ML20141P101

Amend 111 to License NPF-1,changing Tech Spec Section 4.9.9 to Clarify Surveillance Requirements for Containment Ventilation Sys by Specifying Which Monitoring Channels Included in Sys Operability Tests

ML20141P101
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/04/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141P100	List: ML20141P099 ML20141P101 ML20141P247
References
NUDOCS 8603180566
Download: ML20141P101 (4)

Text

'o, UNITED STATES 8" ' 7. NUCLEAR REGULATORY COMMISSION l; E WASHINGTON, D. C. 20665

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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.lll 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., (the licensee) dated October 11, 1985, complies with the staiidards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C. There is reasonable assurance (i) that the activities authorized 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 issuarce 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 Comission's regulations and all applicable requirements have been satisfied. )

l 8603180566 860314 PDR ADOCK 05000344 P PDR

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.111 , 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 NUC EAR REGULATORY COMMISSION

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Stev n W. ar a, Director 1-ufPWR Pro.iect Directorate No. 3 b Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuence: March 4, 1986 i

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4 ATTACHMENT TO LICENSE AMENDMENT NO.lli ,

TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 i

Revise Appendix A as follows:

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. LCA 131

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, REFUELING OPERATIONS CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY: MODE 6 ACTION:

With the Containment Ventilation Isolation System inoperable, close each of the penetrations providing direct access from the Containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation Isolation System shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation signal from each of the applicable Containment proces: radiation monitoring 4

instrumentation channels specified in idble 3.3-13.

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