ML17264A950
| ML17264A950 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/08/1997 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9707170124 | |
| Download: ML17264A950 (9) | |
Text
I CATEGORY j.
l REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
A" ACCESSION NBR:9707170124 DOC.DATE: 97/07/08 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna.Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas !'lectric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
SUBJECT:
Submits 30-day annual ECCS rept re error in LOCA analysis per 10CFR50.46,paragraph (a)(3)(ii).
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 T
RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
INTERNA FILE CENTE 01 DE NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL "RIDS" RECIPIENTS:
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12
AND ROCHESTER GASANDEIECTRIC CORPORATION ~ 89 EASTAVENUE, ROCHESTER, N. Y Id6fI9-000I ARFA CODE7I6 5'-2700 ROBERT C. MECREDY Vice President Nvcteor Operations July 8, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
10CFR50.46 30 Day and Annual ECCS Report R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Westinghouse letter SAE-ESI-97-340,
Subject:
10CFR50.46, Reporting Information, dated June 4,
1997.
(b)
Westinghouse letter RGE-97-200, Subject 10CFR50.46 Annual Notification and Reporting, dated April 17, 1997.
Dear Mr. Vissing:
In accordance with the requirement in 10CFR50.46, paragraph (a)(3)(ii), this 30 day and annual ECCS report is hereby submitted.
Westinghouse, the provider of LOCA analysis for the R.E.
Ginna Nuclear Power Plant, has provided RGSE with information regarding an error in the LOCA analysis that requires 30 day NRC notification (Reference a).
In addition, References (a) and (b) provide an update to the peak cladding temperature (PCT) margin for 1996 and 1997 changes.
The large break LOCA PCT has increased by 58 F
due to the misinterpretation/re-calculation of nominal initial accumulator water volume and transposition errors in transfer of code restart data.
The new large break LOCA PCT is 2158 F and is summarized in Attachment 1 to this letter.
The 58'F PCT penalty is the result of Ginna specific computer runs.
The computer runs utilized the latest code version, a bounding initial accumulator water volume, implicitlycorrects the restart data transfer errors, and corrects the errors reported in the 1995 Westinghouse Annual Report.
Therefore, the current PCT is the result of direct plant specific sensitivity reanalysis.
No schedule for reanalysis is proposed because Ginna specific analysis bas been completed in determining
~/
the PCT penalty.
9707i70i24 970708 PDR ADQCK 05000244 F
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The small break LOCA PCT has increased by 10 F due to an error in the fuel rod initialization process.
The new small break LOCA PCT is 1323 F and is summarized in Attachment 1 to this letter.
Very truly yours, Robert C. Mecredy Attachment RWE/465 xc:
Mr. Guy Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
SUMMARY
JULY 1997 UPDATE
L
~
SUMMARY
Small Break LOCA R.E.
Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:
NOTRUMP Fuel:
OFA Fg = 2.50 F~ = 1.75 SGTP =
15%'nalysis of Record (6/95) (effective 6/96) 1995 10CFR50.46 Model Assessments 1.
NOTRUMP Specific Enthalpy Error 2.
SALIBRARY Double Precision Errors PCT = 1308'F dPCT = 20 F dPCT = -15~F 1996 10CFR50.46 Model Assessments 1.
SBLOCA Fuel Rod Initialization Error
~PCT = +10'F 1997 10CFR50.46 Model Assessment 1.
none Other margin allocations 1.
none Licensing Basis zPCT = 0' 4PCT = 0 F PCT = 1323 F Revision Date:
7/97
SUMMARY
Large Break LOCA R.E.
Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:
UPI SECY Fuel:
OFA Fg = 2.45 F~ = 1.75 SGTP = 154 Analysis of Record (5/95) (effective 6/96) 1995 10CFR50.46 Model Assessments 1.
Fixed heat transfer node assignment error/Accumulator water injection error PCT = 2051 F aPCT = 48 F 1996 10CFR50.46 Model Assessments 1.
none dPCT = O~F 1997 10CFR50.46 Model Assessments 1.
Accumulator Initial Water Volume Restart Data Transposition Error Plant Specific Analytical Reassessment of 1995 Model Assessments 10CFR50.59 Evaluations 1.
Service Water Temp.
~ 30'F (1997 evaluation; SEV-1090)
Licensing Basis aPCT = 58~F dPCT = 1F PCT = 2158 F Revision Date:
7/97
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