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| =Text= | | =Text= |
| {{#Wiki_filter:F'RIC)RITY(ACCELERATED RIDSPROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9511290100 DOC.DATE: | | {{#Wiki_filter:F'RIC)RITY (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9511290100 DOC.DATE: 95/11/20 NOTARIZED: |
| 95/11/20NOTARIZED: | | 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 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
| Rochester Gas6ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsrevisedimprovedTechSpecsreventilation filtertestingprogram.DISTRIBUTION CODEA001DCOPIESRECEIVEDLTRENCLSIZETITLE:ORSubmittal:
| | Forwards revised improved Tech Specs re ventilation filter testing program.DISTRIBUTION CODE A001D COPIES RECEIVED LTR ENCL SIZE TITLE: OR Submittal: |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| DOCKET0500024405000244RECIPIENT IDCODE/NAME PDl-1LAJOHNSON,A INTERNAFICENTEOlRR7r~DR8CBNRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | DOCKET 05000244 05000244 RECIPIENT ID CODE/NAME PDl-1 LA JOHNSON,A INTERNA FI CENTE Ol RR7r~DR8 CB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| NOACCOPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111NOTETOALL"RIDS"RECIPIENTS:
| | PLEASE HELP US TO REDUCE iVASTE!CONTACTTIIE DOCU~IENTCONTROL DESK, ROOIiI Pl-37 (EXT.504-2083)TO ELliiIINATE YOUR VAME F ROD!DISTRIBUTION LISTS FOR DOCUMENTS YOU DON"I'EED! |
| PLEASEHELPUSTOREDUCEiVASTE!CONTACTTIIE DOCU~IENTCONTROL DESK,ROOIiIPl-37(EXT.504-2083)TOELliiIINATE YOURVAMEFROD!DISTRIBUTION LISTSFORDOCUMENTS YOUDON"I'EED!
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 AND ROCHEST'ER GAS AND ELECTRIC CORPORATION |
| TOTALNUMBEROFCOPIESREQUIRED:
| | ~89 FAST AVENUE, ROCHESTER, N.Y Idbf9-0001 ARFA CODE716 546-2700 ROBERT C.MECREDY Vice President Nvdear Operations November 20, 1995 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555 |
| LTTR12ENCL11 ANDROCHEST'ER GASANDELECTRICCORPORATION
| |
| ~89FASTAVENUE,ROCHESTER, N.YIdbf9-0001 ARFACODE716546-2700ROBERTC.MECREDYVicePresident NvdearOperations November20,1995U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-1Washington, D.C.20555 | |
|
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| ==Subject:== | | ==Subject:== |
| Conversion toImprovedTechnical Specifications Ventilation FilterTestingProgramR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | Conversion to Improved Technical Specifications Ventilation Filter Testing Program R.E.Ginna Nuclear Power Plant Docket No.50-244 Ref.(a): Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
|
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseConversion toImprovedTechnical Specifications, datedMay26,1995. | | Application for Amendment to Facility Operating License Conversion to Improved Technical Specifications, dated May 26, 1995. |
|
| |
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| ==DearMr.Johnson:== | | ==Dear Mr.Johnson:== |
| ByReference (a),RG&Eproposedtoimplement aVentilation FilterTestingProgram(VFTP)aspartoftheconversion toImprovedTechnical Specifications (ITS).Basedonnumerousconversations betweenNRCstaffandRG&E,theproposedVFTPhasbeenrevised.Therefore, enclosedpleasefindacopyoftheITSforGinnaStationwhichcontainstherevisedVFTPthatincorporates allcommentsreceivedtodate.PleasecontactMarkFlahertyat716-724-8512 ifyouhaveanyfurtherquestions.
| | By Reference (a), RG&E proposed to implement a Ventilation Filter Testing Program (VFTP)as part of the conversion to Improved Technical Specifications (ITS).Based on numerous conversations between NRC staff and RG&E, the proposed VFTP has been revised.Therefore, enclosed please find a copy of the ITS for Ginna Station which contains the revised VFTP that incorporates all comments received to date.Please contact Mark Flaherty at 716-724-8512 if you have any further questions. |
| VeryulyyoursI%0.',Qea'QQ.'wQl&Q0EAS,O'Q'~,QUQQO'CK',Pl,nat0L.L.I'IAttachment RobertC.Mecrdyxc:U.S.NuclearRegulatory Commission Mr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission (w/oattachment)
| | Very uly yours I%0.',Qea'QQ.'wQ l&Q 0 EAS , O'Q'~,QU QQ O'CK', Pl ,na t 0 L.L.I'I Attachment Robert C.Mecr dy xc: U.S.Nuclear Regulatory Commission Mr.Allen R.Johnson (Mail Stop 14B2)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission (w/o attachment) |
| Mr.CarlSchulten(MailStop011E22)OfficeofTechnical Specifications BranchWashington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA194att~~o 0-8GinnaSeniorResidentInspector p0}} | | Mr.Carl Schulten (Mail Stop 011E22)Office of Technical Specifications Branch Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 194att~~o 0-8 Ginna Senior Resident Inspector p0}} |
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Category:CORRESPONDENCE-LETTERS
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Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
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Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
IR 05000244/19992011999-09-24024 September 1999
Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld
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Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
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ML17265A6611999-05-24024 May 1999
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Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
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ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
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ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
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Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
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ML17265A7631999-10-0505 October 1999
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ML17265A7641999-10-0505 October 1999
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ML20212J3561999-09-30030 September 1999
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ML20212J3801999-09-30030 September 1999
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IR 05000244/19990051999-09-24024 September 1999
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Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
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Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
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ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
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ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
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Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
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Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
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Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
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Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
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Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
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Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
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Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
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Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
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1999-09-30
[Table view] |
Text
F'RIC)RITY (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9511290100 DOC.DATE: 95/11/20 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards revised improved Tech Specs re ventilation filter testing program.DISTRIBUTION CODE A001D COPIES RECEIVED LTR ENCL SIZE TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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~89 FAST AVENUE, ROCHESTER, N.Y Idbf9-0001 ARFA CODE716 546-2700 ROBERT C.MECREDY Vice President Nvdear Operations November 20, 1995 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555
Subject:
Conversion to Improved Technical Specifications Ventilation Filter Testing Program R.E.Ginna Nuclear Power Plant Docket No.50-244 Ref.(a): Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License Conversion to Improved Technical Specifications, dated May 26, 1995.
Dear Mr.Johnson:
By Reference (a), RG&E proposed to implement a Ventilation Filter Testing Program (VFTP)as part of the conversion to Improved Technical Specifications (ITS).Based on numerous conversations between NRC staff and RG&E, the proposed VFTP has been revised.Therefore, enclosed please find a copy of the ITS for Ginna Station which contains the revised VFTP that incorporates all comments received to date.Please contact Mark Flaherty at 716-724-8512 if you have any further questions.
Very uly yours I%0.',Qea'QQ.'wQ l&Q 0 EAS , O'Q'~,QU QQ O'CK', Pl ,na t 0 L.L.I'I Attachment Robert C.Mecr dy xc: U.S.Nuclear Regulatory Commission Mr.Allen R.Johnson (Mail Stop 14B2)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission (w/o attachment)
Mr.Carl Schulten (Mail Stop 011E22)Office of Technical Specifications Branch Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 194att~~o 0-8 Ginna Senior Resident Inspector p0
