ML20141P081

From kanterella
Jump to navigation Jump to search
Amend 112 to License NPF-1,revising Tech Specs to Add Operability & Surveillance Requirements for Core Exit Thermocouples & Reactor Vessel Level Instrumentation Sys
ML20141P081
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 03/10/1986
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141P059 List:
References
NUDOCS 8603180530
Download: ML20141P081 (5)


Text

' UNITED STATES

, [o,,

3 o NUCLEAR REGULATORY COMMISSION C W ASHINGTON, D. C. 20655 l

s., .... /

PORTLAND GENERAL ELECTRIC COMPANY .

THE CITY OF EUGENE, OREGON l

t PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. NPF-1 l

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 August 7, 1985, complies with the sTaiidards 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 confonnity with the application, the provisions of the Act, and the rules and regulations of l

, the Comission; 1

( 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 l

conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements I have been satisfied.

l l .

l h

i gRO3180530 860310 p ADOCK 05000344 PDR l

1

4 2

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.112, 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

, R Lt.m (gSteven A. Va a Director

\ PWR Project Directorate No. 3

, Di' vision of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of issuance: March 10,1986 i

E

,. L

{

l s

i l

I

\

i i

! ATTACHMENT TO LICENSE AMENDMENT NO.112 j i TO FACll!TY OPERATING LICENSE NO. NPF-1 1 DOCKET N0.50-34A ,

l Revise Appendix A as follows:

i

Remove Pages insert Pages i 3/4 3-52 3/4 3-52  ;

1 i 3/4 3-54 3/4 3-54 l l l t

i r I

I Y l (

i 1

1 5

k I

l 1 l I

i

i-j i i  !

I l

l l i i

4 I I l

i i

t 1

I I  :

i ,

V

. TABLE 3.3-11 ACCIDENT MONITORING INSTRUMENTATION TOTAL NO. MINIMUM NUMBER INSTRUMENT OF CHANNELS OF CHANNELS

1. Reactor Coolant System Subcooling 2 l Margin Monitor
2. PORV Position Indicator
  • 1/ valve 1/ valve
3. PORV Block Valve Position 1/ valve 1/ valve Indicator **
4. Safety Valve Position Indicator 1/ valve 1/ valve (Acoustical Flow)
5. Auxiliary Feedwater Flow Rate 4 per pump 2 per pump
6. Pressurizer Water Level 3 2
7. Containment Atmospheric Pressure 2 1

._ (-10 to 190 psig)

8. Containment Water Level (Wide 2 1 Range)
9. Containment Water Level (Narrow 1/ sump 1/ sump Range)
10. Core Exit Thermocouples 4/ core 2/ core quadrant # quadrant #
11. Reactor vessel Level Instrumenta- 2 1 tion System
  • Not applicable if the associated block valve is in the closed position.

Not applicable if the block valve is verified in the closed position and power removed.

  1. The core exit thermocouples required to be OPERABLE shall be those l which are displayed on the Subcooling Margin Monitors. I TROJAN-UNIT I 3/4 3-52 Amendment No. If, f,3,10$/,112

. I i

]

TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS

~

CHANNEL CHANNEL CHANNEL FUICTIONAL INSTRUMENT CHECK CALIBRATION TEST

1. Reactor Coolant System M R Subcooling Margin Monitor
2. PORY Position Indicator M R
3. PORV Block Valve Position M R Indicator
4. Safety Valve Position M R Indicator ( Acoustical Flow)
5. Auxiliary Feedwater Flow Rate M* R
6. Pressurizer Water Level M R

.. 7. Containment Atmospheric M R Pressure (-10 to 190 psig)

8. Containment Water Level (Wide M R Range)
9. Containment Water Level M R (Narrmd Range)
10. Core Exit Thermocouples M R **
11. Reactor vessel Level Instru- M R mentation System
  • Not applicable in Modes 1 and 2.
    • Calibration shall consist of calibrating the thermocouple indicators.

TROJAN-UNIT 1 3/4 3-54 Amendment No. 55. ,f 3, Idf .112