ML20113H395

Proposed Tech Spec Providing Operability & Surveillance Requirements for Emergency Feedwater Sys Automatic & Manual Initiation Channels & Replacement Specs for Main Steam Line Rupture Matrix

ML20113H395
Person / Time
Site:	Crystal River
Issue date:	01/23/1985
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20113H375	List: 3F0185-08, Application for Amend to License DPR-72,changing Tech Specs to Provide Operability & Surveillance Requirements for Emergency Feedwater Sys Automatic & Manual Initiation Channels.Fee Paid ML20113H395
References
NUDOCS 8501250129
Download: ML20113H395 (10)

Text

7 TATLE 3 3-3 (Cont'd)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g

MINIMUM x

TOTAL NO.

CHANNELS CHANNELS APPLICABLE j

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 9r-3 b.

Main Feedwater and Main Steam Isolation W

I h

1.

Manual Initiation H

a.

SGA MFW Isolation 4

2####

3 1,2,3 14#

1 "

b.

SGB MFW Isolation 4

2####

3 1,2,3 14#

i c.

SGA MSL Isolation 4

2####

3 1,2,3 14#

d.

SGB MSL Isolation 4

2####

3 1,2,3 14#

2.

OTSG A or B Pressure Low 4/ Steam 2/ Steam 3/ Steam 1,2,3 5 *

• 14#

Generator Generator Generator 3.

Automatic Actuation Logic a.

SGA MFW Isolation 2

1 2

1,2,3 10 m

b.

SGB MFW Isolation 2

1 2

1,2,3 10 c.

SGA MSL Isolation 2

1 2

1,2,3 10 d.

SGB MSL Isolation 2

1 2

1,2,3 10 c.

Emergency Feedwater 1.

Manual Initiation 4

2####

3 1,2,3 14#

2.

MFW Pump Turbines A and B Control Oil Low 4

2 3

l##

14#

4 3.

OTSG A or B 4/ Steam 2/ Steam 3/ Steam 1,2,3 14#

Level Low-Low Generator Generator Generator 4.

OTSG A or B 4/ Steam 2/ Steam 3/ Steam 1,2,3 * *

• 14#

Pressure Low Generator Generator Generator 5.

All Reactor Coolant Pumps Tripped 4

2 3

1,2###

14#

6.

Automatic Actuation Logic 2

1 2

1,2,3 10 ohohoh7 D

PDR

e TABLE 3.3-3 (Continued)

TABLE NOTATION

• Trip function may be bypassed in this MODE with RCS pressure below 1700 psig. Bypass shall be automatically removed when RCS pressure exceeds 1700 psig.

• • Trip function may be bypassed in this MODE with RCS pressure below 900 psig. Bypass shall be automatically removed when RCS pressure exceeds 900 psig.

• • • Trip function may be bypassed in this MODE with steam generator pressure below 750 psig.

-Bypass shall be automatically removed when steam generator pressure exceeds 750 psig.

1. The provisions of Specification 3.0.4 are not applicable.

1. 1. Trip' automatically bypassed below 20 percent of RATED THERMAL POWER.

~ ### Trip function may be bypassed below 10 percent of RATED THERMAL POWER.

. #### Manual trip function occurs if two channels in the same train are actuated.

ACTION STATEMENTS ACTION 9 -

With the number of OPERABLE Channels one less than the Total Number of Channels operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channelis placed in 1

the tripped condition within I hour.

- ACTION 10 -

With the number of OPERABLE channels'one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one chtnnel may be bypassed for up to I hour for surveillance testing per Specification 4.3.2.1.1. -

ACTION 11 -

With less than the Minimum Channels OPERABLE, operation may continue

~

provided the containment purge and exhaust valves are maintained closed.

ACTION 12 -

With the number of OPERABLE Channels one less than the Total Numkr of Channels operation may proceed provided the inoperable channel is placed in the. bypassed condition and the minimum channels OPERABL2 required is demonstrated within I hour; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Surveillance testing per Specification 4.3.2.1.1.

~

ACTION 13 -

With the number of OPERABLE Channels one less than the Total Number of

' Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

~ ACTION 14 -

With the number of OPERABLE Channels one less than the Total Number of -

Channels operation may proceed provided the inoperable channel is placed in the tripped condition within~1 hour; one additional channel may be bypassed b

- for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Surveillance testing per Specification 4.3.2.1.1.

i CRYSTAL RIVER - UNIT 3 -

3/4 3-14

TABLE 33-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 0

3.

REACTOR BUILDING SPRAY d

a.

Reactor Building Pressure High-High f 30 psig 430 psig F

coincident with See 1.a.2, 3, 4 See 1.a.2, 3, 4 2

HPI Signal b.

- Automatic Actuation Not Applicable Not Applicable h

4.

OTHER SAFETY SYSTEMS

{

a.

Reactor Building Purge Exhaust Duct Isolation w

on High Radioactivity Gaseous Not Applicable b.

Main Feedwater and Main Steam Isolation 1.

Manual Not Applicable Not Applicable w

s*

2.

OTSG A or B y

Pressure Low 2600 psig E600 psig 3.

Automatic Actuation Logic Not Applicable Not Applicable c.

Emergency Feedwater 1.

Manual Initiation Not Applicable Not Applicable 2.

MFW Pump Turbines A and B Control Oil t 55 psig g 55 psig 3.

OTSG A or B Level Low-Low a 0 inches

r 0 inches 4.

OTSG A or B Pressure Low 2600 psig e 600 psig 5.

All Reactor Coolant Pumps Tripped Loss of 4 pumps Loss o! 4 pumps (per Table 2.2-1, //3) 6.

Automatic Actuation Logic Not Applicable Not Applicable

• Determined by the requirements of Appendix "B" Technical Specifications Section 2.4.2 -

Crystal River 3 Operating License No. DPR-72.

m TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

• 1.

Manual a.

High Pressure Injection Not Applicable

- b.

Low Pressure Injection Not Applicable c.

Reactor Building Cooling Not Applicable d.

Reactor Building Isolation Not Applicable e.

Reactor Building Spray Not Applicable f.

Reactor Building Purge Isolation Not Applicable i

g.

MFW and MSL 1 solation I

1.

Emergency Feedwater Actuation Not Applicable 2.

Feedwater Isolation Not Applicable 3.

Steam Line Isolation Not Applicable h.

Emergency Feedwater Actuation Not Applicable l

2.-

. Reactor Building Pressure-High a.

High Pressure Injection 25*

b.

Low Pressure Injection 25*

c.

Reactor Building Cooling 25*

d.

Reactor Building Isolation 60*

e.

Emergency Feedwater Actuation Not Applicable l

3.

Reactor Building Pressure High-High (with HPI signal) a.

Reactor Building Spray 56*

4.

RCS Pressure Low a.

High Pressure Injection 25*

b.

HPI Isolation 60*

c.

Emergency Feedwater Actuation Not Applicable l

5.

RCS Pressure Low-Low a.

High Pressure Injection 25*

b.

Low Pressure Injection 25*

c.

Emergency Feedwater Actuation Not Applicable l

6.

- Low Steam Generator Pressure I

a.

Feedwater Isolation 28 b.

Steam Line Isolation 5

c.

Emergency Feedwater Actuation Not Applicable l

l CRYSTAL RIVER - UNIT 3 3/4 3-17

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

• 7.

Containment Radioactivity-High a.

Reactor Building Purge Isolation 15*

8.

Ms.in Feedwater Pump Turbines A and B Control Oil Low a.

Emergency Feedwater Actuation Not Applicable 9.

OTSG A or B Level Low-Low a.

Emergency Feedwater Actuation 50*

10.

All Reactor Coolant Pumps Tripped a.

Emergency Feedwater Actuation Not Applicable i

l l

• Diesel Generator starting and sequence loading delays included.

Response time limit includes movement of valves and attainment of pump or blower discharge pressure, CRYSTAL RIVER - UNIT 3 3/4 3-17a

'T TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION SURVEILLANCE REQUIREMENTS Q

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

>r 3.

REACTOR BUILDING SPRAY h

a.

Reactor Building Pressure rn High-High coincident with f

HPI Signal S

R M(4) 1,2,3 g

b.

Automatic Actuation Logic N/A N/A M(1)(3)(3) 1,2,3 4

4.

OTHER SAFETY SYSTEMS a.

Reactor Building Purge Exhaust Duct Isolation on High Radioactivity 1.

Gaseous S

Q M

All Modes b.

Main Feedwater and Main Steam Isolation 1.

Manual Initiation

a. SGA MFW Isolation N/A N/A M

1,2,3 1.

b. SGB MFW isolation N/A N/A M

1,2,3

'o

c. SGA MSL Isolation N/A N/A M

1,2,3

d. SGB MSL Isolation N/A N/A M

1,2,3 2.

OTSG A or B Pressure Low S

R M

1,2,3 3.

Automatic Actuation Logic l

a. SGA MFW lsolation N/A N/A M(6) 1,2,3

b. SGB MFW Isolation N/A N/A M(6) 1,2,3

c. SG A MSL 1 solation N/A N/A M(6) 1,2,3

d. SGB MSL isolation N/A N/A M(6) 1,2,3 c.

Emergency Feedwater 4

1.

Manual Initiation N/A N/A M

1,2,3 2.

MFW Pump Turbine A and B Control Oil Low S

R M

1 3.

OTSG A or B Level Low-Low S

R M

1,2,3 4.

OTSG A or B Pressure Low S

R M

1,2,3 5.

All Reactor Coolant Pumps Tripped S

R M

1,2 6.

Automatic Actuation Logic N/A N/A M

1,2,3

TABLE 4.3-2 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic need only demonstrate one _ combina. tion of the three two-out-of-three logic combinations that are operable provided that a different combination is tested at each test interval, such that all three combinations will be confirmed to be operable by the time the third successive test is completed.

(2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying pressure to the appropriate side of the transmitter.

(3)

Each logic channel shall be tested at least once every other 31-day period (applies only to Test Groups HPI-3, LPI-l and LPI-2 for the duration of Fuel Cycle 5 - see (5) below).

(4) Reactor building pressure High-High signal only.

(5) Monthly CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic circuitry has been waived for all Test Groups with the exception of Test Groups HPI-3, LPI-l and LPI-2 for the duration of Fuel Cycle 5 for Crystal River Unit 3.

(6)

Tne Channel functional test need not include actuation of the end d evice.

CRYSTAL RIVER UNIT 3 3/4 3-21 Amendment No.

p TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION g

o N

MINIMUM MEASUREMENT CHANNELS gq INSTRUMENT RANGE OPERABLE rn f

1.-

Power Range Nuclear Flux 0-125 %

2 j

2.

Reactor Building Pressure 0-70 psia 2

4 3.

Source Range Nuclear Flux 10-1 to 106 cps 2

4.

Reactor Coolant Outlet Temperature 5200 F - 6200 F 2 per loop 5.

Reactor Coolant Total Flow 0-160 x 106 lb./hr.

I 6.

RC Loop Pressure 0-2503 psig 2

0- 600 psig i

1700-2500 psig 2

7.

Pressuiizer Level 0-320 inches 2

3.

Steam Generator Outlet Pressure 0-1200 psig 2/ steam generator

{

9.

Steam Generator Operating Range Level 0-100 %

2/ steam generator l

10.

Borated Water Storage Tank Level 0-50 feet 2

11.

Startup Feedwater Flow 0-1.5x106 lb./hr.

2 12.

Reactor Coolant System Subcooling Margin Monitor

-635F0 to +663Fo 1

13.

PORY Position Indicator (Primary Detector)

N/A i

14.

PORY Position Indicator (Backup Detector)

N/A N/A 15.

PORV Block Valve Position Indicator N/A N/A 16.

Safety Valve Position Indicator (Primary Detector)

N/A 1/ Valve 17.

Safety Valve Position Indicator (Backup Detector)

N/A N/A 13.

Emergency Feedwater Flow 0-350 gpm 2/ steam generator

r.

-3 w

TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ox j

CHANNEL CHANNEL g

INSTRUMENT CHECK CALIBRATION r-m Q

l.

Power Range Nuclear Flux M

Q*

~ rn M

2.

Reactor Building Pressure M

R b

3.

Source Range Nuclear Flux M

R*

2q 4.

Reactor Coolant Outlet Temperature M

R 5.

Reactor Coolant Total Flow Rate M

R 6.

RC Loop Pressure M

R 7.

Pressurizer Level M

R 8.

Steam Generator Outlet Pressure M

R mD 9.

Steam Generator Level M

R 10.

Borated Water Storage Tank Level M

R I1.

Startup Feedwater Flow Rate M

R 12.

Reactor Coolant System Subcooling Margin Monitor M

R 13.

PORY Position Indicator (Primary Detector)

M R

14.

PORV Position Indicator (Backup Detector)

M R

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

13.

Emergency Feedwater Flow M

R

• Neutron detectors may be excluded from CHANNEL CALIBRATION

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying that each valve (manual, power operated, or automatic) in the l

flow path is in its correct position, b.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on an emergency feedwater actuation test signal.

2.

Verifying that the steam turbine driven pump and the motor driven pump are capable of starting automatically:

I a.

Upon receipt of an emergency feedwater actuation OTSG A or B level low-low test signal, and b.

Upon receipt of an emergency feedwater actuation main feedwater pump turbines A and B control oil low test signal, and c.

Upon receipt of an emergency feedwater actuation OTSG A or B low pressure test signal, and d.

Upon receipt of an emergency feedwater actuation all reactor coolant pumps tripped test signal.

• c.

Prior to startup after any refueling outage or other cold shutdown of longer than 30 days, verify the operability of an emergency feedwater flow path by utilizing an Emergency Feedwater Pump to pump water from the emergency feedwater supply tank to the steam generators.

• This surveillance requirement becomes effective after completion of the new emergency feedwater supply tank.

- CRYSTAL RIVER - UNIT 3 3/47-5

.