ML20205A309

Amend 125 to License NPF-1,revising Shutdown Rod & Control Rod Insertion Limits by Changing Definition of Fully Withdrawn Rods from 228 Steps to Greater than 225 Steps

ML20205A309
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/20/1987
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205A259	List: ML20205A253 ML20205A309 ML20205A314
References
NUDOCS 8703270413
Download: ML20205A309 (6)

Text

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.g'd r o,, UNITED STATES E- NUCLEAR REGULATORY COMMISSION 3

' g y E WASHINGTON, D. C. 20555

%.....j 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.125 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 October 31, 1986, as supplemented ITe'ceiEber 8,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 the Commission; 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 (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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i have been satisfied. .

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1 8703270413 DR B70320 ADOCK 05000344 PDR l

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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.125 , 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 i

i teven , ht tor PWR Project Direc , rate No. 3 Division of PWR Li ensing-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance: March 20, 1987

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{ 3 g NUCLEAR REGULATORY COMMISSION c -l wAssiNcTON, D. C. 20555

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ATTACHMENT TO LICENSE AMENOMENT NO.125 TO FACILITY OPERATING LICFNSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Paaes Insert Paaes TS 3/4 1-22 TS 3/4 1-22 3/4 1-24 3/4 1-24 3/4 1-25 3/4 1-25 j

.~ ,_.m . . . _ , , - , - . , . . . . ,,,.,r, , , , . , _ _ - _ . - , . _ , m .._, .,_ . ,. _ - _m., _ . . _ _ _ . . .,._ _ _ _,_ -. _

l REACTIVITY CONTROL SYSTEMS SHUTDOWN R00 INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be fully withdrawn (> 225 steps).

l APPLICABILITY: MODES 1* and 2*#

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a, Fully withdraw the rod, or

b. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.4 Each shutdown rod shall be determined to be fully withdrawn:

a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C or D during an approach to reactor criticality, and

b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereaf ter.

• See Special Test Exceptions 3.10.2 and 3.10.4.

1. With Reft > 1.0.

TROJAN-UNIT 1 3/4 1-22 Amendment No. 125

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d (FpglY WITHORAWN.> 225 5TEPS)

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FRACTION OF RATED THERMAL POWER FIGURE 3.1- 1

. ROD BANK INSERTION LIMITS VERSUS TIERMAL POWER FOUR LOOP OPERATION TROJAN-UNIT I 3/4 ;.24 Amendment No. ## , ///,125

(FULLY WITHORAWN,> 225 STEPS) 228 l 7

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FRACTION OF RATED THERMAL POWER FIGURE 3.1-2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER THREE LOOP OPERATION TROJAN-UNIT I 3/4 1-25 Amendment No. 125