ML20199E874

Proposed Tech Specs Re Proposed Rev to TS Instrumentation Surveillances

ML20199E874
Person / Time
Site:	Millstone
Issue date:	01/23/1998
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20199E870	List: B16979, Forwards Responses to Questions Re Proposed Rev to TS Instrumentation Surveillances ML20199E874
References
NUDOCS 9802020267
Download: ML20199E874 (5)

Text

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Docket No. 50-423  !

B16979 l

Attachment 3 l

l Millstone Nuclear Power Station, Unit No. 3 1

Marked-Up Page January 1998 9802020267 990123 POR ADnCK 03000423 P PDR

JAN 31 1988 SAFETY LIMfTS AND LfMITENG SAFETY SYSTEM SETTINGS _

I 22 2 LIMITING SAFETY SYSTEM SETTINGS gACTORTRIPSYSTEMINSTRUNENTATIONSETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shwn in Table 2.2-1. 1 AP?lICABILI,T_Y: As shown for each channel in Table 3.3-1.

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.A_C, TION:

a. With a Reactor Trip System Instrumentation or Interlock setpoint less conservative than the value shown in the Trip Setpoint column l but more conservative than the value shown in the Allowable Value I column ofvalut.

Setpoint Table 2.2-1, adjust the Setpoint consistent with the Trip

b. With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value snown in the Allowable Values column of Table 2.2-1, either:

1. Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or

2. Declare the channel inoperabic and apply the applicable ACTION '

statement requirement of Specification 3.3.1 until the channel 1 is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpo',t value.

Equation 2.2-1 2 + R + S < TA Where:

Z = The value from Column 2 of Table 2.2-1 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, l 5 = Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.

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m MILLSTONE - UNIT 3 2-4 im i--i-i-i

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ACTION:

a.

Wiih o Reocior Trio System instrumentation Channel or Interlock Channel Nominal Trip Seipoint inconsistent with the volde shown in the_

Nomino1 Pip Setpoint column of Table 2.2-1, adjust the Setpoint consistent with the Nominal Trip Seipoint value, o.

\ With a Reactor Trjp System Instrumentation Channel or interlock Channel found to be inoperable, declare the channelinoperable and apply the opplicable ACTION statement requirement of Specification 3.3.1 until the channelis restored to OPERABLE status.

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o Docket No. 50-423 B16979 s

I Attachment 4 Millstone Nuclear Power Station, Unit No. 3 Retyped Page January 1998

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- e SAFETY LIMITS AND LIMITING SAFETY SYSTEM SECTINGS r 1, 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INFTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: As shown for each channel in Table 3.3-1.

ACTION:

a. With a Reactor Trip System Instrumentation Channel or Interlock Channel Nominal Trip Setpoint inconsistent with the value shown in the Nominal Trip Setpoint column of Table 2.2-1, adjust the Setpoint l consistent with the Nominal Trip Setpoint value,

b. With a Reactor Trip System Instrumentation Channel or Interlock l Channel found to be inoperable, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification l 3.3.1 until the channel is restored to OPERABLE status.

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MILLSTONE - UNIT 3 2-4 Amendment No.

0550 {

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