ML20196G026

Amend 145 to License NPF-1,revising Means by Which Source Range Neutron Flux Instrumentation Calibr Will Be Performed

ML20196G026
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/23/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196F990	List: ML20196F987 ML20196G026 ML20196G042
References
NUDOCS 8807050396
Download: ML20196G026 (5)

Text

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/ UNITED STA1 ES

[ ') NUCLEAR REGULATORY COMMISSION

$ ,a W ASHINGTON, D. C. 20555

%q PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NilCLEAR PLANT AMENDFENT TO FACILITY OPERATING LICENSE Amendment No.145 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 December 18, 1987, as supplemented Rare 15, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set # orth in 10 CFR Chapter I; B. The facility will operate in confmnity with the application, the provisions of the Act, and the aCulations of the Comission; l C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) 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 comon defense and security or to the health and safety of the public; and l E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appl! cable ~ requirements have been satisfied.

1 8807050396 880623 PDR ADOCK 05000344 P PDR l

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2. Accordingly, the licante 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.145, 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 REGU ATORY COMMISSION eorge . Knightop, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special 'rojects Office of Nuclear Reator Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 23, 1988 I

ATTACHMENT TO LICENSE AMENDMENT N0.145 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-34_4 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-12 -

3/4 3-12 3/4 3-12a I

I l

TABLE 4.3-1 (Continued)

NOTATION

• With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

1. The provisions of Specification 4.0.4 are not applicable.

1. When below the P-6 setpoint.

1. 1. When below the P-10 setpoint.

• When above the P-7 setpoint.

(1) - If not perf ormed in pr6vious 31 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is >2%.

(3) - Compare incore to excore axial imbalance above 15% of RATED THERMAL POWER. Recalibrate if absolut? difference >3 percent.

(4) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) - With the high voltage setting varied, as reconsnended by the manufacturer, an initial discriminator bias curve shall be measured for each detector. Subsequent discriminator bias curves shall be obtained, evaluated, and compared to the initial curves.

(6) - Incore-Excore Calibration.

s?) - Each train tested every other month.

(8) - Setpoint verification is not applicable.

l (9) - See Specification 3/4.9.2 for audio and visual requirements in MODE 5.

(10) - The reactor trip breakers shall be tested using the Automatic Trip Logic trip signal.

(11) - Each channel shall be tested at least every 92 days on a STAGGERfD TEST BASIS.

(12) - The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

j (1r - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY c? the Bypass Breaker trip circuit (s).

TROJAN-UNI! 1 3/4 3-12 Amendment No. 737, 737 145

TABLE 4.3-1 (Continued)

(14) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(15) - Local manual shunt trip prior to placing breaker in service.

(16) - Automatic undervoltage trip.

4 TROJAN-UNIT 1 3/4 3-12a Amendment No.145