View source for AECM-83-0673, RO 83-093/0:on 830914 & 15,control Room Upper Cable Spreading Room Ambient Air Temp Exceeded Area Temp Limit of 77 F in Tech Spec 3.7.8-1.c During 36 H Period.Max Qualification Temp Not Exceeded

{{Adams
| number = ML20081A895
| issue date = 10/14/1983
| title = RO 83-093/0:on 830914 & 15,control Room Upper Cable Spreading Room Ambient Air Temp Exceeded Area Temp Limit of 77 F in Tech Spec 3.7.8-1.c During 36 H Period.Max Qualification Temp Not Exceeded
| author name = Dale L
| author affiliation = MISSISSIPPI POWER &amp; LIGHT CO.
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000416
| license number = 
| contact person = 
| document report number = AECM-83-0673, AECM-83-673, RO-83-093-0, RO-83-93, NUDOCS 8310270167
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 2
}}

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P. O. B O X 16 4 0, J A,C K S O N. MI S SIS SIPP1 3 3 2 0 5 October 14, 1983 03 'ci2I nlc : 7 g NUCLEAlt 4>RODUCTION DE P ARTMENT U. S. Nuclear Regulatory Commissien Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Attention:       Mr. J. P. O'Reilly, Regional Administrr. tor

==Dear Mr. O'Reilly:==

==SUBJECT:==
Crand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. UPF-13 File 0260/L-833.0 Special Report 83-093/0 -
Control Room Upper Cable Spreading Room Exceeds Technical Epecif2 cation Area Tempersture Limit AE0b83/C673 On September 14 and 15, 1983, the Control Room Upper Cable Spreading Room ambient air temperature periodically exceeded the area tonperature limit (77'F) of Technical Specification 3.7.8-1.c.            The peak recorded temperature was 79.65*F.       The temperatura was higher than the limit fot a total of 36 hours.
The maxicun qualification temperatures vary for different types of equipment in the Centrol Room Upper Cable Spreading Room. All equipment in the Control Room is qualified to at least a maximum temperature of 90'F, therefore Lu analysis to demonstrate operability of this equipment is not required. There was no effect on the health and safety of the public nor was there a threat to plant safety. This is reported pursuant to Technical Specification 3.7.8. This is a final report.
Yours truly,
                                                               />M pg     L. F. Dale 7     Manager of Nuclear Services EBS/bHH: sap cc:    (See Next Page) 8310270167 831014 PDC A00CK 05000416 S                          PDR                                                        /p' N, Member Middle South Utilities System hD

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        .o d~'                                                          AECM-83/0673 MISSISSIPPI POWER O LISHT COMPANY  #E' cc: Mr. J. B. Richard Mr. R. B. McGehee Mr. T. B. Conner 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
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