ML19329C792
| ML19329C792 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Davis Besse  |
| Issue date: | 06/23/1975 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002190903 | |
| Download: ML19329C792 (2) | |
Text
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'{ p M 0 ; ;;-75 Cocket No. 50-346
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V. A. V.onre, Assistant Director for LWRs. Group 2. RL SAFETY EVALUATION REPORT - TOLEDO EDISON COMPANY, DAVIS BESSE NUCLEAR POWER STATION - UNIT 1 Plant Name:
Davis Besse 1 Licensing Stage: OL Docket Number: 50-346 Hilestone Number: 24-22 Responsible Branch and Project Leader:
LUR 2-3 L. Engle Technical Review Branch Involved:
EISCS Branch Description of Review: Safety Evaluation Report Requested Completion Date: June 6, 1975 Review Status: Complete with the exception of items stated below, and the supplemental safety evaluation report The enclosed safety evaluation report was prepared by the TR:RS, Electrical. Instrumentation and Control Systems Branch. Thi s evaluation reflects the results of our review of the application through kendment 28.
The report is submitted prior to making a site visit and completion of the drawing review. In addition, the following areas have not been satisfactorily resolved with the applicant and rernain as outstanding items.
1.
Final approval of BAW-10003 Topical Report for RPS equipment Qualification Testing (SER Section 7.2).
2.
Documentation comparing Davis Besse Unit 1 ESF actustion system with Millstone Unit 2 (SER Section 7.3.1).
3.
Documentation confirrhing the applicant's enemitment cou:plydng with the staff requirements regarding diversity for DHR valve interlocks (SERSection7.3.3).
4.
Documentation confiming the applicant's commitments complying with the staff's requirements regarding Core Flooding Tank Isolation Valve System (SER Section 7.3.4).
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Modification of the Auxiliary Feedwater System, liain Steam Line Rupture System and Main Feedwater Line Rupture System, demonstrating confomance with IEEE Std 279-1971 (SER Sections 7.4.1, 7.4.2 and 7.5.3).
6.
Documentation verifying conformance to the staff's requirements on Post-Accident !!onitoring (SER Section 7.5.1).
7.
Documentation fully describing the applicant's Cable Separation and Identification Criteria (SER Section 7.9).
8.
Documentation describing the degree of protection used for maintaining electrical penetration integrity (SER Section 7.10).
Any problems likely to arise as a result
+vSletion of these review activities and their resolution will be re, ud in the supplemental safety evaluation report.
0-im! s:=vi by Victor Ste"o Victor Stello, Jr., Assistant Director for Reactor Safety Division of Technical Review Office of' Nuclear Reactor Regulation
Enclosure:
Safety Evaluation Report cc:
S. Hanauer F. Schroeder A. Giambusso D
D A. Scnwencer L. Engle L)L Ll[
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