Sro Rps Wk4

Front 1

The plant is operating at 100% power, with all systems and controls in normal alignment. A Small Break LOCA occurs.What is the Reactor trip setpoint and coincidence as RCS pressure decreases? A. 1940 psig on three of four instruments, get one protection train, and one reactor trip breaker.B. 1970 psig on two of four instruments, get both protection trains, and both reactor trip breakers.C. 1940 psig on two of four instruments, get both protection trains, and both reactor trip breakers.D. 1970 psig on three of four instruments, get one protection train, and one reactor trip breaker.

Back 1

C

Front 2

What is the C-9 setpoint and logic coincidence? A. <4.0" HgA on 2/2 pressure switchesB. <5.0" HgA on 2/2 pressure switchesC. <5.0 "HgA on 1/2 pressure switchesD. <4.0" HgA on 1/2 pressure switches

Back 2

B

Front 3

The plant is at 100% power when a Tavg circuit fails low (after the Th/Tc averaging). Procedure guidance places the Tavg circuit in "DEFEAT" for the affected loop.What is the adverse consequence if this action is NOT performed? A. Steam dump P-12 interlock prematurely secures steam dumps.B. C-16 prevents using the "Load Decrease Rate circuit".C. Cold overpressure protection circuit sets the pressure setpoint too low.D. Feedwater isolation occurs prematurely with a P-4.

Back 3

B

Front 4

The following conditions exist:A plant startup is in progress, the RCS is currently at 4500F and 1800 psig. The reactor operator raises Reactor Coolant System (RCS) pressure to 2235 psig to perform post-maintenance testing on a Pressurizer Power Operated relief valve.Which one of the following explains the response of the Engineered Safety Features (ESF) for this event? A. SIS and MSLIS actuate on low pressurizer pressure when P-11 energizes.B. SIS actuates on low pressurizer pressure and MSLIS will not actuate.C. SIS will not actuate, but MSLIS actuates on low steam line pressure.D. SIS and MSLIS actuate on low steam line pressure when P-11 de-energizes.

Back 4

D

Front 5

Which one of the following signals resets only by depressing the FWIS RESET switch? A. Low Tavg with P-4B. AFASC. Low-Low steam generator levelD. P-14, High-High steam generator level

Back 5

A

Front 6

Which one of the following uses P-4 as an input to actuate Engineered Safety Features Actuation (ESFAS)? A. Feedwater IsolationB. Steamline IsolationC. Containment Spray ActuationD. Auxiliary Feedwater Actuation

Back 6

A

Front 7

What trip is directly associated with the P-8 permissive? A. Turbine tripB. Pressurizer high pressureC. RCP undervoltageD. Loss of flow on Two loops

Back 7

D

Front 8

At 100% power, NIS channel N41 failed high. All required bistables were tripped as required by Technical Specifications. An ECCS pump failure now requires a T/S shutdown. During this reduction the RO reports readings on the NI channels are:N42 - 7% N43 - 14% N44 - 6%What actions should be taken? A. Trip the reactor and have I & C place the P-10 permissive in a non-tripped (Light Off) condition.B. Have I & C place the P-10 permissive in the tripped (Light On) condition then trip the reactor.C. Bypass N41 and continue power reduction.D. Remove control power fuses from the N43 power range drawer and have I & C trip associated bistables.

Back 8

A

Front 9

Assume S/G level has been restored to 50% narrow range with Auxiliary Feed Water flow. What manipulations would be required to reopen the FWIVs following a P-14 turbine/reactor trip? A. Recharge hydraulic accumulators.B. Close reactor trip breakers.C. Reset SI.D. At both MSFIS Cabinets reset each FWIV (using Operate Switches).

Back 9

D

Front 10

The plant is at 100% power when the controlling channel for "A" Steam Generator (S/G) level control fails to 0%.With no operator action, what is the plant response? A. Reactor trip on S/G Lo-Lo Level.B. Feedwater flow to S/G "A" will initially increase, then decrease causing S/G level to stabilize at a level higher than program.C. Reactor trip on P-14 turbine trip.D. Feedwater flow to S/G "A" will initially decrease, then increase causing S/G level to stabilize at a level lower than program.

Back 10

C

Front 11

At 100% power the controlling S/G level channel on S/G "A" fails to 100%.With no operator action, what is the plant response? A. Feedwater flow to S/G "A" will initially increase, then decrease causing S/G level to stabilize at a level higher than program.B. Reactor trip on P-14 turbine trip.C. Reactor trip on S/G Lo-Lo Level.D. Feedwater flow to S/G "A" will initially decrease, than increase causing S/G level to stabilize at a level lower than program.

Back 11

C

Front 12

What protective function is NOT common between PZR Pressure Channels PT-455 and PT-458? A. P-11B. OTdeltaTC. Low pressure reactor tripD. High pressure reactor trip

Back 12

A

Front 13

Main Steam Line Isolation will occur if: A. 1/3 pressures < 615 psig in 2/4 main steam linesB. 2/3 High Containment pressures > 3.5 psigC. 2/3 pressure rates > setpoint in 1/4 main steam lines if low steam line pressure isolation has been blocked below P-11D. 1/3 pressure rates > setpoint in 2/4 main steam lines if low steam line pressure isolation has been blocked below P-11

Back 13

C

Front 14

Wolf Creek is operating at 95% RTP when the Feedwater Regulating Valve, AE FCV-530, fails to the full open position and the BOP operator is unable to close the valve.Which of the following statements accurately describes the signal which actually generates the Reactor Trip? A. The trip of the Main Feedwater Pumps on S/G #3 high level generates a reactor trip.B. The Main Turbine trip from the high level in S/G #3 generates the reactor trip.C. 78% level in S/G #3 generates the reactor trip.D. The FWIS generated on the high level in S/G #3 causes a low level in the other S/G's to generate a reactor trip.

Back 14

B

Front 15

What reactor trip CANNOT be blocked by an interlock or permissive? A. Pressurizer Low PressureB. Power Range Hi Neutron Flux RateC. Pressurizer High LevelD. Turbine Trip

Back 15

B

Front 16

At 100% power the controlling S/G level channel on S/G "A" fails to 100%.With no operator action, what is the plant response? A. Reactor trip on P-14 turbine trip.B. Feedwater flow to S/G "A" will initially decrease, than increase causing S/G level to stabilize at a level lower than program.C. Reactor trip on S/G Lo-Lo Level.D. Feedwater flow to S/G "A" will initially increase, then decrease causing S/G level to stabilize at a level higher than program.

Back 16

C

Front 17

The plant is at 4% RTP performing a startup. Intermediate range channel N-36 fails high.How does this failure affect the startup? A. Startup may continue if the channel is bypassed within 6 hours.B. Power must be reduced <6% or increased >10% within 24 hours.C. Power must be reduced <P-6 within 24 hours.D. The reactor will trip.

Back 17

D

Front 18

How are the Reactor Trip Breaker trip coils affected by a MANUAL Reactor trip switch? A. Shunt coils are energized directly from NK, the UV coils remain energizedB. UV coils are de-energized, the shunt coils are energized from NNC. Under-voltage coils are de-energized; the shunt coils are energized from NKD. UV coils and shunt coils all de-energize

Back 18

C

Front 19

Plant parameters are sensed by various process instruments which provide an output to the Reactor Protection System. What component is between the analog signal and the RPS? A. Slave RelayB. BistableC. Master RelayD. Digital Controller

Back 19

B

Front 20

The plant is operating at 100% power, with all systems and controls in normal alignment. A Small Break LOCA occurs.What is the Reactor trip setpoint and coincidence as RCS pressure decreases? A. 1940 psig on two of four instruments, get both protection trains, and both reactor trip breakers.B. 1970 psig on three of four instruments, get one protection train, and one reactor trip breaker.C. 1970 psig on two of four instruments, get both protection trains, and both reactor trip breakers.D. 1940 psig on three of four instruments, get one protection train, and one reactor trip breaker.

Back 20

A

Front 21

Which term is an input in the calculations of BOTH the OT?T and OP?T calculations? A. RCS Lead-Lag TavgB. RCS Temperature rateC. Pressurizer PressureD. Delta I

Back 21

D

Front 22

Which accident is the Intermediate Range High Flux Trip designed to protect the plant against? A. Startup AccidentB. Single Rod Drop AccidentC. Over-power AccidentD. Multiple Rod Ejection Accident

Back 22

A

Front 23

Which Reactor Protection System trip is designed to prevent the effects of a Rod Ejection Accident? A. Power Range, Neutron Flux Low SetpointB. Overpower ?T TripC. Power Range, Neutron Flux, High Positive RateD. Overtemperature ?T Trip

Back 23

C

Front 24

> A. Pressurizer Low Pressure TripB. RCP Undervoltage TripC. Overtemperature deltaT TripD. Intermediate Range High Flux Trip

Back 24

D

Front 25

At what value does P-6 change states during a reactor startup? A. 5X105 cpsB. 5X10-10 AmpsC. 105 cpsD. 10-10 Amps

Back 25

D

Front 26

Which describes the setpoint and coincidence for a change in state of P-9? A. 50% Reactor Power; 2/4 Power Range ChannelsB. 48% Reactor Power; 2/4 Power Range ChannelsC. 50% Turbine Power; 1/2 Impulse PressureD. 48% Turbine Power; 2/2 Impulse Pressure

Back 26

A

Front 27

Which of the following describes the setpoint and coincidence for the state change of P-10 during plant startup? A. 10% current equivalent on 1/2 Intermediate Range ChannelsB. 10% Power on 3/4 Power Range ChannelsC. 10% Power on 2/4 Power Range ChannelsD. 25% current equivalent on 1/2 Intermediate Range Channels

Back 27

C

Front 28

Which of the following is NOT associated with P-10? A. De-energizes Source Range high voltageB. Allows blocking of the Power Range high flux low setpoint Reactor TripC. Allows blocking of IR hi flux Reactor Trip and Rod Stop (C-1)D. Provides an input to P-13

Back 28

D

Front 29

Reactor Protection System interlocks are separated into two basic groups or categories. What are they? A. Protective and ControlB. Protective and ProcessC. Permissive and ControlD. Process and Control

Back 29

D

Front 30

When a P-4 permissive is generated signals are provided to ESFAS components.When is a P-4 permissive considered complete? A. Either bypass breaker open and any reactor trip breaker closedB. Both reactor trip breakers openC. All reactor trip and bypass breakers openD. Any reactor trip breaker or bypass breaker open

Back 30

C

Front 31

What is the plant response once a P-4 permissive is received? A. Arms Steam Dumps in the PLANT TRIP Mode.B. Causes a Reactor trip when the Turbine trips.C. Allows the operator to Block an automatic SIS immediately after a Reactor Trip.D. Generates a CISA if Low TAVG is present.

Back 31

A

Front 32

What is the purpose of the P-6 permissive? A. Allows bypassing Source Range high flux trips during reactor startup.B. Causes a Turbine trip when the reactor trips.C. Automatically enables Pressurizer Pressure - Low Reactor Trip.D. Prevents a Reactor Trip below 48% due to a single Reactor Coolant Loop Loss of Flow.

Back 32

A

Front 33

What signal will initiate the P-6 permissive? A. 2/4 Power Range channels > 48%B. Source Range channel > 105 cpsC. 2/4 Power Range channels > 10%D. Intermediate Range channel > 10-10 amps

Back 33

D

Front 34

The P-7 permissive is actuated by input from which other permissive? A. P-11B. P-10C. P-12D. P-9

Back 34

B

Front 35

What function does the P-8 permissive accomplish? A. Arms the Steam Dump upon a Load Rejection.B. Prevents a single loop RCS Low Flow Reactor Trip at <48% Reactor Power.C. Enables a Reactor Trip on Turbine Trip at > 50% Reactor Power.D. Generates a FWIS if TAVG is < 564 degrees.

Back 35

B

Front 36

What function does the P-9 permissive accomplish? A. Arms the Steam Dump upon a Load Rejection.B. Generates a FWIS if TAVG is < 564 degrees.C. Prevents a single loop RCS Low Flow Reactor Trip at < 48% Reactor Power.D. Enables a Reactor Trip on a Turbine Trip at >50% Reactor power.

Back 36

D

Front 37

The P-10 permissive provides key functions within the Reactor Protection system. What other permissive does P-10 provide input to? A. P-13B. P-11C. P-6D. P-7

Back 37

D

Front 38

What is the function of the P-11 permissive? A. Allows manual block of the low Pzr Press Reactor Trip.B. Allows manual block of the low Pzr Press Safety Injection Actuation.C. Replaces the low steam-line pressure steam line isolation with a high steam pressure Reactor Trip.D. Replaces the high steam pressure rate steam-line isolation with a low steam-line pressure steam line isolation.

Back 38

B

Front 39

What logic and setpoint actuates the P-12 permissive? A. 2/3 Pressurizer Pressure Bistables < 1970 psigB. 1/2 Intermediate Range Channels > 1E-10 ampsC. 2/4 TAVG instruments > 550 ?FD. 2/4 NIS Power channels > 10%

Back 39

C

Front 40

What actions occur following the receipt of a P-14 permissive? A. Turbine Trip, MSLIS, CISAB. Turbine Trip, Trip of both Main Feed Pumps, FWISC. Trip of both Main Feed Pumps, FWIS, MSLISD. Reactor Trip, Turbine Trip, SGBSIS

Back 40

B

Front 41

What is the function of the C-7 interlock? A. Blocks automatic and manual control rod withdrawal.B. Prevents automatic rod withdrawal with power < 15%.C. Blocks automatic withdrawal of control bank "D".D. Arms the steam dump upon a load rejection.

Back 41

D

Front 42

What will actuate the C-1 Interlock? A. Low auctioneered TAVG < 553?FB. 3% less than the variable OPDT setpointC. 1/2 Intermediate channels > 20% powerD. 1/4 Power Range channels > 103% power

Back 42

C

Front 43

Given the following: Reactor Power is 13% SG A level is 77% SG B level is 82% SG C level is 76% SG D level is 75%Which one of the following lists AUTOMATIC actions that should directly result from the above situation? A. No auto action should occurB. Turbine trip, Feedwater isolation, Feed Pumps tripC. Turbine trip, Reactor trip, Feed Pumps tripD. Reactor trip, Feedwater isolation, Feed Pumps trip

Back 43

B

Front 44

> A. steam dump logicB. safety injection logicC. control rod drive logicD. feedwater isolation logic

Back 44

C

Front 45

The plant was operating at 51% power when a reactor trip occurred due to a loss of "B" RCP. The plant responded in the following manner:* Tavg decreased to 560?F* The Main Turbine did not automatically trip* Feedwater isolation did not immediately occurThe above mentioned plant response to the reactor trip suggests that a failure occurred in which permissive circuit? A. P-8B. P-9C. P-14D. P-4

Back 45

D

Front 46

The following plant conditions exist:* Beginning of life (BOL)* Reactor Power is at 100% with rod control in AUTOMATIC* Control Bank "D" is at 218 steps* A failure in rod control causes rods to step OUT Which rod control interlock is the FIRST to stop outward rod movement assuming NO Operator action? A. Power Range Rod Stop (C-2)B. Overtemperature ?T Rod Stop (C-3)C. Overpower ?T Rod Stop (C-4)D. Control Bank "D" Position Rod Stop (C-11)

Back 46

D

Front 47

A plant shutdown from 50% power is in progress when Intermediate Range Channel SENI36 fails HIGH.Power Range NIs currently indicate:* SENI41 9%* SENI42 10%* SENI43 11%* SENI44 11%What is the plant response to this failure? A. The reactor will NOT immediately trip, but will trip when the Intermediate Range Trip is reinstated when power decreases below the P-10 setpoint.B. The reactor will immediately trip on IR High Flux and Source Range Trip will NOT reinstate automatically when SENI35 decreases below the P-6 setpoint.C. The reactor will immediately trip on IR High Flux and Source Range Trip will reinstate automatically when SENI35 decreases below the P-6 setpoint.D. The reactor will NOT immediately trip, but will trip when the Source Range Trip is reinstated when power decreases below the P-6 setpoint.

Back 47

A

Front 48

The reactor is operating at 100% with all systems in a normal lineup with control rods in manual.What is the effect on the OT?T setpoint for channel II if Power Range Channel 42 lower detector fails to zero? A. Becomes InvalidB. DecreasesC. IncreasesD. No Change

Back 48

B

Front 49

Reactor Power has been reduced to 8% from 50% due to problems with the main turbine and feedwater systems.Which Reactor Protection System function has now been automatically re-enabled? A. All Reactor Trips associated with P-7.B. Source Range High Flux Reactor Trip.C. Intermediate Range High Flux Reactor Trip.D. Overpower Differential Temperature Trip (OP?T).

Back 49

C

Front 50

With the plant in Mode 3, the Main Control Board Handswitch for the Reactor Trip Breakers is rotated to the CLOSE position.Which of the following conditions would prevent the Reactor Trip Breakers from closing? A. Pressurizer Level at 17%B. Pressurizer Pressure at 1870 psigC. Pressurizer Level at 95%D. Pressurizer Pressure at 2400 psig

Back 50

D

Front 51

The reactor is operating at 100% with all systems in a normal lineup with control rods in manual.What is the effect on the OT?T setpoints if Reactor Power is decreased to 50% with normal pressure and temperature? A. IncreasesB. DecreasesC. No ChangeD. Increases, then decreases

Back 51

A

Front 52

With the plant at full power, Reactor Trip Breaker "B" is mechanically inoperable at 0800 on Monday. Reactor Trip Breaker "A" was determined to be operable.At what time would the plant be required to be in Mode 3? A. 1500 WednesdayB. 1500 MondayC. 1600 MondayD. 1400 Wednesday

Back 52

B

Front 53

The unit is operating at 100% RTP following a refueling outage.After several months operation in Mode 1, the following was determined:* STS IC-726B, 7300 PROCESS RESPONSE TIME TEST (2/3 LOGIC) CYCLE B, was last performed 41 months ago.* STS IC-726C, 7300 PROCESS RESPONSE TIME TEST (2/3 LOGIC) CYCLE C, was last performed 23 months ago* STS IC-726A, 7300 PROCESS RESPONSE TIME TEST (2/3 LOGIC) CYCLE A, was last performed 5 months agoAssuming each of these procedures satisfy only SR 3.3.1.16, for Function 10, Reactor Coolant Flow - Low, then what actions must be taken? A. Perform STS IC-726B within the next 18 months.B. Immediately enter LCO 3.0.3 because Technical Specifications have been violated.C. Perform STS IC-726B within the next 13 months.D. Enter SR 3.0.3 and perform STS IC-726B within the next 24 hours.

Back 53

C

Front 54

The unit is in Mode 3. S/G "A" Narrow Range Water Level - Low Low instrument (Channel 4) is declared inoperable at 0400. At 0600, the inoperable channel is placed in trip.Is entry into Mode 2 permitted with the inoperable S/G "A" Narrow Range Water Level - Low Low instrument? A. No. There are no exceptions to LCO 3.0.4 noted in the applicable Technical Specifications.B. Yes. Once the unit is in Mode 2 the only Action is to continue efforts to restore compliance with TS 3.3.2 LCO statement.C. Yes. Once the unit is in Mode 2 the Actions of TS 3.3.1 must also be entered.D. No. LCO 3.0.4 requires all channels be OPERABLE prior to entering the Mode of Applicability.

Back 54

C

Front 55

With bypass breaker A (BYA) in the closed position, and both normal reactor trip breakers (RTA and RTB) in the closed position, which one of the following will generate a reactor trip? A. RTA opens up (by itself)B. RTB opens up (by itself)C. BYA opens up (by itself)D. None of the above, a reactor trip requires at least two breakers open to generate a reactor trip

Back 55

B

Front 56

Which of the following Control Rod Stops requires only one channel to exceed its setpoint to stop all control rod withdrawl? A. Power Range High FluxB. Overpower delta TC. Overtemperature delta TD. Both A and B

Back 56

A

Front 57

Wolf Creek is operating at 95% RTP when the Feedwater Regulating Valve, AE FCV-530, fails to the full open position and the BOP operator is unable to close the valve.Which of the following statements accurately describes the signal which actually generates the Reactor Trip? A. The FWIS generated on the high level in S/G #3 causes a low level in the other S/G's to generate a reactor trip.B. 78% level in S/G #3 generates the reactor trip.C. The Main Turbine trip from the high level in S/G #3 generates the reactor trip.D. The trip of the Main Feedwater Pumps on S/G #3 high level generates a reactor trip.

Back 57

C

Front 58

The plant experienced a refueling outage and is ready to return to service. The P-8 permissive has been satisfied.Which one of the following would be the expected color of the window seen on the reactor partial trip status permissive/block indicating panel for the permissive? A. GreenB. WhiteC. YellowD. Red

Back 58

A

Front 59

Which of the following correctly describes the C-7 interlock and its relationship to the Steam Dump System? A. It arms the steam dump valves on a turbine load rejection.B. Receives inputs from P-10 and P-13 protective circuits.C. Stops further turbine loading by closing the control valves.D. Enabled by 2 RCS loop Tavg channels <550 degrees F.

Back 59

A

Front 60

The following conditions exist:A plant startup is in progress, the RCS is currently at 4500F and 1800 psig. The reactor operator raises Reactor Coolant System (RCS) pressure to 2235 psig to perform post-maintenance testing on a Pressurizer Power Operated relief valve.Which one of the following explains the response of the Engineered Safety Features (ESF) for this event? A. SIS actuates on low pressurizer pressure and MSLIS will not actuate.B. SIS and MSLIS actuate on low steam line pressure when P-11 de-energizes.C. SIS and MSLIS actuate on low pressurizer pressure when P-11 energizes.D. SIS will not actuate, but MSLIS actuates on low steam line pressure.

Back 60

B

Front 61

Which indication would alert the operator to the "under compensation" of one intermediate range channel? A. P-6 does not energize following a reactor trip.B. P-6 does not energize following a reactor startup.C. P-6 energizes much sooner than expected following a reactor startup.D. P-6 energizes much sooner than expected following a reactor trip.

Back 61

C

Front 62

What is the C-9 setpoint and logic coincidence? A. <4.0" HgA on 2/2 pressure switchesB. <5.0" HgA on 2/2 pressure switchesC. <5.0 "HgA on 1/2 pressure switchesD. <4.0" HgA on 1/2 pressure switches

Back 62

B

Front 63

Power Range Neutron Flux High Setpoint

Back 63

109% power with a 2/4 coincidence) provides protection against an over-power condition.

Front 64

Power Range Neutron Flux Low Setpoint

Back 64

25% power with a 2/4 conincidence protects against a startup accident

Front 65

Power Range Neutron Flux High Positive Rate

Back 65

power range detectors experience a power increase equivalent to 4% in 2 seconds.

Front 66

Power Range, Neutron Flux, High Negative Rate

Back 66

power decrease of 4% in 2 seconds. This protects against multiple rod drop accidents, DNB, and localized peaking

Front 67

Intermediate Range High Flux Trip

Back 67

initiates at an ion current value equivalent to 25% full power. Protects against startup accident. The IR trips may be bypassed when the P-10 permissive at 10 percent.

Front 68

Source Range High Flux Trip

Back 68

Trip occurs at 10^5 cps. This trip is bypassed when the P-6 permissive at 10^-10 amps, derived from the IR channels is met.

Front 69

OTDT

Back 69

prevents DNB. Primary Coolant Temperature, pressurizer pressure, and axial flux are used to determine a DT that corresponds to reactor power and compared to the COLR

Front 70

OPDT

Back 70

protects against overpower conditions. Not credited in SA

Front 71

Pressurizer Pressure Low

Back 71

Initiates at 1940 psig protects against DNB. It is automatically bypassed below 10 percent power by the P-7 interlock.

Front 72

Pressurizer Pressure High Trip

Back 72

2385 psig protects against overpressure.

Front 73

Pressurizer Water Level High Trip

Back 73

Initiates at 92% level. This signal is blockwd when power is less than the P-7 setpoint.

Front 74

Reactor Coolant Low Flow Trips

Back 74

Protect against DNB following a loss of flow, senses RCP bus undervoltage. RCP bus underfrequency, or Measured Flow in the Reactor Coolant Piping. Blocked by P-7 less than 10% power.

Front 75

UnderVoltage RCP

Back 75

10578 Volts AC is the trip setpoint and is blocked below P-7

Front 76

Under-frequency RCP trip

Back 76

Setpoint of 57.2 Hz. Blocked below P-7

Front 77

RCS flow low Trip

Back 77

Setpoint is flow less than 90 percent of normal flow. Trips the reactor if flow is greater than P-8 (48 percent) and flow is lost in any loop.

Front 78

SG water level low trip

Back 78

Trip setpoint is 23.5% NR

Front 79

Turbine Trip on Reactor Trip

Back 79

trip as a result of a mismatch between turbine and reactor power. This trip will only initiate if above P-9 (50% power).

Front 80

SI Reactor Trip

Back 80

A reactor trip with SI occurs either by manual initiation, Containment High pressure (3.5 psig), Pressurizer Low pressure (1940 psig), or Low Steam Line Pressure (615 psig)

Front 81

P-4

Back 81

occurs when reactor trip breaker and bypass breaker are open. Causes a turbine trip, MFWIS if Tavg is low (564F), Allows blocking SIS for 60 seconds, and arms steam dumps.

Front 82

P-6

Back 82

bypasses the source Range High flux trip at 10^-10 amps

Front 83

P-7

Back 83

Upon increasing power, enables trips for Pressurizer pressure low trip, Pressurizer Water level High trip, reactor coolant flow low trip, undervoltage RCPs trip, or underfrequency RCPs. (Reactor trip and Turbine load must be less than 10% power.), It blocks the two loop flow, RCP Bus Undervoltage, RCP Bus Under-frequency, High Pressurizer Water Level, Low Pressurizer Pressure when below P-7

Front 84

P-8

Back 84

prevents a reactor trip from occuring below 48% power with a loss of flow in one loop.

Front 85

P-9

Back 85

enables reactor trip on turbine trip when power is greater than 50% reactor power.

Front 86

P-10

Back 86

allows manual block/automatic reinstatement of IR High flux trip, C-1 rod step, low setpoint power range trip and backup to P-6 SR cutout

Front 87

P-11

Back 87

blocks low pressurizer pressure safety injection SI and allows blocking the low steam. P greater than 1970 psig

Front 88

P-12

Back 88

automatically blocks steam dump system Tavg less than 550F

Front 89

P-13

Back 89

when turbine pressure is greater than 10 percent power, all the reactor trips associated with P-7 are automatically unblocked.

Front 90

P-14

Back 90

protects turbine from moisture carryover. Setpoint is >78% NR high high level. When it occurs turbine trip and FWIS.

Front 91

C-1

Back 91

High Neutron Flux Rod Stop blocks automatic and manual rod withdrawal. When IR channels > 20% power.

Front 92

C-2

Back 92

Overpower Rod Stop blocks automatic and manual control rod withdrawal when channels exceed 103% power.

Front 93

C-3

Back 93

decreases turbine load at an average rate of 10%/min when the OTDT setpoint is 3 percent below the variable OTDT reactor trip setpoint

Front 94

C-4

Back 94

Same as C-3 except the variable is OPDT

Front 95

C-5

Back 95

prevents automatic rod withdrawal when power is less than 15 percent power

Front 96

C-7

Back 96

arms steam dumps on a load rejection when turbine load is reduced by greater than 10 percent step or 5 percent per minute ramp

Front 97

C-9

Back 97

arms the steam dumps to the condenser

Front 98

C-11

Back 98

Prevents misalignment of rod position counters by blocking automatic withdrawal of control bank D when control bank D position is at 232 steps

Front 99

C-16

Back 99

stop turbine loading and defeat remote dispatching. Setpoint Tavg < 553F or Tavg 20F lower than Tref.