ML20151E453

Amend 147 to License NPF-1,revising Surveillance Requirements in Tech Spec Section 3/4.6.1.1, Containment Integrity

ML20151E453
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/11/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151E447	List: ML20151E444 ML20151E453 ML20151E455
References
NUDOCS 8807260071
Download: ML20151E453 (4)

Text

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PORTLAND GENERAL ELECTRIC COMPAliY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT y4ENDMENT TO FACILITY OPERATING LICENSE Amendment flo 147 License No. NPF-1

1. The Nuc1 car Regulatory Comission (the Commission) has found that:

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated July 29, 1985 complies with the stalidards 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; D. The facility will o)erate in conformity with the ap)lication the provisions of tie Act, and the regulations of t1e Comission; C. Thereisreasonableassurance(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 comon 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.

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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.147 , 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 REGULATORY COMMISS10ll i

George W. Knighton, Director Project Directorate V Division of Reactor Projects - Ill, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: July 11, 1988 1

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ATTACHMENT TO LICENSE AllENDMENT N0.147 .

TO FACILITY OPERATING LICENSE N0. NPF-1 DOCKET N0. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 6-1 3/4 6-1 e

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Oe 3/4.6 CONTAINNENT SYSTENS 3/4.6.1 PRINARY CONTAINNENT CONTAINNENT INTEGRITY LINITING CONDITION FOR OPERATIO'd 3.6.1.1 Primary CONTAINNENT INTEGRITY shs11 be maintained.

- APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION .

Without primary CONTAINNENT INTEGRITY, restore CONTAINNENT INTEGRITY within one hour or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE RE0VIRENENTS __

4.6.1.1 Primary CONTAINNENT INTEGRITY shall be demonstrated:

i a. At least once per 21 d9ys by verifying that:

1. All penetrations (except those portions located inside containment) not capable of being closed by OPERABLE coe'.iinment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Specification 3.6.3.1, l and

2. All equipment hatches are closed and scaled.

b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

c. By vr.rifying that valves, blind flanges, and deactivated automatic valvus which are located inside the containment are verific d closed durin3 each COLD SHUTDOWN except that such verification ne6d not be performed more of ten than once per 92 days.

TkOJAN-UNIT 1 3/4 6-1 Amendment No.

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