ML19267A296

Amend 35 to License NPF-1.Modifies Waiver Portions of Tech Specs & FSAR Criteria Which Have Not Been Followed Due to Design Deficiency in Control Bldg Shear Walls

ML19267A296
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/22/1978
From:	Stello V Office of Nuclear Reactor Regulation
To:
Shared Package
ML19263A932	List: ML19267A290 ML19267A296 ML19267A302
References
TAC-07551, TAC-08348, TAC-7551, TAC-8348, NUDOCS 7901040010
Download: ML19267A296 (3)

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-1 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

Interim operation of the Trojan Nuclear Plant should be pemitted in accordance with the amendment to the Operating License set forth below and subject to the terms and conditions therein; B.

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 set forth in 10 CFR Chapter I; C.

The facility will operate in conformity with the amendment, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance that the activities authorized by the operating license, as thus amended, and including the tems and conditions set forth below (1) can be conducted v.th-out endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; E.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and F.

The issuance of this amendment is not a major federal action significantly affecting the quality of the human environment and does not require the preparation of an environmental impact statement under the National Environmental Policy Act of 1969, as amended, 42 U.S.C.

4321, et seo., and Part 51 of the Commission's regulations,10 CFR Part 51, or the preparation of an environmental impact appraisal and negative declaration under Part 51 of the Commission's regulations.

01040010.

. 2.

Accordingly, the license is amended by changes to paragraph 2.C.(2) and the addition of new paragraph 2.C.(10) of Facility Operating License No. NPF-1. These paragraphs now read as follows:

"2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 34, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in paragraph 2.C.(10) below.

"2.C.(10) Control Building (a) Upon the effective date of this amendment (Amendment No. 35), and until further Order of the Atomic Safety and Licensing Board issued in conjunction with the decision on the scope and timeliness of modifications from a safety standpoint required by the Order for Modification of License dated May 26, 1978, Facility Operating License No. NPF-1 is modified by waiver of those portions of Technical Specification 5.7.1 and the FSAR criteria referenced therein which are not complied with because of the identified design deficiencies in the Control Building shear walls, including:

(1) the requirement that the Control Building meet an OBE capacity of 0.15g using 2%

damping as required by FSAR Table 3.7.1; (ii) the requirement that the Control Building meet an OBE capability of 0.15g and an SSE capability of 0.25g using a yield strength for reinforcing steel of 40,000 psi in accordance with ASTM ninimum values as required by FSAR Section 3.8.1.3.3; and (iii) the requirement that the masonry portions of the Control Buf1 ding walls meet Uniform Building Code requirements for reinforced grouted masonry as specified in FSAR Section 3.8.1.4.

. (b) During the term of this amendment, the facility shall be operated in accordance with the following conditions: -

(i) no modification which may reduce the strength of the existing shear wa'Is shall be made without prior NRC approval; and (ii) in the event that an earthquake occurs that exceeds the facility criteria for a 0.08g peak ground acceleration at the plant site, the facility shall be brought to a cold shutdown condition and be inspected to determire the effects, if any, of the earthquake. Operation cannot resume under these circumstances without prior NRC approval.

(c) Operation of the Trojan facility pursuant to this amendment may commence only after completion of such additions and modifications of pipe supports and pipe restraints as are necessary to assure that piping systems within the Control, Auxiliary and Fuel Building complex required for safe shutdown and to maintain off-site doses from accidents to within the guide-lines of 10 CFR Part 100 are qualified to withstand earthquakes up to and including the 0.25g SSE.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Victor Stello, Jr., Director Division of Operating Reactors Date of Issuance: December 22, 1978

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