ML20214T674

Environ Assessment & Finding of No Significant Impact Re Licensee 870304 Application for Amend to Tech Specs,Deleting Certain Valves from Table 3.7-4 That Lists Containment Isolation Valves Subj to Leak Rate Testing,Per 10CFR50

ML20214T674
Person / Time
Site:	Hatch
Issue date:	05/29/1987
From:	Youngblood B Office of Nuclear Reactor Regulation
To:
Shared Package
ML20214T643	List: ML20214T640 ML20214T674
References
TAC-64785, NUDOCS 8706100373
Download: ML20214T674 (4)

Text

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7590-01 U. S. NUCLEAR REGULATORY COMMISSION GEORGIA POWER COMPANY, ET. AL.

DOCKET NO. 50-321 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of an amendment to the Georgia ' Power Company, Oglethorpe Power Cor-poration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) for the Edwin I. Hatch Nuclear Plant, Unit 1, located in Appling County, Georgia.

Environmental Assessment Identification of Proposed Action: The amendment would revise the Tech-i nical Specifications for Hatch, Unit 1, to: (1)deletecertainvalvesfromthe i Table 3.7-4 that lists containment isolation valves subject to leak rate testing pursuant to the requirements of Appendix J to 10CFRPart50(i.e.,removethe 4

Technical Specification requirements for leak testing these valves), (2) correct erroneous infonnation in Table 3.7-4, and (3) change the pressure at which the main steam isolation valves are required to be leak tested.

These revisions to the Technical Specifications would be made in response to the licensee's application for amendment dated March 4, 1987, as revised April 21, 1987.

The Need for the Proposed Action: Paragraph III.C.2 of Appendix J to 10 CFR 50 requires that containment isolation valves be pressurized with air or nitrogen for leak testing purposes unless such valves are sealed with flui,d  !

from e seal system. Table 3.7-4 of the Technical Specifications for Hatch Unit I lists the valves that must be pressure tested for leakage. The valves i l

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that would be deleted from the table by this amendment are valves that would I

remain covered by water following a LOCA. These valves, thus, are sealed by f a fluid in a seal system and are not required to be pressure tested with air j or nitrogen and should not be listed in the Table 3.7-4. The amendment also would incorporate revisions to the table which correct erroneous nomenclature and valve / penetration relationships. The amendment also would correct the l test pressure for the MSIVs to specify a pressure of 28 psig instead of 1/2 i

Pa. The original staff evaluation (October 30,1986) used a test pressure

of 28 psig, but the tenn 1/2 Pa was erroneously entered in the Technical Specification.

Environmental Impacts of the Proposed Action:

A. Occupational Radiological Exposure Correction of the test pressure for the MSIVs and correction of the nomenclature and valve / penetration relationships would have no impact on 1

occupational exposure. Deletion of the valves required to be pressure I

tested would have a minor impact on occupational exposure by reducing the j number of valves needing testing. The change, if any, would be a decrease l

in occupational exposure.

, B. Radiological Impacts During Plant Operation and Accidents The amendments would have no impact on radiological release during normal plant operation or under accident conditions. The valves to be deleted from l  ;

the Table 3.7-4 do not constitute leakage pathways since they are sealed by water. The staff analysis for leakage through the MSIVs was originally per-i fonned (SER dated October 30,1986) at a test pressure of 28 psig. The a

amendment to the Technical Specification would merely correct an erroneous entry of 1/2 Pa to the 28 psig used in the staff analysis.

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l Non-Radiological Impacts C.

The proposed amendments involve systems located entirely within the re-stricted area as defined in 10 CFR Part 20. They do not affect non-radiological plant effluents and have no other environmental impact. Therefore, the ,

Commission concludes that there are no significant non-radiological environ-

. mental impacts associated with the proposed amendments.

Alternative to the Proposed Actions: Since we have concluded that no adverse environmental impacts are associated with the proposed action, any alternatives would have equal or greater environmental impact and need not  ;

be selected.

s The principal alternative would be to deny the amendments. This, in effect, would require continuation of unnecessary tests of those valves pro-posed to be deleted from Table 3.7-4, with an attendant increased exposure potential to plant workers. It would also perpetuate erroneous nomenclature and valve / penetration relationships in the Technical Specifications and a

, reference to an incorrect test pressure for the MSIVs.

' Alternative Use of Resources: This action does not involve the use of resources not previously considered in connection with the Nuclear Regulatory Commission's Final Environmental Statement dated October 1972 related to this facility.

Agencies and Persons Consulted: The NRC staff reviewed the licensee's requests of March 4,1987, and April 21, 1987, and did not consult other agencies or persons. I Finding of.No Significant Impact: The Commission has determined not to prepare an environmental impact statement for the proposed license amendment.

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. *e Based upon this environmental assessment, we conclude that the proposed ,

action will not have a significant adverse effect on the quality of the human environment.

For further details with respect to this action, see the request for amendments dated March 4,1987 as supplemented by request dated April 21, 1987, which are available for public inspection at the Consnission's Public Document Room, 1717 H Street, N. W., Washington, D. C., 20555 and at the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia 31513.

FOR THE NUCLEAR REGULATORY COMMISSION f

i B. Q. 'oungbl od, Direc or Profecp Directorate II-3 Divisihn of Reactor Projects-I/II Dated at Bethesda, Maryland, this 29th day of May 1987.

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