ML19242A298
| ML19242A298 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/20/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17244A722 | List: |
| References | |
| TASK-07-02, TASK-RR NUDOCS 7908010319 | |
| Download: ML19242A298 (2) | |
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JUN 2 01979 MEMORANDUM FOR:
D. Ziemann, Chief, Operating Reactors Granch #2, Division of Operating Reactors FROM:
G. Lainas, Chief, Plant Systems Branch, Division of Operating Reactors
SUBJECT:
SAFETY EVALUATION REPORT - R.E. GINNA NUCLEAR POWER PLANT - UNIT 1 - EVALUATION OF SAFETY INJECTION SYSTEM ACTUATION TECHNICAL SPECIFICATION CHANGE REQUEST (TAC 11818)
The Plant Systems Branch has reviewed the Rochester Gas and Electric Corporation's submittal of June 7,1979, in which the licensee requested amendments to Facility Operating License DPR-18 to incorporate changes to the Technical Specifications for the R.E. Ginna Nuclear Power Plant, Uni t 1.
The proposed change is the result of a modification proposed in response to the directions of IE Bulletin No.79-06A dated April 14, 1979.
The amendments proposed changes to the Technical Specifications which relate to modifications to the Safety Injection (SI) actuation system logic.
The design change requested is that SI signal be developed by a two-out-of-three logic based en low pressurizer pressure instead of a one-of-three logic based on 1tw pressurizer pressure coincident with low pressurizer level.
Based on our review, we conclude that the modifications to the SI actuation syster logic satisfy the rcquirements of IEEE 279-1971 and that the associated Technical Specifications are correct; and therefore, are accept-able.
SW G. Lainas, Chief
/ Plant Systems Branch Division of Operating Reacto a
Contact:
R. Scholl X28077 400
)4J C
79080103/7
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Enclosure:
As stated cc w/ enclosure:
D. Eisenhut R. Vollmer J. Shea G. Lainas D. Tondi R. Scholl
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