ML20071G432

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Safety Evaluation Supporting Amends 121 & 115 to Licenses NPF-35 & NPF-52,respectively
ML20071G432
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 07/05/1994
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20071G428 List:
References
GL-93-05, GL-93-5, NUDOCS 9407120256
Download: ML20071G432 (2)


Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON. D C. 20$$H001 SAFETY EVALVATION BY THE OFF MC.E NUCLEAR REACTOR RE0yLATION 4

RELATED TO AMENDMENT NO.12' TO FACIL t OPERATING LICENSE NPF-35 t

AND AMENDMENT NO. 115 1 FACILITY ERATING LICENSE NPF-52 DUKE P0k r(J,QMt

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CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 1.0 JNTRODljCJ10N Py htter dated March 30, 1994 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 would revise TS Table 4.3-3 to allow the analog channel operational test interval for radiation munim um instrumentation to be increased from monthly to quarterly.

The am ndments are consistent with the guidance in Generic letter 93-05, "Line-Iten Technical Specifications Improvements to Reduce Surveillance Requirements for inting During Power Operation."

2.0 LVAtVATION irn, ic o,a e hn proposed to change the analog channel operational test inverval for the radiation monitoring instrumentation in TS Table 4.3-3 from monthly (M) to quarterly (0).

The NRC staff evaluated this issue as discussed in Section 5.14 of NUREG-1366, " Improvements to Technical Specification Surveillance Requirements" dated December 1992.

The following discussion is based on the NUREG report and on the Generic Letter 93-05 that identified potential changes that licensees could propose to facility TS.

As with other instrumentation, radiation monitors are required to undergo three types of surveillances: a channel check, a channel functional test, and a calibration.

In addition, a source check, which provides an integral

. verification of the response of the detector, is performed.- The NRC staff found that radiation monitor testing appears to require a large amount of.-

resources and that most-failures of radiation monitors can be found from channel checks, source checks, or alarms.

The channel _ functional tests do not involve the sensor-(radiation monitor) itself.

The revised testing frequency would decrease the licensee-burden and_ increase the availability of the radiation monitoring systems. Accordingly, the staff concluded that the frequency of the thannel functional test could be changed to quarterly, subject to licensee verification that the change would be compatible with-plant operating experience.

The licensee for the Catawba plant stated that the subject changes would be -

compatible _with_ observed plant operating experience as it pertains to the tolerance history of the radiation monitors. The licensee has reviewed two 2

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. l hundred analog channel test procedure results for the Catawba monitors that are subject to the revised TS. The licensee found that, with eight exceptions, the radiation monitor trip setpoints were within tolerance and no problems with the channels were identified.

The eight exception cases did not suggest an adverse performance history for any particular monitor, involved 1

only a slight out-of-tolerance condition, and were not indicative of monitor failure. The NRC staff finds that the licensee has established that the proposed change is consistent with Catawba operating experience and is, therefore, acceptable, i

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 comments.

4.0 ENVIRONNENTAL CONSIDERATION The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.

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 may be released of fsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a i

proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 27054 dated May 25, 1994).

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 env'ronmental assessment need be prepared in connection with the issuance of the amendments.

50 CONCLUSION The Commission has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that-the health and safety of the pubiic will not be endangered by operation in the proposed manner,-(2) such ac.ivities will be conducted in compliance with the Commission's regulations, a ad (3) the issuance of the amendments will not be inimical to the common Jefense and security or to the health and safety of the public.

Principal Contributors:

R. Martin T. Dunning Date: July 5, 1994 m

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