ML19329C605
| ML19329C605 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 02/12/1975 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19329C606 | List: |
| References | |
| NUDOCS 8002180123 | |
| Download: ML19329C605 (2) | |
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Jgih.t/j %' U.k FEB 12 E Docket No. 50-346
- 7. A. Moore, Assistant Director for Light Water Reactors, Group 2, RL DRAFT SAFETY EVALUATION REPORT - DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 Plant Names Davis-Besse Nuclear Power Station, Unit 1 Docket No. :
50-346 Licensing Stage OL MSSS Suppliers Babcock and Vilcox Containment Type Dry Dual Architect Engineer:
Bechtel Responsible Branch & Project Manager: LW 2-3; L. Engle Raquested Completion Date: February 7, 1975 Review Status: Incomple te Enclosed is the draf t Safety Evaluation Report from the Contairment Systems Branch for the Davis-Besse Nuclear Power Station, Unit 1.
Based on our evaluation we conclude that additional information will be necessary on containment vessel end interior compartment design pressures. It also has not been demonstrated that potential containment vessel leak paths which bypass the volumes served by the emergency ventilation system have been property identified.
Before we can conclude on the acceptability of the contaituent vessel and interior compartment design pressures we will need the following information:
(1) revised mass and energy release data for postulated loss-of-coolant accidents which neglects the quenching action of the ECC5 water on the exiting atears following blovdown; (2) revised mass and energy reicase data for the contai:nent vessel intarior ceripartment analysis that adequately describes the blowdown profile over the time scale of interest for each postulated pipe break; and (3) results of contai= ment vessel and interior compart: neat analyses based on the revised mass and energy release data.
The applicant has cocunitted to providing this information. The applicant has also comitted to providing niore definitive information regarding potential containment vessel leak paths which bypass the volumes served by the emergency ventilation system. The Project Manager is aware of this need for additional E
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1 FER 1 2 M informa tion. We will report our findings, based ou our review of this in-femation, in a supplement to the Safety Evaluation Report.
./ Orfstnal s!.m.4 by:
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Robert L TWeem y
Robert L. Tedesco, Assistant Director for Containment safety Division of Technical Review Of fice of Nuclear Reactor Regulation Enclosure As stated ces w/o encl.
A. Ciambusso V. Mcdonald w/ encl.
P. Schroeder S. Hansuer V. Stallo J. Glynn R. Klecker D. Eisenhut J. Carter S. Varga A. Schwencer L. Engle C. Lainas T. Povak J. Shapaker L - Reading CS - Reading CSB - Reading Docket Files
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