ML20100Q224
| ML20100Q224 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/10/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-23, NLS-84-499, NUDOCS 8412170047 | |
| Download: ML20100Q224 (1) | |
Text
lI" Carolina Power & Light Company SERIAL:
.DEC 1 0 1984 Mr. ' Darrell G. Eis' enhut, Director Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO GENERIC LETTER No. 84-23 REACTOR VESSEL WATER LEVEL INSTRUMENTATION
Dear Mr. Eisenhut:
By letter dated October 26,1984 (Generic Letter 84-23), Carolina Power &
Light Company (the Company) was requested to submit a description of its plans and schedule for implementation of the three potential improvement categories for BWR water level measurement and inctrumentation systems presented in Generic Letter 84-23.
The first improvement category suggested modifications to reduce level indication errors caused by high drywell temperature. The Company is currently pursuing engineering assistance in evaluating potential design modifications such as reference leg cooling and reduction of vertical drops in the drywell. Due to the engineering effort necessary to evaluate potential solutions to the problem of high drywell temperature, an implementation plan and schedule cannot be provided within the 30 days requested by the Generic Letter. Carolina Power & - Light Company anticipates the engineering evaluation to be completed by October 1985 with submir.tal of our planned improvements by December 31, 1985. Any modifications resutting from the engineering evaluation will be incorporated into the'five-year program beiag developed for Brunswick.
The second improvement category recommends replacement of mechanical icvel indication equipment with analog level transmitters. An analog trip system has already been installed at Brunswick. Reactor water level iv:dication is included in this system.
The final improvement category, dealing with changes to the protection system logic, is still being evaluated.by the NRC. The Company will address this category when a final recommendation is made.
Should you have any questions concerning this matter, please contact Mr. Sherwood R. Zimmerman at (919) 836-6242.
Yours very t t 8412170047 841210 PDR ADOCK 05000324 P
PDR A. B. Cutter - Vice resident Nuclear Engineering & Licensing MAT /crs (906 MAT) cet Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC) 411 Fayetteville Street
- P. O. Box 1$51
- Raleigh. N. C. 27602 b