ML082270515

Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process

ML082270515
Person / Time
Site:	Nine Mile Point
Issue date:	08/14/2008
From:	Polson K J Constellation Energy Group, Nine Mile Point
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML082270515 (17)

Text

Keith J.Polson Vice President-Nine Mile Point 0/\Constellation Energy.-,..'*N ine M ile Po int Nuclear Stat ionU.S.Nuclear Regulatory Commission Washington,DC20555-0001 P.O.Box 63 Lycoming ,NewYork13093 315.349.5200315.349.1321Fax August 14 , 2008 ATTENTION:

SUBJECT:

Document Control DeskNineMilePoint Nuclear Station Unit No.2;Docket No.50-410 LicenseNo.NPF-69 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequencyanda Clarification of a Frequency Example Using the Consolidated L ine Item Improvement Process In accordancewiththeprovis ions of 10 CFR 50.90, NineMilePoint Nuclear Station , LLC (NMPNS)is submitting a requestforan amendmenttothe Technical Specifications(TS)forNineMilePointUnit2 (NMP2).The proposed amendmentwould:(1)revisetheTS surveillance requirement (SR)frequencyinTS3.1.3,"Control Rod OPERABILITY,"and(2)revise Example1.4-3inTS1.4,"Frequency" to clarify the applicability ofthe1.25 surveillancetestinterval extension.

Attachment 1 providesadescript ion of the proposed change , the requested confirmation of appl icability , and plant-specific verifications.Attachment 2 provides the existingTSpages marked-uptoshowthe proposed changes.AssociatedTSBaseschangesare marked-up in Attachment 3.TheTSBaseschanges are provided for informationonlyandwillbe processed in accordance withtheNMP2TS5.5.10

,"Technical Specifications(TS)BasesControl Program." Attachment 4 provides a summary of the regulatory commitmentsmadeinthissubmittaL NMPNS requests approval of the proposed License Amendment by February 16 ,2009,withthe amendment being implementation within60days of approval of the amendment.

In accordancewith10CFR50

.91, NMPNS has providedacopy ofthislicense amendmentrequest,with attachments

,tothe appropriate state representative

.

Document Control DeskAugust14,2008Page2Shouldyouhaveany questions regarding the informationinthissubmittal, please contactT.F.Syrell, Licensing Director,at(315)349-5219.Verytrulyyours,STATE OF NEW YORK TO WIT: COUNTY OF OSWEGO I, KeithJ.Polson,beingdulysworn,statethatIamVice President-NineMilePoint,andthatIamduly authorized to executeandfilethis request on behalf of NineMilePoint NuclearStation,LLC.Tothebest of my knowledgeandbelief,the statements containedinthis documentaretrueandcorrect.Totheextentthatthese statementsarenot basedonmy personal knowledge,theyarebased upon information providedbyotherNineMilePoint employees and/or consultants.

Such information has been reviewed in accordance with company practiceandI believeittobereliable.

Subscribedandsworn beforeme,a NotaryPublicinandfortheState ofNewYorkand County ofOswego,this day of OJ....%-*;2008.WITNESSmyHandand Notarial Seal: My Commission Expires:__--'-I_Date KJP/GB/--Notary PublicSANDRAA.OSWALDNotaryPublic

.StateofNewYork No.010S6032276Qualifiedin OswegoCommissionExpires16

<<S'd)ct Attachments:

1.2.3.4.Description and Assessment Proposed Technical Specification Changes (Marked-Up Pages)Proposed Technical Specifications Bases Changes (Marked-Up Pages)Summary of Regulatory Commitmentsmadeinthis Submittal DocumentControlDeskAugust14,2008Page3cc:S.J.Collins,NRC Regional Administrator, Region IR.V.Guzman,Jr.,NRC Project ManagerE.C.Knutson, Senior NRC Resident InspectorJ.P.Spath, NYSERDA ATTACHMENT 1 DESCRIPTION AND ASSESSMENT TABLE OF CONTENTS

1.0DESCRIPTION

2.0ASSESSMENT2.1Applicability ofPublishedSafetyEvaluation2.2OptionalChangesandVariations3.0REGULATORYANALYSIS3.1NoSignificantHazardsConsiderationDetermination3.2VerificationandCommitments4.0ENVIRONMENTALEVALUATIONNineMile Point Nuclear Station, LLC August14,2008 ATTACHMENT 1 DESCRIPTION AND ASSESSMENT

1.0 DESCRIPTION

The proposed amendmentwould:(1)revise the Technical Specification (TS)surveillance requirement(SR3.1.3.2)frequencyinTS3

.1.3,"Control Rod OPERABILITY,"and(2)revise Example1.4-3inTS Section 1.4,"Frequency"to clarify the applicability ofthe1.25 surveillance test interval extension.Thechangesare consistent with Nuclear Regulatory Commission (NRC)approved Industryffechnical Specification Task Force (TSTF)Standard Technical Specification(STS)changeTSTF-475

, Revision 1.The F ederal Register Notice published on November13,2007 announced the availability ofthisTS improvement through the consolidatedlineitem improvement process (CLIIP).2.0 ASSESSMENT

2.1 Applicability

of Published Safety Evaluation NineMilePoint Nuclear Station , LLC (NMPNS)has reviewed the safety evaluation dated November 13 ,2007aspart oftheCLIIP.Thisreviewincludedareview oftheNRC staffs evaluation

,aswellasthe supporting information provided to support TSTF-475, Revision 1.NMPNS has concludedthatthe justifications presentedintheTSTF proposalandthesafety evaluation preparedbytheNRC staff are applicable to Nine Mile PointUnit2(NMP2)and justify this amendmentforthe incorporation of thechangestothe NMP2 TS.2.2 Optional Changes and VariationsNMPNSis proposing to implementthefollowingTS editorial changes whichdifferfromthoseTS changes described in TSTF-475, Revision 1 ,andtheNRC staffs model safety evaluation dated November13,2007.Thechangesdonot adversely impact the considerations or conclusionsinthemodel safety evaluationortheintent of the amendment.

NMPNS chooses to designate Surveillance Requirement(SR)3.1.3.2 as"Deleted"andretain current SR numbersSR3.1.3.3,SR3.1.3.4,andSR3.1.3.5.This proposed variation will alleviate the requirement to make editorialchangeslistedin TSTF-475, Revision1forTS3.1.3,3.1.4and associatedTSBases.Additionally, the TSTF-475, Revision 1 requestedchangetotheTSBasesforSR3.1.3.4(torevise referencestoSR3.1.4.3andSR 3.1.4.4)wasnot includedasthese surveillancesarenot affectedbythe proposed changes.During the NMP2 conversiontotheSTS (NUREG-1433)forTS3.3.1.2,"Source Range Monitor (SRM)Instrumentation

" by Amendment 91 dated February 15 ,2000(TACNo.MA3822), Required Action E.2 was revised and presently reads"Initiate actiontofullyinsertall insertable controlrodsincorecells containingoneormorefuel assemblies."Theterm"fully"wasalso includedinTS Bases 3.3.1.2.Therefore,theseTSTF-475

, Revision 1 changesarenot necessaryforNMP2.3.0 REGULATORY ANALYSIS3.1No Significant Hazards Consideration DeterminationNMPNShas reviewed the proposed no significant hazards consideration determination (NSHCD)publishedinthe Federal Register as part oftheCLIIP.NMPNShas concludedthatthe proposed NSHCD 10f2 ATTACHMENT 1 DESCRIPTION AND ASSESSMENTpresentedinthe Federal RegisternoticeisapplicabletoNMP2andisherebyincorporatedbyreferencetosatisfytherequirements of10CFR50.91(a).

3.2 Verification

and CommitmentsAsdiscussedinthenotice ofavailabilitypublishedinthe Federal Register on November13,2007forthisTSimprovement,NMPNShasverifiedtheapplicability ofTSTF-475toNMP2,andcommitstoestablishingTechnicalSpecificationBasesfortheTSasdescribedinthislicensingamendmentrequest.ThesechangesarebasedonTSTFchangetravelerTSTF-475(Revision1)thatproposesrevisionstotheSTSby: (1)revisingthefrequency ofSR3.1.3.2,notchtesting ofawithdrawncontrolrod,from"7daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM"to"31daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM";and(2)revisingExample1.4-3inSection1.4,"Frequency"toclarifythatthe1.25surveillancetestintervalextensioninSR3.0.2isapplicabletotimeperiodsdiscussedinNOTESinthe"SURVEILLANCE "columninadditiontothetimeperiodsinthe"FREQUENCY" column.4.0 ENVIRONMENTAL EVALUATIONNMPNShasreviewedtheenvironmentalevaluationincludedinthemodelsafetyevaluationdated November 13,2007aspart oftheCLIIP.NMPNShasconcludedthatthe staffsfindingspresentedinthatevaluationareapplicabletoNMP2andtheevaluationisherebyincorporatedbyreferenceforthis application.

20f2 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARKED-UP PAGES)TSPage1.4-4TSPage1.4-5TSPage3.1.3-2 TSPage3.1.3-4NineMile Point Nuclear Station, LLC August14,2008 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)"Thereafter" indicates future performances must be established per SR 3.0.2,butonly after a specified condition is first met (i.e., the lIonce" performance in this example).If reactor powerdecreasesto

<25%RTP, the measurementofboth intervals stops.New intervals start upon reactor power reaching 25%RTP.EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE

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

Notrequiredto be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after25%RTP.Perform channel adjustment.

FREQUENCY7days (continued)

The interval continues whetherornotthe unit operation is<25%RTP between performances.

As the Notemodifiesthe required performanceofthe Surveillance, it isconstruedtobe partofthe"specified Frequency.

" Shouldthe 7 day i nterva 1 be exceeded wh il eoperationis

<25%RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches25%RTP to perform the Surveillance.

The Surveillance is stillconsideredto bewithinthe"specified Frequency.

" Therefore, if the Surve ill ance were not performedwithinthe 7 day interval(plusthe extension allowed by SR 3.0.2), but operation was<25%RTP, it would not constitute a failureofthe SR or failure to meet the LCO.Also, no violation of SR 3.0.4 occurs when changing MODES, evenwiththe 7 day Frequencynotmet,provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).\with power25%RTP.(PLus The ex teIJS;O'"

&;:f<6r<3.0.:J)'3 I NMP2 1.4-4 Amendment'"9-i)

1.4 Frequency

EXAMPLES Frequency 1.4 EXAMPLE 1.4-3 (continued)

Once the unit reaches 25%RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed forcompletingthe Surveillance.

If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval, there wou then be a failuretoperforma Surveillance within the specified Frequency, and the SR 3.0.3 wouldapply.\(fLl.5" the..ex\eU61 Q1-'5R 3.0.d;EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE

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

Only requiredtobe met in MODE 1.FREQUENCYVerifyleakage ratesarewithin limits.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-4 specifies that the requirements of this Surveillancedonot havetobe met untiltheunit is in MODE 1.The interval measurement for the Frequency of this Surveillance continues at all times,asdescribedin Example 1.4-1.However, the Note constitutes an"otherwise stated" exceptiontothe Applicability of this Surveillance.

Therefore, if the Surveillance were not performedwithinthe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval(plusthe extension allowed by SR 3.0.2),butthe unit wasnotin MODE 1, there would be no failure of the SR nor failure to meet the LCO.Therefore, no violation of SR 3.0.4 occurs when changing MODES, evenwiththe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequencyexceeded,providedthe MODE change was not made into MODE 1.Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency werenotmet), SR 3.0.4 would require satisfying the SR.NMP2 1.4-5 Amendment*)

ACTIONS Control Rod OPERABILITY

3.1.3 CONDITION

REQUIRED ACTION COMPLETION TIME A.(continued)

A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from--aftEI-SR3.1.3.3fordiscoveryof each withdrawn Condition A OPERABLE control rod.concurrentwith THERMAL POWER greaterthanthe low power setpoint (LPSP)ofthe RWM AND A.4 Perform SR 3.1.1.1.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.Two or more withdrawnB.1 Be in MODE 3.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />scontrolrods stuck.C.One or more control C.1--------NOTE---------rodsinoperable for RWM may be bypassedreasonsotherthan as allowed by ConditionAor B.LCO 3.3.2.1, if required,toallow insertion of inoperable control rod and continued operation.

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Fully insert 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> inoperable control rod.AND C.2 Disarm the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CRD.(continued)

I NMP2 3.1.3-2 Amendment"'*j Control Rod OPERABILITY

3.1.3 SURVEILLANCE

REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.1.3.2 SR 3.1.3.3-------------------NOTE--------------------

Notrequiredtobe performed until 31 days after the controlrodis withdrawn and THERMAL POWER is greaterthanthe LPSP of the RWM.Insert withdrawn control rod 31 days at least one notch.I SR 3.1.3.4 NMP2 Verify each control rod scram time from fully withdrawntonotch position 05 is7 seconds.3.1.3-4 In accordance with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

Amendment-*)

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS BASES CHANGES (MARKED-UP PAGES)TSBasesPageB3

.1.3-4 TS BasesPageB3.1.3-7 TS BasesPageB3.1.3-8NineMilePoint NuclearStation,LLC August 14,2008 BASES ACTIONS Control Rod OPERABILITY B 3.1.3 A.I.A.2.A.3.and A.4 (continued) control rod separation criteriaarenotmet.

Therefore, a verification that the separation criteria are met must beperformedimmediately.

The stuck control rod separation criteriaarenot met if:a)the stuck control rod occupies a location adjacent to two"slow" control rods,b)the stuck controlrodoccupiesa location adjacenttoone"slow" control rod, andtheone"slow" control rod is also adjacent to another"slow" controlrod,orc)if the stuck control rod occupies a location adjacenttoone"slow" control rod when there is another pair of"slow" controlrodselsewhereinthecore adjacenttoone another.The description of"slow" control rods isprovidedin LCD 3.1.4,"Control Rod ScramTimes."In addition, the associated control rod drivemustbedisarmed within2hours.The allowed Completion Timeof2hours is acceptable, considering the reactor can stillbeshut down, assuming no additional control rods fail to insert, and provides a reasonable amount oftimetoperformtheRequiredActionin an orderly manner.The control rod must be isolated frombothscram and normal insert and withdraw pressure.Isolating the control rod from scram and normal insert and withdraw pressure prevents damagetothe CROM or reactor internals.

The control rod isolation method should also ensure coolingwatertothe CRO is maintained.Monitoringofthe insertion capability for each withdrawn control rod must also be performed within24hours from discoveryofCondition A concurrent with THERMAL POWER greaterthanthe low (LPSP)of the RWM.SR 3.1.3.2SR 3.1.3.3 periodic tests of the control rod insertion capabilityofwithdrawn control rods.Testing each withdrawn control rod ensures that a genericproblemdoesnot exist.This Completion Time also allows for an exceptiontothe normal"timezero" forbeginningtheallowedoutagetime"clock." TheRequiredActionA.3 Completion Timeonlybegins upon discovery of Condition A concurrent with THERMAL POWER greater than the actual LPSP of the RWM, sincethenotch insertions maynotbe compatiblewiththe requirementsofrod pattern control (LCD 3.1.6)and the RWM (LCD 3.3.2.1).TheallowedCompletion Time provides a reasonabletimeto test the control rods , considering the potential foraneedtoreduce powertoperform the tests.(continued)

NMP2 B 3.1.3-4 Revi s ion.e; Control Rod OPERABILITY B 3.1.3 BASES ACTIONS E.1 (continued)

If anyRequiredAction and associated Completion Time of Condition A, C,orDarenot metornineor more inoperable control rods exist, the plant mustbebroughttoa MODE in which the LCOdoesnotapply.

To achieve this status, the plant mustbebroughtto MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.This ensures all insertable controlrodsare inserted and places the reactorina condition thatdoesnot require the active function (i.e., scram)ofthe control rods.The number of control rods permittedtobe inoperable when operating above 10%RTP (i.e., no CRDA considerations)couldbe more thanthevalue specified, but the occurrenceofa large number of inoperable controlrodscouldbe indicativeofa generic problem, and investigation and resolutionofthe potential problemshouldbe undertaken.

The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditionsinan orderly manner and without challenging plant systems.(continued)

SURVEILLANCE REQUIREMENTS SR 3.1.3.1 The positionofeach control rod must be determined, toensureadequate information on control rod position is availabletothe operator for determining control rod OPERABILITY and controlling rod patterns.Controlrod position maybedetermined bytheuseof OPERABLE position indicators, by moving controlrodstoa positionwithan OPERABLE indicator, (full-in, full-out, or numeric indicator), by verifying the indicatorsonenotch"out" and onenotch"in"are OPERABLE, or bytheuseof other appropriate methods.The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is based on operating experience relatedtoexpectedchangesin control rod position and the availability of control rod position indications in the control room.-SR aRe-SR 3.1.3.3 I-L-hJ\{No"t'e5R 3.'.3.a hfls ce e JControlrod insertion capability is demonstrated by inserting each partially or fully withdrawn controlrodat least one notch and observing that the control rod moves.The control rod maythenbe returned to its original position.Thisensuresthe control rod is not stuck andfreeto insert on a scram signal.not required when THERMAL POWER is lh I S SuRve, u,

'I S NMP2 B 3.1.3-7 Revi s i on..Q-J BASES SURVEILLANCE REQUIREMENTS Control Rod OPERABILITY B 3.1.3 SR aRS SR 3.1.3.3 (continued) actual LPSPofthe RWM sincethenotch insertions maynotbecompatiblewiththe requirementsofthe banked positionwithdrawalsequence (BPWS)(LCD 3.1.6)and the RWM (LCD 3.3.2.1).TAe 7 day sf J.l.J.2 is eases eR sperating related te tAe cAaRges lA eRD fwll¥witRQraWR cSRtrel regs, Partiilly witRQraWR fods are tested at a 31 gay gases SR tRe redijctieR to allew tAe ceRtrel rod* aRS cSRsideriRg large testiRg of SR 3.1.3.4 Verifying the scramtimeforeach controlrodtonotch position 05 is7secondsprovides reasonable assurance that the control rod will insert when requiredduringa DBA or transient, thereby completing its shutdown function.This SR is performed in conjunctionwiththe control rod scram time testing of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4.The LOGIC SYSTEM FUNCTIONAL TEST in LCD 3.3.1.1,"Reactor Protection System (RPS)Instrumentation," and the functional testing of SDV vent and drainvalvesin LCD 3.1.8,"Scram Discharge Volume (SOV)Vent andDrainValves,"overlap this Surveillance to provide complete testingofthe assumed safety function.The associatedFrequenciesare acceptable, considering the more frequent testingperformedtodemonstrate other aspects of control rod OPERABILITY and operating experience, which shows scramtimesdonot significantly changeoveran operating cycle.(continued) r , r NMP2 B 3.1.3-8 Rev is i ATTACHMENT 4

SUMMARY

OF REGULATORY COMMITMENTSMADEIN THIS SUBMITTALNineMile Point Nuclear Station, LLC August14,2008 ATTACHMENT 4

SUMMARY

OF REGULATORY COMMITMENTS MADE IN mrs SUBMITTAL LIST OF REGULATORY COMMITMENTS The following table identifies those actions committedtoby NMPNSinthis document.Any other statementsinthis submittal are provided for information purposesandarenot consideredtobe regulatory commitments.

Please direct questions regarding these commitmentstoT.F.Syrell, Licensing Director , at (315)349-5219.REGULATORY COMMITMENT DUE DATE NMPNS will establish the Technical Specifications Bases for This commitment will beTSB3.1.3 consistent with those shown in TSTF-475, implemented within60daysfrom Revision 1,"Control Rod Notch Testing Frequency and SRMthedate of the approval of the Insert Control Rod Action" as describedinthe license proposed amendment.

amendment request.1 of 1