ML17262B093
| ML17262B093 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/17/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9211250135 | |
| Download: ML17262B093 (7) | |
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ACCESSION NBR:9211250135 DOC.DATE: 92/11/17 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear plant, Unit 1, Rochester G
AUTH"NP41E AUTHOR AFFILIATION MEECREDY,R.C.
Rochester Gas,6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSONFA.R.
Project Directorate I-3
SUBJECT:
Submits 10CFR50.46 annual ECCS rept. Small break LOCA PCT increased by 10 F since issuance of 910725 30-day ECCS evaluation model change rept. Current PCTs for facility listed on encl.
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ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER N. K 14649-0001 ROBERT C MECREDY Vice President Cinna Nuclear Production November 17, 1992 TELEPHONE ArtEAccmE T le 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
10CFR50.46 Annual ECCS Report R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):
RG&E letter from R.
C. Mecredy to A. R. Johnson,
- NRC,
Subject:
10CFR50.46 30 Day Report ECCS Evaluation Model Changes dated July 25, 1991 (b):
RG&E letter from R.C. Mecredy to A.R. Johnson,
- NRC,
Subject:
ECCS Evaluation Including the Effects of Upper Plenum Injection, dated Nov. 5, 1992
Dear Mr. Johnson:
In accordance with the requirement in 10CFR50.46 paragraph (a)(3)(ii), the following annual report is hereby submitted.
Westinghouse, the provider of LOCA analyses for the Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna.
The large break LOCA PCT has increased by 27'F since the issuance of Reference (a) report.
The increase is due to resolution of a modeling inconsistency associated with accumulator/SI interaction for Ginna.
The new large break LOCA PCT becomes 1986 F.
The small break LOCA PCT has increased by 10'F since the issuance of the Reference (a) report.
The increase is associated with thimble plug removal at Ginna.
The new small break LOCA PCT becomes 1234'F.
Attachment 1 to this letter summarizes the current PCTs for Ginna.
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9211250135 92iii7 PDR ADOCK 05000244
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This is based on the currently approved model and will be replaced by the new Upper Plenum Injection model, submitted by reference (b), upon NRC approval.
Very truly yours, Robert C. Mecredy RWEi265 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
ATTACHMENT 1 LOCA PCT SUMMARIES
Large Break LOCA R.E.
Ginna A.
B.
C.
D.
E.
F.
Analysis of record 1.
UPI penalty 2.
RIP penalty Prior LOCA Model Assignments 1989 Prior LOCA Model Assianments 1990 Prior LOCA Model Assignments 1991 LOCA Model Assignment 1992 1.
Accumulator/SI Interaction Model 10CFR50.59 Safety Evaluations 1.
Fuel reconstitution (1990 evaluation)
Licensing Basis PCT = 1871~F dPCT = +6~F hPCT = +3~F dPCT = +2~F
~PCT = O~F dPCT = +76~F hPCT = +27~F dPCT = +1~F PCT = 1986~F Potential Issues Temporary Allocation of Margin ~PCT = +140'F Licensing Basis
+ Temporary Allocation PCT = 2126'F
Small Break LOCA R.E. Ginna A.
Analysis of record B.
Prior LOCA Model Assignments 1989 C.
Prior LOCA Model Assignment 1990 D.
Prior LOCA Model Assignment 1991 E.
LOCA Model Assignment 1992 PCT = 1092~F
~PCT = OoF zPCT = O~F dPCT = +77~F hPCT = O~F F.
10CFR50.59 Safety Evaluations 1.
AFW enthalpy delay (1989 evaluation) aPCT = +11 F
2.
MFIV closure delay (1990 evaluation)
~PCT = +43 F
3.
Fuel reconstitution (1990 evaluation)
~PCT = +1'F 4.
Thimble Plug Deletion (1991 evaluation)
~PCT = +10'F Licensing Basis PCT = 1234'F Potential Issues Temporary Allocation of Margin ~PCT = O' Licensing Basis
+ Temporary Allocation PCT = 1234'F