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| {{#Wiki_filter:ACCELERATED DIK+BUTION DEMONSTR+OAI SYFI'EM~~REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR-8901120447 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DIK+BUTION DEMONSTR+OAI SYFI'EM~~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR-8901120447 DOC.DATE: 88/12/30'OTARIZED: |
| 88/12/30'OTARIZED: | | NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P. |
| NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Indiana&05000315AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendtoLicenseDPR-58,modifying TechSpec4.1.1.5remintempforcriticality. | | Application for amend to License DPR-58,modifying Tech Spec 4.1.1.5 re min temp for criticality. |
| DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR JENCLQSIZE:7~TITLE:ORSubmittal: | | DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL Q SIZE: 7~TITLE: OR Submittal: |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LASTANG,JINTERNAL:
| | General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 0 1.1 1 1 1 1 1 1 1 0 1 1 1 1 1.1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 NUDOC-BSTRACT G F g 01 NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE'ro ALL"RIDS" RECIPXZmS. |
| ARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DEST/SICB NRR/PMAS/ILRB12 OGC/HDS1RES/DSIR/EIB EXTERNAL: | | (/d cg g/<~~2.9(~g~h D S PZZASE HELP US K)REDUCE WIPE!CGHIACZ'%HE DOCUMEÃZ CONTROL DESKi ROOM P1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRZKITION LISTS FOR DOCGKBTZS YOU DGNiT NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 IMEHANll NlCMGAN ROMEO AEP:NRC:1067A 10 CFR 50.90 Donald C.Cook Nuclear Plant Unit 1 Docket No.50-315 ll License No.DPR-58 SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGES FOR REDUCED TEMPERATURE AND PRESSURE PROGRAM U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley December 30, 1988 |
| LPDRNSICCOPIESLTTRENCL1011101.11111111011111.1RECIPIENT IDCODE/NAME PD3-1PDNRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8ENRR/DOEA/TSB 11NUDOC-BSTRACTGFg01NRCPDRCOPIESLTTRENCL2211111111111111NOTE'roALL"RIDS"RECIPXZmS.
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| (/dcgg/<~~2.9(~g~hDSPZZASEHELPUSK)REDUCEWIPE!CGHIACZ'%HEDOCUMEÃZCONTROLDESKiROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRZKITION LISTSFORDOCGKBTZS YOUDGNiTNEED!TOTALNUMBEROFCOPIESREQUIRED: | |
| LTTR20ENCL17 IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216IMEHANllNlCMGANROMEOAEP:NRC:1067A 10CFR50.90DonaldC.CookNuclearPlantUnit1DocketNo.50-315llLicenseNo.DPR-58SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGESFORREDUCEDTEMPERATURE ANDPRESSUREPROGRAMU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyDecember30,1988
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| ==DearDr.Hurley:== | | ==Dear Dr.Hurley:== |
| Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnit1.Specifically, weareproposing tomodifyT/S4.1.1.5(MinimumTemperature forCriticality) suchthatthetemperature belowwhichthereactorcoolantsystemaveragetemperature mustbemonitored every30minutesisreducedfrom551Fto545F.ThechangeisdesiredsinceweplantooperatetheupcomingUnit1Cycle11atreducedtemperature andpressure(RTP)conditions.
| | This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant Unit 1.Specifically, we are proposing to modify T/S 4.1.1.5 (Minimum Temperature for Criticality) such that the temperature below which the reactor coolant system average temperature must be monitored every 30 minutes is reduced from 551 F to 545 F.The change is desired since we plan to operate the upcoming Unit 1 Cycle 11 at reduced temperature and pressure (RTP)conditions. |
| TheRTPprogramsupportsarangeofnominalfullpowerTavgfrom547Fto567.8F.TheexpectedfullpowerTavgforCyclellis0approximately 550F,reducedfromthepresent(non-RTP) fullpower0Tavgof567.8F.Plantoperation withthepresentT/Sisnotprecluded undertheRTPconditions; however,theT/Sdoesplaceaburdenontheplantoperators sinceTavgwillhavetobemonitored every30minutesatessentially alltimeswhenthereactoriscritical.
| | The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The expected full power Tavg for Cycle ll is 0 approximately 550 F, reduced from the present (non-RTP)full power 0 Tavg of 567.8 F.Plant operation with the present T/S is not precluded under the RTP conditions; however, the T/S does place a burden on the plant operators since Tavg will have to be monitored every 30 minutes at essentially all times when the reactor is critical.This letter supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted the analyses that support RTP operation, as well as the T/S changes necessary to allow plant operation. |
| Thislettersupplements ourletterAEP:NRC:1067, datedOctober14,1988.Thatlettertransmitted theanalysesthatsupportRTPoperation, aswellastheT/Schangesnecessary toallowplantoperation.
| | We request that your review of this request be completed by April 15, 1989, which is the same date requested in AEP:NRC:1067 for approval of the RTP analyses and associated T/S changes.pic'l pDR ADQCK 05OOo P'g,eel: 4i~~I os%~ |
| Werequestthatyourreviewofthisrequestbecompleted byApril15,1989,whichisthesamedaterequested inAEP:NRC:1067 forapprovaloftheRTPanalysesandassociated T/Schanges.pic'lpDRADQCK05OOoP'g,eel:4i~~Ios%~
| | Dr.T.E.Hurley-2-AEP:NRC:1067A Additional details about the change and our evaluation concerning significant hazards consideration are contained in Attachment 1 to this letter.The proposed revised T/S change is found in Attachment 2.We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that, may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee, and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission, and Mr.George Bruchmann of the Michigan Department of Public Health.Pursuant to the requirements of 10 CFR 170'2(c), we have enclosed an application fee of$150.00 for the proposed amendments. |
| Dr.T.E.Hurley-2-AEP:NRC:1067A Additional detailsaboutthechangeandourevaluation concerning significant hazardsconsideration arecontained inAttachment 1tothisletter.TheproposedrevisedT/SchangeisfoundinAttachment 2.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthat,maybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | | This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee, andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
| | Sincerely, M.P.Alexich Vice President MPA/eh Attachments cc: D.H.Williams, Jr.W.G.Smith, Jr.-Bridgman R.C.'allen G.Charnoff G.Bruchmann A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:1067A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C.COOK NUCLEAR PLANT UNIT 1 |
| copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission, andMr.GeorgeBruchmann oftheMichiganDepartment ofPublicHealth.Pursuanttotherequirements of10CFR170'2(c),wehaveenclosedanapplication feeof$150.00fortheproposedamendments.
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| Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
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| Sincerely, M.P.AlexichVicePresident MPA/ehAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanR.C.'allenG.CharnoffG.Bruchmann A.B.Davis-RegionIIINRCResidentInspector | |
| -Bridgman ATTACHMENT 1TOAEP:NRC:1067A DESCRIPTION AND10CFR50.92SIGNIFICANT HAZARDSEVALUATION FORCHANGESTOTHETECHNICAL SPECIFICATIONS FORTHEDONALDC.COOKNUCLEARPLANTUNIT1 | |
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| ATTACHMENT 1TOAEP:NRC:1067A Page1DescritionofChaneUnit1Technical Specification (T/S)4.1.1.5.b (MinimumTemperature forCriticality) aspresently writtenrequiresverification thatthereactorcoolantsystemTavgis>541Fatleastonceper30minuteswhenthereactoriscriticalandTavgislessthan551F.Weareproposing torevisetherequirement suchthatTavgmustbeverifiedevery30minuteswhenTavgisbelow/(545ForwhenthelowTavgalarmisinoperable. | | ATTACHMENT 1 TO AEP:NRC:1067A Page 1 Descri tion of Chan e Unit 1 Technical Specification (T/S)4.1.1.5.b (Minimum Temperature for Criticality) as presently written requires verification that the reactor coolant system Tavg is>541 F at least once per 30 minutes when the reactor is critical and Tavg is less than 551 F.We are proposing to revise the requirement such that Tavg must be verified every 30 minutes when Tavg is below/(545 F or when the low Tavg alarm is inoperable. |
| 0ReasonfortheChaneUnderpresentoperating conditions, fullpowerTavgis567.8F.0FortheupcomingUnit1Cycle11,however,weareplanningtooperatetheplantunderreducedtemperature andpressure(RTP)conditions.
| | 0 Reason for the Chan e Under present operating conditions, full power Tavg is 567.8 F.0 For the upcoming Unit 1 Cycle 11, however, we are planning to operate the plant under reduced temperature and pressure (RTP)conditions. |
| TheRTPprogramsupportsarangeofnominalfullpowerTavgfrom547Fto567.8F.ThefullpowerTavgwillbeloweredtoapproximately 550FforUnit1Cyclell.Sincethis0isbelow551F,thepresentwordingofT/S4.1.1.5.b wouldrequirethatTavgbeverifiedtobeabove541F(theminimumtemperature 0forcriticality) every30minutesessentially alltimeswhenthereactoriscritical.
| | The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The full power Tavg will be lowered to approximately 550 F for Unit 1 Cycle ll.Since this 0 is below 551 F, the present wording of T/S 4.1.1.5.b would require that Tavg be verified to be above 541 F (the minimum temperature 0 for criticality) every 30 minutes essentially all times when the reactor is critical.Although this does not preclude operation under RTP conditions, it is burdensome and will distract the operators from other duties.This request supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted. |
| Althoughthisdoesnotprecludeoperation underRTPconditions, itisburdensome andwilldistracttheoperators fromotherduties.Thisrequestsupplements ourletterAEP:NRC:1067, datedOctober14,1988.Thatlettertransmitted.
| | the analyses which support RTP operation, as well as the T/S changes that are necessary in order to implement the RTP program.Justification for Chan e The proposed change does not alter the minimum temperature for criticality. |
| theanalyseswhichsupportRTPoperation, aswellastheT/Schangesthatarenecessary inordertoimplement theRTPprogram.Justification forChaneTheproposedchangedoesnotaltertheminimumtemperature forcriticality.
| | Tavg must be maintained above 541 F any time the reactor is critical.Should Tavg drop below 541 F, the action statement for T/S 3.1.1.5 requires that Tavg be restored above 0 541 F within 15 minutes or the unit must be placed in hot standby.T/S 4.1.1,5.b presently requires Tavg to be determined every 30 minutes when Tavg is less than 10 F above 541 F.This 10 F value is consistent with the latest revision of Westinghouse Standard T/Ss.Westinghouse has informed us the 10 F was established to protect against encroachment upon the 541 F minimum temperature 0 for criticality. |
| Tavgmustbemaintained above541Fanytimethereactoriscritical.
| | The 10 F value is not derived from any analysis.0 The plant is equipped with a low Tavg alarm that is currently set 0 at 554 F.The low Tavg alarm is derived from the bistables that close the main feedwater control valves on low Tavg coincident with a reactor trip.This function helps protect the reactor from excessive cooldown following a reactor trip.Diversity of signals |
| ShouldTavgdropbelow541F,theactionstatement forT/S3.1.1.5requiresthatTavgberestoredabove0541Fwithin15minutesortheunitmustbeplacedinhotstandby.T/S4.1.1,5.b presently requiresTavgtobedetermined every30minuteswhenTavgislessthan10Fabove541F.This10Fvalueisconsistent withthelatestrevisionofWestinghouse StandardT/Ss.Westinghouse hasinformedusthe10Fwasestablished toprotectagainstencroachment uponthe541Fminimumtemperature 0forcriticality.
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| The10Fvalueisnotderivedfromanyanalysis.
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| 0TheplantisequippedwithalowTavgalarmthatiscurrently set0at554F.ThelowTavgalarmisderivedfromthebistables thatclosethemainfeedwater controlvalvesonlowTavgcoincident withareactortrip.Thisfunctionhelpsprotectthereactorfromexcessive cooldownfollowing areactortrip.Diversity ofsignals
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| ATTACHMENT 1TOAEP'NRC'1067A Page2forterminating mainfeedwater isprovidedviatheP-4permissive, whichtripsthemainfeedwater pumpsintheeventofareactortrip.Thefunctions associated withthelowTavgbistableandthemainfeedwater pumptriponreactortriparenotdelineated intheT/Ss.Weareproposing tolowerthelowTavgsetpoint(including thealarm)from554Fto545F.Thetemperature of545Fis00sufficiently belowtheoperating temperature tolessenthepossibility ofunnecessary.=alarms, butishighenoughtoprovidetheoperatorwithamplewarningthatTavgisapproaching the541F0minimumtemperature forcriticality. | | ATTACHMENT 1 TO AEP'NRC'1067A Page 2 for terminating main feedwater is provided via the P-4 permissive, which trips the main feedwater pumps in the event of a reactor trip.The functions associated with the low Tavg bistable and the main feedwater pump trip on reactor trip are not delineated in the T/Ss.We are proposing to lower the low Tavg setpoint (including the alarm)from 554 F to 545 F.The temperature of 545 F is 0 0 sufficiently below the operating temperature to lessen the possibility of unnecessary.=alarms, but is high enough to provide the operator with ample warning that Tavg is approaching the 541 F 0 minimum temperature for criticality. |
| LoweringthelowTavgsetpointhasminimaleffectontheresponseoftheplanttoreactortripbecause,asdiscussed above,themainfeedpumps (MFP)aretrippeddirectlyonareactortrip,viatheP-4permissive.
| | Lowering the low Tavg setpoint has minimal effect on the response of the plant to reactor trip because, as discussed above, the main feedpumps (MFP)are tripped directly on a reactor trip, via the P-4 permissive. |
| TheFSARLOCAandtransient analysesdonottakecreditforfeedwater isolation derivedfromthe'lowTavgbistable.
| | The FSAR LOCA and transient analyses do not take credit for feedwater isolation derived from the'low Tavg bistable.The function is modeled in the Westinghouse Owners Group analysis of steamline break mass and energy releases outside containment (WCAP 10961), because it is conservative to do so.Modeling of the function is conservative because it leads to earlier feedwater isolation than the other (T/S)signals that also provide feedwater isolation. |
| ThefunctionismodeledintheWestinghouse OwnersGroupanalysisofsteamline breakmassandenergyreleasesoutsidecontainment (WCAP10961),becauseitisconservative todoso.Modelingofthefunctionisconservative becauseitleadstoearlierfeedwater isolation thantheother(T/S)signalsthatalsoprovidefeedwater isolation.
| | Early termination of feedwater results in greater steam generator tube uncovery, and thus more superheating of the steam exiting the break.Lowering the low Tavg setpoint is conservative with respect to this analysis, since it will somewhat delay the feedwater isolation. |
| Earlytermination offeedwater resultsingreatersteamgenerator tubeuncovery, andthusmoresuperheating ofthesteamexitingthebreak.LoweringthelowTavgsetpointisconservative withrespecttothisanalysis, sinceitwillsomewhatdelaythefeedwater isolation.
| | We propose that the operator only be required to monitor and document Tavg on a 30-minute basis if Tavg is below the proposed low Tavg setpoint of 545 F, or if the low Tavg alarm is 0 inoperable. |
| WeproposethattheoperatoronlyberequiredtomonitoranddocumentTavgona30-minute basisifTavgisbelowtheproposedlowTavgsetpointof545F,orifthelowTavgalarmis0inoperable.
| | This will avoid the burden that monitoring Tavg every 30 minutes places on the operators, and will help ensure the operators'ttention is not diverted from more important safety functions. |
| Thiswillavoidtheburdenthatmonitoring Tavgevery30minutesplacesontheoperators, andwillhelpensuretheoperators'ttention isnotdivertedfrommoreimportant safetyfunctions.
| | Tavg will continue to be measured at least once per 12 hours in Mode 1, as required by T/S 3.2.5 (DNB Parameters). |
| Tavgwillcontinuetobemeasuredatleastonceper12hoursinMode1,asrequiredbyT/S3.2.5(DNBParameters).
| | The resetting of the Tavg alarm to 545 F will ensure the operator is warned that Tavg is encroaching upon the 541 F minimum temperature 0 for criticality. |
| Theresetting oftheTavgalarmto545FwillensuretheoperatoriswarnedthatTavgisencroaching uponthe541Fminimumtemperature 0forcriticality.
| | 10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not: |
| 10CFR50.92Evaluation Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:
| | ATTACHMENT 1 TO AEP:NRC:1067A Page 3 1)Involve a significant increase in the probability or consequences of an accident previously analyzed, 2)Create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or 3)Involve a significant reduction in a margin of safety.Criterion 1 The periodic monitoring and documenting of Tavg when the plant is operated near the minimum temperature for criticality will be reduced.However, this change will be compensated for by lowering the alarm setpoint to warn the operator of approach to the minimum temperature for criticality. |
| ATTACHMENT 1TOAEP:NRC:1067A Page31)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously | | Therefore, we do not believe our proposal will result in an increase in the probability or consequences of an accident previously analyzed.Criterion 2 The proposed T/S changes do not revise the minimum temperature for criticality of 541 F specified in T/S 3.1.1.5.The change only impacts the temperature at which Tavg must be monitored every 30 minutes.This will be compensated for by providing an alarm at a 0 Tavg of 545 F that will warn the operator that the plant is approaching the minimum temperature at which it may remain critical.Thus, we do not believe the change can result in any new or different kinds of accidents from any previously analyzed or evaluated. |
| : analyzed, 2)Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or3)Involveasignificant reduction inamarginofsafety.Criterion 1Theperiodicmonitoring anddocumenting ofTavgwhentheplantisoperatedneartheminimumtemperature forcriticality willbereduced.However,thischangewillbecompensated forbyloweringthealarmsetpointtowarntheoperatorofapproachtotheminimumtemperature forcriticality.
| | Criterion 3 The purpose of the T/S is to ensure the reactor is not critical with Tavg below 541 F, without appropriate action being taken.We will ensure that the operator is warned that Tavg is approaching the 541 F limit by lowering the low Tavg alarm setpoint to 545 F.We believe this will provide adequate assurance that the 541 F Tavg limit is protected. |
| Therefore, wedonotbelieveourproposalwillresultinanincreaseintheprobability orconsequences ofanaccidentpreviously analyzed. | | Therefore, the proposed change should not significantly reduce the margin of safety.Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing examples (48 FR 14870)of amendments considered not likely to involve significant hazards consideration. |
| Criterion 2TheproposedT/Schangesdonotrevisetheminimumtemperature forcriticality of541Fspecified inT/S3.1.1.5.Thechangeonlyimpactsthetemperature atwhichTavgmustbemonitored every30minutes.Thiswillbecompensated forbyproviding analarmata0Tavgof545Fthatwillwarntheoperatorthattheplantisapproaching theminimumtemperature atwhichitmayremaincritical. | | The sixth of these examples refers to changes that may result in some*increase to the probability or consequences of a previously analyzed accident, but the results of which are within limits established as acceptable. |
| Thus,wedonotbelievethechangecanresultinanynewordifferent kindsofaccidents fromanypreviously analyzedorevaluated. | | As discussed in the bases, the minimum temperature for criticality ensures that the reactor, instrumentation, and vessel are operated in their analyzed temperature ranges.These requirements are not I C ATTACHMENT 1 TO AEP:NRC:1067A Page 4 affected by our proposed revision to the surveillance requirements. |
| Criterion 3ThepurposeoftheT/SistoensurethereactorisnotcriticalwithTavgbelow541F,withoutappropriate actionbeingtaken.WewillensurethattheoperatoriswarnedthatTavgisapproaching the541FlimitbyloweringthelowTavgalarmsetpointto545F.Webelievethiswillprovideadequateassurance thatthe541FTavglimitisprotected. | | The change only impacts the temperature at which the operator must monitor Tavg every 30 minutes to ensure the temperature does not drop below the minimum temperature for criticality. |
| Therefore, theproposedchangeshouldnotsignificantly reducethemarginofsafety.Lastly,wenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding examples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration. | | Me will be providing an alarm that will alert the operator that the temperature is approaching its minimum Tavg limit.Therefore, we believe the example cited is applicable and that the changes should not involve a significant hazards consideration.}} |
| Thesixthoftheseexamplesreferstochangesthatmayresultinsome*increasetotheprobability orconsequences ofapreviously analyzedaccident, buttheresultsofwhicharewithinlimitsestablished asacceptable.
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| Asdiscussed inthebases,theminimumtemperature forcriticality ensuresthatthereactor,instrumentation, andvesselareoperatedintheiranalyzedtemperature ranges.Theserequirements arenot IC ATTACHMENT 1TOAEP:NRC:1067A Page4affectedbyourproposedrevisiontothesurveillance requirements.
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| Thechangeonlyimpactsthetemperature atwhichtheoperatormustmonitorTavgevery30minutestoensurethetemperature doesnotdropbelowtheminimumtemperature forcriticality.
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| Mewillbeproviding analarmthatwillalerttheoperatorthatthetemperature isapproaching itsminimumTavglimit.Therefore, webelievetheexamplecitedisapplicable andthatthechangesshouldnotinvolveasignificant hazardsconsideration.}}
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
ACCELERATED DIK+BUTION DEMONSTR+OAI SYFI'EM~~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR-8901120447 DOC.DATE: 88/12/30'OTARIZED:
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License DPR-58,modifying Tech Spec 4.1.1.5 re min temp for criticality.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL Q SIZE: 7~TITLE: OR Submittal:
General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 0 1.1 1 1 1 1 1 1 1 0 1 1 1 1 1.1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 NUDOC-BSTRACT G F g 01 NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE'ro ALL"RIDS" RECIPXZmS.
(/d cg g/<~~2.9(~g~h D S PZZASE HELP US K)REDUCE WIPE!CGHIACZ'%HE DOCUMEÃZ CONTROL DESKi ROOM P1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRZKITION LISTS FOR DOCGKBTZS YOU DGNiT NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 IMEHANll NlCMGAN ROMEO AEP:NRC:1067A 10 CFR 50.90 Donald C.Cook Nuclear Plant Unit 1 Docket No.50-315 ll License No.DPR-58 SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGES FOR REDUCED TEMPERATURE AND PRESSURE PROGRAM U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley December 30, 1988
Dear Dr.Hurley:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant Unit 1.Specifically, we are proposing to modify T/S 4.1.1.5 (Minimum Temperature for Criticality) such that the temperature below which the reactor coolant system average temperature must be monitored every 30 minutes is reduced from 551 F to 545 F.The change is desired since we plan to operate the upcoming Unit 1 Cycle 11 at reduced temperature and pressure (RTP)conditions.
The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The expected full power Tavg for Cycle ll is 0 approximately 550 F, reduced from the present (non-RTP)full power 0 Tavg of 567.8 F.Plant operation with the present T/S is not precluded under the RTP conditions; however, the T/S does place a burden on the plant operators since Tavg will have to be monitored every 30 minutes at essentially all times when the reactor is critical.This letter supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted the analyses that support RTP operation, as well as the T/S changes necessary to allow plant operation.
We request that your review of this request be completed by April 15, 1989, which is the same date requested in AEP:NRC:1067 for approval of the RTP analyses and associated T/S changes.pic'l pDR ADQCK 05OOo P'g,eel: 4i~~I os%~
Dr.T.E.Hurley-2-AEP:NRC:1067A Additional details about the change and our evaluation concerning significant hazards consideration are contained in Attachment 1 to this letter.The proposed revised T/S change is found in Attachment 2.We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that, may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee, and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission, and Mr.George Bruchmann of the Michigan Department of Public Health.Pursuant to the requirements of 10 CFR 170'2(c), we have enclosed an application fee of$150.00 for the proposed amendments.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M.P.Alexich Vice President MPA/eh Attachments cc: D.H.Williams, Jr.W.G.Smith, Jr.-Bridgman R.C.'allen G.Charnoff G.Bruchmann A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:1067A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C.COOK NUCLEAR PLANT UNIT 1
ATTACHMENT 1 TO AEP:NRC:1067A Page 1 Descri tion of Chan e Unit 1 Technical Specification (T/S)4.1.1.5.b (Minimum Temperature for Criticality) as presently written requires verification that the reactor coolant system Tavg is>541 F at least once per 30 minutes when the reactor is critical and Tavg is less than 551 F.We are proposing to revise the requirement such that Tavg must be verified every 30 minutes when Tavg is below/(545 F or when the low Tavg alarm is inoperable.
0 Reason for the Chan e Under present operating conditions, full power Tavg is 567.8 F.0 For the upcoming Unit 1 Cycle 11, however, we are planning to operate the plant under reduced temperature and pressure (RTP)conditions.
The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The full power Tavg will be lowered to approximately 550 F for Unit 1 Cycle ll.Since this 0 is below 551 F, the present wording of T/S 4.1.1.5.b would require that Tavg be verified to be above 541 F (the minimum temperature 0 for criticality) every 30 minutes essentially all times when the reactor is critical.Although this does not preclude operation under RTP conditions, it is burdensome and will distract the operators from other duties.This request supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted.
the analyses which support RTP operation, as well as the T/S changes that are necessary in order to implement the RTP program.Justification for Chan e The proposed change does not alter the minimum temperature for criticality.
Tavg must be maintained above 541 F any time the reactor is critical.Should Tavg drop below 541 F, the action statement for T/S 3.1.1.5 requires that Tavg be restored above 0 541 F within 15 minutes or the unit must be placed in hot standby.T/S 4.1.1,5.b presently requires Tavg to be determined every 30 minutes when Tavg is less than 10 F above 541 F.This 10 F value is consistent with the latest revision of Westinghouse Standard T/Ss.Westinghouse has informed us the 10 F was established to protect against encroachment upon the 541 F minimum temperature 0 for criticality.
The 10 F value is not derived from any analysis.0 The plant is equipped with a low Tavg alarm that is currently set 0 at 554 F.The low Tavg alarm is derived from the bistables that close the main feedwater control valves on low Tavg coincident with a reactor trip.This function helps protect the reactor from excessive cooldown following a reactor trip.Diversity of signals
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ATTACHMENT 1 TO AEP'NRC'1067A Page 2 for terminating main feedwater is provided via the P-4 permissive, which trips the main feedwater pumps in the event of a reactor trip.The functions associated with the low Tavg bistable and the main feedwater pump trip on reactor trip are not delineated in the T/Ss.We are proposing to lower the low Tavg setpoint (including the alarm)from 554 F to 545 F.The temperature of 545 F is 0 0 sufficiently below the operating temperature to lessen the possibility of unnecessary.=alarms, but is high enough to provide the operator with ample warning that Tavg is approaching the 541 F 0 minimum temperature for criticality.
Lowering the low Tavg setpoint has minimal effect on the response of the plant to reactor trip because, as discussed above, the main feedpumps (MFP)are tripped directly on a reactor trip, via the P-4 permissive.
The FSAR LOCA and transient analyses do not take credit for feedwater isolation derived from the'low Tavg bistable.The function is modeled in the Westinghouse Owners Group analysis of steamline break mass and energy releases outside containment (WCAP 10961), because it is conservative to do so.Modeling of the function is conservative because it leads to earlier feedwater isolation than the other (T/S)signals that also provide feedwater isolation.
Early termination of feedwater results in greater steam generator tube uncovery, and thus more superheating of the steam exiting the break.Lowering the low Tavg setpoint is conservative with respect to this analysis, since it will somewhat delay the feedwater isolation.
We propose that the operator only be required to monitor and document Tavg on a 30-minute basis if Tavg is below the proposed low Tavg setpoint of 545 F, or if the low Tavg alarm is 0 inoperable.
This will avoid the burden that monitoring Tavg every 30 minutes places on the operators, and will help ensure the operators'ttention is not diverted from more important safety functions.
Tavg will continue to be measured at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Mode 1, as required by T/S 3.2.5 (DNB Parameters).
The resetting of the Tavg alarm to 545 F will ensure the operator is warned that Tavg is encroaching upon the 541 F minimum temperature 0 for criticality.
10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:
ATTACHMENT 1 TO AEP:NRC:1067A Page 3 1)Involve a significant increase in the probability or consequences of an accident previously analyzed, 2)Create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or 3)Involve a significant reduction in a margin of safety.Criterion 1 The periodic monitoring and documenting of Tavg when the plant is operated near the minimum temperature for criticality will be reduced.However, this change will be compensated for by lowering the alarm setpoint to warn the operator of approach to the minimum temperature for criticality.
Therefore, we do not believe our proposal will result in an increase in the probability or consequences of an accident previously analyzed.Criterion 2 The proposed T/S changes do not revise the minimum temperature for criticality of 541 F specified in T/S 3.1.1.5.The change only impacts the temperature at which Tavg must be monitored every 30 minutes.This will be compensated for by providing an alarm at a 0 Tavg of 545 F that will warn the operator that the plant is approaching the minimum temperature at which it may remain critical.Thus, we do not believe the change can result in any new or different kinds of accidents from any previously analyzed or evaluated.
Criterion 3 The purpose of the T/S is to ensure the reactor is not critical with Tavg below 541 F, without appropriate action being taken.We will ensure that the operator is warned that Tavg is approaching the 541 F limit by lowering the low Tavg alarm setpoint to 545 F.We believe this will provide adequate assurance that the 541 F Tavg limit is protected.
Therefore, the proposed change should not significantly reduce the margin of safety.Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing examples (48 FR 14870)of amendments considered not likely to involve significant hazards consideration.
The sixth of these examples refers to changes that may result in some*increase to the probability or consequences of a previously analyzed accident, but the results of which are within limits established as acceptable.
As discussed in the bases, the minimum temperature for criticality ensures that the reactor, instrumentation, and vessel are operated in their analyzed temperature ranges.These requirements are not I C ATTACHMENT 1 TO AEP:NRC:1067A Page 4 affected by our proposed revision to the surveillance requirements.
The change only impacts the temperature at which the operator must monitor Tavg every 30 minutes to ensure the temperature does not drop below the minimum temperature for criticality.
Me will be providing an alarm that will alert the operator that the temperature is approaching its minimum Tavg limit.Therefore, we believe the example cited is applicable and that the changes should not involve a significant hazards consideration.