ML17256A664
| 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