L-83-353, Forwards BAW-1976, Small Break LOCA Analysis for B&W 177FA Lowered Loop Plants in Response to NUREG-0737,Item II.K.3.31, & Generic Ltr 83-35
| ML20215H710 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/16/1986 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215H713 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM GL-83-35, GL-83-3531, JEW-86-631, NUDOCS 8610240100 | |
| Download: ML20215H710 (1) | |
Text
esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852 1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-631 October 16, 1986 So-Sl%
Director of Nuclear Reactor Regulation Attn: Frank J. Miraglia, Jr., Director Division of PWR Licensing-B U. S. Nuclear Regulatory Commission Washington DC 20555
SUBJECT:
NUREG 0737 II.k.3.31 - SMALL BREAK LOCA METHODS
Dear Mr. Miraglia:
Enclosed is the Babcock & Wilcox (B&W) Owners Group report BAW-1976, Small Break Loss of Coolant Accident Analysis for B&W 177FA Lowered Loop Plants in Response to NUREG-0737, Item II.k.3.31.
This report presents the B&W Owners Group analysis to satisfy the NUREG 0737, Item II.k.3.31 requirements.
The results of the analysis confirm the results of previous studies: The B&W-designed, lowered loop, 177 fuel assembly plants can be maintained within the limits of 10 CFR 50.46, should a small break LOCA occur.
The subject report is applicable to Rancho Seco and satisfies the requirements of NUREG 0737, Item II.k.3.31, as clarified by Generic Letter 83-35.
If you have any questions, please contact Robert Little at (916) 732-6021.
Sincerely, P
Joh
. Ward Deputy General Manager, Nuclear Attachment l
cc:
Glen Perez, NRC-Rancho Seco Syd Miner, NRC-Bethesda l
M. A. Rowden (FFIIS&J) l 8610240100 h h i2 DR ADOCK PDR
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DISTRICT HEADQUARTERS O 6201 S Street, Sacramento CA 95817-1899 J