ML13316A927
| ML13316A927 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/30/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A924 | List: |
| References | |
| NUDOCS 8606130280 | |
| Download: ML13316A927 (4) | |
Text
0 REUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
93 TO PROVISIONAL OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
By letter dated June 8, 1984, as modified on December 17, 1985 and supplemented on April 1, 1986, Southern California Edison Company (the licensee) proposed changes to the San Onofre Nuclear Generating Station, Unit No. 1 Technical Specifications (TSs).
The amendment modifies the TSs to specify that reactor shutdown is not required and that changing of operational modes is allowed when certain fire protection equipment is inoperable, provided that specified compensatory measures have been taken. The remainder of the technical specification changes requested by the above submittals are still under staff review and will be addressed by a separate evaluation.
2.0 DISCUSSION The licensee's June 8, 1984 proposal included a specification in certain ACTION statements to note that if certain fire protection equipment was inoperable, the provisions of existing Technical Specification 3.O.A do not apply. TS 3.0.A stated that if the limiting conditions for operation are not met and the required action is not taken, actions must be initiated to put the unit into an operational mode in which the specification does not apply, i.e.;
(1) At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, (2) At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and (3) At least COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-8606130960 860530 PDR ADOCK 05000206 SP PDR
-2 Since the existing fire protection TSs are applicable in all operational modes, reactor shutdown would eventually be required by TS 3.0.A.
However, License Amendment No. 83, issued on November 2, 1984 removed TS 3.0.A and replaced it with TSs 3.0.3 and 3.0.4, which are consistent with the NRC's Standard Technical Specifications. Thus, the licensee's December 17, 1985 proposed Technical Specifications were modified to state that neither TS 3.0.3 or TS 3.0.4 is applicable in the event that certain fire protection equipment is inoperable. TS 3.0.3 is identical to old TS 3.O.A. TS 3.0.4 prohibits entry into an operational mode unless all limiting conditions for operation (LCO) are met without reliance on the provisions contained in the ACTION statements.
3.0 EVALUATION The licensee's December 17, 1985 submittal proposed to add the statement that TSs 3.0.3 and 3.0.4 are not applicable when fire protection equipment LCO's are not met for fire suppression water systems, fire suppression spray and/or sprinkler systems, fire hose stations, and fire detection instrumentation. However, if all fire suppression water systems become inoperable, TSs 3.0.3 and 3.0.4 would be applicable; reactor shutdown would be required and entry into an operational mode would be prohibited.
As discussed in Section 2.0 above, the above changes modify the fire protection technical specification requirements to be consistent with the requirements prior to the issuance of License Amendment No. 83 on November 2, 1984. When Amendment No. 83 was issued, the staff did not intend for the change to effect plant operation when certain fire protection equipment became inoperable. The changes implemented by this Amendment will resolve the situation inadvertently created by Amendment No. 83.
The staff has reviewed the proposed changes for the fire protection systems listed above and has determined that they are consistent with the NRC's Standard Technical Specifications. Thus, the staff concludes that the technical specification changes described above meet the applicable NRC guidance and are acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted
-3 area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts,-and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ACKNOWLEDGEMENT This Safety Evaluation has been prepared by Richard F. Dudley.
Dated:
May 30, 1986
MAY 3 0 1986 DISTRIBUTION:
Docket Files NRC PDR Local PDR G. Lear P. Shuttleworth OELD L. Harmon E. Jordan B. Grimes J. Partlow E. Butcher (TSCB)
T. Barnhart (4)
ACRS (10)
OPA FOB, (DPLA)
LFMB PD#1 r/f PD#1 s/f R. Dudley