Similar Documents at Ginna |
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Category:ARCHIVE RECORDS
MONTHYEARML17264B0451997-09-19019 September 1997
Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary.
ML17265A6891997-06-30030 June 1997
Rev 1 to Calculation 96190-C-68, Pressure Locking Analysis for Valve(S) 871A/B.
ML17264A9261997-06-10010 June 1997
Low Temp Overpressure Analyses Summary Rept, Calculational Summary Sheet 86-1234820-01
ML20132A3921996-12-13013 December 1996
Press Release I-96-81, NRC Staff Proposes to Fine Rg&E $100,000 for Alleged Violations at Ginna Nuclear Plant
ML20129B7031996-10-22022 October 1996
Press Release I-96-69,informing That NRC Has Rescheduled Meeting W/Officials of Rg&E to Discuss Latest Systematic Assessment of Licensee Performance at Gnpp
ML20128M2981996-10-15015 October 1996
Press Release I-96-68, NRC Staff Rates Ginna Good in Three Areas & Excellent in One Category on Latest SALP Rept
ML17264A6131996-08-0202 August 1996
Rev 0 to Verification of Pressure Locking Analysis Program Preslok.
ML17264A2651995-11-16016 November 1995
Gamma-Body Offsite Dose Calculation.
ML17264A6111993-12-23023 December 1993
Rev 1 to Valve Thrust Calculation for 6x4x6 Class 300# Anchor Darling Gate Valve,857A,B & C & 860A,B,C & D.
ML20085M5451991-11-11011 November 1991
Responses to NUMARC Aquatic Resources Survey & Socioeconomic Question in Support of NRC License Renewal Rulemaking
ML17262A4511991-04-10010 April 1991
Devonrue Calculation Re Plant Atmospheric Relief Valve (ARV) Area Ambient Temp rise-revised Methodology
ML17262A4531990-06-0505 June 1990
Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise
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ML20237D7901987-12-10010 December 1987
Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys
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Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
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Human Factors Engineering Dcrdr In-Progress Audit,Re Ginna Nuclear Power Plant
ML20129F4831985-05-0909 May 1985
Package of Compilations of Results of Operator Licensing & Requalification Exams
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Slide Presentation from 820323 Meeting Re Steam Generator Repair Activities at Facility
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1997-09-19
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML17264B0451997-09-19019 September 1997
Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary.
ML17265A6891997-06-30030 June 1997
Rev 1 to Calculation 96190-C-68, Pressure Locking Analysis for Valve(S) 871A/B.
ML17264A9261997-06-10010 June 1997
Low Temp Overpressure Analyses Summary Rept, Calculational Summary Sheet 86-1234820-01
ML17264A6131996-08-0202 August 1996
Rev 0 to Verification of Pressure Locking Analysis Program Preslok.
ML17264A2651995-11-16016 November 1995
Gamma-Body Offsite Dose Calculation.
ML17264A6111993-12-23023 December 1993
Rev 1 to Valve Thrust Calculation for 6x4x6 Class 300# Anchor Darling Gate Valve,857A,B & C & 860A,B,C & D.
ML17262A4511991-04-10010 April 1991
Devonrue Calculation Re Plant Atmospheric Relief Valve (ARV) Area Ambient Temp rise-revised Methodology
ML17262A4531990-06-0505 June 1990
Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise
ML17251A4791989-04-14014 April 1989
Prv Block Valve Thrust Calculation.
1997-09-19
[Table view] |
Text
I~CALCULATIONALSUMMARYSHEET(CSS)20&97-3(12/g&)DOCUMENTIDENTIFIER86-1234820-01TiTLELOWTEMPERATUREOVERPRESSUREANALYSES-SUMMARYREPORTPREPAREDBY:NAMEN.VASUDEVANSIGNATURE~REVIEWEDBY:NAME+QPE2/-gE~SlGRATURETITLEPrincipalEngineerDATE6/9/97cosTcENTFR41p1pREF.PAGE(s)32b.DATE@/0TMSTATEMENT:REVIEWERINDEPENDENCEPURPOSEANDSUMMARYOFRESULTS:ThisdocumentisacompletereplacementofRevision00.FramatomeTechnologiesinc.,performedthelowtemperatureoverpressureeventanalysesfortheRochesterGasandElectric(RGE)R.E.GinnaNuclearPowerStation,afterthesteamgeneratorswerereplacedwithBI/l-designedgenerators.fnthiseffort,aspectrumofLTOPeventstoboundallpossibleoperationalconfigurationsisanalyzedandtheresultscomparedtoAppendixGlimitsandtheRHRpressurelimit.Themostlimitingmassadditioncaseisacasewithonechargingpumpturnedonwhentheprimarysystemisat60'FwithoneRCpumprunning.Thiscaseresultedinapeakreactorvesselpressureof554.3psiawhichistheAppendixGlimitatthistemperature.Themostlimitingheatadditioncaseiswiththeprimarysystemat60'F,withaninitialpressureof329.7psia.OneRCpumpisturnedonwiththesecondarysystematatemperatureof50'Fhigherthantheprimary.Thepeakreactorvesselpressureinthistransientis551.3psiawhichisbelowtheAppendixGlimitof554.71ThelimitingeventfortheRHRsystemoccursat280'F,whentwoRHRpumpsarerunningwithacapacityof2000gpmtotal.inthisheatadditioncase,thepeakRHRsystempressurereachedis663.7psiacomparedwithanallowabieof674.7psia.THEFOLLOWINGCOMPUTERCODESHAVEBEENUSEDINTHISDOCUMENT:YENDOR'SDOCUMENTREYIEWBplg'CI4Q0APPROVEOSUBMITFINALOOCUMENTMANUFACZUR',NOMAyPROCEEOAPRRCVEDASNOTED~MARECHAIIOES>'IC.IIIDSUSMIIPARLDDGC'IENEMAIIIJ.PACEIIIINOMATPRCCEEOASAPPGPVEONOTAI'PROVEO~CORRECTANORESUBMITREVIFWNOTREOUlREO~MANUFACTURINQMAYPROCEEOBy,RRArR~<<lII7ROCHESTER,NYAPPROVALOFTHISOOCUMFNTOOESNOTREUEVEBUPPLIRFROMFULLCOMPUANCEWIINCONTRACTORPUSRDERREQUIREMENTSCODEIVERSION/REVRELAP5/MOD2/20/OHPCODE/VERSION/REVTHISDOCUMENTCONTAINSASSUMPTIONSTHATMUSTBEVERIFIEDPRIORTOUSEONSAFETY-RELATEDWORKYES()NO()970b240i56970b03PDRADOCK05000244PPDRIPAGE1OF&&AND32a&32b
