ML20148S642

Amend 140 to License NPF-1,revising Offsite & Facility Organization Charts for Tech Specs

ML20148S642
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/11/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148S635	List: ML20148S642 ML20148S649
References
NUDOCS 8804190142
Download: ML20148S642 (6)

Text

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1. fog UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION

r. .j wAssinatow. o. c. rosss

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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. 140 License No. NPF-1

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

A. The application for amendment by Portland General Electric Company, et al. 15, 1988, as revised TebWar,y(the 15, 1988, licensee) complies dated January with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in cenformity with the application, the provisions of the Act, anc the regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safet/ of tha 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 comon defense and security or to the health and safety of the public; and E. The issuance of this emendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements nave been satisfied.

8804190142 000411 DR ADOCK OSO 4

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2. Accordingly, the license is ainanded 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.140, 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.

FOR THE NUCLEAR REG LATORY COMMISSION

'f4/ wi V George W. Knighton// Director Project Directorate V Division of Reactor Projects - !!!,

IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: April 11, 1988 6

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April 11, 1988 j t

i ATTACHMENT TO LICENSE AMENDHENT NO.140' TO FACILIYY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344 l,

Revise Appendix A as follows:  ;

Remove Pages Insert Pages .

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. 4/_11/88

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, ADMINISTRATIVE CONTROLS ,

COMPOSITION 6.5.;.2 The Plant Review Board shall be composed of the:

Chairman: Manager, Technical Services Member: System EngineeMng Branch Manager Member: Maintenance Branch Manager Member: Operations Branch Mar,ager Member: Quality Assurance Operations Branch Manager Member: Radiation Protection Branch Manager ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to :;erve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any

) one time.

MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

OUORUM 6.5.1.5 A quorum of the PRB shall consist of tl.6 Chairman or his

, designated alternate and at least four members including alternates.

ESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:

a. Review of the safety evaluations for: (1) procedures, (2) change to procedures, equipment, systems or facilities, and (3) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.

b. Review of proposed precedures and changes to procedures,

equipment, systems or facilities which may involve an unreviewed safety question as defined in 10 CFR 50.59 or involver a change in Technical Specifications.

, c. Review of proposed ta-t or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59 cr requires a change in Technical Specifications.

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, d. Reviev of proposed changes to Technical Specifications or the Operating License. .

TROJAN-UNIT 1 6-6 Arr.endment No. #2, 728, 735,140 4/11/88

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