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

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

{ ggo INSTRUMENT CHECK CALIBRATION TEST REQUIRED

-o

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

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 i

5.

RCS Pressure--Low S

R M

1,2 I

f 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

• l M

1,2 and

• 12.

Reactor Trip Module N.A.

N.A.

13 [

Shutdown Bypass RCS Pressure--High S

R M

2**,3**,4**,5**

f j

g 4.-

Reactor Coolant Pump Power Monitors S

R(9)

M 1,2

}

B 15.

Anticipatory Reactor Trip - Main Turbine S

R M

1 f

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 ) as follows:

g RTP (APlo API )

- Imbalance Error I

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

.w1

.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

EN 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.

l l

.j a

TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRURENTATION SURVEILLANCE REQUIREMENTS c.

CHANNEL CHAf5 GEL 5

INSTRUMENT _

CHFCK CALIBRATION

{

g i

j!:

1.

Power Range Nuclear Flux M

Q*

=

2.

Reactor' Building Pressure M

R i

15i 3.

Source Range Nuclear Flux M

R*

m 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 f

9.

Steam Generator Level M

R 10.

Borated Water Storage Tank Level M

R l

11.

Startup Feedwater Flow Rate M

R t

m f

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

f 1

15.

PORY Block Valve Position Indicator M

R l

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 l

22.

Reactor Vessel Head Level NA R

5 I

E 1

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 l

refueling outage.

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