ML20063L309
| ML20063L309 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/01/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063D083 | List: |
| References | |
| NUDOCS 9403040189 | |
| Download: ML20063L309 (2) | |
Text
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!.kJ [. j UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555 0001
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'N SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.109 TO FACILITY OPERATING LICENSE NO. NPF-10 AND AMENDMENT NO. 98 TO FACILITY OPERATING LICENSE NO. NPF-15 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA SAN ONOFRE NUCLEAR GENERATING STATION. UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
By letter dated November 25, 1991, Southern California Edison Company, et al.
(SCE or the licensee) submitted a request for changes to the Technical Specifications (TS) for San Onofre Nuclear Generating Station, Unit Nos. 2 and 3.
The proposed changes would revise TS 3/4.7.8, " Fire Suppression Systems."
This TS revision deletes the phrase "during shutdown" from the fire pump diesel engine surveillance requirement 4.7.8.1.2.c.
This will allow the surveillance of the fire pump diesel engine to be performed when one or both Units 2 and 3 are in operation.
2.0 EVALUATION The diesel engine for the redundant fire water pump is to be inspected every 18 months. The inspection shall be in accordance with procedures prepared in conjunction with the manufacturer's recomendations. This Surveillance Requirement (SR) is described in Technical Specification 4.7.8.1.2.c, which currently states that this surveillance is to be parformed during plant shutdown.
Because the fire pump is comon to Units 2 and 3, and the SR is in the TS's for both Unit 2 and 3, either both Units 2 and 3 must be shut down simultaneously for a single surveillance to be performed or the Units may be shutdown separately and two surveillances must be performed. The proposed TS change deletes the phrase "during shutdown" from the SR, and clarifies that a single surveillance performed at any time within the surveillance interval satisfies the SR for both units. This clarification avoids an unnecessary shutdown of Unit 2 and/or Unit 3 when the inspection schedule does not coincide with outages.
MUN$k P
, The fire pump diesel engine drives the fire water pump P220.
This 100%
capacity pump provides redundancy to the two 50% capacity electrical driven pumps P221 and P222. The purpose of these three pumps is suppression of fires. The fire pumps are common to Units 2 and 3.
The 18-month inspection entails inspecting the oil level, turbocharger clearance, V-belt, idler, hub, hose and fuel, air, and cooling systems for the Fire Pump Diesel Engine. Performance of the inspection requires declaring the diesel engine and the fire pump it serves INOPERABLE.
Inoperability of the diesel driven fire pump for all modes is covered by ACTION statement 3.7.8.1, which specifies an allowed outage time (A0T) of 7 days.
TS 3.7.8.1 is applicable at all times. The ACTION statement 3.7.8.1.a requires the pump to be returned to service within 7 days or provide an alternate backup pump or fire water supply. The proposed change to the SR does not alter the ACTION statement.
The fire pump diesel engine inspection can be performed in approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />, which is a small fraction of the 7-day A0T. Actual inspection times have been 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 18.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, and 16.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
The three previous inspections were performed on December 8, 1987, June 21, 1989, and November 6, 1990.
The inspections resulted in routine mai tenance on all three occasions.
Maintenance involved replacing cracked V-belts, a broken flex hose, and a frayed wire, and adding engine oil. Combined inspection and maintenance inoperability periods were 2, 3, and 6 days, respectively. There is reasonable assurance that the inoperability of the fire pump diesel engine will not exceed the 7-day A0T based on this maintenance history.
The staff finds acceptable the deletion of the phrase "during shutdown" from SR 4.7.8.1.2.c because during the time period while the dicsel-driven fire pump is undergoing maintenance, the two electric-driven fire pumps provide the 100% flow capacity requirement. Therefore, the entry into the 7-day A0T to perform maintenance on the diesel-driven fire pump once every 18 months will not have a significant impact on the system's overall ability to perform its function. This flexibility is due to San Onofre having three fire pumps, instead of the two 100% capacity fire pumps specified in the Standard Technical Specifications for Combustion Engineering PWRs (NUREG-0212 Rev. 2).
In addition, surveillance of the fire pump diesel engine has no effect on normal operating status of the plant and does not increase the likelihood of a transient.
There is no change in the 18-month inspection interval length, so reliability and availability of the fire pump diesel engine are not affected.
The licensee's November 25, 1991, letter also requested that an editorial change be made to the Unit 3 electrical power system SR 4.8.1.1.1.a to correct the mis-identification of breakers 2A0619 and 2A0417. This editorial correction was included in the staff's June 15, 1993, approval of TS amendment request No. PCN-427.
PCN-427 affected the same page that contains SR 4.8.1.1.1.a, and was processed first because of its higher priority.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement. The NRC staff has determined that the amendments involve 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 the amendments involve no significant hazards consideration, and there has been no public comment on such finding (57 FR 2600). Accordingly, the amendments meet 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 the amendments.
5.0 CONCLUSlQN The Commission 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, (2) tuch activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Hel B. Fields Date: February 1, 1994 i
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