AECM-83-0633, RO 83-088/0:on 830904,control Room Temp Exceeded 77 F Limit.Upper Cabinet Area on Elevation 189 Ft of Control Room Bldg Also Exceeded Limit.Excessive Temps Sporadic from 830904-10.Cause Under Investigation

RO 83-088/0:on 830904,control Room Temp Exceeded 77 F Limit.Upper Cabinet Area on Elevation 189 Ft of Control Room Bldg Also Exceeded Limit.Excessive Temps Sporadic from 830904-10.Cause Under Investigation

ML20078J291
Person / Time
Site:	Grand Gulf
Issue date:	10/04/1983
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AECM-83-0633, AECM-83-633, RO-83-088-0, RO-83-88, NUDOCS 8310170408
Download: ML20078J291 (2)

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MISSISSIPPI POWER & LIGfiT; COMPANY -

l Helping Build Mississippi W EmiMdWdidd5 P. O. B O X 16 4 0. J A C K S O N , M I S S I S S I P Fri fB S 2 0 5 October 4, 1983

• fy NUCLEAR PRODUCTION DEPARTMENT U. S. Nuclear itegulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Attention: Mr. J. F. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File 0260/L-835.0 Special Report 83-088/0 -

Control Room Temperature Exceeded Technical Specification Limitation AECM-83/0633 On September 4, 1983, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> the Control Room temperature exceeded the 77*F limit of Technical Specification 3.7.8. The temperature reached 80*F but was brought within limits by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on September 5, 1983. The equipment in the area is qualified to a minimum of 90*F. No further evaluation is considered necessary.

The upper cabinet area on elevation 189 feet of the Control Building also exceeded 77*F. The excessive temperature readings were somewhat sporadic from September 4 to September 10 and are suspect. The maximum recorded temperature was 97*F, the lowest was 73*F. An investigation is in progress to determine the validity of the temperature readings. An analysis of the effects of this excessive temperature on plant equipment is still in progress. This is an interim report submitted pursuant to Technical Specification 6.9.2. An update report is expected to be submitted by November 15, 1983.

Yours truly,

)N g L. F. Dale Manager of Nuclear Services EBS/SHH: sap cc: (See Next Page) 8310170408 6 ,,;yic MN PDR ADOCK 0 PDR S

Member Middle South Utilities System

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• AECM-83/0633

1. E MICCIS2iPPl POWER O LIGHT COMPANY cc: Mr. J. B. Richard Mr. R. B. McGehee Mr. T. B. Corner Mr. G. B. Taylor Mr. Richard C. DeYoung, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555