ML20041D565
| ML20041D565 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/02/1982 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203050416 | |
| Download: ML20041D565 (1) | |
Text
Sp&L i
Carolina Power & Light Company RacsNED MAR 021982 5
MAR 05582> $
ammur.
Mr. Darrell G. Eisenhut, Director
\\
M Division of Licensing
/
Office of Nuclear Reactor Regulation
/, G United States Nuclear Regulatory Commission Washington, D.C.
20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 l
LICENSE NOS. DPR-71 AND DPR-62 l
IMPLEMENTATION OF GENERAL ELECTRIC SERVICE I
INFORMATION LETTER 299 - HIGH DRYWELL TEMPERATURE EFFECT ON REACTOR VESSEL WATER LEVEL INSTRUMENTATION l
Dear Mr. Eisenhut:
At a meeting between the BWR Owners' Group and the NRC Staff on i
January 27, 1982, regarding inadequate core cooling detection, the NRC expressed a concern regarding the BWR owners' implementation of General Electric Company (GE) Service Information Letter (SIL) 299. General l
Electric SIL 299 and SIL 299, Supplement 1, concern a high drywell l
temperature effect on reactor vessel water level instrumentation. The l
Brunswick Plant has implemented the recommendations of GE SIL 299 and l
SIL 299, Supplement 1.
If you need any additional information regarding this matter, please contact us.
Yours very truly, Z
9
/
~'
L. W. Eu l
Senior Vice President Power Supply DCS/lr (1288)
I cc:
Mr. J. P. O'Reilly (NRC-RII)
Mr. J. Van Vliet (NRC)
O I
e, o I
411 Fayetteville Street
- P. O. Box ;551 + Raleigh, N. C. 27602 r203050416 820302
- s erm.,# n m o ou e; PDR ADOCK 05000324 p
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