ML20206B239

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Safety Evaluation Supporting Amend 106 to License DPR-40
ML20206B239
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/26/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206B224 List:
References
TAC-64445, NUDOCS 8704090036
Download: ML20206B239 (2)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.1ne; TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT' .

FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 i

INTRODUCTION:

By letter dated January 71986, [ Sic](1987), Omaha Public Power District (the licensee) requested a change to Fort Calhoun Station, Unit No. 1, Tech-i nical Specifications (TS) Section 3.12.1(2)d regarding surveillance require-j j ments for the hydrogen and oxygen monitoring system for the waste gas decay i j tanks. The proposed revision would clarify the requirement that the hydro-i gen and oxygen monitors on the waste gas decay system receive a daily chan-nel check when in service. The licensee stated that the change will assure agreement with the requirements of TS 2.9.1(2)d which specifies these in-

! struments shall monitor the inservice gas decay tank during the transfer of i

waste gases to the gas decay tank. The TS defines, in part, a channel

! check as "a qualitative detemination of acceptable operability by observa-l tion of channel behavior during nomal plant operation." i i EVALUATION NUREG-0472, " Standard Radiological Effluent Technical Specifications for

Pressurized Water Reactors," provides for daily channel checks for the hy-j drogen and oxygen monitors in the waste gas holdup system during system operation. NUREG-0472 also provides, in part, that a channel check shall be l the qualitative assessment of channel behavior during operation by obser-

{ vation. Based on the above, the proposed revision meets the intent of j NUREG-0472 and is, therefore, acceeptable.

ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of facility component located within the restricted area as defined in 10 CFR Part 20

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or a change in a surveillance requirement. The staff has determined that

, the amendment involves no significant increase in the amounts, and no signi-i ficant change in the types, of any effluents that may be released offsite, 4 and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the

! eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).

Pursuant to 10 CFR 551.22(B), no environmental impact statement or environmental

assessment need be prepared in connection with the issuance of the amendment, t

8704090036 870326 PDR ADOCK 05000285

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CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of public.

Date: March 26, 1987 Principal Contributor: C. Nichols l

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