ML19329B336
| ML19329B336 | |
| Person / Time | |
|---|---|
| Site: | North Anna, Davis Besse  |
| Issue date: | 08/08/1975 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19329B337 | List: |
| References | |
| NUDOCS 8002040765 | |
| Download: ML19329B336 (2) | |
Text
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t AUG B G75 DOCIET NO.: 50-346
."S : 24-11 0
V V. A.sAoore, Assistant Director O'
for Light %'ater Reactors, Group 2 D
Division of Reactor Licensing
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DAVIS BESSE tiUCLEAR POWER STATION UNIT 1 Plant ;iame: Davis 3 esse Nuclear Power Station Licensing Stage: OL Docket No. : 50-346 Respo:nsible RL 3 ranch i Project Manager: Lb2 2-3, L. Engle Description of Response: Safety Evaluation Report Review Status: Complete, as noted The FSAR submitted by tha applicant, includin:; Amendment 30 (Revision 14) has been reviewed by the Mcchanical Engineering 3 ranch, Division of Technical Review. Tha appropriate sections of the Safety Evaluation are enclosed and are identified by section nu=hers which refer to the Standard Format and Content of Safety Analysis Reports for iuclear Power Plants, Revision 1 dated October 1972.
It should be noted that the information in section 3.6 is based on verbal a;;reement reached during discussions with the a;iplicant's A/E on August 4, 1975. If the applicant does notaadequately document these cor:mitments in a future amendnent, this Safety 2 valuation may have to be revised.
On :tay 7,1975 the Nuclear Regulatory Cen:::ission staff was informed by the Virginia Elactric and Pouer Co,:pany that one type of load that would occur in the unli'4aly event of a cold leg loss-of-coolant accident (LOCA) has been underestimated in the original design of the reactor vessel rapport systen for North Anna Units 1 5 2.
To decarmine if the same
>otential problen exists in the case of Davis Besse Unit 1 and to assess c.ts effects on the reactor vessel support system, a request for additional
.nformation is also forwardad. The applicant's response will be evaluated and treated in a supplement to the 522.
rR:.O;hcD7 g n.._; - r" R. R. Maccary, Assistant Director for Engineering Division of Technical Review
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Enclosure:
- 1. Safety Evaluation Report
- 2. Requen for Add (tional Inf on
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