Text

Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves
	ML20148E592
Person / Time
Site:	Farley
Issue date:	05/27/1997
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20148E589	List: ML20148E585; ML20148E592;
References
	NUDOCS 9706030180
	Download: ML20148E592 (21)
	v • d • e

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

s se TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION p MINIMUM

$ TOTAL NO. CHANNELS CHANNELS APPLICABLE ^

FUNC"rIONAL UNIT - OF CHANNELS TO TRIP OPERABLE MODES ACTION d Manual-Reactor Trip 2 2

1. 1 1, 2 12 .

3*, 4*, 5* 13

2. Power Range, Neutron Flux '

A. High 4 2 3 1, 2 2#

B. Low 4 2 3 2 2#

3. Power Range, Neutron Flux, 4 2 3 1, 2 2# ,

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2#

High Negative Rate w

} 5. Intermediate Range,' Neutron 2 1 2 1, 2, and

3#### ,

, Flux b

6. Source Range, Neutron Flux A. Startup 2 1 2 2##, and

4 [

B. Shutdown 2 0 1### 3***, 4 and 5 5 l l

7. Overtemperature AT Three Loop Operation 3 2 2 1, 2 7# l Two Loop Operation '

3 1** 2 1, 2 9 l.

8. Overpower AT ;

Three Loop Operation 3 2 2 1, 2 7# ;

Two Loop Operation 3 1** 2 1, 2 9 '

N

9. Pressurizer Pressure-Low 3 2 2 1 7#

10. Pressurizer Pressure--High 3 2 2 1, 2 7#

O I

l 9706030180 970527 PDR ADOCK 05000348-P PDR. ,

._ . . _ . , ._.__._____m.__.__..-m________.____ _____.m.mm____ . _. . . ,,, ,, , ...___mm.. . _ _ _ - . , , . m.. .

._,y..- , ,_ . , _ ,

.- .._ . . , _ . . ._ _ _ _ _ _ _ . . _ _ . . . _ . _ . _ . . _ _ __m-_. __4 _ _ . . .._ -

i

, e i

TABLE 3.3-1 (Continued)

. TABLE NOTATION i

With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

I:

- The channel (s) associated with the protective functions derived from-the out of service Reactor Coolant Loop shall be placed in the tripped condition.

- - Below the P-6 (Block of Source Range Reacter Trip) setpoint. l

The provisions of Specification 3.0.4 are not applicable,

[

l ## High voltage to detector may be de-energized above P-6.

l' ### Indication only.

1. 1. 1. The provisions of Specification 3.0.3 are not applicable if [

THERMAL POWER level 2 10% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 -- With.the number of OPERABLE channels one less than required

! by the Minimum Channels OPERABLE requirement, be in-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 l 4.3.1.1.

ACTION 2 - With the number of OPERABLE channels one less than the Total I Number of Channels, STARTUP and/or POWER OPERATION may l 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; i

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 the other channels per Specification 4.3.1.1.

I cs Either, THERMAL POWER is restricted to less than or equal

!~ to 75% of RATED THERMAL POWER and the Power Range Neutron

~

Flux 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 from the remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

i I

FARLEY-UNIT 1 3/4 3-6 AMENDMENT NO.

l 5'

( i l TABLE 4.3-1 (Continued) i TABLE NOTATION l - With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1) - If not performed in previous 7 days.

1 (2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than 2 percent.

(3) - Compare incore to excore axial flux dif ference every 31 EFPD.

i

,Recalibrate if the absolute difference is greater than or equal to 3 percent.

(4) - Manual ESF functional input check every 18 months. l I (5) - Each train or logic channel shall be tested at least zery 62 days on a STAGGERED TEST BASIS.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Below the P-6 (Block of Source Range Reactor Trip) setpoint.

Upon reaching P-6 from MODE 2 the CHANNEL CHECK must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(8) - Logic only, if not performed in previous 92 days.

(9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.

(10) - If not performed in the previous 31 days.

(1.) - Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

(12) - Verify reactor trip breaker and reactor trip bypass breaker open upon actuation of each Main Control Board handswitch.

(13) - Local manual shunt trip prior to placing breaker in service.

Local manual undervoltage trip' prior to placing breaker in service.

(14) - Undervoltage trip via Reactor Protection System.

(15) - Local manual shunt trip.

l FARLEY-UNIT 1 3/4 3-14 AMENDMENT NO.

. i'

! 6 EMERGENCY CORE COOLYNG SYSTEMS i 3/4.5.2 ECCS SUBSYSTEMS - T3yg > 350*F

\

! LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

l l a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger, I

c. One OPERABLE residual heat removal pump, and f d. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.* l

[ t APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable l subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the 7

, actuation and the total accumulated actuation cycles to l date. The current value of the usage factor for each ;

i affected safety injection nozzle shall be provided in this l Special Report whenever its value exceeds 0.70.

t l

L

Upon entry into Mode 3 from Mode 4, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be locked open for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 4

, requirements.

FARLEY-UNIT 1 3/4 5-3 AMENDMENT NO.

1

- ._ . -. _ . . __ _ _ .__m . _ .._ . . .._. . . __. _ _-

i I

.. o l

EMERGENCY CORE CCOLING SYSTEMS

j. 3 /4. 5. 3 NCCS SUBSYSTEMS - Tavg e 350*F l

LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump, l

b. One OPERABLE residual heat removal heat exchanger, i #

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned l and transferring suction to the containment sump during the recirculation phase of operation.* l l

APPLICABILITY: MODE 4.

ACTION: l

a. With no ECCS subsystem OPERABLE because of the inoperability l of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RER loop is OPERABLE.

l

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS l subsystem to OPERABLE status or maintain the Reactor Coolant System-Tavg less than 350'F by use of alternate heat removal methods.

l l

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared l and submitted to the Commission pursuant to Specification l 6.9.2 within 90 days describing the circumstances of the j actuation and the total accumulated actuation cycles to

date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

l i:

Upon entry into Mode 4 from Mode 3, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be closed for up i to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 3 requirements.

'ARLEY-UNIT 1 3/4 5-7 AMENDMENT NO.

TABLE 3.3-1 _

i REAC" TOR TRIP SYSTEM INSTRUMENTATION-

n

. MINIMUM h TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION N

i 1. Manual Reactor Trip 2 1 2 1, 2 12 3*, 4*, 5* 13 '

2. Power Range, Neutron Flux A. High -4 2 3 1, 2 2#

B. - Low 4 2 3 2 2# ,

3. Power Range, Neutron Flux, 4 2 3 1, 2 2#-

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2#.

g -High Negative Rate l

} "h w 5. Intermediate Range, Neutron 2 1 2 1, 2 and

3#### ;

y Flux

6. Source Range, Neutron Flux A. Startup 2 .1 2 2##, and

4' !

B. Shutdown 2 0 1### 3***, 4 and 5 5 l 1

-i

7. Overtemperature AT Three Loop Operation 3 2 2 1, 2 7# l Two Loop Operation 3 1** 2 1, 2 9 !

4

8. Overpower AT r Three Loop Operation 3 2 2 1, 2 7# ,

Two Loop Operation 3 1** 2 1, 2 9 j i

9 ' Pressurizer Pressure-Low 3 2 2 1 7#

.i g 10. Pressurizer Pressure--High 3 2 2 1, 2 7# [

O E s

l t

l L

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_- _ _ _ _ _ .____w____wu

l

, e TABLE 3.3-1 (Continu*d) t TABLE NOTATION

With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

i

- The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

- - Below the P-6 fdlock of Source Range Reactor Trip) setpoint. l

The provisi'sns of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above P-6.

1. 1. Indication only. j l

1. 1. 1. The provisions of Specification 3.0.3 are not applicable if l THERMAL POWER level ,> 10% of RATED THERMAL POWER.

ACTION STATEMENTS l ACTION 1 - With the number of OPERABLE channels one less than required by the

! Minimum Channels OPERAELE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypaased 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.

I ACTION 2 - With the number of OPERABLE channels one 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 condition I 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, l 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 the other channels per Specification j 4.3.1.1.

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux 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 from the remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

l i

L FARLEY-UNI; 3/4 3-6 AMENDMENT NO.

i I

I TABLE 4'. 3-1 '(Continued)

TABLE NOTATION l

- With,the reactor trip system breakers closed and the control l

l- rod drive system _ capable of rod withdrawal.

(1) -- If not performed in previous 7 days.

(2)' -

Heat balance only, above 15% of RATED THERMAL POWER. Adjust.

channel if absolute difference is greater than 2 percent.

(3) -

Compare incore to excore axial flux difference every 31 EFPD. Recalibrate if the absolute difference is greater than or equal to 3 percent.

l (4) - Manual ESF functional input check every 18 months. l

.s.

(5) -

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

, (6) - Neutron detectors may be excluded.from CHANNEL CALIBRATION.

L j . (7) -

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

l Upon reaching P-6 from MODE 2 the CHANNEL CHECK must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . l

)

I (8) - Logic only, if not performed in previous 92 days.

I (9). - CHANNEL FUNCTIONAL TEST will consist of verifying that each ,

channel indicates a turbine trip prior to latching the l turbine and indicates no turbine trip prior to P-9. ]

I

( 10) - If not performed in the previous 31 days.

(11) - Independently verify OPERABILITY of the undervoltage and l shunt trip circuitry for the Manual Reactor Trip Function.

'(12) - Verify reactor trip breaker and reactor trip bypass breaker j open'upon actuation of each Main Control Board handswitch.

l (13). - Local manual shunt trip prior to placing breaker in service .

j Local manual undervoltage trip prior to placing breaker in

! service.

, (14) - Undervoltage trip via Reactor Protection System.

(15). - Local manual shunt trip.

l i

i FARLEY-UNIT 2 /4 3-14 AMENDMENT NO.

l l

l

l ,

EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T gyg > 3 50*F _

LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

f

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger,

c. One OPFRABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.* l MODES 1, 2 and 3.

APFldCABILITY:

ACTION:

a.

With one ECCS subsyntem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

Upon entry into Mode 3 from Mode 4, the breaker or disconnect device to the *;alve operators for MOVs 8706A and 8706B may be locked open for up 'c 4 hoars to allow for repositioning from Mode 4 l requireme....

AMENDMENT NO. J FARLEY-UNIT 2

... es ,

e !

EMERGENCY CORE COOLING SYSTEMS g 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350JE l

l LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum. .one ECCS subsystem comprised of the following shall be OPERABLE:

l l

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger, i

c. One OPERABLE residual heat removal pump, and

.d. An OPERABLE flow path capable of taking suction from the i

refueling water storage tank upon being manually realigned !

l and transferring suction to the containment sump during the recirculation phase of operation.* l APPLICABILITY: MODE 4.

ACTION: t l

1 l a. With no ECCS subsystem OPERABLE because of the inoperability l of either the centrifugal charging pump or the flow path j from the refueling water storage tank, restore at least one l ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR l loop is OPERABLE.

b. With no ECCS subsystem OPERABLE because of the inoperability

, of either the residual heat removal heat exchanger or ,

residual heat removal pump, restore at least one ECCS l subsystem to OPERABLE status or maintain the Reactor Coolant l System Tavg less than 350*F by use of alternate heat removal !

methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification

! 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to l date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this l Special Report whenever its value exceeds 0.70. j t

l t

, *- Upon entry into Mode 4 from Mode 3, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be closed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositionins from Mode 3 requirements.

FARLEY-UNIT 2 3/4 5-7 AMENDMENT NO.

c.

l ENCLOSURE 4 Joseph M. Farley Nuclear Plant Request to Revise Technical Specifications Technical Specification Compliance Issues Amendments Marked Paces 1

l I

1 1

_._.._._.m.__. _ _ . _ _ . . - _ . _ . _ _ _ _ _ _ . . . . _ _ _ . . _ _ _ . _ . _ . _ _ . _ . . _ _ _ _ _ . . . _ . _ . . - . _ . _ _ _ _ _ _ _ _ . . . _ _ _ _ _ . . _ . . . _ .

a l

g TABLE 3.3-1 f

M m REACTOR TRIP SYSTEN INSTRUDENTATION !

? -

E f 5 MilltfRM

- TOTAL NO. CMAINIELS CHANNELS APPLICA6LE .-

FUNCTIGIIAL Uilli . OF CNAINELS TS ikiP OPERABLE Notas ACTION !

1. Meeval Reactor Trip 2 1 2 1, 2 12 3* , 4 * , 5* 13 ;

2. Power Range,llestron Flux . I A. IN gh 4 2 3 1, 2 2# i

5. f.ow 4 2 3 2 2r !

3. Power Range, flestron Flux, 4 2 3 1, 2 ?#

INgh Posttive Rate ;

4. Power Range,liestron Flux, '4 2 3 1, 2 ?#

)

tifgh flegative Rate

3####

, 5. Intermediate Range, IIeutron 2 1 2 1, 2, and

i 4 Flux l Source Range. IIeutron Flux 6.

A. Startup 2 1 2 2##, and

4 :

i 5. Shutdown 2 0 Ifff -

, 4 and 5 5 j i

7. Overtemperature & T p Three Loop W etton 3 2 2 1, 2 1# !

Two Loop W atton 3 1** 2 1, 2 9 !

8. Overpower AT - -

i ihree Loop W etton 3 2 2 1, 2 If .

Two toop h atten 3 1** 2 1, 2 9 i 2 2 18

9. Pressertrer Pressure-Low 3 1 ,

18 g

m

10. Pressurizer Pressure--N1gh 3 2 2 1, 2 l

-4 5

J

,, TABLE 3.3-1 (Continued) s

! TABLE NOTATION

}

With the reactor trip systen breakers in the closed position, the -

i control rod drive systen capable of rod withdrawal, and fwi in the 1 reactor vessel.

i

) ** The channel (s) associated with the protective functions derived from the 1 out of service Reactor Coolant loop shall be placed in the tripped 1 i j h* m P4 (6/mk /brec, lo.iW3 efdd, j # p sr w1 c .. .

1 '

j N High voltage to detector may be de-energized above p-4.

1 j Ni Indication only.

i MN The 1sions of Specification 3.0.3 are not applicable if THOUW.

level at 105 of MTED THDOW. POWER.

l I '

ACTIGI STATDEEf1 ACTION 1 - With the number of'OptMOLE channels one less than

~' ~

trod by the matame Channels OptMEE regelmaant be in NOT ST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; heuever, one channel may be bypassed for up to I hours for i serve 111ance testing per Specification 4.3.l.1.

i i ACTION 2 - With the number of OpEMBLE channels one less than the Total Number of i j Channels, STARTUp and/or POWDt OPERATION may proceed provided the following conditions are satisfied:

j a. The inoperable channel is placed in the tripped condition within j $ hours. l l

! b. The Minimum Channels OpDIAtLE regoirement is met; heuever, 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 l

{ serve 111ance testing of the other channels per Specification i

4.3.1.1. -

i l -

1

! c. Either TMWull PIME is to less then er equal to 735 of ARTIB TMMM. MMR and the Genes Nestres Flus trip ist is reeleced to less er easel to SM of MTEB TIEMAL witkim 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the quMMNT POWER TILT MTIO from the remaining 1 detectors is usettered at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per

) Specification 4.2.4.2.

)

I l

i FARLEY-talIT 1 3/4 3-4 ,

AfGOENT NO.fl.107 ,

.m _ . - . __._ . . . . _ . _ . . = _ . _ _ . _ _

_ - . _ _ . - . _ . _ _ . . - _ . . . . _ _ . . . _ _ ~ . . . _ _ _ _ _ . ._ _ _____ __._.

J

. 1 6

l taste 4.3-1 (Continued)

~

TABLE NOTATION ,

i

* - With the reactor trip systee breakers closed and the control rod drive systes capable of rod withdrawal. !

n

{ (1) - If not performed in previous 7 days.

4 (2) -

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than 2 percent.

i I l' (3) - compare incore to escore axial flus difference every 31 EFFD. j Recalibrate if the absolute difference is greater than or equal to '

j 3 percent.

(4) - Manual ESF functional input check every 18 months. See-4he- i

! f:r -- ti :; rt '- :-?--1."'-*--"-.'-"--* I t.%- z ":f: 2 :nt-,- _ "-f: 2. l l

(5) -

Each train or logic chamaal shall be testod at least every 62 days on a STAGGERED TEST MASIS.

(6) - Neutros detectors e6y be excluded from twunrrt CALIBRATION.

i

! (7) -

Bely t P-6 (Block of Sour Range g or Tri eet

2. DIAN94 - C. w3f- be. E O A I b e.

l (8) -

Logic only, i per av s 2 .

I 1 (9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each j channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.

l (10) - If not performed in the previous 31 days.

i (11) - Independently verify OPERABILITY of the undervoltage and shunt l trip circuitry for the Manual Reactor Trip Function.

l 4

(12) -

Verify reactor trip breaker and reactor trip bypass breaker open .

l

, upon actuation of each Main Costsel Board handsmitch.

(13) - Imcal manual shunt trip prior to placing breaker la service.

Local manual undervoltage trip prior to placing breaker in

, service.

j (14) - Undervoltage trip via Reactor Protection systee.

I (15) - Local manual shunt trip.

i i

i

! FARLEY-UNIT 1 3/4 3-14 AMENDMENT No.120 t

j i

i ,.. EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUSSYSTEMS - T > 350*F -

av ,_

LIMITING CONDITION FOR OPERATION 1

j 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystees shall be -

OPERA 8LE with each subsystes comprised of:

!,. a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger, j c. One OPERABLE residual heat removal pump, and I

, d. An OPERABLE flow path capable of taking suction free the refueling i

water storage tank on a safety injection signal and transferring

, suction to containment susp during the recirculation phase of operation. '

,' ~

APPLICA8ILITY: M00E5 1, 2 and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem i to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months er be in at least MT STAM8Y

withis the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in NOT SitRDOW withis the following l l 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ,

b. In the event the ECCS is actuated and injects water into the Reutor

! Coolant Systas, a Special Report shall be prepared and submitted to

! the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumu-

{ 1ated actuation cycles to date. The current value of the usage j factor for each affected safety injection nozzle shall be previded in this Special Report whenever its value exceeds 0.70.

l i l' ". *

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t o p en % uh 3 % Me 4, he l>cco% e Mecb clevke e e Ae. q;emb -G,- Mov3 m W sus 6 lodeA y & up 4o <6 hwrg. fo it% 4 ep4, c nae + cupanwe, FARLEY-UNIT 1 3/4 5-3 AMENDMENT NO. 26

._ _._ . _ _ . ~ . _ _ _ _ . . _ _ _ . _ _ . _ _ _ _ . . . _ . _ . _ _ _ . _ _ _ . _ _ _ _ . _ _ .

,., EME*GENCY CORE COOLING SYSTEMS

\

3/4.5.3 ECCS SU85YSTEMS - T, .<350{F .)

LINITING CONDITION FOR OPERATION 4

3.5.3 As a minimum,.one ECCS subsystes comprised of the following shall be !

j. OPERA 8LE: '

i j a. One OPERA 8LE centrifugal charging puep,

! b. One OPERA 8LE residual heat removal heat exchanger, I

c. One OPERABLE residual heat removal puep, and d.

- An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring i suction to the containment susp during the recirculation phase of operation.@ ;

)

APPLICA8ILITY: M10E 4.

ACTION

9 \

j a. With no ECCS subsystem 0PERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the 8 refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR loop is OPERABLE.

I.

i b. With no ECCS subsystem OPERA 8LE because of the inoperability of

either the residual heat removal heat exchanger or residual heat 1

removal pump, restore at least one ECCS subsystem to 0PERA8LE status i or maintain the Reactor Coolant System T"'8 less than 350*F by use i of alternate heat removal. methods.

~

c. In the event the ECCS is actuated and injects water into the . Reactor Coolant Syste6, a Special Report shall be prepared and submitted to the Caenisstu pursuant to Specification 6.9.2 within 90 days i describing the circumstances of the actuation and the total

accueulated actuation cycles to date. The current value of the l- usage factor for each affected safety injection nozzle shall be l

}' provided in this Special Report whenever its value exceeds 0.70.

1 ;

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M W CMENT P FARLEY hMIT Z 3/4 3-2 3

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1

i 4 TAhLE RIATIM

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' With the reactor trip system breakers in the closed position, the

! control rod drive systen capable of rod withdrawal, and fuel in the reactor vessel.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped v h kc PeubTrip)sefp44. I sm. er apoctrica on .. c e.

N High voltage to detector any he de-enegtred aheve F-4.

! l l Nf Indication only.

HM The isiens of Spectfication 3.0.3 are not appitcable if THEIIIAL

, level a 105 of AATB THOWIAL p0WER.

I ACTIM ETATBENTS i

ACTION 1 - With the ausher of Op BASLE channels one less them trod by the Mintana Chamaels GFDAOLE regatrement, be in WT ST within 6 )

t hours; twuever, one channel any be bypassed for op to t bours for j survet11asco testing por Specificaties 4.3.1.1. {

ACTI M t - With the muuher of Op GRALE channels one less than the Total nuuher of '

Channels. STARTUp and/or poler OpGATIM may proceed provided the l following 'cendittens are satisfied:

a. The tasperable channel is placed in the tripped conditten within g 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i 1

b. The filataus Channels OpmAALE receirament is met; heuever, the I

tasperable channel any be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l l servet11ance testing of the other channels per Specification 1

4.3.1.1.

i

' c. Elther TIEBML PERER is restri to less than er ogsel to 75 of O M FM and the Restree Flus is redseed to less SE of RETB withis '4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the TILT RAT M from the j ' remeistep 3 detectors is usettered at least asce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per i

. Spectftcatt.en 4.t.4.2. .

3 j

i FARLEY-4RIIT 2 3/4 3-4 AfEDWIT NO. M.99

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. O l TABLE 4.3-1 fcontinued)

TABLE NOTATION 4 * - With the reactor trip system breakers closed and the controi j ' rod drive system capable of rod withdrawal.

(1) - If not performed in previous 7 days.

2 (2) -

Heat balance only, above 15% of RATED THERMAL POWER. A3just channel if absolute difference is greater than 2 percent.

.; (3) -

Compare incore to excore axial flux difference every 31 EFFD.

l Recalibrate if the absolute difference is greater than or equal 4 to 3 percent.

l (4) -

Manual ESF functional input check every 18 monthe. -pee-the-

{ r1; .125 g ::t ' 7 , --ir r-1;. "'- ' r ^

n :: g' : ;nii th: n-; ":f: ? r- -- '___ " " S i

l (5) - Rach train or logic channel shall be tested at least every 62

j. days on a STAGGERED TEST SASIS.

i l (6) - Neutron detectors may be excluded from CHANNEL CALIBRATIcel.

1 j (7) - 1 t P-6_(31p k of ce Trini eetmeint.

Log c Y6h ye o d

L$ [ N ys. 5 4 CAtEC mwf 'd kb ihour j

l (8) , - - - -

1 j (9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine

)

4 and indicatee no turbine trip prior to P-9. l f

! (10) - If not performed in the previoue 31 days.

(11) - . Independently verify OPERASILITT of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

l (12) - verify reactor trip breaker and reactor trip bypass breaker i open upon actuation of each Main control Board handowitch.

I-j (13) - Local manual shunt trip prior to placing breaker in service.

Local manual undervoltage trip prior to placing breaker in

! service.

1 a (14) - Undervoltage trip via Reactor Protection System.

l (15) - Local manual shunt trip.

FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 112

.t , y EMRGENCY CORE COOLING SYSTDe$

i 3/4.5.2 ECCS SUBSYSTDt$ - T av_w

> 3502F i LINITING CONDITION FOR OPERATION t

1 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be l

OPERA 8LE with each subsystem comprised of:

i

! a. One OPERA 8LE centrifugal charging pump, t -

j b. One OPERA 8LE residual heat removal heat exchanger, 1

j c. One OPERA 8LE residual heat removal pump, and 4

! d. An OptRASLE flew path capable of taking suction from the refueling j water storage tank en a safety injection signal and transferring l suction to containment sump during the recirculation phase of j operation.

l APPLICA8ILITY: MOES 1, 2 and 3.

j 1

M: -

! a. With one ECCS subsystem inoperable, restore the inoperab1's subsystem i

to OPERASLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least MIT STAW8Y withis the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in WT SWTOOW within the following 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

I .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to i the Commission pursuant to Specification 6.9.2 within 90 days ,

I describing the circumstances of the actuation and the total accumu- l

} 1ated actuation cycles to date. The current value of the usage l 1 factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

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y Opm en info Mode 3 km Mcdo i le bMk or A'EuwM device b -k Vo.\Vc c9eru.b Grr MoV o Dt%A M 37%8 M3

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'"' FARLEY-WIT 2 3/4 5-3 -

t .-

_ _ _ . _ _ . . . _ . . .._. _ m . . _ _ _ - . _ . . ~ . . _ _ _ - . _ . _ _ . _ . . - . . _ _ . . _ _ . . _ . _ _ _ _

ji ** ** EMERGENCY CORE COOLING SYSTEMS l 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350*F .;

LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be i

OPERA 8LE:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger, j

c. One OPERA 8LE residual heat removal pump, and

d. An OPERA 8LE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring ;

suction to e containment sump during the recirculation phase of operation.

APPLICA8ILITY: MODE 4.

l ACTION: I

a. With no ECCS subsystem OPERA 8LE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystes to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR loop is OPERA 8LE. ,

l

b. With no ECCS subsystes OPERA 8LE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystes to OPERA 8LE status or maintain the Reactor Coolant System T8 less than 350*F by use of alternate heat removal methods.

c. In the event tne ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage facter for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

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! FARLEY-UNIT 2 3/4 5-7 s '

4 s N

- - _ _- . ._. -.

ML20148E592

Text

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