ML19329C506
| ML19329C506 | |
| 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 8002140880 | |
| Download: ML19329C506 (1) | |
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'375 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 I Licensing Stage: OL Docket Number: 50-346 liilestone Number:
24-22 Responsible Branch and Project Leader; L'4R 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 1tems stated helow, and the Supplemental Safety Evaluation Report In the continuing effort to review the Davis Besse Unit I 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. '4e 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 163 heurs prior to testing the cable under LOCl condition. Since the LCCA conditions inside and outside the prinary containment are different (as shcwn in Table 7-4), we will require that the design conditions for the cable tests be a
identified, and tne test criteria (i.e., basis for passing or failing) be provided.
In addition, the applicant is requested to provide a surnary of results of the cable qualification tests.
These concerns have been discsssed with you, our cognizant engineer, and tne applicant on June 25, 1975. This memorandum sum.arizes our concerns and requests that they be transmitted to the applicant.
0%hM s' peg g, T.A. by,.y Thomas A. Ippolito, Chief Electrical, Instrumentation & Control Sy:.cems Branch Division of Technical Review Office of Nuclear Reactor Regulation or rie s >
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