ML20148B833
| ML20148B833 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/14/1988 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-001, 88-1, SL-4339, NUDOCS 8803220157 | |
| Download: ML20148B833 (3) | |
Text
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Georgia Power Company 333 Piedmont Annue Atlanta, Georg a 30308 Telephone 404 526 6526 Marling Address Post Offce Box 4545 Abanta, Georga 39302 Georgia Power L. T. Gucwe the southern ekttrc system Manager Nuclear Safety and Lcensing SL-4339 f
0831m X7GJ17-V540 March 14, 1988 U. S.. Nuclear Regulatory Commis!,lon ATTN: Document Control Desk Hashington, D.C.
20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SPECIAL REPORT 88-001 AREA TEMPERATURE HONITORING Gentlemen:
In accordance with the requirements of the Plant Vogtle Unit 1 Technical Specification sections 3.7.10.a and 6.8.2, Georgia Power Company is submitting the enclosed Special Report concerning the exceeding of a maximum normal temperature limit for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. A copy of this submittal is being provided to the NRC Region II office for review.
Sincerely, f4,y L. T. Gucwa PAH/im
Enclosure:
Special Report 50-424/1988-001 c: Georaia Power Comoany Mr. P. D. Rice Hr. G. Bockhold, Jr.
GO-NORMS U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle 8803220157 880314 PDR ADOCK 05000424 i
S PDR Ii l
GeorgiaPower A u
ENCLOSURE PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SPECIAL REPORT 50-424/1988-001 A.
Reauirement for the Reoort The Plant Vogtle - Unit 1 Technical Specification 3.7.10, ar_ea Temperature Monitoring, requires that:
s "The Maximum Normal Temperature of each area shown in Table 3.7-3 shall not be exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the Maximum Abnormal Temperature of Table 3.7-3 shall not be exceeded."
On. January 6, 1988, the room temperature for rooms R147 and R149 in the Control Building were recorded at 81 degrees Fahrenheit for a twelve hour period.
Table 3.7-3 indicates that the maximum normal temperature for those rooms is 80 degrees Fahrenheit and that the maximum abnormal temperature is 87 degrees Fahrenheit.
It should be noted that R147 is the lobby outside elevator no. 2 and that R149 is the corridor from the lobby to the Instrument Repair Room.
Technical Specification 3.7.10.a states:
"Hith one or more areas exceeding the Maximum Normal Temperature limit (s) shown in Table 3.7-3 for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that provides a record of the cumulative time and the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analysis to demonstrate the continued l
OPERABILITY of the affected equipment.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable."
Since the maximum normal temperature was exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, a Special Report is required to be submitted to the NRC in accordance with Technical Specifications 3.7.10.a and 6.8.2.
0831m E-1 03/14/88 SL-4339 700775
LT, GeorgiaPower d ENCLOSURE (Continued)
SPECIAL REPORT 50-424/1988-001 B.
Enaineerina Evaluation The equipment qualification temperatures for the safety-related equipment located in Rooms R147 and R149 were reviewed by Plant Field Engineering - Operations.
This review determined that the safety-related equipment in these Control Building rooms was qualified for at least 120 degrees Fahrenheit.
Based on this review, the 81 degrees Fahrenheit reading will not decrease or adversely affect the qualified life of any safety-related components in these rooms.
This demonstrates the continued operability of any affected equipment.
0831m E-2 03/14/88 SL-4339 mns