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| {{#Wiki_filter:V.S.NUCLLABflEGULATOB VCOMMISSION fIIICr:o>>M1951776Iw"rr~>In~NRCDISTRIBUTION FOB,P,TGODOCICETMATERIALDOCKETNUMBER50-220FI'NVMOEB'lMr.George'LearFROM:NiagaraMohawkPowerCorp.Syracuse, NewYorkMr,RudolphR.Schneider DATEOFDOCUMENT8/3/76DATL=RECEIVED8/6/76ABETTERPjjjDBIOINALQCOPVDESCRIPTION ONOTOBIZEDPKVNCLASSIF IEDPROPINPUTFORMENCLOSURENUMBEROFCOPIESRECEIVEDOnesignedLtr,w/attached,;,re their5/1'9/76ltr,andour6/9/76ltr.~~.furnishing additional ininformation concerning AssemblyAveraged'ower-Void Relationship | | {{#Wiki_filter:V.S.NUCLLAB flEGULATOB V COMMISSION fIIIC r:o>>M 195 17 76I w" r r~>In~NRC DISTRIBUTION FOB,P, T GO DOCICET MATERIAL DOCKET NUMBER 50-220 FI'NVMOEB'l Mr.George'Lear FROM: Niagara Mohawk Power Corp.Syracuse, New York Mr, Rudolph R.Schneider DATE OF DOCUMENT 8/3/76 DATL=RECEIVE D 8/6/76 ABETTER PjjjDB IOINAL Q COP V DESCRIPTION ONOTOB IZED PKVNCLASSIF I ED PROP INPUT FORM ENCLOSU RE NUMBER OF COPIES RECEIVED One signed Ltr, w/attached,;,re their 5/1'9/76 ltr, and our 6/9/76 ltr.~~.furnishing additional in information concerning Assembly Averaged'ower-Void Relationship.Tech Spec,-~ACKNOWLEDGED PLANT NAME: Nine Mile Point gi (5-P)'O NOT RziMOVZ.SAFETY.ASSXGNED AD: BRANCH CHIEF: PROJECT MI ANAGER: LXC~ASSTo: Lear Parrish FOR ACTION/INFORMATION ASSI NED DE PRO i NA~L S RE'C'X F'NTERNAL D SYSTE'IS SAFETY IS1 Rl BUTION SITE SA~NRC PDR X&E OEI.D GOSSXCIC&STAFF MIPC CASE IIANAUER JIARLES PROJECT HAVAGFtIEN BOYD P COLLINS HOUSTON PETERSON MELTZ 11ELTEMES S KOVIIOLT LPDR: Oswe o N Y.TXC:.NS,I ASLB: ACI<S CYS He&BBKI NBC Fof1M 166 (2 76)HE XNEI IAN SCHROEDER ENGXNEERING ifIACCARRY |
| .TechSpec,-~ACKNOWLEDGED PLANTNAME:NineMilePointgi(5-P)'ONOTRziMOVZ.SAFETY.ASSXGNEDAD:BRANCHCHIEF:PROJECTMIANAGER:LXC~ASSTo:LearParrishFORACTION/INFORMATION ASSINEDDEPROiNA~LSRE'C'XF'NTERNAL DSYSTE'ISSAFETYIS1RlBUTIONSITESA~NRCPDRX&EOEI.DGOSSXCIC&STAFFMIPCCASEIIANAUERJIARLESPROJECTHAVAGFtIEN BOYDPCOLLINSHOUSTONPETERSONMELTZ11ELTEMES SKOVIIOLTLPDR:OsweoNY.TXC:.NS,IASLB:ACI<SCYSHe&BBKINBCFof1M166(276)HEXNEIIANSCHROEDER ENGXNEERING ifIACCARRY | | .KNIGHT SIHIPEIL PAMLICKI REACTOR SAFETZ ROSS NOVAK ROSZTOCZY CHECK AT&X SALTZMAN RUTBERG EXTERNAL DISTRIBUTION Nl lT LAB REGS VIE LA PDR CONSULTANTS |
| .KNIGHTSIHIPEILPAMLICKIREACTORSAFETZROSSNOVAKROSZTOCZY CHECKAT&XSALTZMANRUTBERGEXTERNALDISTRIBUTION NllTLABREGSVIELAPDRCONSULTANTS | | ~~?r BENAROYA IPPOLXTO~KIRKICOOD OPERATItIG REACTORS OPERATXN r CI EISENHUT SHAO BAER BUTLI R GRIMES W UL'RIKSON ORNL ENV?.'RO AMASS~??i.NZm~~lf,aa ENV S E CONTROL NUMiBER 7F/B~ |
| ~~?rBENAROYAIPPOLXTO~KIRKICOOD OPERATItIG REACTORSOPERATXNrCIEISENHUTSHAOBAERBUTLIRGRIMESWUL'RIKSON ORNLENV?.'ROAMASS~??i.NZm~~lf,aa ENVSECONTROLNUMiBER7F/B~ | | N y tY~N I~~4~N t~~~ |
| NytY~NI~~4~Nt~~~
| | NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE, H.Y.l3202 August 3, 1976 Director of Nuclear Reactor Regulation Attn: Mr.George Lear, Chief Operating Reactors Branch III3 U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63 |
| NIAGARAMOHAWKPOWERCORPORATION NIAGARA~MOHAWK300ERIEBOULEVARD WESTSYRACUSE, H.Y.l3202August3,1976DirectorofNuclearReactorRegulation Attn:Mr.GeorgeLear,ChiefOperating ReactorsBranchIII3U.S.NuclearRegulatory Commission Washington, D.C.20555Re:NineMilePointUnit1DocketNo.50-220DPR-63
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| ==DearMr.Lear:== | | ==Dear Mr.Lear:== |
| Ourletterof'ay19,1976transmitted proposedchangestotheAssemblyAveragedPower-Void Relationship Technical Specification forNineMilePointUnit1.1'ourletterofJune9,1976requested additional information regarding that'roposed change.Theattachedresponses addressthequestions contained inyourletter.Sincerely, NIAGARAMOHAWKPOWERCORPORATION peg(P~opoS.gangPRudolph.Schneider,VicePresident
| | Our letter of'ay 19, 1976 transmitted proposed changes to the Assembly Averaged Power-Void Relationship Technical Specification for Nine Mile Point Unit 1.1'our letter of June 9, 1976 requested additional information regarding that'roposed change.The attached responses address the questions contained in your letter.Sincerely, NIAGARA MOHAWK POWER CORPORATION pe g(P~o po S.gang P Rudolph.Schnei der, Vice President-Electric Operations Attachment |
| -ElectricOperations Attachment | | '~<5 il't K'i c RESPOND.S TO JUNE 9, l976 NRC QUESTION NINE HILE POINT UNIT 1 Docket No.50-220 DPR-63 RecCuest Provide a quanti tative explanation of'ow exposure dependent"B" values are calculated. |
| '~<5il'tK'i cRESPOND.STOJUNE9,l976NRCQUESTIONNINEHILEPOINTUNIT1DocketNo.50-220DPR-63RecCuestProvideaquantitativeexplanation of'owexposuredependent "B"valuesarecalculated. | | Include examples which show how different values of"B" were calculated for two different exposures of the same fuel.The examples should show (1)the relationships (equations) assumed, and (2)the source and numerical values of all terms in the relationship for: 1.maximum Average Planar Linear Heat=Generation Rate (EQPLHGR)and Average Heat Generation Rate (q)(i.e., assumed peaking factors).2.Dryout Time.(i.e., h, h.,flow, average density, q).g'n'" 3."B" values (i.e., void fraction, peaking factor, power).R~es ense The duration of nucleate boiling for non-jet pump plant ECCS analyses has been determined using the correlation (Equation 1, below)described in"General Electric Compliance with 10CFR50 Appendix K-Acceptance Criteria I.C.4." That correlation shows the time to boiling transition (dryout time)is a function exclusively of liquid volume fraction and power input to the bundle.Converged HAPLHGR limits and conservative axial power distributions were assumed for the dryout time determinations. |
| Includeexampleswhichshowhowdifferent valuesof"B"werecalculated fortwodifferent exposures ofthesamefuel.Theexamplesshouldshow(1)therelationships (equations) assumed,and(2)thesourceandnumerical valuesofalltermsintherelationship for:1.maximumAveragePlanarLinearHeat=Generation Rate(EQPLHGR) andAverageHeatGeneration Rate(q)(i.e.,assumedpeakingfactors).2.DryoutTime.(i.e.,h,h.,flow,averagedensity,q).g'n'"3."B"values(i.e.,voidfraction, peakingfactor,power).R~esenseThedurationofnucleateboilingfornon-jetpumpplantECCSanalyseshasbeendetermined usingthecorrelation (Equation 1,below)described in"GeneralElectricCompliance with10CFR50AppendixK-Acceptance CriteriaI.C.4."Thatcorrelation showsthetimetoboilingtransition (dryouttime)isafunctionexclusively ofliquidvolumefractionandpowerinputtothebundle.Converged HAPLHGRlimitsandconservative axialpowerdistributions wereassumedforthedryouttimedeterminations.
| | Both HAPLHGR limits and dryout times are exposure dependent. |
| BothHAPLHGRlimitsanddryouttimesareexposuredependent.
| | The following development shows how"B" values are calculated. |
| Thefollowing development showshow"B"valuesarecalculated.
| | (0~31)(Pf)(hf)gt I I Equation 1 ht=time to transition boiling, hr.3 p=saturated liquid density, ibm/ft h enthalpy of'aporization, BTU/ibm fg gist V (1--a) |
| (0~31)(Pf)(hf)gtIIEquation1ht=timetotransition boiling,hr.3p=saturated liquiddensity,ibm/fthenthalpyof'aporization, BTU/ibmfggistV(1--a) | |
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| (~/q=Poworgeneration inbundle,BTU/hr=(PF)(FCP)(ABTU)PF=bundleradialpowerfactorFCP~fractional corepowerrelativeto1850Hh'BTU=averagebundleoutputat1850Hft,BTU/hr3V=activecoolantvolume,fta.=voidfractionTherefore ht='0.31)(P)(hf)(V)(1-a.)(ABTU)(PF)(FCP)Equation2"B"Factor=(1-a.)i(PF)(FCP)Equation3~tLimitingthis"B"factorrelatioriship willassurethatlocalpowervoidvalueswillnotresultindr@outtimesshorterthanthoseused.intheECCSAnalysis. | | (~/q=Powor generation in bundle, BTU/hr=(PF)(FCP)(ABTU)PF=bundle radial power factor FCP~fractional core power relative to 1850 Hh'BTU=average bundle output at 1850 Hft, BTU/hr 3 V=active coolant volume, ft a.=void fraction Therefore ht='0.31)(P)(hf)(V)(1-a.)(ABTU)(PF)(FCP)Equation 2"B" Factor=(1-a.)i (PF)(FCP)Equation 3~t Limiting this"B" factor relatioriship will assure that local power void values will not result in dr@out times shorter than those used.in the ECCS Analysis.Using Equation 2: "B" Factor=(ABTU)Qt)(0.31)(P f)(hf)(V)fg Equation 4 Assumed nominal values are: ABTU=1.1869 x 10 BTU/hr 7 pf~45.977 ibm/ft 3 hf=641.36 BTU/1 bm fg V~1.2696 ft, Znitial Core V=1.2948 ft , Reloads 1, 2, 3 3 r~~ |
| UsingEquation2:"B"Factor=(ABTU)Qt)(0.31)(Pf)(hf)(V)fgEquation4Assumednominalvaluesare:ABTU=1.1869x10BTU/hr7pf~45.977ibm/ft3hf=641.36BTU/1bmfgV~1.2696ft,ZnitialCoreV=1.2948ft,Reloads1,2,33 r~~
| | V=1.2936 ft , Reloads 4, 5 3 Substituting the above values in Equation 4 yields the"B" factor relatiori-ships for the different reloads: "B" Factor=(1022.688)(ht)"B" Factor=(1002.784)(ht)"B" Factor=(1003.714)(b t)2'ni tial Core Reloads 1, 2, 3 Reloads 4, 5 Equation 5 Equa,tion 6 Equation 7 The folloving examples shov hov different values of"B" vere calculated for tvo different exposures of the same fuel (Reload 3):~Ex osure ECCS Anal sis Dr out Times HAPLHGR 5000 7fVD/T 25000 HVD/T 1.48 sec 1.59 sec 10.68 9.92 Sunsti tuting the above dryout times in Equation 6 yields: For 5000 IWD/T: "B" Factor=(1002.784)(ht)"B" Factor=1002.784lhr) |
| V=1.2936ft,Reloads4,53Substituting theabovevaluesinEquation4yieldsthe"B"factorrelatiori-shipsforthedifferent reloads:"B"Factor=(1022.688) | | (1.48 sec)3600 sec/hr"B" Factor=0.412 For 25000 IWD/T: "B" Factor=(1002.784) gt)"B" Factor=(1002.784/hr) |
| (ht)"B"Factor=(1002.784) | | (1.59 sec)3600 sec/hr"B" Factor=0.443 |
| (ht)"B"Factor=(1003.714) | |
| (bt)2'nitialCoreReloads1,2,3Reloads4,5Equation5Equa,tion 6Equation7Thefolloving examplesshovhovdifferent valuesof"B"verecalculated fortvodifferent exposures ofthesamefuel(Reload3):~ExosureECCSAnalsisDroutTimesHAPLHGR50007fVD/T25000HVD/T1.48sec1.59sec10.689.92SunstitutingtheabovedryouttimesinEquation6yields:For5000IWD/T:"B"Factor=(1002.784) | |
| (ht)"B"Factor=1002.784lhr) | |
| (1.48sec)3600sec/hr"B"Factor=0.412For25000IWD/T:"B"Factor=(1002.784) gt)"B"Factor=(1002.784/hr) | |
| (1.59sec)3600sec/hr"B"Factor=0.443 | |
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| e~eeest:Demonstrate how"B"valuesarecalculated toassureconservatism whenusingthedryouttimesassumedintheECCSanalysis. | | e~eeest: Demonstrate how"B" values are calculated to assure conservatism when using the dryout times assumed in the ECCS analysis.R~es see As indicated in the above response, nominal values were.used to calculate, the"B" factors.Converged HApLHGR limits and conservative axial power distributions were assumed for t'e dryout time, determinations. |
| R~esseeAsindicated intheaboveresponse, nominalvalueswere.usedtocalculate, the"B"factors.Converged HApLHGRlimitsandconservative axialpowerdistributions wereassumedfort'edryouttime,determinations. | | 'In addition, a conservative c4rrelation (G.E.compliance with 10CFR50, Appendix K criteria I.C.4:)was used which was previously approved by the Commission. |
| 'Inaddition, aconservative c4rrelation (G.E.compliance with10CFR50,AppendixKcriteriaI.C.4:)wasusedwhichwaspreviously approvedbytheCommission. | | A"B" Factor Limiting Condition for Operation is not necessary to assure that actual dryout times are conservative. |
| A"B"FactorLimitingCondition forOperation isnotnecessary toassurethatactualdryouttimesareconservative. | | Dryout time is only one of many conservative inputs used to determine HAPL/EGR limits, the ultimate restriction of interest.Sensitivity analyses performed by our fuel supplier have determined that the parameters used to calculate dryout time (void fraction, axial power distributions) are conservative when compared to normal plant operation. |
| Dryouttimeisonlyoneofmanyconservative inputsusedtodetermine HAPL/EGRlimits,theultimaterestriction ofinterest.
| | ~r~w y~}} |
| Sensitivity analysesperformed byourfuelsupplierhavedetermined thattheparameters usedtocalculate dryouttime(voidfraction, axialpowerdistributions) areconservative whencomparedtonormalplantoperation. | |
| ~r~wy~}} | |
|
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Category:Letter
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2024-02-01
[Table view]
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Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021
Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves
JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021
Company - Response to Request for Additional Information
JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021
Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021
Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2
NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2
NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021
Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020
Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2
NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020
Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020
Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568
NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020
Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components
ML20188A2642020-07-0606 July 2020
Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information
NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates
NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019
Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879
JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019
Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880
NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019
Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants
NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm
JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019
Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880
NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018
Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.
NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018
Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres
NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...
NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)
NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018
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RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018
Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)
ML18025A7992018-01-25025 January 2018
Response to Request for Additional Information Regarding Generic Letter 2016-01
NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017
Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water
NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017
Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)
RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017
Response to Request for Additional Information Regarding Generic Letter 2016-01
NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017
Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J
RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017
Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal
ML17037A2652017-02-0606 February 2017
Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant
RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016
Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure
ML16131A6542016-05-0404 May 2016
Response to a Question Raised During the Audit
ML16131A6552016-05-0404 May 2016
White Paper Prepared in Response to a Question Raised During the Audit
NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016
Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....2016-01-25025 January 2016
Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....
NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016
Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015
Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....
2023-08-04
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V.S.NUCLLAB flEGULATOB V COMMISSION fIIIC r:o>>M 195 17 76I w" r r~>In~NRC DISTRIBUTION FOB,P, T GO DOCICET MATERIAL DOCKET NUMBER 50-220 FI'NVMOEB'l Mr.George'Lear FROM: Niagara Mohawk Power Corp.Syracuse, New York Mr, Rudolph R.Schneider DATE OF DOCUMENT 8/3/76 DATL=RECEIVE D 8/6/76 ABETTER PjjjDB IOINAL Q COP V DESCRIPTION ONOTOB IZED PKVNCLASSIF I ED PROP INPUT FORM ENCLOSU RE NUMBER OF COPIES RECEIVED One signed Ltr, w/attached,;,re their 5/1'9/76 ltr, and our 6/9/76 ltr.~~.furnishing additional in information concerning Assembly Averaged'ower-Void Relationship.Tech Spec,-~ACKNOWLEDGED PLANT NAME: Nine Mile Point gi (5-P)'O NOT RziMOVZ.SAFETY.ASSXGNED AD: BRANCH CHIEF: PROJECT MI ANAGER: LXC~ASSTo: Lear Parrish FOR ACTION/INFORMATION ASSI NED DE PRO i NA~L S RE'C'X F'NTERNAL D SYSTE'IS SAFETY IS1 Rl BUTION SITE SA~NRC PDR X&E OEI.D GOSSXCIC&STAFF MIPC CASE IIANAUER JIARLES PROJECT HAVAGFtIEN BOYD P COLLINS HOUSTON PETERSON MELTZ 11ELTEMES S KOVIIOLT LPDR: Oswe o N Y.TXC:.NS,I ASLB: ACI<S CYS He&BBKI NBC Fof1M 166 (2 76)HE XNEI IAN SCHROEDER ENGXNEERING ifIACCARRY
.KNIGHT SIHIPEIL PAMLICKI REACTOR SAFETZ ROSS NOVAK ROSZTOCZY CHECK AT&X SALTZMAN RUTBERG EXTERNAL DISTRIBUTION Nl lT LAB REGS VIE LA PDR CONSULTANTS
~~?r BENAROYA IPPOLXTO~KIRKICOOD OPERATItIG REACTORS OPERATXN r CI EISENHUT SHAO BAER BUTLI R GRIMES W UL'RIKSON ORNL ENV?.'RO AMASS~??i.NZm~~lf,aa ENV S E CONTROL NUMiBER 7F/B~
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NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE, H.Y.l3202 August 3, 1976 Director of Nuclear Reactor Regulation Attn: Mr.George Lear, Chief Operating Reactors Branch III3 U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63
Dear Mr.Lear:
Our letter of'ay 19, 1976 transmitted proposed changes to the Assembly Averaged Power-Void Relationship Technical Specification for Nine Mile Point Unit 1.1'our letter of June 9, 1976 requested additional information regarding that'roposed change.The attached responses address the questions contained in your letter.Sincerely, NIAGARA MOHAWK POWER CORPORATION pe g(P~o po S.gang P Rudolph.Schnei der, Vice President-Electric Operations Attachment
'~<5 il't K'i c RESPOND.S TO JUNE 9, l976 NRC QUESTION NINE HILE POINT UNIT 1 Docket No.50-220 DPR-63 RecCuest Provide a quanti tative explanation of'ow exposure dependent"B" values are calculated.
Include examples which show how different values of"B" were calculated for two different exposures of the same fuel.The examples should show (1)the relationships (equations) assumed, and (2)the source and numerical values of all terms in the relationship for: 1.maximum Average Planar Linear Heat=Generation Rate (EQPLHGR)and Average Heat Generation Rate (q)(i.e., assumed peaking factors).2.Dryout Time.(i.e., h, h.,flow, average density, q).g'n'" 3."B" values (i.e., void fraction, peaking factor, power).R~es ense The duration of nucleate boiling for non-jet pump plant ECCS analyses has been determined using the correlation (Equation 1, below)described in"General Electric Compliance with 10CFR50 Appendix K-Acceptance Criteria I.C.4." That correlation shows the time to boiling transition (dryout time)is a function exclusively of liquid volume fraction and power input to the bundle.Converged HAPLHGR limits and conservative axial power distributions were assumed for the dryout time determinations.
Both HAPLHGR limits and dryout times are exposure dependent.
The following development shows how"B" values are calculated.
(0~31)(Pf)(hf)gt I I Equation 1 ht=time to transition boiling, hr.3 p=saturated liquid density, ibm/ft h enthalpy of'aporization, BTU/ibm fg gist V (1--a)
(~/q=Powor generation in bundle, BTU/hr=(PF)(FCP)(ABTU)PF=bundle radial power factor FCP~fractional core power relative to 1850 Hh'BTU=average bundle output at 1850 Hft, BTU/hr 3 V=active coolant volume, ft a.=void fraction Therefore ht='0.31)(P)(hf)(V)(1-a.)(ABTU)(PF)(FCP)Equation 2"B" Factor=(1-a.)i (PF)(FCP)Equation 3~t Limiting this"B" factor relatioriship will assure that local power void values will not result in dr@out times shorter than those used.in the ECCS Analysis.Using Equation 2: "B" Factor=(ABTU)Qt)(0.31)(P f)(hf)(V)fg Equation 4 Assumed nominal values are: ABTU=1.1869 x 10 BTU/hr 7 pf~45.977 ibm/ft 3 hf=641.36 BTU/1 bm fg V~1.2696 ft, Znitial Core V=1.2948 ft , Reloads 1, 2, 3 3 r~~
V=1.2936 ft , Reloads 4, 5 3 Substituting the above values in Equation 4 yields the"B" factor relatiori-ships for the different reloads: "B" Factor=(1022.688)(ht)"B" Factor=(1002.784)(ht)"B" Factor=(1003.714)(b t)2'ni tial Core Reloads 1, 2, 3 Reloads 4, 5 Equation 5 Equa,tion 6 Equation 7 The folloving examples shov hov different values of"B" vere calculated for tvo different exposures of the same fuel (Reload 3):~Ex osure ECCS Anal sis Dr out Times HAPLHGR 5000 7fVD/T 25000 HVD/T 1.48 sec 1.59 sec 10.68 9.92 Sunsti tuting the above dryout times in Equation 6 yields: For 5000 IWD/T: "B" Factor=(1002.784)(ht)"B" Factor=1002.784lhr)
(1.48 sec)3600 sec/hr"B" Factor=0.412 For 25000 IWD/T: "B" Factor=(1002.784) gt)"B" Factor=(1002.784/hr)
(1.59 sec)3600 sec/hr"B" Factor=0.443
e~eeest: Demonstrate how"B" values are calculated to assure conservatism when using the dryout times assumed in the ECCS analysis.R~es see As indicated in the above response, nominal values were.used to calculate, the"B" factors.Converged HApLHGR limits and conservative axial power distributions were assumed for t'e dryout time, determinations.
'In addition, a conservative c4rrelation (G.E.compliance with 10CFR50, Appendix K criteria I.C.4:)was used which was previously approved by the Commission.
A"B" Factor Limiting Condition for Operation is not necessary to assure that actual dryout times are conservative.
Dryout time is only one of many conservative inputs used to determine HAPL/EGR limits, the ultimate restriction of interest.Sensitivity analyses performed by our fuel supplier have determined that the parameters used to calculate dryout time (void fraction, axial power distributions) are conservative when compared to normal plant operation.
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