ML20196F929

Amend 143 to License NPF-1,changing Tech Spec Section 3/4.3.3.10 by Adding Two Instruments for Monitoring Steam Generator Blowdown Liquid Effluent Discharge

ML20196F929
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/16/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196F882	List: ML20196F876 ML20196F929 ML20196F947
References
NUDOCS 8807050359
Download: ML20196F929 (6)

Text

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. [ UNITED STATES 8 NUCLEAR REGULATORY COMMISSION g ;j WASHINGTON, D. C. 20555

%.....j PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY D0CKET NO. 50-3a4 TROJAN NUCLEAR PLANT AMENDMENT TO FACIL!TY OPERATING LICENSE Amendment No.143 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 February 17, 1988 complies with the Halidards and requirements of the Atomic Energy Act of 1954, as l amended (the Act), and the Connission's regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the ap>11 cation, the provisions of t1e Act, and the regulations of tie Comission; 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; I and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

l l 8807050359 880616 PDR ADOCK 05000344 P PDR

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 8, as revised through Amendment No.143 , are hereby incorporated in the license. The licensee shall operate

' the facility in accordince 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

/ tit" George . Knighton / irector Projec Directora e V Division of Reactor Projects - III, IV, Y and Special Projects

, Office of Nuclear Reactor Reculation l

Attachment:

Changes to the Technical Specifications Date of Issuance: June 16, 1988 l

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ATTACHMENT TO LICENSE AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages

~

3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-58 3/4 3-58

j TABLE 3.3-12 E

$; RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION E:

25 MINIMUM

-' CHANNELS INSTRUMENT QPERABLE APPLICABILITY ACTION

} 1. Gross Radioactivity Monitors Providing Automatic Termination 1

of Release Liquid Radwaste Effluent Line

• 23

a. 1 (PRM-9)

b. Steam Generator Blowdown 1 24 Ef fluent Line (PRM-10) or '

u, Steam Generator Blowdown Ion

); Exchanger Ef fluent (P2M-17)

2. Gross Radioactivity Monitors

'" Not Providing Automatic Termination of Release

a. Component Cooling Water System 1 At all times 25 i

Train A (PRM-7) i

b. Component Cooling Water System 1 At all times 25 i Train B (PRM-8) d i

p l &

• During releases via this pathway.

S 4

a E

m

-4 TABLE 3.3-12 (Continued)

$$ RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Ei MINIMUM El CHANNELS

_a INSTRUMENT OPERABLE APPLICABILITY ACTION

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1

• 26 (FT-4044 or FIY-4098)

b. Discharge Structure 1

• 26 (FR-3495)

c. Steam Generator Blowdown 1

• 26 Effluent Line R.f (FI-6715 or FI-4921)

E F

R

{

e

• During releases via this pathway.

3 w

__ m

~

g TABLE 4.3-8 o

y RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATI0al SURVEILLANCE REQUIREMENTS CHANNEL

-e CHANNEL SOURCE CHANNEL FUNCTIONAL l INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta or Gannia Radioactivity

Monito s Providing Alarm and Automatic Isolation

a. Liquid Radwaste Effluents Line D* P R(1) Q(1)

(PRM-9)

b. Steam Generator Blowdown Effluent D* M R(1) Q(1)

Line (PRM-10) w c. Steam Generator Blowdown Ion D* M R(1) Q(1)

• Exchanger Ef fluent (PRM-17) w h 2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Isolation l Component Cooling System (PRM-7, -8) D M R(1) Q(1)

3. Flow Rate Monitors

a. Liquid Radwaste Effluent Line D* N/A R** N/A (FT-4044/FIY-4098) p b. Discharae Structure (FR-3495) D* N/A R** N/A g c. Steam Generator Blowdown Line D* N/A R** N/A (FI-6715 or FI-4921)

• During releases via this pathway.

g ** Applies only to flow indication loop.

, (1) The Channel Functional Test shall, where applicable, include verification that automatic a isolation of the ef fected pathway and/or control room annunciator occurs if:

1) Instrument indicates above alarm trip setpoint.

2) Instrument indicates a downscale failure.

3) Controls not in OPERAIE mode, or instrument de-energized.

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