ML17263A473
| ML17263A473 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/18/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9311300174 | |
| Download: ML17263A473 (9) | |
Text
FORD 1 4
- REGULA, INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR: 9311300174 DOC. DATE: 93/11/18 NOTARIZED:
NO DOCKET 0 FACEL: 50-244 Robert Emmet Ginna NucleaT Planti Unit li Rochester G
05000244 AUTH. NAME AUTHOR AFFILIATION MECREDYi R. C.
Rochester Gas Sc Electric Corp.
RECIP. NAME RECIPEENT AFFILIATION JOHNSON> A. R.
PT object Directorate I-3 R
SUBJECT:
Submits annual ECCB rept in accordance Uj/10CFR50. 46. Summary of current PCTs for plant encl.
DISTRIBUTION CODE:
A001D COPlES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
General Distribution NOTES: License Exp date in accordance with 10CFR2i 2. 109(9/19/72).
05000244 F
REC IP IENT ID CODE/NAME PD1-3 LA JOHNSON'
'INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SRXB DCB RE F
01 COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
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1 REC IP IENT ID CODE/NAME PD1-3 PD NRR/DORS/OTSB NRR/DSSA/SPLB NUDOCB-ABSTRACT OGC/HDS1 CQPIEB LTTR ENCL 1
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EXTERNAL:
NRC PDR 1
1 NSIC C,e~~+ f 571 5(g 357 NOTE TO ALL RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM P 1-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COP IEB REQUIRED:
LTTR 15 ENCL 13
0 ll P
i PJ48'
//rI///
i,"/I';l'OCHESTER GAS AND ELECTRIC CORPORATION o
ROBERT G MECREDY Vice President Clnna Nuetear Production rr reae srAre 89 EAST AVENUE, ROCHESTER N.K 14649-0001 TELEPHONE AREACODE7t6 546 2700 November 18, 1993 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):
RG&E letter from R.
C. Mecredy to A. R. Johnson,
- NRC,
Subject:
10CFR50.46 30 Day Report ECCS Evaluation Model. Changes dated November 17, 1992 (b):
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 following annual report is hereby submitted.
Westinghouse, the provider of LOCA analyses for the Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna.
The large break LOCA PCT has not changed since the issuance of Reference (a) report.
The large break LOCA PCT is 1986'F.
The small break LOCA PCT has not changed since the issuance of the Reference (a) report.
The small break LOCA PCT is 1234'F.
Attachment 1 to this letter summarizes the current PCTs for Ginna.
p 9311l
- PDR, ADOCK 0 R.
,'I J il ",~
t
This is based on the currently approved model and will be replaced by the new Upper Plenum Injection model, submitted by reference (b),
upon NRC approval.
Very truly yours, Robert C. Mecr dy RWE4313 xc:
Mr. Allen R. Johnson (Mail Stop 14Dl)
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 SUMMARXES
Large Break LOCA R.E.
Ginna Eval. Model:
81EM Fuel:
OFA FQ =
2'2 FhH = 1 66 SGTP =
15'.
B.
C.
D.
E.
F.
G.
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 LOCA Model Assignments 1993 1.
(as of 8/93) none 10CFR50.59 Safety Evaluations 1.
Fuel reconstitution (1990 evaluation)
Licensing Basis PCT = 1871~F hPCT = +6+F dPCT = +3~F a.PCT = +2~F
~PCT = O.F hPCT = +76~F aPCT
= +27~F aPCT
=
0 F
aPCT
= O' PCT = 1986'F Potential Issues Temporary Allocation of Margin ~PCT = +140'F Licensing Basis
+ Temporary Allocation PCT = 2126'F
T
)
I,
Small Break LOCA R.E.
Ginna Eval. Model:
WFLASH Fuel:
OFA FQ = 2'2 FhH =
1'6 SGTP =
12'.
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 LOCA Model Assignment 1993 1.
(as of 8/93) none PCT = 1092~F
~PCT = OoF
~PCT = OoF dPCT = +77~F
~PCT = OoF
~PCT = OoF G.
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 hPCT = +11~F dPCT = +43~F dPCT = +1~F dPCT = +10~F dPCT = 04F PCT = 1234~F Potential Issues Temporary Allocation of Margin ~PCT = O' Licensing Basis
+ Temporary Allocation PCT = 1234'F