ML13092A285
| ML13092A285 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/05/2013 |
| From: | Mcneil D NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| Download: ML13092A285 (46) | |
Text
PALISADES REACTOR OPERATOR EXAMINATION Page 1 of 46 QUESTION # 001 Given the following:
The Plant was at full power when an equipment malfunction resulted in an automatic Reactor trip During the performance of EOP-1.0, Standard Post-Trip Actions, P-1A, Main Feed Pump, Speed controller will not shift into manual P-1A speed is constant at 5250 RPM Based on this, the Reactor Operator will (1) to prevent (2).
- a. (1) close A Steam Generator Feed Water Regulating Valve (2) feed flow imbalance to A and B Steam Generators
- b. (1) close A Steam Generator Feed Water Regulating Valve (2) overcooling the PCS (Primary Coolant System)
- c. (1) trip P-1A (2) feed flow imbalance to A and B Steam Generators
- d. (1) trip P-1A (2) overcooling the PCS (Primary Coolant System)
QUESTION # 002 Given the following:
The Plant has been tripped from 100% power due to a small break LOCA 4160V Buses 1A and 1B are de-energized due to an equipment malfunction The actions of EOP-1.0, Standard Post Trip Actions, have been completed The CRS has given the direction to commence a PCS cooldown and depressurization Based on the given conditions the NCO will operate the (1) to lower PCS temperature and the PZR (2) to lower PCS pressure.
- a.
(1)
(2)
Main Spray Valves
- b.
(1)
(2)
Auxiliary Spray Valve
- c.
(1)
ADVs (Atmospheric Dump Valves)
(2)
Main Spray Valves
- d.
(1)
ADVs (Atmospheric Dump Valves)
(2)
Auxiliary Spray Valve
PALISADES REACTOR OPERATOR EXAMINATION Page 2 of 46 QUESTION # 003 Given the following:
The Plant was manually tripped from full power due to a large break LOCA The Control Room team has implemented EOP-4.0, LOCA Recovery PCS temperature is 540°F and stable PCS pressure is 1200 PSIA and lowering The Control Team has determined that PCS cooldown is required 2400V Bus 1D is de-energized P-55C, Charging Pump, is in service providing 40 GPM charging flow Based on the given conditions, PCS cooldown (1) commence (2).
- a.
(1) may (2) with no restrictions
- b.
(1) may (2) but must be stopped at 490°F to verify shutdown margin
- c.
(1) cannot (2) until additional charging pumps are started
- d.
(1) cannot (2) until adequate shutdown margin has been verified
PALISADES REACTOR OPERATOR EXAMINATION Page 3 of 46 QUESTION # 004 Given the following initial indications for Primary Coolant Flow on Panel C-12:
Which one of the following would validate alarm EK-0902, PRI COOLANT PUMP P-50B TRIP? Assume all four PCPs are initially in service.
FI-0102A FI-0102B FI-0102C FI-0102D
- a. lowers lowers lowers lowers
- b. lowers lowers unchanged unchanged
- c. lowers lowers rises rises
- d. unchanged lowers unchanged unchanged
PALISADES REACTOR OPERATOR EXAMINATION Page 4 of 46 QUESTION # 005 Given the following:
EOP-4.0, LOCA Recovery, procedure has been implemented due to RV-1040, Pressurizer Safety Valve, lifting PCS pressure is 260 PSIA PCS temperature is 250°F PZR level is 100%
Control Room indications show RV-1040 has not reseated In preparation for Shutdown Cooling operations Low Temperature Overpressure Protection (LTOP) is enabled and placed in the SDC mode Based on the given conditions, if RV-1040 reseated resulting in a PCS pressure rise to 295 PSIA, PORV(s) (Power Operated Relief Valves) will actuate.
- a. no
- b. Left Channel PRV-1043B only
- c. Right Channel PRV-1042B only
- d. Left Channel PRV-1043B and Right Channel PRV-1042B QUESTION # 006 Given the following with the Plant in MODE 5:
Shutdown Cooling is in service using P-67A, LPSI Pump, at 3200 gpm Bulk PCS Temperature is stable at 105°F Shutdown Cooling Return temperature to the PCS is currently 80°F The Control Room team notes that Shutdown Cooling Return temperature is rising uncontrollably and implements ONP-17 Loss of Shutdown Cooling procedure Which one of the following is a possible cause of the Shutdown Cooling Return temperature rise?
- a. HIC-0826, Instrument Air Regulator for CV-0826, CCW HX E-54B SW Outlet, malfunction resulting in rising output air pressure from 45 to 85 psig.
- b. FIC-0306, SDC HX Bypass Controller for CV-3006, SDC Heat Exchangers Bypass, malfunction resulting in rising controller output from 15% to 30%.
- c. HIC-03025A, Shutdown Cooling Controller for CV-3025, SDC Heat Exchangers Outlet, malfunction resulting in rising controller output from 30% to 55%.
- d. MO-3008, LPSI to Reactor Coolant Loop 1A, Limitorque operator electrical malfunction resulting in valve travel in the open direction an additional 10%.
PALISADES REACTOR OPERATOR EXAMINATION Page 5 of 46 QUESTION # 007 CV-0823 and CV-0826, CCW Heat Exchanger Service Water High Capacity Outlet Valves, receive an open signal during emergency conditions.
What condition generates the open signal and what is the reason?
QUESTION # 008 Given the following conditions with the Plant at full power:
LIC-0101B, Pressurizer Level Control Channel B, is in service Then, LIC-0101B input fails low The following are in the stated position:
o HS-1/LRC-0101, Pressurizer Level Channel Selector Switch, is placed in the A position o HS-1/LIC 0101, Pressurizer Heater Control Channel Selector Switch, is in the A+B position The Control Room Supervisor directs the Reactor Operator to reset and close152-211, Pressurizer Heater Transformer EX-16 Feeder Breaker Based on the given conditions, which one of the following describes the Pressurizer Heaters, if any, that will be energized for pressure recovery after the Reactor Operator places 152-211 Control Switch to the CLOSE position?
- a. Proportional Heaters and Backup Heaters for D bus only.
- b. Proportional Heaters and Backup Heaters for E bus only.
- c. Proportional Heaters and Backup Heaters for D and E bus.
- d. No heaters will be energized.
PALISADES REACTOR OPERATOR EXAMINATION Page 6 of 46 QUESTION # 009 With the plant at 100% power the following occurs:
The Main Turbine trips due to a low vacuum condition, but the Reactor does not trip The Reactor Operator attempts to trip the reactor using the pushbutton on panel C-02 but is unsuccessful The Reactor Operator then successfully trips the reactor using the pushbutton on Panel C-06 Based on the above conditions, which one of the following describes the status of Reactor Trip Breakers, 42-1RPS/42-2RPS and EK-0972, Reactor Trip Alarm Red Tile Annunciator?
- a. 42-1RPS and 42-2RPS are closed.
EK-0972 is off.
- b. 42-1RPS and 42-2RPS are closed.
EK-0972 is lit.
- c. 42-1RPS and 42-2RPS are tripped.
EK-0972 is off.
- d. 42-1RPS and 42-2RPS are tripped.
EK-0972 is lit.
QUESTION # 010 Given the following with the Plant initially at full power:
The Plant is manually tripped due to a tube rupture in the B Steam Generator (S/G)
B S/G level is 7% and stable A S/G level is 4% and lowering slowly TAVE is 535°F and stable EOP-1.0, Standard Post-Trip Actions, Immediate Actions are currently in progress Which one of the following describes the required action for the above conditions per EOP-1.0?
- a. Close CV-0779 and CV-0780, B S/G Atmospheric Dump Valves.
- b. Restore A and B S/G levels to a band of 60 - 70%.
- c. Cooldown the PCS to < 524°F Hot Leg temperature.
- d. Secure Auxiliary Feedwater flow to the B S/G.
PALISADES REACTOR OPERATOR EXAMINATION Page 7 of 46 QUESTION # 011 Given the following:
The Plant is at full power A steam line break occurs outside the Containment Building upstream of CV-0510, A Steam Generator Main Steam Isolation Valve (MSIV)
A S/G Pressure indicates 475 psia B S/G Pressure indicates 850 psia Which one of the following describes the expected response of the MSIVs and Feed Regulating Valves (FRVs) to this event?
- a. Both A and B S/G MSIVs close.
Both A and B S/G FRVs close.
- b. Both A and B S/G MSIVs close.
Only A S/G FRV closes.
- c. Only A S/G MSIV closes.
Both A and B S/G FRVs close.
- d. Only A S/G MSIV closes.
Only A S/G FRV closes.
QUESTION # 012 Given the following plant conditions:
Plant has been manually tripped from full power due to a transient After EOP-1.0, Standard Post-Trip Actions, is complete, the Control Room Team has implemented EOP-2.0, Reactor Trip Recovery, procedure Subsequently, a major grid disturbance occurs resulting in a transition to EOP-3.0, Station Blackout Recovery, procedure Based on the given conditions the Control Team will utilize (1) to determine that PCS subcooling is at least (2) °F for the establishment of natural circulation.
- a.
(1)
Sub-Cooling Margin Monitors on panel C-12 (2) 25
- b.
(1)
Average Qualified CET indication on the PPC (2) 25
- c.
(1)
Sub-Cooling Margin Monitors on panel C-12 (2) 50
- d.
(1)
Average Qualified CET indication on the PPC (2) 50
PALISADES REACTOR OPERATOR EXAMINATION Page 8 of 46 QUESTION # 013 Given the following conditions:
Plant was at full power when a Loss of Offsite Power occurred EOP-1.0, Standard Post Trip Actions, have been completed and the Control Room Team has transitioned to EOP-8.0, Loss Of Offsite Power/Forced Circulation Recovery Steam Generator (S/G) levels are 35% and rising slowly One action in EOP-8.0 is to maintain or restore at least one S/G level to between 60% and 70%.
The reason for the S/G level band is to provide (1) and the operator should be aware of (2) due to excessive feeding.
- a.
(1) heat removal capability under forced flow and natural circulation conditions (2) the potential for overcooling
- b.
(1) heat removal capability under forced flow and natural circulation conditions (2)
S/G tube sheet damage
- c.
(1)
S/G inventory to mitigate a possible subsequent Loss of All Feedwater event (2) the potential for overcooling
- d.
(1)
S/G inventory to mitigate a possible subsequent Loss of All Feedwater event (2)
S/G tube sheet damage QUESTION # 014 Given the following:
The Plant has been manually tripped from full power due to a transient During EOP-1.0, Standard Post Trip Actions, verbal verifications, a loss of Y-01, Instrument AC Bus, occurs PZR level is 56% and rising LIC-0101B, PZR Level Controller, is in service in the CASCADE mode Based on the given conditions, the minimum action(s) the NCO will need to perform to maintain PZR level within the normal band is to.
- a. maintain PZR Level controller LIC-0101B in cascade
- b. shift PZR Level controller LIC-0101B to manual
- c. alternate to PZR Level controller LIC-0101A in cascade
- d. operate charging and letdown components manually
PALISADES REACTOR OPERATOR EXAMINATION Page 9 of 46 QUESTION # 015 Given the following with the Plant at full power:
Battery Chargers #3 and #4 are in service.
DC Bus #1 Tie Breaker, 72-10, is opened.
Which one of the following loads, if any, will be de-energized?
- a. Y10 (Preferred AC Bus No. 1 Inverter), D11-1, and D11-2.
- b. Y10 (Preferred AC Bus No. 1 Inverter) only.
- c. None.
- d. Y30 (Preferred AC Bus No. 3 Inverter) only.
QUESTION # 016 Given the following:
The Plant is at full power Frazil Ice conditions are present EK-1124, TRAVELING SCREEN HI Dp, annunciates PPC Points DL_1336 and DL_1337 indicate 9 and rising The Control Room Team implements ONP-6.1, Loss of Service Water Based on the given information the Traveling Screen Wash system (1) be washing the screens and P-5, Warm Water Recirc Pump, can be started utilizing its control switch located in the (2) to de-ice the screens.
- a.
(1) will (2)
Screen House, Turbine Building
- b.
(1) will not (2)
Screen House, Turbine Building
- c.
(1) will (2)
Cooling Tower Pump House
- d.
(1) will not (2)
Cooling Tower Pump House
PALISADES REACTOR OPERATOR EXAMINATION Page 10 of 46 QUESTION # 017 Given the following:
The Plant is at full power A loss of Instrument Air occurs resulting in all three Instrument Air Compressors being in service The Control Room Team implements ONP-7.1, Loss of Instrument Air Instrument Air pressure is 70 psig and stable The Nuclear Plant Operator reports:
o FI-1210, Instrument Air Dryer M-2 Flow, indicates > 300 CFM o F-12A, Instrument Air Dryer Pre-filter D/P, is > 4 psid Based on the above conditions, closing air valve(s) associated with could be a possible action for isolating the air leak.
- a. Feedwater Purity Air to Plant Air
- b. VRS/Track Alley Fire Deluge System
- c. Cooling Tower Pump House
- d. West Safeguards Room QUESTION # 018 Given the following:
Plant is at 100% power The following indications exist on Panel C-01:
o Main Generator Power = 844 MW o Main Generator Reactive Load = 0 MVARS o Main Generator Terminal Voltage = 22.6 KV o Main Generator Phase currents (X,Y,Z) = 22,000 amps o F (front) bus voltage = 357 KV Then, an electrical grid disturbance occurs causing F bus voltage to lower to 350 KV Based on the given conditions and no operator action taken, the C-01 indication for Main Generator VARS will.
- a. remain constant
- b. indicate VARS in
- c. indicate VARS out
- d. initially indicate VARS out and slowly return to 0
PALISADES REACTOR OPERATOR EXAMINATION Page 11 of 46 QUESTION # 019 Given the following:
The Plant is at full power The Control Room Team has implemented ONP-5.1, Dropped Rod, due to a dropped rod event The ONP-5.1 strategy to be utilized with regards to reactivity control is to.
- a. coordinate with PCS dilution and insert group 4 rods above the PDIL limit to minimize worth of the dropped rod.
- b. perform PCS dilution to maintain TAVE within 3°F of TREF to minimize worth of the dropped rod.
- c. perform control rod insertion in small increments during plant shutdown to maximize shutdown margin.
- d. maintain control rods in an all rods out configuration to maximize shutdown margin.
QUESTION # 020 Given the following:
Plant has been tripped from full power due to a transient EOP-1.0, Standard Post Trip Actions, are in progress Control Rod matrix indications are shown below When determining if the Reactivity Control safety function is met for this condition,the Shutdown Margin (SDM) calculation (1) take into account the present control rod indications and (2) EOP-1.0 contingency actions are required to address the indications.
- a.
(1) does (2) no additional
- b.
(1) does (2) additional
- c.
(1) does not (2) no additional
- d.
(1) does not (2) additional
PALISADES REACTOR OPERATOR EXAMINATION Page 12 of 46 QUESTION # 021 Given the following:
The Plant is manually tripped from full power due to a loss of Y01, Instrument AC Bus EOP-1.0, Standard Post Trip Actions, are in progress Plant conditions require manual Emergency Boration Based on the given conditions which motor operated valves, if any, must be manually operated to ensure proper Emergency Boration is in progress?
- a. MO-2087, VCT Outlet Isolation, must be manually closed.
- b. MO-2160, SIRW Tank to Charging Pumps Isolation, must be manually closed.
- c. MO-2140, Boric Acid Pump Feed Isolation, must be manually opened.
- d. No Motor Operated valves will need to be manually operated.
QUESTION # 022 Given the following:
The Plant is in MODE 3 GCL-3, MODE 3 525F TO MODE 2, checklist is in progress with preparations for critical approach PCS boron concentration is 1080 PPM ( 525F, 2% )
Source Range/Wide Range channels NI-1/3 and NI-2/4 are in service Source Range NI Audible Counter selected to NI-2 is audible in Control Room Due to an equipment malfunction, power is lost to Source Range/Wide Range Channels NI-1/3.
Based on the given plant conditions critical approach (1) continue due to (2).
- a.
(1) may (2)
Source Range NI Audible Counter remaining audible in Control Room
- b.
(1) may not (2) less than required Source Range/Wide Range channels present
- c.
(1) may (2)
Source Range/Wide Range channels NI-2/4 remaining in service
- d.
(1) may not (2) insufficient PCS boron concentration
PALISADES REACTOR OPERATOR EXAMINATION Page 13 of 46 QUESTION # 023 Given the following:
The Plant was at full power when P-39A, Cooling Tower Pump, tripped The Control Room team has implemented ONP-14, Loss of Condenser Vacuum, and ONP-26, Rapid Power Reduction Power is 85% and lowering with Turbine Run Back at 300%/hour Condenser vacuum is 26 Hg and lowering EK-0911, ROD POSITION 4 INCHES DEVIATION, has annunciated The Reactor Operator notes the following position indication for Group 4 Rods:
Rod position (inches) 38 90 39 96 40 94 41 90 Which one of the following action(s), if any, is required to be performed by the Reactor Operator per ONP-26?
- a. none, rod insertion may continue
- b. balance control rod 39 only
- c. balance control rods 39 and 40
- d. trip the reactor
PALISADES REACTOR OPERATOR EXAMINATION Page 14 of 46 QUESTION # 024 Given the following:
A batch release of T-68C, Waste Gas Decay Tank, is in progress EK-1364, GASEOUS WASTE MONITORING HI RADIATION annunciates RIA-1113, Waste Gas Discharge Process Monitor is in High alarm RIA-1113, Waste Gas Discharge Process Monitor counts continue to rise Then, RIA-2326, Stack Gas Normal Range Monitor, counts begin to rise Based on the given conditions, which one of the following action will be used to secure the release?
- a. Close CV-1113, WGST Discharge to Stack.
- b. Close MV-WG114, Waste Gas Outlet to Stack.
- c. Secure V-14A/B, Radwaste Exhausters.
- d. Lower High alarm setpoint on RIA-1113, Waste Gas Discharge Process Monitor.
QUESTION # 025 Given the following conditions:
P-8B, Turbine Driven Aux. Feedwater Pump, is the only available operating AFW Pump.
The Control Room has been evacuated due to a fire.
C-150, Auxiliary Shutdown Panel, is being placed in service.
What will be the effect on the Auxiliary Feedwater components due to C-150 being in service?
- a. Any low suction pressure trip of P-8B must be reset at C-150.
- b. P-8B low suction pressure trip will not be available.
- c. AFW Flow Control Valves, CV-0727 and CV-0749, must be locally controlled.
- d. CV-0522B, Steam Supply to P-8B, must be locally controlled.
PALISADES REACTOR OPERATOR EXAMINATION Page 15 of 46 QUESTION # 026 Given the following:
The Control Room team has implemented EOP-6.0, Excess Steam Demand Event The tubing associated the containment sump level indication has failed resulting in a leak from containment into East Safeguards room Containment pressure was initially at 40 psia when the leak was discovered and estimated to be 3 gpm.
atmospheric pressure in the East Safeguards room is 15 psia If containment pressure lowers to 20 psia the leak rate will be gpm.
- a. 0.60
- b. 1.34
- c. 1.50
- d. 2.12 QUESTION # 027 Given the following:
The Control Room Team has implemented EOP-6.0, Excess Steam Demand Event, due to a Main Steam Line break on the B S/G inside Containment Based on the given plant conditions, which one of the following is a concern if a steaming path from the A S/G generator is not established prior to dryout of the B S/G?
- a. Void formation in the Reactor Vessel upper head region.
- b. A rise in core exit temperatures resulting in the loss of natural circulation.
- c. A rise in TCOLD of the unaffected loop resulting in a loss of natural circulation.
- d. A repressurization of the Primary Coolant System and subsequent pressurized thermal shock.
PALISADES REACTOR OPERATOR EXAMINATION Page 16 of 46 QUESTION # 028 Given the following:
The Plant is in MODE 3 PCS temperature is 532°F PCS pressure is 2060 psia Preparations are in progress for critical approach Based on the given conditions, which one of the following will lower the departure from nucleate boiling ratio for the Reactor?
- a. Fully withdrawing Shutdown Rod Group A.
- c. Securing a PCP for PZR Spray Valve testing.
- d. Raising PCS pressure by 10 psia.
QUESTION # 029 The Plant is in MODE 2 when Component Cooling Water is lost to the Letdown Heat Exchanger.
Which one of the following describes the automatic action that is expected to occur within the Chemical and Volume Control System?
- a. CV-2009, Letdown Containment Isolation Valve closes.
- b. CV-2003, 2004, and 2005 Letdown Orifice Stop Valves close.
- c. CV-2056, VCT Select swaps to the TO CLEAN WASTE RCVR TANKS position.
- d. CV-2023, Ion Exchangers Bypass Valve swaps to the BYPASS position.
PALISADES REACTOR OPERATOR EXAMINATION Page 17 of 46 QUESTION # 030 Given the following:
The Plant is in MODE 4 The Control Room Team is commencing cooldown of the PCS utilizing the Shutdown Cooling System (SDC)
The Reactor Operator will control PCS cooldown rate and monitor (1) to ensure CCW system design operating temperature limit of (2) °F is not exceeded.
- a.
(1)
TI-0912 and TI-0913, SDC HX CCW Outlet temperatures (2) 200
- b.
(1)
TIA-0914 and TIA-0916, CCW HX Outlet temperatures (2) 200
- c.
(1)
TI-0912 and TI-0913, SDC HX CCW Outlet temperatures (2) 140
- d.
(1)
TIA-0914 and TIA-0916, CCW HX Outlet temperatures (2) 140 QUESTION # 031 Given the following:
The Control Room Team has implemented EOP-4.0, Loss of Coolant Recovery Safety Injection has initiated P-66A, HPSI pump, is unavailable due to a discharge piping rupture The rupture has been isolated Hot Leg Injection is required Based on the given conditions Hot Leg Injection is (1) based on aligning P-66B HPSI pump (2).
- a.
(1) available (2) to the Cold leg loops and Hot legs via the PZR
- b.
(1) available (2) to the cold leg loops and operating Charging Pumps to the Hot legs via the PZR
- c.
(1) unavailable (2) in this configuration could result in pump damage
- d.
(1) unavailable (2) in this configuration would result in uneven flow to the Cold legs and Hot legs
PALISADES REACTOR OPERATOR EXAMINATION Page 18 of 46 QUESTION # 032 Given the following:
The Plant was tripped in response to a Loss of Coolant Accident inside Containment Safety Injection has actuated EOP-1.0, Standard Post Trip Actions, are in progress The Reactor Operator notes the Blue and Red lights are lit for MO-3009, HPSI Train 1 Loop Injection Valve The Green light is not lit Based on the given conditions, MO-3009 has
- a. an over-torque condition and the valve will operate if required.
- b. an over-torque condition and the valve will not operate if required.
- c. a motor thermal overload actuation and the valve will operate if required.
- d. a motor thermal overload actuation and the valve will not operate if required.
PALISADES REACTOR OPERATOR EXAMINATION Page 19 of 46 QUESTION # 033 Given the following Plant conditions:
Pressurizer pressure is 1000 psia Quench Tank pressure is 5 psig Quench Tank temperature is 90°F Which one of the following tailpipe downstream temperatures would be expected for a leaking Pressurizer Safety Valve under these conditions?
- a. 300°F
- b. 270°F
- c. 220°F
- d. 180°F QUESTION # 034 Given the following conditions:
A Plant cooldown is in progress with PCS temperature currently at 470°F and Pressurizer pressure at 1680 psia The Low Temperature Overpressure Protection (LTOP) system has just been placed in service Both PRV-1043A and PRV-1043B, Power Operated Relief Valves (PORVs) are in AUTO and both MO-1042A and MO-1042B, PORV Isolation Valves are open Then the following occurs:
o Alarm EK-0743, PRESSURIZER PWR OPERATED RELIEF VALVE DISCH HI TEMP, annunciates o Alarm EK-1373, SV AND/OR PORV OPEN annunciates o TIA-0106, Power Relief Valves Discharge Temperature, indicates 225°F o FI-1043B, Pressurizer Acoustic Flow Monitor is in alarm o Pressurizer pressure is lowering slowly Which one of the following is required within one hour?
- a. Verify PRV-1043B indicates closed.
- b. Place PRV-1043B in manual control.
- c. Close PRV-1043B associated block valve.
- d. Place PRV-1043B associated LTOP channel in DEFEAT.
PALISADES REACTOR OPERATOR EXAMINATION Page 20 of 46 QUESTION # 035 Given the following with the Plant at full power:
The Control Room team notices that T-3, Component Cooling Water (CCW) Surge Tank, level is 76% and rising slowly.
EK-1365, PROCESS LIQ MONITORING HI RADIATION, annunciates RIA-0915, Component Cooling Water Rad Monitor, is in alarming Which one of the following describes the expected indication for CV-0915, CCW Surge Tank Vent, and CV-0918, CCW Surge Tank Makeup Valve?
CV-0915 is lined up to the (1) and CV-0918 is (2).
- a. (1)
Vent Gas Collection Header (VGCH)
(2) closed
- b. (1)
Vent Gas Collection Header (VGCH)
(2) open
- c. (1)
Waste Gas Surge Tank (2) closed
- d. (1)
Waste Gas Surge Tank (2) open QUESTION # 036 Given the following with the Plant operating at full power:
A loss of all offsite power occurs Diesel Generator (D/G) 1-1 will not start D/G 1-2 starts and sequences loads as designed Coincident with D/G 1-2 loading, a leak develops in the Component Cooling Water (CCW) System which causes CCW pressure to lower from 105 psig to 77 psig For the above conditions, which one of the following describes which CCW Pump(s) will be operating five minutes after D/G 1-2 has completed sequencing loads?
- a. P-52B only.
- b. P-52A only.
- c. P-52B and P-52C.
- d. P-52A and P-52C.
PALISADES REACTOR OPERATOR EXAMINATION Page 21 of 46 QUESTION # 037 Given the following:
The Plant is at full power when an equipment issue arises requiring the Control Room Team to implement ONP-26, Rapid Power Reduction Turbine runback at 100%/hour and rod insertion are in progress TAVE is currently higher than TREF by 3°F A malfunction occurs in the in-service Pressurizer Pressure Controller resulting in its setpoint failing high If the rapid power reduction were to continue with current TAVE/TREF deviation and no operator action on the Pressurizer Pressure Controller issue, the Plant would automatically trip on (1) if PCS pressure reaches (2) psia.
- a.
(1)
TM/LP (2) 1760
- b.
(1)
TM/LP (2) 1780
- c.
(1)
High PZR Pressure (2) 2235
- d.
(1)
High PZR Pressure (2) 2375 QUESTION # 038 Which one of the following describes the importance of having Spray Bypass Needle Valves (MV-PC1056 and MV-PC1058) throttled open 2 turns, as required by procedure?
- a. Provides faster response for Pressurizer pressure control by raising the differential pressure across the main spray valves.
- b. Prevents thermal shock to Pressurizer spray lines by providing a small amount of continuous flow through both spray headers.
- c. Ensures the Pressurizer hydrogen concentration is equal to that of the PCS, by continually mixing PCS and Pressurizer inventory, in case of main spray valve closure.
- d. Ensures Auxiliary Spray function is maintained ready for emergency use if needed, by providing continual flow through the Auxiliary Spray header.
PALISADES REACTOR OPERATOR EXAMINATION Page 22 of 46 QUESTION # 039 Given the following:
The Plant is at 28% power during a startup The white High Power Rate pre-trip light for RPS Channel A is lit (see picture below)
Startup Rate is 0.6 DPM Which one of the following describes the cause of this condition and the action the operator will perform to verify the cause?
- a. Axial Shape Index (ASI) is approaching a limit. Check the Power Density status on each Thermal Margin Monitor.
- b. Axial Shape Index (ASI) is approaching a limit. Check the Alarms sub-screen on each Thermal Margin Monitor.
- c. Startup Rate has reached the pre-trip setpoint. Verify EK-0917, ROD WITHDRAWAL PROHIBIT, is annunciating on panel C-12.
- d. Startup Rate has reached the pre-trip setpoint. Verify all control rod motion has stopped and trip the Reactor if an uncontrolled rod withdrawal is occurring.
PALISADES REACTOR OPERATOR EXAMINATION Page 23 of 46 QUESTION # 040 Given the following:
Plant is at full power The power supply breaker to the A Channel Thermal Margin Monitor (TMM) trips resulting in a loss of power to A Channel TMM Based on the given conditions, A Channel Reactor Protection system Variable High Power Trip channel will indicate (1) and TM/LP trip channel will indicate (2).
- a.
(1) clear (2) clear
- b.
(1) clear (2) tripped
- c.
(1) tripped (2) clear
- d.
(1) tripped (2) tripped QUESTION # 041 Given the following The Plant has been tripped from full power due to a Loss of Coolant Accident in Containment Control Room Team has implemented EOP-4.0 Loss of Coolant Recovery SIRWT level is 24%
The Reactor Operator is preparing to place HS-3027A and HS-3056A, SI Pump Minimum Flow Stop Valve Handswitches, to the CLOSE position Based on the given conditions, the Reactor Operator should observe CV-3027 and CV-3056 SI Pump Minimum Flow Stop Valves going closed (1) to ensure (2).
- a.
(1) after placing the associated Handswitches to CLOSE (2) no significant release of radiation to the environment
- b.
(1) after placing the associated Handswitches to CLOSE (2) maximum Safety Injection flow to the PCS
- c.
(1) when SIRWT level reaches 2%
(2) no significant release of radiation to the environment
- d.
(1) when SIRWT level reaches 2%
(2) maximum Safety Injection flow to the PCS
PALISADES REACTOR OPERATOR EXAMINATION Page 24 of 46 QUESTION # 042 Given the following with the plant operating at 50% power:
A fault occurs on Preferred AC Bus Y-20 which subsequently de-energizes Y-20 The crew enters ONP-24.2, Loss of Preferred AC Bus Y-20 Subsequently, the Plant is manually tripped due to a Main Steam Line Break inside the Containment PCS pressure is 1720 psia Containment pressure is 4.5 psig Due to these conditions, which one of the following describes the correct action(s) during EOP-1, Standard Post trip Actions, if any?
- a. Manually align Right Channel SIS equipment only.
- b. Start P-54A, Containment Spray Pump, only.
- c. Manually align Right Channel SIS equipment and start P-54A, Containment Spray Pump.
- d. No actions are necessary; Containment Spray and Safety Injection Actuation will operate automatically for this event.
QUESTION # 043 Given the following:
EOP-1.0, Standard Post Trip Actions, are in progress:
EK-1361, CONTAINMENT HI PRESSURE, annunciates Which one of the following describes the status of the Containment Air Cooler Fans?
- a. All A fans ON.
All B fans ON.
- b. All A fans ON.
All B fans OFF.
- c. V-1A, V-2A, and V-3A ON.
V-4A and all B Fans OFF.
- d. V-1A, V-2A, and V-3A OFF, V-4A ON.
All B Fans OFF.
PALISADES REACTOR OPERATOR EXAMINATION Page 25 of 46 QUESTION # 044 Which one of the following describes the operation of the white ARMED light located below the breaker CHARGED light for P-54A, P-54B and P-54C, Containment Spray Pumps? Refer to the below picture of P-54B controls.
The white light illuminates when...
- a. Containment Pressure reaches 0.85 psig.
- b. a Containment High Radiation Signal is received.
- c. a Safety Injection Actuation Signal is received.
- d. the associated Diesel Generator is supplying the bus.
QUESTION # 045 Which one of the following strategies will be implemented to maintain PCS Heat Removal during an Excess Steam Demand Event?
- a. Steam the least affected S/G using Atmospheric Steam Dumps to maintain least affected S/G pressure 0 to 50 psi above the most affected S/G pressure.
- b. Steam the least affected S/G when the affected S/G level reaches -50% using the MSIV bypass valve and Turbine Bypass Valve.
- c. Open both MSIV Bypass Valves and steam both S/Gs to Main Condenser to ensure a monitored release path.
- d. Maximize Aux Feed flow to most affected S/G while steaming the least affected S/G using Atmospheric Steam Dump Valve.
PALISADES REACTOR OPERATOR EXAMINATION Page 26 of 46 QUESTION # 046 Given the following:
The Plant is operating at full power The following is noted on LIC-0701, E-50A Level Indicating Controller:
Based on the given conditions and no operator action, which one of the following describes the response of the Plant?
- a. The Reactor will trip on low level for the A Steam Generator.
- b. The Feed Flow portion of SGWLC system will control A Steam Generator at a lower level.
- c. The Main Turbine will experience excessive vibration due to moisture carry over.
- d. The A Steam Generator Feed Regulating Valve will close at the high level alarm setpoint.
PALISADES REACTOR OPERATOR EXAMINATION Page 27 of 46 QUESTION # 047 Given the following with the Plant operating at full power:
A Reactor trip occurs due to a loss of all offsite power Diesel Generator 1-2 will not start automatically or manually A loss of Y10, Preferred AC Bus, occurs two minutes after the loss of offsite power Then, an Auxiliary Feedwater Actuation Signal (AFAS) occurs Which Auxiliary Feedwater (AFW) Pump, if any, will be operating one-minute after the AFAS occurs? (Assume no Operator actions associated with AFW occur)
- a. P-8A, AFW Pump.
- b. P-8B, AFW Pump.
- c. P-8C, AFW Pump.
- d. None.
QUESTION # 048 Given the following:
The Plant is in MODE 3 with the PCS at normal operating temperature and pressure Station Battery Chargers 3 and 4 are in service Station Battery Chargers 1 and 2 are OPERABLE A fault occurs on Bus 1D resulting in EK-0532 BUS 1C OR 1D OVERCURRENT LOCKOUT alarming Two (2) minutes have elapsed since the fault Based on the given conditions, which one of the following lists the Station Battery Chargers that will be available?
- a. Battery Chargers 2 and 3 only.
- b. Battery Chargers 1 and 4 only.
- c. Battery Chargers 1 and 3 only.
- d. All Battery Chargers.
PALISADES REACTOR OPERATOR EXAMINATION Page 28 of 46 QUESTION # 049 Given the following ONP-20, Diesel Generator Manual Control, for 1-1 Diesel Generator is in progress Then, DC Breaker 72-301 for 1-1 D/G Control was found tripped on Panel D-11A The Remote Local Transfer Switches (RLTS) on 1-1 D/G Exciter Cabinet (HS-C22-RLTS) and Gauge Board (HS-G20-RLTS) were placed to the LOCAL position The DC breaker is then reset and closed on Panel D-11A Based on the given plant conditions 1-1 D/G
- a. will automatically start on a Bus undervoltage condition and can be started from the Control Room.
- b. will automatically start on a Bus undervoltage condition and can not be started from the Control Room.
- c. will not automatically start on a Bus undervoltage condition and can be started from the Control Room.
- d. will not automatically start on a Bus undervoltage condition and can not be started from the Control Room.
QUESTION # 050 Given the following:
The reactor trips at 0832 due to a loss of all AC Power Neither Diesel Generator will start EOP-3.0, Station Blackout Recovery, has been implemented The latest time that the Station Batteries will be capable of performing their design function, if power is not restored, is (1) assuming Battery Load Stripping per EOP Supplements 7 and 8 (2) performed.
- a. (1) 1232 (2) is not
- b. (1) 1232 (2) is
- c. (1) 1632 (2) is not
- d. (1) 1632 (2) is
PALISADES REACTOR OPERATOR EXAMINATION Page 29 of 46 QUESTION # 051 Given the following conditions:
The Plant has experienced a loss of all offsite power Emergency Diesel Generator (D/G) 1-1 is loaded to 2200 kW D/G 1-2 is not available There is an unrecoverable leak of 1.1 gpm from T-10A T-10A, Fuel Oil Storage Tank, level is 92.5 by dipstick For the above conditions, how many days will T-10A inventory be able to support D/G 1-1 operation?
- a. 6.2.
- b. 6.8.
- c. 8.8.
- d. 9.0.
QUESTION # 052 All of the following Radiation Monitors will initiate automatic equipment actuation to prevent radioactive releases upon an alarming condition except:
- a. RIA-1810, East Engineered Safeguards Radwaste Ventilation Monitor.
- b. RIA-0631, Condenser Off-gas Monitor.
- c. RIA-0707, Steam Generator Blowdown Monitor.
- d. RIA-5711, Radwaste Addition Ventilation Monitor.
PALISADES REACTOR OPERATOR EXAMINATION Page 30 of 46 QUESTION # 053 Given the following:
The Plant is at full power P-7C, Service Water Pump, is out of service Then, P-7B, Service Water Pump, trips The Control Room team implements ONP-6.1, Loss of Service Water Critical SW Header A and B pressure is 40 psig EK-1165, NON-CRITICAL SERV WATER LO PRESS, is in Which one of the following (1) occurs in the Service Water System due to this event and (2) the condition that requires a Reactor trip?
- a.
(1)
P-4, Screen Wash Pump, automatically starts (2)
EK-0260, GENERATOR H2 COOLER HI TEMP
- b.
(1)
P-7A, Service Water Pump, is operating in a runout condition (2)
EK-0259, EXCITER COOLER HI TEMP
- c.
(1)
P-7A, Service Water Pump, is operating in a runout condition (2)
EK-0260, GENERATOR H2 COOLER HI TEMP
- d.
(1)
P-4, Screen Wash Pump, automatically starts (2)
EK-0259, EXCITER COOLER HI TEMP QUESTION # 054 Which one of the following correctly completes the following statement regarding automatic operation of C-2A, C-2B, and C-2C, Instrument Air Compressors?
The Instrument Air Compressors will automatically start in standby (AUTO) when pressure reaches (1) and will unload when pressure reaches (2).
- a.
(1) 92 (2) 100
- b.
(1) 92 (2) 105
- c.
(1) 88 (2) 100
- d.
(1) 88 (2) 105
PALISADES REACTOR OPERATOR EXAMINATION Page 31 of 46 QUESTION # 055 Given the following conditions with the Plant initially at full power:
A loss of coolant accident (LOCA) has occurred Safety Injection has actuated Containment pressure rose to 8.5 psig and has since lowered to 2.0 psig The CHP signal is then RESET:
o The Reactor Operator placed the Containment Spray Pump hand switches in TRIP and returned them to mid-position o The Containment Spray valves have been closed If the LOCA becomes larger causing Containment Pressure to rise and exceed the Containment High Pressure (CHP) actuation setpoint, the Containment Spray valves will (1) and the Containment Spray Pumps will (2).
- a.
(1) not open (2) not start
- b.
(1) open (2) start
- c.
(1) open (2) not start
- d.
(1) not open (2) start QUESTION # 056 Which one of the following correctly completes the following statement?
During a Reactor startup, any Regulating Control Rod group cannot be withdrawn until all Shutdown Control Rods are above a minimum of (1) and during a Reactor shutdown any Shutdown Control Rod group cannot be inserted until all Regulating Control Rods are below a maximum of (2).
- a.
(1) 122 (2) 4
- b.
(1) 131 (2) 4
- c.
(1) 122 (2) 6
- d.
(1) 131 (2) 6
PALISADES REACTOR OPERATOR EXAMINATION Page 32 of 46 QUESTION # 057 Given the following:
A Reactor startup is in progress PCS temperature is 532°F Which one of the following is the expected value for Hot Leg temperature (TH) when the Reactor reaches 75% power?
- a. 556°F.
- b. 570°F.
- c. 576°F.
- d. 583°F.
QUESTION # 058 Given the following:
A Plant start up is in progress Shutdown Control Rod Group B is being withdrawn in preparation for a critical approach While moving Shutdown Group B rods to the upper electrical limit (UEL), power is lost to the Primary Information Processor (PIP)
Which one of the following describes how Control Rod Position Indication will be affected due to the loss of the PIP?
- a. All red Control Rod Matrix lights on Panel C-12 will be lit (ON).
- b. All Control Rod Matrix lights on Panel C-12 will be dark (OFF).
- c. Position indication from the Reed Switches will be 0.0 on the Plant Process Computer.
- d. Position indication from the Synchro-transmitters will be -188.8 on Panel C-02.
PALISADES REACTOR OPERATOR EXAMINATION Page 33 of 46 QUESTION # 059 Given the following:
The Plant is operating at full power NI-5, Power Range Nuclear Instrument, sub-channel A fails low due to a faulty amplifier (see picture below showing C-06, Reactor Protective System Panel, indications)
Which one of the following alarms is expected to be received for this condition?
- a. EK-0606A, HIGH POWER RATE CHANNEL PRE-TRIP/ASI.
- b. EK-0601A, VARIABLE HIGH POWER LEVEL CHANNEL TRIP.
- c. EK-0608C, NI CHANNEL TROUBLE.
- d. EK-0941, GROUP 4 PREPWR DEPENDENT INSERTION LIMIT.
LIT LIT
PALISADES REACTOR OPERATOR EXAMINATION Page 34 of 46 QUESTION # 060 Given the following:
The Plant is operating at full power Qualified Core Exit Thermocouple #2 (CET #2) develops an open in the thermocouple circuit KCETA, Qualified CET Average, on the PPC is orange Which one of the following describes (1) the effect on Qualified CET #2 indication and (2) the required action the Control Room team will take in response to this indication?
- a.
(1)
CET #2 will indicate low (2)
Manually calculate Qualified CET Average.
- b.
(1)
CET #2 will indicate high (2)
Manually calculate Qualified CET Average.
- c.
(1)
CET #2 will indicate low (2)
Utilize Excores to monitor Linear Heat Rate.
- d.
(1)
CET #2 will indicate high (2)
Utilize Excores to monitor Linear Heat Rate.
QUESTION # 061 Given the following with the Plant in MODE 6:
Reactor Cavity water level is 647 2 Door-950, Spent Fuel Pool (SFP) South Tilt Pit Gate, is removed EK-1309, SPENT FUEL POOL HI/LO LEVEL, alarm annunciates due to a leak in the SFP Cooling System The Control Room team confirms that SFP level is lowering The Control Room Supervisor implements ONP-23.3, Loss of Refueling Water Accident Which one of the following conditions requires tripping the in-service SFP Cooling Pump?
- a. Alarm EK-1308, FUEL POOL CLG PUMPS DISCH LO PRESS, annunciates.
- b. RIA-2313, Spent Fuel Pool Criticality Monitor, alarms.
- c. Spent Fuel Pool temperature indicates greater than 108°F.
- d. Spent Fuel Pool temperature rises uncontrollably.
PALISADES REACTOR OPERATOR EXAMINATION Page 35 of 46 QUESTION # 062 Given the following:
The Reactor was manually tripped 45 minutes ago due to S/G tube leak indication on the B Steam Generator EOP-1.0, Standard Post Trip Actions, have been completed and all equipment operated as designed EOP-5.0, SGTR Recovery, is being implemented.
B S/G has been isolated per EOP Supplement 13 B S/G pressure is 700 psia PCS pressure is 900 psia Which one of the following is the highest B S/G level that does not exceed the maximum allowable in accordance with EOP-5.0 for the above conditions?
- a. 84%.
- b. 90%.
- c. 105%.
- d. 125%.
QUESTION # 063 Given the following:
The Control Room team is implementing EOP-7.0, Loss of all Feedwater Recovery, in response to a trip of both Main Feed Pumps from full power Auxiliary Feedwater is not available Emergency Boration is in progress The Control Room Supervisor directs the Reactor Operator to verify conditions are met to feed the S/Gs with P-2A, Condensate Pump Which one of the following conditions would preclude the Control Room team from using P-2A to feed the S/Gs?
- a. Either S/G level is less than - 75%.
- b. Turbine Bypass Valve is not available.
- c. The Condensate Storage Tank is isolated from the Condenser Hotwell.
- d. Condenser Hotwell level is less than 40%.
PALISADES REACTOR OPERATOR EXAMINATION Page 36 of 46 QUESTION # 064 Given the following:
A leak on the Instrument Air system occurs Instrument Air pressure is 93 psig and lowering slowly If Instrument Air pressure continues to lower, which one of the following lists the pressure at which CV-1212, Service Air Isolation Valve, is expected to automatically close?
- a. 88 psig.
- b. 85 psig.
- c. 80 psig.
- d. 75 psig.
QUESTION # 065 Given the following:
The Plant is shutdown in MODE 3 A Fire Protection System rupture has occurred which renders the system unavailable Which one of the following lists a system or component that will lose a backup water supply due to the above conditions?
- a. Non-critical Service Water System.
- b. C-2B, Instrument Air Compressor.
- c. P-8C, Auxiliary Feedwater Pump.
- d. P-8A, Auxiliary Feedwater Pump.
PALISADES REACTOR OPERATOR EXAMINATION Page 37 of 46 QUESTION # 066 Which one of the following describes the minimum requirements for receiving an alarm in the Control Room that is unexpected (i.e., not part of a planned activity)?
- a. Announce the alarm to the operating crew for each occurrence and reference the appropriate alarm response procedure each time the alarm comes in.
- b. Announce the alarm only if it is deemed critical by the ATC Operator and reference the appropriate alarm response procedure each time the alarm comes in.
- c. Announce the alarm to the operating crew for each occurrence and reference the alarm response procedure the first time the alarm comes in on each shift.
- d. Announce the alarm only if it is deemed critical by the ATC operator and reference the alarm response procedure the first time the alarm comes in on each shift.
QUESTION # 067 Which one of the following condition will cause V-94, Control Room Purge Exhaust Fan, to automatically trip when in service?
- a. Control Room pressure lowers to < 0.125 H2O.
- b. V-26A, Emergency Filter Fan, starts.
- c. VC-10, Control Room HVAC Condensing Unit, trips.
- d. RIA-1818A, Control Room Continuous Air Monitor, alarms.
PALISADES REACTOR OPERATOR EXAMINATION Page 38 of 46 QUESTION # 068 Given the following with the Plant initially at 100% power:
Preparations are being made to lower Plant power to 50% due to a problem with Steam Generator chemistry A 500 gallon continuous boration of the Primary Coolant System is commenced at 7 gpm Which one of the following correctly completes the statement below describing the expected effect on Moderator Temperature Coefficient (MTC) and Axial Shape Index (ASI) due to the boration?
MTC will be (1) and ASI will be (2).
- a.
(1)
Less negative (2)
More negative (less positive)
- b.
(1)
More negative (2)
More negative (less positive)
- c.
(1)
Less negative (2)
More positive (less negative)
- d.
(1)
More negative (2)
More positive (less negative)
QUESTION # 069 Which one of the following is not a criterion that is considered when evaluating if the controls of EN-OP-116, Infrequently Performed Tests or Evolutions, apply for a given test or evolution?
The test or evolution
- a. has the potential to introduce plant transients if performed incorrectly.
- b. requires the use of special test procedures in conjunction with existing procedures.
- c. is performed on equipment essential to maintain the plant within Technical Specification limits.
- d. is performed by an inexperienced operator.
PALISADES REACTOR OPERATOR EXAMINATION Page 39 of 46 QUESTION # 070 Given the following:
The Plant is operating at full power The Pressurizer Level Control System is lined-up normally Then, the in-service Pressurizer Level Transmitter, LT-0101B, fails low The following alarms are received:
o EK-0704, LETDOWN HT EX TUBE INLET HI-LO PRESS o EK-0741, PRESSURIZER HTR TRANSF #15 AND #16 BREAKERS TRIP o EK-0742, PRESSURIZER HTR BUS GROUND/UNDERVOLTAGE o EK-0761, PRESSURIZER LEVEL HI-LO o EK-0764, PRESSURIZER LEVEL CH B LO-LO Approximately how long will it take for Pressurizer level to reach a Technical Specification limit?
(Assume no operator action)
- a. 2 minutes, 58 seconds.
- b. 4 minutes, 7 seconds.
- c. 5 minutes, 44 seconds.
- d. 11 minutes, 12 seconds.
QUESTION # 071 Given the following:
Preparations are being made to synchronize the Turbine Generator to the Grid TAVE is 538°F and stable Reactor power is 13% and stable by Nuclear Instrumentation (NI)
PIC-0511, Turbine Bypass Valve Controller, output is 50% and stable The Reactor Operator begins withdrawing Control Rods to raise PIC-0511 output Which one of the following alarms will annunciate if the Reactor Operator continues to withdraw Control Rods and power reaches 15%?
- a. EK-0917, ROD WITHDRAWAL PROHIBIT
- b. EK-0107, TURBINE NO LOAD PRETRIP
- c. EK-0101, TURBINE TRIP
- d. EK-0605A, VARIABLE HIGH POWER LEVEL CHANNEL PRE-TRIP
PALISADES REACTOR OPERATOR EXAMINATION Page 40 of 46 QUESTION # 072 The Plant is being cooled down in MODE 4 following a Steam Generator Tube Rupture event.
An RP Technician performing a survey in the Component Cooling Water room measures a dose rate of 120 mrem/hr one-foot away from the B Steam Generator Main Steam line.
Which one of the following postings is required for this dose rate at this location?
- a. Radiation Area.
- c. Very High Radiation Area.
QUESTION # 073 Which one of the following is not an action from ONP-23.2, Steam Generator Tube Leak, to help limit the spread of contamination following the discovery of a Steam Generator Tube Leak?
- a. Start a Plant Heating Boiler.
- b. Route After Condenser Drains to the Condenser.
- c. Isolate Steam Generator Blowdown flow.
- d. Isolate the Moisture Separator Reheaters.
QUESTION # 074 Given the following:
The Reactor is tripped from full power due to a loss of both Main Feedwater Pumps EOP-7.0, Loss of All Feedwater, has been implemented due to problems with Auxiliary Feedwater Which one of the following conditions requires the initiation of Once-Through Cooling per EOP-7.0?
- a. Both S/Gs have level at - 84% and rising slowly.
- b. A S/G level is - 88%, B S/G level is - 79%, and Cold Leg temperatures have risen 10°F and continue to rise.
- c. A S/G level is - 88%, B S/G level is - 83%, and Cold Leg temperatures are stable.
- d. Both S/Gs have level at - 80% and lowering slowly.
PALISADES REACTOR OPERATOR EXAMINATION Page 41 of 46 QUESTION # 075 Given the following:
The Plant is in MODE 1 at full power Charging and Letdown systems are aligned for normal operation Alarm EK-0709, VOLUME CONTROL TANK HI-LO LEVEL annunciates While investigating EK-0709, alarm EK-0710, VOLUME CONTROL TANK LO-LO LEVEL alarm annunciates Which one of the following describes the effect on the Plant due to this condition and the reason?
- a. Reactor power will be lowering due to Charging Pumps swapping suction to Boric Acid Storage Tanks.
- b. Reactor power will be lowering due to Charging Pumps swapping suction to the SIRW Tank.
- c. Pressurizer level will be lowering due to all Charging Pumps automatically tripping.
- d. Pressurizer level will be lowering due to all Letdown Orifice Stop Valves automatically opening.
- END OF EXAMINATION **************
PALISADES REACTOR OPERATOR EXAMINATION Page 42 of 46 001
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REACTOR OPERATOR EXAMINATION REFERENCES Page 43 of 46 The following question references were for modifications or replacements for unsatisfactory questions. The references for unchanged questions are in the proposed written examination.
QUESTION # 001 ANSWER:
- d.
REFERENCE:
EOP-1.0, Step 3 EOP-1.0 Basis Document, page 10 NEW FUNDAMENTAL K/A:
CE-EO2 EK3.3 - Knowledge of the reasons for the following responses as they apply to the (Reactor Trip Recovery): Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.
DISTRACTOR ANALYSIS
- a. First part candidate may confuse the required contingency action of EOP-1.0 if the MFP will not go into manual (and constant speed) with also having to close the FRV which is in another step, second part candidate incorrectly believes the action is due to concern over fed flow imbalance to A and B S/Gs.
- b. First part candidate may confuse the required contingency action of EOP-1.0 if the MFP will not go into manual (and constant speed) with also having to close the FRV which is in another step, second part is correct per EOP-1 basis document.
- c. First part is correct, second part candidate incorrectly believes the action is due to concern over feed flow imbalance to A and B S/Gs.
- d. Correct QUESTION # 008 ANSWER:
- d.
REFERENCE:
ARP-4, Window 64 SOP-1A 7.2.1.f, Step 5 ONP-18, Step 4.2.1 NEW HIGHER K/A:
000027A104 Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Pressure recovery, using emergency-only heaters.
DISTRACTOR ANALYSIS
- a. Candidate incorrectly believes that ONLY the conditions are met for D bus PZR heaters to be energized when in fact, with HS-1/LIC-0101 in the A+B position the system will still receive input from the failed LOW. ALL PZR heaters will be de-energized (there are steps in ONP-18 for CS 152-211 manipuation).
- b. Candidate incorrectly believes that the conditions are NOT met to restore D PZR heaters but E PZR heaters were restored after placing the PZR level channel selector to A position.
- c. Candidate incorrectly believes all conditions are met and E heaters were already on prior to closing CS for D bus heaters and once CS 152-211 is closed D and E bus heaters will be on.
- d. correct
REACTOR OPERATOR EXAMINATION REFERENCES Page 44 of 46 QUESTION # 011 ANSWER:
- b.
REFERENCE:
EOP-6, Section 2.0 M-207, Sheet 1 EOP-1, Step 8 BANK HIGHER K/A: CE/EO5 EK2.1 Knowledge of the interrelations between the Excess Steam Demand and the following: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
DISTRACTOR ANALYSIS
- a. Plausible if the student believes that all valves close similar to a CHP event.
- b. Correct
- c. Plausible if the student misapplies the concept that only the A FRV closes.
- d. Plausible if the student believes that the goal of an MSIS on low S/G pressure is to isolate only the affected S/G.
QUESTION # 032 ANSWER:
- c.
REFERENCE:
ARP-8, Window 12 NEW FUNDAMENTAL K/A: 006A303 Ability to monitor automatic operation of the ECCS, including: ESFAS operated valves.
DISTRACTOR ANALYSIS
- a. Plausible if the student believes the valve has an over-torque condition. This is plausible because these are limitorque valves.
- b. See distractor (a.)
- c. correct
- d. Plausible if the candidate correctly believes that the motor thermal overload has actuated but believes that it will keep the va.ve from operating.
REACTOR OPERATOR EXAMINATION REFERENCES Page 45 of 46 QUESTION # 046 ANSWER:
- d.
REFERENCE:
ARP-5, Window 61 ARP-1, Window 5 M-207, Sheet 1 OA 115 for LIC 0701/0703 NEW HIGH K/A: 059K103 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems S/Gs DISTRACTOR ANALYSIS
- a. Plausible if the student believes the presented controller condition will cause the FRV on A S/G to close. However, the red pointer represents the S/G level input and since it is failed low the FRV will open.
- b. Plausible if the student believes the feed flow portion of the SGWLC circuitry will compensate for the failed input.
- c. Plausible since the failed low S/L level input will cause the FRV for A S/G to open and the student does not recall that the high level override circuitry is enacted at 84.7% from a different level transmitter to prevent moisture carry-over.
- d. correct QUESTION # 057 ANSWER:
- b.
REFERENCE:
FSAR Figure 4.9 NEW HIGHER K/A: 002K510 Knowledge of the operational implications of the following concepts as they apply to the RCS: Relationship between reactor power and RCS differential temperature.
DISTRACTOR ANALYSIS
- a. Plausible if the student misapplies the delta T concept and approaches the problem as if Tave is constant.
- b. correct
- c. Plausible if the student assumes TH starts at 538°F, which is the value of Tc at full power
- d. Plausible because this is the TH value at 100% power.
REACTOR OPERATOR EXAMINATION REFERENCES Page 46 of 46 QUESTION # 066 ANSWER:
- a.
REFERENCE:
EN-OP-115-08, 5.2.10 and 5.2.11.2 BANK FUNDAMENTAL K/A: G 2.1.1 Knowledge of conduct of operations requirements.
DISTRACTOR ANALYSIS
- a. correct
- b. Plausible because this is how alarms are announced during transient conditions.
- c. Plausible because this was an acceptable method in the past but the requirement is now to review the ARP every time.
- d. Plausible for a combination of (b.) and (c.).