ML19259D458
| ML19259D458 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/19/1978 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910240665 | |
| Download: ML19259D458 (2) | |
Text
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Sf,P 191978
' T MEMORANDUM FOR:
R. Reid, Chief, Operating Reactors, Branch #4 Division of Operating Reactors i
i FROM:
G. Lainas, Chief, Plant Systems Branch Division of Operating Reactors i
I
SUBJECT:
FIRE PROTECTION TECHNICAL SPECIFICATIONS i
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Facility: Three Mile Island Power Station, Unit I Licensee: Metropolitan Edison Company i
Docket Mumber: 50-289 l
Responsible Branch: ORB f4 j
Pmject Manager:
G. B. Zwetzig Reviewing Branch: Plant Systems Branch l
Status: Draft Safety Evaluation Report Issued:
l The Technical Specifications for fim protection for the Three Mile Island Power Station, Unit I were issued as Amendnent No. 32 i
. of Facility Operating Licensee No. DPR-50 on November 30,197ES -
We have reviewed the Limiting Condition For Operation and Surveillance l
Requirements as stated in Andndment No. 32. We find that the i
present Technical Specifications do not adequately address all of l
the existing fire pmtection systems that were relied upon in the fire protection program evaluation.
l The changes to the Technical Specifications, which werreconmend to adequatelw cover the existing fire protection systems are enclosed.
Items 1.arough 6 are revisions required to make the Technical Specifications consistent with the NRC's model Technical Specifications for fire protection in areas where the licensee has not justified his departure from the model Technical Specifications.
Item 7 is a new Technical Specification for a plant specific feature not covered in the Model Technical Specifications.
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, We request that the enclosed changes be discussed with the licensee and incorporated into the Three Mile Island, Unit I Technical Specifications in the near future.
l I
i G. Lainas, Chief i
Plant Systems Branch i
Division of Operating Reactors l
Enclosure:
As stated j
Contact:
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-B. Grimes i
G.-Lainas J. McGough l
R. Ferguson
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