ML14183A334
| ML14183A334 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/15/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML14183A333 | List: |
| References | |
| NUDOCS 9603210270 | |
| Download: ML14183A334 (2) | |
Text
ISpf REG&I 1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE NO. DPR-23 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261
1.0 INTRODUCTION
By letter dated November 22, 1995, the Carolina Power & Light Company (licensee) submitted a request for changes to the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBR), Technical Specifications (TS).
The requested changes would delete the qualifying statement, "...
provided the remaining systems are in continuous operation," from TS Section 3.3.4.2.
Currently, this statement requires the remaining systems to be in continuous operation while allowing one SW loop header, or one SW pump, or one SW booster pump to be inoperable for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.0 EVALUATION The Service Water System (SWS) is designed to provide cooling water to those components necessary for plant safety either during normal operation or under accident conditions. The SWS also supplies cooling water to various other heat loads in both the primary and secondary portions of the plant. The SWS consists of four SW intake pumps, two 100% capacity SW booster pumps, two 100%
capacity supply lines, and associated interlocks, piping, and valves. The four pumps and two supply lines are cross-connected by normally open valves.
The four SW intake pumps are located in three separate bays. Either of the two supply lines can be used to provide cooling water to all containment air recirculation cooling coils, the containment air recirculation fan motor coolers, the turbine-driven auxiliary feedwater pump, and the diesel generators. The booster pumps supply service water to the containment ventilation cooling units from the supply lines.
During normal operation, cooling loads are supplied by three of the four SW pumps.
Following a simultaneous loss-of-coolant-accident and loss of offsite power, the essential loads can be supplied by any two of the four service water pumps. The current TS require all remaining system components to operate whenever one SW pump, booster pump, or header is out of service. The proposed revision to the TS deletes the requirement for continuous operation of redundant system components.
The requirement that "the remaining systems are in continuous operation" was intended to demonstrate operability of the SW system. This method of demonstrating operability was a typical requirement that was included in the TS when HBR was granted its operating license. However, continuous operation of redundant components/systems does not provide a necessary or optimal 9603210270 960315 PDR ADOCK 05000261 P
-2 requirement for operation of a system. The NRC staff currently accepts periodic surveillance testing as adequate assurance that a system is operable.
Continuous operation of redundant systems/components is not required in NUREG 1431, "Standard Technical Specifications for Westinghouse Plants" nor in recently issued TS.
Based on the above NRC position, the continuous operation of a redundant component/system to demonstrate operability is not necessary. Additionally, the requirement imposes unnecessary operational restrictions that have no safety basis, nor is there a basis supported by the plant design or the license as originally issued or currently revised. Therefore, the NRC staff concludes the requirement to maintain a system in continuous operation for the sole purpose of demonstrating operability is unnecessary and the TS change is acceptable..
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of South Carolina official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC 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 the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 62487). Accordingly, the 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 the amendment.
5.0 CONCLUSION
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) such 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 Contributors: B. Mozafari and A. Dummer Date:
March 15, 1996