ML20206F116

Amend 116 to License NPF-1,removing Max Total Fuel Rod Weight Limit of 1,760 G U from Section 5.3.1 of Tech Specs

ML20206F116
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/09/1986
From:	NRC
To:
Shared Package
ML20206F115	List: ML20206F110 ML20206F116 ML20206F121
References
NUDOCS 8606240231
Download: ML20206F116 (3)

Text

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. gaucg jog UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION g j W ASHINGTON, D. C. 20655

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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. 116 License No. NPF-1

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated April 11, 1986 complies with the standards aiid requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 i the Comission;

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C. There is reasonable assurance (i) that the activities authorized I 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 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 Comission's regulations and all applicable requirements have been satisfied.

8606240231 860609 PDR ADOCK 05000344 P PDR r

i ATTACHMENT TO LICENSE AMENDMENT N0.116 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-344 Revise Appendix A as follows:

Remove Page Insert Page 5-4 5-4 l

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i-1 DESIGN FEATURES .

i DESIGN PRESSURE AND TEMPERATURE

'i 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 60 psig and a temperature of 288'F.

PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and  !

shall be maintained in accordance with the original design provisions contained '

in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.3 REACTOR CORE I

FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4. Each fuel rod sha'11 have a nominal active fuel length of 144 inches. The initial core loading l shall have a maximum enrichment of 3.15 weight percent U-235. Reload fuel  !

shall be similar in physical design to the initial core loading and shall have  ;

a maximum enrichment of 3.5 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. Eight part length control rod assemblies originally installed in the core contained a nominal 36 inches of absorber' material at their lower ends. The part length control rod assemblies have been removed and are stored in the spent fuel pool.

5.4 REACTOR COOLANT SYSTEM l

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DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

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1 TROJAN-UNIT 1 5-4 Amendment No. 116

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