ML17265A380
| ML17265A380 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/21/1998 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-04, GL-97-4, TAC-M99993, NUDOCS 9807290250 | |
| Download: ML17265A380 (5) | |
Text
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~ ~ ATEGORY REGULA Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9807290250 DOC.DATE: 98/07/21 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.,NAME.
'AUTHOR AFFILIATION MECREDY,"R.C.
Rochester Gas E Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Forwards addi info re response to GL 97-04,as requested in 980608 ltr.
C DISTRIBUTION CODE: A076D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: GL 97-04 Assurance of Sufficient Net Positive Suction Head For Emerg T
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 E
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N NOTE TO ALL nRIDSn 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:
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ANO ROCHESTER GAS ANDELECTRIC CORPORATION.89EASTAVENIJE, ROCHESTER, N.Y 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nvctear Operations July 21, 1998 U. S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate 1-1 Washington, D.C.
20555
Subject:
Response to Request for Additional Information (RAI)Related to Generic Letter 97-04 (TACNo.
M99993)
R. E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (1):
Letter from Guy S. Vissing (NRC) to Robert C. Mecredy (RG&E),
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION(RAI)RELATINGTO GENERIC LETTER97-04 RESPONSE FOR THE R. E. GINNANUCLEARPOWER PLANT(TACNO. M99993), dated June 8, 1998
Dear Mr. Vissing:
By Reference 1, the NRC staff requested additional information regarding the Response to Generic Letter 97-04 for the R. E. Ginna Nuclear Power Plant.
The attachment to this letter provides the requested information.
Robert C. Mecredy Attachment Subscribed and sworn to before me on this 21st day of July, 1998 Notary Public MARIE C. VILLfNEUVE Notary Public, State of Hew YorR Monroe County gprtltttiesipn Expires October 31, 19
'stSO7VV02SO 'stS072i PDR ADQCK 05000244 f
xc:
Mr. Guy S. Vissing (Mail Stop 1482)
Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
uestionNo.
1:
8%at is the maximum sump temperature assumed in the NPSH analyses?
Res onse to uestion No. 1:
As stated in response to item 4 in our January 6, 1998 response to GL 97-04, the sump temperature assumed in the NPSH analysis is 212'F at 14.7 psia. This was chosen such that the vapor pressure would equal the atmospheric pressure in the NPSH calculation, thus negating each other.
uestion No. 2 In response to question 5, itis stated that "although containment overpressure is not credited, a review ofcontainment pressure and temperature versus time curves indicates that containment overpressure should exist at the beginning ofSump 'B 'ecirculation.
Since Ginna Station was licensed prior to fhe publication ofRegulatory Guide l.I, and has never commitfed fo use that guide, containment overpressure could be credi ted to add margin to the NPSH calculations.
RGcKat this time has not chosen to do so." Itis the staff's position that whether or not a licensee is commifted fo RGI.I, NRC staffreview and approval should be obtained before a licensee can credit containmenf overpressure in their NPSH calculations.
Additionally,it appears to the staffthat the containment pressure and femperature curves discussedin the Generic Letter response are the peak containment pressure curves and not the minimum containment pressure curves.
Only minimunt containment pressure curves should be used to determine ifcontainment overpressure exists.
8%ich pressure curves were usedin the GL response?
Res onse to uestion No. 2:
RG&E did not use any containment environment curves to assess the adequacy ofthe RHR system NPSH for design basis events (single failure), but used 212'F at 14.7 psia, as discussed in the response to question no.
1 above.
We have performed evaluations ofcontainment temperature and pressure in order to provide emergency operations procedure (EOP) setpoints which are designed to address conditions which may be beyond design basis (i.e. multiple failures).
We also note that the Ginna Station license predates Regulatory Guide 1.1, and no restriction on use ofcontainment overpressure existed prior to the publication ofthat guide.
Should RG&E in the future decide to credit containment pressure in NPSH calculations we would evaluate the change in accordance with 10CFR50.59 and 10CFR50.109.