ML20198E662

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Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value
ML20198E662
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/31/1997
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20070L114 List:
References
NUDOCS 9801090184
Download: ML20198E662 (20)
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Text

______ ____-_ - __--__- .

s .

4 ATTACilMENT I Joseph M. Farley Nuclear Plant Technical Specifications Charge Request Intermediate Range Neutron Flux Reactor Trip Setpoint FNP Unit 1 Technical Specifications Changed Pages List FNP Unit i Technical Specifications Marked-up Pages IHP Unit i Technical Specifications Typed Pages FNP Unit 2 Technical Specifications Changed Paps List FNP Unit 2 Technical Specifications Marked-up Nge1 FNP Unit 2 Technical Specifications Typed Pages 9001090184 971231 PDR P

ADOCK 05000348 py

4 Joseph M. Farley Nuclear Plant Technical Specifications Change Request Intennediate Range Neutron Flux Reactor Trip Setpoint Unit I Changed Pages bg; instruction 25 Replace 112 4 Replace 3/4103 Replace 3/4104 Replace U

TABLE 2.2-1 m

> REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS w

E ALLOWABLE VALUES y FUNCTIONAL UNIT TRIP SETPOINT s

1. Manual Reactor Trip Not Applicable Not Applicable

}

- i

2. Power Range, Neutron Flux Low Setpoint - 5 25% of RATED Low Setpoint - 5 25.4% of RATED 1 THERMAL POWER THERMAL POWER High Setpoint - 5 109% of RATED High Setpoint - $ 109.4% of RATED l THERMAL POWER THERMAL POWER
3. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with 6 5.4% of RATED THERMAL POWER l High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seccada 5 5.4% of RATED THERMAL POWER I
4. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with High Negative Rate a. time constant 2 2 seconds wit a time constant 2 2 secosids 35 40 u 5. Intermediate Range, Neutron 5 .- of RATED THERMAL POWER S 4 of RATED THERMAL POWER Flux

^ ^

6. Source Range; Neutron Flux s 105 counts per second s 1.3 X 105 counts per second
7. Overtemperature AT See Note 1 See Note 3
8. Overpower AT See Note 2 See Note 6
9. Pressurizer Pressure--Low 2 1865 psig 2 1862 psig  !
10. Pressurizer Pressure--High 5 2385 psig s 2388 psig l
11. Pressurizer Water 5 92% of instrument span 6 92.4% of instrument span -l~

y

$ Level-High

=

0

~

% 12. Loss of Flow 2 90% of minimum measured flow 2 89.7% of minimum measured flow l par loop- per loep*

. 7 P

  • Minimum measured flow is 88,100 gpm per loop. l O

6

i LIMITINGfA(dTYSYSTEMSETTINCS 35 B.A.S.E.S..................................... .......... .....................

Intermediate and Source Range, Nuclear Flux The Intermediate and Source Range, Nucl r Flux trips provide re:ctor core protection during reactor startup, ase trips provide redundant -

protection to the lov setpoint trip of e Power Range, Neutron Flux chapnels. The Source Range Channels 11 liitiate a reactor trip at about 10 counts per second unless manup y bloc ted when P-6 becomes active. The Intermediate Range Channels villAnt tiate a reactor trip at a current level proportional to approximately 45 percent of RATED THERMAL POVER unless 4

manually blocked when P-10 becom;es active. No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature at The Overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slov vith respect to piping transit, thermovell, and RTD response time delays from the core 'o'the l temperature detectors (about 4 seconds), and pressure is within tre range between the High and Lov Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of vater with temperature and dynamic compensation for transport, thermovell, and RTD response time delays from the core to RTD output indication. Vith normal axial pover distribution, this reactor trip limit is always below the core saf ety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom pover ran.ie nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

P-8 Operation with setpoint does a reactor coolant loop out of service belov the 3 loop not require reactor protection system setpoint modification because the P-8 setpoint and associated trip vill prevent DNB during 2 loop operation exclusive of the Overtemperature delta T setpoint.

Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the K1, K2, and K3 inputs to the Overtemperature delta T channels and raising the P-8 setpoint to its 2 loop value. In this mode of op9tation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced power level.

FARLE1 - UNIT 1 B24 26, 87 AMENDMENT NO.

i

.[

SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS  ;

LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5 -

and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided: r

a. The THERMAL POWER does not exceed 5% of_ RATED THERMAL POWER, e d
b. The raisio, t-47 entnoints on the OPERABLE fn'*- ::1.iw and Power Range Nuclear Channels ar- :_. .. m*= than or equal to 25% of RATED THrDMA{ pgg q, ggg b, Ar. i The Reactor Coolant System lowest operating loop temperature (T**9) is greater than or t. qual to 531*F. ,

APPLICABILITY: MODE 2.

ACTION:

a. With the THERMAL POWER greater than 5% of RATED THERMAL POWER, immediately open the reactor trip breakers.
b. less With than a Reactor 531'F, restoreCoolant i System operating loop temperature (Ttowithinitslimitwi inatleastHOTSTAND$Y9within the next.15 minutes.

SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperature (T shall be determined to '

be greater than or equal to 531*F at least once per 30) minutes during PHYSICS 8 TESTS.

4 5 7 FARLEY-UNIT 1- 3/4 10-3 AMENDMENT NO. 26

SPECIAL TEST EXCEPTIONS .

3/4.10.4 REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of start up and PHYSICS TESTS provided/

Jg' f7he THERMAL POWER does not exceed the P-7 Interlock Setpoint, .

[ D art M et oints on the;rOPERA Range Channels are se e and Power ual to 25% of RATED THERMAL Powro APDLICABILITY: Luring operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during start up and PHYSICS TESTS.

4.10.4.2 Each Intermediate. Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSICS TESTS.

FARLEY-UNIT 1 3/4 10-4 AMENDMENT NO. 26

TABLE 2.2-I ,

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETFOINTS "1

y FUNCTIONAL UNIT TRIP SETPOINT ALLCWABLE VALUES

. c -

Z y 2. . Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - 5 25.4% of RATED THERMAL POWER THERMAL PCWER '

High Setpoint - s 109% of RATED High Setpoint - 5 109.4% of RATED THERMAL POWER THERMAL POWER

3. ' Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with 5 5.4% of RATED THERMAL POWER High Positive Rate a time constant 2 2 econds with a time constant 2 2 seconds
4. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 5.4% of RATED THEFMAL POWER

, High Negative Rate a time constant 2 2 seconds with a time consta st 2 2 seconds

5. Intermediate Range, Neutron s 35% of RATED THERMAL POWER S 40% of RATED THERMAL POWER l g -Flux t
6. Source Rance, Neutron Flux s 105 counts per second s 1.3 X 105 counts per second
7. Overtemperature AT See Note 1 See Note 3
8. Overpower AT See Note 2 See Note 6
9. Pressurizer Pressure--Low 2 1865 psig 2 1862 psig i
10. Pressurizer Pressure--High s 2385 psig s 2388 psig  !

I

11. Pressurizer Water s 925 of instrument span s 92.4% of instrument span tr L-vel--High z

g 12. Loss of Flow 2 90% of minimum measured flow 2 89.7% of minimaum measured flow t1 per loop

  • per loop *  !

O Z

O

  • Minimum measured flow is 88,100 gpm per loop.

r

_ ,- , -_-m

l l I LIMITING SAFETY SYSTIM SETTINGS BASES Intermediate and Source Ranae, Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup. These trips provide redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels. The Source Range Channels will initiate a reactor trip at about 10+5 counts per second uniens manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless l manually blocked when P-10 becomes active. No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the a7c. dent analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Rohetor Protection System, n

Overtemperature AT The overtemperature delta T trip provides core protection to prevent DNB for all tambinations of pressure, power, coolant temperature, and axial power distribution, provided that the tranutent is slow with respect to piping transit, thermowell, and RTD response time delays from the core to the temperature detectors (about 4 seconds), and pressure is t#ithin the range between the High and Low Pressure reactor tripe This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for transport, thermowell, and AfD response time delays from the core to RTD output indication. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peake are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the Pa8 setpoint and associated trip will prevent DNS during 2 loop operation exclusive of the overtemperature delta T setpoint.

Two loop operation above the 3 loop P-8 setpoint is permissible af ter resetting the K1, K2, and K3 inputs to the Overtemperature delta T channels and raising the P-8 setpoint to its 2 loop value. In this mode of operation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced power level.

FARLEY-UNIT 1 B 2-4 AMENDMENT NO.

l

SPECIAL TEST EXCEPTIONS e'

)].id 0. 3 P11YSICS TggIl LIMITING CONDITION FOR OPERATION

=a.

3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of PitySICS TESTS provided

a. The THERMAL POWr.R does not exceed 5% of RATED THERMAL POW 1:R, and l
b. The Reactor Coolant System lowest operating loop temperature (Tavg) l is greator than or equal to 531'F.

APPLICABILIIIs HODE 2.

ACTION:

a. . With the THERMAL POWER greater than 5% of RATED THERMAL POWER, immediately open the reactor trip breakers,
b. With a Reactor Coolant System operating loop temperature (Tavg) less than 531'F, restore Tavg to within its limit within 15 minutes or be in at least HOT STANDBY within the next 15 minutes.

SURVEILLANCE REQU1REMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperaturo (Tavg) shall be determined to be greater than or equal to 531*F at least once por 30 minutes during PHYSICS TESTS.

FARLE.*-UNIT 1 3/4 10-3 AMENDKENT No.

SPECI AL TES? EXCEFFIQJig 3/4.10.4 _._ REACTOR COOLANT LOQM LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of start up and PHYSICS TESTS provided the THERMAL POWER does not exceed the P-7 Interlock setpo nt.

hPPLICABILITY: During operation below the P-7 Interlock Setpoint.

AEI1QIf8 With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during start up and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Pcwer Range Channel and P-7 Interlock shall bo subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSIca TESTS.

FARLEY-bWIT 1 3/4 10-4 AMENDMENT NO.

4

_____.__.___m_____________.__._._ . _ - -

4 Joseph M. Farley Nuclear Plant Technical Specifications Change Request Intermediate Range Neutron Flux Reactor Trip Setpoint Unit 2 Chanced Pag _es hgr Instruction 25 Replace B 2-4 Peplace 3/4103 Replace 3/4104 Replace 3

~.

TABLE 2.2 -l

$ REACTOR TRIP SYSTEM INSTPUMENTATION TRIP SETPOINTS b '

N FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VA',UES 4

5' 1. Manual Reactor Trip Not Applicabl'.e Not Applicable H

2. Power Range, Neutron Flux Low Setpoint - $ 25% of RATED Low Setpoint - s 25.4% of RATED .l THERMAL P'JdER THERMAL POWER High S'.stpoint - 5 109% of RATED High Setpoint - 5 109.4% of RATED l THEPP.AL POWER THERMAL POWER l' 3. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with 5 5.4% of RATED THERM ROWER l i High Poaitive Rate a time constant 2 2 seconds with a time constant c seconds '

j

4. . Power Range, Nutron Flux, 5 5% of RATED TdERMAL POWER with 5 5.4% of RATED THERMAL 7 l High Negative Rate a me constant 2 2 seconds wi a time constant 2 1 seconds g 5. Intermediate Range, Neutron s  % of RATED THERMAL POWER s t of RATED THERMAL POWER 4 Flux A ^
6. St.mrce Range, Neutron Flux 5 105 counts per second s 1.3 X 105 counts per second
7. Overtemperature AT See Note 1 See Note 3
8. Overpower AT See Note 2 See Note 6
9. Pressurizer Pressure--Low ,2 1865 psig 2 1862 psig l
10. Pressurizer Pressure--High s 2385 psig s 2388 sig l
11. Pressurizer Water s 92% of instrument span s 92.4% of instrument span l h Leve? --High z

U g 12. Loss of Flow 2 90' of minimum measured flore 2 89.7% of minimum measured flow e

l g per loop

  • per loop *

' 2 .

O I

  • Minimum measured flow is 88,100 gpm per loop. l 1

LIMITING SAFETY SYSTEM SETTINGS BASES

/

/

Intermediate and Source Range, Nuclear Flux The Intermediate and Source Range, Nucl r Flux trips provide reactor core protection during reactor startup. ese trips provide redundant protection to the lov setpoint trip of e Power Range, Neutron Flux chapnels. The Source Range Channels 11 initiate a reactor trip at about 10' counts per second unless manu ly blocked when P-6 becomes active. The Intermediate Range Channels vill nitiate a reactor trip at a et rrent level proportional to approximately 4 h percent of RATED THERMAL POVER unless manually blocked when F 10 becomes active. No credit was t& ken for operation of the trips associated vith either the Intermediate or Source Range Channels in the accident analyses; however, their functional capebility at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature oT The Overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, pover, ceolant temperature, and axial pover distribution, provided that the transient is slow vith respect to piping trr--it, thermovell, land RTD response time delays from the core to the l t " ,: tature detectors (about 4 seconds), and pressure is within the range m veen the High and Lov Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water vith temperature and dynamic compensation for transport, thermovell, ano RTD response time delays from the core to hTD cutput indication. Vith nor.aal axial power distribution, this reactor trip limit is always below the core saf ety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1. {

Operation with a reactor coolant loop out of service belov the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip vill prevent DNB during 2 loop operation exclusive of the Overtemperature delta T setpoint.

Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the Kl. K2, and K3 inputs to the Overtemperature delta T channels and raising the P-8 setpoint to its 2 loop value. In this mode of operation, the P-8 interlock and trip functions as a High Neutrun Flux trip at the reduced power level.

FARLEY - UNIT 2 B 2-4 AMENDMENT NO. 85

1 * .

SPECIAL TEST EnCEPTIONS -

3/4.10.3 PHYSICS TESTS LIMITING CON 0! TION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of PNYSICS TESTS provided:

a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, e d
b. The w o @ in setpoints on the OPERABLE IntermaMAu ci,J Fvwer Range Nuclear Channels are ' n2- tnan or equal to 25% of RATED THERPAL PC'G, iig ._
b. # The Reactor Coolant System lowest operating loop t'em'perature (T**9) is greater than or equal to 531'F.

APPLICABILITY: MODE 2.

ACTION:

a. With the THERMAL POWER greater than 5% of RATED THFRMAL POWER, immediately open the reactor trip breakers.
b. less With than 531'F, a Reactor Coolant cestore i System operating loop temperature (Ttowithinitslimitwithin15min in at least HOT STANON9within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4,10.2.1 The THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POWER at least once per h ur during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperature (T shall be determined to begreaterthanorequalto531'Fatleastonceper'N)minutesdurngPHYSICS i TESTS.

FARLEY-UNIT 2 3/4 10-3

~;

CPECIAL TEST EXCEvi!0NS , ,

3/4.10.4 REACTOR' COOLANT LOOPS LIMITING ,,

0!T10N FOR OPERATION 3.10.4 The limitatier.s of $pecification 3.4. l.1 may be suspended during the performance of start up and PHYSICS TESTS provide 4(

/ f4 ep"T THERMAL POWER does not exceed the P-7 Interlock SetpointA D

_OWD t 2% E H tN APPt.lCABILITY: During operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock P tpoint, immediately open the reactor trip breakers.

SURVEltl.ANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during start up and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Ir.terlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSICS TESTS.

FARLEY-UNIT 2 3/4 10-4

~.

TABLE 2.2-1 *

!- g REACTOR TRIP SYSTEM INurwru.nlaTION TPIP SETPOINTS FUNCTIONAL UNIT TRIP..SITPOINT , JLMf*"*N VAI.tTES *

- M i *< .

i .1. Manual Reactor Trip E- Not Applicable T51e

, - x -

w'

" 2. - Power Range, Neutron Flux Low Setpoint - S 25% of RATED .5 25.4% of RATED

, THERMAL POWER i f

I.

1 High Setpoi2t - 5 209% of RATED a 1 y int - 5 109.4% of RATED

! THERMAL POWER THERMAL POWER

3. Power Range, Neutron Flux, S 5% of RATED THERMAL POWER with 5 5.4% of RATED THERMAL POWER

} High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seconda y

4. Power Range, Neutron Flux, 5 5% of F.ATED THERMAL POWER with 5 5.4% of RATED THERMAL POWER I

High Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds

-5. Intermediate Range, Peutron G 35s of RATED THERMAL POW R S 40% of RATED THE'. MAL POWER l i' y Flux

- t

. us

6. Source Range, Neutron Flux $ 105 counts per second 5 1.3 X 105 counts per second i
7. Overtemperature AT See Note 1 . See Note 3 i
8. Overpower AT- See Note 2 See Note 6
9. Pressurizer Pressure-Low 2 1865 peig 2 1862 poig u.

{~ 30. Pressurizer Pressure-High 5 2385 poig S 2388 peig l 11. Pressurizer Water S 92% of instrument span S 92.4% of instrument span 4 -Level--High i

f

'g 12. Loss of Flow 2 90% of minimum measured flow 2 89.7% of minimum measured flow g per loop

  • per loop
  • _ z

-! H i 2

?

  • Minimum measured flow is 88,100 gpm per loop.

I i

J yw -r . .s, i,.y..- ... , _ .,, ,, .- % - , . . . . + . - . _ , , , _ _ . . ,- , _wnu.,,,,y-. ,,,,_n.,-.,,re..,, ..,_.....w. _-, . - _ , _ . ~ , , , . . . . -- i

e >

LIMITINO M ETY SYSTEM SETTINGS EASES Intermediate and Source Ranos. Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup. These trips provide redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels.

The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes activo. The Intermediate Range Channels will initle.te a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unlers n.anually blocked when l P-10 becomes active. No credit was taken for operation of the trips associated with either the Intermediate or Source Range channels in the accident analyses; however, their functional capabi*ity at the epecified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemnerature 6T The Overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit, thermowell, and RTD response time delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for transport, thermowell, and RTD response time delays from the core to RTD output indication. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip will prevent DND during 2 loop operation exclusive of the Overtemperature delta T setpoint. Two loop operation above the 3 loop P-8 setpoint is permissible af ter resetting the K1, K2, and K3 inputs to the Overtemperature delta T channels and raising the P-6 metroint to its 2 loop value. In this mode of operation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced power level.

FARLEY-UNIT 2 B 2-4 AMENDMENT NO.

l . ,

1 6

SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of FIIYSICS TESTS provided:

a. s'he Tl!ERMAL POWER does not exceed 5% of RATED THERMAL POWER, and l
b. The Reactor Coolant System lowest operating loop tomperature (Tavg)  !

is greater than or equal to 531*F.

APPLICABILITY: MOsE 2.

-hCTION:

a. With the TilERMAL POWER greater than 5% of RATED THERHAL POWER, immediately open the reactor trip breakurs.
b. With a Reactor Coolant System operating loop temperature (Tavg) less than 531*F, restore T avg to within its limit within 15 minutes or be in at least iiOT STANDBY within the next 15 minutes.

SURVEILLANCE ItEQUIREMEbTS ,

4.10.3.1 The TiiERMAL POWER shall be determined to be lass than or equal to 5%

of RATED TIIERMAL POWER at least once per hour during PIIYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEFT within 12 houro prior to initiating PliYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperature (T av shall be determined to begreaterthanorequalto531*Fatleastonceper3b)minutesduringPHYSICS TESTS.

FARLEY-UNIT 2 3/4 10-3 AMENDMENT NO.

o gfECIAL TEST _. EXCEPTIONS 3/4.10.4 REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.3 may be suspended during the performance of start up and PHYSICS TESTS provided the THERMAL POWER does not exceed the P-7 Interlock Setpoint.

hPILICADILITYs During operation below the P-7 Interlock Setpoint.

hC112HL With the THERMAL POWER greater tha.) the P-7 Interlock Setpoint, inanediately open the reactor trip breakers. '

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSICS TESTS.

FARLEY-UNIT 2 3/4 10-4 AMENDMENT NO.

e ATTACllMENT II Joseph M. Farley Nuclear Plant Technical Specifications Change Request intermediate Range Neutron Flux kcactor Trip ietpoint Westinghouse letter CAW 97 1017, dated February 10,1997, " Application For Withholding Proprietary Information From Public Disclosure," with the following enclosures: Affidavit, Proprietary Information Notice, and Copyright Notice, NSA SSO 96 524, Revision I," Joseph M. Farley Nuclear Plant Safety Analysis intermediate Range Neutron Flux Reactor Trip Setpoint Change," Westinghouse Proprietary Class 2C.

NSA SSO 96 525, Revision 1," Joseph M. Farley Nuclear Plant Safety Analysis Intermediate Range Neutron Flux Reactor Trip Setpoint Change," Westinghouse Class 3 Non Proprietary,

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