ML20005B852
| ML20005B852 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/25/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005B851 | List: |
| References | |
| NUDOCS 8109020369 | |
| Download: ML20005B852 (4) | |
Text
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,o, UNITED STATES
! y, #, c,' j NUCLEAR REGULATORY COMMISSION
': E WASHINGTON. D. C. 20553 k..v i
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. 67 License No. HPF-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated July 13 and 27,1981 comply with the standards
'and 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 cperate in confonnity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inidical 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 Commission's regulations and all applicable requirements l
have been satisfied.
i l
8109020369 810825 ~
PCR ADOCK 05000344 lf P
4 2.
Accordingly, Facility Operating License No. NPF-1 is amended by deleting paragraphs 2.C.(10) and 2.C.(12) and by anending
- i Paragraph 2.C.(2) to read as follows
- j (2) Technical Specifications li The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67, are j
hereby incorporated in the license. The licensee shall cperate the facility in accordance with the Technical Specifications, except as noted in 2.C.(11) below.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3 l.' ' ~
,1 : s-.-
Robert A. Clark, Chief
~
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 23, 1981 i
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1 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Pages Insert Pages I
5-6 5-6 4
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DESIGN FEATURES DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained with siphon breakers in the piping extending into the pool which prevent inadvertent draining of the pool below elevation 83'11".
j CAPACITY i
5.6.3 The spent fuel storage peal is designed and shall be maintained with a
' i storage capacity limited to ao more than 651 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category I items 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 Tor the Control Building Complex which is subject to Specificat;ons 5.7.2.1 and 5.7.2.2.
5.7.2.1 The Control-Auxiliary-Fuel Building O olex (Complex) shall be designed a ' maintained to the design provisions contained in Sections 3.7 and 3.8 of the FSAR (as amended through Amendment No. 34) with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.7.2.2 No modifications which will result in a net:
l (a) 1 percent increase in lateral shear forces on any story of the Complex; (b) 1 percent decrease in lateral shear resistance of any story of the Complex; (c) 5 percent increase in combined interstructure displacements between the Control and Turbine Buildings; or (d) 5 percent reduction in clear space between the Turbine and Control Buildings l
shall be performed without prior approval of the Director of Nuclear Reactor Regulation. An increase in equirxnent weight not to exceed 10 percent on a l
per story, per building basis is permissible and excluded from consideration un&r this specification.
l TROJAN-UNIT 1 5-6 Amendment No. 75, 3J, J7, 67
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