ML20245E649
| ML20245E649 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/20/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245E641 | List: |
| References | |
| NUDOCS 8906270357 | |
| Download: ML20245E649 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
- E WASHINGTON, D, C. 20655
,o PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 I
TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.154 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Portland General Electric Company, et al., (the licensee) dated February 10, 1989 complies with the st'aiidards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; i
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B.
The facility will o)trate in conformity with the ap)lication, j
the provisions of tie Act, and the regulations of tie Commission; C.
There is reasonable assurance (i) that the activities authorized
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by this amendment can be conducted without endan'gering the health
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and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of tnis amendment will not be inimical to the common I
defense and security or to the health and safety of the public;-
i and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
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 follcws:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.154, 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 I
A w
George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 20, 1989 l
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LATTACHMENT TO LICENSE AMENDMENT NO.154 l
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TO FACILITY OPERATING LICENSE NO. NPF-1 l
DOCKET'NO. 50-344
- 1 Revise Appendix A as follows:
_j Remove Pages Insert Pages 5-6 5-6 l
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DESIGN' FEATURES DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be paintained with siphon breakers in the piping extending into the pool which prevent inadvertent i
draining of the pool below elevation 83'11".
I CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a i
storage capacity limited to no more than 1408 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category 1 items I
in Section 3.2.1 of the FSAR shall be designed and maintained..to the original design provisions contained in Section 3.7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements except for the Control Building Compicx which is subject to Specifications 5.7.2.1-and 5.7.2.2.
5.7.2.1 The Control-Auxiliary-Fuel Building Complex (Complex) shall be designed and maintained to the design provisions contained in Sections 3.7 end 3.8 of the FSAR (as amended through Amendment No. 34) with allowance l
for normal degradation pursuant to the applicable Surveillance Requirements.
5.7.2.2 No modifications wh ch will result in a net:
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(a) 3 percent increase in lateral shear forces on any story of l
the Complex; (b) 1 percent decrease in lateral shear resistance of any story I
of the Complex; v
(c) 5 percent increase in combined interstructure displacements between the Control and Yurbine Buildings; or (d) 5 percent reduction in clear space between the lurbine and Control Buildings shall be performed without prior approval of the Director of Nuclear Reactor Regulation. An increase in equipment weight not to exceed 10 percent on a per story, per building basis is permissible and excluded from consideration under this specification.
l TROJAN-UNIT 1 5-6 Amendment No. 76, ZK, #7, 87, $5 154-
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