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Amend 137 to License NPF-1,revising Tech Spec Table 3.3-1, Reactor Trip Sys Instrumentation & Table 4.3-1, Reactor Trip Sys Instrumentation Surveillance Requirements, Per Generic Ltr 85-09
	ML20236X517
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/01/1987
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20195G820	List: ML20195G811; ML20236X517; ML20236X531;
References
	GL-85-09, GL-85-9, NUDOCS 8712090258
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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.137 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 June 22, 1987 complies with the staiidards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; E. The facility will operate in conformity with the application, the provisions of the Act, and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized t'y 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 common defense and security or to the health and safety of the public; and E. The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8712090258 871201 PDR ADOCK 05000344 ,

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?. Accordingly, the licerse is amended by changes to the Technical Specifk etions as indicated in the attachment to this license mendment, and paragraph P.C.(2) of Facility Operating License No. hPF-1 is hereby amended to reac as follows:

(2) Technical Specifications The Technical Specifications containea in Appendices A and B, as revised through An'endment No. 137, 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 COW.!SSION O Y George ighto rector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projecte Office of Nuclear Reactor Reg alation 4 Attachnient:

Charges to the Technical Specifications Date of Issuance: December 1,1987 I

December i, 1987 ATTACHM.EllT TO LICENSF AMENDM_E_NT f10.137 TO FACILITY OPERATING LICENSE _NO. NPF-1 LOCKET NO. 50-344 Revise Appendix A as follows:

Remove _Pages incert Paoes TS 3/4 3-4 TS 3/4 3-4 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 1

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TABLE 3.3-1 (Continued)

ACTION 9 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 10 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 11 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 1. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required f or perf orming maintenance to restore the breaker to OPERABLE status.

REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT FUNCTION DESIGNATION P-6 With 2 of 2 Intermediate Range Prevents or defeats the manual block of l Neutron Flux Channels <6x10-Il amps. source range reactor ,

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i P-7 With 2 of 4 Power Range Neutron Prevents or defeats l Flux Channels 111% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low i

impulse chamber pressure flow in more than one channels 166 psia, primary coolant loop, reactor coolant pump under-voltage and under-f requency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-D With 2 of 4 Power Range Neutron Prevents or defeats Flux Channels t39% of RATED the automatic block of THERMAL POWER.

reactor trip on low i coolant flow in a l single loop. l 3/4 3-7 Amendment No. 33, is, #B, 737 137 l TROJAN-UNIT 1 l 12/1/87

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TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT FUNCTION DESIGNATION P-10 With 3 of 4 Power Range Neutron Prevents or defeats the-Flux Channels <9% of RATED manual block of: Power l THERMAL POWER. range low setpoint reactor trip, intermediate range reactor trip, and inter-mediate range rod stops.

Provides input to P-7.

P-13 With 2 of 2_ Turbine Impulse Provides input to P-7.

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<66 psia.

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NOTATION

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

The provisions of Specification 4.0.4 are not applicable.

-## When below the P-6 setpoint.

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

l e When above the P-7 setpoint.

(1) If not performed in previous 31 days.

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

I (3) - Compare incore to excore axial imbalance above 15% of RATED THERMAL POWER. Recalibrates if absolute dif ference >3 percent.

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

(5) - Detector plateau curves shall be obtained and evaluated.

(6) - Incore-Excore Calibration.

(7) - Each train tested every other month.

(8) - Setpoint verification is not applicable.

(9) - See Specification 3/4.9.2 for audio and visual requirements in MODE 6.

(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 STAGGERED TEST BASIS.

(12) - The surveillance frequency and/or MODES specified for these ;

- channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(13) - 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 of the Bypass Breaker trip circuit (s).

(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.

TROJAN-UNIT 1 3/4 3-12 Amendment No. 727 137 12/1/87

ML20236X517

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