Text

Proposed Tech Specs Increasing Surveillance Test Intervals & Allowed Outage Times for RPS & ESFs Actuation Sys
	ML20094J327
Person / Time
Site:	Millstone
Issue date:	03/03/1992
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20094J324	List: B14018, Application for Amend to License NPF-49,revising TSs to Increase Surveillance Test Intervals & Allowed Outage Times for Reactor Protection Sys & Engineered Safety Features Actuation Sys; ML20094J327;
References
	NUDOCS 9203120333
	Download: ML20094J327 (21)
	v • d • e

_ . _ . . .

Docket No. 50 421 B14018 Attachment 1 H111 stone Nuclear Power Station, Unit No. 3 Proposed Technical Specification Changes Reactor Protection System and Engineered Safety features Actuation System March 1992 9203120333 920303 DR ADOCK 0500 3

List of the_Pages Af fects EGLlh 3/4 3 3 3/4 3-4 3/4 3-7 3/4 3 10 3/4 3-11 3/4 3 13 3/4 3-14 3/4 3-17 3/4 3-19 3/4 3-20 3/4 3 23 3/4 3 24 3/4 3 25 3/4 3-30 3/4 3-36 3/4 3-37 3/4 3-38 3/4 3-39 3/4 3 40

a TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTD4 INSTRUMENTATION oz.

P

~5; MINIMUM a

=

TOTAL NO. CHANNELS CF.ANNELS APPLICABLE ;

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION l c- 12. Reactor Coolant Flow--Low 5 a.- Single Loop (f.bove P-8) 3/ loop in 2/ loop in 2/ loop in 1 6 l

each oper- any oper- each oper- ;

" ating loop ating locp ating loop 4

, b.. Two Loops (Above F-7 and 3/ loop in 2/ loop in 2/ loop 1 6 !

below P-8) each oper- two oper- each oper- l ating loop- ating loops ating loop i

d

13. Steam Generator Water 4/stm. gen. 2/stm. gen. 3/sta. gen. 1, 2 6 (1) !

Level--Low-Low in each oper- in any oper- each oper- ;

ating stm. ating stm. ating stm.

w gen. gen. gen.

4- 1

. w 14. Low Shaft Speed--Reactor ;

~

4, Coolant Pumps

a. Four loop operation 4-1/ pump 2 3 1** 6 h Three loop operation 3-1/ pump 2 2 1** 6

15. Turbine Trip .

a a. Low Fluid Oil Pressure 3 2 2 1*** 12 !

b. Turbine Stop Valve Closure 4 4 4 1*** 6 [

i F -

g 16. Safety Injection Input

& froa ESF 2 1 2 1, 2 13A ;

3 3

.17. Reactor Trip System Interlocks g a. Intermediate Range Neutron Flux, P-6 2 1 2 2## 8 M ~

b. Low Power Reactor Trips Block, P-7 3- P-10 Input 4 2 3 I 8 j or !

P-13 Input 2 1 2 1 8 i

i

-.m

_ {~ TABLE 3.3-1 (Continued) o REACTOR TRIP SYSTEM INSTRUMENTATION 4

A -

MINIMUM s TOTAL NO. CHANNELS CHANNELS APPLICASLE i.

[- FUNCTIONAL UNIT =OF CHANNELS .TO TRIP OPERABLE MODES ACTION

{

8

17. Reactor Trip System Interlocks (Continued)

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

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

e Power Range Neutron i-

, R.

Flux, P-10 4 2 3 1,2 8 -

' w i 1 18. Reactor Trip Breakers 2. 1 ,

2 1, 2 10, 13

!' 2 1 2 3*, 4*, 5* 11 1

19. Automatic Trip and Interlock 2- 1 2 1, 2 13A Logic. 2 1 2 3*, 4*, 5* 11 F , 20. Three icop Operation 8 2 8 1, 2 1 .

g Bypass Circuitry (1 switch per (From differ-

= loop in each ent loop

! S train) switches in

, E

, bypass) f 21. Shutdown Margin Monitor 2 0 2 30, 4, 5 5 f 1"

!' 'G L

e !

L 4

TPBLE 3.3-1 ((snLinuedi

&CTION STATEMENTS ((_qatinued)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least 1101 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

One channel associated with an operating loop 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.

ACTION 10 - 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 ; 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 4.3.1.1, provided the other channel 1:, OPERABLE. ,

ACTION 11 - 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 System breakers within the next hour.

ACTION 12 - With the number of OPERABLE channels one less than the Total Number of Channels, SMRTUP and/or POWER OPERATION may proceed provided the followint 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. When the Minimum Channels OPERABLE requirement is met, 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 sveillance testing of the Turbine Control Valves.

ACTION 13 - With one of the diverso trip features (undervoltage or shunt trip attachments inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months )or declare the break- ino)erable and apply ACTION 10. The breaker shall not be bypassec while one of the diverse _ trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 13A - 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 110T 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_ survelliance testing per Specification 4.3.1.1, provided the other channel is operable, n

MILLSTONE - UNIT 3 3/4 3-7 0058 i

TABLE-4.3-1 om REACTOR TRIP' SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS U TRIP M ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH c CHANNEL CHANNEL OPERATIONAL ' OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED

1. Manual Reactor Trip 'N.A. N.A. N.A. R(14)' N.A. 1, 2, 3*, 4*

5* .

' 2. Power Range, Heutron Flux

! a. High Setpoint S D(2,4), Q N.A. N.A. 1, 2 1- M(3,4),

! Q(4, 6),

R(4, 5)

b. Low Setpoint S R(4) S/U(1) N.A. N.A. 1***, 2

3. Power Range, Neutron Flux, N.A. R(4) Q N.A. N.A. 1, 2 i Y High Positive Rate o

! 4. Power Range, Neutron Flux, N.A. R(4) Q N.A. N.A. 1, 2 High Negative Rate

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

6. %urce Range, Neutron Flux 5 R(4,5) S/U(1), N.A. N.A. 2**, 3, 4, Q(9) 5

7. Overtemperature AT S R Q N.A. N.A. 1, 2 E 8. Overpower AT S R Q N.A. N.A. 1, 2 S

E 9. Pressurizer Pressure--Low S R Q(18) N.A. N.A. 1

= .

. 10. Pressurizer Pressure--High S R Q(18) N.A. N.A. 1, 2

11. Pressurizer Water Level--High S R Q N.A. N.A. I

12. Reactor Coolant Flow--Low S R Q N.A. N.A. 1 b

~;

TABLE 4.3-1 (Continuad)

%3' REACTOR TRIP SYS1EM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-

E-- '

$ TRIP E

ANALOG ACTUATING MODES FOR ;

CHANNEL DEVICE WHICH l CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE E FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED Z

w 13. Steam Generator Water Level-- S R Q(18) M.A. N.A. 1, 2 Low-Low

14. Low Shaft Speed - Reactor N.A. R(13) Q N.A. N.A. I Coolant Pumps

15. Turbine Trip

'a. Low Fluid Oil Pressure N.A. R N.A. S/U(1, 10)**** N.A. I w b. Turbine Stop Valve N.A. R N.A. S/U(1, 10)**** N.A. I 1 Closure g N.A.

~

16. Safety Injection' Input from N.A. N.A. M.A. R 1, 2 ESF

17. Reactor Trip System Interlocks

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

b. Low Power Reactor Trips Block, P-7 N.A. R(4) R N.A. N.A. I

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

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

e. Power Range Neutron Flux, P-10 N.A. R(4) R N.A. N.A. 1, 2

f. Turbine Itpulse Chamber Pressure. P-13 N.A. R R N.A. N.A. I

TABLE 4.3-1 (CoatJn gdl IMLE NOTAT10t$

When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

Below P 6 (Intermediate Range Neutron flux Interlock) Setpoint.

- - Below P 10 (Low Setpoint Power Range Neutron flux Interlock) Setpoint. .

- - - Above the P 9 (Reactor Trip / Turbine Interlock) Setpoint.

(1) If not performed in previous 31 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1, (3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, and evaluated and compared to taanufacturer's data, for the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The

provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST

, BASIS.

(8) (Not used)

(9) Quarterly surveillance in MODES 3*, 4*, and 5* shall also include v rification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. ,

MILLSTONE - UNIT 3 3/4 3-13 Amendment No. Ep 0081

_, .~ _ ,_., - - . . _ _ _ _ . . _ __ _

laBLE 4.3-1 (Continued)

TABLE NQIM10NS (Continuedl (10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12)(notused)

(13) Reactor Coolant Pump Shaft Speed Sensor may be excluded from CHANNEL CAllBRAT10N.

(14) The TRIP ACTUATING DEVICE OPERATIONAL lEST shall independently verify the OPERABillTY of the undervoltage and shunt trip circuits for the Manual Reactor Tri) function. The test shall also verify the OPERABILITY of the BypassBrea(ertripcircuit(s).

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

(16) Automatic undervoltage trip.

(11)(notused).

(18) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 should be reviewed for applica')ility.

(19) Quarterly surveillance shall include verification that the Shutdown Margin Monitor is set per the CORE OPERATING LIMITS REPORT (COLR).

MILLSTONE - UNIT.3 3/4 3-14 Amendment No. J/, #

0060

. . . - _ , . - _ , . . , . . _ _ _ _ .-__-_ _~, . _ . _ _ .

g TABLE 3.3-3 3h- ENGINEERED SAFrTY FEATURES ACTUATION SYSTEM INSTFLHENTATION

~ 7u, l$

2: MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE S' ACTION FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE 80 DES c_

f5

-d I. . Safety Injection (Reactor

'a Trip, Feedwater Isolation, Control Building Isolation (Manual Initiation Only),

Start Diesel Generators, and Service Water).

-a. Manual Initiation 2 1 2 1,2,3,4 19

b. Automatic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation 4d

- Relays Y 1, 2, 3 20

c. Containment 3 2 2 Pressure--High-1

d. Pressurizer 4 2 3 1, 2, 3! 20

,, Pressure--Low R I, 2, 38 20 j[ e. Steam Line Pressure-- 3/ steam line 2/ steam line 2/ steam line g Low in each in any in each operating operating operating EL loop loop loop

_=

?

2. Containment Spray (CDA)

a. Manual Initiation 2 I with' 2 1, 2, 3, 4 19 2 coincident switches

..=.- - - - . . . . . . . . .

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ . _ . . . . . . . . . . _ . . = . _ _ _ . . . . . . . . . . . . . . . __

~

i I

{. -- ,2 TABLE 3.3-3 (Continuedi l'

P a g -- ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION i 5-i t

' MINIMUM !

c. .

TOTAL NO.'. CHANNELS CHANNELS APPLICABLE !

z FUNCTIONAL UNIT OF CHANNELS- TO TRIP OPERABLE McCES ACTION

] ;

9 3. Containment Isolation (Continued) !

t i 3) Containment 4 2 3 1, 2, 3, 4 17 4 ..

Pressure--High-3 ..

1

4. Steam'Line Isolation !

! a. Manual Initiation - i i- t i,

R 1) Individual 1/ steam line 1/ steam line I/ operating 1, 2, 3, 4 24

!. a steam line i' y !

l g 2) Sysiem 2 1 2 1, 2, 3, 4 23 l

- 1

b. Automatic Actuation 2 1 2 1, 2, 3, 4 22 .

Logic and Actuation !

Relays i

i c. Containment Pressure-- 3 2 2 1, 2, 3. 4 20 i

j. p High-2 l 1

' E i g- d Steam Line Pressure-- 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# 20 '

. g Low in each in any in each j - operating operating operating loop'

~

j g loop loop I

i g e. Steam Line Pressure - 3/ steam line 2/ steam line 2/ steam line 3**** 20 j Negative Rate--High in each in any in each y R operating operating operating }

, loop loop loop !

i, t

.. . - .- , . . - - . . . - . . - .. - ..-~ _ _ . ___ . _ -_ _ - _ _ _ _ _ _

TABLE 3.3-3 (Continuad)

"0; ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E "

. MINIMUM c- TOTAL NO. CHANNELS CHANNELS APPLICABLE 5

FUNCTIONAL UNIT OF CHANNELS .TO TRIP OPERABLE MODES ACTION

" Turbine' Trip and 5.

Feedwater Isolation !

t

a. . Automatic Actuation '2 1 2 1, 2 25 Logic and Actuation "

Ralays i

b. Steam Generator 4/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2, 3 20, 21 t Water Level-- in each in any oper- in each !

R High-High (P-14) operating ating loop operating i loop- ' loop .

Y i 3 c. Safety Injection 2 1 2 1, 2 22 I Actuation Logic

d. T ave L w Coincident with P-4 g 1) Four Loops 1Tave/1 p 1T ave in 1 T,yg in 1, 2 20 g Operating any two any three

& loops loops E i 2). Three Loops IT 1T a in 1T in 1, 2 16 F Operating opeflfing anyl$o anyi l$c

-loop operating operating R loops loops :

i i I i

l 8

. . . .. - - -. - ~ . . .- .-

i 33 TABLE 3.3-3 (Continued)

Op

^2;

@ ENGINEERED SAFETY FEATURES ACTUATION CVSTEM INSTRtRENTATION g MINIMUM g- TOTAL NO. CHANNELS CHANNELS Av~_ICABLE FUNCTIONAL UNIT '0F CHANNELS TO TRIF OPERABLE MODES ACTTT!

w.

9. Engineering Sd.'ty Features Actuation System Interlocks-

a. Pressurizer Pressure, 3 2 2 1, 2, 3 21 P-Il

b. . Low-Low T,yg, P-12

'4 2 3 1, 2, 3 21 3 c. Reactor Trip, P-4 2 2 2 1, 2, 3 23 l t

Emergency Generator Load 2 1- 2 1, 2, 3, 4 14

[

w 10., Sequencer

JfA f 3.3 3 (Continued) .

l 1ABLE NOTA 110NS

1he Steam 11ne Isolation Logic and Safety injection Logic for this trip i function. may be blocked in this MODE below the P-ll (Pressurizer Pressure Interlock) Setpoint.

- 1he Safety injection Logic for this trip function may be blocked in this MODE below the P 12 (Low Low T,yg Interlock) Setpoint.

- - The channel (s) associated with the protective functions derived from the out of service reactor coolant loop shall be placed in the tripped mode. ;

i **** Trip function automatically blocked above P ll and may be blocked below P ll when Safety injection on low steam line pressure is not blocked.

ACTION STATEMENTS l ACTION 14 With the number of OPERARLE channels one less than the Minimum !

l Channels OPERABLE requirement, restore the inoperable channel to l OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least 110T STANDBY '

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SilV1DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 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 4.3.2.1, provided the other channel is OPERABLE.

l ACTION IS - (not useo).

F ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, o)eration may proceed until performance of the next required ANA.0G CHANNEL OPERATIONAL TEST 3rovided the inoperable channel is placed in the tripped condition within I hour.

l l ACTION 17 - 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 by)assed condition and the Minimum Channels OPERABLE requirement ts met. One additional 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. ,

ACTION 13'- With less than the Minimum Channels OPERABLE recuirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of- t le Control Room ,

Emergency Ventilation System in the recirculation mode of operation. ;

HILLSTONE . UNIT.3 3/4 3-24 Amendment No. A7 0063

. _, . . , , _ . _ __ __-,,--,-..._,,-,,__-----_.._c.-.__-___

1UM 3.hLitsnLim!cd1 ACT10t1 STATEliU111 X ontinuell AC110f419 - With the number of OPERABLE channels one less than the liinimum 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 il0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SilV100Wil within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 20 - With the number of OPERABLE channels one less th3n the Total Number of Channels, STAR 1UP and/or POWER OPERATION nay 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 liinimum 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 su;veillance testing of other channels per Specification 4.3.2.1.

AC110tl 21 - With less than the liinimum llumber of 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 22 - With the number of OPERABLE channels one less than the liinimum Channels OPERABLE requirement, restore the inoperible 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 il01 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least 1101 SilV100WN 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 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.

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 be in at least 1101 STAtlDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least il0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 - 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 25 - 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 fl0T 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 4.3.2.1 provided the other channel is OPERABLE.

tilLLSTONE - UNIT 3 3/4 3-2S 0063

o _it 3- TABLE 3.3-4 (Continued) v>

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

. SENSOR s; . TOTAL ERROR

$ FUNCTIONAL UNIT Att0WANCE (TA) 1- (S) TRIP SETPOINT Att0WABLE VALUE

8. Loss of Power

a. 4 kV Bus Undervoltage N.A. N.A. N.A. > 2800 > 2720 volts (Loss M Voltage) volts with with a $ 2 a i 2 second second time time delay. delay.

b. 4 kV Bus Undervoltage N.A. N.A. M.A. 2 3710 volts 2 3706 volts (Grid Degraded Voltage) with a $ 8 with a $ 8 second time second time

[ delay with ESF delay with ESF actuation or actuation or E 1 300 second 1 300 second time delay time delay without ESF without ESF actuation. actuation.

9. Engineered Safety Features Actuation System Interlocks

[ a. Pressurizer Pressure, P-il- N.A. N.A. N.A. $ 1985 psig i 1995 psig

b. Low-tow T,yg, P-12 N.A. N.A. N.A. 1 553*F 1 549.6*F f c. Reactor Trip, P-4 N.A. N.A. N.A. N.A. N.A.

U 10. Emergency Generator Load N.A. N.A. N.A. N.A. N.A.

Sequencer

- - . . =- , - . . - - . . - . -. - .-- . -

' TABLE 4.3-2

%3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION P SURVEILLINCE REOUIREMENTS E

TRIP ANALOG ACTUATING MODES

FOR WHICH CHANNEL DEVICE MASTER SLAVE E CHANNEL CHANNEL' -OPERATIONAL. OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE OFUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED w

I. Safety Injection (Reactor Trip, Feedwater Isolation,.Centrol

. Building Isolation (Manual Initiation Only), Start Diesel Generators, and Service Water)

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. I,2,3,4 w b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(I) Q I,2,3,4 1 Logic and Actuation w Relays .

N.A. N.A. N.A.

c. Containment Pressure- S R Q N.A. I, 2, 3 High-I l

d. Pressurizer Pressure- S R Q N.A. M.A. N.A. N.A. I,2,3 Low

> e. Steam Line S R Q N.A. N.A. N.A. N.A. I,2,3 2

Pressure-Low E

5 2. Containment Spray l.

g

!. z a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. I, 2, 3, 4 N.A. N.A. N.A. N.A. M(I) M(I) I, 2, 3, 4 w b. Automt. tic Actuation Q Logic and Actuation Relays

c. Containment Pressure- S R Q N.A. N.A. N.A. N.A. I,2,3,4 High-3

TABLE 4.3-2 (Centinued) o "E: -

"F ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRURENTATION

G #

SURVEILLANCE REQUIREMENTS-M '

TRIP

. ANALOG ACTUATING MODES c CHANNEL DEVICE' MASTER SLAVE FOR WHICH E' , CHANNEL CHANNEL. OPERATIONAL OPERATIONAL ACTUATION . RELAY RELAY SURVEILLANCE

[FUNCTIONALUNIT- ,

CHECK CALIBRATION TEST TEST ' LOGIC TEST TEST TEST IS REQUIRED 3.. Containment Isolation

a. Phase'"A" Isolation

1) Manual Initiation N.A. N.A. N.A. R N . A .' N.A N.A 1, 2, 3, 4

2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 Logic and Actuation Relays

, .]

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

b. Phase "B" Isolation' i

1) Manual Initiation- N.A. N.A. N.A. R N.A. N.A. N.A 1, 2, 3, 4

2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q I,2,3,4 Logic Actuation 1

{

o Relays

& 3) Containment 5 R Q N.A. N.A. N.A. N.A. 1, 2, 3, 4 E

Pressure-High-3

! F4. Steam Line Isolation..

j D a. Manual. Initiation.

l- 1) Individual- . N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 j- 2) System N.A. N.A. N.A. R N.A. N.A. N.A. I, 2, 3, 4 4

e I

4

.% - . . a y ._<-- s% - , . - r - -4. es * , - - - - . . - - - - .e.- - -+4- **. - -a--- ~ ' - - - - - - ---

r TABLE 4.3-2 (Continued) of "F ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

-SURVEILLANCE REGUIREMENTS "j!

o M TRIP

.. ANALOG ACTUATING MODES e _

CHANNEL DEVICE- ' MASTER SLAVE FOR WHICH 5 -

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

~~TUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 4.. Steam Line Isolation (Continued)

N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 b.' Automatic Actuation' '

Logic and Actua', ion Relays

c. Containment Pressure- S. P, Q N.A. N.A. N.A. N.A. I, 2, 3, 4

-l High-2 s*

d. Steam Line -S R Q N.A. N.A. N.A. N.A. I, 2, 3 l Pressure-Low 4

co

e. Steam Line Pressure- S R Q N.A. N.A. N.A. N.A. 3 Negative Rate-High

5. Turbine Trip and Feedwater Isolation

.N.A. M(I) I, 2 F a. Automatic Actuation N.A. N.A. N.A. M(I) Q 3 Logic and Actuation

@ Relays

" N.A. M(1) M(1) Q I, 2, 3

b. Steam Generator Water S R Q

'f Level-High-High' D c. Safety Injection 'N.A. N.A. N.A. R N.A. N.A. N.A. I, 2

~ Actuation Logic; i

d. T Low Coincident -N.A. R Q. N.A. N.A. N.A. N.A. I, 2 l ave l

with Reactor , Trip (P-4) i

TABLE 4.3-2 (Continuedl b

'G ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5 SURVEILLANCE REOUIREMENTS M

TRIP e ANALOG ACTUATING 5 CHANNEL DEVICE MASTER MODES CHANNEL CHANNEL SLAVE FOR WHICH

[FUNCTIONALUNIT CHECK CALIBRATION TEST OPERATIONAL OPERATIONAL ACTUATION RELAY RELA SURVEILLANCE TEST LOGIC TEST TEST TEST IS REQUIRED

6. Auxiliary Feedwater

a. Manual Ir.!tiation N.A. N.A. N.A. R N.A. N.A. N.A. I, 2, 3

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

and Actuation Relays N.A. M(1) M(I) Q I, 2, 3

c. Steam Generator Water S ,

g Level-Low-Low R Q N.A. N.A. N.A N.A I 2. 3 Y d. Safety Injection M See Item I. above for all Safety Injection Surveillance Requirements.

e. Loss-of-Offsite Power See Item 8 below for all loss of Power Surveillance.

f. Containment Depres- !

surization Actuation See Item 2. above for all CDA Surveillance Requirements.

(CDA)

F7. Control Building Isolation E

& a. Manual Actuation N.A.

S N.A. N.A. R

" N.A. N.A. N.A. All

b. Manual Safety H.A. N.A.

@ Injection Actuation N.A. R N.A.

, N.A. N.A. I, 2, 3, 4 D c. Automatic Actuation N.A. N.A.

Logic and Actuation N.A. N.A. M(1) M(I) Q I . 2, 3, 4 Relays

d. Containment Pressure-- S R High-1 Q N.A. N.A. N.A.

.i N.A. I, 2. 3 I

l

_ i

f j &-

%f

/ TABLE 4.3-2 (Continued)

V - f

= 3#'~

~'#p- .

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLAf4CE REQUIREHENTS f %

I $

,=

TRIP MODES

" ANALOC ACTUATING DEVICE' MASTER SLAVE FOR WHICH

' CHANNEL I RELAY RELAY SURVEILLANCE CHANftEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION E TEST LOGIC TEST TEST TEST IS RE0VIRED Z FUNCTIONAL UNIT CHECK CALIBRATION TEST __

us

7. Control Building Isolation (Continued)

N.A. N.A. N.A. N.A. All

e. Control Building Inlet S R Q Ventilation Radiation

3. Loss of Power N.A. N.A. N.A. 1, 2, 3, 4 l N.A. R N.A M(3) j

a. 4 kV Bus Undervoltage (Loss 1 of Voltage)

$ N.A. R N.A. M(3) N.A. N.A. N.A. 1, 2, 3, 4

- u> b. 4 kV Bus i Undervoltage (Grid Degraded Voltoge)

9. Engineered Safety Teatures Actuation 5,otem Interlocks N.A. N.A. N.A. N.A. 1, 2, 3

> a. Pressurizer N.A. R Q l Pressure, P-Il N.A. N.A. N.A. N.A. N.A. 1. 2, 3 y b. Low-Low T3yg, P-12 R Q N.A. N.A. N.A. 1, 2, 3

c. Reactor Trip, P-4 N.A. N.A. N.A. R A

N.A. Q(1, 2) N.A. N.A. 1, 2, 3, 4 i N.A. N.A. N.A. '

10. Emergency Generator Load Sequencer D ,

l

_ ,

ML20094J327

Text

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