introductory paragraphoftheBasestoSR3.0,"SR Applicability, IIstates,"SR3.0.1throughSR3.0.4establishthegeneral requirements applicabletoall Specificationsandapplyatalltimes,unless otherwise stated.IIToclarifythattheSR3.0usagerulesare applicable wheninvokedbyaSection5.5testing requirement,theSR3.0 introductory paragraphisbeingrevisedtostate,"SR3.0.1 throughSR3.0.4 establishthegeneral requirements applicabletoall Specificationsandapplyatalltimes,unless otherwise stated.SR 3.0.2 andSR3.0.3 apply in Chapter 5 only when invoked by a Chapter 5 Specification. IITheSR3.0.2Basesarerevisedtoaddthe followingafterthethird paragraph(Le.,asa separate paragraphbeforeliAsstatedinSR3.0.2,..."): When a Section 5.5,"Programs and Manuals," specification statesthatthe provisions of SR 3.0.2 are applicable, a 25%extension ofthetestinginterval, whether statedinthe specification or incorporated byreference,is permitted.SomeSection5.5 programs reference documents,suchas RegulatoryGuides,whichcontaintestingintervals.Hence,the discussionoftesting intervals incorporatedbyreferencewas included.TheSR3.0.3Basesarerevisedtoaddthe followingafterthefirst paragraph: When a Section 5.5,"Programs and Manuals," specification statesthatthe provisions of SR 3.O.3 are applicable, it permits the flexibility to defer declaringthetesting requirement not met in accordancewithSR 3.O.3whenthetestinghas not been completedwithinthe testing interval (including the allowance of SR 3.0.2 if invokedbytheSection5.5 specification). The changestotheSR3.0.Basesare consistentwiththe historical applicationofSR3.0usagerulestoSection5.5testing requirementsandservetoexplaintheir applicationinareadily accessible location.Inorderto facilitate operator understandingoftherevisedTS requirementsrelatedtothe 1STProgram,theexistingSR3.0.2 discussion of Frequencies specifiedinthe regulations isexpandedto addressITSprogramtestingintervals: The 25%extensiondoesnot significantly degradethereliabilitythatresultsfrom performing the Surveillanceatits specifiedFrequency.Thisisbasedontherecognitionthatthemost probableresultofany particular Surveillance being performedisthe verification of conformancewiththeSRs.The exceptionstoSR3.0.2arethose Surveillancesforwhichthe 25%extensionoftheinterval specifiedinthe Frequencydoesnotapply.These exceptionsarestatedinthe individual Specifications. The requirements of regulations take precedenceovertheTS.An example Examples ofwhereSR3.0.2doesnotapply are fs-.iRthe[Primary] ContainmentLeakageRate GNRO-2015/00037 Attachment 1TestingProgram requiredby10CFR50, Appendix J, and the American Society of Mechanical Engineers(ASME)Code inservice testing required by10CFR50.55a. These+J::Hs programs establishes testing requirements and Frequencies in accordancewiththe requirementsofregulations.TheTScannot,inandof themselves,extendatestintervalspecifiedinthe regulations directlyorbyreference.

4.0 REGULATORY

ANALYSIS4.1Applicable Regulatory Requirements/Criteria10CFR50.55a(b),"Standardsapprovedfor incorporationbyreference," references the approved standardsrequiredtobefollowedfor systems and components of nuclear powerreactors.10CFR50.55a, paragraph (b)(3), referencestheASMEOMCode.10CFR50.55a,paragraph(b)(6),"Operationand Maintenance of NuclearPowerPlantsCodeCases,"allowslicenseestoapplytheASMECodeCaseslistedin RegulatoryGuide1.192,"Operationand MaintenanceCodeCase Acceptability,ASMEOMCode,"withoutpriorNRCapproval subject to the conditionslistedin10CFR 50.55a(b)(6), paragraphs(i)through(iii).10CFR50.55a,paragraph(a)(3)(i)allowslicenseestorequesttheuseofASMECodeCasesthatarenotreferencedinthe currentversionof RegulatoryGuide1.192.TheuseoftheapprovedASMEOMCodeCaseOMN-20is consistentwiththeseregulations.10CFR50.36(c)(5),"Administrativecontrols,"states,"Administrative controlsarethe provisionsrelatingto organization and management, procedures, recordkeeping,reviewandaudit,and reporting necessarytoassureoperationofthefacilityinasafemanner.Eachlicenseeshallsubmitanyreportstothe Commission pursuant to approved technical specifications asspecifiedin §50.4.11 The proposedchangetotheTSInserviceTestingProgramdoesnotaffect compliancewiththisrequirement.Therefore,theproposedchangetotheTSdoesnotaffectplant compliancewiththese regulations.4.2No Significant Hazards Consideration DeterminationEntergyrequestsapprovaltoremoveInserviceTestingProgramfromtheTSandtoclarifySRusagerule applicationtoSection5.5Testing.The proposedchangerevisestheTS Chapter 5,"AdministrativeControls,"Section5.5,"ProgramsandManuals,"todeletethe"InserviceTesting (1ST)Program" specification. Requirementsinthe 1STProgramareremoved,astheyareduplicativeof requirementsintheAmericanSocietyofMechanicalEngineers(ASME) Operations and Maintenance(OM)Code,asclarifiedbyCodeCaseOMN-20,"lnservice TestFrequency."Other requirementsinSection5.5are eliminatedbecausethe Nuclear RegulatoryCommission(NRC)has determined their appearanceintheTSis contrarytoregulations.Anewdefinedterm,"InserviceTestingProqrarn,"isadded,which references the requirementsofTitle10oftheCodeofFederal Regulations(10CFR),Part50, paragraph50.55a(f).The Surveillance Requirement(SR)Section3.0,"SR Applicability,"Basesarerevisedtoexplainthe application oftheusagerulestotheSection5.5testing requirements.Entergyhasevaluated whetherornota significant hazards considerationisinvolvedwiththe proposed amendment(s) by focusing onthethree standardssetforthin10CFR50.92,"lssuance of amendment, II as discussed below:1.Doestheproposedchangeinvolvea significantincreaseinthe probability or consequencesofan accident previously evaluated? GNRO-2015/00037 Attachment 1 Response: No The proposed changerevisesTS Chapter 5,"Administrative Controls,"Section5.5,"ProgramsandManuals,"by eliminatingthe"lnservice Testing Program" specification. Requirementsinthe 1ST programareremoved,astheyare duplicative of requirementsintheASMEOMCode,as clarifiedbyCodeCase OMN-20,"lnserviceTest Frequency." Other requirementsintheSection5.5 1STProgramare eliminatedbecausetheNRChas determinedtheirinclusionintheTSis contrary to regulations.Anewdefinedterm,"lnserviceTestingProgram, IIisaddedtotheTS,which references the requirements of10CFR 50.55a(f). The proposed changealsorevisestheSRSection3.0,"SR Applicability,"Basestoexplainthe applicationoftheusagerulestotheSection5.5 testing requirements. Performance of inservicetestingisnotan initiatortoany accident previously evaluated.Asaresult,the probability of occurrenceofan accidentisnot significantly affected by the proposed change.lnservice test periodsunderCodeCase OMN-20 are equivalent to the currenttestingperiodallowedbytheTSwiththe exceptionthattesting periods greaterthan2yearsmaybe extendedbyupto6 months to facilitate test scheduling and considerationofplant operating conditionsthatmaynotbe suitable for performance oftherequiredtesting.Thetestingperiod extensionwillnotaffecttheabilityofthe componentstomitigateany accident previously evaluatedasthe components arerequiredtobe operableduringthetestingperiodextension. Performanceofinservicetestsutilizingthe allowances in OMN-20willnot significantlyaffectthereliabilityofthe tested components.Asaresult,the availabilityofthe affected components,aswellastheirabilityto mitigate the consequences of accidents previously evaluated,isnot affected.The proposedSR3.0Bases changesclarifythe appropriate applicationoftheexisting TS requirements. Since the proposedchangedoesnot significantlyaffectsystem Operability, the proposed changewillhaveno significanteffectontheinitiatingevents for accidents previously evaluatedandwillhaveno significanteffectontheabilityofthe systemstomitigate accidents previously evaluated. Therefore, the proposed changedoesnotinvolvea significant increaseinthe probability or consequencesofan accident previously evaluated.2.Doesthe proposed changecreatethe possibilityofanewor differentkindof accidentfromany previously evaluated? Response: No The proposed changedoesnotalterthedesignor configurationoftheplant.The proposedchangedoesnotinvolveaphysical alterationoftheplant;nonewor differentkindof equipmentwillbeinstalled.The proposed changedoesnotalterthetypesofinservicetesting performed.Inmostcases,the frequencyofinservicetestingis unchanged.However,the frequencyoftestingwouldnotresultinanewor different kind of accidentfromany previously evaluatedsincethetesting methodsarenotaltered.TheproposedBaseschangedoesnot change the Operability requirementsforplant systems GNRO-2015/00037 Attachment 1orthe actionstakenwhenplant systemsarenot operable.TheproposedBaseschange clarifies the current applicationofthe specifications. Therefore, the proposed changedoesnotcreatethe possibilityofanewor different kind of accidentfromany previously evaluated.3.Doesthe proposed changeinvolvea significantreductioninamarginofsafety? Response: No The proposed change eliminates some requirementsfromtheTSinlieuof requirementsintheASMECode,as modifiedbyuseofCodeCaseOMN-20. CompliancewiththeASMECodeisrequiredby10CFR50.55a.The proposed changealsoallows inservicetestswith periods greaterthan2yearstobe extendedby6 months to facilitate test scheduling and considerationofplant operating conditionsthatmaynotbe suitable for performanceofthe requiredtesting.Thetestingperiod extensionwillnotaffecttheabilityofthe componentstorespondtoan accidentasthe componentsarerequiredtobe operableduringthetestingperiod extension. The proposed change will eliminate theexistingTSSR3.0.3 allowance to defer performanceofmissed inservicetestsuptothe durationofthe specifiedtestingperiod,andinsteadwillrequirean assessmentofthemissedteston equipment operability. This assessment will considertheeffectonamarginofsafety (equipment operability).Shouldthe component be inoperable, the Technical Specifications provide actionstoensurethatthemarginofsafetyis protected. The proposedchangealso eliminates a statementthatnothingintheASMECodeshouldbe construed to supersede the requirementsofanyTS.TheNRChas determined that statementtobeincorrect.However, eliminationofthe statement willhavenoeffectonplant operationorsafety.The proposed changestotheSR3.0Basesclarifythe applicationoftheexistingTS requirementsand,asaresult,haveno significanteffectonamarginofsafety. Therefore, the proposed changedoesnotinvolvea significantreductioninamarginof safety.Basedontheabove,Entergy concludesthatthe proposed change presents no significant hazards considerationunderthe standardssetforthin10CFR50.92(c),and, accordingly, afindingof"no significant hazards consideration II is justified.

5.0 ENVIRONMENTAL

EVALUATIONTheproposed change would change a requirementwithrespectto installationoruseofafacility componentlocatedwithintherestrictedarea,as definedin10CFR20,orwould change aninspectionor surveillance requirement.However,the proposed changedoesnotinvolve(i)a significant hazards consideration,(ii)a significant changeinthetypesor significant increase in the amountsofany effluentsthatmaybereleasedoffsite,or(iii)a significant increase inindividualor cumulative occupational radiation exposure.Accordingly, the proposed changemeetsthe eligibilitycriterionfor categorical exclusionsetforthin10CFR 51.22(c)(9). Therefore, pursuantto10CFR51.22(b),no environmental impact statement or environmental assessmentneedbepreparedin connectionwiththe proposed change. GNRO-2015/00037 Attachment 16.0References 1.Regulatory Issue Summary2012-10,"NRC Staff Position on Applying Surveillance Requirement3.0.2and3.0.3to Administrative Controls ProgramTests,"datedAugust23, 2012.2.Enforcement Guidance Memorandum 2012-001,"Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic RequirementsthatExtend Test FrequenciesandAllow PerformanceofMissedTests,"datedFebruary24,2012. 3.AmericanSocietyof Mechanical EngineersCodeCaseOMN-20,"InserviceTestFrequency,"issuedJanuary2013.4.NRC InspectionManualPart9900, Technical Guidance,"Operability Determinations &Functionality Assessments for Resolution of Degraded and Nonconforming Conditions AdversetoQualityorSafety,"Revision1,datedApril16,2008(ADAMSAccessionNumber ML073440103)." 5.RegulatoryGuide1.192,"Operation and MaintenanceCodeCase Acceptability,ASMEOMCode,"August2014. 6.TSTF-GG-05-01,"Writer'sGuidefor Plant-Specific Improved Technical Specifications." Attachment 2 to GNRO-2015/00037 Description and Assessment of Proposed Alternative to theASMECode GNRO-2015/00037 Attachment 2 DESCRIPTION AND ASSESSMENTOFTHE PROPOSED ALTERNATIVETOTHE ASME CODE Request in Accordance with10CFR 50.55a(a)(3)(i) Alternative Provides Acceptable Level of Quality and Safety

1.0 DESCRIPTION

Therequestisto adopt a proposed alternativetothe American Society of Mechanical Engineers (ASME)Operation and Maintenance(OM)Codeby adoption of approvedCodeCaseOMN-20,"Inservice Test Frequency." 2.0 ASSESSMENT 2.1 Technical Evaluationofthe Proposed AlternativetotheOMCode Section 1STofDivision1oftheOMCode,whichis incorporated by referencein10CFR 50.55a(b)(3), specifies component test frequenciesbasedeitheronelapsedtimeperiods(e.g.,quarterly,2years)oronthe occurrenceofaplant conditionorevent(e.g.,cold shutdown, refueling outage).The 1ST Program controls specifiedinSection5.5ofTSprovide:a)atable specifying certain 1ST frequencies;b)an allowance to applySR3.0.2to inservicetestsrequiredbytheOMCodeandwith frequenciesoftwoyearsorless;c)an allowancetoapplySR3.0.3to inservice testsrequiredbytheOMCode;andd)a statementthat,"NothingintheASMEOMCodeshallbe construed to supersede the requirementsofanyTS."In Regulatory Issue Summary(RIS)10,"NRCStaffPositionon Applying Surveillance Requirement3.0.2and3.0.3to Administrative ControlsProgramTests,"and Enforcement Guidance Memorandum (EGM)2012-001,"Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic RequirementsthatExtend Test FrequenciesandAllow PerformanceofMissedTests,"theNRCstatedthatitemsb,c,anddoftheTS 1STProgramwere inappropriately addedtotheTSandmaynotbeapplied (althoughtheEGMallows licenseestocontinuetoapply those paragraphspendinga genericresolutionoftheissue).ASMECodeCaseOMN-20,"Inservice Test Frequency,"hasbeen approvedforusebytheASMEOM committeeasan alternativetothetest frequencies for pumpsandvalves specified inASMEOMDivision:1Section 1ST2009EditionthroughOMa-2011 Addenda,andallearliereditionsand addendaofASMEOMCode.CodeCase OMN-20isnot referencedinthelatestrevisionof RegulatoryGuide1.192(August2014)asan acceptableOMCodeCaseto complywith10CFR50.55a(f) requirements asallowedby10CFR 50.55a(b)(6). The proposed alternativeisto permanentlyuseCodeCase OMN-20toextendorreducethe 1ST frequency requirements until OMN-20 is incorporated intothenextrevisionof RegulatoryGuide1.192. GNRO-2015/00037 Attachment 2ASMECode Components AffectedTheCodeCaseappliesto pumpsandvalves specifiedinASMEOMDivision:1Section 1ST2009EditionthroughOMa-2011 Addendaandall earlier editions and addendaofASMEOMCode.Period extensionsmayalsobeappliedto accelerated test frequencies(e.g.,pumpsinAlertRange)as specified in OMN-20.Forpumpsandvalveswithtest periodsof2yearsofless,thetestperiodallowedbyOMN-20 and the current TS Inservice TestingProgram(as modifiedbySR3.0.2andEGM 2012-001)arethesame.Forpumpsandvalveswithtest periods greaterthan2years,OMN-20allowsthetestperiodtobe extendedby6months.The current TS Inservice TestingProgramdoesnotallowextensionoftest periodsthatare greaterthan2years.ApplicableCodeEditionand AddendaASMECodeCase OMN-20 appliestoASMEOMDivision:1Section 1ST2009Editionthrough OMa-2011 Addendaandall earlier editions and addendaofASMEOMCode.TheGrandGulf NuclearStationUnit1CodeEditionand Addendathatare applicabletotheprogramintervalareASMEOMCode2001Editionwith addendathroughandincludingASMEOMbCode2003 Addenda (referredtoas OMb-2003), with exceptionfortheMainSteamSafetyReliefValvestesting.ForMainSteamSafetyReliefValvestestingtheGrandGulf NuclearStationUnit1 implements Appendix I, Paragraphs1-3410(a)&(b)ofSAMEOM Code-2004Editionwithno addenda.Theterm"theCode"isusedinthisplantocalloutbothofthesesetsofrules.Where necessary,OM-1,OM-6,orOM-10willbelistedatthebottomofapageorcalledouttoindicatethatasectionisonly applicabletoa specificcode.TheGrandGulf NuclearStationUnit1 currentintervalends November30,2017.Applicable Code RequirementThisrequestismadein accordancewith10CFR 50.55a(a)(3), and proposes an alternative to the requirementsof10CFR 50.55a(f),whichrequirespumpsandvalvestomeetthetest requirementssetforthin specific documents incorporated by referencein10CFR50.55a(b).ASMECodeCase OMN-20 appliestoDivision1,Section 1SToftheASMEOMCodeand associatedaddenda,whichare incorporated by referencein10CFR 50.55a(b)(3).ReasonforRequestInRIS 2012-10andEGM 2012-001,theNRCstatedthatthe current TS allowancetoapplySR3.0.2andSR3.0.3tothe Inservice TestingProgramwouldno longerbepermitted.Inresponse,OMN-20,which provides allowances similartoSR3.0.2,was approvedandis proposedtobeusedasan alternativetothetest periods specifiedintheOMcode.The proposed change substitutes an approvedCodeCaseforexistingTS requirementsthattheNRChas determinedarelegally,butnot technically, unacceptableasaTS allowance. GNRO-2015/00037 Attachment 2 Proposed AlternativeandBasisforUse The proposed alternativeisOMN-20,"Inservice Test Frequency," which addresses testingperiodsforpumpsandvalves specifiedinASMEOMDivision1,Section 1ST,2009EditionthroughOMa-2011 Addenda,andall earliereditionsand addendaofASMEOMCodeThisrequestisbeingmadein accordancewith10CFR 50.55a(a)(3)(i)andis considered an alternative that provides an acceptablelevelof quality and safetyforthefollowingreasons:1)For 1ST testing periodsuptoand including2years,CodeCaseOMN-20providesan allowancetoextendthe 1ST testing periodsbyupto25%.Theperiodextensionisto facilitate test scheduling and considers plant operating conditionsthatmaynotbe suitable for performanceoftherequiredtesting(e.g., performanceofthetestwouldcausean unacceptable increaseintheplantriskprofiledueto transient conditions or other ongoing surveillance,testor maintenanceactivities).Period extensions are notintendedtobeused repeatedly merelyasan operational conveniencetoextendtest intervalsbeyondthose specified..Thetestperiodextensionandthe statementsregardingthe appropriateuseoftheperiodextensionare equivalenttotheexistingTSSR3.0.2 allowanceandthe statementsregardingitsuseintheSR3.0.2Bases.UseoftheSR3.0.2period extensionhasbeenapracticeinthe nuclearindustryformany decadesandthereisno evidencethattheperiod extensions affect component reliability.2)For 1ST testing periods of greaterthan2years, OMN-20allowsanextensionofupto6months.TheASMEOM Committee determinedthatsuchanextensionis appropriate.The6-month extensionwillhaveaminimalimpacton component reliability consideringthatthemost probableresultof performinganyinservicetestis satisfactory verificationofthetest acceptancecriteria.Assuch,pumpsandvalveswill continuetobe adequately assessed for operational readinesswhentestedin accordancewiththe requirements specifiedin10CFR 50.55a(f)withthe frequency extensionsallowedbyCodeCase OMN-20.3)AsstatedinEGM 2012-001,ifan InserviceTestisnot performedwithinits frequency,SR3.0.3willnotbeapplied.Theeffectofamissed InserviceTestonthe Operability of TS equipmentwillbe assessedunderthe licensee's Operability Determination Program.DurationofProposed Alternative The proposed alternative is requestedtobe permanent,effectivethroughthetermofthelicense,oruntilCodeCase OMN-20 is incorporatedintoafuturerevisionof Regulatory Guide 1.192, whichever occurs first.PrecedentsTheNRC approvedtheuse of OMN-20forQuadCitieson February14,2013(NRCADAMS Accession Number ML 13042A348). Attachment 3 to GNRO-2015/00037 Proposed Technical Specification Changes (Marked-Up) 1.0-3 1.1 Definitions DOSE EQUIVALENT 1-131 (continued) EMERGENCY CORE COOLING SYSTEM (ECCS)RESPONSE TIME END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)SYSTEM RESPONSE TIME ISOLATION SYSTEM RESPONSE TIME mT:1tJ&ftQ<;tAJl1 GRAND GULF Definitions 1.1 be those listed in Federal Guidance Report (FGR)11,"Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial movement of the associated turbine stop valve or the turbine control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker.The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured, except for the breaker arc suppression time, which is not measured but is validated to conform to the manufacturer's design value.The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation* setpoint at the channel sensor until the isolation valves travel to their required positions. The response time (continued)1: JJs c JLVI(ci: o 6 l.ts,Ii-I U u-;rt.-f*J YU&1 t S , 0 c-fL?"o.s"$'A",)AmendmentNo. 188 I'SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE SLC System 3.1.7 FREQUENCY SR 3.1J7.6 Verify each SLC subsystem manual, power operated, and automatic valve in t he-flow path that is not locked;sealed, or secured in position, is in the correct position, or can be to the correct position.31 days SR 3.1:.7.1 Verify each pump develops a flow rate41.2 gpm at a discharge pressure1340 psig.In accordance (VI I,h the.........Inservice A tt Program'6A&SR 3.1.7.8 SR*3.1.7.9 SR 3.1.7.10 Verify flow through one SLC subsystem from pump into reactor pressure vessel.Determine Boron-l0 enrichment in atom.percent (E).Verify piping the storage tank and pump suction is not blocked.24 monthsona STAGGERED,*TEST BASIS Once within 24 hours..af ter boron is added to the solution.Once within 24 hours after solution is restored to>45°F GR.Z\ND GULF Next page is 'Amendment No. 197 S/RVs 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.4 Safety/Relief Valves (S/RVs)LCO 3.4.4 The safety_function of nine S/RVs shall be OPERABLE, AND The relief function of six additional S/RVs shall be OPERABLE.APPLICABILITY: MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIMEA.One or more required S/RVs inoperable. A.1 AND Be in MODE 3.12 hours 0 A.2 Be in MODE 4.36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with the Tnservice-1 Jt1b-{Ge.- Testing Program I A lL.-, Number of Setpoint S/RVs (psig)8 1165+/-34.9 6 1180+/-35.4 6 1190+/-35.7 Verify the safety function lift setpoints of the required S/RVs are as follows: 3.4.4.1 SR (continued) GRAND GULF 3.4-10 Amendment No.ire, ir3, 191 -ACTIONS RCS PIV Leakage 3.4.6-" CONDITION REQUIRED ACTION COMPLETION TIME A.(continued) A.2 Isolate the high 72 hourspressureportionof the affected system from the low pressure portion by useofa second closed manual, deactivated automatic, or check valve.B.Required Action and B.1 Be 1n MODE 3.12 hours associated Completion Time not met.AND B.2 Be 1n MODE 4.36 hours SURVEILLANCE REQUIREMENTS --." SR 3.4.6.1 GRAND GULF SURVEILLANCE

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NOTE--------------------

Onlyrequiredtobe performed in MODES 1 and 2.Verifyequivalentleakageof each ReS PIV is1 gpm, at an RCS pressure1040 psig and1060 psig.3.4-15 FREQUENCY In accordance ."A I with/lnservice _-1ALL GAle Amendment No.120 ECCS-Operating

3.5.1 SURVEILLANCE

REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 SR 3.5.1.2 SR 3.5.1.3 Verify, for each ECCS injection/spray 31 days subsystem, the piping;s filled with water from the pump discharge valve to the injection valve.Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.Verify ADS accumulator supply pressure is 31 days150 psig.SR 3.5.1.4 Verify each ECCS pump develops the specified flow rate with the specified total developed head.TOTAL SYSTEM FLOW RATE PEVELOPEP HEAP LPCS7115 gpm290 psid LPCI7450 gpm125 psid HPCS7115 gpm445 psid In accordance will the(JI1 J l(fnserVTce \Testi ng Program ALL"----------\ //\./I\..;/"(I.J.(continued) GRAND GULF 3.5-4 Amendment No. ECCS-Shutdown*3.5.2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE \FREQUENCY7115 gpm7450 gpm7115 gpm FLOW RATE SYSTEM*Verify each required EtCSI pump In accordance speci f ied flow rate wi th.the speci fi ed t-.:.:ha..-:::.t:.;.;,he::-- _*total deve.,loped.head.'....'.Testlng TOTAL-DEVELOPED HEAD'290 psid125 psid445 psid.LPCS LPCI HPCS SR 3.5.2.5 SR 3.5.2.6----------------NOTE------------------- Vessel injection/spray may be excluded.Verify each required ECCS injection/spray subsystem actuatesonan actual or simulated automatic initiation signal.24 months GRAND GULF 3.5-9*Amendment No.133, 197 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) SR 3.6.1.3.3 SR 3.6.1.3.4 SURVEILLANCE

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NOTES------------------

1.Valvesand blind flangesinhigh radiation areas may be verified by use of administrative means.2.Not required tobemet for PCIVs that areopenunder administrative controls.Verifyeachprimary containment isolation manual valve and blind flange that is located inside primary containment, drywell,orsteam tunnelandnot locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.Verify the isolationtimeofeach power operated, automatic PCIV, except MSIVs, is within limits.FREQUENCY Prior to entering MODE 2 or 3 from MODE 4, if not performed within the previous 92 days In accordance with the I I(Inservi ce.A eng Program)[Ars (continued) GRAND GULF 3.6-15 Amendment No. PCIVs.3.6.1.3 FREQUENCY'.24months In.accordance - rrestirig Program\l' ,.SURVEILLANCE Verify each automatic PCIV actuates to the isolation positiononan actual or'simulated signal**::**t** .'Ver'ifythe isolation time of each MSIV is....';.".,:3 seconds and.s 5 seconds..,......:..".SURVEI-LLANCE.REQUIREMENTS (continued) ....: '.;:'/.:....::,'******l,.*.:*...:....".'.\". ..{;.!:.":': ".,'::'*..'.'..:-.".:.".=:.*:.,:;r.**...:*"3':6,,1.3.7 In accordanGe with 10 CFR 50, Append i x J:, Testing Program Only required tobemetin MODES 1, 2;and 3: verify leakage rate througheachmain steam I ine is.s 100 scfh when tested.at.Pa.and the totaI*I eakage rate through al ImainsteamI ines is.s 250 sqfh when tested atP a. ..Only required tobemetin MODES1,2,and3..'..3.6.1.3.9"." I."*..*.**.'.1..:..'":i;,/t:,'t*;:') ---:..:---' !_.-.-..-;-.;...----------------,-.;..------t---------- ":'..:->.':...:':. ..: ':...'*.:**:**r-. ".';";;:}{\,:;::' SR'3.6.i ,3.8'j:""',c;')':r:I,'...',***I"'..*.'...i'..'.I-.'.'***Verify'combined rate of 1 gpm times the number of PCIVs through Iy tested lines'that, penetrate'the primary containment is not exceeded when these isolation valves are at1.1Pa.In accordance with'10 CFR 50, Appendix J, Testing ..:..,'.'......:;..'......**.:..:*.*.;."*...*I.';','.'I:.I**'*****:i",','/,,',; .. ..GULF ,.!.3.6-17'Amendment No.:+4-5, 197 .;.....'.:...;'.1 RHR Containment Spray .*3.6.1.7: FREQUENCY In accordance with thenservice 1\L J\., Testing H L..Program CAI-s.'31days Yerify.each RHR pump.developsaflow rate'of7450gpm on recirculation flow through the associated heat exchanger to the suppression pool., Verify each RHR containment spray*.subsystemmanual,'power operated, and.automatic valve in the flow path that is. locked,'sealed, or otherwise secured:.l n pos l tlon is in the correct position. RHR spray subsystems may be considered OPERABLE duringalignmentand ope rat i'on for decay heat remova I when:' the RHR cut in pressure in.MODE*3 if capable or being manually realignedand not otherwise inoperable. '.'....;...,....:..:.:...: "::.:.:;-,::>:-';".:.: /:'..>":--:;." ..,,;,-,..... '.:': ',.-:'.,:.'SR 3.6.1.7.1

'.:::.'-,:::......;'.'":"::....::.'.':.:..:,;':'::',.:.:,:::()<<..:"'>:.,...'I;':::".:::;.....:...,'

I;:....*,:::.:.".:;)::',.,::,:;",:::,' .... ,:,--"':-+-...;....___=__:":.:\:::3:6,1 ,'7:......:.:'-:.....'..l.*".'.'.,',:;.i-:.:'.:":',._..............--,.-+-,.;"",;,__Ver'i ry.each RHR c.onta i.nment spray automatic valve in the flow..path*-actuates to*i ts correctpasitionon an*actual or automatic signal.24 months.:': '.:.***1'!.:-: '.':-::.,..:.':":..s'.;.::'.::.i..:: 'v...::.;..:..' .*...,*.:..

LF*1'.1:**0:*.'_,.00:.*,'./*3.6-23'....'.A,mendment No...:rre r,':1:,

'_.RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automaticvalveinthe flow path that is not locked,\sealed,orotherwisesecured in positionisinthe correct position or canbealignedtothe correct position.-SR 3.6.2.3.2 Verify each RHR pumpdevelopsa flow rate7450 gpm through the associated heat exchangerstothesuppressionpool. In accordance with t tsting Program GRAND GULF 3.6-32 Amendment No.120 SCIVs 3.6.4.2 SURVEILLANCE FREQUENCY SR 3.6.4.2.1------------------NOTE S-----------------1.Valves,dampers,rupturedisks,andblindflangesinhighradiationareasmaybeverifiedbyuse of administrative means.2.Notrequiredtobemetforthatareopenunder:administrativecontrols.Verifyeachsecondarycontainment isolationmanualvalve,damper,rupturedisk,andblind flangethatis required.tobeclosedduringaccidentconditionsisclosed. 31 daysVerifytheisolationtime.ofeachpoweroperated,automaticSCIViswithin limits.SR 3.6.4.2.2Inaccordance IJ J/I.with. -)""'tI"'(£.....lGt. ICSlingprOgrarn J4 L t:--------------------.-.,r------.-SR 3.6.4.2.3VerifyeachautomaticSCIVactuatestotheisolationpositionon 24 monthsanactualorsimulated automatic isolation signal.GRANDGULF 3.6-48AmendmentNo. 69, 197 SURVEILLANCE REQUfREMENTS (continued) SURVEILLANCE Drywell Isolation Valves 3.6.5.3 FREQUENCY v, SR 3.6.5.3.3 SR3.6.5..3.4GRANDGULF VerifY the isolationtimeofeachpower operated, automatic drywell isolationvalveiswithin limits..Verifyeach autornaticdrywell isolationvalveactuatestothe isolationpositiononanactualor simulated isolation signal.3.6-61 In accordance JlAul (JAdtb.thefInservice'

A--l24 months Amendment No.+69, 197 ProgramsandManuals 5.55.5ProgramsandManuals (continued) 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the cyclic and transient occurrences identified on UFSAR Table 3.9-35 to ensure that the reactor vessel is maintained within the design limits.(continued)

Ampnnmpnt Nn++A l42 Requir Frequencies p rforming inservice n activities least onceper7 days least onceper31 days least once per 92 days least onceper184 days onceper276 days onceper366 days once pet 731 days 3.0.2 are applica]e to the above for performing inse vice testing su.r: The provisions of required frequen activities; Weekly Monthly Quarterly or every3months Semiannually or every6monthsEvery9months Yearly or annually Biennially or every 2 years Testing frequencies specified in Section XI of oiler and Pressure Vessel Code and applicablefolows: ASME and PressureVesseldeand applicable Addenda terminology or inservice tes activities d.'n the ASME Boiler and Pressure Vesseldto supersede the requirementsofany b.c.The provisio of SR 3.0.3 testing act'vities; and Inservice Testing Program This program provides controls for inservice testing of ASM Class1,2,and3 components.Theprogram shall include e following: 5*5,6 GRAND GULF Attachment 4 to GNRO*2015/00037 Revised Technical Specification Pages (Clean)

1.1 Definitions

DOSE EQUIVALENT 1-131 (continued) EMERGENCY CORE COOLINGSYSTEM(ECCS) RESPONSE TIMEENDOFCYCLE RECIRCULATIONPUMPTRIP(EOC-RPT)SYSTEMRESONSETIME INSERVICE TESTING PROGRAMISOLATIONSYSTEMRESPONSETIME Definitions 1.1bethoselistedinFederal GuidanceReport(FGR)11,"LimitingValuesof RadionuclideIntakeandAir ConcentrationandDose ConversionFactorsforInhalation, Submersion,andIngestion,"1989.TheECCS RESPONSETIMEshallbethattimeintervalfromwhenthemonitored parameter exceedsitsECCS initiation setpointatthechannel sensoruntiltheECCS equipmentiscapableofperformingitssafetyfunction(i.e.,thevalvestravelto theirrequiredpositions,pump discharge pressures reach theirrequiredvalues,etc.).Timesshallincludediesel generatorstartingand sequence loadingdelays,whereapplicable.Theresponsetimemaybe measuredbymeansofanyseriesof sequential, overlapping,ortotalstepssothattheentire responsetimeismeasured. The EOC-RPT SYSTEM RESPONSETIMEshallbethattimeintervalfrominitial movementoftheassociatedturbinestopvalveortheturbinecontrolvalveto complete suppressionofthe electricarcbetweenthefullyopen contactsofthe recirculationpumpcircuitbreaker.Theresponsetimemaybemeasuredbymeansofanyseriesof sequential, overlapping,ortotalstepssothattheentire responsetimeismeasured, exceptforthe breaker arc suppressiontime,whichisnot measuredbutisvalidatedtoconformtothe manufacturer'sdesignvalue. The INSERVICE TESTINGPROGRAMisthelicenseeprogramthatfulfillsthe requirements of 10 CFR50.55a(f). The ISOLATION SYSTEM RESPONSETIMEshallbethattimeintervalfromwhenthemonitored parameter exceedsitsisolationinitiation setpointatthechannel sensoruntiltheisolation valvestraveltotheirrequiredpositions. The response time(continued)GRANDGULF 1.0-3 Amendment No.44a, 488,__ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCESLCSystem 3.1.7 FREQUENCYSR3.1.7.6SR3.1.7.7SR3.1.7.8SR3.1.7.9 SR 3.1.7.10GRANDGULFVerifyeachSLC subsystem manual, power operated, and automaticvalveintheflowpath thatisnotlocked,sealed,or otherwise securedinposition,isin the correctposition,orcanbe alignedtothe correct position.Verifyeachpump developsaflowrate 241.2gpmat a discharge pressure1340psig.Verifyflow throughoneSLC subsystemfrompump into reactor pressure vessel.Determine Boron-10 enrichmentinatom percent (E).Verifypiping between the storagetankandthepump suctionisnotblocked. 3.1-23Nextpageis3.1-26.31days In accordance with the INSERVICE TESTING PROGRAM 24 monthsona STAGGERED TEST BASIS Oncewithin24 hoursafterboronisaddedtothe solution.Oncewithin24hoursafter solution temperature isrestoredto Amendment No.+90,-1-9+,__ S/RVs 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.4 Safety/Relief Valves (S/RVs)LCO3.4.4Thesafety functionofnine S/RVsshallbe OPERABLE, The relief functionofsix additional S/RVsshallbe OPERABLE.APPLICABILITY: MODES1,2,and3.ACTIONS CONDITIONA.Oneormorerequired S/RVs inoperable. A.1 AND A.2 REQUIRED ACTIONBeinMODE 3.BeinMODE4. COMPLETION TIME 12 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verifythesafety function lift setpointsoftherequired S/RVsareasfollows:SR3.4.4.1 GRAND GULF Number of S/RVs 8 6 6 3.4-10 Setpoint 1Q§ig1 1165+/-34.9 1180+/-35.41190+/-35.7 In accordance with the INSERVICE TESTING PROGRAM (continued) Amendment No.W+,__ RCSPIV Leakage 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.(continued) A.2 Isolatethehigh pressure 72 hours portionofthe affected systemfromthelow pressure portionbyuse of a second closed manual, deactivated automatic, or check valve.B.Required ActionandB.1Bein MODE 3.12 hours associated Completion Timenotmet.ANDB.2Bein MODE 4.36 hours SURVEILLANCE REQUIREMENTSSR3.4.6.1 SURVEILLANCE

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Only requiredtobe performed in MODES1and2.Verify equivalent leakage of eachRCSPIVis S 1gpm,atanRCS pressure1040psigand S 1060 psig.FREQUENCYIn accordance with INSERVICE TESTING PROGRAM GRAND GULF 3.4-15 Amendment No.+2:Q,__ ECCS-Operating

3.5.1 SURVEILLANCE

REQUIREMENTSSR3.5.1.1SR3.5.1.2SR3.5.1.3SR3.5.1.4 SURVEILLANCEVerify,foreachECCS injection/spraysubsystem,thepipingisfilledwith waterfromthepump dischargevalvetotheinjectionvalve.VerifyeachECCS injection/spray subsystem manual, poweroperated,and automaticvalveintheflowpath,thatisnotlocked,sealed,or otherwisesecuredinposition,isinthe correct position.VerifyADS accumulator supply pressure is150psig.VerifyeachECCSpump developsthespecifiedflowratewiththespecifiedtotal developed head.TOTAL SYSTEM FLOW RATE DEVELOPED HEAD LPCS7115gpm290psid LPCI7450gpm125psid HPCS7115gpm445psid FREQUENCY31days31days31daysIn accordance with the INSERVICE TESTING PROGRAM (continued)GRANDGULF 3.5-4 Amendment No.-te9,__ SURVEILLANCE ECCS-Shutdown 3.5.2 FREQUENCY VerifyeachrequiredECCSpump develops the specifiedflowratewiththe specified total developed head.SR3.5.2.5 SYSTEM LPCS LPCI HPCS445psid FLOW RATE7115 gpm7450 gpm TOTAL DEVELOPED HEAD290psid125psid7115 gpmIn accordancewiththe INSERVICE TESTING PROGRAMSR3.5.2.6---------------------N 0 TE--------------------------------------- Vessel injection/spraymaybe excluded.VerifyeachrequiredECCS injection/spray subsystem actuatesonanactualor simulated automatic initiation signal.24 months GRAND GULF 3.5-9 Amendment No.-1-97,__ PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) SR 3.6.1.3.3 SR 3.6.1.3.4 SURVEILLANCE--------------------------N0TE S---------------------------- 1.Valvesandblind flangesinhigh radiation areasmaybe verifiedbyuse of administrative means.2.Not requiredtobemetfor PCIVsthatare open under administrative controls.Verify each primary containment isolation manual valveandblind flangethatis located inside primary containment, drywell, or steam tunnelandnot locked, sealed, or otherwise securedandis requiredtobeclosed during accident conditions is closed.Verify the isolation timeofeach power operated, automatic PCIV, exceptMSIVs,is within limits.FREQUENCY Prior to entering MODE2or3from MODE4,ifnot performed within the previous 92 days In accordancewiththe INSERVICE TESTING PROGRAM (continued) GRAND GULF 3.6-15 Amendment No.4-99,__ PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) SR 3.6.1.3.6 SR 3.6.1.3.7 SR 3.6.1.3.8 SR 3.6.1.3.9 SURVEILLANCE Verify the isolation time of each MSIV is3 seconds and S 5 seconds.Verify each automatic PCIV actuatestothe isolation positiononan actual or simulated isolation signal.-------------------NOTE----------------------- Only requiredtobe met in MODES1,2,and3.Verify leakage rate through each main steam line is S100scth when tested atP a, and the total leakage rate through all four main steam lines is S 250 scth when tested atP a--------------------NOTE-------------------------- Only requiredtobe met in MODES1,2,and3.Verify combined leakagerateof1 gpm times the total number of PCIVs through hydrostatically tested lines that penetrate the primary containment is not exceeded when these isolation valves are tested at1.1P a.FREQUENCY In accordance with the INSERVICE TESTING PROGRAM 24 months In accordance with10CFR50, Appendix J, Testing ProgramIn accordance with10CFR50, Appendix J, Testing Program GRAND GULF 3.6-17 Amendment No.44a,-1-9+,__ RHR ContainmentSpraySystem 3.6.1.7 SURVEILLANCE REQUIREMENTSSR3.6.1.7.1 SR 3.6.1.7.2 SR 3.6.1.7.3 SURVEILLANCE

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N()TE-------------------------------

RHR containment spray subsystemsmaybe considered ()PERABLE during alignment and operation for decayheatremovalwhen below theRHRcutin permissive pressure in M()DE3if capableofbeing manually realignedandnot otherwise inoperable. VerifyeachRHR containment spray subsystem manual, power operated, and automaticvalveintheflowpaththatisnotlocked,sealed,or otherwise secured in positionisinthe correct position.VerifyeachRHRpump developsaflowrateof7450gpmon recirculation flow through the associated heat exchangertothe suppression pool.VerifyeachRHR containment spray subsystem automaticvalveintheflowpath actuatestoits correct positiononanactualor simulated automatic initiation signal.FREQUENCY31days In accordancewiththe INSERVICE TESTING PR()GRAM24months GRAND GULF 3.6-23 Amendment No.-1-9+,__ RHR SuppressionPoolCooling 3.6.2.3 SURVEILLANCE REQUIREMENTSSR3.6.2.3.1SR3.6.2.3.2 SURVEILLANCEVerifyeachRHR suppressionpoolcooling subsystem manual, poweroperated,and automaticvalveintheflowpaththatisnotlocked,sealed,or otherwisesecuredinpositionisinthe correctpositionorcanbealignedtothecorrectposition.VerifyeachRHRpump developsaflowrate7450gpmthroughthe associated heat exchangerstothe suppression pool.FREQUENCY31daysIn accordance with the INSERVICE TESTING PROGRAMGRANDGULF 3.6-32 Amendment No.__ SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTSSR3.6.4.2.1 SURVEILLANCE

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N0TE S-----------------------------1.Valves,dampers,rupturedisks,andblindflangesinhighradiationareasmaybeverifiedbyuseof administrative means.2.NotrequiredtobemetforSCIVsthatareopenunder administrative controls.FREQUENCYVerifyeach secondary containment isolationmanualvalve,damper,rupturedisk,andblindflangethatisrequiredtobeclosedduring accident31days conditionsisclosed.SR3.6.4.2.2SR3.6.4.2.3Verifytheisolationtimeofeachpoweroperated, automaticSCIViswithinlimits.Verifyeach automaticSCIVactuatestotheisolationpositiononanactualorsimulated automaticisolationsignal.

In accordancewiththe INSERVICE TESTING PROGRAM24monthsGRANDGULF 3.6-48 Amendment No.49Q, 4-9+,__ DrywellIsolationValves 3.6.5.3 SURVEILLANCE REQUIREMENTS (continued)SR3.6.5.3.3SR3.6.5.3.4 SURVEILLANCEVerifytheisolationtimeofeach power operated, automaticdrywellisolationvalveiswithinlimits.Verifyeach automaticdrywellisolationvalve actuatestotheisolationpositiononanactualorsimulatedisolationsignal. FREQUENCY In accordancewiththe INSERVICE TESTING PROGRAM24monthsGRANDGULF 3.6-61 AmendmentNo.169,197,__ Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient LimitThisprogram provides controlstotrackthe cyclic and transient occurrences identified on UFSAR Table 3.9-35 to ensurethatthe reactorvesselis maintained withinthedesignlimits.5.5.6Deletd (continued) GRAND GULF 5.0-11 Amendment No.-1-2Q,__}}