ML20059C790
| ML20059C790 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/27/1990 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059C783 | List: |
| References | |
| NUDOCS 9009050339 | |
| Download: ML20059C790 (4) | |
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'o UNITED STATES '
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NUCLEAR REGULATORY COMMISSION I-WASHINGTON, D. C. 20666 e
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PORTLAND GENERAL ELECTRIC COMPANY'
.THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY 1
DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE l
1 Amendment No.162 l
License No. NPF-1 l
L 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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L A.
The application for amendment by Portland General-Electric Company, l
et al.
(the licensee) dated February 10, 1989 complies with the j
l-standards and requirements of the Atomic Energy-Act of 1954, as amended (the Act), and the Comission's regulations set forth in i
10 CFR Chapter I; j
B.-
The facility will operate in conformity with the application, l
the provisions of the Act, and the regulations of the Comission; l-L C.
There-is reasonable assurance-(i) that the activities authorized by 1his 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 51 of the Comission's r9gulations and all applicable requirements ir have been satisfied.
l l
i 9009090339 900e27 PDR ADOCK 05000344 P
PDC j
y 2-2.
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 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.162, are hereby incorporated in the license. The licensee shall operate the facility in accord.=nce with the Technical-Specifica-tions, except where otherwise stated in specific license conditions.
3.
This license amendment is effettive as of the date of-its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION v
Y O
John T. Larkins. Acting Director Project Directorate Y Division of Reactor Projects III, IV, Y and Special Projects Office of. Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1990 I
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l ATTACHMENT TO LICENSE AMENDMENT NO.162 TOFACILITYOPERATINGLICENSENO.NPFi DOCKET NO. 50-344 L
Revise Appendix A Technical Specifications by removing the page identified I
below and inserting the enclosed page. The revised page is identified by L
amendment numer and conthins marginal lines indicating the area of change. -
1 Remove Pages Insert Pages 3/4 6-1 3/4 6-1
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)
s.
4 3/4.6= CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGR1TY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
l APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMEN1 IN1EGRITY, restore CONTAINMENT INTEGRITY within one hour or be in COLD SHU10DWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVE1LLANCE REQUIREMENTS 4.6.1.1 Primary CON 1 AINMEN1 INTf GRITY shall be demonstrated:
a.
At least once per 31 days by verifying that:
All penetrations (except those portions located inside Containment) not capable of being closed by OPERABLE Containment Automatic isolation valves and required to be closed during accident conditions are elesed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Specification 3.6.3.1.
b.
By verifying that each containment air lock is OPERABLE per-Specification 3.6.1.3.
c.
By verifying that valves, blind flanges, and deactivated automatic valves which are located inside the Containment are verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
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TROJAN-UNll 1 3/4 6-i Amendment No. 747, 162 a