ML20057A863
| ML20057A863 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/09/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A861 | List: |
| References | |
| NUDOCS 9309160090 | |
| Download: ML20057A863 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION g sg je WASHINGT ON. D.C. 2055 % 4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-3 TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. I DOCKET NO. 50-346 1.0 INTRODUC110N By letter dated May 1,1992, Toledo Edison Company requested a revision to the, 2
Technical Specifications for the Davis-Besse Nuclear Power Station. The proposed amendment would revise Technical Specification (TS) 3/4.4.6.2,
" Reactor Coolant System-Operational Leakage," and its Bases. The changes would clarify the applicability of TS 4.0.4 exceptions, specify the allowed usage of the containment atmosphere gaseous radioactivity monitoring system as an alterrate method of determining the presence of reactor coolant system (RCS) leakage, and clarify other existing wording. The proposed revisions to the Bases clarify that leakage from the RCS pressure isolation valves is
" identified leakage" under TS 3/4.4.6.2 and is considered a portion of the allowed limit.
2.0 EVALUATION The reactor coolant leakage detection system includes the containment atmosphere particulate radioactivity monitoring system, the containment gaseous radioactivity monitoring system, and the containment sump level and i
flow monitoring system.
The containment atmosphere particulate and gaseous radioactivity monitoring systems incorporate monitors which are seismic, redundant, and supplied with essential power.
Both were designed to detect an increase in RCS pressure boundary leakage of one gallon per minute in less than one hour, and are capable of monitoring the containment atmosphere under normal and accident conditions. The RCS is tested for leakage by surveillance tests which monitor the containment atmosphere gaseous and particulate radioactivity, monitor the containment sump level, measure and record the controlled leakage from the reactor coolant pump seals, and perform the RCS water inventory balance. The water inventory balance determines the amount of RCS leakage and provides guidance for the type, location and classification of 9309160090 93o909 O
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The containment vessel normal sump level alarms on the plant computer, and the annunciator and level indicator are located in the control room.
TS 4.0.4 states that entry into an operational mode or other specified i
applicability condition shall not be made unless the associated Surveillance Requirements (SRs) have been performed within the stated surveillance interval or as otherwise specified. An exception to TS 4.0.4 for the purpose of testing the RCS pressure isolation valves in Modes 3 and 4 is currently written in Action statement "d" of TS 3.4.6.2.
The proposed change relocates l
the exception to TS 4.0.4 to the text of SR 4.4.6.2.2.
The NRC staff finds l
this relocation in the TS to be acceptable.
j Another proposed change adds the containment gaseous radioactivity monitoring system as an alternate method of detecting RCS leakage in containment. As.
stated above, the design of the gaseous monitor is commensurate with the particulate monitor. Therefore, the NRC staff finds the proposed change to be acceptable.
Rewording of TS 4.4.6.2.3 for clarity and editorial changes for clarity are also proposed by the licensee.
The NRC staff has reviewed these proposed changes and finds them to be acceptable.
Finally, the licensee proposes adding a paragraph to the TS Bases discussing
- the purpose of the SRs for the RCS pressure isolation valves.
The NRC staff has reviewed the proposed paragraph and finds it to be acceptable.
i The NRC staff has reviewed the proposed amendment.
Based on the above, the NRC staff finds the changes to be acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official had no-comments.
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4.0 ENVIRONMENTAL CONSIDERATION
This 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 or changes a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, and no signif-icant change in the types, of any effluents that may be released offsite, and that there_is no si radiation exposure.gnificant increase in individual or cumulative occupational 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-(57 FR 40222).
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
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I statement or environmental assessment need be prepared in connection with the j
issuance of the amendment.
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5.0 CONCLUSION
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The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health-and safety of the public i
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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
a Principal Contributor:
J. Hopkins Date: September 9, 1993 1
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