3F1193-11, Responds to Generic Ltr 92-08, Thermo-Lag 330-1 Fire Barriers
| ML20058D867 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/24/1993 |
| From: | Beard P FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 3F1193-11, GL-92-08, GL-92-8, NUDOCS 9312060072 | |
| Download: ML20058D867 (2) | |
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9 Florida Power CORPORATION Cryataf %+t Unit 3 Docket No. M302 November 24, 1993 3F1193-Il l
U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
Subject:
Response to Generic Letter 92-08
References:
A. NRC to FPC letter, 3N1292-17, dated December 17, 1992 B. FPC to NRC letter, 3F0493-06, dated April 15, 1993 C. NRC to FPC letter, 3N1093-15, dated October 21, 1993
Dear Sir:
The Nuclear Regulatory Commission issued Generic letter 92-08, "Thermo-Lag 330-1 Fire Barriers," Reference A, requesting Florida Power Corporation (FPC) provide i
information concerning the use, testing, installation, ampacity ratings, i
configurations, planned corrective actions, and compensatory measures taken for l
Thermo-Lag 330-1 material used at Crystal River Unit 3.
By Reference B, FPC j
l responded to this request for information. An additional request for information i
was received, Reference C, concerning the schedule for completion of corrective actions on restoring the fire barrierr. We understand the NRC is aware that the l
supplemental information requested cannot be readily supplied. This response, however, does provide FPC's current approach to the issue.
i Florida Power Corporation will review the results of the NUMARC industry Thermo-Lag program and develop a corrective action plan for resolution of the fire endurance and ampacity concerns for both the generic and plant specific Thermo-Lag fire Sarrier configurations.
This plan will be submitted to the NRC followins management approval of the corrective action plan.
010033 CRYSTAL RIVER ENERGY COMPLEX: 15760 W. Power Line Street + Crystal River, Florida 34423-0219 + (904) 795-6486 pita n8M EddMoa
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PDR I
e U. S. Nuclear Regulatory Commission 3F1193-11 Page 2 of 2 FPC does not expect to upgrade any fire barriers.
Rather, we anticipate using the results of the test program and our plant specific risk assessment to demonstrate that adequate protection is provided. Further, the ampacity impacts are not expected to require significant corrective action.
Sincerely, P.
. Beard, Jr.
Senior Vice President Nuclear Operations PMB/REF:ff i
xc: Regional Administrator, Region II NRR Project Manager Senior Resident Inspector l
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