ML20137C208

Ack Completion of Licensing Action of GL 92-08, Thermo-Lag 330-1 Fire Barriers, & Requests to Retain All Documentation Related for Future NRC Audits & Insp

ML20137C208
Person / Time
Site:	Wolf Creek
Issue date:	03/20/1997
From:	Stone J NRC (Affiliation Not Assigned)
To:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
References
GL-92-08, GL-92-8, TAC-M85625, NUDOCS 9703240178
Download: ML20137C208 (4)

Text

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'% March 20,1997 Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 92-08,

" THERM 0-LAG 330-1 FIRE BARRIERS," DATED DECEMBER 17, 1992, i

WOLF CREEK GENERATING STATION (TAC NO. M85625)

Dear Mr. Maynard:

By letters dated April 16, 1993, February 9, 1994, July 15, 1994, December 22, 1994, February 15, 1995, March 10, 1995, March 29, 1995, June 27, 1995, June 20, 1996, August 2, 1996, August 23, 1996, and February 3,1997, Wolf Creek Nuclear Operating Corporation (WCN0C) responded to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," dated December 17, 1992, and follow-up requests for additional information dated May 24, 1993, June 15, 1993, December 22, 1993, September 23, 1994, December 29, 1994, May 21, 1996, and July 2,1996, in regard to Thermo-Lag 330-1 fire barriers installed at the Wolf Creek Generating Station.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your letters.

Your responses stated that one of the following actions would be completed for l Thermo-Lag conduit and raceway applications installed to satisfy commitments '

to 10 CFR 50, Appendix R:

1. An analysiT te document that the fire barrier wrap on the raceway is not required to u hieve safe shutdown,

2. Modifications to the plant such that the fire wrap on the raceways would no longer be required for 2,afe shutdown,

3. Modifications to reroute wrapped conduits and raceways, or

4. Replace existing Thermo-Lag 330-1 with Darmatt KM-1. This includes the radiant energy heat shield used inside containment.

By letter dated February 3, 1997, you stated that the corrective actions had been completed at the Wolf Creek Generating Station and that Thermo-Lag is no longer relied on to satisfy WCNOC's commitment to 10 CFR 50, Appendix R. On the basis of its review, the staff has determined that you have provided the information requested in GL 92-08 and the actions tracked by TAC No. M85625 are complete.

For other issues related to Thermo-Lag, WCNOC committed to take the following

actions

3

\) O\l 9703240178 970320 2

. PDR ADOCK 0500

Mr. Otto L. Maynard March 20, 1997 1

i

1. With respect to Thermo-Lag installed to achieve physical independence between electrical systems associated with the Class 1E power system, WCNOC would document that the existing .Thermo-Lag installations satisfy the requirements of~IEEE 384-74.

2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag.

3. For Thermo-Lag that is left installed in the plant, the material would be evaluated and added to the combustible loading for the applicable i fire areas, using industry-developed heat release values for the I material. Also, the plant Fire Hazards Analysis would be updated with the new combustible loading values.

By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been implemented at the Wolf Creek Generating Station.

The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ,

ampacity derating. The resolution of these ampacity derating issues are being treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review.

You should retain all documentation related to the resolution of the concerns with Thermo-Lag 330-1 fire barrier systems for future NRC audits or inspections, j

~

If you have any questions regarding this matter, please contact me at (301) ,

415-3063.  !

Sincerely, Original Signed By James C. Stone, Senior Project Manager 1 Project Directorate IV-2  ;

Division of Reactor Projects III/IV l Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:

Docket File EPeyton cc: See next page PUBLIC WBateman PDIV-2 Reading JStone  !

JRoe ACRS ,

EAdensam TMarsh OGC JCalvo D0udinot LTran AHowell, RIV WJohnson, RIV DOCUMENT NAME: 85625CLO.WC *See Previous Concurrence OFC PDIV-2/PMh PDIV-2/LA' NRR:SPLB* NRR:EELB* .

NAME JStone:ye E TMarsh -JCalvo DATE 3/%/97 340/97 3/19/97 3/12/97 0FFICIAL RECORD COPY

l 5 Mr. Otto L. Maynard March 20, 1997

1. With respect to Thermo-Lag installed to achieve physical independence between electrical systems associated with the Class IE power system,  ;

j WCNOC would document that the existing Thermo-Lag installations satisfy the requirements of IEEE 384-74.

2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag.

3. For Thermo-Lag that is left installed in the plant, the material would l be evaluated and added to the combustible loading for the applicable l fire areas, using industry-developed heat release values for the ,

material. Also, the plant Fire Hazards Analysis would be updated with l the new combustible loading values.

4 By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been completed at the Wolf Creek Generating Station.

The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ampacity derating. The resolution of these ampacity derating issues are being 2

treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review.

You should retain all documentation related to the resolution of the concerns with Thermo-Lag 330-1 fire barrier systems for future NRC audits or inspections.

3 If you have any questions regarding this matter, please contact me at (301) 415-3063.

Sincerely, l

[

James C. Stone, Senior Project Manager l Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nucles Peactor Regulation Docket No. 50-482 cc: See next page l

l l 1

s

. l 4

o Mr. Otto L. Maynard March 20, 1997 4 cc:

Jay Silberg, Esq. Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office  !

P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division i Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027

. Office of the Governor State of Kansas Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W. 10th 2nd Floor Topeka, Kansas 66612 County Clerk l

Coffey County Courthouse l Burlington, Kansas 66839 Public Health Physicist Bureau of Air & Radiation i Division of Environment Kansas Department of Health and Environment Forbes Field Building 283 i Topeka, Kansas 66620 4 4

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