ML20083E672
| ML20083E672 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/20/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| LAP-83-581, NUDOCS 8312290336 | |
| Download: ML20083E672 (2) | |
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CP&L Carolina Power & Light Company DEC 2 01983 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 BATTERY CAPACITY TEST REQUEST FOR ADDITIONAL INFORMATION
Dear Mr. Vassallo:
In a letter dated December 7,1983 (Serial:
LAP-83-564),
Carolina Power & Light Company (CP&L) requested a change to the Technical Specifications (TS) for the Brunswick Steam Electric Plant Unit No. 2.
This revision af fects the surveillance requirements for the 125-volt battery (bank 2A-2) specified in TS 4.8.2.3.2.d.2.a.
Following several telephone conversations conducted on De cemb er 16, 1983 with members of the Staf f, CP&L was requested to provide some additional information concerning the requirements of TS 4.8.2.3.2.d.1 and TS 4.8.2.3.2.d.2.
Specification 4.8.2.3.2.d requires that at least once The every 18 months, during shutdown, a battery capacity test be performed.
GE/BWR-4 Standard Techr,1 cal Specifications (and the Brunswick TS) permit the licensee the option of performing either (1) a battery service test using actual emergency loads or (2) a service test using dummy (i.e., simulated) emergency loads. The dummy load service test is need to test the Brunswick batteries. The actual loads service test specified in TS 4.8.2.3.2.d.1 is not used for the following rea%ns:
1.
Because of the technical complexity of establishing the actual loss of coolant accident loads to be tested, 2.
Because of the dif ficulty of developing a procedure to use in performing such a test, and 3.
Due to the dif ficulty of performing and monitoring an eight hour test using those actual (not simulated) loads with the unit in the cold shutdown condition.
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D. B. Vassallo In conclusion, for the above reasons a procedure for performing an actual loads service test has not been developed and is, therefore, not used at the Brunswick Plant. Should you have any questions concerning this letter, please contact our licensing staff.
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Yours very truky
[
P. W. Howe Vice President Brunswick Nuclear Project WRM/ctr (9118WRM) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O' Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC) i l
....