ML20077G582

Proposed Tech Specs Re Reactor Protection Sys Instrumentation Surveillance Requirements

ML20077G582
Person / Time
Site:	Crystal River
Issue date:	06/25/1991
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20077G580	List: 3F0691-10, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 188,to Request one-time Extension to Surveillance Interval for Performing Channel Calibr of Reactor Coolant Outlet Resistance Temp Detectors ML20077G582
References
NUDOCS 9107020038
Download: ML20077G582 (4)

Text

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( S TABLE 4.3-1 88 pg REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8

us 83 oo CHANNEL NODES IN WHICH 5 388 CHANNFL CHANNEL FUNCTIONAL SURVEILLANCE

{ ggo INSTRUMENT CHECK CALIBRATION TEST REQUIRED

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i 1. Manual Reactor Trip N.A. N.A.

= S/U(1) . N.A.

' 2. Nuclear Overpower S D(2) and Q(7) M 1,2 E

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l 3. RCS Outlet Temperature--High S R(10) M 1,2.

4. Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE S(4) M(3) and Q(7,8) M 1,2

5. RCS Pressure--Low S R M 1,2

6. RCS. Pressure--High S R M I,2 y 7. Variable Low RCS Pressure S R M 1,2 a- ,

8. Reactor Containment Pressure--High S R M 1,2

9. Intermediate Range, Neutron Flux and Rate S R(7) S/U(1)(5) 1,2 and *

10. Source Range, Neutron Flux and Rate S R(7) S/U(1)(5) 2,3,4 and 5 t

11. Control Rod Drive Trip Breaker N.A. N.A. M and S/U(1) 1,2 and *

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12. Reactor Trip Module N.A. N.A. M 1,2 and *

! 13 [ Shutdown Bypass RCS Pressure--High S R M 2**,3**,4**,5**

! $ 4.- Reactor Coolant Pump Power Monitors j g S R(9) M 1,2

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B 15. Anticipatory Reactor Trip - Main Turbine S R M 1

16. Anticipatory Reactor Trip - Both Main Feedwater Pumps S R M 1

~l TABLE 4.3-1 (ContinuedL_

M0TATION With any control rod drive trip breaker closed.

When Shutdown Bypass is actuated.

(1) -

If not performed in previous 7 days.

(2) -

Heat balance only, above 15% of RAlc0 THERMAL POWER.

(3) -

When THERMAL POWER (TP) is above 30% of RATED THERMAL POWER (RTP) compare out-of core measured AXIAL POWER IMBALANCE (API,) to incore measured AXIAL POWER IMBALANCE (api g

) as follows:

RTP (APlo APII ) - Imbalance Error IP Recalibrate if the absolute value of the imbalance Error is equal to or greater than 2.5%.

(4) -

AXIAL POWER IMBALANCE and loop flow indications only.

(5) -

Verify at least one decaae overlap if not verified in previous 7 days.

(6) -

Each train tested every other month.

(7) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(8) -

Flow rate measurement sensors may be excluded from CHANNEL CAllBRATION.

However, each flow measurement sensor shall be calibrated at least once per 18 months.

(9) -

Current and voltage sensors may be excluded from CHANNEL CAllBRATION.

l (10) - The CHANNEL CALIBRATION requirement for this function does not have to be met until the end of the cycle 8 refueling outage.

1 CRYSTAL RIVER - UNIT 3 3/4 3-8 Amendment-No.

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TABLE 4.3.6 REMOTE SHUTDOWN NOMITORING INSTRUNQUATION SURVEILLANCE REQUIRENENTS 2

5:n r- CHAMEL CHANNEL

= INSTRtMDIT CHECK CALISRATION M

= '

. 1. Reactor Trip Breaker Indication M N.A.

E l 2. Reactor Coolant . Temperature-Th M R(1)

3. Reactor Coolant Pressure M R

4. Pressurizer Level M R

5. Steam Generator Level M R

6. Steam Generator Pressure M R

.w 1 .7. Decay Heat Removal M R y Temperature-M 8. Motor Driven Emergency M R Feedwater Pressure

9. Nuclear Services Closed M R Cycle Cooling Pumps Discharge Pressure

10. . Nuclear Services Closed M R g Cycle Ceoling Cooler

,m Outlet Temperature

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N l (1) The CHANNEL CALIBRATION requirement for this function does not have to be met until the end of the cycle 8 i refueling outage.

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! TABLE 4.3-7

POST-ACCIDENT MONITORING INSTRURENTATION SURVEILLANCE REQUIREMENTS

c. CHANNEL CHAf5 GEL 5 INSTRUMENT _ CHFCK CALIBRATION i g .

j!: 1. Power Range Nuclear Flux M Q*  !

= 2. Reactor' Building Pressure M R  !

i 15i 3. Source Range Nuclear Flux M R*

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, l 4. Reactor Coolant Outlet Temperature M R(1) g 5. Reactor Coolant Total Flow Rate M R Q 6. RC Loop Pressure M R w 7. Pressurizer Level M R ,

8. Steam Generator Outlet Pressure M R ,

9. Steam Generator Level M R

10. Borated Water Storage Tank Level M R m 11. Startup Feedwater Flow Rate M R t i 12. Reactor Coolant System Subcooling Margin Monitor M R Y 13. PORV Position Indicator (Primary Detector) M R i Y 14. PORV Position Indicator (Backup Detector) M R 1

15. PORY Block Valve Position Indicator M R  !

16. .. Safety Valve Position Indicator (Primary Detector) M R

17. Safety Valve Position Indicator (Backup Detector) M R I

. 18. Emergency Feedwater Flow M R 19.. Reactor Building Flood Level M R l i

20. Core Exit Thermocouples M R l

, 21. Reactor Vessel Hot Leg level NA R l 22. Reactor Vessel Head Level NA R 5 I 1 E

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• Neutron detectors may be excluded from CHANNEL CALIBRATION 4

l .- (1) The CHANNEL CALIBRATION Requirement for this function does not have to be met until the end of the cycle 8 refueling outage. ,

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