ML19340D464
| ML19340D464 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/21/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340D459 | List: |
| References | |
| NUDOCS 8012300631 | |
| Download: ML19340D464 (4) | |
Text
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UNITED STATES 1
j NUCLEAR REGULATORY COMMISSION
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5 WASHINGTON, D. C. 20555 i
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4 SUPPLEMENT NO. 1 TO THE FIRE PROTECTION SAFETY E'/ALUATION REPORT 3Y THE OFFICE OF NUCLEAR REACTOR REGULATION U.S. NUCLEAR REGULATORY COMMISSION IN THE MATTER OF NEBRASKA PUBLIC POWER DISTRICT
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COOPER NUCLEAR STATION DOCKET NO. 50-298 License Amendment No. 66 OATE: November 21, 1980 8cnsoo 651
1 By letter dated January 16, 1980, the Nebraska Public Power District (licensee) provided information regarding three specific fire protection modifications identified as "open" in the Cooper Nuclear Station Fire Protection Safety Evaluation Report (SER), issued May 23, 1979. We have completed our review and it is presented below:
Item 3.8 - Reactor Building Cable Trays; EL 903' In the SER, we statec that an automatic fire suceression system be installed in the northeast coraar of the reactor building at elevaticn 903 feet to preclude the possibility of a fire affecting redundant sets of cable trays.
The utility proposed an automatic wet-pipe sprinkler system designed and installed per NFPA Standarc No.13.
The sprinkler system water supcly neader will be connected to the existing fire protection header.
We have reviewed the arcocsed design mocification and calculations and determined that an appropriate design basis has been selected.
Based en our evaluation, we concluce that the installation cf the # ire su:-
pression system per ne aporo:riate NFPA Standards will creclude the pessi-aility of a fire affecting redundant sets of cables at elevation 903 feet, and, tnerefore, it is acceptacle.
Item 3.11 - Reactor and Control Building Automatic Sucoression Water Feed ince:encency The concern identified in the SER was for establisning an independence be: ween the automatic and manual fire protection systems water supply.
The li:ensee agreed to provide this water supply indeoendence to creclude the pcssioility of a single failure in tne fire water system from imoairing both automatic and manual fire protection systems.
The new water supply header will be installed per NPFA Standard No.13. We nave reviewed the prooosed design modification and calculations, and conclude that a proper design basis has been selected.
Based on our evaluation, we conclude that the ins tallation of an independent water supply for the manual fire protection systens per the appropri.ite NFPA Standards will preclude the possibili ty of a single failure from impairing both automatic and manual fire protection systems and, therefore, it is acc ep tabl e.
Item 3.16 - penetra tion Fires too Barri ers In the SER, we s tated that additional information was necessary tc determine the adequacy of the penetration firestop barriers. The licensee has provided this information in the form of drawings, materials description, and fire tes ted design references.
The fire tes t ref erence was the fire endurance tes t: incorporating silicone foam, ceramic fiber, cellular concrete, and marinite XL panels conducted on May 10, 1978, for Bechtel Power Corporation by Factory Mutual Research at the National Gypsum Research Center, FC 258, FC 259, and FC 250. This series of tes ts were witnessed by the NRC and have been approved by ANI and the NRC.
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2-Based on our evaluation, we conclude that sufficient information and documentation has been provided to substantiate the design adequacy of the licensee's esble penetration firestop ratings, and, therefore, is acceptable.
In sumary, with the evaluation of the above three items, we have completed the review of the Cooper Nuclear Station, Unit 1, Fire Protection program.
Technical Scecifications and Additional Information Amendment No. 56 to Facility Operating License No. OPR 46 requested that the licensee propose revised Technical Specifications related to fire protection facility modifications and provide certain additional information.
Additional information has been orovided as sumarized in Table 1.
A safety evaluation describing the licensee's complete fire protection pro-gram, including administrative procedures and the equipment to which these Technical Specifications pertain was issued on May 23, 1979, accompanying License Amendment No. 56.
Technical Specifications incorporating limiting conditions of oceration and surveillance requirements for fire protection systems were pmposed by the licensee by letter dated October 22, 1979 and subsequently modified based on telepnone discussions between the staff and the licensee. We have reviewed the proposed changes and determined that the proposed additions and changes include all necessary items contained in our fim protection evaluation, are consistent with licensing guidance contained in the NRC Standard Technical Specifications, and are therefore acceptable.
We find that the Fire Protection Program for the Cooper Nuclear Station with the improvements already made by the licensee is adequate and meets the guidelines contained in Appendix A to Branch Technical Position 9.5-1 i
and is, therefore, acceptable.
Environmental Considerations We have detemined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an i
action which is insignificant from the standpoint of environmental impact, and pursuant to 10 CFR Section Sl.5(d)(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of the amendment.
Conclusion l
We have concluded, based on the considerations discussed above, that:
l (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Dated: November 21, 1980 L
TABLE 1 ADDITIONAL FIRE PROTECTION INFORtiATION FOR COOPER Item 4 Item Descriotion S tatus 3.3.1 Foam & Spr Sys Closed by 6/28/79 ltr 3.6 Cable Chase / Turbine N. Wall Closed by 6/28/79 ltr 3.7 MG Set Oil Coolers Closed by 10/19/79 ltr i
l 3.12 Cable Expansion Room Closed by 10/19/79 ltr 3.15.2 carticle Board 'dall' Closed by 10/19/79 ltr 3.19 Laundry Rocm Spr Sys
-Closed by 10/19/79 ltr 3.27 Fire Pump Discharge Header Closed by 6/28/79 ltr 4
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