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| {{#Wiki_filter:CATEGORY1REGULATEINFORMATION DISTRIBUTIOh SYSTEM(RIDS)ACCESSION NBR:9806100264 | | {{#Wiki_filter:CATEGORY 1 REGULATE INFORMATION DISTRIBUTIOh SYSTEM (RIDS)ACCESSION NBR:9806100264 |
| 'OC.DATE: | | 'OC.DATE: 98/06/04 NOTARIZED: |
| 98/06/04NOTARIZED: | | YES DOCKET¹FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME" AUTHOR AFFILIATION MECREDY,R.C. |
| YESDOCKET¹FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAME"AUTHORAFFILIATION MECREDY,R.C.
| | Rochester Gas 8 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING, G.S. |
| Rochester Gas8ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Providesmoredetaileddescription ofbasisforproposedsetpointlanguagecontained in970929application foramend,per980428,0513 R20R0603telconsw/NRCrechangetomainsteamisolation setpoint.Revised TSpagesencl.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
| | Provides more detailed description of basis for proposed setpoint language contained in 970929 application for amend, per 980428,0513 R 20 R 0603 telcons w/NRC re change to main steam isolation setpoint.Revised TS pages encl.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72)
| | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) |
| .E05000244GRECIPIENT IDCODE/NAME PD1-1LAVISSING,G. | | .E 05000244 G RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G. |
| 01EXTENOACINTERNAL:
| | 01 EXTE NOAC INTERNAL: ILE CE DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 0 D 0 E N NOTE TO ALL"RIDS" RECIPIENTS: |
| ILECEDE/EMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT COPIESLTTRENCL11111111111111RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3NRCPDRCOPIESLTTRENCL1111111110110D0ENNOTETOALL"RIDS"RECIPIENTS:
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 II 1V P 1 r I ll C3 AND ROCHESTER GAS AND ELECTRIC CORPORATION |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
| | ~89 EASTAVENLIE, ROCHESTER, N.Y 14649-000I ARFA CODE716 546-270O ROBERT C.MECREDY Vice President Nvdeor Operotions June 4, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 |
| LTTR13ENCL12 II1VP1rIll C3ANDROCHESTER GASANDELECTRICCORPORATION
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| ~89EASTAVENLIE, ROCHESTER, N.Y14649-000I ARFACODE716546-270OROBERTC.MECREDYVicePresident NvdeorOperotions June4,1998U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| MainSteamIsolation SetpointLicenseAmendment RequestRochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Main Steam Isolation Setpoint License Amendment Request Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==Reference:== | | ==Reference:== |
| | (a)Letter from.R.C.Mecredy, RG&E, to G.S.Vissing, NRC, |
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| (a)Letterfrom.R.C. | | ==Subject:== |
| Mecredy,RG&E,toG.S.Vissing,NRC,
| | Application for Amendment to I"acili(y Operating License, Change to Main Steam Isolation Setpoint (LCO Table 3.3.2-l, Function 4.d), dated September 29, 1997.(b)Conference calls of April 28, May 13 and 20, and June 3, 1998 between RG&E and NRC. |
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| ==Subject:== | | ==Dear Mr.Vissing In Reference (a),== |
| Application forAmendment toI"acili(y Operating License,ChangetoMainSteamIsolation Setpoint(LCOTable3.3.2-l,Function4.d),datedSeptember 29,1997.(b)Conference callsofApril28,May13and20,andJune3,1998betweenRG&EandNRC.DearMr.VissingInReference (a),RG&Esubmitted aproposedchangetotheImprovedTechnical Specification (ITS)setpointformainsteamisolation (Table3.3.2-1,Function4.d).Recently, RG&EandtheNRCdiscussed thelanguagebeingproposedfortherevisedsetpointandwhythisdifferedfromStandardITS(Reference (b)).ThepurposeofthisletteristodescribeinmoredetailthebasisfortheproposedsetpointlanguageandtorevisetheproposedITSbasestoprovidefurtherclarification.
| | RG&E submitted a proposed change to the Improved Technical Specification (ITS)setpoint for main steam isolation (Table 3.3.2-1, Function 4.d).Recently, RG&E and the NRC discussed the language being proposed for the revised setpoint and why this differed from Standard ITS (Reference (b)).The purpose of this letter is to describe in more detail the basis for the proposed setpoint language and to revise the proposed ITS bases to provide further clarification. |
| Thefollowing tableillustrates thedifferences betweentheRG&EproposedchangestoITSTable3.3.2-1,FunctionDandthoseinStandardITS:TripSetpoints0.4E6ibm/hr1005psig~GGdAllowable Values0.66E6ibm/hr1005psigStandardITSs[25%]offullsteamflowatnoloadsteampressures[]offullsteamfiowatnoloadsteampressure(s-'lA~P,
| | The following table illustrates the differences between the RG&E proposed changes to ITS Table 3.3.2-1, Function D and those in Standard ITS: Trip Setpoint s 0.4E6 ibm/hr1005 psig~GG d Allowable Value s 0.66E6 ibm/hr1005 psig Standard ITS s[25%]of full steam flow at no load steam pressure s[]of full steam fiow at no load steam pressure (s-'lA~P,.9806i00264 980604'DR ADOCK 05000244 P PDR As can be seen, the primary differences are: (1)use of a specific flowrate versus a percentage of full steam flow,.and (2)use of a specific pressure versus"no load steam pressure." These differences are discussed in detail below.I Attachment I provides a simplified figure of one of the four main steam flow instrument loops.As can be seen on this figure, FT-464 is a differential pressure transmitter whose signal is sent to three functions. |
| .9806i00264 980604'DR ADOCK05000244PPDR Ascanbeseen,theprimarydifferences are:(1)useofaspecificflowrateversusapercentage offullsteamflow,.and (2)useofaspecificpressureversus"noloadsteampressure." | | The first signal goes to main control board indicator FI-464 after being compensated by main steam pressure (PM-464A)and processed by a square root extractor (FM-464B)and a repeater (FM-464C). |
| Thesedifferences arediscussed indetailbelow.IAttachment Iprovidesasimplified figureofoneofthefourmainsteamflowinstrument loops.Ascanbeseenonthisfigure,FT-464isadifferential pressuretransmitter whosesignalissenttothreefunctions.
| | The second signal goes to an alarm (FC-464A)and then to two bistables for the high steam flow and high-high steam flow functions listed in ITS Table 3.3.2-1, Function 4.The third and last signal goes to a repeater (FM-464D)and to the advanced digital feedwater control system (ADFCS).The only output signal from FT-464 which is pressure compensated is that for the main control board indication. |
| Thefirstsignalgoestomaincontrolboardindicator FI-464afterbeingcompensated bymainsteampressure(PM-464A) andprocessed byasquarerootextractor (FM-464B)andarepeater(FM-464C).
| | The output signal to the high and high-high steam flow bistables via alarm FC-464A is a direct value from the differential pressure transmitter. |
| Thesecondsignalgoestoanalarm(FC-464A) andthentotwobistables forthehighsteamflowandhigh-high steamflowfunctions listedinITSTable3.3.2-1,Function4.Thethirdandlastsignalgoestoarepeater(FM-464D) andtotheadvanceddigitalfeedwater controlsystem(ADFCS).TheonlyoutputsignalfromFT-464whichispressurecompensated isthatforthemaincontrolboardindication.
| | However, the bistable trip setpoints do have a pressure compensation"adjustment". |
| Theoutputsignaltothehighandhigh-high steamflowbistables viaalarmFC-464Aisadirectvaluefromthedifferential pressuretransmitter.
| | That is, the bistable trip setpoint matches the ITS specified conditions of 0.4E6 Ibm/hr N 1005 psig.This is accomplished by identifying the required signal to main control board indicator FI-464 for steam line flow/pressure conditions of 0.4E6 Ibm/hr1005 psig.This signal value is traced back through the logic shown in Attachment I (repeater, square root extractor, and steam pressure multiplier) to identify the required output of the differential pressure transmitter for FT-464.This calculated output signal from the differential pressure transmitter is what is used for the bistable setpoint;hence, the pressure compensation"adjustment". |
| However,thebistabletripsetpoints dohaveapressurecompensation "adjustment". | | Attachment II provides additional details.As described above, the bistable setpoints are based on a specific set of plant steam flow and pressure conditions. |
| Thatis,thebistabletripsetpointmatchestheITSspecified conditions of0.4E6Ibm/hrN1005psig.Thisisaccomplished byidentifying therequiredsignaltomaincontrolboardindicator FI-464forsteamlineflow/pressure conditions of0.4E6Ibm/hr1005psig.ThissignalvalueistracedbackthroughthelogicshowninAttachment I(repeater, squarerootextractor, andsteampressuremultiplier) toidentifytherequiredoutputofthedifferential pressuretransmitter forFT-464.Thiscalculated outputsignalfromthedifferential pressuretransmitter iswhatisusedforthebistablesetpoint; hence,thepressurecompensation "adjustment".
| | Consequently, the Ginna Station ITS must specify these plant conditions versus the Standard ITS terms of"%full steam flow" and"no load steam pressure" even though the Ginna specified conditions are essentially equivalent to the Standard ITS terms.The accident analysis also uses these same plant conditions. |
| Attachment IIprovidesadditional details.Asdescribed above,thebistablesetpoints arebasedonaspecificsetofplantsteamflowandpressureconditions. | | That is, for those analyzed steam line breaks requiring automatic steam line isolation, the accident analysis assumes a main steam isolation signal is generated immediately aiba a safety injection setpoint is reached.The analysis is then reviewed afterwards to ensure that the remaining coincident main steam isolation parameters listed in ITS Table 3.3.2-1 are also met.For the case of small steam line breaks, the accident analysis verifies that the main steam flow is>0.66E6 Ibm/hr with pressure s 1005 psig prior to reaching safety injection setpoints. |
| Consequently, theGinnaStationITSmustspecifytheseplantconditions versustheStandardITStermsof"%fullsteamflow"and"noloadsteampressure" eventhoughtheGinnaspecified conditions areessentially equivalent totheStandardITSterms.Theaccidentanalysisalsousesthesesameplantconditions. | | Higher steam flowrates or lower pressures would generate a higher differential pressure across the flow transmitter ensuring that the bistable setpoint is reached.Since normal full power conditions result in steam flows and pressures of approximately 3.3 ibm/hr and 730 psig respectively, the bistables for ITS Table 3.3.2-1, Function 4.d are normally tripped.Therefore, the use of a specific flowrate and pressure remains consistent with the accident analysis and reflects that the bistable setpoint does not automatically change if steam conditions were to change.As such, the Ginna Station ITS is different from Standard ITS in implementation, but not in intent. |
| Thatis,forthoseanalyzedsteamlinebreaksrequiring automatic steamlineisolation, theaccidentanalysisassumesamainsteamisolation signalisgenerated immediately aibaasafetyinjection setpointisreached.Theanalysisisthenreviewedafterwards toensurethattheremaining coincident mainsteamisolation parameters listedinITSTable3.3.2-1arealsomet.Forthecaseofsmallsteamlinebreaks,theaccidentanalysisverifiesthatthemainsteamflowis>0.66E6Ibm/hrwithpressures1005psigpriortoreachingsafetyinjection setpoints.
| | The bases originally submitted in Reference (a)are revised in Attachment 3 to provide this additional discussion. |
| Highersteamflowrates orlowerpressures wouldgenerateahigherdifferential pressureacrosstheflowtransmitter ensuringthatthebistablesetpointisreached.Sincenormalfullpowerconditions resultinsteamflowsandpressures ofapproximately 3.3ibm/hrand730psigrespectively, thebistables forITSTable3.3.2-1,Function4.darenormallytripped.Therefore, theuseofaspecificflowrateandpressureremainsconsistent withtheaccidentanalysisandreflectsthatthebistablesetpointdoesnotautomatically changeifsteamconditions weretochange.Assuch,theGinnaStationITSisdifferent fromStandardITSinimplementation, butnotinintent.
| | This replaces in its entirety, the bases provided in Attachment II to Reference (a).In addition, based on discussions during the June 3, 1998 conference call, an issue was identified with respect to the presentation style of ITS Table 3.3.2-1.Specifically, the Trip Setpoint column of this table is actually a nominal setpoint value (with tolerance bands)while the Allowable Value column is the analytical value used in the accident analysis.While consistent with the Ginna Station Setpoint Analysis, it does not provide a clear operability setpoint.In order to provide this clarification, RG&E is reevaluating the format and specific content of ITS Table 3.3.2-1 for inclusion in a future License Amendment Request.Very yours, Robert C.Mecredy Subscribed and sworn to before me on this+day of June i998.5 Notary Public MARIE C.VILI.ENEUYE Notary Public, State of New York Monroe County MDF/100 Commission Expires October 31, 19 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Guy S.Vissing (Mail Stop 14B2)PWR Project Directorate I-1 Washington, DC 20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector I f (I, 4 t,g i II 4~It J i t-.tt t'II Attachment I Block Diagram of Steam Flow Transmitter Instrument Loop FT-464 4.0 Block Diagram and Scope of Analysis Ref;Precalculation Instrument Review Checklist Block Diagram for Steam Generator Instrument Loop F464.DISC.VERTVRI IVOE Ifa WtSTMOHOVSE Mottt: SH II<<41 ft FT~M 444 OMI ItsTRAM DESC PWR OSOSY 454 ISO'fOASORO MODEM IIOA(4H FM~54 A CESC: VIA I, SCAI 5 WD I45D AVL 41 I IRHOI Mf 0: f 0)OCR 0 MODELl OOPS W 15>V DESC.ERV.Ietaa IRAHSMT IER 14<<ma<<IIHS OSO;FOMORO IIODIL'E I II<<HO I4E DESC IAAI PIER MFO foxsoeo MODEL MCR4HI PISS ISL 5'I M.PRESS.10 50 MA.0 (400 PS IS DESC 50 RI tXIRACI Mfa FOXOORO MOCEL'NAR4H(DESC RtftAI(R Mf 0.f 0100RO MODEL 440R4H FC 454 A DISC ALARM Mf 0'OX00R 0 MODEL 4150R4DHA MAN ST EMI ISO(AT ERI HI STEAM FLOW AHO LO 1 AVO (~545 DEC.Fl OA MPPH (1044 IRII 5.5 MPFII (45~IAAI MAN STEAM ISOLA(CN HHO S1EAII flOW FM 454 DE5C REIEAIER IMO folteRO MODEL'MR 4H LEO EHO'EVCE MAY HOT Af f ECT lDOP ACCURACY" DEVICE DVTfVT IS HOT WITHN THE SCOPE OF AHALYSIS SCOPE S(RIHDARY MAINSTEAM F464 BLOCK DIAGRAM SHEET I MSF464.(TWG Figure 1 EWR 5126 Design Analysis DA EE-92-089-21 Page 11 of 52 Revision~ |
| Thebasesoriginally submitted inReference (a)arerevisedinAttachment 3toprovidethisadditional discussion.
| | Attachment II Pressure Compensation Evaluation |
| Thisreplacesinitsentirety, thebasesprovidedinAttachment IItoReference (a).Inaddition, basedondiscussions duringtheJune3,1998conference call,anissuewasidentified withrespecttothepresentation styleofITSTable3.3.2-1.Specifically, theTripSetpointcolumnofthistableisactuallyanominalsetpointvalue(withtolerance bands)whiletheAllowable Valuecolumnistheanalytical valueusedintheaccidentanalysis.
| |
| Whileconsistent withtheGinnaStationSetpointAnalysis, itdoesnotprovideaclearoperability setpoint.
| |
| Inordertoprovidethisclarification, RG&Eisreevaluating theformatandspecificcontentofITSTable3.3.2-1forinclusion inafutureLicenseAmendment Request.Veryyours,RobertC.MecredySubscribed andsworntobeforemeonthis+dayofJunei998.5NotaryPublicMARIEC.VILI.ENEUYE NotaryPublic,StateofNewYorkMonroeCountyMDF/100Commission ExpiresOctober31,19Attachments xc:U.S.NuclearRegulatory Commission Mr.GuyS.Vissing(MailStop14B2)PWRProjectDirectorate I-1Washington, DC20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector If(I,4t,giII4~ItJit-.ttt'II Attachment IBlockDiagramofSteamFlowTransmitter Instrument LoopFT-464 4.0BlockDiagramandScopeofAnalysisRef;Precalculation Instrument ReviewChecklist BlockDiagramforSteamGenerator Instrument LoopF464.DISC.VERTVRI IVOEIfaWtSTMOHOVSE Mottt:SHII<<41ftFT~M444OMIItsTRAMDESCPWROSOSY454ISO'fOASORO MODEMIIOA(4HFM~54ACESC:VIAI,SCAI5WDI45DAVL41IIRHOIMf0:f0)OCR0MODELlOOPSW15>VDESC.ERV.IetaaIRAHSMTIER14<<ma<<IIHS OSO;FOMORO IIODIL'EIII<<HOI4EDESCIAAIPIERMFOfoxsoeoMODELMCR4HIPISSISL5'IM.PRESS.1050MA.0(400PSISDESC50RItXIRACIMfaFOXOOROMOCEL'NAR4H(
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| DESCRtftAI(RMf0.f0100ROMODEL440R4HFC454ADISCALARMMf0'OX00R0MODEL4150R4DHA MANSTEMIISO(ATERIHISTEAMFLOWAHOLO1AVO(~545DEC.FlOAMPPH(1044IRII5.5MPFII(45~IAAIMANSTEAMISOLA(CNHHOS1EAIIflOWFM454DE5CREIEAIERIMOfolteROMODEL'MR4HLEOEHO'EVCEMAYHOTAffECTlDOPACCURACY"DEVICEDVTfVTISHOTWITHNTHESCOPEOFAHALYSISSCOPES(RIHDARY MAINSTEAM F464BLOCKDIAGRAMSHEETIMSF464.(TWG Figure1EWR5126DesignAnalysisDAEE-92-089-21 Page11of52Revision~
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| Attachment IIPressureCompensation Evaluation | |
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| Rochester GasandElectricCorporation Inter-Office Correspondence May5,1997 | | Rochester Gas and Electric Corporation Inter-Office Correspondence May 5, 1997 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| HiandHi-HiSteamFlowSetpoints forSteamline Isolation LogicTO:MarkFlahertyNuclearSafetyandLicensing Theinstrument bistables whichprovidetheHiandHi-HiSteamFlowtripfunctions forMainSteamIsolation donotreceiveasteampressurecompensation.
| | Hi and Hi-Hi Steam Flow Setpoints for Steamline Isolation Logic TO: Mark Flaherty Nuclear Safety and Licensing The instrument bistables which provide the Hi and Hi-Hi Steam Flow trip functions for Main Steam Isolation do not receive a steam pressure compensation. |
| signal,however,thesetpoints havebeenappropriately calculated andsettoaccountfortherequiredsteampressures specified intheGinnaTechnical Specifications. | | signal, however, the setpoints have been appropriately calculated and set to account for the required steam pressures specified in the Ginna Technical Specifications. |
| TheHi-Histeamflowbistableissettotripat,asteamflowdifferential pressure(DP)of861.2inwcwhichcorresponds totheDPassociated withamainsteamflowof3.6MPPHat755psig(i.e.fullloadconditions) asrequiredby.theTechnical Specifications.
| | The Hi-Hi steam flow bistable is set to trip at,a steam flow differential pressure (DP)of 861.2 inwc which corresponds to the DP associated with a main steam flow of 3.6 MPPH at 755 psig (i.e.full load conditions) as required by.the Technical Specifications. |
| Refertotheattachedblockdiagramforanoverviewofthemethodology usedtodetermine theappropriate setpoints.
| | Refer to the attached block diagram for an overview of the methodology used to determine the appropriate setpoints. |
| Similarmethodology using0.4MPPHsteamflowand1005psigS/Gpressureisusedtodetermine thecompensated HiSteamFlowbistabletripsetpoint.
| | Similar methodology using 0.4 MPPH steam flow and 1005 psig S/G pressure is used to determine the compensated Hi Steam Flow bistable trip setpoint.Attachment Richard A.Baker Technical Support Nuclear Engineering Services ROCHESTER GAS AND ELECTR I C CORP I ON 42~33 ENG DEPT.STATION: TA tie%""'H4Wh~+k~I/O:~~4o M F(ahern DATE:$$$8 MADE 8Y: PAGE l OF t CK: Mba)676AM FLD~Hi<~h Hi-9t TR-iP S<Ttw'oiNT5 jp (5c5)oi'=gr t Z inwc D>)QO F<FT nr)Ob S/C Pre.SSure(~t'Hi TriP se~~Co~p MG6 ln4cator C~tc~s 44 bP Q5 N-0'i Tr(p (3A K 6 Ibm/hi)Co~pe~s&e4 5+e~F(om V4 require)'0'~or Hei Se(pi~%ts de4r~,'nQ 4y~eel(I'eg<o-cK tJorh)mal+e M.Cg Ukicakor 4lou ro.4e4~Qr~w~f46, zu.4pv.K 4+48 w'tcnw cow p8R Qcklow (Au.lQ-I'P t I e C,QS'~<" o~'"9<<<5uL RIP l IC r o~WPu+5 a d 8 e Q.e.6e~ere-4r pre.@sue e I~~c<Hlg&rpe5p wowie l)P va(~e-Oo Li 44m I eguiM co~peas.otic.d. |
| Attachment RichardA.BakerTechnical SupportNuclearEngineering Services ROCHESTER GASANDELECTRICCORPION42~33ENGDEPT.STATION:TAtie%""'H4Wh~+ | | 5kea~4(<w is he,4.raid ed.a~d.useck 4C+e 4i>4.4le 5'gQoi~4~The.C.y.amp I<qh o~w iS for Qe Q'I-p'I 4<ip Se 4()oi~4.Tge.Ri 4r i'p Qe$poi~+Ig$e4r~i~ed USIA<}l&~cobd 54eaw 4Low of 0 (G(p (b~/4r cr 0 t<o5 5/C Press ur C..I' |
| k~I/O:~~4oMF(ahernDATE:$$$8MADE8Y:PAGElOFtCK:Mba)676AMFLD~Hi<~hHi-9tTR-iPS<Ttw'oiNT5 jp(5c5)oi'=grtZinwcD>)QOF<FTnr)ObS/CPre.SSure | |
| (~t'HiTriPse~~Co~pMG6ln4catorC~tc~s44bPQ5N-0'iTr(p(3AK6Ibm/hi)Co~pe~s&e45+e~F(omV4require)'0'~orHeiSe(pi~%tsde4r~,'nQ 4y~eel(I'eg | |
| <o-cKtJorh)mal+eM.CgUkicakor4louro.4e4~Qr~w~f46,zu.4pv.K4+48w'tcnwcowp8RQcklow(Au.lQ-I'PtIeC,QS'~<"o~'"9<<<5uLRIPlICro~WPu+5ad8eQ.e.6e~ere-4r pre.@sueeI~~c<Hlg&rpe5p wowiel)Pva(~e-OoLi44mIeguiMco~peas.otic.d. | |
| 5kea~4(<wishe,4.raid ed.a~d.useck4C+e4i>4.4le5'gQoi~4~The.C.y.ampI<qho~wiSforQeQ'I-p'I4<ipSe4()oi~4.Tge.Ri4ri'pQe$poi~+Ig$e4r~i~edUSIA<}l&~cobd54eaw4Lowof0(G(p(b~/4rcr0t<o55/CPressurC..I' | |
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| Attachment IIIRevisedBases}} | | Attachment III Revised Bases}} |
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Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view] |
Text
CATEGORY 1 REGULATE INFORMATION DISTRIBUTIOh SYSTEM (RIDS)ACCESSION NBR:9806100264
'OC.DATE: 98/06/04 NOTARIZED:
YES DOCKET¹FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME" AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 8 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING, G.S.
SUBJECT:
Provides more detailed description of basis for proposed setpoint language contained in 970929 application for amend, per 980428,0513 R 20 R 0603 telcons w/NRC re change to main steam isolation setpoint.Revised TS pages encl.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)
.E 05000244 G RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
01 EXTE NOAC INTERNAL: ILE CE DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 0 D 0 E N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 II 1V P 1 r I ll C3 AND ROCHESTER GAS AND ELECTRIC CORPORATION
~89 EASTAVENLIE, ROCHESTER, N.Y 14649-000I ARFA CODE716 546-270O ROBERT C.MECREDY Vice President Nvdeor Operotions June 4, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
Subject:
Main Steam Isolation Setpoint License Amendment Request Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
Reference:
(a)Letter from.R.C.Mecredy, RG&E, to G.S.Vissing, NRC,
Subject:
Application for Amendment to I"acili(y Operating License, Change to Main Steam Isolation Setpoint (LCO Table 3.3.2-l, Function 4.d), dated September 29, 1997.(b)Conference calls of April 28, May 13 and 20, and June 3, 1998 between RG&E and NRC.
Dear Mr.Vissing In Reference (a),
RG&E submitted a proposed change to the Improved Technical Specification (ITS)setpoint for main steam isolation (Table 3.3.2-1, Function 4.d).Recently, RG&E and the NRC discussed the language being proposed for the revised setpoint and why this differed from Standard ITS (Reference (b)).The purpose of this letter is to describe in more detail the basis for the proposed setpoint language and to revise the proposed ITS bases to provide further clarification.
The following table illustrates the differences between the RG&E proposed changes to ITS Table 3.3.2-1, Function D and those in Standard ITS: Trip Setpoint s 0.4E6 ibm/hr1005 psig~GG d Allowable Value s 0.66E6 ibm/hr1005 psig Standard ITS s[25%]of full steam flow at no load steam pressure s[]of full steam fiow at no load steam pressure (s-'lA~P,.9806i00264 980604'DR ADOCK 05000244 P PDR As can be seen, the primary differences are: (1)use of a specific flowrate versus a percentage of full steam flow,.and (2)use of a specific pressure versus"no load steam pressure." These differences are discussed in detail below.I Attachment I provides a simplified figure of one of the four main steam flow instrument loops.As can be seen on this figure, FT-464 is a differential pressure transmitter whose signal is sent to three functions.
The first signal goes to main control board indicator FI-464 after being compensated by main steam pressure (PM-464A)and processed by a square root extractor (FM-464B)and a repeater (FM-464C).
The second signal goes to an alarm (FC-464A)and then to two bistables for the high steam flow and high-high steam flow functions listed in ITS Table 3.3.2-1, Function 4.The third and last signal goes to a repeater (FM-464D)and to the advanced digital feedwater control system (ADFCS).The only output signal from FT-464 which is pressure compensated is that for the main control board indication.
The output signal to the high and high-high steam flow bistables via alarm FC-464A is a direct value from the differential pressure transmitter.
However, the bistable trip setpoints do have a pressure compensation"adjustment".
That is, the bistable trip setpoint matches the ITS specified conditions of 0.4E6 Ibm/hr N 1005 psig.This is accomplished by identifying the required signal to main control board indicator FI-464 for steam line flow/pressure conditions of 0.4E6 Ibm/hr1005 psig.This signal value is traced back through the logic shown in Attachment I (repeater, square root extractor, and steam pressure multiplier) to identify the required output of the differential pressure transmitter for FT-464.This calculated output signal from the differential pressure transmitter is what is used for the bistable setpoint;hence, the pressure compensation"adjustment".
Attachment II provides additional details.As described above, the bistable setpoints are based on a specific set of plant steam flow and pressure conditions.
Consequently, the Ginna Station ITS must specify these plant conditions versus the Standard ITS terms of"%full steam flow" and"no load steam pressure" even though the Ginna specified conditions are essentially equivalent to the Standard ITS terms.The accident analysis also uses these same plant conditions.
That is, for those analyzed steam line breaks requiring automatic steam line isolation, the accident analysis assumes a main steam isolation signal is generated immediately aiba a safety injection setpoint is reached.The analysis is then reviewed afterwards to ensure that the remaining coincident main steam isolation parameters listed in ITS Table 3.3.2-1 are also met.For the case of small steam line breaks, the accident analysis verifies that the main steam flow is>0.66E6 Ibm/hr with pressure s 1005 psig prior to reaching safety injection setpoints.
Higher steam flowrates or lower pressures would generate a higher differential pressure across the flow transmitter ensuring that the bistable setpoint is reached.Since normal full power conditions result in steam flows and pressures of approximately 3.3 ibm/hr and 730 psig respectively, the bistables for ITS Table 3.3.2-1, Function 4.d are normally tripped.Therefore, the use of a specific flowrate and pressure remains consistent with the accident analysis and reflects that the bistable setpoint does not automatically change if steam conditions were to change.As such, the Ginna Station ITS is different from Standard ITS in implementation, but not in intent.
The bases originally submitted in Reference (a)are revised in Attachment 3 to provide this additional discussion.
This replaces in its entirety, the bases provided in Attachment II to Reference (a).In addition, based on discussions during the June 3, 1998 conference call, an issue was identified with respect to the presentation style of ITS Table 3.3.2-1.Specifically, the Trip Setpoint column of this table is actually a nominal setpoint value (with tolerance bands)while the Allowable Value column is the analytical value used in the accident analysis.While consistent with the Ginna Station Setpoint Analysis, it does not provide a clear operability setpoint.In order to provide this clarification, RG&E is reevaluating the format and specific content of ITS Table 3.3.2-1 for inclusion in a future License Amendment Request.Very yours, Robert C.Mecredy Subscribed and sworn to before me on this+day of June i998.5 Notary Public MARIE C.VILI.ENEUYE Notary Public, State of New York Monroe County MDF/100 Commission Expires October 31, 19 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Guy S.Vissing (Mail Stop 14B2)PWR Project Directorate I-1 Washington, DC 20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector I f (I, 4 t,g i II 4~It J i t-.tt t'II Attachment I Block Diagram of Steam Flow Transmitter Instrument Loop FT-464 4.0 Block Diagram and Scope of Analysis Ref;Precalculation Instrument Review Checklist Block Diagram for Steam Generator Instrument Loop F464.DISC.VERTVRI IVOE Ifa WtSTMOHOVSE Mottt: SH II<<41 ft FT~M 444 OMI ItsTRAM DESC PWR OSOSY 454 ISO'fOASORO MODEM IIOA(4H FM~54 A CESC: VIA I, SCAI 5 WD I45D AVL 41 I IRHOI Mf 0: f 0)OCR 0 MODELl OOPS W 15>V DESC.ERV.Ietaa IRAHSMT IER 14<<ma<<IIHS OSO;FOMORO IIODIL'E I II<<HO I4E DESC IAAI PIER MFO foxsoeo MODEL MCR4HI PISS ISL 5'I M.PRESS.10 50 MA.0 (400 PS IS DESC 50 RI tXIRACI Mfa FOXOORO MOCEL'NAR4H(DESC RtftAI(R Mf 0.f 0100RO MODEL 440R4H FC 454 A DISC ALARM Mf 0'OX00R 0 MODEL 4150R4DHA MAN ST EMI ISO(AT ERI HI STEAM FLOW AHO LO 1 AVO (~545 DEC.Fl OA MPPH (1044 IRII 5.5 MPFII (45~IAAI MAN STEAM ISOLA(CN HHO S1EAII flOW FM 454 DE5C REIEAIER IMO folteRO MODEL'MR 4H LEO EHO'EVCE MAY HOT Af f ECT lDOP ACCURACY" DEVICE DVTfVT IS HOT WITHN THE SCOPE OF AHALYSIS SCOPE S(RIHDARY MAINSTEAM F464 BLOCK DIAGRAM SHEET I MSF464.(TWG Figure 1 EWR 5126 Design Analysis DA EE-92-089-21 Page 11 of 52 Revision~
Attachment II Pressure Compensation Evaluation
Rochester Gas and Electric Corporation Inter-Office Correspondence May 5, 1997
SUBJECT:
Hi and Hi-Hi Steam Flow Setpoints for Steamline Isolation Logic TO: Mark Flaherty Nuclear Safety and Licensing The instrument bistables which provide the Hi and Hi-Hi Steam Flow trip functions for Main Steam Isolation do not receive a steam pressure compensation.
signal, however, the setpoints have been appropriately calculated and set to account for the required steam pressures specified in the Ginna Technical Specifications.
The Hi-Hi steam flow bistable is set to trip at,a steam flow differential pressure (DP)of 861.2 inwc which corresponds to the DP associated with a main steam flow of 3.6 MPPH at 755 psig (i.e.full load conditions) as required by.the Technical Specifications.
Refer to the attached block diagram for an overview of the methodology used to determine the appropriate setpoints.
Similar methodology using 0.4 MPPH steam flow and 1005 psig S/G pressure is used to determine the compensated Hi Steam Flow bistable trip setpoint.Attachment Richard A.Baker Technical Support Nuclear Engineering Services ROCHESTER GAS AND ELECTR I C CORP I ON 42~33 ENG DEPT.STATION: TA tie%""'H4Wh~+k~I/O:~~4o M F(ahern DATE:$$$8 MADE 8Y: PAGE l OF t CK: Mba)676AM FLD~Hi<~h Hi-9t TR-iP S<Ttw'oiNT5 jp (5c5)oi'=gr t Z inwc D>)QO F<FT nr)Ob S/C Pre.SSure(~t'Hi TriP se~~Co~p MG6 ln4cator C~tc~s 44 bP Q5 N-0'i Tr(p (3A K 6 Ibm/hi)Co~pe~s&e4 5+e~F(om V4 require)'0'~or Hei Se(pi~%ts de4r~,'nQ 4y~eel(I'eg<o-cK tJorh)mal+e M.Cg Ukicakor 4lou ro.4e4~Qr~w~f46, zu.4pv.K 4+48 w'tcnw cow p8R Qcklow (Au.lQ-I'P t I e C,QS'~<" o~'"9<<<5uL RIP l IC r o~WPu+5 a d 8 e Q.e.6e~ere-4r pre.@sue e I~~c<Hlg&rpe5p wowie l)P va(~e-Oo Li 44m I eguiM co~peas.otic.d.
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Attachment III Revised Bases
