ML17256A664: Difference between revisions
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{{#Wiki_filter:I'4~~sREGULATOR) | {{#Wiki_filter:I'4~~sREGULATOR) | ||
FORMATION DISTRIBUTION SEM,(RIDS) | |||
'ACCESSION NBR:8305060271 DOC~DATE:83/04/28NOTARIZED: | |||
NODOCKETFACIL:50244RobertEmme,tGinnaNuclearPlant~UnfitiiRochester G05000244'AUTHBYNAMEAUTHORAFFILIATION MAIERgJ,E~Rochester Gas8ElectricCorp'ECIP | |||
~NAMERECIPIENT AFFILIATION CRUTCHFIELDgD | |||
~Operating ReactorsBranch5 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards," | Forwards,"Containment VesselEvaluation ofDomeLinerLStudsi"reSEP,Topic III-"7'~"loadCombinations (Containment LinerAnalysis) | ||
~,"DISTRIBUTION CODEtA035S,COPIES RECEIVED:LTR "ENCLSIZE+..'baE | |||
%%@IS.((/~Q/TITlE:ORSubmittal: | |||
SEPTopicNOTES;NRR/DI./SEP 1cy,05000244RECIPIENT IDCODE/NAME NRRORB5BC01INTERNAL: | |||
NRR/DL/ORAB 11EGFJ04COPIESLTTRENCI-33111111RECIPIENT IDCODE/NAME NRR/DL/SEPB 12NRR/DSI/CSB07RGN1COPIESLTTRENCL3-3111EXTERNAL: | |||
ACRS14NRCPDR02NOTES:e1111LPDRNTIS0351111(TOTALNUMBEROFCOPIESREQUIRED: | |||
LTTR21ENCl21 | |||
~IrvL~ | ~IrvL~ | ||
~~rc/tIIIIIIIIIIIII// | ~~rc/tIIIIIIIIIIIII/ | ||
/IIIIIIIIIII AHDI/Illlj/ggl!I IIII!I!IIIIII | |||
/IIIIIII//I//'IIIIIIIIIII ROCHESTER GASVOHt48<MAILERVicePreeident ANDELECTRICCORPORATION | |||
~89EASTAVENUE,ROCHESTER, N.Y.146491TEI.EPHOHE AREAcoDETle546.2700April28,1983DirectorofNuclearReactorRegulation Attention: | |||
Mr.DennisM.Crutchfield, ChiefOperating ReactorsBranchNo.5U.S.NuclearRegulatory Commission Washington, D.C.20555 | |||
==Subject:== | ==Subject:== | ||
SEPTopicIII-7.B,LoadCombinations( | SEPTopicIII-7.B,LoadCombinations (Containment LinerAnalysis) | ||
R.E.GinnaNuclearPowerPlantDocket50-244 | |||
==DearMr.Crutchfield:== | ==DearMr.Crutchfield:== | ||
Enclosedisareport" | |||
Enclosedisareport"Containment VesselEvaluation ofDomeLinerandStuds"preparedbyGilbert/Commonwealth forRochester GasandElectric. | |||
Thepurposeofthereportistodescribetheanalysisperformed toevaluatethepost-accident behaviorofthecontainment linerandstuds.Theconclusion reachedinthereportisthatfailureofsomestudsincertainareasoftheliner,althoughnotexpected, ispossible. | |||
However,itisdetermined thatthiscondition wouldnotcausetearingoftheliner,andthuswouldnotpreventthelinerfrommaintaining itspost-accident leak-tight integrity. | |||
Asapointofclarification, itshouldbenotedthattheaccidentpressureandtemperature profilesusedinNUREG/CR-2580 (theSMA/LLLlineranalysis) areforthesteamlinebreakcondition, ratherthanaLOCA,asimplied.ThisisobviousfromtheLLLanalysispresented inAppendixAtotheSafetyEvaluation ReportforSEPTopicsVI-2.DandVI-3,MassandEnergyReleaseforPipeBreaksInsideContainment", | |||
November3,1981.Nonetheless, asshownbytheattachedanalysis, thelinerintegrity willbemaintained forallaccidentsituations. | |||
Verytrulyyours,JnE.MaierC!83050b027i 830428jPDRADOCK05000244PPDR A'I~~Ir1'f'N,rrh~'1IrI}} | |||
Revision as of 12:50, 29 June 2018
| ML17256A664 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 04/28/1983 |
| From: | MAIER J E ROCHESTER GAS & ELECTRIC CORP. |
| To: | CRUTCHFIELD D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17256A666 | List: |
| References | |
| TASK-03-07.B, TASK-3-7.B, TASK-RR NUDOCS 8305060271 | |
| Download: ML17256A664 (4) | |
Text
I'4~~sREGULATOR)
FORMATION DISTRIBUTION SEM,(RIDS)
'ACCESSION NBR:8305060271 DOC~DATE:83/04/28NOTARIZED:
NODOCKETFACIL:50244RobertEmme,tGinnaNuclearPlant~UnfitiiRochester G05000244'AUTHBYNAMEAUTHORAFFILIATION MAIERgJ,E~Rochester Gas8ElectricCorp'ECIP
~NAMERECIPIENT AFFILIATION CRUTCHFIELDgD
~Operating ReactorsBranch5
SUBJECT:
Forwards,"Containment VesselEvaluation ofDomeLinerLStudsi"reSEP,Topic III-"7'~"loadCombinations (Containment LinerAnalysis)
~,"DISTRIBUTION CODEtA035S,COPIES RECEIVED:LTR "ENCLSIZE+..'baE
%%@IS.((/~Q/TITlE:ORSubmittal:
SEPTopicNOTES;NRR/DI./SEP 1cy,05000244RECIPIENT IDCODE/NAME NRRORB5BC01INTERNAL:
NRR/DL/ORAB 11EGFJ04COPIESLTTRENCI-33111111RECIPIENT IDCODE/NAME NRR/DL/SEPB 12NRR/DSI/CSB07RGN1COPIESLTTRENCL3-3111EXTERNAL:
ACRS14NRCPDR02NOTES:e1111LPDRNTIS0351111(TOTALNUMBEROFCOPIESREQUIRED:
LTTR21ENCl21
~IrvL~
~~rc/tIIIIIIIIIIIII/
/IIIIIIIIIII AHDI/Illlj/ggl!I IIII!I!IIIIII
/IIIIIII//I//'IIIIIIIIIII ROCHESTER GASVOHt48<MAILERVicePreeident ANDELECTRICCORPORATION
~89EASTAVENUE,ROCHESTER, N.Y.146491TEI.EPHOHE AREAcoDETle546.2700April28,1983DirectorofNuclearReactorRegulation Attention:
Mr.DennisM.Crutchfield, ChiefOperating ReactorsBranchNo.5U.S.NuclearRegulatory Commission Washington, D.C.20555
Subject:
SEPTopicIII-7.B,LoadCombinations (Containment LinerAnalysis)
R.E.GinnaNuclearPowerPlantDocket50-244
DearMr.Crutchfield:
Enclosedisareport"Containment VesselEvaluation ofDomeLinerandStuds"preparedbyGilbert/Commonwealth forRochester GasandElectric.
Thepurposeofthereportistodescribetheanalysisperformed toevaluatethepost-accident behaviorofthecontainment linerandstuds.Theconclusion reachedinthereportisthatfailureofsomestudsincertainareasoftheliner,althoughnotexpected, ispossible.
However,itisdetermined thatthiscondition wouldnotcausetearingoftheliner,andthuswouldnotpreventthelinerfrommaintaining itspost-accident leak-tight integrity.
Asapointofclarification, itshouldbenotedthattheaccidentpressureandtemperature profilesusedinNUREG/CR-2580 (theSMA/LLLlineranalysis) areforthesteamlinebreakcondition, ratherthanaLOCA,asimplied.ThisisobviousfromtheLLLanalysispresented inAppendixAtotheSafetyEvaluation ReportforSEPTopicsVI-2.DandVI-3,MassandEnergyReleaseforPipeBreaksInsideContainment",
November3,1981.Nonetheless, asshownbytheattachedanalysis, thelinerintegrity willbemaintained forallaccidentsituations.
Verytrulyyours,JnE.MaierC!83050b027i 830428jPDRADOCK05000244PPDR A'I~~Ir1'f'N,rrh~'1IrI