ML20132C537
| ML20132C537 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 07/25/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM GL-83-35, GN-666, NUDOCS 8507300343 | |
| Download: ML20132C537 (2) | |
Text
p Georgi 2 Power Company y
.=
Routa 2. Box 299A Waynssboro, Georgia 30830 Telephone 404 554-9961 404 724-8114 Southem Company Services, Inc.
Post office Bcx 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Project July 25, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log:
GN-666 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 REF.: ADENSAM'IU FOSTER, DATED 5/30/85 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-1209 V0GrLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER CONFIRMNIORY ITEM 41: NUREG-0737, II.K.3.31
Dear Mr. Denton:
In the referenced letter confirmation was requested that GPC was 1) a member of the Westinghouse Owners' Group (WOG) and that NOTRUMP was to be used in the small break LOCA analysis for Vogtle Units 1 and 2, thus completing 1MI Action Item II.K.3.30, and 2) a plant-specific analysis would be provided within one year upon receipt of the referenced letter to satisfy the requirements of 'IMI Action Item II.K.3.31.
Both of the above are correct. As stated in the NRC safety evaluation of II.K.3.30 for Westinghouse plants and the Plant Vogtle SER, compliance with Action Item II.K.3.31 may be submitted on a generic basis. A status of the generic WOG efforts is discussed below.
The WOG, as part of its II.K.3.30/31 programs, has established the following schedule, based on the recently issued SER for N01 RUMP:
Receipt of NOTRUMP SER (II.K.3.30, Phase I Complete) - May 21, 1985 Commencement of Generic Studies Program (II.K.3.31) - June 3, 1985 Submittal of WOG Generic Studies WCAP Report
- May 21, 1986 Objectives of the Generic Studies portion (or phase III) of the program are to:
1 1.
Satisfy NUREG-0737 II.K 3.31 requirements by demonstrating previous evaluation model results are conservative when compared to NOTRUMP small j
break evaluation model results.
I 2.
Demonstrate conservatism on a generic basis, as allowed by NRC Generic Letter No. 83-35, l
g7gg Q7 4
g o E
1
Director of Nuclear Reactor Regulation File: X7BC35 July 25, 1985 Log:
GN-666 Page 2 3.
Benchmark NOTRUMP small break evaluation model peak clad temperatures are bounded by WFLASH peak clad temperatures.
4.
Demonstrate that NOTRUMP small break evaluation model peak clad temperatures are bounded by WFLASil peak clad temperatures.
Thti Generic Studies will include a review of 2-loop, 3-loop, and 4-loop plant characteristics and bounding plant characteristics determined. The NOTRUMP/LOCA analyses will be performed and will consist of a full break spectrts on one plant type; and reduced cold leg break spectrum for other plant types. Finally, a comparison of NOTRUMP and WFLASH results will be doctnented. The results will be submitted to the NRC in May 1986 by the WOG.
It is the intention of GPC to reference this submittal to close 'DfI Action Item II.K.3.31 and SER Confimatory Item 41 for Plant Vogtle.
If your staff requires any additional information, please do not hesitate to contset me.
Sincerely,
.h.
J. A. Bailey Project Licensing Manager JAB /caa xc:
D. O. Foster G. Bockhold, Jr R. A. Thomas T. Johnson J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire L. Fowler M. A. Miller W. C. Ramsey B. Jones, Esquire Vogtle Project File L. T. Gucwa 0053V E
J