ML17265A674
| ML17265A674 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/15/1999 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9906210060 | |
| Download: ML17265A674 (7) | |
Text
CATEGORY
SUBJECT:
Submits annual ECCS rept IAW 10CFR50.46(a)
(3) (ii) requirements. There have been no change to large break LOCA PCT 6 small break LOCA PCT.
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).
1 A,
R>~GULATO Y INFORMATION DISTRIBUTION aY'STEM" (RIDS)
ACCESSION NBR:9906210060 DOC.DATE: 99/06/15 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 8 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
DOCKET 05000244 05000244 E
RECIPIENT ID 'CODE/NAME LPD1-1 LA VISSING,G.
COPIES LTTR ENCL 1
1 1
1 RECIPIENT ID CODE/NAME LPD1-1 PD COPIES LTTR ENCL 1
1 INTERNAL CENTER 01 NRR/DE/EMCB NRR/DSSA/SPLB NRR/SPSB JUNG,I OGC/HDS3 1
1 1
1 1
1 1
1 1
0 NRR/DE/EEIB NRR/DE/EMEB NRR/DSSA/SRXB NUDOCS-ABSTRACT 1
1 1
.1 1
1 1
1 EXTERNAL: NOAC 1
1 NRC PDR 1
1 D
0
'E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTZON 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:
LTTR 14 ENCL 13
t IIIIIIItIIIt IIIZiZi
<I<<llII"',llllllll'rw
%ha ~ 0 to~
ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001 ROBERT C. MECREDY Vice President Nuclear Operations Group TELEPHONE ARE* COOE Tle 546-2700 June 15, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
10CFR50.46 Annual ECCS Report R.E. Ginna Nuclear Power Plant Docket No.
50-244 Ref. (a):
Westinghouse letter RGE-99-206,
Subject:
10CFR50.46, Annual, Notification and Reporting for
- 1998, dated March 5, 1999.
Dear Mr. Vissing:
In accordance with the requirement in 10CFR50.46, paragraph (a)(3)(ii), this annual ECCS report is hereby submitted.
Westinghouse, provider of LOCA analysis for the R.E.
Ginna Nuclear Power Plant, has provided RGEE with an update to the peak cladding temperature (PCT) margin for Ginna Station (Reference a).
There has been no change to the large break LOCA PCT.
The large break LOCA PCT is 2097'F and is summarized in Attachment 1
to this letter.
There has been no change to the small break LOCA'PCT.
The small break LOCA PCT is 1333'F and is summarized in Attachment 1 to this letter.
Very truly yours, ii I
)
3
'~l 4
(
Eri9062i0060 9906%5 PDR ADGCK 05000244 P
PDR Robert C. Mecredy
@oh
I bh b If o
,, b r
Attachment xc'r.
Guy Vissing (Mail Stop SC2)
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
JUNE 1999 UPDATE
SUMMARY
Large Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:
UPI SECY
" Fuel:
OFA F{} =
2
~ 45 F 8 =
1 75 SGTP
= 15o Analysis of Record (5/95)
(effective 6/96) 1995 10CFR50.46 Model Assessments 1.
Fixed heat transfer node assignment error/Accumulator water injection error 1996 10CFR50.46 Model Assessments 1.
none PCT
= 2051 F 6PCT
= 48 F
~PCT
=
O' 1997 10CFR50.46 Model Assessment 1.
Accumulator Initial Water Volume Restart Data Transportation Error Plant Specific Analytical Reassessment of 1995 Model Assessments 2.
Accumulator Initial Water Vol.
= 1125 ft'.
1-D Transition Boiling Heat Transfer Error 4.
Vessel Channel DX Error 5.
Input Consistency 1998 10CFR50. 46 Model Assessments 1.
none 10CFR50.59 Evaluations 1.
Service Water Temp.
30'1997 evaluation; SEV-1090)
Other Margin Allocations 1.
none hPCT
= 58~F hPCT
= -25 F aPCT
= -13 F
~PCT
= 18~F
~PCT
= -41'F
~PCT
= O'
~PCT
= 1'F
~PCT
= O' Licensing Basis dPCT
= 2097 F Revision Date:
6/99
SUMMARY
Small Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:
NOTRUMP F~
= 2.50 F, = 1.75 Fuel:
OFA 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 1996 10CFR50.46 Model Assessments 1.
SBLOCA Fuel Rod Initialization Error 1997 10CFR50.46 Model Assessment 1.
none 1998 10CFR50.46 Model Assessments 1.
none PCT
= 1308~F 4PCT
= 20 F aPCT
= -15'F hPCT
= +10~F aPCT
=
0 F zPCT
= OF 10CFR50.59 Evaluations 1.
Annular Axial Pellets (1997 evaluation; SEV-1108)
Other Margin Allocations 1.
none aPCT
= 10 F
~PCT
= O' Licensing Basis 6PCT
= 1333 F Revision Date:
6/99