ML20237D697

Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves

ML20237D697
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/18/1987
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20237D674	List: ML20237D672 ML20237D680 ML20237D697
References
TAC-66871, NUDOCS 8712240132
Download: ML20237D697 (3)

Text

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4 TABLE 4.3-1 (Continued)

NOTATION l

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• 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. 1. When below the P-6 setpoint.

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

• 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 I channel if absolute difference is >2%.

(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 from CHANNEL CALIBRATION. l (5) - With the high voltage setting varied, as recommended by the manuf acturer, 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.

(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 i 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).

TROJAN-UNIT 1 3/4 3-12 Amendment No. 737, 737 8712240132 871218 PDR ADOCK 05000344 P PDR

i 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.

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

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UNITED STATES OF AMERICA l'-

NUCLEAR REGULATORY COMMISSION kntheMatterof )

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PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )

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(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 160, to the Operating License for Trojan Nuclear Plant, dated December 18, 1987, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 18th day of December 1987:

Mr. William Dixon State of Oregon Department of Energy 625 Marion St NE Salem OR 97310 Mr. Michael J. Sykes Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051 y , v_ - _ -

W. A. Lmmerman, Manager Nuc1 ar Regulation Branch Nucl rtafety & Regulation Subscribed and sworn to before me this 18th day of December 1987.

JA 0-NotaryP%i6of' Oregon My Commission Expires:

BE TY J. SIMICH NOTARY PUBLIC-OREGON y commfu. ion cxvws /04W#

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