ML20005B642

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Comments on Latest Sandia & Underwriters Labs Info Re NRC-sponsored Fire Protection Sys Replication Tests.Water Supply Sys Pressure & Flow Info Should Be Increased.Proposed Second Fire Brigade Response Test Should Be Changed
ML20005B642
Person / Time
Site: Browns Ferry  
Issue date: 06/30/1981
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8107080470
Download: ML20005B642 (2)


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JUL 0 71981 > 1 Mr. Harold R. Denton, Director

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U.S. Nuclear Regulatory Commission t/s Washington, DC 20555

Dear Mr. Denton:

L In the Matter of the

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Docket Nos. 50-259 Ter.nessee Valley Authority

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50-260 50-296 A review has been made of the latest information supplied by Sandia and Underwriters' Laboratories concerning NRC-sponsored fire protection system replication tests for the Browns Ferry Nuclear Plant (BFNP). The following comments are submitted for your consideration.

Water Supply System There is a slight difference between the pressure and flow information supplied by TVA and that stated by Underwriters' Laboratories, Inc.

(UL) to be used in the replication tests.

Pressure Flow TVA 118 psi 248 gpm UL 107 psi 225 gpm Because the flow error approaches 10 percent, we believe that the pressure and flow should be increased to reflect actual conditions.

Cable Type All uncoated cable observed in tray KS-ESIl at BFNP was type PXMJ. Thi3 cable is covered with a chlorosul_"onated-polyethylene outer jacket and will pass the IEEE 383 Flame Test. The test plan indicates that a more flammable PCV cable will be used. We believe that a less flammable cable would be more representative of Browns Ferry.

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. Mr. Harold R. Denton June 30, 1981 Water Spray System Location From illustration 4, submitted with the latest test plan, it appears that the water spray system designated in the detail drawings as H17 is mistakenly located to the east of vertical trays KT and KE-ESII.

In fact, H17 branches off beneath the centerline of tray KT and the discharge nozzles are located in the space between the four vertical trays. This offset to the west, to ensure that a set of nozzles is located between the vertical trays, can be noted on drawing 47W491-17(R4), Detail H17 Because this set of nozzles will significantly reduce the chimney effect between trays, we believe that proper installation of the nozzles is very critical to the test.

Fire Brigade Response We believe that changes should be made with regard to the proposed second test. Upon comp 1stion of the first test we shall make a formal recommendation of suggested changes to NRC on the proposed test.

Very truly yours, TENNESSEE VALLEY AUTHORITY s

L. M. Mills, Man ger Nuclear Regulation and Safety Subscrib sworn before me thi day of W 81.

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