ML20077C617
| ML20077C617 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/28/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C614 | List: |
| References | |
| NUDOCS 9412050322 | |
| Download: ML20077C617 (4) | |
Text
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UNITED STATES i hf.lf )
E NUCLEAR REGULATORY COMMISSION c'
I WASHINGTON, D.C. 205W0001 gg, v /
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 80 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated July 15, 1994, Wolf Creek Nuclear Operating Corporation (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-42) for the Wolf Creek Generating Station. The proposed changes would revise Technical Specification Table 4.3-3, Radiation Monitoring Instrumentation for Plant Operations Surveillance Requirements, to increase the analog channel operational test (ACOT) interval for the following radiati.on monitors from monthly to quarterly:
Containment Atmosphere - Gaseous Radioactivity - High (GT-RE-31 and 32)
Gaseous Radioactivity - RCS Leakage Detection (GT-RE-31 and 32)
Particulate Radioactivity - RCS Leakage Detection (GT-RE-31 and 32)
Fuel Building Exhaust - Gaseous Radioactivity - High (GG-RE-27 and 28)
Criticality - High Radiation Level (SD-RE-37 and 38, SD-RE-35 and 36)
Control Room Air Intake - Gaseous Radioactivity - High (GK-RE-04 and 05)
This proposed change is identified as a line item improvement in Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," and recommends the ACOT interval be changed from monthly to quarterly.
2.0 BACKGROUND
The following safety-related radiation monitors:
control room air supply (GK-RE-04 and 05), fuel building exhaust (GG-RE-27 and 28), and containment atmosphere (GT-RE-31 and 32), are designed to isolate the control room, fuel building and containment, respectively, if airborne radioactivity exceeds allowable limits.
In addition, containment monitors GT-RE-31 and 32 provide for detection of gaseous and particulate leakage from the reactor coolant system.
These monitors are redundant for single-failure protection, designed to meet seismic Category I requirements and are powered from a Class IE power source.
9412050322 941128 DR ADOCK 05000482 PDR
' Monitors SD-RE-35, 36, 37, and 38, are part of the fuel building area radiation monitoring system and serve as the criticality monitors for the new spent fuel pool (SD-RE-35 and 36) and the spent fuel storage pool (SD-RE-37 and 38). These monitors are not safety-related and are powered from a non-Class IE power source.
3.0 EVALUATION The licensee has stated in their application that performing the ACOT on the radiation monitors requires access to the delicate instruments inside the radiation monitor cabinets.
The monthly tests have the potential to cause damage to these delicate instruments.
In addition, the licensee has reviewed ACOT data and determined that for the safety-related radiation monitors, no calibration or set-point problems have been experienced since the beginning of plant operation.
Increasing the ACOT interval from monthly to quarterly will reduce the potential for instrument damage and reduce the instrument out-of-service time, thus effectively increasing system reliability and availability.
The criticality monitors have no function related to the safe shutdown of the plant or the capability to. mitigate the consequences of an accident.
Credit is not taken in the accident analysis for these monitors.
Extending the ACOT interval will not adversely affect the operation of the instruments and will reduce the potential for instrument damage and reduce the instrument out-of-service time, thus effectively increasing system reliability and availability.
This is consistent with Generic Letter 93-05, Section 5.14.
The staff finds the above changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State Official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment 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 (59 FR 53845). 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.
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, 6.0 CONCLVSION 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:
J. Stone Date:
November 28, 1994 1
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