ML19274F965
| ML19274F965 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/02/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908270228 | |
| Download: ML19274F965 (3) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION y',. g( [, ;
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MEMORANDUM FOR:
T. Ippolito, Chief, Operating Reactors Branch #3, D0R FROM:
G. Lainas, Chief, Plant Systems Branch, 00R
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - VERMONT YANKEE NUCLEAR POWER STATION - UNIT 1 - EMERGENCY CORE COOLING SYSTEM LOGIC TECHNICAL SPECIFICATION CHANGE REQUEST (TAC 11758)
The Plant Systems Branch has reviewed the Vermont Yankee Nuclear Power
. Corporation's submittal of May 18, 1979, in which the licensee requested amendments to Facility Operating License 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 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 the logic test interval times for the LPCI, HPCI, RCIC, SJAE and A0G trip logics be doubled.
Based on our review, we find that insufficient data and bases have beer submitted to enable an independent safety review. Therefore, we find that the proposed Technical Specifications may not be correct and, therefore, require additional information as outlined in Enclosure 1.
6 G. Lainas, Chief Plant Systems Branch Division of Gparating Reactors
Contact:
R. Scholl X-28077 7 908 2 70Pvf
Enclosure:
As stated cc w/ enclosure:
D. Eisenhut B. Grimes V. Rooney G. Lainas D. Tondi R. Scholl I
4
ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION, UNIT 1 EMERGENCY CORE COOLING SYSTEM LOGIC TECHNICAL SPECIFICATION CHANGE Your request of May 18, 1979 did not contain sufficient design infor-mation to enable the staff to conduct an adequate safety review.
Therefore, the staff requires the following additional information:
a.
Updated. ASBUILT copies of the system schematics, functional logic diagrams, and piping and instrumentation diagrams for each affected system; and b.
A reliability analysis similar to that provided in GESSAR or Appendix 6A to the Zimmer application.
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