ML20035D428
| ML20035D428 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/06/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035D422 | List: |
| References | |
| NUDOCS 9304130202 | |
| Download: ML20035D428 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.170TO FACILITY OPERATING LICENSE NO. DPR-66 AND AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO. NPF-73 DV0VESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY
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BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 I
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1.0 INTRODUCTION
By letter dated November 2,1992, the Duquesne Light Company, et al. (the licensee) submitted an application for amendments to the Beaver Valley Power i
Station, linits 1 and 2, Technical Specifications.
The proposed amendments would allow the licensee to use approved temporary closures for containment penetrations during alterations of the core or movement of irradiated fuel t
within the containments. The temporary closures would be functionally equivalent to the ::lvas or blind flanges th.c are normally used as closures.
2.0 BACKGROUND
Limiting Condition for Operation (LCO) 3.9.4.c in the Technical Specifications for both units is applicable during alterat;ons of the core or movement of irradiated fuel within the containments. The LC0 requires that each containment penetration be closed with a valve or blind flange or that the containment atmosphere be continuously purged to the environment through high efficiency filters and charcoal absorbers. However, closing certain penetrations with valves or blind flanges would prevent the licensee from using the penetrations for routing cables into containment that are necessary in order to use eddy current test equipment for the examination of piping or other components or to facilitate other outage activities.
3.0 PROPOSED CHANGE
S TO THE TECHNICAL SPECIFICATIONS 3.1 LC_0Ls.
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LC0 3.9.4.c.1 would be revised to permit closure of containment penetrations with approved temporary closures that would be functionally equivalent to 9304130202 930406 PDR ADOCK 05000334 P
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i d valves or blind flanges in that they would prevent air and contaminants within the containment from leaking to the environment as a result of barometric, diurnal, or other modest pressure changes.
3.2 BASES The Bases for LC0 3.9.4 and Surveillance Requirement 4.9.4 would be changed to indicate that temporary closures would be capable of retaining the radioactivity released within containment that would be associated with credible accidents, including the rupture of a fuel element, that might occur during alterations of the core or movement of irradiated fuel.
4.0 EVALUATION The " Standard Technical Specifications for Westinghouse Plants" (NUREG-1431, Revision 0, Volumes 1 and 3, dated September 28, 1992), permits the use of closures that are equivalent to valves or blind flanges for closure of containment penetrations during alterations of the core or movement of irradiated fuel assemblies within containment.
Pressure ratings for the equivalent closures are not set forth in the Technical Specifications because failure of a fuel assembly in containment with the reactor shut down would not cause a measurable pressure transient. Further, the bases for this Standard Technical Specification state that containment pressurization is unlikely while the reactor is shut down for refueling and that 10 CFR Part 50, Appendix J leakage criteria and tests are not required.
The staff finds the licensee's proposed addition to the Technical Specifications for Beaver Valley Units 1 and 2 consistent with the Westinghouse Standard Technical Specifications and is acceptable since it provides an adequate level of safety for the applicable conditions.
5.0 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.
6.0 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.
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 nc public comment on such finding (58 FR 5429). Accordingly, the amendments meet j
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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7.0 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 Contributor:
R. Woodruff Date: April 6, 1993 i
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