ML19329B574
| ML19329B574 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 07/01/1975 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002050710 | |
| Download: ML19329B574 (1) | |
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0:CI Gh JUL 1 55 Docket No. 50-346 A. Schwencer, Chief Light Water Reactors Branch 2-3, RL DAVIS BESSE UNIT 1 - SAFETY EVALUATION REPORT UPDATE Plant Name: Davis Besse Unit 1 Licensing Stage: CL Docket Number: 50-346 Milestone Number: 24-22 Responsible Branch and Project Leader; LWR 2-3, L. Engle Technical Review Branch Involved: EI&CS Branch Description of Review: Safety Evaluation Report Update Requested Completion Date: N/A Review Status: Complete with the exception of items stated below, and the Supplemental Safety Evaluation Report In the continuing effort to review the Davis Besse Unit 1 application for the Operating License permit, it has come to my attention that the applicant's information regarding cable qualification presented in the FSAR is too general to complete our evaluation. We will require that the applicant supplement the FSAR to clarify the following:
Sections 3.11.2.1.5 and 3.11.2.2.1 states that cable samples were air-oven aged at 121*C for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> prior to testing the cable under LOCA condition. Since the LOCA conditions inside and outside the primary containment are different (as shown in laole 7-4), we will require that the design conditions for the cable tests be identified, and tne test criteria (i.e., basis for passing or failing) be provided.
In addition, the applicant is requested to provide a summary of results of the cable qualification tests.
These concerns have been discassed with you, our cognizant engineer, and the applicant on June 25, 1975. This memorandum summarizes our concerns and requests that they be transmitted to the applicant.
Origins S.g I A. ID%i*O Thomas A. Ippolito, Chief Electrical, Instrumentation & Control Systems Branch Division of Technical Review Hice f Nuclear Reactor Regulation 8 0 0 2 0 5(T'l to l
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