ML17263A861
| ML17263A861 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/18/1994 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9412010338 | |
| Download: ML17263A861 (7) | |
Text
PRIORITY (ACCELERATED RIDS PROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION, NBR: 9412010338 DOC. DATE: 94/11/18 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.S.
Project Directorate I-3
SUBJECT:
Submits 1994 annual rept,per 10CFR50.46.Attachment 1 to ltr summarizes current peak cladding temps for plant.
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General Distribution DOCKET 05000244 P
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 R
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AND ROCHESTER GASANDElECTRIC CORRORATION ~ 89EASTAVENUE, ROCHESTER, N. Y Id849-0001 AREA CODE716 5'-2700 ROBERT C. MECREDY Vice President Huctear Operations November 18, 1994 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): Westinghouse letter NSAL-94-004U,
Subject:
10CFR50.46, Notification and Reporting Information dated February 8/
1994 (b): Westinghouse letter NSAL-94-022T,
Subject:
SBLOCTA Axial Nodalization dated October 25, 1994 (c):
RG&E letter from R.
C. Mecredy to A. R. Johnson,
- NRC,
Subject:
10CFR50.46 Annual ECCS Report dated November 18/
1993 (d):
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 1994 annual report is hereby submitted.
Westinghouse, the provider of LOCA analysis for the Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna (Ref.
a and b).
The large break LOCA PCT has decreased 6'F due to model error corrections and increased 59'F due to 10CFR50.59 Safety Evaluations.
The net change since the issuance of our last
- report, Reference (c), is an increase of 53'F, resulting in a large break LOCA PCT of 2038 The small break LOCA PCT has increased by 22'F since the issuance of the Reference (c) report due to SBLOCTA Axial Nodalization as reported in Reference (b) and decreased by 1'F due to removal of reconstituted fuel.
The net change is an increase of 21 F
resulting in a small break LOCA PCT is 1255 F.
(
'stOi2010338 94iii8 pDR AoaaK 05000244 R
PDR o0
Attachment 1 to this letter summarizes the current PCTs for the R.E.
Ginna Nuclear Power Plant.
This is based on the currently approved model and will be replaced by the new Upper Plenum Injection model, submitted by reference (d), upon NRC approval.
Very truly yours, Robert C. Mecredy RWEK351 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 Eval. Model:
81EM Fuel:
OFA FQ = 2.32 FhH = 1.66 SGTP =
15'.
Analysis of record 1.
UPI penalty 2.
RIP penalty B.
Prior LOCA Model Assignments 1989 C.
Prior LOCA Model Assignments 1990 D.
Prior LOCA Model Assignments 1991 E.
Prior LOCA Model Assignments 1992 F.
Prior LOCA Model Assignments 1993 G.
LOCA Model Assessments 1994 1.
LUCIFER Error Correction PCT = 1871~F dPCT = +6'F aPCT = +3'F hPCT = +2 F
dPCT = O' dPCT = +76~F zPCT = +27'F
~PCT = OoF hPCT = -6~F H.
10CFR50.59 Safety Evaluations 1.
Fuel reconstitution (1990 evaluation) 2.
Thimble plug deletion (1992 evaluation) 3.
Containment Fan Cooler Replacement (1993 evaluation) hPCT = +1 F (Fuel not used)
~PCT = OoF hPCT = +59~F Licensing Basis PCT = 2038'F Potential Issues Temporary Allocation of Margin ~PCT = +140 F
Licensing Basis
+ Temporary Allocation PCT = 2178'F
5 Small Break LOCA R.E.
Ginna
'val. Model:
WFLASH Fuel:
OFA FQ = 2.32 FhH = 1.66 SGTP = 124 A.
Analysis of record B.
Prior LOCA Model Assignments 1989 C.
Prior LOCA Model Assignment 1990 D.
Prior LOCA Model Assignment 1991 E.
Prior LOCA Model Assignment 1992 PCT = 1092~F dPCT = O~F dPCT = O' dPCT = +77~F dPCT = O' F.
Go Prior LOCA Model Assignment 1993 dPCT=
0 F
LOCA Model Assignment 1994 1.
Axial Nodalization, RIP Model Revision and SBLOCTA Error Correction Analysis dPCT = 22~F H.
10CFR50.59 Safety Evaluations 1.
AFW enthalpy delay (1989 evaluation) 2.
MFIV closure delay (1990 evaluation) 3.
Fuel reconstitution (1990 evaluation) 4.
Thimble Plug Deletion (1991 evaluation) 5.
Increase SGTP to 15%
Licensing Basis dPCT = +11~F hPCT = +43+F dPCT = +1~F (Fuel not used) hPCT = +10~F zPCT = O~F PCT = 1255~F Potential Issues Temporary Allocation of Margin ~PCT = O~F Licensing Basis
+ Temporary Allocation PCT = 1255 F
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