ML17262A565
| ML17262A565 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/16/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9107260144 | |
| Download: ML17262A565 (4) | |
Text
ACCELERATED STRIBUTION DEMON~
TION SYSTEM
.(
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9107260144 DOC.DATE: 91/07/16 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..
Project Directorate I-3 DOCKET 05000244 R
SUBJECT:
Informs that plant ECCS analysis, including effects of UPI will be performed using method described in Westinghouse Rept,WCAP-10924-P,Rev 2,Vol 2
6 schedule for submitting analysis will be finalized,per NRC review I!'I acceptance.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTRj ENCL O SIZE:
2-TITLE: OR Submittal:
General Distribution D
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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05000244 A
RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL NRR/DET/ECMB 7D NRR/DOEA/OTSBl1 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LFMB RES EXTERNAL: NRC DR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC COPIES LTTR ENCL D
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I 5TAte ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N. K 14649-0001 ROBERTC MECREDY Vice President Cinna Nudear Production July 16, 1991 TELEPHONE AstEAcooET16 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen RE Johnson Project Directorate I-3 Washington, D AC.
20555
Subject:
ECCS Evaluation Including the Effects of Upper Plenum Injection R.E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
NRC to RG&E letter, from J.
A. Zwolinski to R.
W. Kober, "Development of an Acceptable ECCS Evaluation Model Which Includes the Effects of Upper Plenum Injection,"
dated 2/12/85.
2.
RG&E to NRC letter, from R.
C. Mecredy to A. R. Johnson, "NRC Bulletin 88-04, Potential Safety-Related Pump Loss,"
dated 3/12/90.
3.
4 ~
NS-NRC-91-3537, "WCAP-10924-P, Revision 1; "Westinghouse Large Break LOCA Best Estimate Methodology, Volume 1;
Model Description and Validation,"
Addendum 4,
"Model Revisions
[Proprietary]," Letter from W. J. Johnson (Westinghouse) to V.
H. Wilson (NRC), dated September 5,
1990.
Letter from A.. C.
Thadani (NRC) to W.
J.
Johnson (Westinghouse),
"Acceptance for Referencing Licensing Topical Report WCAP-10924,
'Westinghouse Large Break LOCA Best Estimate Methodology,'olume 1,
'Model Description and Validation,'ddendum 4, 'Model Revisions," dated February 8, 1991.
5.
NS-NRC-91-3582, "WCAP-10924-P, Revision 2,
. Volume 2;
"Westinghouse Large Break LOCA Best Estimate Methodology:
Application to Two-Loop PWRs Equipped with Upper Plenum Injection,"
Addendum 3,
"Upper Plenum Injection Model Improvement
[Proprietary],
Letter from S.
R.
Tritch (Westinghouse) to LE Sapp (NRC), dated April 19, 1991
'ear Mr. Johnson:
' 91072~ 0.i 0g000244 9107i+
pDR s 'ADOCK 0 pDR P
Reference 1
requested Rochester Gas and Electric (RG&E) to submit an ECCS evaluation that included the effects of Upper Plenum Injection (UPI).
Reference 2 stated an analysis would be submitted in mid-lggl using the Westinghous g "1
Methodology for UPI.
This analysis would incorporate SECY-83-472 best estimate methodology.
The Westinghouse efforts have been delayed by activities related to the resolution of the decay heat code logic deviation, documented in Reference 3, and subsequent analysis activities.
The NRC provided a favorable safety evaluation report (SER) in,Reference 4.
Since it is desirable to obtain the maximum benefit
- possible, the Ginna Station ECCS analysis will be performed using the methods described in Reference 5, which provides UPI model improvements.
It is our understanding from discussions with Westinghouse that the review of this document will be completed by the end of 1991.
The RG&E schedule for submitting the analysis will be finalized following this NRC review and acceptance.
Very truly yours, Robert C.
Mec d
RWE/160 Attachment 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