ML20205J606

Amend 109 to License NPF-1,authorizing Tech Spec Re Definitions of Operational Mode & operable-operability

ML20205J606
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/10/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205J603	List: ML20205J599 ML20205J606 ML20205J610
References
NUDOCS 8602260125
Download: ML20205J606 (4)

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,,., k, UNITED STATES g g NUCLEAR REGULATORY COMMISSION ti  : E WASHINGTON, 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.109 "

License No. NPF-1

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

A. The application for amendment by Portland General Electric Company, et al. , (the licensee) dated April 19, 1985, cortplies with the Italidards and 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 g .

the Comissio.n; - -

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 Commission's regulations; D. The issuance of this amendment will not be inimical to the comon 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.

8602260125 860210 PDR P

ADOCK 05000344 PDR ,

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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 follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.109, 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

/ l () & n Styven A. Varga, Director PWR t Project Directorate No. 3 Division of PWR Licensing-A 4

Attachment:

Changes to the Technical Sp.ecifications 7 ,

Date of Issuance: February 10, 1986 l

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ATTACHMENT TO LICENSE AMENDMENT NO.109

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TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Page Insert Page 1-1 1-1 e

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G 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER 1.2 THERMAL POWER shall be total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

OPERATIONAL MODE OR MODE l

1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principal specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERAllLE  :

or have OPERABILITY when it is capable of performing its specified safety-related function (s). Implicit in this definition shall be the l assumption that all necessary attendant instrumentation, controls, normal ano energency ciectric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety-related function (s) are also l capabie of performing their rated support function (s).

Nonessential portions of a system, subsystem, train, component, or device need not be operational as long as its lack of operational capability does not in any way degrade the safety-related function (s) of the system, sub-system, train, component, or device. For example, the Component Cooling Water System need not be declared inopercble if the waste gas compressor aftercooler is isolated due to a leak in the aftercooler since this portion of the system does not perform a safety-related function. As a further example, consider a failure of the manual operator on valve 8921A (SI Pump A discharge isolation) such that the valve cannot be repositioned.

If the valve is open, there is no safety-related impact since this does not prevent the SI train from performing its safety-related function.

However, if the valve is shut, then the SI Train A would be declared inoperable since it cannot perform its safety-related function.

TROJAN-UNIT 1 1-1 Amendment No. 53 109

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