ML19267A302

Notice of Issuance of Amend 35 License NPF-1

ML19267A302
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/22/1978
From:	Trammell C Office of Nuclear Reactor Regulation
To:
Shared Package
ML19263A932	List: ML19267A290 ML19267A296 ML19267A302
References
TAC-07551, TAC-08348, TAC-7551, TAC-8348, NUDOCS 7901040019
Download: ML19267A302 (5)

Text

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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-344 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nucle. - Regulatory Commission (the Commission) has, pursuant to the Partial Initial Decision of its Atomic Safety and Licensing Board (ASLB) dated December 21, 1978, issued Amendment No. 35 to Facility Operating License No. NPF-1, issued to Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee), which revised the license and appended Technical Specifications for operation of the Trojan Nuclear Plant (the facility), located in Columbia County, Oregon.

The amendment is effective as of its date of issuance.

The amendment consists of the addition of operating restrictions to the license and a waiver of those portions of Appendix A Technical Specification 5 7.1 and the Final Safety Analysis Report criteria referenced thet ain which describe the seismic capacity of the Trojan Control Building and which are not complied with because of design deficiencies in the Control Building shear walls originally identified in the licensee's letter dated May 5,1978. The operating 79010400/t

7590-01 restrictions to the license prohibit modifications which may reduce the strength of the Control Building shear walls unless approved by the NRC, and require that in the event of an earthquake having greater than 0.08g peak ground acceleration the facility be brought to cold shutdown and inspected for any effects of the earthquake. Finally, the snendment requires that the on-going seismic qualification program with respect to certain piping systems be completed prior to resumption of reactor operation. The operation of Trojan will be subject to further Order of the Atomic Safety and Licensing Board with respect to the scope and timeliness of structural modifications to the Control Building.

The Partial Initial Decision is subject to rcy."

hy an Atomic Safety and Licensing Appeal Board prior to its becoming final. Any decision or action taken by an Atomic Safety and Licensing Appeal Board in connection with the Initial Decision may be reviewed by the Commission.

The amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.

7590-01 On May 26, 1978, the NRC's Director of Nuclear Reactor Regulation

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issued an Order for Modification of License that set forth findings that design errors in the Control Buf1 ding shear walls had reduced the seismic capability of the Control Building; that the originally intended seismic capability should be substantially restored by modifications to that structure; and that operation of the facility with the Control Building in its as-built condition would violate the existing facility license. Based on the related safety evaluation by the NRC staff, however, the Order stated that the Control Building nevertheless had adequate structural capacity to resist the ifcensed Safe Shutdown Earthquake and that the facility operating ifcense should be modified to permit operation, with conditions, in the interim period prior to approval and completion of modifications required by the Order.

The Order also provided opportunity for hearing and was published in the Federal Register on June 1, 1978 (43 F.R. 23768). Requests for hearing were to be filed by June 26, 1978, and, in the event that a hearing was ordered, the terms of the Order would not become effective until a hearing was held.

Numerous requests for a hearing were received. The requests filed by: Columbia Environmental Council; Eugene Rosolf e, acting on his own behalf and as representative of the Coalition for Safe Power; Stephen M. Willingham; David B. McCoy; C. Gail Parson;

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Nina Bell; and the Bonneville Power Administration were granted.

In addition, the State of Oregon was granted leave to participcte as an interested State.

The hearing was held October 23 through November 3, and December 11-14, 1978, in Salem and Portland, Oregon. The above-referenced Partial Initial Decision was subsequently issued on December 21, 1978.

The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.

For further details with respect to this action, see (1) letters from the licensee dated May 5, 24, arid 26; June 30; August 19, and 21; September 1,12 and 20; October 4, 6. 10, 13, 17, and 27; November 2, 22 and 24,1978; (2) Amendment No. 35 to License No.

NPF-1; (3) Order for Modification of License dated May 26, 1978 and related Safety Evaluation; and (4) the Partial Initial Decision of the Atomic Safety and Licensing Board dated December 21, 1978.

7590-01 All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D. C.

20555, and at the Columbia County Courthouse, Law Library, Circuit Court Room, St. Helens, Oregon 97051. A single copy of items (2), (3) and (4) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: Director, Division of Operating Reactors.

Dated at Bethesda, Maryland, this 22nd day of December,1978.

FOR THE NUCLEAR REGULATORY COMMISSION A4 Charles M. Trammell, Acting Chief Operating Reactors Branch #1 Division of Operating Reactors

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