ML19220C419
| ML19220C419 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1978 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905010244 | |
| Download: ML19220C419 (5) | |
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p 1. i S3 Occket No. 50-320 MEMORMDmi FOR:
D. Vassallo, Assistant Director for Light Water Reactors, Om FROM:
R. Tedesco, Assistant Director for Plant Syste:ss,- OSS SUSJECT:
DRAFT SAFETY EVALUATION REPORT SUPPLEiENT TOR TiiREE MILE ISLMD, L' NIT 2 Plant Name: inree Mile Island Nuclear Station, Unit 2 Docket Nunber: S0-320 Licensing Stage: OL MSSS Sup? lier: Babcock & Wilcox Architect Engineer: B m s a Roe Containment Type: Dry Responzible Branch & Project Manager: LWR-2; H. Silver Requested Completion Date: N/A Review Statas:
Incaz:plete The Containment Systems Branch and the Power Systems Branch have reviewed the infor: nation provided in Section S3-42 of the FSAR with regard to environraental qualificatica of safety related equipment needed for a main steam line break (MSLS) inside contain:r.cnt. This has included the identification of equipcent needed for an MSLB accident and the actual environmental qualification testing perfomed for this equipc:ent. The applicant has relied on component themal analyses to justify the environmental qualification of equipment to temperatures less than those calculated during a postulated MSLB accident. Although this is an acceptable approach, sane additional infomation is required and certain assumptions require additional justification. However, on an overall basis, considering results of the analysis and the relatively hign temperatures to which the equipment has been qualified, we conclude that the Three Mile Island Unit 2 power plant can begin operation.
In our evaluation which is enclosed we have cited the results of the appifcant's analysis and our best estimate analysis as the basis for plant licensing. We will require that the applicant provide the additional
Contact:
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I'MA i ij;,d D. Vassallo infomation and justification needed to bring the applicant's documented analysis in confomance with the Interim Evaluation Model wnich we nave developed from our 'cest estimate analysis.
We will be discussing with you the *1 ming of the submittal of the additional informtion by the applicant and a.G plant operating limitations tnat ray be required.
Robert L. Tedesco, Assistant Director for Plant Systems Division of Systems Safety
Enclosure:
As Stated cc:
S. Hanauer R. Mattson R. Boyd R. Hartfield K. Knfel G. Lainas H. Silver J. Kudrick J. Shapaker J. Glynn P. Baranowsky F. Ashe F. Rosa
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