ML17261B148: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:ACCELERATED DISRIBUTIONDEMONSTRATION SYSTEMri~g~4REGULATORY INFORMATXON DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9009100295 DOC.DATE:
{{#Wiki_filter:ACCELERATED DIS RIBUTION DEMONSTRATION SYSTEM r i~g~4 REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9009100295 DOC.DATE: 90/08/28 NOTARIZED:
90/08/28NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
Rochester Gas&Electric Corp.RECXP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R.
Rochester Gas&ElectricCorp.RECXP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244 R$05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
ProjectDirectorate I-3DOCKET05000244R$05000244NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).


==SUBJECT:==
==SUBJECT:==
Listsunderstanding ofissuesutilplanningtoaddressreIcontainment integrity,per 900718telcon.DISTRIBUTXON CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
Lists understanding of issues util planning to address re I containment integrity,per 900718 telcon.DISTRIBUTXON CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
GeneralDistribution RECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
General Distribution RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSXR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPXENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTS B1 1 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFMB.~~IaQEeenmee~
NRR/DET/ECMB 9HNRR/DST8E2NRR/DST/SICB 7ENUDOCS-ABSTRACT OGC/HDS2RES/DSXR/EIB EXTERNAL:
0i~NSIC COPIES LTTR ENCL D D a (>gg)q~)~~R D$NOTE TO ALL"RIDS" RECIPIENTS:
NRCPDRCOPIESLTTRENCLRECIPXENT IDCODE/NAME PD1-3PDNRR/DOEA/OTS B11NRR/DST/SELB 8DNRR/DST/SRXB 8EOC/LFMB.~~IaQEeenmee~
PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL A D D N I I i 4)~ZuZu//'I//I/////////
0i~NSICCOPIESLTTRENCLDDa(>gg)q~)~~RD$NOTETOALL"RIDS"RECIPIENTS:
/I///I I////I///I
PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
/////Z//ZSF/ROCHESTER GAS AND ELECTRIC CORPORATION HEW Liil Oalla I'i TOE@STATE 4 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C MECREDY Vice Ptesldent Clnna Nuclear Ptoduction TELEPHONE AREA CODE 71B 546 2700 August 28, 1990 U.S.Nuclear Regulatory Commission Attention:
LTTR17ENCLADD NII i4)~ZuZu//'I//I/////////
Allen R.Johnson Project Directorate I-3 Document Control Desk Washington, D.C.20555  
/I///II////I///I
/////Z//ZSF/ROCHESTER GASANDELECTRICCORPORATION HEWLiilOallaI'iTOE@STATE489EASTAVENUE,ROCHESTER N.Y.14649-0001 ROBERTCMECREDYVicePtesldent ClnnaNuclearPtoduction TELEPHONE AREACODE71B5462700August28,1990U.S.NuclearRegulatory Commission Attention:
AllenR.JohnsonProjectDirectorate I-3DocumentControlDeskWashington, D.C.20555


==Subject:==
==Subject:==
Containment Integrity R.E.GinnaNuclearPowerPlantDocketNo.50-244
Containment Integrity R.E.Ginna Nuclear Power Plant Docket No.50-244  


==DearMr.Johnson:==
==Dear Mr.Johnson:==
InlettersdatedJuly11,1990andAugust15,1990,RG&EprovidedtotheNRCourproposedcourseofactionforresolution ofcontainment issues.Basedonthiscorrespondence, andaJuly18,1990conference callbetweentheNRCandRG&E,thefollowing isatabulation ofourunderstanding oftheissuesthatRG&Eisplanningtoaddressrelativetotheintegrity oftheGinnaStationContainment.
In letters dated July 11, 1990 and August 15, 1990, RG&E provided to the NRC our proposed course of action for resolution of containment issues.Based on this correspondence, and a July 18, 1990 conference call between the NRC and RG&E, the following is a tabulation of our understanding of the issues that RG&E is planning to address relative to the integrity of the Ginna Station Containment.
1.Takeexpeditious stepstoremovethestandingwaterfromthecontainment annularaccessarea,andmaintainitdry.2.Relativetothestructural detailbetweenthecylin-dricalwallofthecontainment andthebasemat,verifywhenandifslidingwilloccurunderdesignloadcon-ditions.Alsoevaluatetheeffectsofnoslidingonwallstresses.
1.Take expeditious steps to remove the standing water from the containment annular access area, and maintain it dry.2.Relative to the structural detail between the cylin-drical wall of the containment and the basemat, verify when and if sliding will occur under design load con-ditions.Also evaluate the effects of no sliding on wall stresses.3.Determine the effects of the bellows on the function of the tendons.Consider the bellows performing or not performing their design intent.4.Determine the capability of the tension rods to perform their functions, and assess the margins associated with this system.9009100295 900S28 PDR ADOCK 05000244 P PDI Te(P+)Pl lf (pg l" 5.Perform an assessment of the following boundary condi-tions on the overall joint design.a.Sliding condition with hinge connection.
3.Determine theeffectsofthebellowsonthefunctionofthetendons.Considerthebellowsperforming ornotperforming theirdesignintent.4.Determine thecapability ofthetensionrodstoperformtheirfunctions, andassessthemarginsassociated withthissystem.9009100295 900S28PDRADOCK05000244PPDITe(P+)Pllf(pgl" 5.Performanassessment ofthefollowing boundarycondi-tionsontheoveralljointdesign.a.Slidingcondition withhingeconnection.
b.Non-sliding condition with hinge connection.
b.Non-sliding condition withhingeconnection.
c.Partially fixed base for a and b above.6.Investigate all above issues, considering appropriate seismic and LOCA load combinations.
c.Partially fixedbaseforaandbabove.6.Investigate allaboveissues,considering appropriate seismicandLOCAloadcombinations.
7.Provide a copy of GAI Report I2347"Containment Building Tendon Investigation", and the results of the chemical analysis of the groundwater at Ginna to the NRC.We understand that the NRC will make a site visit to Ginna Station on September 5 and 6, 1990.Any concerns or action items different from those listed above should be provided to RGGE prior to that time.Very truly yours, LAS/155 Robert C.Mecr y xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}}
7.ProvideacopyofGAIReportI2347"Containment BuildingTendonInvestigation",
andtheresultsofthechemicalanalysisofthegroundwater atGinnatotheNRC.Weunderstand thattheNRCwillmakeasitevisittoGinnaStationonSeptember 5and6,1990.Anyconcernsoractionitemsdifferent fromthoselistedaboveshouldbeprovidedtoRGGEpriortothattime.Verytrulyyours,LAS/155RobertC.Mecryxc:Mr.AllenR.Johnson(MailStop14D1)ProjectDirectorate I-3Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector}}

Revision as of 13:24, 7 July 2018

Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant
ML17261B148
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/28/1990
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To: JOHNSON A R
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9009100295
Download: ML17261B148 (4)


Text

ACCELERATED DIS RIBUTION DEMONSTRATION SYSTEM r i~g~4 REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9009100295 DOC.DATE: 90/08/28 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas&Electric Corp.RECXP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R.

Project Directorate I-3 DOCKET 05000244 R$05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

SUBJECT:

Lists understanding of issues util planning to address re I containment integrity,per 900718 telcon.DISTRIBUTXON CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:

General Distribution RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSXR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPXENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTS B1 1 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFMB.~~IaQEeenmee~

0i~NSIC COPIES LTTR ENCL D D a (>gg)q~)~~R D$NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL A D D N I I i 4)~ZuZu//'I//I/////////

/I///I I////I///I

/////Z//ZSF/ROCHESTER GAS AND ELECTRIC CORPORATION HEW Liil Oalla I'i TOE@STATE 4 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C MECREDY Vice Ptesldent Clnna Nuclear Ptoduction TELEPHONE AREA CODE 71B 546 2700 August 28, 1990 U.S.Nuclear Regulatory Commission Attention:

Allen R.Johnson Project Directorate I-3 Document Control Desk Washington, D.C.20555

Subject:

Containment Integrity R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Johnson:

In letters dated July 11, 1990 and August 15, 1990, RG&E provided to the NRC our proposed course of action for resolution of containment issues.Based on this correspondence, and a July 18, 1990 conference call between the NRC and RG&E, the following is a tabulation of our understanding of the issues that RG&E is planning to address relative to the integrity of the Ginna Station Containment.

1.Take expeditious steps to remove the standing water from the containment annular access area, and maintain it dry.2.Relative to the structural detail between the cylin-drical wall of the containment and the basemat, verify when and if sliding will occur under design load con-ditions.Also evaluate the effects of no sliding on wall stresses.3.Determine the effects of the bellows on the function of the tendons.Consider the bellows performing or not performing their design intent.4.Determine the capability of the tension rods to perform their functions, and assess the margins associated with this system.9009100295 900S28 PDR ADOCK 05000244 P PDI Te(P+)Pl lf (pg l" 5.Perform an assessment of the following boundary condi-tions on the overall joint design.a.Sliding condition with hinge connection.

b.Non-sliding condition with hinge connection.

c.Partially fixed base for a and b above.6.Investigate all above issues, considering appropriate seismic and LOCA load combinations.

7.Provide a copy of GAI Report I2347"Containment Building Tendon Investigation", and the results of the chemical analysis of the groundwater at Ginna to the NRC.We understand that the NRC will make a site visit to Ginna Station on September 5 and 6, 1990.Any concerns or action items different from those listed above should be provided to RGGE prior to that time.Very truly yours, LAS/155 Robert C.Mecr y xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector