ML20137D814

Notice of Environ Assessment & Finding of No Significant Impact Re Util 830126 Request for Exemptions from Section III of 10CFR50,App J

ML20137D814
Person / Time
Site:	Fort Calhoun
Issue date:	08/01/1985
From:	Lainas G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137D819	List: ML20137D814
References
TAC-8910, NUDOCS 8508230049
Download: ML20137D814 (4)

Text

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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION OMAHA PUBLIC POWER DISTRICT ,

DOCKET NO. 50-285 NOTICE OF ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commissien) is e,nsiderint, issuance of exemptions from the requirements of Appendix J to 10 CFR Part 50 to the Omaha Public Power District (the licensee), for the Fort Calhoun Station, Unit No.1, located in Washington County, Nebraska.

ENVIRONMENTAL ASSESSMENT Identification of Proposed Action: The requested exemptions are related to

.. Section III of Appendix J to 10 CFR Part 50.Section III contains containment leakage testing requirements. Specifically, the licensee has requested an exemption from paragraph III.D.2(b)(ii) which states " Air locks opened during periods when containment integrity is not required by the plant's Technical Specifications shall be tested at the end of such periods at not less than Pa." The licensee has also requested an exemption in regard

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to performing Type C leakage testing on the isolation valves associated with the Charging Pump Discharge Line (penetration M-3).

These proposed exemptions are responsive to the licensee's letter requesting exemptions dated January 26, 1983.

The Need for the Proposed Action: The existing Personnel Air Lcck (PAL) doors are so designed that a full pressure test can only be performed after strong backs (structural bracing) have been installed on the inner door.

0000230049 850801 PDR ADOCK 05000285 P PDR

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Strong backs are needed since the pressure exerted on the inner door during the test is in a direction opposite to that of the accident pressure direction. The strong backs are extremely difficult to install and the outer door must be opened to remove the strong backs. As a result, about 18-24 hours are required to complete a full pressure test of an air lock.

Alternately, the licensee proposes to leak test the door seals at 5 psig prior to returning to a plant operating condition requiring containment integrity, and conduct a full pressure test on the PAL assembly within 2 weeks. The licensee contends that this proposal will provide adequate assurance of air lock integrity without imposing undue delays on return to power operations.

The containment isolation valves associated with penetration M-3 are part of the charging pump discharge line. The licensee believes that i testing is unnecessary because the pressure of the fluid in the line will always be greater than the containment pressure, thereby providing a seal barrier against escape of the containment atmosphere.

Environmental Impacts of the Proposed Action: Our evaluation of the proposed exemptions from Appendix J to 10 CFR Part 50 indicates that the granting of the exemptions will not impair containment integrity for the following reasons. Iftheperiodic6-monthtestofparagraphIII.D.2(b)(1)of Appendix J and the test required by paragraph III.D.2(b)(iii) of Appendix J are current, there should be no reason to expect an air lock to leak excessively just because it has been opened during cold shutdown or refueling. Regarding the charging pump discharge line, the pressure of the fluid in the line will always be greater than the containment pressure, thereby providing a seal barrier against escape of the containment atmosphere.

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's Accordingly, post-accident radiological releases will not be greater than previously determined nor does the proposed exemption otherwise affect radiological plant effluents and there is no significant increase in occupational exposures. Therefore, the Commission concludes that there are no significant radiological environmental impacts associated with the proposed exemptions.

With regard to potential non-radiological impacts, the proposed exemptions involve features located entirely within the restricted area as defined in 10 CFR Part 20. They do not affect non-radiological plant effluents and have no other envirormental impact. Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated with the proposed exemptions.

Alternative Use of Resources: This action involves no use of resources not previously considered in the Final Environmental Statement (construction permit and operating license) for the Fort Calhoun Station, Unit No.1.

Agencies and Persons Consulted: The NRC staff reviewed the licensee's request and did not consult other agencies or persons.

FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed exemptions.

Based upon the foregoing environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.

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, I For further details with respect to this action, see the letter requesting the exemptions dated January 26, 1983, which is available for i

public inspection at the Comission's Public Document Room,1717 H Street, N.W.,

Washington, D. C., 20555 and at the W. Dale Clark Library, 215 South 15th Street, Omaha, Nebraska 68102.

Dated at Bethesda, Maryland this 1st day of August,1985.

FOR THE NUCLEAR REGULATORY COMMISSION 1

Gus C. Lainas, Assistant Director for Operating Reactors Division of Licensing

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