ML20151N864

Proposed Tech Specs Table 4.3.1.1-1,reactor Protection Sys Instrumentation Surveillance Requirements Deleting Daily Check Requirements of Note G for APRM Flow Biased Neutron flux-high Scram Functional Unit

ML20151N864
Person / Time
Site:	Fermi
Issue date:	04/20/1988
From:	DETROIT EDISON CO.
To:
Shared Package
ML20151N844	List: ML20151N864 NRC-88-0105, Application for Amend to License NPF-43,revising Tech Spec Table 4.3.1.1-1,reactor Protection Sys Instrumentation Surveillance Requirements.Fee Paid
References
NUDOCS 8804260030
Download: ML20151N864 (2)

Text

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a r0 TABLE 4.3.1.1-1

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88 7:o r" REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E OPERATIONAL CHANNEL I O$ 7 FUNCTIONAL CHANNEL CONDITIONS FOR WHICH CHANNEL 82 e FUNCTIONAL UNIT CHECK TEST CALIBRATION (,) SURVEILLANCE REQUIRED

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, os* Intermediate Range Monitors:

'o 1. S/U(c),W 2

a. Neutron Flux - High S/U,5,(b) SA S W SA 3,4,5 l

W NA 2,3,4,5 l b. Inoperative NA I

2. Average Power Range Monitor (f):

5/U.S,(b) S/U(c),W SA 2

a. Neutron Flux - W SA 3, 5

w Flux - High 5 .

1 4 w c. Fixed Neutron Flux - S/U(c),W W(d), SA 1 4 nigh 5 W NA 1,2,3,5

d. Inoperative NA

3. Reactor Vessel Stean: Dome R 1, 2 Pressure - High 5 M J 4. Reactor Vessel Low Water M R 1, 2 S

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Level - Level 3

5. Mein Steam Line Isolation M R 1 Valve - Closure NA i

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6. Main Steam Line Radiation -

5 M R 1,2(i)

! High 4 R 1, 2 S M

7. Drywell Pressure - High l

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TABLE 4.3.1.1-1 (Continued) .

,. REAC10R PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS m '

CHANNEL OPERAT10NAL f

~ CONDITIONS FOR WHICH CHANNEL FUNCTIONAL CHANNEL.

FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

. 8. Scram Discharge Volume Water

• Level - High -

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a. Float Switch NA Q R 1,2,5(j)

b. Level Transmitter S M R 1, 2, 5(j)

' 9. Turbine Stop Valve - Closure NA M R 1

! 10. Turbine Control Valve Fast Closure NA M NA 1 l

11. Reactor Mode Switch Shutdown Position NA R NA 1,2,3,4,5 m

12. Manual Scram NA M NA 1,2,3,4,5 w 13. Backup Manual Scram NA R NA 1,2,3,4,5 ,

g s w (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least decades during each 4

startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least decades during each controlled shutdown, if not performed within the previous 7 days.

(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.

(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED _

THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute difference.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 ef fective full power hours (EFPH) using the TIP system. +

(g) "e" 'y r 2 cered cere '! = te be les th2r er r^"2! te est9!! Sed cere '!= ct the existing !:r; d?re l 55m*. Qele ted.

' (h) This calibration shall consist of verifying the 6 1 1 second simulated thermal power time constant.

(i) 1his function is not required to be OPERABLE when the reactor pressure vessel head is removed per j Specification 3.10.1.

(j) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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