ML20073D998

Proposed Tech Spec Table 4.3.1.1-1 Re Channel Check for flow-biased Simulated Thermal Power

ML20073D998
Person / Time
Site:	Grand Gulf
Issue date:	04/26/1991
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20073D996	List: ML20073D991 ML20073D998
References
NUDOCS 9104300009
Download: ML20073D998 (2)

Text

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@ TABLE 4.3.1.1-1 -

'23 E e_

Io REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ r-j G; CHANNEL OPERATIONAL q.

@8 FUNCTIONAL CHANNEL CONDITIONS FOR WHICH O oo c'- CHANNEL W-Se 2 FUNCTIONAL UNIT CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED N* 1. Intermediate Range Monitors:

S/U,5,ID) S/U, W 2 8S a. Neutron Flux - High R 5 W R 3, 4, 5

@g7 x~

" b. Inoperative NA W NA 2,3,4,S D 2. Average Power Range Monitor: II)

S/U.S,g) S/U, W 2

a. -Neutron Flux - High, SA W SA 3, 5 Setdown S

$ b.  : Flow Biased Simulated Thermal Power - High Sy Q W(d)(e) , SA, R II) 1 i

w L

c. Neutron Flux --High 5 Q W fd) , SA 1 Inoperative NA 1, 2, 3, S

d. NA Q

3. Reactor Vessel Steam Dome Pressure - High S Q R f9) 1, 2 fi)

4. Reactor Vessel Water Level -

Low, Level 3 S Q R I9) 1, 2 k 5. Reactor Vessel Water Level -

High, Level 8 S Q R f9) 1 R

3 6. Main Steam Line Isolation 1 2 Valve - Closure NA Q R

?

7. Main Steam Line Radiation - 1, 2 fd)

R

$ High S Q Drywell Pressure - High 5 R(9) 1, 2(k)

8. Q

,-=,

TABLE 4.3.1.1-1 (Continued) ,

c3

g- REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS , 23, 5 CHANNEL 7-c3 . CHANNEL- FUNCTIONAL CHANNEL OPERATIONAL i CONDITIONS FOR WHICH 'CL FUNCTIONAL UNIT CHECK

(( TEST CALIBRATION SURVEILLANCE REQUIRED $5 a 9. " Scram Discharge Volume Water 55 Level - High

a. Transmitter / Trip Unit R(9) r2 S Q 1, 2, S II)

! b. Float Switch NA Q R 1, 2, S II)

10. Turbine Stop Valve - Closure S Q R I9) 1

11. Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low S Q R(9) 1

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

$$ 13. Manual Scram NA W hA 1,2,3,4,5 Y

co (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup af ter entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be deter-mined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the previous 7 days.

(c) [ DELETED]

(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 TilERMAL POWER > 25% of RATED D(dated THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

sr (e)1 This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a g  ! calibrated flow signal.

gt (f) The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.

g (g) Calibrate trip unit at least once per 92 days.

(h)'-Vcrify acc;ured drive #1cu to bc !cc: ther er equal to c;teblished drive '?cw at the existir.g '?ct cer-if trel valvc pc;ition.

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

f} (j) Not applicable when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.

j (k) Not applicable whe. DRYWELL INTEGRITY is not required.

1 (1) Applicable with any control rod withdrawn. Not applicable to control rods removed per Specifica-tion 3.9.10.1 or 3.9.10.2.

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