Text

Proposed Tech Specs Re Reactor Trip Sys Instrumentation Surveillance Requirements & ESFAS Instrumentation
	ML20029B207
Person / Time
Site:	Wolf Creek
Issue date:	03/01/1991
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20029B206	List: ML20029B205; ML20029B207;
References
	NUDOCS 9103060199
	Download: ML20029B207 (23)
	v • d • e

_ _ _ _ _ _ _ _ - _ _

Attachment IV to ET 91 0047 Page 1 of 23 ATTACIMENT IV PROPOSED TECHNICAL SPECIFICATION CHANGES 9103060199 910301 PDR ADOCK 05000482 P PDR

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION g

MINIMUM [h oo TOTAL NO. CHANNELS CHANNELS APPLICABLE G ACTION O TO TRIP OPERABLE MODES -

?

^

FUNCTIONAL UNIT OF CHANNELS ok

11. Pressurizer Water Level-fligh 3 2 2 1 6# I [A-E ,

Z 12. Reactor Loolant Flow - Low O e*

2/ loop in 6# I

a. Single Loop (Above F-8) 3/ loop 2/ loop in 1 ,,,

each oper- l any oper-ating loop ating loop 3l E) '

b. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop in 1 6# l 2

'I two oper- each oper-below P-8) ating loops ating loop

13. Steam Generator Water 4/stm. gen. 2/stm. gen. 3/stm. gen. in in any oper .each oper-1, 2 h(1) l Level-Low-Low ating stm. ating stm.

Y gen. gen.

14. Undervoltage-Reactor Coolant 1 6#

4-2/ bus 2-1/ bus 3 Pumps

15. Underfrequency-Reactor Coolant 1 6#

4-2/ bus 2-1/ bus 3 Pumps

16. Turbine Trip 2 1 6# l 3 2

a. Low Fluid Oil Pressure 4 1 1 11#

b. Turbine Stop Va;ve Closure 4 E

g 17. Safety Injection Input l

R from ESF 2 1 2 1, 2 h

3 O

l

r 5

t TABLE 3.3-1 (Continued) 6 REACTOR TRIP SYSTEM INSTRIMENTATION

. g >,l o

ee R MINIMUM -S TOTAL NO. CilANNELS CilANNELS - APPLICABLE "I E FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION %$

18. Reactor Trip System Interlocks

e

- a. Intermediate Range-Neutron Flux, P-6 2 1 2 2## 8 0

b. Low Power Reactor e'~

Trips Block, P-7 P-10 Input 4 2 3 1 8 8

-or O P-13 Input 2 1 2 1 8 w c. Power Range Neutron 1 Flux, P-8 4 2 3 1 8 w

I d. Power Range Neutron Flux, P-9 4 2 3 1 8

e. Power Range Neutron Flux, P-10 4 2 3 1, 2 8

f. Turbine Impulse Chamber Pressure, P-13 2 1 2 1 8

19. Reactor Trip Breakers 2 1- 2 1, 2 9. 12 l 2 1 2 3* , 4 * , 5* 10

20. Automatic Trip and Interlock Logic- 2 1 2 1, 2

& 2 1 2 3*, 4*, 5* @

10 o

O 4.

. ,' Attachment IV to ET 91-0047 Pag,e 4 of 23 TABLE 3.3-1 (Continued)

TABLE NOTATIONS

0nly if the Reactor Trip System breakers hap. pen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.

- The boron dilution flux doubling signal may be blocked during reactor startup in accordance with normal operating procedures.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below the P-10 (Low Set oi.nj,_fgwer n Rante Neutron Flux Interlock) Setpoint.

(1)The applicable MODES -qd 3C_TICO%nhM)for these channels noted in Table 3.3-3 are more restrictive and therefore applicable.

ACTION STATEMENTS ACTION l'- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels on'e less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped ccndition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; l

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i for surveillance testing of other channels per Specification 4.3.1.1; and w

c. Either, THERFAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Fluy Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once f.er 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTICH 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERFAL POWER level:

a. Below the P-6 (Intermediate Range Neutron Flux Interlo^ )

Setpoint, restore the inoperabit. channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or

b. Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restoie the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERFAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

WOLF CREEK - UNIT 1 3/4 3-5 Amendment No.12

~

. Attachment'lV to ET 91-0047- -I Page 5 of 23

~

m L ,

TABLE 3.3-11 (Continued) -

ACTION STATEMENTS (Continued)

~

ACTION 5 a. Withithe number of OPERABLE channels one less than the Mini-m'um Channels OPERABLE requirement, restore the inoperable.

channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reac-i: tor Trip Breakers, suspend all operations-involving positive reactivity changes-and verify valves:BG-V178 and BG-V601 are closed and secured'in position.within the next hour. )

b. With no channels OPERABLE, open the Reactor Trip Breakers, -

suspend all operations involving positive reactivity changes-and verify compliance with the SHUTDOWN MARGIN requirements-of Specification 3.1.1.1 or 3.1.1.2,.as-applicable, within I hour and.every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereaf ter, and verify valves

'BG-V178 and BG-V601 are closed and secured in position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured,in position every 14 days.

ACTION'6 - With the number of OPERABLE channels one less than the Total Number of Cnannels, STARTUP and/or POWER OPERATION may proceed provided the following conditions-are satisfied:

a. The inoperable channel is placed in,the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per (M Specification 4.3.1.1.

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive

_ __ _ ._ . annunciator window (s) that the interlock it. in its required state keactor Trip Breakegfor the existino plant condition, or apply Lpecification 3.0.3.

-~

ECTION 9 - With the number of OPERABLE Ihrneh one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within r.) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, onethennel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the-b) other thanne' is OPERABLE.

ACTION' With the number of OPERABLE channels-one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the-Reactor trip breakers within the next hour.

. . ACTION 11 With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within-Fhour. 6 _

- ACTION 12 - With one of the diverse trip features -(undervoltage or shunt trip attachment) inoperable, restore it to OPEP.ABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 9.

The breaker shall not be bypassed while one cf the diverse trip features is inoperable except for the time required for perform-ing maintenance to restore the breaker to OPERABLE status.

WOLF CREEK - UNIT 1 3/4 3-6 Amendment No.12,26

.m_ . _ _

_ _- _ . _ . - - _ _ _ _ - m ,

Attachment IV to ET 91-0047 Page 6 of 23 Insert A ACTION 7 With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

i

s TABLE 4.3-1 6 ' REACTOR TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIREMENTS-

~

o>

'E G c,

R TRIP . *E m ANALOG CllANNEL ACTUATING MODES FOR "E DEVICE WHICH 2,8 FUNCTIONAL UNIT Cl!ANNEL- CllANNEL CIIECK OPERATIONAL CALIBRATION . TEST OPERATIONAL ~ ACTUATION TEST SURVEILLANCE m"'

LOGIC TEST 15 REQUIRCD "2

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

~r

] N.A. R(11) N.A. 1, 2, 3*, 4*, 5* i o m

2. Power Range, Neutron Flux

a. High Setpoint S - D(2, 4) Q{-14}- N.A. N.A. 1, 2

[

y M(3. 4) o Q(4,6) 2 R(4. 5) -"

b. Low Setpoint S R(4) S/U(1) N.A. N.A. l###, 2 w 3. Power Range, Neutron Flux, N.A. R(4). Q(itt N. A. N.A. 1, 2 1 High Positive Rate

, w i

a 4. Power Range, Meutron Flux, N.A. R(4) Q(44-). N.A. N. A. 1, 2 liigh Negative Rate

5. Intermediate. Range, S R(4, 5) S/U(1) N.A. N.A. 1###, 2 Neutron Flux

6. Source Range, Neutron Flux 5 R(4,5,12), S/U(1) 443 N.A. N.A. 2##, 3, 4, 5

7. Overtemperature AT S R(13) Q(-14t N.A. N.A. 1, 2 3" 8. Overpower AT S R N.A. N.A. 1, 2.

( Q(443-i 3 (

l g. 9. Pressurizer Pressure-Low S R l Q(-l+}- N.A. N.A. 1 l $

I

10. Pressurizer Pressure-liigh 5 R Q(-1+}- N.A. N.A. 1, 2 E

11. Pressurizer Water level-liigh 5 R Q(44}. N.A. N.A. I U

l i, - 12. Reactor Coolant Flow-Low , , 5 R Q N.A. N.A. I V( @ ?

i

---w. a.~m - 1 _ w -- - , - . . + . . . . . - . .

l TABLE 4.3-1 (Continued) i g REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP 2I 3I'

~S ANALOG ACTUATING MODES FOR 5$E7 5 CHANNEL: DEVICE WHICH co E}

CHANNEL CHANNEL DPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE o@

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED ~' S -

E . E$ -.

El 13. Steam Generator Water Level- S R Qf14,15) N.A. N.A. 1, 2 I w Low-Low E; 1 m

-d

14. Undervoltage - Reactor N.A. R N.A. Qf14F N.A. 1 l Coolant Pumps J $?

h E> .

15. Underfrequency - Reactor N.A. R N.A. i Qtl43- N.A. 1 l j?

'd Coolant Pumps i

u, 16. Turbine Trip 32 a. Low Fluid Oil Pressure H.A. R N.A. S/U(1, 10) N.A. 1 u, b. Turbine Stop Valve N.A. R N.A. S/U(1, 10) N.A. 1 p'; Closure

17. Safety Injection Input from N.A. N.A. N.A. R N.A. 1, 2 ESF

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 N.A. R(4) R N.A. N.A. 2## t

b. Power Range Neutron Flux, P-8 N.A. R(4) R N.d. N.A. I

c. Power Range Neutron Flux, P-9 N.A. R(4) R N.A. N.A. 1 S

a M

a

.??

[

. . Attachment IV to ET 9150470 Ppge 9 of 23 4

0 1ABLE 4.3-1 (Continued)

TABLE NOTATIONS (13) CHANNEL CAllBRATION shall include the RTD bypass loops flew rate.

(14) E4c.Lchannsi-#aM-

H, ed-* t --Ita tt--every-92-d e ynn-e4HG6f*N BAtl's. DELElt (15)Table The 6ef.;il1$ce _f rc;;utr.;[sctive M are more rest andir27FF)M00ES

, therefore, applicable. specified for these (16) The TRIP ACTUATING DEVICE OPERATIONAL TES' shail independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(17) local manual shunt trip prior to placing breaker in service.

(18) Automatic undervoltage trip.

WOLF. CREEK - UNIT 1 3/4 3-12a Amendment No.12,26

TABLE 3.3-3 -

~-

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION r-

. MINIMUf4 y3 Q TOTAL NO. CHANNELS CHANNELS APPLICABLE o, g

? FUNCTIONAL UNIT OF' CHANNELS TO TRIP OPERABLE MODES ACTION _2 >

1. Safety Injection, (Reactor oM Trip, Phase "A" Isolation, og c '"

Feedwr.ter Isolation, Compo-Zi nent Cooling Water, Turbine W

~

Trip, Auxiliary Feedwater- ,

o Motor-Driven Pump Emergency r, Diesel Generator Operation, "

Containment Cooling, and Essential Service Water y

o Operation) 2 w

a. Manual Initiation 2 1 2 1,2,3,4 18 u, b. Automatic Actuation 2 1 2 1,2,3,4 14 1 Logic and Actuation u, Relays (SSPS) h c. Containment 3 2 2 1,2,3 -IS^- 28*

Pressure-High-1

d. Pressurizer 4 2 3 1,2,3 -198-Pressure - Low

e. Steam Line Pressure- 3/ steam line 2/ steam line 2/ steam line 1, 2, 3 -15*-

Low any steam line

2. Containment Spray

a. Manual Initiation 2 pair 1 pair 2 pair 1, 2, 3, 4 18 operated simul-taneously

b. Automatic Actuation 2 1 2 1,2,3,4 14 !

Logic and Actuation Relays (SSPS)

c. Containment Pressure- 4 2 3 1, 2, 3 16 High-3

TABLE 3.3-3 (Continued) -

r ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

e .

' ~

MINIMUM 9 TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT '0F CHANNELS TO TRIP -OPERABLE MODES ACTION Jg.

{ e c+

. 4. Steam Line Isolation *g c-5 -"5 4

a. Manual Initiation ag m e.

1) Individual 1/ steam line 1/ steam line 1/ operating 1, 2, 3 23 =

steam line

2) System 2 1 2 1,2,3 22 E m

b. Automatic Actuation 2 1 2 1,2,3 29 Logic and Actuation 3 l Relays (SSPS) g'l s ,

c. Containment Pressure - 3 2 2 1,2,3 " I w

-E*-O28*

1 High-2

d. Steam Lir.e 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# -15*-

Pressure-Low any steam line

e. Steam Line Pressure- 3/ steam line 2/ steam line 2/ steam line 3## M *- 28*

Negative Rate-High any steam line S. Turbine Trip &

Feedwater ation

a. Automatic Actuation 2 1 2 1, 2 27 Logic and Actuation Relay (SSPS)

b. Steam Generator 4/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2 -198 28*

Water Level- in any oper- in each oper-High-High ating stm. gen. ating stm.

gen.

c. Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

~ -___________\

l )-

i ..

~~

TABLE 3.3-3 (Continued) .

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 2 r>

,-. er m arp D n MINIMUM _. Q. l g TOTAL NO. CHANNELS CHANNELS APPLICABLE N@ .

m FUNCTIONAL UNIT TO TRIP OF CHANNELS OPERABLE MODES ACTION Q3 1 z

6. Auxiliary Feedwater W^ e 3 a. Manual Initiation 3(1/ pump) 1/ pump 1/ pump -1, 2, 3 24 o- i m

b. Automatic Actuation Logic 2 1 2 1,2,3 and Actuation Relays (SSPS) ] .. '

7 o.

c. Automatic Actuation 2 1 2 1, 2, 3 21 2 Logic and Actuation " '

Relays..(BOP ESFAS) [

d. Stm. Gen. Water ievel-

, Low-Low x

^

1) Start Motor-

[ Driven Pumps 4/stm. gen. 2/stm. gen. 3/stni. gen. 1, 2, 3 -19* 28

w in any opera- in each ting sim. gen. operating sim. gen.

2) Start Turbine-Driven Pump 4/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2, 3 -1&& 28*

in any in each 2 operating operating ,

stm. gen. stm. gen.

e. Safety Injection - Start Motor-Driven Pumps .See Item 1. abov: for all Safety Injection initiating functions and requirements.

f. Less-of-Of fsite Power -

Start Turbine-Driven Pump 2 1 2 1,2,3 22

TABLE 3.3-3 (Continued)

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

q . . . .

n MINIMUM g TOTAL NO. CHANNELS CHANNELS APPLICABLE m FUNCTIONAL UNIT g OF CHANNELS TO TRIP OPERABLE MODES ACTION gg i

6. Auxiliary Feedwater (Continued)

$ g. '." rip of All Main w Feedwater Pumps - % c+

~ Start Motor- tv -

Driven Pumps ***

4-(2/ pump)** 2-(1/ pump in same 3 1, 2 19

"[. o.

separation) m e

h. Auxiliary Feed- u>

water Pump Suction -^

Pressure-Low g' (Transfer to ESW) 3 2 2 1,2,3 15* O M 7. Automatic Switchover to

[ Containment Sump b

a. Autorratic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation Relays (SSPS)

b. RWST Level - Low-Low 4 2 3 1,2,3,4 16 Coincident With Safety Injection See Item 1. above for Safety Injc; tion initiating functions and requirements.

8. Loss of Power

a. 4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 19*

-Loss of Voltage l b. 4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 19*

-Grid Degraded Voltage l

l l

2 [AttachmentIVtoET 91-0047' l

, _ P, age 1,4 of 23 !

1 TABLE 3.3-3 (Continued)

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

The provisions of Specification 3.0.4 are not applicable.

- Cf.e in Separation Group 1 and one in Separation Group 4.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum

~ Channels OPERABLE requirement, be in at least HOT STANDBY 12 within4-hours and in COLD SHUTDOWN within the following e-30 hours; however, one channel may be bypassed 'or up to f hours 4 for surveillance testing per Specification 4.3.;.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less , nan 'he Total Number of Channels, operation may proceed unt~1 per/ormance of the next required ANALOG CHANNEL OPERATIONAL 'EST ,. ided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 - 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 bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up toje-hours for surveillance testing per- -

Specification 4.3.2.1. /

-ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDSY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

' ION 19 - With the number of OPERABLE channels one less than the Total s Number of Channels, STARTUP and/or POWER OPERATION may proceeti provided the following conditions are satisfied,

a. The inoperable channel is placed in the tripped condition within I hour, and WOLF CREEK - UNIT 1 3/4 3-20

L

, , [ Attachment IV to ET 91-0047 P, age 15 of 23 4

TABLE 3.3 3 (Continued)

ACTION STATEMENTS (Continueo;

b. The Minimum Channels OPERABLt: requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With less than the Minimum Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the action required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION required by-Specification 3.7.1.2.

ACTION 25 - With the number of OPERABLE channels one lets than the Minimum Channels OPERABLE requirement, declare the affected diesel generator and off-site power source inoperable and take the ACTIOW required by Specification 3.b.1.1.

ACTICN 26 - With the number of CoERABLE channels one less than the Minimum Channels OPERABLE regylrement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or initiate and maintain operation of the Control Room Etaergency Ventilat'on System.

During operation in Hooi 5 .nd 5, the provisions of Specification 3.0.4 are nec applicable.

ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY O12 within4-hours; however, one channel may be bypassed for up Q) --

to+ hours for surveillance testing per Specification 4.3.2.1 provided the other chaanel is OPERABLE.

j I

t -

I WOLF CREEK - UNIT 1 3/4 3-21 Amendment No.37

e e s . e Attachment IV to ET 91-0047 Page 16 of 23 Insert B

- - The de-energization of one train of BOP ESPAS actuation logic and actuation relays renders two of the four channels inoperable. Action Statement 21 applies to both Functional Units 6.c and 6.g in this ca.e.

Insert C ACTION 28 - With the number of OPERABLE channels one less than the Total Namber of Channels. STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The minimum channels OPERABLE requirement is met however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

Insert D ACTION 29 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is operable.

l

[

~

TABLE 4.3-2 .

sc ENGINEERED SAFETY FEATURES ACVUATION SYSTED INSTRUMENTATION J

$URVEllLANCE REQUIREMENTS .

t

{ .

O TRIP 2 ANALOG ACTUATING MODES w

'

CHANNEL DEVICE MASTER SLAVE FOR WHICH .3 ;; ,

CHANNEL CHANNEL OPERATIOMAL OPERATIONAL ACTUATIGN RELAY RELAY sun ilLLANCE *g '

E CHECK CALIBRATION TE5T TEST LOGIC TEST TEST TEST 15 REQUIRED

j. FJUNCTIONAL UNIT

1. Safety Injection (Reactor RS Trip, Phase "A" Isolation, n3 ,_, l w< ;

Feedwater Isolation, j-

Turbine Trip, Component g.

Cooling Water, Auxiliary n j- Feedwater-Motor-Drived --* r e

Pump. Emergency Diesel

~

s Generator Operation, Containment Cooling, and 8 l

R Essential Service Water .

O<

Operation)

N.A. N. A. N. A.. N. A. 1, 2, 3, 4

a. Manual Initiation N.A. N.A. R l

b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q(3) i, x .4 j Logic and Actuation Relays (55PS) I

c. Containment Pressure- 5 R 'i. A. N.A. N.A. N.A. 1, 2, 3 High-1

d. Pressurizer Pressure- 5 R .

Q N.A. N.A. N.A. N.A. 1, 2, 3 l' Low .

5 -M- N.A. N.A. N.A. N.A. 1, 2, 3

c. Steam Line Pressure- R Low

! 2. Containment Spray

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 f N.A. N.A. N.A. Ql) M(1) Q(3) 1, 2, 3, 4

b. Automatic Actuation N.A.

I.ogic and Actuation j kelays (55PS)

Containment Pressure- 5 N.A. N.A. N.A. N.A. I, 2, 3

c. R Q High-3

1 l ,

- i -

c;gO C.O.

h 3,2 y_ "' s E

CD 4 NE 4 4 4 4 4 4 HAR , , , , , , ,

CLI I LU 3 3 3 3 3 3 3 3 .

HI Q s 5 WEE , , , , , , , , t E VR 2 2 2 2 2 2 2 2 n 1 DRR , , , , ,

e e

OOU5 , ,

s r

MFS1 1 I 1 1 I I I I c t r n i e u q

EY m e

VAT . ) e . . . ) .

ALS 3 r 3 R LEE A. ( i A. A. A. ( A.

u e 5RT N Q N Q N N Q N q c e n R R

) )

a EY . ) . . . l TAT 1 e A.

1 A. A..

1 A.

l 5LS A. ( c ( ( i AEE N M n P M N NM N e MRT a v l r N l u O T i S I NS e T OE v n A I T r ) o T T u 2 i N AC S ( t T UI . ) . ) . . ) ) a M TG 1 n 1 1 1 l U CO A. ( o A. ( A. A. ( ( o R AL NM i NM N NM M s T ,

t I S c N L e I A j "A G N n "

M N O . I . . . .

E s I I A. y A. A. A.

A e

). T i TET s d S N ACA R N t 9 N N R N N. a e Y E PUI RT e h u S M I T VES f P n E RCEPE a i N R T ADOT s l t O I l n I U l a o T Q L l C A E A a r

( I I R N o T O r f 2 C L LI o

- A C GET f e 3 N ONA v S A LNRT . . e . . . . . o

4. E t AAES '

v b R t NHPE A. A. o A. A. - A. A. A. a E U I ACOT N N b N N t N N N t-L T E a .

R A V S E R N . a.

! F U O 1 3

$ I Y T m m T LA e e E ER t t F NB I I A NI . . . . .

S AL e A.

A.

t e HA A. A. e A. A. . e D CC N N S N. N R N N N S E

R E L E E N NK I NC . . . . . .

G AE n N HH A. A. A. A. o A. A. A.

E CC N N N N 5 i N N N t

nn nn a nn nn n oo oo l oo oo) o n ii n ii o n ii iiS i o tt n o tt s o tt ttA t n i aa o n i aa 3 I i aa aaF a o t uu i o t uu - t uu uu5 l n i a tt) t i a tt) h e a g g tt) ttE o o t i ccS c t i ccS i cc5 cc s i a t AAP e a t AAP ti r t AAP AAP I t l i 5 j l i 5 nH u i 5 O a o n cd5 n o n cd5 e- P n cd5 cdB l s I i n( I s I i n( me I i n( in( "A o I t a i t a nr t t a t a "

a a mcy as e a mcy mcya e s a s l s y l a s i u n l s I " a mcy t "

T A u oiat e B u oia t s m u oia oia s I t " n gl f ' n t gl ne n n t cl t gl a N n a uoe a a uoe or i a uoe uoe h t e e M ALR S e s

M ALR CP a M ALRt ALR P m s L n a a n A i h ) ) ) h ) ) ) o ) ) ) )

N a P 1 2 3 P I 2 3 C 1 2 3 4 O t I n T o . . .

C C a b c N

F 3 r ( 9 5 ]' g"~ " swh llIli!l flfljIlI ll(ll l(l ll ll !f i ll

O TABLE 4.3-2 (Continocd) ,

ENGINEERED SAFETY FEATURES r.CTUATION SYSTEM INSTRIMENTATION t SURVEILLANCE REQUiFEMENTS ,

G TRIP g ACTUATING MODE 5 Z

ANALOG DEVICE MASTER SLAVE FOR WHICH ,2N CHANNEL

^

OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE WC

' CHANNEL CHANNEL 9 TEST tOGIC TEST TEST TEST , IS REQfilPED CALIBRATION TEST g FUNCTIONAL UNIT CHECK N

oa y

4. Steam Line Isolation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3 y

a. Manual initiation e N.A. N.A. M(1) M(1) Q 1,2,3 o

b. Automatic Actuation N. A. N.A.

Logic and Actuation C Relays (SSP 5)

R -M- N.A. N.A. N.A. N.A. 1, 2, 3 $

c. Containment Pressure- 5 High-2 6

d. Steam Line Pressure- 5 R r.

Q N.A. N.A. N.A. N.A. 1, 2, 3 h Q* Low

-M- N.A. N.A. N.A. N.A. 3 ,

c. Steam Line Pressure- 5 R 3

& Negative Rate-liigh

5. Turbine Trip and Feedwater Isolation N.A. M(1) Q(3) I, 2 Automatic Actuat;on N.A. N.A. N.A. M(1) a.

Logic and Actuation l Relay (55P5)

-M- N.A. N.A. N.A. N.A. I, 2

b. Stean Generator Water 5 R l

Level-High-High 1

c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirceents.

6. Auxiliary Feedwater N.A. R N.A. N.A. N.A. I, 2, 3 1

a. Manual Initiation N.A. N.A.

1, 2, 3

b. Automatic Actuation N.A. N.A. N.A. N.A. Pil) M(I) Q Logic and Actuation Relays (55P5)

I I

l l

i e

TABLE 4.3-2 (Continm d) .

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g $URVEILLANCE REQUIREMENIS q

TRIP O ACTUATING MODE 5 ro9-ANALOG

?

" CHANNEL DEVICE MASTER SLAVE FOR kHICH M

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE RS TEST LOGIC TEST TEST TEST Is RFQt;IRFD _

CHECK CALIBRATION TEST w<

F F34CTIONAL UNIT

,i g

,_. 6. Auxiliary Feedwater (Continued) m N.A. N.A. M(1)(2) N.A. N.A. 1, 2, 3 "

c. Automatic Actuation N.A. N.A.

logic and Actuation 'S Relays (BOP ESFAS) 5 R 4 N.A. N.A. N.A. N.A. 1, 2, 3 h

d. Steam Generator Water 0 level-Low-low

e. Safety Injection See Item 1 above for all Safety Injection Surveillance Requirect.ts N.A. M N.A. N. A. N.A. 1, 2, 3

f. L9ss-Offsite Power N.A. R s

N.A R N.A. N.A. N.A. 1, 2

g. Trip of All Main N.A. N.A.

w

, Feedwater Put::ps j

M N.A. N.A. N.A. N.A. 1, 2, 3

h. Auxiliary Feedwater 5 R Pump Suction Pressure-Low

7. Automatic'Switchover to Containment Sump M(1) Q(3) 1, 2, 3, 4 N.A. N.A. N.A. N. A. N(1)

a. Automatic Actuation Logic and Actuation Relays (SSPS)

N. A. N.A. N. A. N.A. 1, 2, 3, 4 Rh'ST Level - Low-Low 5 R b.

Coincident With see Item 1. above for all Safety Injection Surveillance Requirceent s.

Safety Jnjection S. Loss of Power N.A. 1, 2, 3, 4 N.A. M N.A. N.A.

a. 4 kV Undervoltage - N.A. R Loss of Voltage M N.A. N.A. N.A. I, 2, 3, 4 N.A. R N.A.

b. 4 kV Undervoltage -

Grid Degraded Voltage i _______

O TABLE 4.3-2(Continue ( ,

r ENGINEERED SAFETY FEATURES ACTUAlION SYSTEM INSTRIMENTATION **

=

{ SURVLILLANCE REQUIREMENTS 0 TRIP

?*

ANALOG ACTUATING MODES g3 CHANNEL DEVICE MASTER SLAVE FOR WICH to &

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE *E l E FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST 15 REQUIRED 25

9. Control Room Isolation os E$2

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A N.A. All y ,

b. Automatic Actuation N. A. N.A. N.A. N.A. M(1) M(1) Q(3) 1, 2, 3, 4 o Logic and Actuation r, Relays (55PS)

c. Automatic Actuacion N.A. N.A. N.A. N.A. M(1)(2) N.A. N.A. All 3 Logic and Actuation E, Relays (B0P ESFAS) g R u

d. Phase "A" Isolation See Iten: 3.a. above for all Phase "A" Isolation Surveillance Rec;srements. N Y 10. Solid-State Load Sequencer N.A. N.A. N.A. N.A. M(1)(2) N.A. N.A. 1, 2, 3, 4 5

11. Engineered Safety Features l Actuation System Interlocks

a. Pressurizer Pressure, N.A. R -M- Q N.A. N.A. N.A. N.A. 1, 2, 3 P-11

b. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3 TABLE NOTATIONS (1) Each train shall be tested at 1 cast every 62 days on a STA MERED TEST BASIS.

(2) Contir.uity check may be excluded from the ACTUATION LOGIC TEST.

(3) Except Relays K602, K620, K622. K624, K630, K740, and K741, which shall be tested at least once per 18 months during refueling and during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless they have been tested within the previous 90 days.

- . - _ - - _ _ _ - ----,m_ _ _ - __ _ .- - - - - - -

2. _- .m__

--,,m.

o.[ Attachment IV to ET 91-0047

, , ,,Page 22 of 23 3/4.3 INSTRUMENTATICJ BASES 3/4.3.1 and 3/4.3.2 R TUAT]ON SYSTEM INSTRUMENTAllTNREACTOR 1 RIP SYSTEM A features Actuation System instrumentation and interlocks (1) the ensur associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintain e (3) sufficient redundancy is main-tained to permit a channel to be out-^urvice for testing or maintenance, and (4) sufficient system functienal capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The Integrated vperation of each of these systems is consistent with the assumptions used in the safr / analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The ;eciodic m surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability, and Supplement 1 The Engineered Safety Features Actuation System Instrumentation Trip e peints specified in Table 3.3 4 are the ncminal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy. Specified surveillanc.e intervals and surveillance and maintenance outage times have been determined in accordance withWCAP-10271?"EvaluationofSurveillanceFrequenciesandOutofService times for the Reactor Protection Instrumentation System," supplements to that report, and the NRC's Safety Evaluation dated February 21, 1965. Surveillance intervals and out of service times were determined based on mainta' ing and an appropriate level of reliability of the Reactor Protection Safety features instrumentation, 7 tem 105e % a 4 Engineered tion of the RWST and VCT valves (Notes 3 and 4) are based o the non LOCA safety analysis. These analyses take credit for injection of borated water from the RWST. Injection of borated water is assumed not to of the RWST charging pump suction valves. occur until the VCT charging pum When the sequential operation of the RWST and VCT valves is not includeo in the response times (Note 7), the values specified are based on the LOCA anal);es. The LOCA analyses take credit for injection flow regardless of the source. Verification of the response times +

specified in Tabir 3.3 5 will assure t'iat the assumptions used for the LOCA and non-LOCA analyses with respect to operation of the VCT and RWST valves are valid.

To accommodate the instrument drif t assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, WOLF CREEK - UNIT 1 B 3/4 3-1 Amend ent No. 9,12

o 6 e

l l

Attachment IV to ET 91-0047 Page 23 of 23 '

Insert E

, WCAP-10271 Supplement 2 and WCAP-10271-P-A Supplement 2 Revision 1

' Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features Actuation System,' the NRC's Safety Evaluation '

dated February 22, 1989, and the NRC's Supplemental Safety Evaluation dated j April 30, 1990. j l

l l

(

._ . _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ - _ - _ - - _ _ _ _ _ _ _

ML20029B207

Text

Navigation menu

Search