ML19256F422
| ML19256F422 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/15/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912190123 | |
| Download: ML19256F422 (2) | |
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NOV 151979 MEMORANDUM FOR:
T. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
SAFETY EVALUATION REPORT - VERMONT YANKEE NUCLEAR POWER STATION, UNIT 1 - EMERGENCY c'DE COOLING SYSTEM LOGIC TECHNICAL SPECIFICATI01 CH3NGE REQUEST (TAC 11758)
The Plant Systems Branch has reviewed the Vennont Yankee Nuclear Power Corporation's submittal of May 18, 1979, in which the licensee requested amendments to Facility Operating License No. DPR-28 to incorporate changes to the Technical Specifications for the Vermont Yankee Nuclear Power Station, Unit 1.
The proposed changes are the result of a procedural change proposed in response to the directions of IE Bulletin No. 79-08 dated April 14, 1979 and the " Standard Technical Specifications for General Electric Boiling Water Reactors."
The licensee's amendments proposed changes to the Technical Specifi-cations which relate to modifications to the testing of the Emergency Core Cooling actuation logic. The change requested is that the logic test interval times for the LPCI, HPCI, SJAE, and A0G trip logics be doubled. We requested additional information from the licensee. The licensee has not responded. Therefore, we find that insufficient data and bases have been submitted to enable an independent safety review. We recommend that the proposed Technical Specifications be rejected and this TAC be closed out.
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/. Lainas, Chief G
Plant Systems Branch
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Division of Operating Reactors Enclosure :
Safety Evaluation Report
Contact:
R. Scholl, X27162 go 001 cc w/ enclosure:
D. Eisenhut V. Rooney G. Lainas
.a M8 cho 1 7912190
Enclosure u,-
- SAFETY EVALUATION REPORT VERMONT YANKEE NUCLEAR POWER STATION, UNIT 1 EMERGENCY CORE COOLING SYSTEM LOGIC TECHNICAL SPECIFICATION CHANGE I.
INTRODUCTION The licensee, Vermont Ya'1kee Nuclear Power Corporation, in its submittal of May 18, 1979, proposed certain modifications to the Technical Specifications for the Vermont Yankee Nuclear Power Station, Unit 1, Facility Operating Licensing No. DPR-28. The status of the staff's evaluation is presented below.
II. EVALUATION The amendments proposed changes to the Technical Specifications which relate to modifications to the testing of the Emergency Core Cooling actuation logic. The change requested is that tha logic test interval times for the LPCI, HPCI, RCIC, SJAE, and A0G trip logics be doubled. Our review indicated that the FSAR did not provide the supporting information that is required to evaluate and justify the change.
In order to gain further in sight to the requested changes, the staff requestad additional information from the licensee. The licensee has not been responsive.
III. CONCLUSION Based on our review, we find that insufficient data and bases have been submitted to enable an independent safety review.
Therefore, we conclude that the proposed Technical Specifications is not acceptable and recommend that the licensee's request be denied.
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