ML17265A674

Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT

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 1 A,

R>~GULATO Y INFORMATION DISTRIBUTION aY'STEM" (RIDS)

ACCESSION NBR:9906210060 DOC.DATE: 99/06/15 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 8 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

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). 05000244 E RECIPIENT . COPIES RECIPIENT COPIES ID 'CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 LA 1 1 LPD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL CENTER 01 1 1 NRR/DE/EEIB 1 1 NRR/DE/EMCB 1 1 NRR/DE/EMEB 1 .1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NRR/SPSB JUNG,I 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 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

<I t

<<llII"',llllllll'rw IIIIIIItIIIt IIIZiZi ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001 ROBERT C. MECREDY

%ha ~ 0 to~

Vice President TELEPHONE Nuclear Operations Group 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, Robert C. Mecredy

@oh ii I'~l 4 ) 3 Eri9062i0060 9906%5 PDR ADGCK

' 05000244

( P PDR

I bh b If ,, b r

o

Attachment xc'r. Guy Project Vissing (Mail Stop Directorate I-1 SC2)

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

SUMMARY

JUNE 1999 UPDATE

ATTACHMENT 1 LOCA PCT

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) PCT = 2051 F 1995 10CFR50.46 Model Assessments

1. Fixed heat transfer node assignment error/Accumulator water injection error 6PCT = 48 F 1996 10CFR50.46 Model Assessments

1. none ~PCT = O' 1997 10CFR50.46 Model Assessment

1. Accumulator Initial Water Volume hPCT = 58~F Restart Data Transportation Error Plant Specific Analytical Reassessment of 1995 Model Assessments

2. Accumulator Initial Water Vol. = 1125 hPCT = -25 F Transition Boiling Heat Transfer ft'.

1-D aPCT = -13 F Error

4. Vessel Channel DX Error ~PCT = 18~F

5. Input Consistency ~PCT = -41'F 1998 10CFR50. 46 Model Assessments

1. none ~PCT = O' 10CFR50.59 Evaluations

1. Service Water Temp. >

evaluation; SEV-1090)30'1997

~PCT = 1'F Other Margin Allocations

1. none ~PCT = O' Licensing Basis dPCT = 2097 F Revision Date: 6/99

ATTACHMENT 1 LOCA PCT

SUMMARY

Small Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model: NOTRUMP Fuel: OFA F~ = 2.50 F, = 1.75 SGTP =

of Record (6/95) (effective 6/96) 15'nalysis PCT = 1308~F 1995 10CFR50.46 Model Assessments

1. NOTRUMP Specific Enthalpy Error 4PCT = 20 F

2. SALIBRARY Double Precision Errors aPCT = -15'F 1996 10CFR50.46 Model Assessments

1. SBLOCA Fuel Rod Initialization Error hPCT = +10~F 1997 10CFR50.46 Model Assessment

1. none aPCT = 0 F 1998 10CFR50.46 Model Assessments

1. none zPCT = OF 10CFR50.59 Evaluations

1. Annular Axial Pellets aPCT = 10 F (1997 evaluation; SEV-1108)

Other Margin Allocations

1. none ~PCT = O' Licensing Basis 6PCT = 1333 F Revision Date: 6/99