ML20214C812

Proposed Tech Specs Re Max Pressurizer Spray Water Temp Differential.Certificate of Svc Encl

ML20214C812
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/18/1986
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20214C792	List: ML20214C789 ML20214C799 ML20214C812
References
TAC-60781, NUDOCS 8602210280
Download: ML20214C812 (3)

Text

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. . LCA 137 Attachment 1 Page 1 of 2 REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:

l a. A maximum heatup of 100*F in any one hour period,

b. A maximum cooldown of 200'F in any one hour period, and

c. A maximum spray water temperature differential of 560*F.

(NOTE: Spray actuations with a temperature differential

>320*F and $560*F are limited in accordance with Table 5.9-1.) l APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an analysis to determine the effects of the out-of-limit condition j on the fracture toughness properties of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

I SURVEILLANCE REQUIREMENTS 4.4.9.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per hour during system heatup or cooldown.

4.4.9.2.2 The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during spray operation.

Any occurrence of spray operation with a temperature differential >320*F shall be recorded for evaluation of the cyclic limits in Table 5.9-1.

0602210200 860218 DR ADOCK 0 g4 j TROJAN-UNIT 1 3/4 4-28 Amendment No. 27

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TABLE 5.9-1 g . .

COMPONENT CYCLIC OR TRANSIENT LIMITS h

Y

% CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT q COMPONENT  :

~

Reactor Coolant System 200 heatup cycles at $100*F/hr Heatup cycle - Tavg from $200*F and 200 cooldown cycles at to 1552*F.

5100*F/hr (pressurizer cooldown Cooldown cycles - Tavg from 1552*F at $200*F/hr). to $200*F.

80 loss of load cycles, without 115% of RATED THERMAL POWER to immediate turbine or reactor trip. 0% of RATED THERMAL POWER.

40 cycles of loss of offsite Loss of offsite A.C. electrical A.C. electrical power. power source supplying the onsite ESF Electrical System.

80 cycles of loss of flow in one Loss of only one reactor vi reactor coolant pump. coolant pump.

400 reactor trip cycles. 100% to 0% of RATED THERMAL POWER.

10 spray actuation cycles. Spray water temperature differential

>320*F and $560*F.

ME

%a*

o n

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

)

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

)

(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 137 to the Operating License for Trojan Nuclear Plant, dated February 18, 1986, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 18th day of February 1986:

Mr. Lynn Frank, Director State of Oregon Department of Energy Labor & Industries Blds, Rm 102 Salem OR 97310 Mr. Michael J. Sykes Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051 G. A. himmerman, Manager Nucl ar Regulation Branch l Nucle r Safety & Regulation Subscribed and sworn to before me this 18th day of February 1986.

dA A Y Notary Publ'ic of Or d n ne_ .

l l My Commission Expires:

0 M[ / M 1

l l

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