ML19260A275
| ML19260A275 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/17/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260A270 | List: |
| References | |
| NUDOCS 7911080426 | |
| Download: ML19260A275 (1) | |
Text
ENCLOSURE SAFETY EVALUATION MODIFICATION TO TECHNICAL SPECIFICATIONS
_FOR THE BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 I.
htroduction T'.e licensee, Tennessee Valley Authority, in its submittal of March 1, 1979, proposed certain modifications to he Technical Specifications for the Browns Ferry Nuclear Plant, Units 1, 2, and 3.
II. Evaluation The licensee, has requested amendment to licenses for Browns Ferry Nuclear Plant, Units 1, 2, and 3.
This request consists of correction of typographical errors, clarification of local power range monitor calibration requiremea+s, removal of obsolete requirements related to startup testing, and N: tion of scram time surveillancc pressure requirement in the Brot. Ferry Unit's Technical Specifications.
The redaction from 950 psig to 800 psig in requir:d pressure for control rod drive scram time surveillance has been requested to allow scram time surveillance in parallel with vessel hydrostatic leak test.
(This is requested to reduce outage time.) The licensee has presented data which show that scram time surveillance at the lower pressure is conservative, i.e., the scram time measured at 800 psig is greater than that at 950 psig.
III.
Conclusion Based on our review of the '. !censee's submittal, we conclude that the modifications to the Technical Specifications are correct, consistent with the requirements of IEEE Std. 279-1971, and therefore, are acceptable.
1297 317 "gg 79110 80