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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{{#Wiki_filter: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 A. One or more Functions with one or more required channels inoperable. B. One Manual Reactor Trip channel inoperable. HBRSEP Unit No. 2 REQUIRED ACTION COMPLETION TIME A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s). Immediately B.1 Restore channel to OPERABLE status. 48 hours B.2.1 Be in MODE 3. 54 hours B.2.2 Open reactor trip breakers (RTBs). 55 hours 3.3-l (continued) Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued) CONDITION C. One channel or train inoperable. D. One Power Range Neutron Flux-High channel inoperable. HBRSEP Unit No. 2 REQUIRED ACTION c.1 Restore channel or train to OPERABLE status. or c.2 Open RTBs. D.l.l Place channel in trip. AND D.1.2 Reduce THERMAL POWER to < 75% RTP. D.2.1 Place channel in 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. OR D.3 Be in MODE 3. 3.3-2 COMPLETION TIME 48 hours 49 hours 6 hours 12 hours 6 hours Once per 12 hours 12 hours (continued) Amendment No. 176

RPS Instrument;t;o~ ACTIONS ~continued) CONDITION E. One channel inoperable. F. THERMAL POWER ' P-6 and c P-10, one Intermediate Range Neutron Flux channel inoperable. G. THERMAL POWER ' P-6 and < P-10, two Intermediate Range Neutron Flux channels inoperable. HBRSEP Unit No. 2 REQUIRED ACTION E.1 Place channel in trip. x E.2 Be in MODE 3. F.l l??dy;-;HERMAL POWER RR F.2 Increase THERMAL POWER to ' P-10. G.l ________ NOTE--s ____-- Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed. Suspend operations involving positive reactivity additions. 6.2 l??d,c,~~HERMAL POWER 3.3-3 3MPLETION TIME hours 2 hours hours hours mmediately hours (continued) Amendment No. f76.190

RPS Instrumentation NS (cQ&U.E& CONDITION H. THERMAL POWER < P-6, one or two Intermediate Range Neutron Flux channels inoperable. I. One Source Range Neutron Flux channel inoperable. J. Two Source Range Neutron Flux channels inoperable. K. One Source Range Neutron Flux channel inoperable. REQUIRED ACTION -1.1 Restore channel(s) to OPERABLE status. I.1

NOTE---------

Limited boron concentration changes associated with RC5 inventory control or limited plant temperature changes are allowed. Suspend operations involving positive reactivity additions. J.l Open RTBs. K.l Restore channel to OPERABLE status. OF3 K.2 Open RTBs. HBRSEP Unit No. 2 3.3-4 COMPLETION TIME Prior to increasing l--EEM;A6POWER Immediately Immediately 48 hours 49 hours (continued) Amendment No. 376.190

RPS Instrumentation 3.3.1 s (continued) CONDITION REQUIRED ACTION -1 NmO-rnn Flux I RPnuirPd Source Range ___---- ------NOTE----------- Plant temperature changes are channel(s) inoperable. allowed provided the temoerature change is I accounted for in-the calculated SDM. L.l Suspend operations involving positive reactivity additions. valves. At!lD L.3 Perform SR 3. 1.1.1. L.2 Close unborated water source isolation HBRSEP Unit No. 2 3.3-4a COMPLETION TIME Immedi ate1 y 1 hour 1 hour Once per 12 hours thereafter (continued) Amendment No. 35X.190 I

RPS Instrumentation 3.3.1 ACTIONS (continued) CONDITION M. One channel inoperable. N. One Reactor Coolant Flow - Low (Single Loop) channel inoperable.

0.

One Reactor Coolant Pump Breaker Position channel inoperable. P. One Turbine Trip channel inoperable. REQUIRED ACTION M.l Place channel in trip. or M.2 Reduce THERMAL POWER to < P-7. N.l Place channel in trip. OR N.2 Reduce THERMAL POWER to < P-8. 0.1 Restore channel to OPERABLE status. OR 0.2 Reduce THERMAL POWER to < P-8. P.l Place channel in trip. P.2 Reduce THERMAL POWER to < P-7. COMPLETION TIME 6 hours 12 hours 6 hours 10 hours 6 hours 10 hours 6 hours 10 hours (continued) HBRSEP Unit No. 2 3.3-5 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued) CONDITION REQUIRED ACTION Q. One train inoperable. R. One RTB train inoperable. HBRSEP Unit No. 2 I~~~~~~~~~~~ NOTE------- One train may be bypassed for up to 12 hours provided the other train is OPERABLE. ____-______I____-___-------- Q.1 Restore train to OPERABLE status. or Q-2 Be in MODE 3. ~~1~~1~~~~~~ NOTE------ One train may be bypassed for up to 12 hours, provided the other train is OPERABLE. _1_______________-_1--------- R.l Restore train to OPERABLE status. or R.2 Be in MODE 3. 3.3-6 COMPLETION TIME 6 hours 12 hours 1 hour 7 hours (continued) Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued) CONDITION S. One channel inoperable. T. One channel inoperable. U. One trip mechanism inoperable for one RTB. V. Two RPS trains inoperable. REQUIRED ACTION s.l Verify interlock is in required state for existing unit conditions. OR s.2 Be in MODE 3. T.l Verify interlock is in required state for existing unit conditions. OR T.2 Be in MODE 2. u.l Restore inoperable trip mechanism to OPERABLE status. OR U.2.1 Be in MODE 3. AND U.2.2 Open RTB. v.l Enter LCO 3.0.3. COMPLETION TIME 1 hour 7 hours 1 hour 7 hours 48 hours 54 hours 55 hours Immediately 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 SR 3.3.1.1 Perform CHANNEL CHECK. SR 3.3.1.2

NOTES-------------------

1.

Adjust NIS channel if absolute difference is > 2%.

2.

Not required to be performed until 12 hours after THERMAL POWER is > 15% RTP. Compare results of calorimetric heat 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 hours after THERMAL POWER is > 15% RTP. Compare results of the incore detector measurements to NIS AFD. HBRSEP Unit No. 2 3.3-8 FREQUENCY 12 hours 24 hours 31 effective full power days (EFPD) (continued) Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE 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. SR 3.3.1.5

NOTE--------------------

Not required to be performed for the inputs from Source Range Neutron Flux logic detector prior to entering MODE 3 from MODE 2 until 4 hours after entry into MODE 3. -__-------_---_I---_----------------------- Perform ACTUATION LOGIC TEST. SR 3.3.1.6

NOTE--------------------

Not required to be performed until 24 hours after THERMAL POWER is > 50% RTP. Calibrate excore channels to agree with incore detector measurements. SR 3.3.1.7

NOTE--------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours after entry into MODE 3. ___-1----1------.-------------------------- Perform COT. HBRSEP Unit No. 2 3.3-9 FREQUENCY 31 days on a STAGGERED TEST BASIS 31 days on a STAGGERED TEST BASIS 92 EFPD 92 days (continued) Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE 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. HBRSEP Unit No. 2 3.3-10 FREQUENCY 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) Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE SR 3.3.1.9

NOTE--------------------

Verification of setpoint is not required. Perform TADOT. 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. SR 3.3.1.11 ---NOTE-------------------- Neutron detectors are excluded from CHANNEL CALIBRATION. Perform CHANNEL CALIBRATION. 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. SR 3.3.1.13 Perform COT. FREQUENCY 92 days 18 months 18 months 18 months 18 months (continued) HBRSEP Unit No. 2 3.3-11 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE SR 3.3.1.14

NOTE--------------------

Verification of setpoint is not required. Perform TADOT. SR 3.3.1.15

NOTE--------------------

Verification of setpoint is not required. Perform TADOT. FREQUENCY 18 months I-M-- NOTE---- Only required when not performed within previous 31 days ~~~~~~~~1~1~~~~ Prior to reactor startup HBRSEP Unit No. 2 3.3-12 Amendment No. 176

RPS Instrumentation 3.3.1 Reactor Table 3.3.1-1 (page 1 of 7) Protection System Instrumentation FUNCTION APPLICABLE MODES NOMINAL TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

1.

Manual Reactor Trip

2.

Power Range Neutron Flux

a.

High 1.2

b.

Low

3.

Intermediate Range Neutron Flux

4.

Source Range Neutron Flux 1.2 3(a), 4(a), 5(a) l(b),2 2(d) 3(a), 4(a), 5(a) 3(e), 4(e), 5(e) 2 6 2 C 4 D 4 E 2 F.G 2 H 2 1.J 2 J,K 1 L SR 3.3.1.14 SR 3.3.1.14 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.11 NA NA <110.93% RTP < 26.93% RTP < 37.02% RTP < 37.02% RTP < 1.28 E5 cps < 1.28 E5 cps N/A NA NA 108% RTP (2) 24% RTP 25% RTP 25% RTP 1.0 E5 cps 1.0 E5 cps N/A (continued) (1) A channel is OPERABLE with 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: (a) 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. 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. indication and alarm. In this condition, source range Function does not provide reactor trip but does provide 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 FUNCTION APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

5.

Overtemperature AT 1.2 3 E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12

6.

Overpower AT

7.
8.

1.2 E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 Pressurizer Pressure

a.

Low l(f) 3 M SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10

b.

High 1.2 3 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 Pressurizer Water l(f) 3 M SR 3.3.1.1 Level -High SR 3.3.1.7 SR 3.3.1.10 Refer to Note 1 (Page 3.3-18) Refer to Note 1 (Page 3-:3:8 Refer to Note 2 (Page 3.3-19) Refer to Note 2 (Page (3) > 1832.02 1844 psig psig < 2381.11 psig 2376 psig 93.47% 94.26% > 93.47% 94.26% NA NA NA NA > 2959 v 3120 V > 57.84 58.2 Hz Hz > 15.36% 16% (continued) (1) A channel is OPERABLE with 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 F ux) 7 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 FUNCTION APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

14.

SG Water 1.2 2 per SG E SR 3.3.1.1 > 29.36% 15 16 Level -Low Coincident with Steam Flow/ Feedwater Flow Mismatch 1.2 Turbine Trip

a. Low Auto Stop Oil Pressure I(f)
b. Turbine Stop Valve Closure I(f)

Safety Injection S1) Input from Engineered Safety Feature Actuation System (ESFAS) 1.2 SR 3.3.1.7 SR 3.3.1.10 2 per SG E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 3 P SR 3.3.1.10 SR 3.3.1.15 2 P SR 3.3.1.15 2 trains Q SR 3.3.1.14 < 7.06 E5 lbm/hr > 40.87 wig NA NA 30% 6.4 E5 lbm/hr 45 psig NA NA (continued) (1) A channel is OPERABLE with 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 FUNCTION APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SETPOINT CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

17.

Reactor Protection System Interlocks

a.

Intermediate Range Neutron

Flux, P-6
b.

Low Power Reactor Trips

Block, P-7 C.

Power Range Neutron Flux, P-8

d.

Power Range Neutron Flux, P-10

e.

Turbine Impulse

Pressure, P-7 input
18.

Reactor Trip Breakers

19.

Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms

20.

Automatic Trip Logic 2(d) 2 S 1 1 1.2 1 per train T 4 T 4 S 1 1.2 3(a), 4(a), 5(a) 1.2 3(a), 4(a), 5(a> l(j),, 3(a), 4(a), ,(a) 2 2 trains 2 trains 1 each per RTB 1 each per RTB 2 trains 2 trains T R,V c,v U C Q.V c.v SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.13 SR 3.3.1.14 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.10 SR 3.3.1.13 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.5 > 7.29 1 E-10 E-11 amp amp NA NA < 42.94% RTP 40% RTP >7.06% RTP and < 12.94% RTP < 10.71% turbine power 10% RIP 10% turbine power NA NA NA NA NA NA NA NA NA NA NA NA (1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provi the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is (a) re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. 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) (J) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. Below the P-6 (Intermediate Range Neutron Flux) interlock for the logic inputs from Source Range Neutron F detector channels. ded lux 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 setpoint 5 A TO (+) (T KI - K2 -- Cl+ 2.?S) - T)+&(P - P)- fib I) 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 POWER in 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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