ML20206H441

Amend 201 to License NPF-1,revising PDTSs by Deleting ISFSI Area,Changes Also Revise TSs by Revising Subsection 4.1.1 & Replacing Existing Figure 4.1-1 with New Figure 4.1-1 & Adding New Page to Figure 4.1-1 as Listed

ML20206H441
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/05/1999
From:	Masnik M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206H435	List: ML20206H433 ML20206H441 ML20206H450
References
NUDOCS 9905110211
Download: ML20206H441 (6)

Text

p i p Mr g & UNITED STATES

r g NUCLEAR REGULATORY COMMISSION t WA&HINGToN, D.C. 20066-0001

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PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER AND ELECTRIC BOARD l PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201  :

License No. NPF-1 j

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

A. The application for amendment filed by Portland General Electric Company (PGE or  ;

the licensee) dated February 12,1997, complies with the standards and requirements  !

of the Atomic Energy Act of 1954, as amended (the Act), and the rules and  !

regulations of the Commission as set forth in 10 CFR Chapter I;  !

1 B. The facility will be maintained in conformity with the application, 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 and safety of the public, and (ii)  !

that such activities will be conducted in compliance with the regulations of the Commission as set forth in 10 CFR Chapter I;

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D. The issuance of this amendment will not be inimical to the common defense and i 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 regulations of the Commission and all applicable requirements have been satisfied.

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! l 9905110211 990505 PDR ADOCK 05000344 W PDR l J

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2. Accordingly, Facility Operating License No. NPF-1 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  ;

follows:

1 (2)- Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 201 , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 6 f Michael T. Masnik, Chief Decommissioning Section, Project Directorate IV & Decommissioning Division of Licensing Project Management

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: May 5, 1999 2

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ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING NO. NPF-1 1

l DOCKET NO. 50-344 Revise the Permanently Defueled Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 4-1 41 4-2 4-2 43 f i

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,. Design Features l 4.0 4.0 DESIGN FEATURES l

! 4.1 Site 4.1.1 Site and Exclusion Area Boundaries "The Site and Exclusion Area Boundaries shall be as shown in Figure.

4.1 1. The Exclusior, Area boundary coincides with the Trojan Nuclear Plant Site boundary on the Oregon side of the Columbia River and extends across the Columbia River to the east where the Washington shore of the river forms the eastern boundary. The Independent Spent Fuel Storage Installation (ISFSI) access controlled area shown in Figure 4.1 1 is subject to a Part 72 License and not Part 50 License NPF 1." i 4.2 Fuel Storage 4.2.1 Criticality 4.2.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U 235 enrichment of 4.5 weight percent;

b. K.,, s 0.95 if fully flooded with unborated water, which l includes an allowance for uncertainties as described in j Section 3.1 of PGE 1037, dated July 1983- 1 1

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c. A nominal 10.5 inch center to center distance between fuel assemblies placed in the fuel storage racks: I 4.2.2 Drainace l

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".

4.2.3 Capacity The spent fuel storage pool is designed and shall be maintained with a )

storage capacity limited to no more than 1408 fuel assemblies.  ;

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TROJAN UNIT 1 41 Amendment No. 194,201 i l

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Site and Exclusion Area Boundaries TROJAN UNIT 1 42 Amendment No. 194,201

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