ML20085F326
| ML20085F326 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/10/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085F316 | List: |
| References | |
| NUDOCS 9110220121 | |
| Download: ML20085F326 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
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RELATED TO AMENDMENT NO.147 TO FACILITY OPERATING LICENSE NO. OPR-46 NEBRASKA PUBLIC POWiR DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
- 1. 0 INTRODUCTION By letter dated July 18, 1991, Nebraska Public Power District (the licensee) submitted a request for changes to the Cooper Nuclear Station, Technical Specifications (TS).
The requested changes would reflect a planned change 1.1 the Reactor Building Isolation and Standby Gas Treatment Initiation radiation mor.itor logic f rom one-out-of-two to one-out-of-two'taken-twice, clarity operability requirements for the radiation monitors, and correct several typographical / editorial deficiencies.
2.0 EVALUATION The Reactor Building Isolation Ventilation Radiation Monitoring System contains 1
two radiation monitoring channels that initiate Reactor Building isolation and Standby Gas Treatment System actuation upon detection of high radiation.
The two channels, each with a single radiation monitor, comprise a one-out-of-two trip logic.
The licensee plans to change the design to a one-out of-two-taken-twice trip logic by the addition of two radiation monitors and associated circuitry.
The intent of the change is to reduce the potential for spurious trips, and thereby reduce unnecessary hallenges to the Reactor Building Isola-tion and Standby Gas Treatment systems.
The change will also eliminate the need for installing jumpers during surveillance testing which reduces the potential for spurious actuations and compromising the logic by the inadvertent failure to remove the jumpers following a surveillance test.
The logic design is consistent with the objectives set forth in IEEE 279-1971 for protection systems and is utilized in other safety systems such as the Reactor Protection System ar.d has been proven to provide an acceptable combination of reliability id operability.
In light of the reasons stated above, the staff finds the proposed change to the Reactor Building Isolation Ventilation Radiation Monitoring systein to be acceptable.
The licensee also propotes to change the operability requirements for the Reactor. Building Isolation Ventilation Radiation Monitoring System, Secondary Containment, and Standby Gas Treatment System to include activities, in addition to fuel handlin9, which introduce a potential to damage irradiatcd fuel.
The addition of activities involving the movement of loads which have the potential to damage irradiated fuel to the operability requirements ensures that those systerns required to mitigate the analyzed fuel handling accident are also available during other conditions in which damage to irradiated fuel might occur.
The expansion of the operability requirements is similar to the Standard ADOCM 0500029G, g@j 711010 9110220121 PDR FDR gg
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2 Technical Specifications (NUREG-0123, Rev. 2) which include spent fuci shipping cask handling in addition to fuel handling. The licensee's propon1 ensures that mitigative systems are available during those activities which introduce the potential for damage to irradiated fuel and provides an 6provement over the existing TS which addressed only fuel handling activities. The staff therefore finds the proposed changes to be acceptable.
In addition to the above changes, the licensee propo',cd several editorial changes to several TS pages.
These changer. includad a correction to TS 3.2.D.2, Reactor Buildirg isolation and Standby Gas Treabient initiation Radiation Monitors, which references TS 3.21. A.2 althou@ these monitors are not addressed by Table 3.21. A.2 (operability requirements defined by Table 3.2.0).
A note was added to Table 4.21.A.2 which defines tne surveillance requirements for these monitors in order to reference TS ?.2.D 2 for the applicable limiting conditions of operation. The remaining proposed changes invnive minor changes to clarify units of mersure or correct component designations. Open review of the proposed corrections and clarifications, the staff determined that the changes were acceptable.
3.0 'iTATE CONSULTATION i
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comment.
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 in surveillance requirements. The NRC staff has detennined 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 issutd a pro.
posed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (56 FR 43809).
Acco 'ingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 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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5.0 CONCLUSION
L The Commission has concluded, b:. sed on the consideratinns discussed above, l
that: (1) there is reasonable assurance that the healtn and safety of the public will not be endangered by operation in the proposed manner, (2) such l
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, 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:
W. Reckley Date: October 10, 1991 l
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