ML20216H514
| ML20216H514 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/24/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216H503 | List: |
| References | |
| NUDOCS 9910010406 | |
| Download: ML20216H514 (2) | |
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g NUCLEAR. REGULATORY COMMISSION WASHINGTON, D.C. aceeH001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. DPR-16 GPU NUCLEAR. INC. AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
By letter dated December 23,1998, GPU Nuclear, Inc. (the licensee) submitted a request for changes to the Oyster Creek Nuclear Generating Station Technical Specifications (TSs). The requested changes would revise the surveillance frequency for verifying the operability of motor-operated isolation valves and condensate makeup valves in the isolation Condenser TS 4.8.A.1 and Bases page from once per month to once per 3 months.
2.0 EVALUATION The Isolation Condenser System (ICS) is a standby, high-pressure system for the removal of fission product decay heat when the reactor vessel is isolated from the Main Condenser. The system prevents overheating of the reactor fuel, controls the reactor pressure rise, and limits the loss of reactor coolant through the relief valves.
The ICS consists of two full-capacity isolation condensers, four AC motor operated isolation valves, four DC motor-operated isolation valves, and three vent lines to the atmosphere. The j
electrical system used to place the ICS in operation. The system operates with steam flowing from the reactor pressure vessel through the condenser tubes and condensate returning by gravity to the reactorpressure vessel, forming a dosed loop. The valves in the steam inlet lines
- are normally open so that the tube bundles are at reactor pressure. The DC motor-operated condensate isolation valves, which are normally closed, are the only valves that need to be opened in order to place the ICS in operation.
"TS 4.8.A.1 requires th'at the operability of motor-operated isolation valves and condensate 4
makeup valves in each isolation condenser loop be verified once per month. These valves are
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normally on standby and should be exercised periodically to ensure their ability to operate freely. The licensee proposes to extend the frequency of testing to once every 3 months. The licensee states that surveillance test data from the previous 3 years indicate that the valves are l
reliable. Also, the risk of a plant transient from surveillance testing, personnel radiation I
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i i exposure, and equipment degradation would be reduced as a result of the proposed increase in the surveillance test interval.
The 1986 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section IWV-3411 requires that inservice testing (IST) of Category A and B valves be conducted at least once every 3 months. Testing at this frequency provides sufficient assurance that, when called upon, valves will operate as required. The licensee's t
proposed change in surveillance test frequency is consistent with the philosophy of the IST
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Code, and therefore will provide acceptable assurance of the valves operability. Also, this
- change is consistent with the surveillance requirements in the boiling-water reactor Standard Technical Specifications.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment. The State official stated that it 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 and changes surveillance requirements. 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 (64 FR 17026). Accordingly, the amendinent 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 Contributor: M. Kotzalas Date: September 24, 1999