ML20247R719

Environ Assessment & Finding of No Significant Impact Re Mods to control-auxiliary-fuel Bldg Complex

ML20247R719
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/01/1989
From:	Rood H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247R697	List: ML20247R691 ML20247R719
References
NUDOCS 8906070296
Download: ML20247R719 (4)

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e 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S.' Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to facility Operating License No. NPF-1 issued to Portland General Electric Company, et al., (the licensee), for operation of' Trojan Nuclear Plant, located in Columbia County, Oregon. ,

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ENVIRONMENTAL ASSESSMENT j Identification of Proposed Action:

The proposed amendment is a request to amend the Trojan license by a Technical Specification (TS) change that will allow modifications to be made to the Control-Auxiliary-Fuel Building Complex which will result in up to a net three percent increase in lateral shear forces on any story.

The proposed action is in accordance with the licensee's application for amendment dated February 10, 1989.

The Need for the Proposed Action:

The proposed amendment would revise TS S.7.2.2.a to allow modifications I to the Control-Auxiliary-Fuel Building Complex (the Complex) which result in 1

up to a net 3 percent increase in lateral shear forces on any story. Trojan Technical Specification 5.7.2 currently provides restrictions on the design 1

provisions of the Complex. One of these restrictions, as stated in TS 5.7.2.2.a, 8906070296 890601 PDR P ADOCK 05000344 FDC

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.; is that no modifications which w11'1 result in a net 1 percent increase in~1ateral shear forces on any story of the Complex shall be performed without prior approval by the Nuclear Regulatory Commission.

In designing modifications to improve Control Building ventilation, the licensee determined that modifications would require up to a 3 percent. increase

-in lateral shear forces for walls in the Control Building. Therefore, a reevaluationofthestructurewasperformedusingthesame(STARDYNE) finite element computer code, but assuming a 3 percent increase in laterai shear 1 forces rather than the one percent originally assumed. For the reevaluation, all the weighp wsed in the original STARDYNE code were increased by 3 percent, and the effects of those weights on the shear wall capacity-to-force ratios, infrastructure displacements, and floor response specth were evaluated. The

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results of the reevaluation, based on an effective increase by 3 percent of all shear forces, indicate that all of the structural components remain well within their allowable stresses and their load capacities are greater than their load demands.

r t' Envircnnental.Incacts of the Proposed. Action:

In performing its evaluation, the staff determined that the increase in loading allowed by this amendment does not overstress any structural component.

All remain well within allowable stresses so that margins of safety with which the building was designed are not reduced. Since margins of safety designed into the building are not reduced, the proposed action would not involve a significant change in the probability or consequences of any accident pre-viously evaluated, nor does it involve a new or different kind of accident.

Consequently, any radiological releases resulting from an accident would not be significantly greater than previously determined. The proposed amendment l

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-> does not otherwise affect routine radiological plant eifluents. Therefore, the Commission concludes that there are no significant radiological environ-mental impacts associated with the proposed amendment. The Commission also concludes that the proposed action will not result in a significant increase in individual or cumulative occupational radiation exposure.

With regard to nonradiological impacts, the proposed amendment does not affect nonradiological plant effluents and has no other environmental impact.

Therefore, the Commission concludes that there are no significant nonradio- N logical environmental impacts associated with the proposed amendment.

The Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the Federal Register on May 4,'1989 (54 FR 19270). No request for hearing #or petition for leave to intervene was filed following this notice.

Alter'atives n to.the. Proposed Actiont Because the Commission has concluded that there are no significant environmental impacts associated with the proposed action, there is no need to examine alternatives to the proposed action.

Alternative Use.of Resources:

This action does not involve the use of resources not previously considered in connection with the Final Environmental Statement related to operation of Trojan Nuclear Plant, dated August 1973.

Agencies and Persons Consulted:

The NRC staff has reviewed the licensee's request that supports the proposed amendment. The NRC staff did not consult other agencies or persons.

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

Based upon the foregoing environmental assessment, the Commi'ssion concludes the proposed action will have no significant adverse effect on the quality of the human environment.

For further details with respect to this action, see the application for amendment dated February 10, 1989, which is available for public inspection at '

the Commission's"Public Document Room, 2120 L Street NW., Washington, DC 205ji5, and at Jhe Portland State University Library, 731 S.W. Harrison Street, Portland, Oregon 97207.

Dated at Rockville, Maryland, this 1st day of June, 1989' FOR THE NUCLEAR REGULATORY COMMISSION f I TQ\

Harry Rood, Acting Director

, Project Directorate V Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation i

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