ML20106B091
| ML20106B091 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/22/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106B089 | List: |
| References | |
| NUDOCS 9209300301 | |
| Download: ML20106B091 (2) | |
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SAFETY EVALU/1110N BY THE OfflCE Of fMLEAR REACTOR REGUL ATION HLLATED TO AMENDEENT NO 154 T0 TACILITY OPERATIMi_LLEGIUiO. DPR-il (MILASKA PVBllC POWER DISTRICT LOOPER NUCLEAR STATION DOCKET NO. 50-298 1.O l!{lRQM11M By letter dated Ane 16, 1988, Nebraska Public Power District (NPPD, the licensee) requestea license amendment Proposed Change (PC) No. 57 to.
incorporate Cooper Nuclear Station Technical Specification (TS) changes regarding the newly installed redundant H /0 monitoring systems in 2 3 containment.
The proposed change incorporated requirements for the redundant oxygen analysis monitor of the redundant oxygen and hydrogen analysis systems.
By letter dated October 7, 1991, the licensee submitted PC No. 76, which proposed a change to the technical specifications that would add limiting conditions for operation and surveillance requirements for the containment post-accident hydrogen concentration analysis systems.
By letter dated August 12, 1992, the NRC issued Amendment No. 153 in response to PC No. 57, technical specifications for the containment atmosphere analyzer systems.
This safety evaluation addresses PC No. 76, technical specifications for limiting conditions for operation (LCOs) and surveillance requirements (SRs) for hydrogen monitoring instrumentation in the post-accident containment atmosphere.
2.0 EVALUATION The licensee proposed changes to Tables 3.2.H and 4.2.H to include requirements for redundant primary containment hydrogen analyzers. A new entry in Table 3.2.H, Post-Accident Monitorino Instrumentation Reauirements.
designates the minimum number of operable channels for each hydrogen concentration analyzer.
The required actions when the number of operational channels is less than the required number is specified in the proposed amendment following the guidance of Generic Letter (GL) 83-36.
The installation of the hydrogen concentration analyzers had already been received and accepted by the NRC staf f (letter from D. Vassallo, NRC, to L. Kuncl, NPPD, dated August 5, 1983); however, there were no TS requirements for operation of the instruments.
However, consistency with the guidance provided in NRC GL 83-36 requires that containment for all Boiling Water Reactors (BWRs) should have both hydrogen and oxygen monitoring instrumentation with appropriato LCOs and SRs. Accordingly, such specified conditions are proposed.
The staff has evaluated the proposed new TS and 9209300301 920922 PDR ADOCK 05000298 P
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finds them to be appropriate and acceptable, in addition, a note has been added to Table 3.2.H to specify that one of two operable hydrogen concentration analyzers is normally in a standby mode of operation. This condition is appropriate to reduce equipment wear and to prolong the service life of the analyzer. The staff has previously approved a similar provision at another BWR-4 installation in a comparable condition, and finds it appropriate and acceptable in this case also.
The operability of the standby analyzer will be verified by performing the calibration and test requirements as described in Table 4.2.H. Post-Accident Monitorina In}trumentation houf tement s.
The licensee proposed to incorporate into Table 4.2.H requirements for calibration and testing of the hydrogen analyzers. These requirements as proposed have been evaluated and found to be appropriate and acceptable.
Another proposed chance to Table 4.2.H not related to hydrogen monitoring instrumentation is the ' listing of an additional channel of primary containment gross radiation monitoring instrumentation.
This change is likewise appropriate and is acceptabl,.
3.0 STATF CONSULTATION In accordance with the Comission'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 determined that the amendment involves no significant inciease 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 Lommission has previously issued a pro-posed finding that the amendment involves no significant hazards consideration-and there has been no public comment on such finding (57 FR 24673).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section Sl.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.
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 ne 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:
R. Bevan i
Date: September 22, 1992
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