ML20204G750

Amend 119 to License NPF-1,deleting Tech Spec 3.4.10.1.d Re Evaluation to Determine Consequences of Continued Operation W/Reduced Structural Integrity of ASME Code Class 1,2 & 3 Components

ML20204G750
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/28/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204G739	List: ML20204G735 ML20204G750 ML20204G766
References
NUDOCS 8608070380
Download: ML20204G750 (4)

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET N0. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. NPF-1

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The application for amendment by Portland General Electric Company,

- et al., (the licensee) dated April 7, 1986 complies with the standards aiid 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; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; ,

C. Thereisreasonablea\surance(i)thattheactivitiesauthorized by this amendment can.be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. 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 E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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g 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

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

F R THE NUC ULATORY COMISSION L)Dir:w rga, tor PWR Project Directo a te No. 3 Division of PWR Licensing-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance: July 28, 1986 s

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ATTACHMENT TO LICENSE AMENDMENT N0.119 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-344 Revise Appendix A as follows:

Remove Page Insert Page 3/4 4-29 3/4 4-29

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J REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1. 2. and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 com-ponents shall be maintained in accordance with Specification 4.4.10.1.

APPLICABILITY: ALL MODES ACTION:

a. With the structural integrity of any ASME Code Class 1 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate t.he affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

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. b. With the structural integrity of any ASME Code Class 2 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.

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c. With the structural integrity of any ASME Code Class 3 com-ponent(s) not conf.orming to the above requirements, restore the structural intygrity of the affected component (s) to within its limit of isolate the affected component (s) from service.

d. The provisions of Specification 3.0.4 are not applicable.

LIMITING CONDITION FOR OPERATION 4.4.10.1 ASME Code Class 1, 2, and 3 components shall be inspected in accordance with the requirements of Specification 4.0.5. In addition, each reactor coolant pump flywheel shall be inspected per the recommenda-tions of Regulatory Position C.4.b of Regulatory Guide 1.14 Revision 1 August 1975.

TROJAN-UNIT 1 3/4 4-29 Amenoment 40. $7 119