ML19322E728
| ML19322E728 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 02/11/1980 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020178 | |
| Download: ML19322E728 (3) | |
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UNITED STATES 8
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r; 'y FEB 111980 MEMORANDUM FOR: Thomas A. Ippolito. Chief. Operating Reactars Branch #3, Division of Operating Reactors FROM:
G. Lainas, Chief. Plant Systems Branch, Division of Operating Reacters
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS FOR BROWNS FERRY UNITS 1,
- 2. AND 3 (TACS 12611/12612/12613)
Insufficient information was provided with the three NRC Forms 197A that were issued by your office. Therefore, in order to conduct an independent safety review, we request that the enclosed questions be forwarded to the licensee for their response.
G. Lainas, Chief
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Plant Systems Branch Division of Operating Reactors
Contact:
R. Scholl, X27162 Enclosure
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ENCLOSURE REQUESTFORADDITIONALINFORMATIM ON PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS FOR BROWNS FERRY UNITS 1, 2, AND 3 1.
Provide an up-to-date (as built) set of functional control diagrams, wiring diagrams, and electrical schematics for the main steam line isolation control system (from the temperature switches to the main steam and bypass valve actuators) including all power supplies.
2.
Using the drawings requested in 1 above, as a reference, explain why fuse A opened as a result of an open cable during Licensee Event 259/7925 but fuse D did not.
(See LER Supplemental Information dated "1/10/79" (SIC)).
3.
Justify the difference between your proposed change to the definition of " Channel" and that of IEEE Std. 279-1971.
4.
The staff's understanding, from the proposed change to foot note 3 to the Table 3.2.A. is that a single channel per steam line is provided to detect leaks.
Explain how this design satisfies (a) the single failure criterion, and (b) IEEE Std. 279-1971.
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