ML17265A488: Difference between revisions

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=Text=
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{{#Wiki_filter:CATEGORY j.
{{#Wiki_filter:CATEGORY j.
REGULA~ RY INFORMATION       DISTRIBUTI       SYSTEM (RIDS)
REGULA~ RY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9812240047           DOC.DATE: 98/12/17 NOTARIZED: NO                       DOCKET FACIL:50-244 robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                       G 05000244 AUTH. NAME.,~~ 'A'UTHOR AFFILIATION MECREDY,R.C.         Rocnester Gas S Electric Corp.
ACCESSION NBR:9812240047 DOC.DATE: 98/12/17 NOTARIZED: NO FACIL:50-244 robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
RECIP.NAME           RECIPIENT AFFILIATION VISSING,G.S.
AUTH.NAME.,~~ 'A'UTHOR AFFILIATION MECREDY,R.C.
Rocnester Gas S Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
DOCKET 05000244


==SUBJECT:==
==SUBJECT:==
Info       ms DISTRIBUTION CODE: AOIID COPIES RECEIVED:LTR TITLE: Generic     Ltr 88-20 re
Info ms DISTRIBUTION CODE: AOIID COPIES RECEIVED:LTR
                                                              )
)
Individual Plant Evaluations ENCL  g    SIZE:
ENCL g SIZE:
NOTES:License Exp     date in accordance with 10CFR2,2.109(9/19/72).                     05000244 E
TITLE: Generic Ltr 88-20 re Individual Plant Evaluations NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
RECIPIENT           COPIES              RECIPIENT              COPIES ID CODE/NAME         LTTR ENCL         ID CODE/NAME         LTTR ENCL PD1-1 PD                                VISSING,G.
05000244 E
INTERNAL: ACRS HOUSTON,                              AEOD/SPD/RRAB C NTER                            NRR/DRPE/PD1-3 NRR/DSSA/SPSB RES/DST/IPEEE                            RES/PRAB RGN 1                                    RGN 2 RGN 3                                    RGN 4 EXTERNAL: LITCO-BRYCE,J.                             NOAC NRC PDR t) Ptit3)
RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: ACRS HOUSTON, C NTER RES/DST/IPEEE RGN 1 RGN 3 COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING,G.
                                                                      ~">pp[pil',
AEOD/SPD/RRAB NRR/DRPE/PD1-3 NRR/DSSA/SPSB RES/PRAB RGN 2 RGN 4 COPIES LTTR ENCL EXTERNAL: LITCO-BRYCE,J.
giiu NOTE TO ALL "RIDS" RECIPIENTS:
NRC PDR NOAC
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR               19   ENCL
~">pp[pil', t) Ptit3) giiu NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL


C'l ANO ROCHESTER GAS AND ELECTRIC CORPORATION 69 EASTAVENUE, ROCHESTER, N.Y. 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nucieor Operotions December 17, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
C'l
 
ANO ROCHESTER GAS ANDELECTRIC CORPORATION 69 EASTAVENUE, ROCHESTER, N.Y. 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nucieor Operotions December 17, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555


==Subject:==
==Subject:==
Internal Flooding Individual Plant Examination per Generic Letter 88-20 Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Internal Flooding Individual Plant Examination per Generic Letter 88-20 Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244


==Dear Mr. Vissing:==
==Dear Mr. Vissing:==
 
In Reference (a), RG&E stated that the revised internal flooding evaluation which addressed NRC issues raised in a Request For Additional Information (RAI) dated February 23, 1985 (Reference (b)) would be submitted to the NRC by December 31, 1998. The purpose ofthis letter is to extend this commitment date until February 15, 1999 for the reasons listed below.
In Reference (a), RG&E stated that the revised internal flooding evaluation which addressed NRC issues raised in a Request For Additional Information (RAI) dated February 23, 1985 (Reference (b)) would be submitted to the NRC by December 31, 1998. The purpose of this letter is to extend this commitment date until February 15, 1999 for the reasons listed below.
The internal flooding evaluation is being performed primarily by an outside vendor who also performed the internal fire evaluation submitted previously. A draft internal flooding evaluation report has been prepared by the vendor and is currently undergoing RG&E review. In an attempt to streamline the NRC review, the report is being revised to match exactly with the remainder of the Level 1 Probabilistic Safety Assessment (PSA) submitted per Reference (c). This willalso support long-term maintenance ofthe PSA project. In addition, the internal flooding results are being organized such that they can be inserted into the Ginna Station risk monitor which RG&E has previously implemented.
The internal flooding evaluation is being performed primarily by an outside vendor who also performed the internal fire evaluation submitted previously. A draft internal flooding evaluation report has been prepared by the vendor and is currently undergoing RG&E review. In an attempt to streamline the NRC review, the report is being revised to match exactly with the remainder of the Level 1 Probabilistic Safety Assessment (PSA) submitted per Reference (c). This will also support long-term maintenance of the PSA project. In addition, the internal flooding results are being organized such that they can be inserted into the Ginna Station risk monitor which RG&E has previously implemented. These efforts require additional time such that the previous commitment date cannot be met.
These efforts require additional time such that the previous commitment date cannot be met.
Ifyou have   any questions in this matter, please contact Mr. Mark Flaherty, Manager, Configuration Support at (716) 771-3150.
Ifyou have any questions in this matter, please contact Mr. Mark Flaherty, Manager, Configuration Support at (716) 771-3150.
Very truly yours, Robert C. Mecredy pe%
Very truly yours, Robert C. Mecredy pe%
98i2240047 98i217 PDR     ADOCK 05000244,'t P                     PDR   Q
98i2240047 98i217 PDR ADOCK 05000244,'t P
PDR Q


==References:==
==References:==
 
(a)
(a)   Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC, Subject), dated September 29, 1997.
Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC, Subject), dated September 29, 1997.
(b)     Letter from A.R. Johnson, NRC, to R.C. Mecredy, RG&E, Ginna Probabilistic Risk Assessment Project Report ofMarch 15, 1994, to the MACin Response to Generic Letter 88-20, Request for Additional Information (TAC No. M74414), dated February 23, 1995.
(b)
(c)   Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,  
Letter from A.R. Johnson, NRC, to R.C. Mecredy, RG&E, Ginna Probabilistic Risk Assessment Project Report ofMarch 15, 1994, to the MACin Response to Generic Letter 88-20, Request forAdditionalInformation (TACNo. M74414), dated February 23, 1995.
(c)
Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,  


==Subject:==
==Subject:==
Generic Letter 88-20, Level 1 Probabilistic Safety Assessment (PSA), dated January 15, 1997.
Generic Letter 88-20, Level 1 Probabilistic Safety Assessment (PSA), dated January 15, 1997.
MDF/113 xc:   U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14B2)
MDF/113 xc:
PWR Project Directorate I-1 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}}
U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector}}

Latest revision as of 09:28, 8 January 2025

Extends Commitment Date Re Internal Flooding Ipe,Per GL 88-20,until 990215 for Listed Reasons
ML17265A488
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/17/1998
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-20, NUDOCS 9812240047
Download: ML17265A488 (4)


Text

CATEGORY j.

REGULA~ RY INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR:9812240047 DOC.DATE: 98/12/17 NOTARIZED: NO FACIL:50-244 robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

AUTH.NAME.,~~ 'A'UTHOR AFFILIATION MECREDY,R.C.

Rocnester Gas S Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

DOCKET 05000244

SUBJECT:

Info ms DISTRIBUTION CODE: AOIID COPIES RECEIVED:LTR

)

ENCL g SIZE:

TITLE: Generic Ltr 88-20 re Individual Plant Evaluations NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 E

RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: ACRS HOUSTON, C NTER RES/DST/IPEEE RGN 1 RGN 3 COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING,G.

AEOD/SPD/RRAB NRR/DRPE/PD1-3 NRR/DSSA/SPSB RES/PRAB RGN 2 RGN 4 COPIES LTTR ENCL EXTERNAL: LITCO-BRYCE,J.

NRC PDR NOAC

~">pp[pil', t) Ptit3) giiu NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 19 ENCL

C'l

ANO ROCHESTER GAS ANDELECTRIC CORPORATION 69 EASTAVENUE, ROCHESTER, N.Y. 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nucieor Operotions December 17, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Internal Flooding Individual Plant Examination per Generic Letter 88-20 Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

In Reference (a), RG&E stated that the revised internal flooding evaluation which addressed NRC issues raised in a Request For Additional Information (RAI) dated February 23, 1985 (Reference (b)) would be submitted to the NRC by December 31, 1998. The purpose ofthis letter is to extend this commitment date until February 15, 1999 for the reasons listed below.

The internal flooding evaluation is being performed primarily by an outside vendor who also performed the internal fire evaluation submitted previously. A draft internal flooding evaluation report has been prepared by the vendor and is currently undergoing RG&E review. In an attempt to streamline the NRC review, the report is being revised to match exactly with the remainder of the Level 1 Probabilistic Safety Assessment (PSA) submitted per Reference (c). This willalso support long-term maintenance ofthe PSA project. In addition, the internal flooding results are being organized such that they can be inserted into the Ginna Station risk monitor which RG&E has previously implemented.

These efforts require additional time such that the previous commitment date cannot be met.

Ifyou have any questions in this matter, please contact Mr. Mark Flaherty, Manager, Configuration Support at (716) 771-3150.

Very truly yours, Robert C. Mecredy pe%

98i2240047 98i217 PDR ADOCK 05000244,'t P

PDR Q

References:

(a)

Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC, Subject), dated September 29, 1997.

(b)

Letter from A.R. Johnson, NRC, to R.C. Mecredy, RG&E, Ginna Probabilistic Risk Assessment Project Report ofMarch 15, 1994, to the MACin Response to Generic Letter 88-20, Request forAdditionalInformation (TACNo. M74414), dated February 23, 1995.

(c)

Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,

Subject:

Generic Letter 88-20, Level 1 Probabilistic Safety Assessment (PSA), dated January 15, 1997.

MDF/113 xc:

U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14B2)

PWR Project Directorate I-1 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector