ML100910311
| ML100910311 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/17/2009 |
| From: | Moore C NRC/RGN-III/DRS/OLB |
| To: | Detroit Edison |
| References | |
| Download: ML100910311 (107) | |
Text
2009 Fermi 2 NRC SRO License Exam QUESTION 1
With the plant operating at 100% power, the following indications exist: 7D14, GEN SERV H2O HEADER PRESSURE HIGH/LOW alarms 4D64 GENERATOR H2 COOLERS INLET/OUTLET GAS TEMP HIGH / LOW TEMP HIGH alarms. Main Generator H 2 Cooler Outlet Temperat ure is 195ºF on N30-R807. GSW Pressure is 60 psig, lowering 1 psig per minute with ALL GSW Pumps running. RBCCW HX Outlet temperature is 88ºF.
With one of the following actions is required?
_____ A. Direct the CRNSO to place the Reactor Mode Switch in SHUTDOWN and TRIP the Main Turbine Generator, per 20.131.01, Loss of General Service Water System.
_____ B. Direct the CRNSO to place the Reactor Mode Switch in SHUTDOWN and TRIP BOTH Reactor Recirculation Pumps within TWO minutes per 20.127.01, Loss of Reactor Building Closed Cooling Water.
_____ C. Direct the CRNSO to REDUCE Reactive Load as necessary to reduce Hydrogen Coolers Outlet Temperature, per ARP 4D64, GENERATOR H2
COOLERS INLET/OUTLET GAS TEMP HIGH / LOW TEMP HIGH.
_____ D. Direct the CRNSO to INCREASE cooling water flow using N30-K813, Hydrogen Coolers Temp Controll er, per ARP 4D64, GENERATOR H2 COOLERS INLET/OUTLET GAS TEMP HIGH / LOW TEMP HIGH.
2009 Fermi 2 NRC SRO License Exam QUESTION 2
While mitigating a transient involving a failure to scram and an unisolable Main Steam Line Break, plant conditions are as follows: Reactor Power is 14%. Reactor Pressure is 800 psig. RPV Water Level is -20 (minus 20) inches, maintained with Feedwater. Radiation Dose rates at the Site Boundary are 950 mrem/hr, rising. 29.ESP.03, Alternate Control Rod Insertion, is in progress.
Which one of the following actions are required?
_____ A. Anticipate Emergency Depressurization by opening Turbine Bypass Valves. _____ B. Terminate and Prevent RPV Injection and lower RPV Water Level until power lowers to 3%.
_____ C. Terminate and Prevent RPV Injection and Emergency Depressurize the reactor by opening Safety Relief Valves.
_____ D. Maintain RPV Pressure 800 to 100 psig and RPV Water Level above -25 (minus 25) inches while continuing Alternate Rod Insertion.
2009 Fermi 2 NRC SRO License Exam QUESTION 3
The plant is in MODE 5, REFUELING. Spent fuel is being moved from the Reactor Vessel and placed in the Spent Fuel Pool, with the following conditions: One RHR Loop is OPERABLE and is in service. BOTH Reactor Recirculation Pumps are secured. Reactor Coolant System Temperature is 105ºF. Spent Fuel Pool Water Level has lo wered to 21 feet above the fuel. The operating Fuel Pool Cleanup Pump has tripped.
Based on these conditions, which one of the following describes the affect of these conditions on tech specs, if any, and the appropriate basis?
_____ A. Fuel movement must be suspended until a Reactor Recirculation Pump is started, based on preserving Decay Heat Removal capability.
_____ B. Fuel movement must be suspended until a second RHR Loop is OPERABLE, based on preserving Decay Heat Removal capability.
_____ C. Fuel movement must be suspended until Spent Fuel Pool Water Level is restored above 22 feet, based on preserving Iodine Absorption capability.
_____ D. Fuel movement may continue until Spent Fuel Pool Water Level lowers to 20 feet 6 inches above the Reactor Pressure Vessel Flange, based on
preserving Iodine Absorption capability.
2009 Fermi 2 NRC SRO License Exam QUESTION 4
Following a transient, the following conditions exist: Drywell Temperature is 280ºF and stable. Drywell Pressure is 15 psig. Reactor Pressure is 20 psig. RPV Water Level is -10 (minus 10) inches. ALL RHR Pumps are injecting.
Which one of the following actions is required?
_____ A. Enter 29.100.01 Sheet 3, RPV Floodi ng, and inject until th e RPV is flooded to the Main Steam Lines.
_____ B. Open Turbine Bypass Valves a nd rapidly depressurize the reactor per 29.100.01 Sheet 1, RPV Control.
_____ C. Enter 29.100.01 Sheet 3, Emergenc y Depressurization, and inject until RPV Pressure is > 64 psig above Torus Pressure.
_____ D. Wait until RPV Water Level lowers to -40 (minus 40) inches and then Emergency Depressurize per 29.100.01 Sheet 3, Steam Cooling.
2009 Fermi 2 NRC SRO License Exam QUESTION 5
The plant is operating at 30%
power. Due to a loss of Drywell Cooling, the following sequence occurred: At 1205; 3D81, PRIMARY CONTAINMENT PRESSURE HIGH/LOW alarmed.
o Drywell Pressure indicated 1.50 psig. At 1206; 8D41, DIV I DRYWELL TEMPERATURE HIGH alarmed. At 1206; 17D41, DIV II DRYWELL TEMPERATURE HIGH alarmed.
o Average Drywell Temperature was 140ºF. At 1300; Drywell Pressure was lowere d by venting Nitrogen, clearing alarm 3D81. At 1320; Drywell Cooling was restored, clearing alarms 8D41 and 17D41. At 1340; 3D81 PRIMARY CONTAINMENT PRESSURE HIGH/LOW alarmed again.
o Drywell Pressure is -0.15 (minus 0.15) psig.
o Drywell Temperature is 120ºF.
Which one of the following describes the OPERABILITY of the Primary Containment, with respect to Temperature and Pressure, during this evolution?
_____ A. The Primary Containment was maintained OPERABLE throughout this evolution and no actions are required.
_____ B. The Primary Containment was rendered INOPERABLE due to Low Drywell Pressure only, and remains INOPERABLE.
_____ C. The Primary Containment was rendered INOPERABLE due to Low Drywell Pressure and High Average Temperature, and remains INOPERABLE.
_____ D. The Primary Containment was rendered INOPERABLE due to High Average Temperature AND High Drywe ll Pressure, and Required Actions were met within the Completion Time.
2009 Fermi 2 NRC SRO License Exam QUESTION 6
The plant is operating at 100% power when the following sequence occurs:
At 0915; 16D27 FIRE ALARM alarms. At 0915; Wet Pipe System in the RFPT Lube Oil Room has actuated. At 0915; 7D10 ELECTRIC FIRE PUMP AUTO START alarms. At 0940; The Fire Brigade is on the scene fighting the fire. At 0950; The Fire Brigade reports that the fire is out.
Which of the following is the appropriate Emergency Action Level (EAL) and why?
_____ A. Unusual Event, because a fire is within the Protected Area Boundary and was NOT extinguished within 15 minutes.
_____ B. Unusual Event, because a fire affecting the operability of systems required to maintain Safe Shutdown has occurred.
_____ C. Alert, because a fire is within the Protected Area Boundary and was NOT extinguished within 15 minutes.
_____ D. Alert, because a fire affecting the operability of systems required to maintain Safe Shutdown has occurred.
2009 Fermi 2 NRC SRO License Exam QUESTION 7
Following a transient, plant conditions are: Reactor Power is 10%. RPV Water Level is 110 inches. 2 Safety Relief Valves are OPEN. Reactor Pressure is 1000 psig. Standby Liquid is injecting. Torus Water Temperature is 121ºF. BOTH Loops of RHR are in Torus Cooling mode.
What action is required and why is this action required by the Emergency Operating Procedure Bases?
_____ A. It is required to lower Reactor Pr essure by opening Safety Relief Valves to place the reactor in a lower energy state.
_____ B. It is required to lower Reactor Water level by terminating and preventing injection to reduce natural ci rculation and reactor power.
_____ C. It is required to raise Reactor Water Level by raising Feedwater Flow to ensure that maximum fuel temperatures are not exceeded.
_____ D. It is required to lower Reactor Water level by terminating and preventing injection to increase the concentration of sodium pentaborate near the fuel.
2009 Fermi 2 NRC SRO License Exam QUESTION 8 With the plant is in Mode 3, Hot Shutdown, with the following conditions: Reactor Pressure is 85 psig. Main Steam Isolation Valves are OPEN. RHR Loop A is operating in Shutdown Coo ling Mode with cooldown in progress. Reactor Water Cleanup is in service.
Power to RPS Bus A is subsequently lost due to a trip of RPS MG Set A. How is the plant affected by this loss, and which of the stated actions will restore the plant to normal?
_____ A. B2103-F022 A through D, Inboard Main Steam Isolation Valves will ISOLATE due to power loss to Main Steam Line Radiation Monitors. Enter SOP 23.137, Nuclear Boiler System. Reopen the MSIVs. Continue
cool down using RHR Loop A.
_____ B. G3352-F004, RWCU Supply Outboard Isolation Valve will ISOLATE due to a loss of logic power. Ente r AOP 20.707.01, Loss of RWCU. RWCU will be restored by placing RPS Div 1 on Alternate Power, resetting the isolation, and r ealigning RWCU.
_____ C. E1150-F015A, Div 1 LPCI Inboard Isolation Valve will ISOLATE due to a spurious RPV Water Level 3 signal. Enter SOP 23.205, RHR System.
Shutdown Cooling will be restored by starting an RHR Loop B Pump and opening E1150-F015B, Div 2 LPCI Inboard Isolation Valve.
_____ D. E1150-F015A, Div 1 LPCI Inboard Isolation Valve AND E1150-F009, RHR SDC Inboard Suction Isolati on Valve will ISOLATE due to a spurious RPV Water Level 3 signal. Enter AOP 20.205.01, Loss of Shutdown Cooling. Shutdown Cooling will be restored by placing RPS Bus A on Alternate Power, resetting the isolation, and realigning RHR Loop A 2009 Fermi 2 NRC SRO License Exam QUESTION 9
The reactor is Mode 2, STARTUP, with the following conditions: Reactor Power is on Range 7 of the Intermediate Range Monitors. Reactor Pressure is 940 psig. At 1105; 3D1, CRD PUMP A/B SUCTION PRESSURE LOW alarms. At 1110; 3D10, CRD ACCUMULATOR TROUBLE alarms for HCU 26-55, which is FULLY INSERTED. A Nuclear Operator confirms a Low Pressure condition. At 1120; 3D10, CRD ACCUMULATOR TROUBLE alarms for HCU 18-47, which is at position 48. A Nuclear Operator confirms a Low Pressure condition.
Which one of the following actions is REQUIRED by Technical Specifications?
_____ A. At 1120, disarm Control Rod 18-47, because without drive capability, Control Rod 18-47 is considered stuck.
_____ B. At 1130, place the Reactor Mode Switch in SHUTDOWN, to avoid the loss of scram function
_____ C. At 1140, place the Reactor Mode Switch in SHUTDOWN, to avoid the loss of scram function.
_____ D. At 1140, declare Control Rods 26-55 AND 18-47 INOPERABLE, due to slower than normal scram times.
2009 Fermi 2 NRC SRO License Exam QUESTION 10
Following a Loss of Coolant Accident, Co re Spray is injecting at 6800 gpm. Which one of the following is the RPV Wa ter Level which requires transitioning to Severe Accident Guidelines?
_____ A. 0 inches
_____ B. -25 (minus 25) inches
_____ C. -40 (minus 40) inches
_____ D. -48 (minus 48) inches
2009 Fermi 2 NRC SRO License Exam QUESTION 11
With RHR Pump D operating in the S hutdown Cooling Mode, 2D26, DIV II RHR SYSTEM LOW FLOW BYPASS INITIATED alarms due to a flow instrument failure.
Which one of the following describes the initi al impact of this c ondition, and what action is required?
_____ A. RHR Pump D will TRIP due to a va lve closure. It is required to START RHR Pump B.
_____ B. RHR Pump D will OPERATE with NO discharge flow path. It is required to STOP RHR Pump D.
_____ C. RPV Water Level will RISE due to reactor coolant temperature rise. It is required to CLOSE E1150-F048B, Div 2 RHR Hx Bypass Valve.
_____ D. RPV Water Level will LOWER due to coolant being pumped to the Torus.
It is required to CLOSE E1150-F007B Div 2 RHR Pumps Minimum Flow Valve.
2009 Fermi 2 NRC SRO License Exam QUESTION 12
A plant transient has occurred which caused the ADS System to automatically actuate. The current plant conditions are as follows: Reactor - All rods inserted Narrow Range RPV Water Level - 197 inches RPV Pressure - 50 psig
Which one of the following surveillances is procedurally required to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> due to the SRV actuation?
_____ A. 24.201.01, SRV Vacuum Breaker Operability Test
_____ B. 24.137.11, Safety Relief Valve (SRV) Operability Test
_____ C. 24.402.07, Drywell to Suppression Chamber Bypass Leak Test
_____ D. 24.402.01, Drywell and Suppression Chamber Vacuum Breaker Operability Test
2009 Fermi 2 NRC SRO License Exam QUESTION 13
The plant is operating at 50% power. Digital Feedwater Level Control is in 3-Element control with the Reactor Level Select Switch in A. 3D164, FEEDWATER CONTROL DCS TROUBLE has alarmed, and both Reactor Feedwater Pump Controllers have switched to Emergency Bypass.
What is the resulting impact to Feedwater Level Control (DCS), and what action is required by procedure?
_____ A. DCS will shift to Forced Single Element Control. Enter SOP 23.107.01.
PLACE the Level Control Mode Switch in 1 ELEM, and continue power operation in Single Element Control.
_____ B. DCS remains in 3 Element Control. Enter SOP 23.107.01. PLACE both Emergency Bypass switches in position "M", manually adjust Reactor Feedwater Pump Controllers to matc h Feed Pump speeds, and continue power operation in 3 Element Control.
_____ C. DCS will shift to Forced Single Element Control. Enter AOP 20.107.01. North and South Reactor Feedwater Pump speeds will lower. Adequate Pumping capacity is NOT available. The Reactor Mode Switch must be placed in Shutdown.
_____ D. DCS remains in 3 Element Control. Enter AOP 20.107.01. PLACE both Emergency Bypass switches in position "M", manually adjust Reactor Feedwater Pump Controllers to match Feed Flow with Steam Flow, and continue power operation with ma nual feed pump speed control.
2009 Fermi 2 NRC SRO License Exam QUESTION 14
The plant is in Mode 4, Cold Shutdown, with CRD Mechanism replacement in progress.
This evolution is an Operation with Potential to Drain the Reactor Vessel (OPDRV). Standby Gas Treatment Train A is op erating for Surveillance Testing.
The following conditions are noted:
Reactor Building Pressure is -0.20 (minus 0.20) inches water column. Standby Gas Train A Flow is 2900 cfm.
Which one of the following is correct regarding the OPERABILITY of Standby Gas Train A?
Standby Gas Treatment Train A is:
_____ A. NOT required OPERABLE dur ing current plant conditions.
_____ B. OPERABLE; and no action is required.
_____ C. INOPERABLE; it is required to restore Train A to OPERABLE status
_____ D. INOPERABLE; it is required to suspend CRD Mechanism replacement IMMEDIATELY.
2009 Fermi 2 NRC SRO License Exam QUESTION 15
The plant is operating at full power, when the following indications are noted: The Normal Feeder for Bus 65E, Breaker E6, OPENED. Emergency Diesel Generator (EDG) 13 did not start. The ESF-EDG Bus Tie Breaker for Bus 65E, Breaker E8, OPENED. Buses 64B, 64C, and 65F are powered from their Normal Sources. EDGs 11, 12, and 14 remain in standby.
Which one of the following conditions produced these indications, and what action is required?
_____ A. A malfunction of EDG 13 has occurred. Enter 20.307.01.01 Emergency Diesel Generator Start Failure , and MANUALLY start EDG 13.
_____ B. An electrical fault has occurr ed on Bus 65E. Enter 20.300.65E, Loss of Bus 65E. After the fault is corrected, re-energize Bus 65E per 23.321, ESF Electrical Distribution System.
_____ C. A spurious Division II Loss of Coolant Accident Signal is received. Place the Emergency Signal Bypass Keylock Selector Switch in BYPASS, and declare EDG 13 INOPERABLE per LCO 3.8.1.1.
_____ D. A malfunction of Breaker E6 has occurred. Enter 20.300.65E, Loss of Bus 65E. Re-energize Bus 65E by MANUALLY closing Breaker E9, Alternate Feed to Bus 65E per 23.321, ESF Electrical Distribution System.
2009 Fermi 2 NRC SRO License Exam QUESTION 16
The plant is operating at 75% power, when the Steam Pressure input to Pressure Regulator 1 FAILS LOW.
Which one of the following is the expected effect of this failure , and what action is required?
Reactor Pressure will __(1)__. It is required to __(2)__.
_____ A. (1) RISE until a reactor scram occurs.
(2) enter 20.000.21, Reactor Scram and 29.100.01, RPV Control.
_____ B. (1) RISE 3.5 psig.
(2) enter 20.109.02 Reactor Pressure Controller Failure and raise Reactor Power above 90%.
_____ C. (1) LOWER until a reactor scram occurs.
(2) enter 20.000.21, Reactor Scram control Reactor Pressure with Safety Relief Valves.
_____ D. (1) RISE 3.5 psig.
(2) enter 20.109.02 Reactor Pressure Controller Failure, and maintain Reactor Power at 75% until both Pressure Regulators are in service.
2009 Fermi 2 NRC SRO License Exam QUESTION 17
Following an Emergency Depressurization under ATWS conditions the following conditions exist: RPV Water Level indications are UPSC ALE due to High Drywell and Reactor Building Temperatures. Injection has been Terminated and Prevented. 4 Safety Relief Valves are OPEN. Reactor Pressure is 300 psig. Reactor Power is 20%.
Under these conditions, which one of the following describes the status of Core Cooling?
Adequate Core Cooling is:
_____ A. ASSURED by core submergence.
_____ B. ASSURED by sufficient steam flow through OPEN Safety Relief Valves.
_____ C. NOT ASSURED because injection is insufficient to cool the core.
_____ D. NOT ASSURED because an inadequate number of Safety Relief Valves are OPEN.
2009 Fermi 2 NRC SRO License Exam QUESTION 18
The plant is in MODE 5, REFUEL , with the following conditions. ONE Control Rod is withdrawn to position 48. The Refuel Platform is moving a New Fuel Assembly from the Spent Fuel Pool towards the Reactor Cavity. The Refuel Platform personnel notify the CRN SO that they are prepared to lower the New Fuel Assembly into the core.
Which one of the following describes these c onditions, and what action is required?
_____ A. This is an expected sequence of events; permission should be granted to continue the move.
_____ B. The Refueling Hoist is prevented from lowering. It is required to fully insert the withdrawn Control Rod and continue fuel movement.
_____ C. The Refueling Platform should have automatically stopped prior to reaching the reactor cavity. It is required to suspend fuel movements after placing the New Fuel Assembly in the Spent Fuel Pool.
_____ D. The Refueling Platform should have automatically stopped prior to reaching the reactor cavity. It is required to suspend fuel movements after placing the New Fuel Assembly in the correct core location.
2009 Fermi 2 NRC SRO License Exam QUESTION 19
Per MGA09, Access Control, certain vehicles may be exempted from searches and Radiation Protection inprocessing with the approval of the Shift Manager. Which one of the following vehicles meets this criterion?
_____ A. Monroe - Mercy Hospital Ambulance responding to Medical Emergency.
_____ B. EPA HAZMAT Truck responding to chemical spill at Aux Boiler House
_____ C. Fuel Oil Delivery Truck re sponding to restore EDG 13 OPERABILITY prior to LCO expiration in 2 Hours
_____ D. ITC Work crew Truck responding to Tech Spec work on 345KV Mat prior to LCO expiration in 3 Hours
2009 Fermi 2 NRC SRO License Exam QUESTION 20
The plant is operating at full power. All systems are aligned for normal operations.
Which one of the following maintenance activities would REQUIRE immediate notifications, and to whom would the notification be made?
_____ A. CTG 11-1 Out of Service: NRC Resident
_____ B. CTG 11-1 Out of Service: Plant Manager
_____ C. CTG 11-2 Out of Service: Work Week Manager
_____ D. CTG 11-2 Out of Service: Central System Supervisor
2009 Fermi 2 NRC SRO License Exam QUESTION 21
Which one of the following contains the limitation of 3430 Megawatts as the Maximum Power Level for operation?
_____ A. Facility Operating License, NPF-43
_____ B. Core Operating Limits Report, Cycle 12
_____ C. Safety Limits, Technical Specifications 2.1
_____ D. Power Distribution Limits , Technical Specifications 3.2
2009 Fermi 2 NRC SRO License Exam QUESTION 22
To prevent exceeding Primary Containment Pressure Limit, 29. ESP.07, Primary Containment Venting is being executed. Containment conditions are: Drywell Pressure is 51 psig. Torus Pressure is 50 psig. Torus Water Level is 0 inches.
Which one of the following vent strategies is appropriate?
_____ A. Vent the Torus via Standby Gas Treatment.
_____ B. Vent the Drywell via Standby Gas Treatment.
_____ C. Vent the Torus using the Hardened Vent Path.
_____ D. Vent the Drywell using the Hardened Vent Path.
2009 Fermi 2 NRC SRO License Exam QUESTION 23
With the plant initially operating at 100% power, a fuel cladding defect resulted in High Offgas and Main Steam Line Radiation Levels. A Plant Shutdown has been performed to comply with LCO 3.4.7 Reactor Coolant Specific Activity. Plant conditions are as follows: All Control Rods are inserted. Reactor Pressure is 940 psig, regulated with Main Turbine Bypass Valves. Offgas is in service with Conde nser Backpressure at 1.0 psia. Offsite dose rates have reached the Alert level 3D82 MN STM LINE RADIATION UPSCL INOP CHANNEL TRIP alarms.
Which one of the following strategies is required to minimize radioactivity release to the environment?
_____ A. Cooldown at LESS THAN 100ºF by de pressurizing to the Main Condenser to allow the Offgas treatment process to limit radioactivity releases.
_____ B. Close the Third MSIVs, and cooldown at LESS THAN 100ºF by depressurizing to the Torus to allow the Containment to limit radioactivity
release.
_____ C. Rapidly cooldown at GREATER THAN 100ºF by depressurizing to the Main Condenser to allow the Offgas treatment process to limit radioactivity releases.
_____ D. Close the Third MSIVs, and rapidly cooldown at GREATER THAN 100ºF by depressurizing to the Torus to allow the Containment to limit radioactivity release.
2009 Fermi 2 NRC SRO License Exam QUESTION 24
The plant is operating at 100% power when a loss of power of 345kv offsite occurs. EDGs 13 and 14 have started and loaded A and B RR MG sets have tripped. 3D79 REAC VESSEL WATER LEVEL L3 CHANNEL TRIP is in alarm. 10D43 DIV 2 BUS VOLTAGE LOW is in alarm. 17D41 DIV 2 DRYWELL TEMP HI is in alarm. T47-R803B DW Cooling System Area Temp Div 2 - Point 24 reads 138°F. The Mode Switch has been placed in SHUTDOWN
Which one of the following procedures will the CRS be required to enter NEXT and direct the crew's actions?
_____ A. 20.300.345kv Loss of 345kv
_____ B. 20.138.01 Recirc Pump Trip
_____ C. 29.100.01 RPV Control Sheet 1
_____ D. 29.100.01 Primary Containment Control Sheet 2
2009 Fermi 2 NRC SRO License Exam QUESTION 25
Which one of the following sets of plant conditions would require an Emergency Classification of Site Area Emergency?
_____ A. Security Event resulting in loss of physical contro l of the facility.
_____ B. Any loss OR potential loss of either fuel clad OR reactor coolant boundary.
_____ C. Failure of reactor protection system instrumentation to complete OR initiate an automatic reactor scram once a reactor protection system
setpoint has been exceeded AND manual scram was NOT successful.
_____ D. Site boundary dose resulting from an actual OR imminent release of gaseous radioactivity that exceeds 1000 mrem TEDE OR 500 mrem Adult Thyroid for the actual OR projected duration of the release using actual meteorology.
2009 Fermi 2 NRC RO License Exam QUESTION 1
With the plant operating at 85% Reactor Power and 80 Mlbm/hr Core Flow, Reactor Power unexpectedly LOWERED to 80%.
The following indications are noted:
Loop A Jet Pump Flow INCREASED to 42 Mlbm/hr. Loop B Jet Pump Flow LOWERED to 33 Mlbm/hr. Jet Pump 3 and Jet Pump 4 Flow LOWERED from 3.5 to 0.0 Mlbm/hr.
Which one of the following is indicated?
_____ A. Riser for Jet Pump 3 has failed.
_____ B. Diffuser for Jet Pump 3 has failed.
_____ C. North RR Motor Generator Set A speed has increased.
_____ D. B3105-F031B, S RR Pump Discharge Valve, has shut.
2009 Fermi 2 NRC RO License Exam QUESTION 2
The Reactor Mode Switch is in SHUTDOWN and Reactor Coolant Temperature is 205ºF.
Electrical power is then lost to the 34 5 kV Switchyard. ALL other AC sources are energized.
Which one of the following describes the applicable Limiting Condition for Operation (LCO) and the status of LCO compliance?
_____ A. LCO 3.8.1, AC Sources - Operating is applicable, and th e LCO is satisfied.
_____ B. LCO 3.8.1, AC Sources - Operating is applicable, and the LCO is NOT satisfied.
_____ C. LCO 3.8.2, AC Sources - Shutdown is applicable, and the LCO is satisfied.
_____ D. LCO 3.8.2, AC Sources - Shutdown is applicable, and the LCO is NOT satisfied.
2009 Fermi 2 NRC RO License Exam QUESTION 3
A complete loss of DC Power from Batte ry 2B-1 Div 2 DC Bus has occurred.
If current exceeds the overcurrent trip setpoint on the breaker for Bus 65E Pos E6, 4160V Normal Feed to Bus 65E, which one of the following will occur with NO operator action?
_____ A. The breaker will TRIP and NEITHER position indication light will be lit.
_____ B. The breaker will TRIP and the OPEN position indication light will be lit.
_____ C. The breaker will REMAIN CLOSED and NEITHER indication light will be lit.
_____ D. The breaker will REMAIN CLOS ED and the CLOSED indication light will be lit.
2009 Fermi 2 NRC RO License Exam QUESTION 4
Following a MANUAL Reactor Scram from 50% power, the following conditions exist:
ALL Turbine Control Valves are SHUT. MRE-R876, Generator Megawatts on H 11-P804 has just reached ZERO. The Main Generator Exciter Field Breaker is CLOSED. BOTH Main Generator output breakers are CLOSED.
Based on these conditions, which one of the following Turbine Generator Trip signals will initiate?
_____ A. Loss of Field
_____ B. Reverse Power
_____ C. Generator Differential
_____ D. Negative Phase Sequence
2009 Fermi 2 NRC RO License Exam QUESTION 5
The Low RPV Water Level Reactor Protection System Trip setpoint causes a reduction in the heat generated from fission, mitigating the effects from which of the following conditions or events?
_____ A. Reaching a Reactor Recirculation Pump trip setpoint.
_____ B. Inducing fuel damage fr om a lowering RPV inventory.
_____ C. Reaching an Emergency Core Cooling System initiation setpoint.
_____ D. Adding positive reactivity which results from Main Steam Isolation Valve Closure.
2009 Fermi 2 NRC RO License Exam QUESTION 6
The Main Control Room has been evacuated.
Which one of the following is the LOWEST RPV Water Level Indication which can be monitored from the Remote Shutdown Panel, H21-P100?
_____ A. +178 inches
_____ B. +160 inches
_____ C. +10 inches
_____ D. -150 (minus 150) inches
2009 Fermi 2 NRC RO License Exam QUESTION 7
The plant is operating at 100% with P 4300-C001 (North) and P4300-C002 (Center) TBCCW Pumps in service, when the following occurs:
5D5, TBCCW PUMPS DIFFERENTIAL PRESSURE HIGH/LOW, alarms TBCCW Headers Pressure Indicator on P43-R805, indicates 19 psig.
With these conditions, which one of the following is the correct diagnosis and required action? _____ A. TBCCW Differential Pressure is too LOW; it is required to REDUCE Main Turbine Generator Load.
_____ B. TBCCW Differential Pressure is too HIGH; it is required to STOP an operating TBCCW Pump.
_____ C. TBCCW Differential Pressure is too LOW; it is required to START P4300-C003 (South) TBCCW Pump.
_____ D. TBCCW Differential Pressure is too HIGH; it is required to OPEN P43-F405, TBCCW DP Control Valve.
2009 Fermi 2 NRC RO License Exam QUESTION 8
Following a transfer of MPU 3, 7D55, INTERRUPTIBLE CONTROL AIR ISOLATION VALVE CLOSED alarmed. The OPEN pushbu tton for P5000-F473, Station Air to IAS Valve has been depressed and the valve REMAINED CLOSED.
Which one of the following is the correct procedurally directed action required to restore the supply to IAS?
_____ A. MANUALLY OPEN P5000-F473, Station Air to IAS Valve.
_____ B. PLACE the IAS ISOLATION SIGNAL keylock switch in OVERRIDE.
_____ C. MANUALLY OPEN the bypass va lve around P5000-F473, Station Air to IAS Valve
_____ D. DEPRESS the OPEN pushbutton fo r P5000-F401, Station Air Header to TB Isolation Valve.
2009 Fermi 2 NRC RO License Exam QUESTION 9
Which one of the following is the LOWEST RPV water level which will maintain natural circulation within the RPV during a loss of shutdown cooling?
_____ A. 173 inches
_____ B. 214 inches
_____ C. 220 inches
_____ D. 255 inches
2009 Fermi 2 NRC RO License Exam QUESTION 10
An irradiated Fuel Assembly has been dropped in the Reactor Cavity, gas bubbles are rising to the surface of the pool.
Which one of the following alarms is associated with actuation of automatic protective functions related to this event?
_____ A. 16D1, RB REFUELING AREA FIFTH FLOOR HIGH RADN
_____ B. 3D32, DIV I/II RB VENT EXH RADN MONI TOR UPSCALE
_____ C. 3D35, DIV I/II FP VENT E XH RADN MONITOR UPSCALE TRIP
_____ D. 3D41, CONT CENTER MAKE UP AIR RADN MONITOR UPSCALE
2009 Fermi 2 NRC RO License Exam QUESTION 11
Following a reactor scram, plant conditions are as follows: Drywell Pressure is 12 psig. Torus Pressure is 10 psig. Drywell Temperature is 225 ºF. Torus Water Level is 0 inches.
With these conditions, why do Emergency Opera ting Procedures require the initiation of Drywell Spray?
_____ A. To reclaim Nitrogen into the Drywell from the Torus.
_____ B. To ensure NPSH limits for ECCS pumps are not violated.
_____ C. To maintain pressure within Primary Containment design limits.
_____ D. To maintain temperature below the Drywell Temperature LCO limits.
2009 Fermi 2 NRC RO License Exam QUESTION 12
Following a Main Steam Isolation Valve closure, conditions are as follows: All control rods are inserted. LLS DIV I SRV OPEN SEALED IN light is OFF LLS DIV I SCRAM PRESS SEALED IN light is OFF LLS DIV II SRV OPEN SEALED IN light is ON LLS DIV II SCRAM PRESS SEALED IN light is ON Reactor Pressure LOWERED to 935 psig and then INCREASED to 1050 psig.
What is the status of Low-Low Set Safety Relief Valves?
_____ A. SRV A is SHUT; SRV G is OPEN.
_____ B. SRV A is OPEN; SRV G is SHUT.
_____ C. BOTH SRV A and SRV G are OPEN.
_____ D. BOTH SRV A and SRV G are SHUT.
2009 Fermi 2 NRC RO License Exam QUESTION 13
With Torus Water Level at 0 inches, which combination of Reactor Pressure and Torus Water Temperature violates the Heat Capacity Limit?
Reactor Torus Water Pressure Temperature
_____ A. 250 psig 195ºF
_____ B. 700 psig 178ºF
_____ C. 900 psig 175ºF
_____ D. 1000 psig 170ºF
2009 Fermi 2 NRC RO License Exam QUESTION 14
When it is determined that Drywell Temperature cannot be restored and maintained below 340ºF, the requirement to scram the reactor is based on which one of the following?
_____ A. RPV Level instrument inaccuracies.
_____ B. To allow Drywell Sprays to be initiated.
_____ C. To reduce the rate of energy input to the Drywell prior to Emergency Depressurization
_____ D. To allow the inboard MSIVs to be closed prior to exceeding their qualification temperature.
2009 Fermi 2 NRC RO License Exam QUESTION 15
Following a LOCA, the following conditions exist:
Torus Level is -30 (minus 30) inches. Torus Pressure is 3.0 psig steady. Torus Temperature is 205ºF steady. 'A' RHR Loop flow is 27,000 gpm. 'B' Core Spray Loop flow is 4,000 gpm. No other ECCS pumps are running.
Based on these conditions, which ECCS Pump s, if any, have sufficient NPSH for continued pump operation?
_____ A. ONLY 'A' Loop RHR Pumps.
_____ B. ONLY 'B' Loop Core Spray Pumps.
_____ C. BOTH 'A' Loop RHR Pumps and 'B' Loop Core Spray Pumps.
_____ D. NEITHER 'A' Loop RHR Pumps NOR 'B' Loop Core Spray Pumps.
2009 Fermi 2 NRC RO License Exam QUESTION 16
Following a transient, plant conditions are as follows: Drywell Temperature is 135ºF. RPV Water Level is +15 inches Wide Range. Reactor Pressure is 1000 psig.
Which one of the following describes the accuracy of Wide Range RPV Water Level Instrumentation and the affect of plant cooldown?
_____ A. Wide Range RPV Water Level is INACCURATE and will read HIGHER than actual during plant cooldown.
_____ B. Wide Range RPV Water Level is ACCURATE and will read LOWER than actual during plant cooldown.
_____ C. Wide Range RPV Water Level is ACCURATE and will read HIGHER than actual during plant cooldown.
_____ D. Wide Range RPV Water Level is INACCURATE and will read LOWER than actual during plant cooldown.
2009 Fermi 2 NRC RO License Exam QUESTION 17
Which one of the following is assured by th e Boron Injection Initiation Temperature (BIIT)?
_____ A. Power oscillations will not exceed a fuel cladding limit.
_____ B. Cold Shutdown Boron Weight will be injected prior to exceeding a primary containment limit.
_____ C. Hot Shutdown Boron Weight will be injected prior to exceeding a primary containment limit.
_____ D. Power transients following Emerge ncy Depressurization will not exceed a fuel cladding limit.
2009 Fermi 2 NRC RO License Exam QUESTION 18
Following a steam leak in the Turbine Bu ilding, 29.100.01 Sheet 5, Radioactivity Release has been entered. Turbine Building Ventilation has TRIPPED and ISOLATED.
Which one of the following actions are required, and why?
_____ A. Maintain Turbine Building Ventilation ISOLATED to lower the radioactivity released.
_____ B. Maintain Turbine Building Ventilation ISOLATED to prevent an unmonitored release.
_____ C. Defeat the isolation and RESTART Turbine Building Ventilation to ensure the release is monitored.
_____ D. Defeat the isolation and RESTART Turbine Building Ventilation to lower the radioactivity release rate.
2009 Fermi 2 NRC RO License Exam QUESTION 19
With a fire in the plant, components in the Relay Room (Fire Zone 8) have been affected.
20.000.18, Control of the Plant from the Dedica ted Shutdown Panel, has been entered.
With these conditions, which one of the following sources will be established for maintaining RPV Water Level at the Dedicated Shutdown Panel?
_____ A. Heater Feed Pump(s)
_____ B. Standby Feedwater Pump(s)
_____ C. Reactor Core Isolation Cooling Pump
_____ D. Control Rod Drive Hydraulic Pump(s)
2009 Fermi 2 NRC RO License Exam QUESTION 20
E1102-C002A Div 1 RHR Pump A is operati ng in Shutdown Cooling Mode. Due to a Grid Disturbance in progress, ONLY the 120 KV power lines voltages are LOWERING at 1 KV per minute. 345 KV lines are NORMAL.
Which one of the following conditions will occur as a result of this trend?
_____ A. RHR Pump A will continue to operate in Shutdown Cooling Mode.
_____ B. Degraded Voltage relays will initiate a Division 1 Load Shed. RHR Pump A will TRIP and automatically RESTART on the EDGs.
_____ C. Bus Undervoltage relays will initiate a Division 1 Load Shed. RHR Pump A will TRIP requiring entry into 20.205.01, Loss of Shutdown Cooling.
_____ D. Degraded Voltage relays will initiate a Division 1 Load Shed. RHR Pump A will TRIP requiring entry into 20.205.01, Loss of Shutdown Cooling.
2009 Fermi 2 NRC RO License Exam QUESTION 21
The plant is shutdown with RHR Division 1 operating in the Shutdown Cooling Mode.
Annunciator 1D33 RHR SYSTEM OVERPRESSURE alarms.
What was the RPV pressure that caused th is alarm and how does the plant respond to protect the RHR system piping?
_____ A. 95 psig, the E1150-F008 and F 009, Shutdown Cooling Inboard and Outboard Isolation Valves will close.
_____ B. 140 psig, the E1150-F008 and F009, Shutdown Cooling Inboard and Outboard Isolation Valves will close.
_____ C. 95 psig, The E1150-F015A/B Division 1/2 LPCI Inboard Isolation Valves will close.
_____ D. 140 psig, The E1150-F015A/B Division 1/2 LPCI Inboard Isolation Valves will close
2009 Fermi 2 NRC RO License Exam QUESTION 22
With the plant operating at 100% power, one Turbine Driven Reactor Feedwater Pump TRIPS.
Which one of the following describes the response of the Reactor Recirculation System and the reason for that response?
_____ A. The 1 Limiter is enforced to protect operating Reactor Recirculation Pumps from cavitation.
_____ B. The 2/3 Limiter is enforced to protect operating Reactor Recirculation Pumps from cavitation.
_____ C. The 1 Limiter is enforced to reduce reactor power within the capacity of the remaining Feedwater Pump.
_____ D. The 2/3 Limiter is enforced to reduce reactor power within the capacity of the remaining Feedwater Pump.
2009 Fermi 2 NRC RO License Exam QUESTION 23
With the plant operating at 100%
power, the following occurs: 3D80, CONTROL ROD DRIFT alarms. The operator selects control rod 14-31. Control rod 14-31 is moving from position 36 to 38. Timer Malfunction red SEL BLOCK light is OFF.
Which one of the following actions will be required?
_____ A. Place the Reactor Mode Switch in SHUTDOWN.
_____ B. Insert Rod 14-31 ONE NOTCH using the Rod Movement Control Switch.
_____ C. Insert Rod 14-31 to FULL IN using the Rod Movement Control Switch.
_____ D. Insert Rod 14-31 to FULL IN using the RONOR EMER IN Switch
2009 Fermi 2 NRC RO License Exam QUESTION 24
The Radioactivity Release Leg of 29.100.01, Sheet 5, requires Emergency Depressurization if a primary system is discharging outside of primary and secondary containment, and radiation levels at the Site Boundary are ap proaching the General Emergency (GE) release rate.
Assuming a single , unisolable leak has occurred, and Site B oundary radiation levels are near the GE level, which one of the followi ng sources of a radioactive leak would meet the requirements for Emergency Depressurization?
_____ A. A leak in the Reactor Water Cleanup Pump discharge piping.
_____ B. A leak in the Fuel Pool C ooling and Cleanup Pump discharge piping.
_____ C. A leak in the Main Steam piping at the High Pressure Coolant Injection Pump inlet.
_____ D. A leak in the Main Steam piping at the Reactor Feedwater Pump inlet.
2009 Fermi 2 NRC RO License Exam QUESTION 25
Due to a steam leak in the Reactor Building, the NE Corner Room indicates above the MAX NORMAL Radiation Level.
Which one of the following actions is required?
_____ A. ISOLATE the RCIC System.
_____ B. ISOLATE the HPCI System.
_____ C. SCRAM the reactor and OPEN Safety Relief Valves.
_____ D. SCRAM the reactor and OPEN Main Turbine Bypass Valves.
2009 Fermi 2 NRC RO License Exam QUESTION 26
Why is it required to enter the Secondary Containment Control Leg of 29.100.01 Sheet 5, when Reactor Building Differential Pressure cannot be maintained negative?
_____ A. An indication that radioactivity will not be treated or monitored prior to release exists.
_____ B. The continued operability of equi pment needed to stabilize the plant may be compromised.
_____ C. The structural integrity of the Secondary Containment may fail under accident conditions.
_____ D. An indication of a primary system discharging into the Secondary Containment exists.
2009 Fermi 2 NRC RO License Exam QUESTION 27
While executing 29.100.01 Sheet 4, Primary Containment Hydrogen / Oxygen Control, why are Torus Sprays operated when procedurally directed?
_____ A. To prevent chugging during the operation of Drywell Sprays.
_____ B. To mix the containment atmosphe re to reduce the localized buildup of combustible gases.
_____ C. To scrub Hydrogen out of the Torus atmosphere prior to the initiation of venting operations.
_____ D. To allow the Reactor Building to Torus Vacuum breakers to OPEN to dilute the concentration of combustible gases in the Torus.
2009 Fermi 2 NRC RO License Exam QUESTION 28
How is the effectiveness of Low Pressure Coolant Injection (LPCI) Mode of RHR affected by loss of Automatic Depressurization System initiation logic?
_____ A. LPCI WILL NOT automatically start following a loss of ADS initiation logic.
_____ B. LPCI is NOT AFFECTED, the system provides protection for ALL Loss of Coolant Accidents (LOCAs) without ADS.
_____ C. LPCI WILL automatically start, but will no longer automatically provide protection for SMALL Break Loss of Coolant Accidents (LOCAs).
_____ D. LPCI WILL automatically start, but will no longer automatically provide protection for LARGE Break Loss of Coolant Accidents (LOCAs).
2009 Fermi 2 NRC RO License Exam QUESTION 29
RHR A Loop is operating in Shutdown C ooling Mode, with conditions as follows:
The plant is in MODE 4, Cold Shutdown. RPV Water Level is 225 inches. NO Reactor Recirculation Pumps are in operation. Cooldown Rate is 100ºF per hour. RHR A Loop Flow is 9,000 gpm. E1150-F048A, Div 1 RHR Hx Bypass Valve is THROTTLED 10% OPEN E1150-F003A, Div 1 RHR Hx Outlet Valve is OPEN. E1150-F068A, Div 1 RHR Hx Service Water Outlet FCV is OPEN.
Which valve must be repositioned per the applicable procedure, and how will RHR Pump Discharge Pressure be affected?
_____ A. E1150-F048A, Div 1 RHR Hx Bypass Valve will be repositioned; RHR Pump Discharge Pressure will INCREASE.
_____ B. E1150-F003A, Div 1 RHR Hx Outlet Valve will be repositioned; RHR Pump Discharge Pressure will INCREASE.
_____ C. E1150-F048A, Div 1 RHR Hx Bypass Valve will be repositioned; RHR Pump Discharge Pressure will DECREASE.
_____ D. E1150-F068A, Div 1 RHR Hx Service Water Outlet FCV will be repositioned; RHR Pump Discharge Pressure will be UNAFFECTED.
2009 Fermi 2 NRC RO License Exam QUESTION 30
Following a transient, High Pressure Coolant Injection is being used to maintain RPV Water Level with the following conditions:
RPV Water Level is 200 inches, stable. HPCI Pump Flow is 5200 gpm. HPCI Turbine Speed is 4800 rpm. Suction is from the Condensate Storage Tank. Torus Water Level is stable at 0 inches Condensate Storage Tank Level 24 inches and lowering.
Which one of the following will occur and what action is required to mitigate the condition?
_____ A. The HPCI Pump will cavitate. TRIP the HPCI Turbine.
_____ B. The HPCI Turbine will TRIP. OP EN the HPCI Torus Suction Valves
_____ C. The HPCI Turbine will be damaged by water impingement. TRIP the HPCI Turbine.
_____ D. The HPCI Turbine will be damaged by excessive speed. LOWER the HPCI Flow controller automatic setpoint
2009 Fermi 2 NRC RO License Exam QUESTION 31
During Manual Initiation of Core Sp ray, the following conditions exist:
Drywell Pressure is 1.75 psig. Reactor Pressure is 250 psig, lowering. E21-R601A, Div 1 Core Spray Flow Indication is 0 gpm. E2150-F031A Div 1 Core Spray Min Flow Valve is OPEN. E2150-F005A, Div 1 Core Spray Inboard Isolation Valve is SHUT.
With these indications, which one of the following actions is required?
_____ A. SECURE Core Spray Pumps A and C to prevent overheating.
_____ B. OPEN E2150-F005A, Div 1 CS I nboard Isolation Valve to provide a flowpath.
_____ C. OPEN E2150-F015A, Div 1 CS Te st Line Isolation Valve to prevent overheating.
_____ D. SHUT E2150-F031A Div 1 Core Spray Min Flow Valve to raise pump discharge pressure.
2009 Fermi 2 NRC RO License Exam QUESTION 32
While operating in the EOPs, SLC was injected, and the system is now shut down. Reactor Water Cleanup is currently being used as an Alternate Pressure Control System.
With a plant cooldown in progress, it becomes necessary to perform 29.ESP.05, RPV INJECTION USING THE SLC TEST TANK, to obt ain a High Pressure injection source.
Which ONE of the following describes expected operator actions and system response after the SLC Test Tank is lined up and filled?
_____ A. One SLC Pump is started locally, and RWCU System automatically isolates.
_____ B. One SLC Pump is started locally, and RWCU remains in service.
_____ C. One SLC Pump is started from the Control Room, and RWCU System automatically isolates.
_____ D. One SLC Pump is started from the Control Room, and RWCU remains in service.
2009 Fermi 2 NRC RO License Exam QUESTION 33
The plant is operating at 100% power.
Condenser Vacuum begins degrading.
What is the lowest pressure that Condenser Vacuum will indicate when an automatic reactor scram occurs?
_____ A. 2.2 psia
_____ B. 2.7 psia
_____ C. 6.9 psia
_____ D. 12.2 psia
2009 Fermi 2 NRC RO License Exam QUESTION 34
Intermediate Range Monitors A, C, E and G are de-energized.
Which one of the following electrical power sources has been lost?
_____ A. 24 / 48 VDC Battery 2IA
_____ B. ESS 130 / 260 VDC Battery 2PA
_____ C. 120 VAC Reactor Protection System Bus A
_____ D. 120 VAC Uninterruptible Power Supply Bus A
2009 Fermi 2 NRC RO License Exam QUESTION 35
The reactor operator is withdrawing a rod to shorten the reactor period during a reactor startup. All IRM channels are on range 4. The reactor mode switch is in STARTUP and no SRM channels are bypassed.
What is the effect if SRM A fails downscale?
_____ A. RMCS permits rod withdrawal to continue.
_____ B. RMCS causes a control rod block.
_____ C. RPS generates a full reactor scram.
_____ D. RPS generates a half scram on RPS A.
2009 Fermi 2 NRC RO License Exam QUESTION 36
The reactor is operating with both recirculation loops in operation, conditions are as follows: APRM Flux is 40%. APRM Recirc Flow is 45% Total Core Flow is 50 Mlbm/hr, equally divided between both loops.
Which one of the following is the LOWEST APRM power which will produce a Simulated Thermal Power Trip?
_____ A. 85%
_____ B. 90%
_____ C. 95%
_____ D. 114%
2009 Fermi 2 NRC RO License Exam QUESTION 37
While manually operating the Reactor Core Isolation Cooling (RCIC)
Pump for injection, the following conditions exist:
RCIC Suction is aligned to the Condensate Storage Tank (CST). RCIC Pump Flow is 120 gpm. RCIC Pump Discharge Pr essure is 600 psig. RCIC Pump Speed is 1900 rpm.
Which one of the following may result from sustained operation with these conditions?
_____ A. The RCIC Turbine may be damaged by excessive speed.
_____ B. The RCIC Lube Oil Cooler will receive inadequate cooling flow.
_____ C. The RCIC Turbine Exhaust Line may be damaged by water hammer.
_____ D. The Condensate Storage Tank inventory will be pumped into the Torus.
2009 Fermi 2 NRC RO License Exam QUESTION 38
Following a transient, plant conditions are: RPV Water Level is 36 inches, lowering 2 inches per minute. Drywell Pressure is 1.50 psig, stable. Power from Division 1 Batteries 2A-1 and 2A-2 has been lost.
Which one of the following describes the affect of these conditions on Automatic Depressurization Valves?
_____ A. ADS will NOT initiate, due to a loss of logic power.
_____ B. ADS will initiate in 3 minutes 45 seconds (225 seconds).
_____ C. ADS will initiate in 9 minutes (540 seconds).
_____ D. ADS will initiate 10 minutes 45 seconds (645 seconds).
2009 Fermi 2 NRC RO License Exam QUESTION 39
The plant is operating at 100% power, when the following indications occur on the IPCS MAIN STEAM display:
STEAM TNL HI TEMP CHA NNEL C light is RED. NSSSS ISOL LOGIC CHANNEL A TRIP light is GREEN. NSSSS ISOL LOGIC CHANNEL B TRIP light is GREEN. NSSSS ISOL LOGIC CHANNEL C TRIP light is RED. NSSSS ISOL LOGIC CHANNEL D TRIP light is RED.
Which one of the following results from these indications?
_____ A. ALL Main Steam Line Drai n Valves receive CLOSE signal.
_____ B. ALL Main Steam Isolation Valves receive CLOSE signal.
_____ C. ONLY INBOARD Main Steam Line Drain Valves receive CLOSE signal.
_____ D. ONLY OUTBOARD Main Steam Li ne Drain Valves receive CLOSE signal.
2009 Fermi 2 NRC RO License Exam QUESTION 40
With the plant at 100% power, the following indications are observed: 1D61 SRV OPEN alarms SRV G OPEN and CLOSE pushbuttons have been depressed. Generator load stabilized about 50 MWe below the initial conditions.
Which one of the following describes present indications and the procedurally required action?
_____ A. SRV G is CLOSED; start all available Torus Cooling.
_____ B. SRV G is OPEN; pull the fuses supplying power to SRV G.
_____ C. SRV G is OPEN; reduce the Pressure Regulator Setpoint to 900 psig.
_____ D. SRV G is CLOSED; verify that the minimum required number of SRVs are operable.
2009 Fermi 2 NRC RO License Exam QUESTION 41
A reactor scram occurred at 100% power.
Which one of the following Post Scram Feed water Logic actuations occurs 6 seconds after a reactor scram?
_____ A. Level Setpoint is lowered to 150 inches.
_____ B. RFPT speed is limited to 2600 to 2700 rpm.
_____ C. N21-F403, RPV Startup LCV, transfers to AUTO.
_____ D. N2100-F607, N RFP Discharge Line Isolation Valve CLOSES.
2009 Fermi 2 NRC RO License Exam QUESTION 42
Following a transient, plant conditions are as follows:
Drywell Pressure is 2.25 psig. 8D46 DIV I REACTOR BLDG PRESSURE HIGH / LOW is alarming. 17D46 DIV II REACTOR BLDG PRESSURE HIGH / LOW is alarming. Reactor Building Pressure is -0.52 (minus 0.52) inches water column.
Which one of the following has occurred?
_____ A. Reactor Building HVAC Exhaust Fans are running.
_____ B. BOTH Trains of Standby Gas Treatment are running.
_____ C. BOTH Trains of Standby Gas Treatment have failed to start.
_____ D. ALL Reactor Building HVAC Isolation Dampers have failed to isolate.
2009 Fermi 2 NRC RO License Exam QUESTION 43
What is the affect on an Emergency Diesel Generator when the associated Emergency Signal Bypass Keylock Selector Switch is placed in the BYPASS position?
_____ A. ALL Emergency Diesel Gene rator NON ESSENTIAL TRIP signals are DEFEATED.
_____ B. ALL Emergency Diesel Generator auto start functions are FUNCTIONAL, but the Emergency Diesel Generator will NOT excite after starting.
_____ C. The Emergency Diesel Generator auto start function due to a Loss of Coolant Accident is DEFEATED, but the Emergency Diesel Generator will auto start due to an Undervoltage condition.
_____ D. The Emergency Diesel Generato r auto start function due to an Undervoltage condition is DEFEATED, but the Emergency Diesel Generator will auto start due to a Loss of Coolant Accident.
2009 Fermi 2 NRC RO License Exam QUESTION 44
With the plant operating at full power, a total loss of Control Rod position indication has occurred.
Which one of the following power sources has been lost?
_____ A. 260/130 VDC Battery Power
_____ B. 120 VAC Modular Power Unit (MPU) 3
_____ C. 120 VAC Reactor Prot ection System (RPS) Bus A
_____ D. 120VAC Uninterruptible Power Supply (UPS) Bus A
2009 Fermi 2 NRC RO License Exam QUESTION 45
With a loss of Division I ESF DC Power, which one of the following will result?
_____ A. The Reactor Core Isolation Cooling (RCIC) automatic start function is DISABLED.
_____ B. The High Pressure Coolant Injection (HPCI) automatic start function is DISABLED.
_____ C. The Reactor Water Cleanup (RWCU)
Outboard Isolation Valve G33-F004 will CLOSE.
_____ D. The Inboard Main Steam Isolation Valves (MSIVs) B2103-F022A through D will CLOSE.
2009 Fermi 2 NRC RO License Exam QUESTION 46
Following a transient initiated by a loss of the 345 kV and 120kV switchyards, the following Emergency Diesel Generator conditions exist:
EDG 11 Jacket Coolant Temperature High is alarming. EDG 12 Crankcase Pressure High is alarming. EDG 13 Oil Temperature High is alarming. EDG 14 Fuel Oil Pressure Low is alarming.
Which one of the Core Spray Pumps is affected?
_____ A. Core Spray Pump A
_____ B. Core Spray Pump B
_____ C. Core Spray Pump C
_____ D. Core Spray Pump D
2009 Fermi 2 NRC RO License Exam QUESTION 47
Which one of the following components can be directly supplied from Division 1 Non Interruptible Air System (NIAS)?
_____ A. Safety Relief Valves B2104- F013 H, E, R, P, and J
_____ B. Outboard Main Steam Isolat ion Valves B2103-F028A, B, C, and D
_____ C. Reactor Recirculation Sample Line Outboard Isolation Valve B3100-F020
_____ D. RCIC Barometric Conde nser Drain to Radwaste Outboard Isolation Valve E5150-F005
2009 Fermi 2 NRC RO License Exam QUESTION 48
Following a transient at full power, plant conditions are:
1D95, DIV I/II RBCCW DIFF PRESS LOW alarms. 2D104, RBCCW PUMPS RECIRC VLV CLOSED alarms. 2D119, RBCCW PUMPS DIFF PRESS HIGH/LOW alarms. NO RBCCW Pumps are operating.
Assuming no operator action, which one of the following components is still supplied with cooling water?
_____ A. Reactor Water Cleanup Pump Seals
_____ B. Control Rod Drive Hydraulic Pumps
_____ C. Division 2 Residual Heat Removal Room Cooler
_____ D. Fuel Pool Cooling and Cleanup Heat Exchangers
2009 Fermi 2 NRC RO License Exam QUESTION 49
Two minutes after a STEAM leak develops inside the drywell the following conditions exist:
Drywell Pressure is 13 psig (rising). Reactor pressure is 400 psig (lowering at 10 psig per minute). RPV level is 170 inches (rising). A RRMG set is running at a speed of 30%. B RRMG set is tripped.
Recirculation Loop (1) has been selected for injection AND on the selected loop (2) .
_____ A. (1) A
(2) BOTH LPCI injection valves are open
_____ B. (1) B
(2) BOTH LPCI injection valves are open
_____ C. (1) A
(2) ONE LPCI injection valves is CLOSED
_____ D. (1) B
(2) ONE LPCI injection valve is CLOSED 2009 Fermi 2 NRC RO License Exam QUESTION 50 The plant is in MODE 3, Hot Shutdown.
Core Spray Loop A is operating in the Full Flow Test Mode. At the end of the Full Flow Test, system fl ow is being reduced, th e following indications occur:
Div 1 Core Spray Test Line Isolatio n Valve, E2150-F015A OPEN and CLOSE lights extinguish. DIV I CSS VALVES THERMAL OVERLOAD alarms.
Which one of the following describes the imp act of this indication on the Core Spray System and what action is required?
_____ A. Core Spray Loop A is NOT assure d to produce the required flow. It is required to enter a Technical Specification LCO.
_____ B. Core Spray Loop A is NOT assured to produce the required flow. Core Spray is NOT required OPERABLE due to present MODE.
_____ C. Core Spray Loop A is assured to produce the required flow by a redundant valve closure. It is required to manually close E 2150-F015A.
_____ D. Core Spray Loop A is NOT assured to produce the required flow. Core Spray Loop A is NOT required because Core Spray Loop B satisfies the
Technical Specification LCO indefinitely in the present mode.
2009 Fermi 2 NRC RO License Exam QUESTION 51
The plant is operating at 40% power, when Turbine Stop Valve 1 and 2 closed.
Which one of the following describes the affect, if any, of this malfunction on the Reactor Protection System?
_____ A. This malfunction re sults in NO actuation of RPS.
_____ B. This malfunction results in a HALF Scram due to Turbine Stop Valve position.
_____ C. This malfunction results in a FULL Scram due to Turbine Stop Valve position.
_____ D. This malfunction results in a FULL Scram due to increasing Reactor Pressure.
2009 Fermi 2 NRC RO License Exam QUESTION 52
With the Reactor Mode Switch in STARTUP HOT STANDBY, the Intermediate Range Monitors are on RANGE 6 with the following readings:
IRM CHANNEL A B C D E F G H READING 122 101 102 102 95 108 103 98 Which one of the following describes the eff ect, if any, of placing the Range Selector Switch for IRM Channel F to RANGE 5?
_____ A. A full reactor scram occurs.
_____ B. A half scram condition occurs.
_____ C. A rod block condition occurs.
_____ D. There is no effect.
2009 Fermi 2 NRC RO License Exam QUESTION 53
The plant is operating at 100% power, when a gradual loss of Interruptible Air System pressure occurs due to a break.
Which one of the following conditions will cause entry into Emergency Operating Procedures?
_____ A. Outboard Main Steam Isolation Valves will fail closed, restricting steam flow, which will result in EOP entry due to High Reactor Pressure
_____ B. Inboard Main Steam Isolation Valves will fail closed, causing void collapse, which will result in EOP entry due to Low RPV Water Level.
_____ C. The ARI Valves will fail open, producing a High Scram Discharge Volume Water Level, which will result in EOP entry due to Low RPV Water Level.
_____ D. The Control Rod Drive Flow contro l valve will fail open, producing a High Scram Discharge Volume Water Level, which will result in EOP entry due to Low RPV Water Level.
2009 Fermi 2 NRC RO License Exam QUESTION 54
When WITHDRAWING a selected control rod, which one of the following describes the INITIAL affect Reactor Manual Control System has on the Control Rod Drive Directional Control Valves?
_____ A. C11F120 and F122 are ENERGIZE D to pressurize the TOP of the rod drive piston.
_____ B. C11F121 and F123 are ENERGIZE D to pressurize the BOTTOM of the rod drive piston.
_____ C. C11F120 and F122 are DEENERGIZED to pressurize the TOP of the rod drive piston.
_____ D. C11F121 and F123 are DEENERGIZED to pressurize the BOTTOM of the rod drive piston.
2009 Fermi 2 NRC RO License Exam QUESTION 55
The plant is opera ting at 40% power.
A control rod is selected a nd is intended to be withdrawn from position 00 to 36. After moving one notch, the control rod becomes uncoupled and sticks.
Which one of the following would result from this condition as the mechanism is moved to position 36?
_____ A. 3D80, CONTROL ROD DRIFT alarms.
_____ B. 3D76, CONTROL ROD OVERTRAVEL alarms.
_____ C. Rod Position Indicati on STOPS CHANGING at Notch 02.
_____ D. Local Power Range Monitor Indi cation STOPS CHANGING at Notch 02.
2009 Fermi 2 NRC RO License Exam QUESTION 56
With the plant operating at full power, which one of the following results directly from a loss of power to 4160 VAC Bus 65G?
_____ A. ONE Station Air Compressor is deenergized.
_____ B. BOTH Reactor Recirculation Pumps are deenergized.
_____ C. BOTH Reactor Feedwater Pump Turbines are tripped.
_____ D. ONE Emergency Diesel Generator will automatically start.
2009 Fermi 2 NRC RO License Exam QUESTION 57
During a plant shutdown with power currently at 65%, which one of the following would result when a Feedwater System transient causes Total Feedwater Flow to drop below 20%? _____ A. BOTH Reactor Recirculation Pumps will TRIP.
_____ B. BOTH Reactor Recirculation MG Set speeds will LOWER to Limiter 1.
_____ C. BOTH Reactor Recirculation MG Set speeds will LOWER to Limiter 2.
_____ D. BOTH Reactor Recirculation Pumps will REMAIN OPERATING at the current speed setting.
2009 Fermi 2 NRC RO License Exam QUESTION 58
With the plant in HOT SHUTDOWN, G 33-R606, RWCU Blowdown Flow Control Valve G3300-F033 Controller Demand is increased from 0% to 100%, resulting in the following:
2D115, RWCU DIFF FLOW HIGH alarms. G33-R800, RWCU System Differential Flow Indication is 80 gpm. All other indications are normal.
Which one of the following will result?
_____ A. G3352-F119, RWCU Supply Isolation Valve CLOSES and the RWCU Pumps TRIP.
_____ B. RWCU Filter Demineralizers will go into HOLD and RWCU Pumps REMAIN OPERATING.
_____ C. G3300-F033, RWCU Blowdown Flow Control Valve CLOSES and RWCU Pumps REMAIN OPERATING.
_____ D. G3352-F001, RWCU Supply Inboa rd Isolation Valve; G3352-F004, RWCU Supply Outboard Isolation Valve; and the G3352-F220, RWCU To FW Outboard Containment Isolation Valve CLOSE and the RWCU Pumps TRIP.
2009 Fermi 2 NRC RO License Exam QUESTION 59
Following a Main Steam Line Isolation, the following conditions exist:
RPV Water Level reached a minimum of 170 inches, and is maintained by Reactor Core Isolation Cooling. Drywell Pressure is 1.8 psig and stable. Safety Relief Valves are being opera ted to control Reactor Pressure. RHR Loop A is operating in the Torus Cooling Mode. BOTH CONTAINMENT SPRAY MODE SELECT switches are in MAN. BOTH CONTAINMENT SPRAY 2/3 CORE HEIGHT OVERRIDE switches are in OFF. RPV Water Level on B21-R610, Division 1 RPV Core Level Recorder suddenly changes to -150 (minus 150) inches, due to a sensing line failure.
Which one of the following will result from these indications?
_____ A. RHR Loop A remains in the Torus Cooling Mode.
_____ B. RHR Loop A is operating on minimum flow and may be returned to Torus Cooling by depressing the OPEN pus hbutton for the affected valves.
_____ C. RHR Loop A is operating on minimum flow and may be returned to Torus Cooling after the associated CONTAINMENT SPRAY 2/3 CORE HEIGHT OVERRIDE switch is placed in MANUAL OVERRIDE.
_____ D. RHR Loop A is operating in the LPCI Mode and may be returned to Torus Cooling after the associated CONTAINMENT SPRAY 2/3 CORE HEIGHT OVERRIDE switch is placed in MANUAL OVERRIDE.
2009 Fermi 2 NRC RO License Exam QUESTION 60 Following a transient, the following conditions exist:
Drywell Pressure is 4.0 psig. Drywell Temperature is 250ºF. Torus Pressure is 3.0 psig. Torus Temperature is 98ºF.
After all required alignments are made for these conditions, which one of the following reflects the expected containment response?
_____ A. Drywell Pressure will lowe r due to Drywell Spray Initiation.
_____ B. Drywell Temperature will lower due to restoring EECW to the Drywell.
_____ C. Drywell Pressure and Torus Pressure will lower due to Drywell Spray and Torus Spray Initiation.
_____ D. Torus Pressure and Torus Temperature will lower due to operation of Torus Spray and Torus Cooling.
2009 Fermi 2 NRC RO License Exam QUESTION 61
The plant is operating at 10% power with the Reactor Mode Switch in STARTUP HOT STBY. A steam leak at the Turbine Inlet has caused Turbine Building Area Temperature to rise to 210ºF.
Which one of the following will result, and what procedure action is required?
_____ A. Main Steam Isolation Valves wi ll CLOSE; it is required to enter 20.000.21, Reactor Scram, and place the Reactor Mode Switch in SHUTDOWN.
_____ B. Main Steam Isolation Valves will CLOSE; it is required to enter 29.100.01, Sheet 5, Secondary Containment Cont rol, and OPERATE available area coolers.
_____ C. Main Steam Isolation Valves will remain OPEN; it is required to enter 20.000.21, Reactor Scram, and place the Reactor Mode Switch in SHUTDOWN.
_____ D. Main Steam Isolation Valves will remain OPEN; it is required to enter 29.100.01, Sheet 5, Secondary Containment Control, and close the Main Steam Isolation Valves.
2009 Fermi 2 NRC RO License Exam QUESTION 62
The plant is operating at full power, when C ondenser Hotwell Level begins to lower. When Condenser Hotwell Level lowers to 15 inches, which one of the following will result? _____ A. Condenser Pump Discharge Pr essure lowers due to cavitation.
_____ B. Condenser Pump Discharge Pressure rises because Reactor Feed Pumps TRIP.
_____ C. Condenser Pump Discharge Pressure lowers because Condenser Pumps TRIP.
_____ D. Condenser Pump Discharge Pressure rises because of Emergency Hotwell Supply Pump START.
2009 Fermi 2 NRC RO License Exam QUESTION 63
With the plant operating at 70% power, the following occurs: 5D44 RFP LOW FLOW / N RFPT TRIPPED alarms. RPV Water Level is 188 inches, lowering. Steam Flow is greater than Feedwater Flow and BOTH are lowering.
Which one of the following actions is procedurally required?
_____ A. INITIATE Reactor Core Isolation Cooling.
_____ B. Inject with BOTH Standby Feedwater Pumps.
_____ C. Manually OPEN the Startup Level Control Valve.
_____ D. Place the South Reactor Feedwater Pump Turbine Controller in EMERGENCY BYPASS.
2009 Fermi 2 NRC RO License Exam QUESTION 64
After the actuation of a wet pipe automatic sprinkler system, the following conditions exist:
Fire Water Header Pressure lowered to 125 psig. General Service Water Header Pressure lowered to 105 psig.
Which one of the following alarms is consistent with this condition?
_____ A. 7D2, DIESEL FIRE PUMP TROUBLE
_____ B. 7D6, DIESEL FIRE PUMP AUTO START
_____ C. 7D10, ELECTRIC FIRE PUMP AUTO START
_____ D. 7D14, GEN SERV H2O HEADER PRESS HIGH/LOW
2009 Fermi 2 NRC RO License Exam QUESTION 65
Which one of the following DIRECTLY results when RBHVAC DIV I MANUAL ISO switch is ARMED and DEPRESSED?
_____ A. T4100-F011, RBHVAC Supply Inboard Isolation Damper, T4100-F009, RBHVAC Exhaust Inboard Isolation Damper will close, and Division 1 SGTS will start.
_____ B. T4100-F010, RBHVAC Supply Outboard Isolation Damper, T4100-F008, RBHVAC Exhaust Outboard Isolation Damper will close, and Division 1 SGTS will start.
_____ C. T4100-F011, RBHVAC Supply Inboard Isolation Damper, T4100-F009, RBHVAC Exhaust Inboard Isolation Damper will close, and Division 1 and 2 SGTS will start.
_____ D. T4100-F010, RBHVAC Supply Outboard Isolation Damper, T4100-F008, RBHVAC Exhaust Outboard Isolation Damper will close, and Division 1 and 2 SGTS will start.
2009 Fermi 2 NRC RO License Exam QUESTION 66
Per 23.138.01, Reactor Recirculation System, which ONE of the following describes the minimum qualification and coordination requirements for local operation of a Recirculation MG Set Scoop Tube?
_____ A. A qualified Nuclear Operator in communication with the Main Control Room can perform scoop tube position adjustment.
_____ B. A licensed Nuclear Supervising Oper ator in communicatio n with the Main Control Room can perform scoop tube position adjustment.
_____ C. A qualified Nuclear Operator can perform scoop tube position adjustment with a licensed Nuclear Supervisi ng Operator supervising at the Recirculation MG Set.
_____ D. A licensed Nuclear Supervising Operator can perform scoop tube position adjustment with a Senior Reactor Operator supervising at the Recirculation MG Set.
2009 Fermi 2 NRC RO License Exam QUESTION 67
What is the reason for limiting Reactor Recirculation MG Set Speed to 75% during Single Loop Operation?
_____ A. To prevent developing oscillations in Reactor Recirculation MG Set speed.
_____ B. To prevent excessive vibration of components inside the Reactor Vessel.
_____ C. To limit the APRM Simulated Therma l Power Trip setpoint values within Single Loop values.
_____ D. To ensure the proper functioning of the LPCI Loop Select Logic in the event of a Loss of Coolant Accident.
2009 Fermi 2 NRC RO License Exam QUESTION 68
The plant is operating at full pow er with the following conditions:
Generator Load is 1120 MWe with power factor at 1.0. Generator Hydrogen Pressure is 60 psig. Due to low grid voltage conditions, it is necessary to raise Generator Voltage.
Which one of the following is the maximum Reactive Power which can be accommodated at the present Generator Load, without exceeding a limit?
_____ A. 125 MVAR (leading)
_____ B. 185 MVAR (leading)
_____ C. 475 MVAR (lagging)
_____ D. 635 MVAR (lagging)
2009 Fermi 2 NRC RO License Exam QUESTION 69
Which one of the following situations is appropriate for the use of Temporary Change Notice per MGA 04?
_____ A. To change the intent of a system operating procedure section.
_____ B. To change the approval requirement for an administrative procedure.
_____ C. To correct a component identification in a system operating procedure.
_____ D. To add a corrective action to preven t recurrence to an existing procedure.
2009 Fermi 2 NRC RO License Exam QUESTION 70
Which one of the following completes the statement which describes the bases of the limiting condition for operation which requires the Main Turbine Bypass valves and the Moisture Separator Reheater to be operable above 25% power?
An operable Main Turbine Bypass system and the Moisture Separator Reheater will ensure ___________________.
_____ A. the MCPR safety limit is not exceeded during rapid over pressurization transients.
_____ B. the APLHGR safety limit is not exceeded during rapid over pressurization transients.
_____ C. RPV pressure scram setpoints are not exceeded during all turbine trip events.
_____ D. the plant cool down limits are not exceeded during all turbine trip events.
2009 Fermi 2 NRC RO License Exam QUESTION 71
During an emergency, authorization to exceed federal occupational dose limits can only be granted by the ___________________.
_____ A. Plant Manager
_____ B. RERP Supervisor
_____ C. Emergency Director
_____ D. Radiation Protection Manager
2009 Fermi 2 NRC RO License Exam QUESTION 72
Following a Main Steam Line Break from full power, 3D45, CONT CENTER MAKEUP AIR RADN MONITOR UPSCALE TRIP alarms.
Div 1 CCHVAC Makeup Air Radiation Monitor, D11-K809 reads 600 cpm. Div 2 CCHVAC Makeup Air Radiation Monitor, D11-K813 reads 700 cpm.
Which one of the following actions is correct?
_____ A. OPERATE CCHVAC in the Purge Mode to maximize dilution.
_____ B. SHUTDOWN BOTH CCHVAC Emer gency Makeup Fans to reduce the main control room pressure.
_____ C. OPERATE CCHVAC in the Recirculation Mode using ONE Emergency Makeup Fan to optimize filtration.
_____ D. OPERATE CCHVAC in the Recirculation Mode using BOTH Emergency Makeup Fans to maximize filtration.
2009 Fermi 2 NRC RO License Exam QUESTION 73
The RECTANGULAR box (shown below) in an Emergency Operating Procedure flowchart indicates which ONE of the following?
_____ A. Decision Step
_____ B. Hold/Wait Point
_____ C. Instructional Step
_____ D. Concurrent Execution 2009 Fermi 2 NRC RO License Exam QUESTION 74
While mitigating an Anticipated Transient Without Scram, the following conditions are noted: RPS A and B are de-energized. ALL HCU blue SCRAM i ndicating lights are ON. 3D2, SCRAM DISCH VOLUME LEVEL HIGH is alarming. C1100-F010, Scram Discharge Volume Vent Valve is CLOSED. C1100-F180, Scram Discharge Volume Vent Valve is CLOSED. C1100-F011, Scram Discharge Volume Drain Valve is CLOSED. C1100-F181, Scram Discharge Volume Drain Valve is CLOSED
Given the above indications, which ONE of the following methods will be most effective to insert Control Rods per 29.ESP.03, Alternate Control Rod Insertion Methods?
_____ A. Vent the Scram Air Header
_____ B. De-energize Scram Solenoids
_____ C. Manual Control Rod Insertion
_____ D. Scram Reset and Manual Scram Re-initiation
2009 Fermi 2 NRC RO License Exam QUESTION 75
Following a LOCA, the following conditions exist:
Drywell pressure.....................................................9 psig and rising Torus pressure.........................................................7 psig and rising Torus Water Temperature......................................130 o F and stable Drywell Temperature.............................................235 o F and rising Torus water level..............................................-14 inches and stable RCIC..............................................injecting to the RPV at 600 gpm RPV water level..............................................120 inches and stable Div. 1 RHR............................................................in Torus Cooling
Which one of the following systems or indications will NOT be available for long term use based on current plant trends.
_____ A. Reactor Core Isolation Cooling System (RCIC)
_____ B. RHR in Torus Cooling Mode.
_____ C. B21-R604A(B), Wide Range RPV level indications
_____ D. T23-R800, Suppression Pool Temperature Recorder.
CURVES CAUTIONS 1 RPV water level indications are affected by instrument run temperatures and RPV pressure:
If the temperature near any instrument run is above the RPV Saturation Temperature, the instrument may be unreliable due to Each instrument in the following table may be used to determine RPV water level only when the instrument reads above the Minimum Indicated Level or the temperatures near all the instrument reference leg vertical runs are below the Maximun Run Temperature Each instrument in the following table may be used to determine RPV water level only when the instrument reads above the minimum indicated reference leg vertical run:
Wide range level detectors (10 to 220 IN.)(B21-N081A,B)(B21-N091A,C)
Core Level Detector (B21-N085A)
Core Level Detector (B21-N085B)
Narrow Range Level Detectors (B21-N080A,B)(B21-N095A,C)(C32-N004A,C)
Narrow Range Level Detectors (B21-N080C,D)(B21-N095B,D)(C32-N004B,D)
-150 to 50 327-142-134 309-150 to 50 169 103 160 to 220 165 273 160 to 220 RANGE(IN.)
MINIMUM INDICATED LEVEL(IN.)
MAXIMUM REACTOR BUILDING RUN INSTRUMENT HIGHEST REACTOR BUILDING RUN TEMPERATURE ( F) BETWEEN MINIMUM INDICATED LEVEL(IN.)
LOW HIGH-80 150 250 250 150 80 350 40 10 15 26 Wide range level detectors (10 to 220 IN.)(B21-N081C,D)(B21-N091B,D) 36 20 10 167 250 350 250 167-HIGH LOW LEVEL(IN.)
INDICATED MINIMUM TEMPERATURE ( F) BETWEEN HIGHEST REACTOR BUILDING RUN Flood up level detector (160 to 560 IN.)(B21-N027) 210 190 175 237 350 150 250 350 250 150-HIGH LOW LEVEL(IN.)
INDICATED MINIMUM TEMPERATURE ( F) BETWEEN HIGHEST DRYWELL RUN 450 450 274 550 C.B.A.3.2.1.2 pressure (50 PSIG).
Elevated torus pressure may trip the RCIC turbine on high exhaust 3 HPCI vortex limit is -94 IN. RCIC vortex limit is -105 IN.
or vortex limit may result in equipment damage.
4 excursion and result in substantial core damage.
A rapid rise in injection into the RPV may induce a large power 5 Temperatures Rec (H11-P601/P602), Points 11 and 12.
must be obtained from T50-R800A/B, Div 1/2 PC Air And Water With torus water level less than -11 IN. torus water temperature 6 water from the RPV.
Executing the following may release pressurized radioactive steam or 7 DETROIT EDISON - FERMI 2 CURVES, CAUTIONS AND TITLE DTC: TPNPP FILE: 1703.02 NUMBER REV 29.100.01 SH 6 11 TABLES-98 4400 0 2000 4000 6000 8000-140-120-100-80-60-40-20 0 CORE SPRAY PUMP FLOW (GPM)
TORUS WATER LEVEL (IN.)
CS VORTEX LIMIT 0 2500 5000 7500 10000 12500 15000 1 PUMP 2 PUMP 0 5000 10000 15000 20000 25000 30000 6800 13600 RHR (LPCI) LOOP FLOW (GPM)
-140-120-100-80-60-40-20 0 DO NOT OPERATE IN THIS AREA TORUS WATER LEVEL (IN.)
-94 RHR (LPCI) VORTEX LIMIT Curves, Cautions & Tables Sheet 6 TEMPERATURE ( F)
IN THIS AREA DO NOT OPERATE RECEIPT: temperature, operation of LPCI, CS, HPCI, or RCIC above the NPSH Below -16 IN. torus water level above 164%%dF torus water For torus water temperatures above 164%%dF, reducing primary containment pressure may exceed NPSH limits for pumps taking suction 8
OR from the torus.
SHALL off as it is completed before proceeding to the next step.
performed in the sequence given;and when required, signed shall be read by the user before performing that step; This procedure be performed as written. Each step Continuous Use Procedure 100 110 120 130 140 150 160 0 2 4 6 8 10 12 REACTOR POWER (%)
TORUS WATER TEMPERATURE (%%dF)
SLC INJECTION AREA BIIT 2.2 157 12.2 100 *TORUS OVERPRESSURE = (Indicated Torus Pressure) + 3.5 PSIG + (INDICATED INCHES OF TORUS WATER LEVEL)
, DO NOT INTERPOLATE BETWEEN NPSH CURVES, USE THE NEXT LOWER CURVE 30-58 7900 14800-16 0 RPV PRESSURE (PSIG)
INSTRUMENT RUN (%%dF)
UNRELIABLE RPV WATER LEVEL RPV SATURATION TEMPERATURE 200 250 300 350 400 450 100 200 300 1200 TEMPERATURE NEAR INDICATION AREA 212 230 29600 25.1 25 30-60-50-30 0 30 TORUS WATER LEVEL (IN.)
TORUS PRESSURE (PSIG)
DO NOT OPERATE IN THIS AREA PSP-40-20-10 10 20 40 50 58 20 15 0 17.1-38 42 545 PRIMARY CONTAINMENT TORUS PRESSURE (PSIG)
DO NOT OPERATE IN THIS AREA 0 PCPL 10 20 30 40 50 60 70 560 580 600 620 640 660-144 0 56 TORUS WATER LEVEL (IN.)
648 39.7 58.8 WATER LEVEL (ELEV - FT) 589.1 0 10 20 30 40 50 58 0 200 400 600 1200 RPV PRESSURE (PSIG)
TORUS WATER LEVEL (IN.)
DO NOT OPERATE IN THIS AREA SRVTPLL 42 246 360 15 140 180 220 260 300 0 500 1500 3000 4500 HPCI PUMP FLOW (GPM)
TORUS WATER TEMPERATURE (%%dF)
DO NOT OPERATE IN THIS AREA HPCI NPSH LIMIT 1000 2000 2500 3500 4000 5000 5 PSIG*0 PSIG*10 PSIG*15 PSIG*164 195 214 229 238 225 209 188 6< -11 IN. 150 0 CORE SPRAY PUMP FLOW (GPM)
TORUS WATER TEMPERATURE (%%dF)
CS NPSH LIMIT 15 PSIG*0 1 PUMP 2 PUMPS 6< -11 IN.160 170 180 190 200 210 220 230 240 250 260 500 1000 2000 1000 3000 1500 4000 2000 5000 2500 6000 3000 7000 3500 8000 4000 DO NOT OPERATE IN THIS AREA 239 212 192 177 220 233 10 PSIG*5 PSIG*0 PSIG*202 227
150 0 2500 5000 10000 15000 RHR (LPCI) LOOP FLOW (GPM)
TORUS WATER TEMPERATURE (%%dF)
DO NOT OPERATE IN THIS AREA RHR (LPCI) NPSH LIMIT 7500 12500 5 PSIG*0 PSIG*10 PSIG*15 PSIG*160 170 180 190 200 210 220 230 240 250 260 0 5000 10000 15000 20000 25000 30000 1 PUMP 2 PUMPS 6< -11 IN.247 236 224 208 230 215 196 167 DO NOT OPERATE IN THIS AREA
140 TORUS LEVEL (IN.)
TORUS WATER TEMPERATURE (%%dF) 6< -11 IN.-30-20-10 0 10 20 30 40 150 160 170 180 190 200 210 220 230 240 250 165-38 149 158 175 187 218 244 153 159 165 173 183 198 42 400 PSIG*200 PSIG*64 PSIG*600 PSIG*800 PSIG** RPV PRESSURE. DO NOT INTERPOLATE BETWEEN HCL CURVES, USE HCL 1000 PSIG*
1135 PSIG*
NEXT HIGHER PRESSURE CURVE.
boiling in the run.
level associated with the highest temperature near an instrument DRYWELL PRESSURE (PSIG) 200 DRYWELL TEMPERATURE (%%dF) 50 0 100 150 2 4 6 8 10 250 300 350 400 500 450 550 600 DO NOT OPERATE DWSIL IN THIS AREA 12 14 16 20 18 2.68 82.9 8.37 DWSIL DWSIL-lim 11.80
140 180 220 260 300 0 100 200 400 600 RCIC PUMP FLOW (GPM)
TORUS WATER TEMPERATURE (%%dF)
DO NOT OPERATE IN THIS AREA RCIC NPSH LIMIT 300 500 231 242 217 198 5 PSIG*0 PSIG*10 PSIG*15 PSIG*230 216 197 168< -11 IN.6 Operation of HPCI or RCIC turbines with suction temperatures above 140%%dF causes increased equipment wear, above 170%%dF may result in equipment damage.
DCR: 08-1260