ML040570699

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Informational Copy of Operating License & Appendices. Technical Specification Pages 3.3-1 Through 3.3-19 for Amendment 176
ML040570699
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 02/18/2004
From:
Progress Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
Download: ML040570699 (20)
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Text

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1 The RPS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

--1-___-__-_-----_1---------------- --NOTE-------------------------------------

Separate Condition entry is allowed for each Function.

-__-___--_---------_------------------------------------------------------- - e-CONDITION REQUIRED ACTION COMPLETIONTIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels Table 3.3.1-1 for the inoperable. channel(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel OPERABLE status.

inoperable.

B.2.1 Be in MODE3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> B.2.2 Open reactor trip 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> breakers (RTBs).

(continued)

HBRSEP Unit No. 2 3.3-l Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETIONTIME C. One channel or train c.1 Restore channel or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. train to OPERABLE status.

or c.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> D. One Power Range D.l.l Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Neutron Flux-High trip.

channel inoperable.

AND D.1.2 Reduce THERMAL POWER 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to < 75% RTP.

D.2.1 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.

AND

~~~~I-~~~-~-~ NOTE---------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

___________________-____I____

D.2.2 Perform SR 3.2.4.2. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR D.3 Be in MODE3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

HBRSEP Unit No. 2 3.3-2 Amendment No. 176

RPS Instrument;t;o~

ACTIONS ~continued)

CONDITION REQUIRED ACTION 3MPLETION TIME E. One channel E.1 Place channel in hours inoperable. trip.

x E.2 Be in MODE3. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> F. THERMALPOWER ' P-6 F.l l??dy;-;HERMAL POWER hours and c P-10, one Intermediate Range Neutron Flux channel RR inoperable.

F.2 Increase THERMAL hours POWER to ' P-10.

G. THERMAL POWER

' P-6 G.l ________NOTE--s____--

and < P-10, two Limited boron Intermediate Range concentration changes Neutron Flux channels associated with RCS inoperable. inventory control or limited plant temperature changes are allowed.

Suspend operations mmediately involving positive reactivity additions.

6.2 l??d,c,~~HERMALPOWER hours (continued)

HBRSEPUnit No. 2 3.3-3 AmendmentNo. f76.190

RPS Instrumentation NS (cQ&U.E&

CONDITION REQUIRED ACTION COMPLETION TIME H. THERMALPOWER < P-6, -1.1 Restore channel(s) to Prior to one or two OPERABLE status. increasing Intermediate Range l--EEM;A6POWER Neutron Flux channels inoperable.

I.1 --------NOTE---------

I. One Source Range Neutron Flux channel Limited boron inoperable. concentration changes associated with RC5 inventory control or limited plant temperature changes are allowed.

Suspend operations Immediately involving positive reactivity additions.

J. Two Source Range J.l Open RTBs. Immediately Neutron Flux channels inoperable.

K. One Source Range K.l Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.

inoperable.

OF3 K.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> (continued)

HBRSEPUnit No. 2 3.3-4 AmendmentNo. 376.190

RPS Instrumentation 3.3.1 s (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I

-. RPnuirPd __ Source

--_.. -- Range ___---- ------NOTE-----------

-1 .

NmO-rnn

..---. -.. Flux .-.. Plant temperature changes are channel(s) inoperable. allowed provided the temoerature change is

,accounted for in-the Icalculated SDM.

L.l Suspend operations Immediate1 y involving positive reactivity additions.

L.2 Close unborated water 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> source isolation valves.

At!lD L.3 Perform SR 3. 1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (continued)

HBRSEPUnit No. 2 3.3-4a AmendmentNo. 35X.190 I

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETIONTIME M. One channel M.l Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> inoperable. trip.

or M.2 Reduce THERMAL POWER 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to < P-7.

N. One Reactor Coolant N.l Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Flow - Low (Single trip.

Loop) channel inoperable. OR N.2 Reduce THERMAL POWER 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to < P-8.

0. One Reactor Coolant 0.1 Restore channel to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Pump Breaker Position OPERABLE status.

channel inoperable.

OR 0.2 Reduce THERMAL POWER 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to < P-8.

P. One Turbine Trip P.l Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel inoperable. trip.

P.2 Reduce THERMAL POWER 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to < P-7.

(continued)

HBRSEP Unit No. 2 3.3-5 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETIONTIME Q. One train inoperable. I~~~~~~~~~~~ NOTE-------

One train may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided the other train is OPERABLE.

____-______I____-___--------

Q.1 Restore train to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OPERABLE status.

or Q-2 Be in MODE3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> R. One RTB train ~~1~~1~~~~~~ NOTE------

inoperable. One train may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, provided the other train is OPERABLE.

_1_______________-_1---------

R.l Restore train to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

or R.2 Be in MODE3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (continued)

HBRSEP Unit No. 2 3.3-6 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETIONTIME S. One channel s.l Verify interlock is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. in required state for existing unit conditions.

OR s.2 Be in MODE3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> T. One channel T.l Verify interlock is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. in required state for existing unit conditions.

OR T.2 Be in MODE2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> U. One trip mechanism u.l Restore inoperable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one trip mechanism to RTB. OPERABLE status.

OR U.2.1 Be in MODE3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> AND U.2.2 Open RTB. 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> V. Two RPS trains v.l Enter LCO 3.0.3. Immediately inoperable.

HBRSEP Unit No. 2 3.3-7 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

_--_________________----------------- NOTE-------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RPS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.2 -------------------NOTES-------------------

1. Adjust NIS channel if absolute difference is > 2%.
2. Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWERis

> 15% RTP.

Compare results of calorimetric heat 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> balance calculation to Nuclear Instrumentation System (NIS) channel output.

SR 3.3.1.3 -------------------NOTES-------------------

1. Adjust NIS channel if absolute difference is > 3%.
2. Not required to be performed until 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after THERMAL POWERis

> 15% RTP.

Compare results of the incore detector 31 effective measurements to NIS AFD. full power days (EFPD)

(continued)

HBRSEP Unit No. 2 3.3-8 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 -------------------NOTE--------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

______--------------l_l_________________---

Perform TADOT. 31 days on a STAGGEREDTEST BASIS SR 3.3.1.5 -------------------NOTE--------------------

Not required to be performed for the logic inputs from Source Range Neutron Flux detector prior to entering MODE3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE3.

-__-------_---_I---_-----------------------

Perform ACTUATION LOGIC TEST. 31 days on a STAGGEREDTEST BASIS SR 3.3.1.6 -------------------NOTE--------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWERis > 50% RTP.

Calibrate excore channels to agree with 92 EFPD incore detector measurements.

SR 3.3.1.7 -------------------NOTE--------------------

Not required to be performed for source range instrumentation prior to entering MODE3 from MODE2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE3.

___-1----1------.--------------------------

Perform COT. 92 days (continued)

HBRSEP Unit No. 2 3.3-9 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.8 -------------------NOTE--------------------

This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT. - -

NOTE-----

Only required when not performed within previous 92 days

~1~~--~~-~~~~~1 Prior to reactor startup AND Four hours after reducing power below P-10 for power and intermediate instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 92 days thereafter (continued)

HBRSEP Unit No. 2 3.3-10 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 92 days SR 3.3.1.10 -------------------NOTE--------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values where applicable.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.11 ---NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.12 -------------------NOTE--------------------

This Surveillance shall include verification that the electronic dynamic compensation time constants are set at the required values, and verification of RTD response time constants.

_1__-_-_______1-____-----------------------

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.13 Perform COT. 18 months (continued)

HBRSEP Unit No. 2 3.3-11 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.14 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.1.15 -------------------NOTE-------------------- I-M-- NOTE----

Verification of setpoint is not required. Only required when not performed within previous 31 days

~~~~~~~~1~1~~~~

Perform TADOT. Prior to reactor startup HBRSEP Unit No. 2 3.3-12 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

1. Manual Reactor 1.2 2 6 SR 3.3.1.14 NA NA Trip 3(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA NA
2. Power Range Neutron Flux
a. High 1.2 4 D SR 3.3.1.1 <110.93% 108%

SR 3.3.1.2 RTP RTP (2)

SR 3.3.1.7 SR 3.3.1.11

b. Low l(b),2 4 E SR 3.3.1.1 < 26.93% 24% RTP SR 3.3.1.8 RTP SR 3.3.1.11
3. Intermediate Range 2 F.G SR 3.3.1.1 < 37.02% 25% RTP Neutron Flux SR 3.3.1.8 RTP SR 3.3.1.11 2 H SR 3.3.1.1 < 37.02% 25% RTP SR 3.3.1.8 RTP SR 3.3.1.11
4. Source Range 2(d) 2 1.J SR 3.3.1.1 < 1.28 E5 1.0 E5 Neutron Flux SR 3.3.1.8 cps cps SR 3.3.1.11 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1 < 1.28 E5 1.0 E5 SR 3.3.1.7 cps cps SR 3.3.1.11 3(e), 4(e), 5(e) 1 L SR 3.3.1.1 N/A N/A SR 3.3.1.11 (continued)

(1) A channel is OPERABLEwith an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(2) The Nominal Trip Setpoint is as stated unless reduced as required by one or more of the following requirements:

LCO 3.2.1 Required Action A.2.2: LCO 3.2.2 Required Action A.1.2.2; or LCO 3.7.1 Required Action 8.2.

(a) With Rod Control System capable of rod withdrawal, or one or more rods not fully inserted.

(b) Below the P-10 (Power Range Neutron Flux) interlock.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlock.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlock.

(e) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication and alarm.

HBRSEP Unit No. 2 3.3-13 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

5. Overtemperature AT 1.2 3 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 Note 1 SR 3.3.1.6 (Page (Page SR 3.3.1.7 3.3-18)

SR 3.3.1.12 3-:3:8

6. Overpower AT 1.2 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 2 Note 2 SR 3.3.1.6 (Page (Page SR 3.3.1.7 3.3-19)

SR 3.3.1.12 (3)

7. Pressurizer Pressure
a. Low l(f) 3 M SR 3.3.1.1 > 1832.02 1844 SR 3.3.1.7 psig psig SR 3.3.1.10
b. High 1.2 3 E SR 3.3.1.1 < 2381.11 2376 SR 3.3.1.7 psig psig SR 3.3.1.10
8. Pressurizer Water l(f) 3 M SR 3.3.1.1 93.47% 94.26%

loop SR 3.3.1.7 SR 3.3.1.10

b. Two Loops l(h) 3 per M  ;; ;.;.;.; > 93.47% 94.26%

loop SR 3:3:1:10

10. Reactor Coolant Pump (RCP) Breaker Position
a. Single Loop l(9) 1 per 0 SR 3.3.1.14 NA NA RCP
b. Two Loops l(h) 1 per M SR 3.3.1.14 NA NA RCP
11. Undervoltage l(f) 1 per M SR 3.3.1.9 > 2959 v 3120 V RCPs bus SR 3.3.1.10
12. Underfrequency l(f) 1 per M SR 3.3.1.10 > 57.84 58.2 Hz bus SR 3.3.1.14 Hz
13. Steam 1.2 3 per SG E SR 3.3.1.1 > 15.36% 16%

Generator (SG) SR 3.3.1.7 Water Level - Low SR 3.3.1.10 Low (continued)

(1) A channel is OPERABLEwith an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(f) Above the P-7 (Low Power Reactor Tri s Block) interlock.

(g) Above the P-8 (Power Range Neutron F7ux) interlock.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

HBRSEP Unit No. 2 3.345 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

14. SG Water 1.2 2 per SG E SR 3.3.1.1 > 29.36% 30%

Level -Low SR 3.3.1.7 SR 3.3.1.10 Coincident with 1.2 2 per SG E SR 3.3.1.1 < 7.06 E5 6.4 E5 Steam Flow/ SR 3.3.1.7 lbm/hr lbm/hr Feedwater Flow SR 3.3.1.10 Mismatch 15 Turbine Trip 3 P SR 3.3.1.10 > 40.87 45 psig

a. Low Auto Stop I(f) SR 3.3.1.15 wig Oil Pressure NA
b. Turbine Stop I(f) 2 P SR 3.3.1.15 NA Valve Closure 16 Safety 1.2 2 trains Q SR 3.3.1.14 NA NA Injection S1)

Input from Engineered Safety Feature Actuation System (ESFAS)

(continued)

(1) A channel is OPERABLEwith an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(f) Above the P-7 (Low Power Reactor Trips Block) interlock.

HBRSEP Unit No. 2 3.3-16 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

17. Reactor Protection System Interlocks
a. Intermediate 2(d) 2 S SR 3.3.1.11 > 7.29 1 E-10 Range Neutron SR 3.3.1.13 E-11 amp amp Flux, P-6
b. Low Power 1 1 per T SR 3.3.1.13 NA NA Reactor Trips train SR 3.3.1.14 Block, P-7 C. Power Range 1 4 T SR 3.3.1.11 < 42.94% 40% RTP Neutron Flux, SR 3.3.1.13 RTP P-8
d. Power Range 1.2 4 S SR 3.3.1.11 >7.06% 10% RIP Neutron Flux, RTP and <

P-10 12.94%

RTP

e. Turbine Impulse 1 2 T SR 3.3.1.1 < 10.71% 10%

Pressure, P-7 SR 3.3.1.10 turbine turbine input SR 3.3.1.13 power power

18. Reactor Trip 1.2 2 trains R,V SR 3.3.1.4 NA NA Breakers 3(a), 4(a), 5(a) 2 trains c,v SR 3.3.1.4 NA NA
19. Reactor Trip 1.2 1 each U SR 3.3.1.4 NA NA Breaker per RTB Undervoltage and Shunt Trip 3(a), 4(a), 5(a> 1 each C SR 3.3.1.4 NA NA Mechanisms per RTB
20. Automatic Trip l(j),, 2 trains Q.V SR 3.3.1.5 NA NA Logic 3(a), 4(a), ,(a) 2 trains c.v SR 3.3.1.5 NA NA (1) A channel is OPERABLEwith an actual Trip Setpoint value found outside its calibration tolerance band provi ded the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(a) With Rod Control System capable of rod withdrawal, or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlock.

(1) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

(J) Below the P-6 (Intermediate Range Neutron Flux) interlock for the logic inputs from Source Range Neutron F lux detector channels.

HBRSEP Unit No. 2 3.347 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-3. (page 6 of 7)

Reactor Protection System Instrumentation

. vertmp&.urt! AT The Overtemperature AT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 2.96% of AT span.

AT setpoint5 A TO KI - K2 --(+) (T - T)+&(P - P)- fib I)

Cl+ 2.?S)

Where: ATO is the indicated AT at RTP, "F.

s is the Laplace transform operator, sec.

T is the measured RCS average temperature, "F.

T' is the reference Tavg at RTP, < 575.9OF.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, I 2235 psig Kl zz 1.1265 K2 = O.O1228/OF K3 = 0.00089/psig TI 2 20.08 set ~2 5 3.08 set f(N) = 2.4{(qb - Cjt) - 17) when qt - qb c - 17% RTP 0% of RTP when -17% RTP < qt - qb 5 12% RTP 2.4{(qt - qb) - 12) when qt - qb > 12% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWERin percent RTP.

HBRSEP Unit No. 2 3.3-18 Amendment No. 196

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Protection System Instrumentation

. verger AT The Overpower AT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 3.17% of AT span.

Where: ATO is the indicated AT at RTP, OF.

s is the Laplace transform operator, set?

T is the measured RCS average temperature, "F.

T' is the reference Tavs at RTP, < 575.9OF.

K4 < 1.06 K5 2 O.O2/OF for increasing Tavs KG 2 O.O0277/OF when T > T' O/OF for decreasing Tavs O/OF when T < T'

~3 2 9 set WI) = as defined in Note 1 for Overtemperature AT HBRSEP Unit No. 2 3 . :3- 19 Amendment No. 196

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