ML19241C224

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Forwards Revision 13 to Fire Protection Evaluation Rept, Consisting of Three Revised Pages & Supplemental Rept, Fire Protective Cable Tray Fire Test
ML19241C224
Person / Time
Site: Zimmer
Issue date: 07/13/1979
From: Borgmann E
CINCINNATI GAS & ELECTRIC CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19241C225 List:
References
NUDOCS 7907300387
Download: ML19241C224 (6)


Text

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THE CINCIN NATI GAS & ELECTRIC C OM PAN Y M '"

CINCINN A TI O 310 452o1 E. A. BO RG M A N N tc r eat s c t =r t % 3 %g t e = ,

Docket No. 50-358 Tuly 13, 1979 Mr. Harold Denton, Di ector Office of Nuclear Rea' tor Fegulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RE: WM. H. ZIMMER NUCLEAR POWER STATICN -

UNIT 1 - AMENDMENT 95 - SUBMITTAL OF REVISION 13 TO THE FIRE PROTECTION EVALUATION FIPCRT

Dear Mr. Denton:

The Cincinnati Gas & Electric Company on behalf of itself and as agent for Columbus and Southern Ohio Electric Cc:rpany and The Payton Power and Light Company hereby submits forty (40) copies of Revision 13 to the Fire Protection Evaluation Report for the Wm. H. Zirrer Nuclear Power Station -

Unit 1 (ZFS-1). This revision is in the form of change out pages to the Ejre Protection Evaluation Report and a supplemental report to the Fire Protection Evaluation Report. It is entitled " Fire Protective Cable Tray Fire Test", by Melvin S. Abrams, of Construction Technology Laboratories.

The supplemental repcrt should be f!!ed with the Fire Protection Evaluation Report as it pertains to Questions 7 and 12.

Very truly yours, TUE CINCINNATI GAS & ELECTRIC COMPANY By E. A. BORGMANN

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Senior Vice President EAB: dew Enclcsure cc: Charles Eechhoefer State of Chio ) A r rj Glenn O. Bright

  • NUU gl U 'i i'i 7 County of Hamilton) '

Frank F. Hooper Troy B. Conner, Jr. Sworn to and subscribed before me James P. Fenstermaker this /3 d day of July, 1979.

Steven G. Smith a William J. Moran J. Robert Newlin 790730033 William G. Porter, Jr. (w'I , abg James D. Flynn tary Public Thomas A. Luebbers MARGAPET L HUBER Leak S. Kosik N/ry FJ "

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THE CINCIN NATI GAS & ELECTRIC C O M PA N Y t'

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Cocket No. 50-358 July 13, 1979 Fr. Harold Centen, Directcr Cffice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Ccemissicn Washington, D.C. 20555 RE: WM. H. ZIP 3ER NUCLEAR PCWER STATICN -

UNIT 1 - AMENCMENT 95 - SCEMITTAL CF REVISICN 13 TO THE FIRE PROTECTICN EVALCATICN REPCRT

Dear Mr. Centen:

The Cincinnat! Gas & Electric Company on behalf of itself and as agent for Colu-tus and Scuthern Chio Electric Company and The Dayton Power and Light Ccepany hereby sub:.jts forty (40) copies cf Revision 13 to the Fire Protection Evaluation Report for the Wm. H. Zimmer Nuclear Pcwer Staticn -

Unit 1 (CPS-1). This revisicn is in the form of change cut.pages to the Fire Protecticn Evaluation Report and a supplemental report to the Fire Protection Evaluation Report. It is entitled " Fire Protective Cable Tray Fire Test", by Melvin S. Abrams, of Ccnstruction Tecnnolcqy Lateratories.

The supplemental repcrt should be filed with the Fire Protect:.cn Evaluation Report as it pertains to Questions 7 and 12.

Very truly yours, THE CINCINNATI GAS & ELECTPlc CCMPANY

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E. A. ECRCP. ANN Senior Vice Pr esident EAB: dew Enclosure cc: Charles Eechhcefer State of Chio )

Glenn O. 3right Ccunty of Hamilton)

Frank F. Eccper Troy 3. Conner, Jr. .

. Swcrn to and subscribed before ce uames P. Fenster.aker this f3g day of July, 1979.

Steven G. Smi.a.

William J. Mcran J. Rchert Newlin W.i '.liam G . Porter, Jr.

James D. r,ynn

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tary Public Thcras A. Luebters y....,-

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ZPS-1 Revision 13 July 1979 WM. H. ZIMMER PCWER STATION IJ iTRUCTICNS FCR UPDATING YOUR FIRE PROTECTION EVALUATICN REPORT Changes to the Fire Protection Evaluation Report are identified by a vertical line and revisien nurter in the right margin of the page. To update your copy of the ZPS-1 Fire l'rotection Evaluation Report, rencve and destroy the following pages and insert pages as indicated:

FEMOVE INSERT QUESTICN AND ANShTR SECTICN Page Q7-1 Page Q7-1 Page 112-1 Pages Q12-1 and Q12-2

-- The supplemental report " Fire Protective Cable Tray Fire Test" should be filed with the Fire Protection Evaluation Report.

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ZPS-1 REVISION 13 JULY 1979 OUESTIOS 7 (SECTIOS a.L.2, DIVISIO5 1 SWITCHGEAR AREA)

" Describe the fire barriers to be provided for the Division 2 cable trays which pass through this area. Indicate the fire barrier rating to be specified."

RESPONSE

In the Division 1 switchgear area, the Division 2 (blue) redundant cable trays will be protected with Kaowool blanket material chich has been qualified by tese for the tray configuration to be protected. The 11 protective material will be of thickness as qualified by test to give a minicus 1-1/2-hour fire barrier.

7 Heri:cntal trays and ve_tical trays (risers) will be enclosed with a 13 Kacwool blanket material which has been qualified to give a minimum 11 1-1/2 hour fire barrier by test.

  • The test titled, " Fire Protective Cable Tray Fire Test, September 1975 Through January 1979, f o r 'in. H. Zimmer Nuclear Station,"

fil (Engineering Report Number 75-9-FP-l) was submitted in Fire Protection Revisicn 12.

A supplementary test titled, " Fire Protective Cable Tray Fire Test," 13 by M. S. Ab rams o f Cons truction Technology Laboratories , a division of Portland Cement Association, June 1979, is submitted in Fevision 13.

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ZPF RE"ISION 13 JULY 1979 OCESTION 12 (SECTION 3.4.9, LIFT TRUCK ROUTE INTO AUXILIARY BUILDING)

"a. Provide the results of an analysis of the effects on the redundant safety related cables and their associated systems of an exposure fire occurring in this area. Assume that the exposure fire is fueled by combustibles that are . o rnally carried through this area by the lift trt s. If a fire should occur in this area that could not be ext _. .,uished by the spria-kler system or should the sprinkler syster fail to operate, what are the consequences as they affect safe shutdown.

"b. Provide the design criteria for the sprinkler systen to be provided for this area.

"c. This area is separated from the turbine building by a rated fire wall. A large opening is provided in thi; wall for the lift trucks to move between the turbine building and the reactor building. Describe the bulkhead type door, including the automatic or self-closing hardware to be provided and the fire rating of the door."

RESPONSE

a. Cable trays and cable bus for Division 2 (blue) whinh cross this area will be protected by a 1-hour passive fire barrier in addition 7 to the automatic sprinkler systen. The cable trays will be protected by Kaowool blanket material (see Question 7) which has been 13 qualified by cest.*

The Division 2 cable bus will be enclosed in a fire rated corridor which will connect tne Division 2 diesel generator room with its associated switchgear room on the opposite side of the lift truck route. Located in this corridor, the caole bus will be segregated from the lift truck coute. Additional information and drawings illustrating this arrangement will be subritted in a future revision.

5. This area is protected by an automatic wet-pipe sprinkler sys ten based on a design density of 0.30 gpm/f t2 for a total flow of 434 gpa.

Ele sprinkler water for this system is a separate supply from the l auxiliary building fire water supply header.

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  • The test titled, "F' e Protective Cable Tray Fire Test, September 1973 Ill Through Januari 1979, f o r ;:m . H. Zi==er Nuclear Station," (Engineering Report Number 78-9-FP-1) was submitted in Fire Protection Revision 12. I A supplementarv test titled, " Fire Protective Cable Tray Fire Test," 13 by M. S. Ab rams of Cons truc tion Te . nology Laboratories, a division af Portland Cement Association, June 09, is submitted in Revision 13.

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ZPS-1 REVISION 13 JULY 1979

c. As shown on drawing M-426, Sheet 11, in Chapter 8, this area is separated from the other areas of the auxiliar'/ building by fire rated walls. At this elevation the lift truck route through this auxiliary building is considered an extension of the turbine building for fire protection requirements.

The removable bulkhead wall is designed to protect safety-related areas from the design-basis flood aa discussed in FSAR Subsection 2.4.1.4.

See paragraph three on Page QS-1 for a description of the water curtain wall at the turbine roca entrance to the lift truck route. 8 h iJU

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