ML20207R494
| ML20207R494 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/06/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207R472 | List: |
| References | |
| NUDOCS 8703170281 | |
| Download: ML20207R494 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OPEGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No.124 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Corrrlission) has found that:
A.
The application for amendment by Portland General Electric Company, et al., (the licensee) dated September 3,1985, as supplemented 12, 1986, complies with the standards and ParBi 5, and December 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; g
There is reasonable assurance (i) that the activities authorized l
C.
by this amendment can be conducted without endangering the health j
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l
i The issuance of this amendment will not be inimical to the common l
D.
l defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements s
have been satisfied.
i 8703170281 870306 PDR ADOCK 05000344 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendrent, and paragraph 2.C.(?) 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.124, 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 COMMISSION 0.dl O e C4
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[h3-teven A. Varga, Director PWR Project Directorate No. 3 Division of PWR Licensing-A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance: March 6, 1987 E
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NUCLEAR REGULATORY COMMISSION o
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ATTACHMENT TO LICENSE AMENDPENT NO.124 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Page Insert Page TS 3/4 7-13 TS 3/4 7-13 1
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i PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 REQUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
By verifying that each component cooling water pump is OPERABLE when tested pursuant to Specification 4.0.5.
c.
At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety related equipment, except s
those valves in Specification 4.7.3.1.d, actuates to its correct position on a Containment isolation signal.
d.
At least once per 18 months, during shutdown, by verifying that valves M0-3294,M0-3296, M0-3300, and M0-3320 actuate to their correct position on:
1.
A Containment isolation signal coincident with a low CCW surge tank level, and 2.
A high-high Containment pressure signal.
e.
By verifying that each power operated (excluding automatic) l valve is OPERABLE when tested pursuant to Specification 4.0.5.
TR03AN-UNIT 1 3/4 7-13 Amendment No. 74,124
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