ML20127N750

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Safety Evaluation Supporting Amends 105 & 99 to Licenses NPF-35 & NPF-52,respectively
ML20127N750
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 01/12/1993
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127N747 List:
References
NUDOCS 9302010058
Download: ML20127N750 (2)


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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.105TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT N0. 99 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMPANY. ET AL.

CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 1.0 INTROD_VCTION By letter dated July 27, 1992, the Duke Power Company, et al. (the licensee),

submitted a request for changes to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS).

The requested changes revise the minimum channels operable requirement of TS Table 3.3-10, Item 17, Steam Relief Valve Exhaust Radiation Monitors, from one to one per each of the four steam lines.

4 2.0 EVALUATION t

As noted in the application, an area radiation monitor is located adjacent to each of the four main steam lines (MSL) upstream of the main steam isolation valves, to detect secondary radiation releases.

The previously existing TS required that a minimum of one channel of these monitors must be operable.

The licensee has previously relied on the steam generator water sample monitor l

(EMF-34) as a backup for the MSL monitors. However, due to continuous operability problems cited by the licensee with EMF-34, its design basis is being changed.

This also results in removal of the backup function provided by EMF-34 to the MSL monitors.

In response, the licensee proposes to change the TS such that all four MSL monitors are subject to the minimum operable channels requirement. This change is (1) more conservative than the previous TS requirement, (2) consistent with the licensee's commitment made in response to Regulatory Guide 1.97 in Table 1-11 of the Final Safety Analysis Report, and (3) consistent with the standard technical specifications for Westinghouse reactors.

Based on the above, the staff finds the change from requiring one MSL monitor to be operable to requiring one for each of the four steam lines to be operable is acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no concents.

9302010058 930112 DR ADOCK 0500 3

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4.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to installation or use of a.

facility component located within the restrictea area as defined in 10 CFP.

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 mcy 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 no public comment on such finding (57 FR 58245, dated December 9, 1992).

Accordingly, the amendments meet 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 r.eed be prepared in connection with the issuance of the amendments.

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 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:

Robert E. Martin Dato: January 12, 1993 1

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