ML20005C109
| ML20005C109 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/12/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.44, TASK-TM JPN-81-90, NUDOCS 8111180401 | |
| Download: ML20005C109 (2) | |
Text
-
POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUM aus CIRCLE NEW YORK. N. Y.10o19 42121 397 6200 G EG",G,E,7,gst,nRycu ar TRusicas
- """,*ic*ur va v cs JOHN s. orsoN emainua=
ensaio nocuounts JOS EP,H,,R. S,,C,H, M I E,D E R vics Cnasamam gy y,g RICHARD M. FLYNN Ng age Mc8ERT I MILLO N Z4 November 12, 1981 LEROY W. $1NCLAIRimos=1
.< ica viu e JPN-81-90
$ r'r%'l."''
r R c o r RiC =
R. C"*
THOM AS R FREY I'."i%la 'c o",' '.'a t m
Director of Nuclear Reactor Regulation
.J4 U.S. Nuclear Regulatory Commission
/Y c
Washington, DC 20555 E'
Attention:
Mr. Thomas A.
Ippolito, Chief i
fl0V181981 TB Operating Reactors Branch No. 2 4
7 Division of Licensing c: w m c=4 N !
-QS
\\
Subject:
James A.
FitzPatrick Nuclear Power Plant
//-
. M Docket No. 50-333 yT NUREG-0737, Item II.K.3.44 -- Assumption Verification for Evaluation of Anticipated Transients Combined with Single Failure
References:
- 1. Letter from Darrel G. Eisenhut (NRC) to all applicants / licensees referencing BWR Owners' Group Response to NUREG-0737 Item II.K.3.44, dated August 7, 1981.
- 2. General Electric BWR Owners' Group Report, Adequate Core Cooling for Transients with a Single Failure, dated December 29, 1980.
Dear Sir:
This letter responds to an NRC letter from D.G. Eisenhut to all applicants dated August 7, 1981 concerning a request for addi-tional information on NUREG-0737, Item II.K.3.44 for the James A.
FitzPatrick Nuclear Power Plant.
The letter requests a verifica-tion that the assumptions and initial conditions used in the general analyses for Item II.K.3.44 are representative for the J.A. FitzPatrick Plant.
We have reviewed the analyses assumptions and initial conditions used for the generic analyses and determined that they are applicable i
to the J.A. FitzPatrick Plant.
i Oh 8111180401 811112 hsD DR ADOCK 05000333 f
)
. Should you or your staff have any questions, please contact us.
Very truly yours, D
i ).P.ddyn~ ~
Senior Vice President Nuclear Generation cc:
Mr. J. Lir.ville Resident Inspector U.S.
Nuclear Reactor Regulation P.O. Box 136 Lycomi ng, NY 13093
/