ML20031A690
| ML20031A690 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/14/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031A685 | List: |
| References | |
| NUDOCS 8109250122 | |
| Download: ML20031A690 (3) | |
Text
.
[*
UNITED ST ATES E
NUCLEAR REGULATORY COMMISSION n-
.: y WASHING TON, D. C. 20555
%..... +o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
' SUPPORTING AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY t
BIG ROCK POINT PLANT ~
i<
DOCKET NO. 50-155
1.0 INTRODUCTION
By letter dated June 27, 1980 and supplement dated September 22, 1980, l
Consumers Power Company (the licensee) requested an amendment to Facility l
Operating License No. DPR-6 for the Big Rock Point Plant.
This amendment would modify the Technical Specifications to add operability and surveil-lance testing requirements for fire protection equipment that was added in accordance with the requirements of Amendment No. 25 to the license dated April 4,1979. Technical Specifications which incorporate limiting conditions for operation and surveillance requirements for previously l
existing fire protection equipment were issued by Amendment No.17 dated March 6,1978.
l l
2.0 EVALUATION L
2.1 Fire Detection Instrumentation l
By letter dated December 17. 1979 the NRC staff documented its having l
found that an adequate number and type of additior.al fire detectors l-would be installed in appropriate locations ad described in the l
licensee's August >31, 1979 submittal.
The licensee's proposed Technical Specifications would add these aoditional detectors to f a bl e 3. 3-8.
Based on our previous review, we conclude that this addition is acceptable.
The licenste's proposed Technical Specifications would modify the su_rveillance requirements for the fire detectors to specify that the detectors in the recirculation pump room will have a channel functional test at each refueling outage rather than once per six months.
The licensee has stated that the recirculation pump room is not accessible during reactor operation because of high radiation levels. Accordingly, the channel functional test will be performed during each refueling
' outage. We conclude that this surveillance schedule is acceptable.
8109250122 810914 DR ADOCK 05000155
~
^
~
a
f
. 2.2 Fire Spray and/or Sprinkler Systems The NRC staff's letter dated December 17, 1979 also found the proposed recirculation pump area sprinkler system acceptable as described in the licensee's submittal dated August 17, 1979. Appendix R to 10 CFR Part 50 requires an oil collection system for the recirculation pump lube oil system. The licensee's compliance with this requirement will he addressed in a separat'e safety evaluation.
The licensee's proposed Technical Specifications would add the recir-culation-pump area sprinkler system to the limiting conditions for operation. Because the recirculation-pump area is not accessible during normal operation, the licensee has stated that it is impossible to establish a continuous fire watch for this area during power operation.
In addition, although access to the area is possible during shutdown conditions, residual radiation levels in the area.would cause signifi-cant personnel radiation exposure if a continuous fire watch were to be established.
The licensee has proposed staging backup fire protection equipment within one hour in the event of inoperability of this system and restoring the system to operable status before startup from the next cold shutdown if the inoperable equipment is inside the pump room or within fourteen days if the inoperable equipment is outside of the pump room.
Because cf the high radiation levels and the provision for backup fire protection equipment, we find the proposed Technical Specification acceptable.
2.3 Fire Hose Stations In the Fire Protection Safety Evaluation supporting Amendment No. 25 dated April 4,1979, the NRC staff found that the addition of two fire hose stati.ons inside containment proposed by the licensee was acceptable because with this addition, all areas with sigcificant combustibles could be effectively reached with hose straams.
The licensee's proposed Technical Specifications would add these two fire stations to the limiting conditions far operation.
.le find this addition acceptable.
1.0 ENVIRONMENTAL CONSIDERAT_ ION We nave determined 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 action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR s51.5(d)(4) that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
3-
4.0 CONCLUSION
S We have concluded, based on the considerations discussed above,'that:
(1) because the amendment does not involve a significant increase in the pro-bability or consecuences of accidents previously considered and does not involve a significant decrease in a safety margin, the amenonent 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 con-ducted in compliance with the Commission's regulations and tne issuance of this amendment will not be inimical to the common defense and security of to th,e health and safety of the public.
Date:
September 14, 1981 e
l
-