ML17264A262

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Submits 1995 Annual Rept,Per Requirement in 10CFR50.46 Paragraph (a)(3)(ii).Attachment 1 to Ltr Summarizes Current Peak Cladding Temps for Plant
ML17264A262
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/27/1995
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9512010074
Download: ML17264A262 (8)


Text

P RIQRITY (ACCELERATED RIDS PROCESSIY REGULATORY INFORMATION DISTRIBUTION SYSTEM '(RIDS)

ACCESSION/NBR: 9512010074 DOC. DATE: 95/11/27 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

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

SUBJECT:

Submits 1995 annual rept,per requirement in 10CFR50.46 paragraph (a)(3)(ii).Attachment 1 to ltr summarizes current peak cladding temps for plant.

DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

General Distribution P

0 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 R

RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A TNTERNAL:~ILE CENTER 01 NR~RRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

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1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DS SA/S PLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1

1 1

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1 1

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE!CONTACTTHE DOCUMENTCONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELI~iIINATEYOUR VAWIE FROliI DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON"I'EED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 11

ANn ROCHESTER GASANDEIECTRIC CORK)RATION ~ 89 FAST AVENIJE, ROCHESTER, N. Y 14649-0001 ARFA CODE 716 546-2700 ROBERT C. MECREDY Vice President t4vcleor Operotions November 27, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson 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 NSAL-95-002,

Subject:

10CFR50.46, Notification and Reporting Information dated February 3,

1995 (b):

RG&E letter from R.

C. Mecredy to A. R. Johnson,

NRC,

Subject:

10CFR50.46 Annual ECCS Report dated November 18(

1994

Dear Mr. Johnson:

In accordance with the requirement in 10CFR50.46 paragraph (a)(3)(ii), the 1995 annual report is hereby submitted.

Westinghouse, the provider of LOCA analysis for the R.E.

Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna (Ref. a).

The large break LOCA PCT has not changed since the issuance of Reference (b) report.

The large break LOCA PCT is 2038o.

The small break LOCA PCT has not changed since the issuance of the Reference (b) report.

The small break LOCA PCT is 1255 F.

Attachment 1 to this letter summarizes the current PCTs for Ginna.

Very truly yours, Robert C. Mecredy RWE~t,403 ttt5i2010074 tt5ii27 PDR 4DOCK 05000244 PDR Ib M4 8

C r

xc:

Mr. Allen R. Johnson (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

ATTACHMENT 1 LOCA PCT SUMMARIES

Large Break LOCA R.E.

Ginna Eval. Model:

1981EM Fuel:

OFA FQ 2'2 FhH 1'6 SGTP =

15'.

B.

C.

D.

E.

F.

G.

H.

Analysis of record 1.

UPI penalty 2.

RIP penalty Prior LOCA Model Assignments 1989 Prior LOCA Model Assignments 1990 Prior LOCA Model Assignments 1991 Prior LOCA Model Assignments 1992 Prior LOCA Model Assignments 1993 Prior LOCA Model Assignments 1994 LOCA Model Assessments 1995 10CFR50.59 Safety Evaluations 1.

Fuel reconstitution (1990 evaluation) 2.

Thimble plug deletion (1992 evaluation) 3.

Containment Fan Cooler Replacement (1993 evaluation)

PCT = 1871~F dPCT = +6~F dPCT = +3~F dPCT = +2~F 4PCT = O' dPCT = +76~F aPCT = +27~F dPCT = O~F dPCT = -6~F wPCT = O' dPCT = +1~F (Fuel not used) dPCT = O' aPCT = +59 F

Licensing Basis PCT = 2038'F Potential Issues Temporary Allocation of Margin ~PCT = +140~F Licensing Basis

+ Temporary Allocation PCT = 2178 F

Small Break LOCA R.E.

Ginna Eval. Model:

WFLASH Fuel:

OFA FQ 2'2 FbH = 1 66 SGTP = 12'

~

5.

Thimble Plug Deletion (1991 evaluation)

Increase SGTP to 154 Licensing Basis 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 F.

Prior LOCA Model Assignment 1993 G.

Prior LOCA Model Assignments 1994 H.

LOCA Model Assignments 1995 10CFR50.59 Safety Evaluations 1.

AFW enthalpy delay (1989 evaluation) 2.

MFIV closure delay (1990 evaluation) 3.

Fuel reconstitution (1990 evaluation)

PCT = 1092~F hpCT = O~F

~PCT = OoF dPCT = +77~F hpCT = O~F zPCT = OoF dPCT = 22~F dPCT = O~F hPCT = +11~F hPCT = +43~F zPCT = +1~F (Fuel not used) dPCT = +10~F hPCT = O' PCT = 1255~F Potential Issues Temporary Allocation of Margin ~PCT = O' Licensing Basis

+ Temporary Allocation PCT = 1255'F