ML20093D569
| ML20093D569 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/03/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM NLS-84-345, NUDOCS 8410110288 | |
| Download: ML20093D569 (1) | |
Text
Cp&L Carolina Power & Light Company SERIAL: NLS-84-345 M 03 M 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 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 NUREG-073 7 ITEM III.D.3.4 CONTROL ROOM HABITABILITY Dear Mr. Vassallo Carolina Power & Light Company (CP&L), by letter dated March 2, 1983 involving NUREG-0737, Item III.D.3.4, Control Room Habitability, committed to revise the existing periodic test acceptance criteria to quantify the positive pressure in the control room during operation of the control room emergency ventilation
- system. This procedure was revised as required. However, during performance of the periodic test on June 15, 1984, the acceptance criteria of 1/8-inch water gauge positive pressure could not be achieved. This is the first such
. periodic test to be performed since the test acceptance criteria was revised to address the control room positive pressure.
Although unable to achieve the 1/8-inch water gauge positive pressure, the system did demonstrate a positive pressure as required by the Brunswick Technical Specifications. Additionally, a review of the Brunswick Control Room Habitability Evaluation indicates that no credit was taken for the 1/8-inch pressure (i.e., the habitability evaluation and its conclusions are still valid), thus the control room ventilation system is considered operable pursuant to Technical. Specification requirements.
The inability to achieve 1/d-inch water gauge positive pressure has been evaluated and apparently is the result of excessive outleakage from the control room area. Carolina Power & Light Company has initiated a program to identify the sources of the outleakage and to perform appropriate repairs. We presently anticipate that this program will be completed by January 15, 1985.
If you have any questions regarding this issue, please contact Mr. S. R.
Zimmerman at (919) 836-6242.
Yours very truly,
(
A. B. Cuttur - Vi President Nuclear Engineering & Licensing WRP/ccc (411WRM) ces Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC) 09 h
8 411 Fayettevme Street e P. O. Don 1551 e naleign. 4 C 27602 1
8410110208 041003 PDR ADOCK 05000324
--.F P DR
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