ML20083M632
| ML20083M632 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/15/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083M629 | List: |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9505190375 | |
| Download: ML20083M632 (3) | |
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j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20866-0001
%,.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS 187 AND 69 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated April 19, 1994, as supplemented March 31, 1995, Duquesne Light Company (DLC or the licensee) proposed Technical Specifications (TSs) changes i
for Beaver Valley Power Station, Units 1 and 2.
These changes were in response to NRC Generic Letter (GL) 90-06, " Resolution of Generic Issue 70,
" Power-Operated Relief Valve and Block Valve Reliability," and Generic Issue 94, "Additionhl Low-Temperature Overpressure Protection for Light-Water Reactors," Pursuant to 10 CFR 50.54(f)." The proposed amendment would revise the TSs related to power operated relief valves (PORVs) and low ~ temperature overpressure protection (LTOP) to enhance plant safety and improve the.
reliability of the PORVs during all modes of plant operation. The March 31, 1995, letter provided typed final TS pages for issuance of these amendments and included minor editorial changes that did not change the initial proposed no significant hazards consideration determination or expand the scope of the original Federal Reaister notice.
2.0 EVALUATION The licensee's proposed TS anendment is consistent with the intent of the recommendations of GL 90-06. The NRC staff-recommended allowable outage times (A0T) for various PORV inoperable conditions are adopted in the licensee's proposed TSs and are, therefore, acceptable to the NRC staff.
GL 90-06 recommends improvements to the quality assurance, maintenance, and testing of the PORVs and block valves.
For both Units 1 and 2, the licensee has proposed improvements which generally agree with the GL recommendations.
The licensee includes both the Unit 1 and 2 PORVs and block valves as QA Category I on the Master Equipment Lists, and the maintenance programs include 9505190375 950515 PDR ADOCK 05000334 P
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4+ maintenance and refurbishment in accordance with the manufacturers recommendations. Since the PORVs on Unit I are air-operated, the air control valves, in addition to the PORVs, are tested and included in the inservice testing (IST) program.
For both Units 1 and 2, the block valves are included in the GL 89-10 motor-operated valve test program as recommended.
The licensee has proposed to demonstrate the operability of the PORVs at least once per 18 months by operating the PORVs through one complete cycle of full travel without specifying operation in any specific mode. This proposal differs from the recommendations of GL 90-06 to test the PORVs at least once per 18 months in Mode 3 or 4.
The proposed change is necessary for Unit 2 because the licensee has determined that (1) the PORVs cannot be fully stroked with their block valves closed, and (2) with the block valve open, repeated cycling of the PORVs would result in overstressing of the downstream piping since it is designed to withstand only a limited number of valve actuation cycles at full pressure conditions. Demonstration of PORV operability at least once per 18 months without specifying operation in any specific mode (testing would normally be performed in Mode 5) is consistent with the NRC staff's current position for testing these valves as reflected in the NRC's improved Standard Technical Specifications (NUREG-1431) and is acceptable to the NRC staff. Therefore, the NRC staff has determined that the proposed TS changes are acceptable since, within the limits of the plant design, the licensee has satisfied the intent of the GL 90-06 recommendations regarding the quality assurance, maintenance, and testing of the Unit 1 and 2 PORVs and block valves.
3.0 STATE CONSULTATION
In accordance' with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change 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 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 (59 FR 34661). 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.
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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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
C. Liang.
C. Hammer Date:
May 15,1995 I
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