EOP Flashcards
1
Q
Which one of the following describes the signal that would have been generated when the reactor coolant system pressure lowers to 1800 psia?
A. Safety injection actuation signal
B. Main steam isolation signal
C. Recirculation actuation signal
D. Containment spray actuation signal
A
Answer: A
2
Q
While you are performing Standard Appendix 64, the Control Room tells you that the Spray Pond water temperature is 63F. What additional actions are required, if any?
A. Place the appropriate train chiller in service.
B. No additional actions are required.
C. Place the opposite train chiller in service.
D. Throttle open the SDC HX bypass valve.
A
Answer: B
3
Q
What potential impact could reverse fluid flow from a steam generator tube rupture to the RCS have on the RCS?
A. Potential dilution of the RCS boron concentration.
B. Corrosive damage to the fuel assembly cladding.
C. Taking the RCS solid and lifting the pressurizer safeties.
D. Excessive cooldown of the RCS.
A
Answer: A
4
Q
Which one of the following is the basis for waiting until Hot leg temperature is less than 540°F when isolating a S/G with a SGTR?
A. Affected Steam Generator pressure is low enough to prevent lifting of the Steam Generator safety valves.
B. Differential pressure between the RCS and the affected Steam Generator can be minimized while still maintaining subcooling.
C. Affected Steam Generator pressure is less than the shutoff head of the High Pressure Safety Injection pumps in case the tube leak propagates.
D. Steam Generator pressure is sufficiently high to minimize the possible RCS boron dilution to an acceptable level during the RCS cooldown.
A
Answer: A
5
Q
Given the following conditions: Tcold 210F. Pressurizer pressure 250 psi. Pressurizer level 50%. All rods inserted. No radiation monitors in alarm. Train “A” Shutdown Cooling is in service, “A” LPSI is the running pump. Essential bus PBB S04 is down powered for an electrical outage. Train “A” LTOP relief valve lifts to 100% open and will not reseat. A loss of offsite power occurs, diesel generator “A” trips on differential and is damaged. What safety functions are jeopardized?
A. HR, CI, CTPC.
B. IC, PC, CI.
C. IC, HR, CTPC.
D. MVAC, IC, HR.
A
Answer: D
6
Q
A steam generator should be “bottled up” if it is expected to take longer than _________ minutes to recover feedwater.
A. 30
B. 15
C. 45
D. 60
A
Answer: B
7
Q
During performance of Standard Appendix 64 for alignment of EW “A” to the SFP, the procedure requires throttling EW to obtain a flowrate of 16,600 - 16,800 gpm total flow. How do you know the flowrate while you are adjusting the valve?
A. The local SDC HX A low flow alarm will clear.
B. EWA-HCV-53 has local position indication corresponding to a flowrate of 16,700 gpm.
C. SDC HX A flowrate is provided locally next to EWA-HCV-53.
D. The control room will inform you based upon control room indication.
A
Answer: D
8
Q
Unit 1 has experienced a reactor trip and a failure of NAN-S01 and NAN-S02 to fast bus transfer. The control room staff has implemented Standard Appendix 64, Align EW to SFP, and has directed performance of Attachment 64-B. Prior to adjustment of NCB-HCV-265 to achieve the required flowrate, you must first:
A. Unlock and adjust EWB-V044, “EC CHILLER B DISCHARGE ISOLATION” to obtain 740-780 gpm.
B. Ensure that Spray Pond A temperature is 65° or less.
C. Place NCN-FI-257, “FPHX B Outlet Flowmeter” in service.
D. Ensure that EW pump B is being powered by Diesel Generator B for fault protection.
A
Answer: C
9
Q
What is the purpose of cooling down the RCS to a Thot of less than 540°F prior to isolating the affected SG in the SGTR ORP? This action ensures….
A. that the core heat removal safety function is met.
B. steam generator safety valves do not lift following SG isolation.
C. SBCVs 1007 and 1008 will not open when using the SBCS.
D. pressurizer safety valves do not lift following SG isolation.
A
Answer: B
10
Q
While recovering from a loss of all feed event the following conditions exist: PZR level 71% and trending up. Letdown is isolated due to valve failure. No RCPs are running. NCW is not in service. S/G levels have been restored to 50% NR by manually operating AFA-P01. Choose which one of the following actions is correct for PZR level control in accordance with the EOPs.
A. Maintain Seal Injection and allow PZR to go solid.
B. Secure the charging pumps.
C. Commence a plant cooldown.
D. Isolate RCP seal bleedoff and secure the charging pumps.
A
Answer: C
11
Q
During a Steam Generator Tube Rupture (SGTR) event, an RCS cooldown to Th (RCS hot leg temperature) less than 540°F before isolating the affected steam generator will prevent…
A. lifting the pressurizer safeties.
B. overfilling the affected steam generator.
C. further steam generator tube degradation.
D. lifting the main steam safeties.
A
Answer: D
12
Q
The LOAF procedure can be exited once it has accomplished its purpose by satisfying ALL of the following:
A. All Safety Function Status Check acceptance criteria are being satisfied. An appropriate procedure to implement has been provided and administratively approved. A cooldown is required to meet Shutdown Cooling Entry conditions.
B. Pressurizer Pressure is 150 psia. RCS Temperature is 340 degrees F. All Safety Function Status Check acceptance criteria are being satisfied. An appropriate procedure to implement has been provided, although not administratively approved.
C. All Safety Function Status Check acceptance criteria are being satisfied. A determination has been made that cooldown will not be required and maintaining Mode 3 conditions is desired. An appropriate procedure to implement has been provided and administratively approved.
D. Pressurizer Pressure is 2000 psia. RCS Temperature is 350 degrees F. All Safety Function Status Check acceptance criteria are being satisfied. An appropriate procedure to implement has been provided and administratively approved.
A
Answer: C
13
Q
Following a SGTR 6 hours ago on SG #2, conditions are as follows: RCS Thot is 325 degrees RCS Pressure is 700 psia SG #1 Pressure is 95 psia SG #2 Pressure is 700 psia RCPs 1A and 2A are running What should be performed at this time?
A. Commence a cooldown of SG #2
B. Place SDC into service
C. Secure RCPs 1A and 2A
D. Lower Pressurizer pressure to less than 400 psia
A
Answer: A
14
Q
Given a steam generator tube rupture event, once a steam generator is isolated, what is the preferred method of reducing the RCS to Steam Generator leak rate?
A. Increase Steam Generator pressure by raising the Steam Bypass Control System setpoint.
B. Blowdown the Steam Generator to the main condenser.
C. Raise the Steam Generator level above the top of the tubes.
D. Reduce RCS pressure to within +/-50 psid of the affected Steam Generator.
A
Answer: D
15
Q
Given the following plant conditions: The reactor is tripped following a Steam Generator Tube Rupture. RCS pressure is 895 psia. RCS subcooling is 55°F. Steam Generator #1 pressure is 890 psia. RU-4 in high alarm. Steam generator #1 is isolated. Steam generator #1 level is 78% NR and rising slowly. Steam generator #2 level is 50% NR and steady. WHICH ONE of the following is the preferred method to control level in the isolated steam generator?
A. Line-up high rate blowdown to the condenser from #1 steam generator.
B. Steam the #1 steam generator to atmosphere via the ADVs.
C. Lower RCS pressure below #1 steam generator pressure and allow backflow to the RCS.
D. Bypass the MSIV and steam the #1 steam generator to the condenser.
A
Answer: C
16
Q
Which one of the following components is tripped to minimize heat input into the RCS after a Loss of All Feedwater?
A. Reactor Coolant Pumps.
B. Pressurizer heaters.
C. Charging pumps.
D. Heated junction thermocouples.
A
Answer: A
17
Q
A major grid perturbation has occurred such that the site has experienced a complete de-energization of the switchyard, and subsequent reactor trips and blackout conditions. Standard Appendix 54 has been implemented and you are directed to perform Attachment 54-A, which accomplishes what function?
A. Energizes EF battery charger NKN-H21 from DG-A.
B. Energizes F battery charger NKN-H19 from the GTG.
C. Energizes EF battery charger NKN-H21 from the GTG.
D. Energizes F battery charger NKN-H19 from DG-B.
A
Answer: C
18
Q
Given the following plant conditions: The reactor has been manually tripped. Pressurizer pressure is 1810 psia and slowly lowering. SPTA’s have been completed. All ESFAS systems are performing as designed. RCS subcooling is 20°F and slowly lowering. Containment temperature is 145°F. 4 RCP’s are running. The crew is required to…..
A. trip one RCP in each loop.
B. trip RCP’s 1A and 1B.
C. trip all four RCP’s.
D. trip all four RCP’s when subcooling is less than 0°F
A
Answer: C
19
Q
Given the following conditions: The reactor has been manually tripped A small LOCA has occurred. The LOCA procedure has been implemented. Under what conditions would an operator be required to trip 2 RCP’s and under what conditions would an operator be required to trip all RCP’s?
A. actuation of CSAS and trip all RCPs on subcooled margin of less than 24 degrees.
B. actuation of MSIS and trip all RCPs on a loss of subcooling.
C. pressurizer pressure remaining below 1837 psia and trip all RCPs on subcooled margin of less than 24 degrees.
D. pressurizer pressure remaining below 1837 psia and trip all RCPs on a loss of seal injection flow.
A
Answer: C
20
Q
Given the following plant conditions: The unit is at 100% power. It has been determined that a 150 gpm high pressure seal cooler leak exists. Before the affected HPSC is isolated, which one of the following describes the limitations on plant operation?
A. Nuclear cooling water flow to the affected RCP must be increased.
B. The plant must commence a normal shutdown within 72 hours.
C. The affected RCP must be stopped, resulting in a automatic trip.
D. The plant must be manually tripped and all RCP’s must be stopped.
A
Answer: D
21
Q
Reflux boiling will be enhanced by raising…
A. pressurizer pressure from 750 to 850 psia.
B. RCS T-cold to >550°F.
C. PZR lever from 15 to 55%.
D. SG level from 10% to 50% N/R.
A
Answer: D
22
Q
Given the following conditions: A hot leg break has occurred. All reactor coolant pumps are stopped. Representative core exit thermocouple temperature is 450°F. Maximum quadrant core exit thermocouple is 456°F. T-hot is 483°F and dropping. Pressurizer pressure is 610 psia. Containment temperature and pressure are 125°F and 2.0 psig. WHICH ONE of the following identify the condition of heat transfer in the reactor coolant system?
A. Saturated natural circulation (reflux boiling)
B. Saturated steaming through the break
C. Subcooled natural circulation
D. Subcooled natural circulation with localized flow blockage.
A
Answer: C
23
Q
Given the following plant conditions: A LOCA occurred with the plant at 100% MOC. RCS pressure is currently 1860 psia. PZR level is 30% and stable. The leak rate was 135 gpm into containment when RCS pressure was 2250 psia. Subcooled margin is 48°F and stable. The reactor was manually tripped and SIAS/CIAS were manually initiated. No equipment is out of service Which one of the following describes the primary heat removal method that will be used during the cooldown? (assume the physical size of the RCS breach remains constant and CSAS does not actuate)
A. Reflux boiling
B. Forced circulation
C. HPSI injection
D. Subcooled natural circulation
A
Answer: B
24
Q
Given the following plant conditions: A subcooled natural circulation cooldown is in progress following a small break LOCA in containment. Aux Spray is in use, lowering RCS pressure. Sub-Cooled Margin is 50°F and degrading slowly. Containment temperature is 120°. Pressurizer level is 45% and rising rapidly. HPSI is throttled. Reactor vessel head is reading 41%. The Control Room Staff should immediately…
A. open the reactor vessel head vents.
B. re-initiate full Safety Injection flow.
C. stop depressurizing the RCS.
D. exit LOCA and enter the functional recovery procedure.
A
Answer: C
25
Which one of the following most correctly describes plant conditions if the switchyard grid has de-energized, and remains so, and both diesel generators have started and are running and powering their respective 4.16kV AC class busses?
A. Loss of All Feedwater (LOAF)
B. Blackout (BO)
C. Loss of Power (LOP)
D. Loss of Offsite Power (LOOP)
Answer: D
26
Given the following conditions: The plant is operating at 100% power The normal supply breaker to PBA-S03 trips open. The "A" Emergency Diesel starts but does not supply power to PBA-S03. All other electric plant buses are energized and normal. Which one of the following events has occurred?
A. Loss of Offsite Power (LOOP)
B. Blackout (BO)
C. Loss of Power (LOP)
D. Loss of Forced Circulation (LOFC)
Answer: C
27
Which one of the following conditions currently exists if NAN-S01 and NAN-S02 are deengergized and PBA-S03 and PBB-S04 are energized from their respective Emergency Diesel Generators?
A. Loss of all Feedwater (LOAF)
B. Blackout (BO)
C. Loss of Power (LOP)
D. Loss of Offsite Power (LOOP)
Answer: D
28
Given the following conditions: The Unit 2 power uprate and SG replacement are complete. The plant is at 100% power. A loss of vacuum occurs. The crew enters the 40AO-9ZZ07, Loss of Vacuum AOP. The secondary operator is told to reduce turbine load using the load limit pot. When compared to Unit 1 and 3, what plant response should the secondary operator expect from the load limit potentiometer?
A. More responsive.
B. Less responsive.
C. The same response.
D. Same response in the throttling range but more responsive outside the throttling range.
Answer: A
29
You have been directed to perform Standard Appendix 54, Attachment 54-A. Which one of the following indicates the appendix or action that the control room operator must assure has been completed, prior to assigning you this attachment?
A. Standard Appendix 53.
B. Normal AHU's for the Turbine Building must be stopped.
C. Standard Appendix 52.
D. NKN-D41 must be energized.
Answer: A
30
The number of starts for an electric motor in a given period of time should be limited because...
A. overheating of the windings can occur due to a high starting current.
B. rotor damage can occur due to excessive cyclic stresses on the shaft.
C. overheating of the windings can occur due to shorting within the stator.
D. rotor damage can occur due to excessive axial displacement of the shaft.
Answer: A
31
During performance of Standard Appendix 62, what is the time restriction for depressurizing the main generator of H2 during a loss of offsite power with a battery charger not restored to NKN-M46?
A. Within 7 hours of the loss of offsite power.
B. Prior to the stopping of the Main Turbine shaft rotation.
C. Prior to the stopping of both MFPT's shaft rotation.
D. Within 4 hours of discovery of the power loss.
Answer: A
32
After reduction of H2 pressure in the Main Generator per Standard Appendix 62, when is the generator purged of residual hydrogen?
A. After power is restored to the CO2 vaporizer from NHN-M27.
B. As soon as possible after a 4.16 kV class bus is restored.
C. When the Main Generator hydrogen concentration is less than 50%.
D. Hydrogen purging is not required by this appendix.
Answer: A
33
While performing Standard Appendix 63-A, valve EWA-HCV-53 is required to be throttled to obtain adequate flow through the RCP seal coolers. How do you [as the assigned NLO] accomplish this?
A. The Control Room notifies you of adequate flow through the RCP seal coolers and Normal Chiller WCN-E01A.
B. The Control Room notifies you of the flowrate through the SDC Heat Exchanger.
C. You obtain the information from the flow indicator on the wall next to the valve.
D. The preset throttle value is obtained from SWMS prior to performing the appendix.
Answer: A
34
With the reactor at 100% power, what is the normal condition of the SIT outlet valves and why are they in that condition?
A. The valves are open and downpowered to maintain it as a passive system.
B. The valves are open and powered up to provide for rapid closure after a SIAS.
C. The valves are closed and powered up to allow the SIAS to automatically open the valves.
D. The valves are closed and downpowered to prevent voiding the RCS with nitrogen after a SIAS.
Answer: A
35
```
Given the following plant conditions: The reactor has tripped An ESD has occurred on SG # 2 SG # 2 has reached dryout conditions, The following indications are available:
Loop 1 Tcold - 460°F
Loop 1 Thot - 480°F
Loop 2 Tcold - 448°F
Loop 2 Thot - 476°F
```
Which one of the following pressures indicates the pressure that SG # 1 should be reduced to?
A. 466 psia
B. 414 psia
C. 545 psia
D. 566 psia
Answer: B
36
When cross-connecting Train "B" EW to NC in accordance with Standard Appendix 63, which one of the following valves is operated from the Control Room?
A. EWB-HCV-66, EW CROSS-TIE VLV TO NC
B. EWB-HCV-54, "B" SDCHX OUTLET ISOLATION
C. EWA-HCV-53, "A" SDCHX OUTLET ISOLATION
D. NCN-UV-99, NC CTMT HEADER RETURN
Answer: D
37
Given the following plant conditions: FRP is in progress. Main steam safety valve has failed open on SG #1. Prior to the trip, the following RMS alarms were alarming: RU-142 Channel 1 at 7.6 x 10+5 RU-142 Channel 2 at 8.2 x 10+5 RU-142 Channel 3 at 2.1 x 10+5 RU-142 Channel 4 at 9.1 x 10+4 Loss of the Grid. DG 'A' tripped on low lube oil pressure. PZR level is off scale low. SI flow is adequate. All other ESFAS systems operate as designed. Assuming no other events, which success path should be performed first?
A. HR-2, SG with SI.
B. HR-1, SG with no SI.
C. CI-1, Auto/man CTMT ISOL.
D. IC-2, SI.
Answer: C
38
Given the following conditions: The Unit 2 power uprate and SG replacement are complete. The plant is operating at 100% power Which AOP would be most impacted by operating in full arc admission when compared to the unit(s) operating in partial arc admission?
A. Control Room Fire, 40AO-9ZZ19
B. Loss of Letdown, 40AO-9ZZ05
C. Loss of Vacuum, 40AO-9ZZ07
D. Inadvertent PPS-ESFAS actuations, 40AO-9ZZ17
Answer: C
39
Given the following conditions: The Unit 2 power uprate and SG replacement are complete. The plant is at 100% power. Condenser vacuum begins to degrade The crew enters the Loss of Vacuum, 40AO9ZZ07, AOP. What plant response would be most affected in Unit 2 when compared to the other units?
A. Charging flow would be more responsive to Pressurizer level changes.
B. SBCVs 1007 & 1008 would be more responsive to thumbwheel changes.
C. Letdown would be more responsive to Pressurizer level changes.
D. Turbine power would be more responsive to load limit pot changes.
Answer: D
40
Given the following conditions: Unit 1 is operating in Mode 1. A Pressurizer Safety valve becomes inoperable. All other safety valves are operable. What actions (if any) are required per Technical Specifications?
A. No actions since the LCO is met.
B. Restore the safety valve to OPERABLE status in 15 minutes.
C. Restore the safety valve to OPERABLE status in 30 minutes.
D. Restore the safety valve to OPERABLE status in 1 hour.
Answer: B
41
Which ONE of the following Unit combinations can be simultaneously energized by the GTGs?
A. 1 and 3 only
B. 1 and 2; or 1 and 3
C. 1 and 2; or 2 and 3
D. 1 and 3; or 2 and 3
Answer: B
42
Which of the following actions taken in the Blackout ORP is designed to assist in preventing core uncovery?
A. Start a Gas Turbine Generator and energize PBA-S03 within one hour.
B. Maximize RCS cooldown and depressurization to minimize RCP seal leakage.
C. Commence cooldown and stabilize RCS pressure to maximize subcooling and maintain natural circulation.
D. Ensuring Core and RCS heat removal is maintained by use of AFN and Train "A" ADVs.
Answer: A
43
During an ESD, why should safety injection be throttled as soon as the throttle criteria is met?
A. Minimizes the possibility of pressurized thermal shock.
B. Prevents excessive cooldown.
C. Minimizes erosion damage to the injection valves.
D. Minimizes the time SI pumps are running on mini-flow.
Answer: A
44
Given the following plant conditions: The plant has tripped from 100% due to a large break LOCA in Containment. The crew has entered the LOCA EOP Containment pressure is 15 psig and stable. A LOOP has occurred. PBA-S03 has faulted. While the crew is performing the actions of the EOP, "B" CS pump trips due to a motor fault. Which of the following is true? The crew …
A. must leave the LOCA ORP because Inventory Control is not met.
B. may remain in the LOCA ORP as all SFSCs are still met.
C. must leave the LOCA EOP because CTPC is NOT met.
D. may remain in the LOCA ORP because no other EOP directly addresses this condition.
Answer: C
45
The control room staff is implementing Standard Appendix 42 to align the Aux Feedwater Pumps suction to the Reactor Makeup Water Tank. A potential for contamination of the CST exists due to:
A. the fact that the suction piping is normally vented back to the CST.
B. the Aux Feed Pump(s) recirculation flow remains aligned to the CST.
C. a gravity flow path that would exist between the RMWT and the CST when the RMWT suction valve(s) are opened.
D. failure of the auto-closure interlock of the mini-flow valves when the Aux Feedwater pumps are aligned to both the RMWT and the CST.
Answer: B
46
The Lower Mode Functional Recovery Procedure addresses three specific conditions or "sets" of Success Paths. Which one of the following correctly identifies those three "sets" of Success Paths?
A. LTOPs not in service, LTOPs in service, and Reactor Vessel Head Removed.
B. Pzr Filled, Pzr Drained, and Reactor Vessel Head Removed.
C. Pzr Manway On, Pzr Manway Off, and Reactor Vessel Head Removed.
D. Reactor Vessel Head Tensioned, Reactor Vessel Head Detensioned, and Reactor Vessel Head Removed.
Answer: C
47
Given the following conditions: An overcooling transient occurred which dropped plant temperature uncontrollably to 470°F. RCS temperature and pressure have been stablized on the left side of the 200°F subcooled line of Standard Appendix 2. Which of the following actions is appropriate?
A. Cool down and maintain RCS pressure constant.
B. Heat up and repressurize the RCS.
C. Cool down and repressurize the RCS.
D. Depressurize and maintain RCS temperature constant.
Answer: D
48
Given the following conditions: Rx tripped due to low RCS pressure The CRS has entered the LOCA procedure RCS is 40 degrees subcooled and stable The Emergency Coordinator has identified the following Emergency Action Levels as being exceeded RCS leakrate > 44 gpm (1-6) Rapid unexplained CTMT pressure decrease (1-10) Which one of the following correctly describes the required event classification?
A. General Emergency
B. Unusual Event
C. Alert
D. Site Area Emergency
Answer: D
49
Given the following plant conditions: An ESD has occurred due to a steam line break inside containment. The Operating crew has just entered in the ESD procedure. Containment pressure peaked and is stable at 9 psig Containment temperature is 186°F. PZR level is 12% and rising. RVUH is 100%. RCS subcooling is 112°F SG 1 is at 24% WR (increasing) and being fed from AFW at 505 gpm. SG 2 is below the indicated level. Both HPSI pumps are injecting into the RCS. Based on these conditions, the operator should...
A. throttle HPSI when PZR level reaches 15%.
B. throttle HPSI immediately.
C. maximize feedflow to SG 1.
D. maximize feedflow to SG 1 and throttle HPSI when PZR level reaches 15%.
Answer: A
50
Given the following conditions: A steam leak occurs in the Turbine Building. A manual reactor trip is initiated. The turbine trip isolates the steam leak. T-cold for both loops indicate 555°F. The crew is performing the SPTAs. SBCS is functioning properly. No ESFAS actuations have occured Based on these conditions, the Control Operator should...
A. allow the RCS to heat up to its normal post trip band of 560° to 570°F Tcold.
B. continue the cooldown to a Tcold of 500°F.
C. initiate an MSIS and stabilize temperature using ADVs.
D. stabilize RCS temperature at its present value with SBCS in manual.
Answer: A
51
The following plant conditions exist: Unit 3 tripped from 75% power An ESD has occurred on # 1 SG The CRS has directed stabilizing RCS temperature The following indications are available:
Loop 1 T-cold 401 degrees
Loop 1 T-hot 485 degrees
Loop 2 T-cold 450 degrees
Loop 2 T-hot 490 degrees
```
Which one of the following pressures indicates the value that # 2 SG pressure should be reduced to?
A. 590 psia
B. 620 psia
C. 250 psia
D. 420 psia
```
Answer: C
52
Given the following plant conditions: An ESD has occurred due to a steam line break inside containment. The Operating crew has just entered in the ESD procedure. Containment pressure peaked and is stable at 9 psig. Containment temperature is 160°F and lowering. PZR level is 34% and rising. RVUH is 100%. RCS subcooling is 112°F and increasing. SG 1 is at 24% WR, rising slowly and being fed from AFW at 505 gpm. SG 2 is below the indicated level and not being fed. Both HPSI pumps are injecting into the RCS. SG 1 indicates 300 gpm Steam Flow Which of the following identifies what operator actions are required?
A. Decrease SG 1 FW flow to
Answer: B
53
"Reactive Power" in an AC electrical circuit is that power that:
A. is lost in the circuit due to the resistance of the electrical conductors.
B. never leaves the source.
C. is consumed by the load(s) to produce heat, light or motion.
D. oscillates in the circuit and produces no useful work.
Answer: D
54
A ESD has occurred due to a steam line break on SG 2 inside containment. The operating crew is in the process of performing the SPTAs. Containment pressure is at 10 psig and rising. Containment temperature is in excess of 200°F. PZR level is 12% and rising. RCS temperature is rising. RCS subcooling is 112°F. SG 1 is at 45% WR and being feed from AFW at 300 gpm. HPSI flow to the RCS is acceptible per appendix 2. Based on these conditions, the operator should:
A. throttle HPSI immediately.
B. increase heat removal on SG 1 to stabilize Tc
C. Start all available charging pumps.
D. immediately reduce RCS pressure to lower subcooling to less than 100°F.
Answer: B
55
Given the following conditions: The control room staff is implementing Appendix 41 of the Standard Appendices. The secondary operator has determined that at least one of the breaker status indicating lights for the AFN-P01 is NOT on. The "A" Battery Charger is available. An appropriate course of action would be to:
A. Cycle the 125 Vdc control power breaker for AFN-P01 from open to close.
B. Terminate the implementation of Appendix 41.
C. Place PBA-U01, "Control Power Transfer Switch For AFN-P01" to the "Alternate Feed From PKA-H11" position.
D. Install temporary power cables from Battery Charger A to supply control power to AFN-P01.
Answer: C
56
Given the following conditions: Steam Generator 2 has experienced a steam line break in the containment. You have been directed to stabilize RCS temperature when SG # 2 reaches "dryout" This will be indicated by.....
A. RCS temperatures beginning to increase.
B. SG 2 level goes off scale low.
C. Loop 1 or 2 Thot drops below 540°F.
D. SG 2 pressure drops below 100 psig.
Answer: A
57
Which of the following is the MINIMUM power source necessary to maintain the unit in a safe condition AND energize switchyard loads for up to 16 hours following a Blackout?
A. One Emergency Diesel Generator
B. One Off-Site power source
C. One Station Black Out Gas Turbine Generator
D. Two Station Black Out Gas Turbine Generators
Answer: C
58
When the Blackout ORP is entered, the operating crew is directed to initiate a MSIS to...
A. avoid FW heater tube erosion damage.
B. avoid lifting FW heater reliefs.
C. minimize main condenser damage.
D. ensure the main turbine does not motorize.
Answer: C
59
The Blackout ORP directs the crew to place all charging pumps in PTL to...
A. ensure that pump suction source is aligned prior to restart.
B. prevent inadvertent dilution on restoration of injection flow.
C. provide for controlled restoration of RCP seal injection.
D. ensure pumps are not immediately anti-pumped on restoration of power.
Answer: C
60
Which of the following is true regarding manual ESFAS actuations ? Manual ESFAS actions are allowed:
A. anytime an exceeded setpoint is discovered.
B. only with CRS concurrence.
C. only during the performance of EOPs.
D. without CRS concurrence whenever plant parameters are trending toward exceeding a setpoint or when the setpoints are exceeded.
Answer: A
61
Given the following conditions: The Unit has been in a blackout condition for 2 hours. QSPDS indicates 32 degrees superheat and has been stable for the last 15 minutes. CET temperatures and RCS pressure have also been stable for the last 15 minutes. What is the condition of RCS and core heat removal?
A. Two phase natural circulation is maintaining heat removal.
B. All natural circulation has been lost, core uncovery has occurred.
C. All natural circulation has been lost, but the core still remains covered.
D. Single phase natural circulation is maintaining heat removal.
Answer: A
62
Unit 1 has been in a Blackout condition for 3 hours. The crew is performing action of 40EP-9EO08, Blackout. PBA-S03 has been energized by one Gas Turbine Generator (Standard Appendix 80). Attempts to restore power from other sources have been unsuccessful. The following parameters exist: REP CET indicated 610°F and STABLE RCS pressure indicates 1650 psia and slowly TRENDING DOWN Pressurizer level indicates 23% and TRENDING DOWN SG1 and SG2 levels are 47% WR and TRENDING UP Train "A" ADVs are THROTTLED OPEN approximately 25% SG1 and SG2 pressures indicate 1150 psig and STABLE Which of the following actions should be taken by the crew?
```
A. ENSURE Train "A" ADVs are throttled adequately to maintain RCS subcooling
B. Use Auxiliary Spray to lower RCS pressure.
C. Commence a cooldown to shutdown cooling entry conditions.
D. OVERRIDE and ENERGIZE Train "A" class backup heater to stabilize RCS pressure
```
Answer: A
63
Given the following conditions: Loss of offsite power. Both DGs fail to start. Which of the following describes how the safety analyses assumes the reactivity control safety function is maintained?
A. Plant cooldown is limited to 75 degrees/hour.
B. Maintain the plant in Hot Standby.
C. Within 1 hour, RCS pressure is reduced below SIT pressure.
D. After verification of all CEAs inserted, cooldown to SDC entry conditions.
Answer: B
64
Consider the following plant conditions: A 180 gpm leak outside of containment on letdown line. RCS activity 153 uci/gm dose equivalent I-131. RVLMS 100% in RVUH. Highest CET temperature is 573°F. SIAS/CIAS initiated. CH-UV-515 and CH-UV-516 failed to close. Site boundary dose rate 120 mrem/hr External EDE due to gaseous activity. RU-148 indicates 1.5 x 103 mrem/hr. RU-149 indicates 1.6 x 103 mrem/hr. 1 hour since reactor trip Which one of the following is the minimum emergency classification for this event?
A. Alert.
B. Unusual Event.
C. Site Area Emergency.
D. General Emergency.
Answer: C
65
Which one of the following describes the signal that will be generated when the pressurizer reaches 1837 psia?
A. Main Steam Isolation Signal (MSIS)
B. Safety Injection Actuation Signal (SIAS)
C. Recirculation Actuation Signal (RAS)
D. Containment Spray Actuation Signal (CSAS)
Answer: B
66
The following plant conditions exist: The reactor tripped 1 hour ago. Pressurizer pressure is at 1200 psia, and rising slowly. Pressurizer level is 40% and stable. Both S/G levels are currently at 65% WR and rising slowly. Both S/G pressures are at 1100 psia and rising slowly. Containment pressure is 12.5 psig and stable. Containment spray flow is adequate Reactor power is 1x10-6 and slowly dropping. RU-148 is indicating 1.2 E+7 mrem/HR All three charging pumps are running. HPSI flow is adequate. The RCS subcooling is zero. SIAS, CIAS have actuated. The minimum required event classification is:
A. Alert.
B. Notification of Unusual Event.
C. General Emergency.
D. Site Area Emergency.
Answer: C
67
Given the following plant conditions: An ESD has occurred due to a steam line break on SG 2 inside containment. The Operating Crew is performing SPTAs. Containment pressure peaked and is stable at 4 psig. Containment temperature is 158 degrees. Tcold is 505 degrees and decreasing. PZR level is 20% and rising. RVUH is 100%. RCS subcooling is 112 degrees. SG 1 is at 45% NR and slowly increasing with 150 gpm AF flow. Both HPSI pumps are injecting into the RCS. Based on these conditions, the crew should:
A. increase SG 1 feedflow to 500 gpm.
B. throttle HPSI immediately.
C. increase heat removal on SG 1 to stablize Tc.
D. immediately reduce RCS subcooling to less than 100 degrees.
Answer: B
68
During an ESD event, what is done immediately after isolating the most affected Steam Generator?
A. Trip the reactor and perform the SPTA's.
B. Commence a rapid cooldown to SDC conditions.
C. Check to ensure that the correct Steam Generator was isolated.
D. Reduce pressure in the unaffected Steam Generator.
Answer: C
69
Given the following plant conditions: Unit 1 is operating at rated power. AFN-P01 is out of service. The reactor trips. Loss of Offsite Power. PKA-M41 trips. SPB-P01 (Spray Pond B) trips. All other systems are operating as designed. Which ONE of the following correctly identifies the correct procedure for plant stabilization?
A. 40EP-9EO06, LOAF.
B. 40EP-9EO09, FRP.
C. 40EP-9EO07, LOOP/LOFC.
D. 40EP-9EO08, BO.
Answer: B
70
Given the following plant conditions: The reactor has tripped. An MSSV has stuck open on SG 1. SG 1 is at 32% WR. SG 1 is at 930 psia. SG 2 is at 43% WR. SG 2 is at 1060 psia. LOOP 1 Tc 538°F, Th 559°F. LOOP 2 Tc 556°F, Th 559°F. With no operator action, which of the following describes the status of SG feedwater?
A. AFA and AFB are feeding both SGs.
B. Neither SG is receiving feedwater
C. AFA and AFB are feeding SG 1 only.
D. MFW is feeding both SGs in RTO at greater than 250 gpm.
Answer: B
71
Given the following plant conditions: Unit 1 has experienced a large break LOCA Containment temperature is 220°F and increasing slowly Containment pressure is 9 psig and increasing slowly Containment Spray 'A' flow is 4370 gpm PBB-S04 has an 86 lockout on the normal supply breaker. The Containment Temperature and Pressure Control Safety Function is...
A. met, all criteria satisfied .
B. not met due to containment spray flow.
C. not met due to Containment pressure.
D. not met due to Containment temperature.
Answer: A
72
Given the following plant conditions: Both Steam Generator pressures are 1170 psia Pressurizer level is 30% and stable Pressurizer pressure is 1100 psia Containment temperature is 220°F and increasing slowly Containment pressure is 9 psig and increasing slowly PBB-S04 is locked out and on fire. PKA-M41, PKC-M43, and PNA-D25 are available. HPSI throttle criteria are met and HPSI 'A' flow is throttled to 200 gpm per cold leg. Containment Spray 'A' flow is 4190 gpm Which of the following safety functions are jeopardized?
A. All Safety Functions are met
B. Inventory control
C. Containment temperature and pressure control.
D. Maintenance of Vital Auxiliaries
Answer: C
73
Given the following conditions: Unit 1 has experienced a Blackout. PBA-S03 has been energized from Unit 3 DG B per Standard Appendix 82. Which of the following equipment sequence combinations is correct for starting loads in Unit 1?
A. AFN-P01, PGA-L31, EWA-P01, SIA-P02.
B. PGA-L31, AFN-P01, SIA-P03, SPA-P01.
C. SIA-P02, PGA-L35, AFN-P01, ECA-E01.
D. AFN-P01, PGA-L35, SIA-P02, EWA-P01.
Answer: D
74
Given the following conditions: Pressurizer pressure is 1250 psia. Pressurizer level is 45%. HPSI injection is 330 gpm/cold leg (acceptable flow). Reactor coolant system is 28°F subcooled. Reactor vessel level monitoring system indicates 100% in plenum and upper head. No reactor coolant pumps are running. Containment temperature and pressure are 195°F and 11 psig, respectively. SIAS, CIAS, MSIS, and CSAS have actuated. A cooldown is in progress using steam generators, both WR levels are 50%. WHICH ONE of the following identifies the action the Control Room Supervisor is to direct concerning high pressure safety injection use?
A. HPSI flow may be throttled until HPSI flow is the same as break flow.
B. Continue maximum injection flow until subcooling is at least 24°F.
C. HPSI flow may be throttled to restore pressurizer level 10 to 70%.
D. Continue maximum injection flow until subcooling is at least 44°F.
Answer: D
75
Given the following plant conditions: The reactor has tripped. SG #1 level is 0% WR. SG #1 pressure is 25 psig.
The following indications are available to the Secondary Operator: Loop 1 T-cold 358°F
Loop 1 T-hot 480°F
Loop 2 T-cold 460°F
Loop 2 T-hot 488°F
Which one of the following pressures indicates the pressure that SG # 2 should be reduced to?
A. 610 psia
B. 466 psia
C. 566 psia
D. 150 psia
Answer: D
76
Given the following plant conditions: The reactor has tripped. An ESD has occurred on SG #1. SG #1 has just reached dryout. The following indications are available to the Secondary Operator:
Loop 1 T-cold 392°F
Loop 1 T-hot 480°F
Loop 2 T-cold 460°F
Loop 2 T-hot 488°F
Which one of the following pressures indicates the pressure that SG # 2 should be reduced to?
A. 610 psia.
B. 465 psia.
C. 565 psia.
D. 225 psia.
Answer: D
77
Given the following conditions: Unit 1 tripped from 100% full power. SPTA's in progress SIAS, CIAS, MSIS, and AFAS-1 have initiated. The RCS is in forced circulation. Steam Generator #1 pressure is 750 psia and dropping rapidly. Steam Generator #1 level is 8% WR and dropping rapidly Steam Generator #2 pressure is 940 psia and slowly lowering. Steam Generator #2 level is 37% WR and slowly lowering. Auxiliary feedwater flow is > 2000 gpm to steam generator #1. Auxiliary feedwater flow is 0 gpm to steam generator #2. WHICH one of the following actions correctly address the existing symptoms ?
A. Allow maximum flow to SG #1 until level is greater than 10% WR.
B. Throttle and balance flow to each steam generator.
C. Stop feeding SG #1 and allow SG #2 to feed in RTO.
D. Stop feeding SG #1 and ensure feedwater flow is restoring level in SG #2.
Answer: D
78
When performing a plant cooldown as part of the Excess Steam Demand procedure actions, when is the standby Letdown Backpressure Control Valve placed in service?
A. Below 650 psig.
B. Below 575 psia.
C. Below 1000 psia.
D. Below 850 psia.
Answer: C
79
Given the following conditions: A sustained LOAF is in progress. Both SGs are dry. RCS temperature is rising. A feedwater source has been restored and is available. Which one of the following describes how the SG(s) should be fed under these conditions?
A. Feed only ONE at 500 maximum gpm.
B. Feed only ONE at 1000 gpm maximum.
C. Feed BOTH at 500 gpm maximum each.
D. Feed BOTH at 1000 gpm maximum each.
Answer: B
80
Given the following, which of the parameters is used to determine the stabilization temperature of the RCS during an excessive steam demand event?
A. S/G level of unaffected S/G.
B. Lowest hot leg temperature.
C. S/G pressure in affected loop.
D. Lowest Cold leg temperature.
Answer: D
81
Given the following plant conditions: FRP is in progress. Main steam safety valve has failed open on SG #1. RU-4 is in HIGH Alarm. LOOP DG 'A' tripped on generator differential. All other ESFAS systems operate as designed. Assuming no other events, which success path should be performed first?
A. IC-2, SI
B. MVAC-2, DGs
C. CI-1, Auto/man CTMT ISOL
D. HR-2, SG with SI
Answer: C
82
The reactor is at full power when a main steam line break occurs. The affected S/G is currently blowing down. Which of the following sets of conditions would be used to identify the affected S/G?
A. Lowest S/G pressure, highest S/G level, highest loop Tc
B. Lowest S/G pressure, lowest S/G level, lowest loop Tc.
C. Highest S/G pressure, highest S/G level, lowest loop Tc
D. Highest S/G pressure, lowest S/G level, highest loop Tc
Answer: B
83
Given the following, which will minimize the rebound effect seen during an excessive steam demand event?
1. Throttle HPSI flow as soon as conditions allow.
2. Fill the affected S/G to cover the tubes.
3. Fill the pressurizer as high as possible.
4. Stabilize RCS temperature with the unaffected loop's S/G.
A. 1,4
B. 1,2
C. 3,4
D. 2,3
Answer: A
84
Given the following, which of the parameters is NOT used to determine the affected S/G during an excessive steam demand event?
A. Cold leg temp
B. Hot leg temp
C. S/G pressure
D. S/G level
Answer: B
85
The Blackout coping strategy assumes that PBA-S03 will be energized from a GTG within:
A. 30 Minutes.
B. 60 Minutes.
C. 90 Minutes.
D. 120 Minutes.
Answer: B
86
Given the following conditions: The unit is in a blackout condition. The CRS has entered 40EP-9EO08, Blackout. The STA has just completed the SFSC for blackout. The status of electrical buses energized are as follows: PNA-D25 is energized from Inverter PNA-N11 PNC-D27 is energized from Inverter PNC-N13 PKA-M41 is energized from its associated battery PKC-M43 is energized from its associated battery All other Buses are de-energized The MVDC Safety Function Status Checks for Blackout are...
A. satisfied because PKA-M41 and PKC-M43 are not required to have their associated chargers in service.
B. not satisfied because there is no 4160 VAC vital bus energized.
C. not satisfied because all energized buses are not in the same train.
D. satisfied because all appropriate acceptance criteria has been met.
Answer: D
87
You have been directed to perform Attachment 31-B of Appendix 31 of the Standard Appendices, local monitoring of IA pressure and emergency nitrogen supply. How often are you required to log the Nitrogen Storage Tank level?
A. Every 60 minutes.
B. Every 15 minutes.
C. Every 30 minutes.
D. Every 45 minutes.
Answer: C
88
Given the following conditions: A steam line break occurs in the Turbine Building. A manual reactor trip is initiated. Shortly after the trip, an MSIS actuates. Tcold for both loops indicate 546°F. The crew is performing the SPTAs. Based on these conditions, the Control Operator should...
A. immediately restore temperature to 560°F Tcold.
B. continue the cooldown to a Tcold of 500°F.
C. stabilize RCS temperature at its present value.
D. slowly heat the RCS back to its normal post trip band of 560° to 570°F Tcold.
Answer: C
89
Given the following conditions following a Rx trip: Pressurizer pressure 1650 psia and decreasing Subcooled margin is 95°F and increasing No activity in the Containment or Steam Plant A single event is in progress with no other complications The most likely diagnosis for this condition is:
A. LOCA
B. ESD
C. LOOP
D. SGTR
Answer: B
90
Given the following conditions: A steam line break occurs in the Turbine Building A manual reactor trip is initiated Shortly after the trip, an MSIS actuates The crew took all appropriate actions and has entered the ESD procedure Based on these conditions, what is the appropriate classification (if any)?
A. NUE
B. This event is not classifiable.
C. Alert.
D. SAE.
Answer: A
91
Given the following conditions: A steam line break occurs in the Turbine Building A manual reactor trip is initiated This steam leak was isolated by the turbine trip, an MSIS did NOT actuate The crew took all appropriate actions and has entered the Reactor Trip procedure Based on these conditions, what is the appropriate classification (if any)?
A. NUE
B. This event is not classifiable
C. Alert
D. SAE
Answer: B
92
Which one of the following plant parameters is an indication that an excessive steam demand event is occurring? Assume the S/G is not dried out.
A. Lowering RCS temperature with increasing pressurizer level.
B. Increasing reactor power with increasing RCS temperature.
C. Lowering RCS temperature with increasing containment pressure.
D. Lowering RCS temperature with increasing pressurizer pressure.
Answer: C
93
When in the performance of the ESD procedure and it has been determined to remain in hot standby, which of the following actions is performed:
A. Stop the Heater Drain pumps.
B. Stop feeding the Steam Generators with the AFW pumps.
C. Perform system walkdowns to determine where leakage exists.
D. Cross connect the EW to NC systems to allow the normal chillers to operate.
Answer: A
94
#1 SG has been isolated following a SGTR and the following conditions exist: 1A and 2A RCP's are operating. T-hot 470°F. #1 SG NR level - 80% and slowly trending up. #1 SG press - 900 psia. PZR press - 1200 psia. Based on the above conditions the RCS should be depressurized to between:
A. 950 and 1000 psia.
B. 800 and 850 psia.
C. 850 and 900 psia.
D. 1050 and 1100 psia.
Answer: C
95
The SGTR ORP may be entered whenever indications of a SGTR are exhibited:
A. from Mode 3 only if LTOPs are not in service .
B. from Mode 4 only if LTOPs are in service.
C. from Mode 5 only if LTOPs are in service.
D. only immediately following completion of SPTAs.
Answer: A
96
Given the following plant conditions: The Reactor has tripped. SPTAs are complete. Feedwater is not available from the Control Room. All RCPs are running. #1 SG Press is 400 psig and decreasing. #1 SG Level is 40% Wide Range and slowly decreasing. #2 SG Press is 850 psig and steady. #2 SG Level is 60% Wide Range and steady. Then: The CRS implements the FRP HR-1 (SG with No SI) is the only Jeopardized Safety Function. Which ONE of the following is the correct application of the HR success paths for this condition?
A. Address the LOAF first by restoring feedwater, then address the ESD.
B. Address the ESD first by isolating the affected SG, then address the LOAF.
C. Perform selected steps from HR-1 and 2 as desired to mitigate the event.
D. Address a potential SGTR by ensuring Th is less than 540°F, then the ESD by isolating the affected SG, and then address the LOAF.
Answer: B
97
Given the following time line: T = 0 minutes.......Unit 1 is operating at 100% with AFA-P01 OOS.T = 60 minutes.....A loss of NBN-S02 resulted in a RPCB (LOFP). T = 120 minutes...Plant is stabilized with NBN-S02 de-energized.T = 180 minutes...Inadvertent MSIS results in plant trip. After the plant trip, the following occurs: PBA-S03 locks out on overcurrent. AFB-P01 supply breaker trips on overcurrent Assuming the operating crew can only take action from the control room, which one of the following appendices should be utilized to supply feedwater to the SGs when the appropriate ORP or FRP is entered?
A. Appendix 44, Feeding with the Condensate Pumps.
B. Appendix 37, Operation of AFN-P01 after MSIS.
C. Appendix 46, Feeding Unit 1 SGs with Unit 2 Condensate Pumps.
D. Appendix 43, Restarting MFPs.
Answer: D
98
Given the following conditions: With the plant at NOT and NOP, the crew is preparing to close the RTCBs in order to startup the reactor. RCS pressure begins to drop, resulting in a SIAS/CIAS. SG #1 level begins to rise, indicating a SGTR. Based on these conditions, the Operating Crew ...
A. must enter the LMEOPs.
B. can directly enter the SGTR procedure.
C. can mitigate the event using the RCS Excessive Leakage AOP.
D. must perform the SPTAs to confirm the diagnosis, then proceed to the SGTR procedure.
Answer: B
99
Given the following conditions: Tcold 210F. Pressurizer pressure 250 psi. Pressurizer level 50%. All rods inserted. No radiation monitors in alarm. Train "A" Shutdown Cooling is in service, "A" LPSI is the running pump. Essential bus PBB S04 is down powered for an electrical outage. Train "A" LTOP relief valve lifts to 100% open and will not reseat. A loss of offsite power occurs, diesel generator "A" trips on differential and is damaged. What safety function criteria are not met?
A. HR, CI, CTPC.
B. IC, PC, CI.
C. IC, HR, CTPC.
D. MVAC, IC, HR.
Answer: D
100
Given the following plant conditions: "A" shell main condenser vacuum breaker has failed Open Rx has tripped on low SG levels AFA-P01 has failed due to a loss of lubricating oil. AFN-P01 has a brighter than normal green light, confirmed 86 lockout and a ground fault trip. PKB-M42 is de-energized due to a fault. Which one of the following should be pursued as the primary method of restoring feedwater?
A. Restart a Main Feed Pump.
B. Local operation of AFA-P01.
C. Local operation of AFN-P01.
D. Local operation of AFB-P01.
Answer: D
101
Given the following conditions: TIME (minutes)EVENT0 Unit 1 is operating at 50%. B MFP is in standby CDN-P01A is OOS5A loss of NBN-S02 resulted in a manual Reactor Trip. (due to low suction pressure trip on A MFP)15After plant stabilization, NAN-S02 trips due to overcurrent. After the trip, the following malfunctions occur: Bus fault on PKA-M41 PBB ground fault occurs. NNN-D16 is de-energized and can not be restored. Assuming the operating crew has entered the FRP, which one of the following feed sources would be used first?
A. This unit's condensate Pump(s).
B. B Main Feed Pump.
C. Other unit's condensate pumps.
D. AFN-P01.
Answer: D
102
Given the following conditions: The unit has tripped and the CRS has diagnosed a LOAF with an inadvertent SIAS. The CRS directs you to start AFN-P01. Tc is 565 °F The SIAS load shed panels have been re-energized Suction valves are open and downcomer valves are in remote-auto Indicating lights for AFN-P01 are lit. You have gone to "START" one time using its handswitch (AFN-HS-11). AFN-P01 is...
A. not running, AFN-P01 will start by going to "START" one more time.
B. running and feeding both Steam Generators.
C. running but not feeding either Steam Generator.
D. not running, AFN-P01 can be started by going to "STOP" then "START".
Answer: D
103
Given the following conditions: The plant has tripped from 100% power. Prior to the trip, RU 4 (Hi Trip) and RU 141 (Hi Trip) conditions were indicated. Following the isolation of Steam Generator #1, level is 78% NR and increasing slowly. SG #1 pressure is 1000 psia T-cold is 492°F T-hot is 495°F Which one of the following is the preferred method for Steam Generator #1 level control?
A. Bypass the blowdown demineralizer and blowdown directly to the condenser.
B. Increase the steaming rate on S/G #1 to the condenser.
C. Increase the steaming rate on S/G #1 to the atmosphere.
D. Lower RCS pressure below #1 SG pressure and allow backfill to the RCS.
Answer: D
104
Given the following conditions: A steam break in the turbine building has occurred and was isolated by an MSIS. While the SPTAs are being performed, the following conditions are noted: AFA-P01 - Under clearance for maintenance AFB-P01 - 86 Lockout trip following the AFAS actuation AO reports that AFB motor is smoking and physically damaged. Both SG levels are 20% WR and slowly lowering Feed rate to both SGs is 0 gpm. Which one of the following can the crew perform to meet RCS Heat Removal safety function of SPTAs?
A. Close ADVs until feed flow to a SG has been established.
B. Reset the 86 lock-out and restart AFB-P01.
C. Depressurize a SG for feeding with a condensate pump.
D. Override the downcomer isolation valves and establish feed using AFN-P01.
Answer: D
105
SG # 1 has been isolated following a SGTR, and the following conditions exist: 1A and 2A RCPs are operating. Th 490°F. SG 1 level 65% NR and slowly trending up. SG 1 pressure 950 psia and slowly trending up. Pressurizer pressure 1200 psia. Per the SGTR ORP and the CE mitigation strategy, the RCS should be depressurized to between:
A. 800 and 900 psia
B. 900 and 1000 psia
C. 1000 and 1100 psia
D. 1100 and 1200 psia
Answer: B
106
During a Loss of Offsite Power (LOOP), the operating crew is directed to startup a Gas Turbine Generator (GTG) within 1 hour and energize NAN-S07. Assuming that each unit is being supplied by their own diesel generators, is this step still necessary, and why or why not?
A. Yes, this step is necessary to augment the DGs, enabling one unit to startup if necessary.
B. Yes, this step ensures that the GTG batteries and HVAC equipment have power.
C. No, this step can be omitted if at least one DG is operating on each unit.
D. No, this is only performed if there is thunderstorm activity in the "vicinity."
Answer: B
107
During a loss of all feedwater event, why are all of the Reactor Coolant Pumps tripped?
A. Allows more rapid depressurization of the steam generators.
B. Natural circulation is a better heat removal method.
C. Minimizes heat input into the RCS.
D. Ensures that adequate electrical system capacity exists to run an Auxiliary Feed Pump.
Answer: C
108
The following plant conditions exist: Unit 1 experienced a SGTR from 100% power CRS is implementing the SGTR ORP RCS depressurization has been initiated Which one of the following is a potential impact of lowering RCS pressure below the existing pressure in the ruptured SG?
A. Causing a dilution of the RCS.
B. Taking the RCS water solid.
C. Excessive cooldown of the RCS.
D. Loss of SG heat removal capability.
Answer: A
109
With a steam generator tube ruptured and faulted SG that is steaming to atmosphere, the safety analyses assumes that feed is restored in approximately ___ minutes.
A. 11
B. 22
C. 30
D. 60
Answer: A
110
Which one of the following would increase the probability of drawing a reactor vessel head bubble during a SGTR. (Assume all equipment functions as designed unless stipulated below.)
A. Loss of offsite power.
B. Energizing pressurizer heaters.
C. Isolating the affected generator.
D. Reducing the rate of RCS depressurization.
Answer: A
111
Durring a LOOP, the operating crew has just completed the appropriate maintenance of vital auxiliaries success paths for power restoration. The status of electrical buses energized are as follows: PBB-S04 is energized from EDG B PNA-D25 is energized from Inverter PNA-N11 PKA-M41 is energized from it's battery PKC-M43 is energized from it's battery All other buses are de-energized The maintenance of vital auxiliaries safety function is:
A. not satisfied because PNC-D27 is not energized.
B. satisfied
C. not satisfied because all energized buses are not in the same train.
D. not satisfied because both PKA-M41 and PKC-M43 do not have their associated chargers in service.
Answer: C
112
Given the following plant conditions: Plant has tripped from 100% power. The Loss of All Feedwater procedure, 40EP-9EO06 has been entered. No other events are in progress. Which one of the following describes plant response when dryout conditions have been reached in both Steam Generators?
A. Steam Generator pressures will stabilize at the saturation pressure corresponding to RCS cold leg temperature.
B. RCS temperatures will decrease.
C. Steam Generator pressures will increase.
D. RCS temperatures will increase.
Answer: D
113
Given the following plant conditions: A reactor trip from 100% power occurs due to an inadvertent MSIS "A". PBA-S03 is de-energized due to a bus lockout. AFB-P01 is out of service to repair a pump bearing and is disassembled. AFA-P01 tripped on overspeed. The crew has completed the SPTA's and the CRS directs entry into 40EP-9EO06, Loss Of All Feedwater. Which one of the following operator actions should be performed first.
A. Ensure AFAS-1 and AFAS-2 are actuated.
B. Start AFN locally at the breaker.
C. Stop all RCPs.
D. Depressurize one S/G to less than condensate pump discharge pressure.
Answer: C
114
An inadvertent MSIS and a reactor trip have occurred and the following conditions exist:
Steam Generator #1 level - 20% WR and decreasing
Steam Generator #2 level - 22% WR and decreasing
Steam Generator #1 pressure - 1240 psia and increasing Steam Generator #2 pressure - 1235 psia and increasing
Main feedwater pressure - 450 psia
AFA-P01 discharge pressure - 500 psia
AFB-P01 has 86 lockout trip following start
PBA-S03 deenergized due to a bus fault
ADVs are being opened by the Secondary Operator
All automatic actuations have occurred
Which one of the following recovery procedures would mitigate this event?
A. 40EP-9EO04, Steam Generator Tube Rupture.
B. 40EP-9EO02, Reactor Trip.
C. 40EP-9EO09, Functional Recovery Procedure.
D. 40EP-9EO05, Excess Steam Demand.
Answer: C
115
Why is it important for the operating crew to energize the switchyard loads from the Gas Turbine Generators during a Loss of Offsite Power (LOOP)?
A. Restores control power NAN-S05 and NAN-S06.
B. Ensures that switchyard breaker operation will be possible.
C. Restores the normal power supply to the security lighting system.
D. Ensures that a minimum load is placed on the GTGs allowing the generators to burn their fuel completely.
Answer: B
116
Given the following conditions: A LOAF is in progress. The CRS has determined to restore feed using Condensate Pumps. The Secondary Operator is directed to utilize the ADV(s) on the selected SG to establish conditions to permit feeding. Which one of the following describes the actions that should be taken?
A. Completely depressurize the selected SG.
B. Depressurize the selected SG to about 450 psia.
C. Depressurize the selected SG to about 550 psia.
D. Depressurize the selected SG to about 750 psia.
Answer: B
117
Which one of the following describes the reason for stopping all RCP's during a Loss of All Feedwater event?
A. Reduces the RCS mass loss to the SGs if tubes break upon initiation of feedwater.
B. Prevents lifting Steam Generator safety valves.
C. Prevents primary system depressurization through the main spray valves.
D. Reduces the heat load that must be removed by the Steam Generators.
Answer: D
118
Based on plant conditions, additional equipment operation may be required to mitigate a blackout event (above and beyond coping loads). Which of the following is an acceptable combination of loads, per Standard Appendix 81 assuming a single GTG in operation?
A. AFN-P01 and CHE-P01.
B. AFN-P01 and LPSI B.
C. AFB-P01 and HPSI B.
D. AFB-P01 and CHE-P01.
Answer: D
119
With a LOAF in progress, which of the following could significantly reduce the time available to restore feedwater before drying out the SGs?
A. A large break LOCA coincident with the LOAF.
B. A SGTR coincident with the LOAF.
C. A spurious CIAS coincident with the LOAF.
D. Delaying the trip of RCPs in 40EP-9EO06, LOAF.
Answer: D
120
Based on plant conditions, additional equipment operation may be required to mitigate a blackout event (above and beyond coping loads). Which of the following is an acceptable combination of loads, per Standard Appendix 81 assuming paralleled GTG operation?
A. AFB-P01, CHE-P01 and SIB-P02.
B. AFN-P01, CHE-P01 and SIB-P01.
C. AFB-P01, CHB-P01 and SIB-P03.
D. AFN-P01, CHA-P01 and SIA-P02.
Answer: A
121
If a total loss of feed flow has progressed to the point where steam generator dryout has occurred and the plant is not yet on SDC, core uncovery can begin in as little as ________ from the time feed is lost.
A. 10 minutes
B. 1 hour
C. 22 minutes
D. 2 hours
Answer: B
122
The requirement in the FRP to feed a ruptured and faulted SG at >1360 gpm is aimed at...
A. reducing the associated radioactive release.
B. rapidly depressurizing the RCS.
C. rapidly depressurizing the affected SG.
D. reestablishing the SG as the primary heat sink.
Answer: A
123
Based on plant conditions, additional equipment operation may be required to mitigate a blackout event (above and beyond coping loads). Which of the following is an acceptable combination of loads, per Standard Appendix 80 assuming a single GTG in operation?
A. AFB-P01 and CHE-P01.
B. AFN-P01 and CHE-P01.
C. AFN-P01 and SIA-P02.
D. AFA-P01 and SIA-P03.
Answer: B
124
In accordance with Emergency Operating Procedures a "Loss of All Feedwater" occurs when:
A. Any time AFAS is initiated, either automaticity or manually.
B. indicated feed flow
Answer: D
125
Tcold 230°F. Pressurizer pressure 250 psia. Pressurizer level 28% and dropping slowly. Train "A" shutdown cooling is in service with LPSI "A" running. Charging pump CHB-P01 is red tagged out of service. Shutdown cooling purification is aligned with the backpressure controller CHN-PIC-201 controlling letdown. RCS is borated to 2500 ppm. A loss of the grid occurs. Contaiment temperature is 110°F and stable. Containment pressure is 0 psig and stable. Following the loss of the grid , the following conditions are present: "A" Diesel Generator tripped on low lube oil pressure and is damaged. Charging pump CHE-P01 trips on overcurrent and is damaged. PBB-S04K has an 86 lockout. (Normal Supply Breaker to PBB-S04) Containment sump level is rising. Pressurizer level is dropping rapidly. Which of the following groups of safety functions are ALL jeopardized?
A. MVAC, IC, CI
B. IC, PC, CTPC
C. MVAC, IC, HR
D. HR, CI, PC
Answer: C
126
Given the following plant conditions: Unit 1 has experienced a trip from 100% power. All feedwater has been lost. Both SGs are dry. Which of the following defines the strategy for feeding the SGs when feedwater is regained?
A. Feed one SG at the maximum available feed rate.
B. Feed both SGs at 1000 gpm or less.
C. Feed one SG at 1000 gpm or less.
D. Feed both SGs at the maximum available feed rate.
Answer: C
127
Given the following plant conditions: Unit 1 has experienced a Blackout. PBA-S03 has been energized from Unit 3 DG B per Standard Appendix 82. Which of the following equipment sequence combinations is correct for starting loads in Unit 1?
A. PGA-L31, SIA-P02, SPA-P01, ECA-E01.
B. SPA-P01, ECA-E01, PGA-L31, EWA-P01.
C. AFN-P01, PGA-L35, EWA-P01, SIA-P02.
D. PGA-L31, PGA-L35, AFN-P01, SIA-P02.
Answer: A
128
With nuclear safety being the number one concern, which impact from reverse fluid flow from a steam generator tube rupture to the RCS is of the utmost concern?
A. Corrosive damage to the fuel assembly cladding.
B. Excessive cooldown of the RCS.
C. Potential dilution of the RCS boron concentration.
D. Taking the RCS solid and lifting the pressurizer safeties.
Answer: C
129
The crew has entered the Lower Mode Functional Recovery Procedure, Safety Function Set 2, and the CRS has identified the following success paths needed to mitigate the event in progress. RC-1 MVAC-2 - In Jeopardy MVDC-1 - In Jeopardy IC-2 PC-7 HR-2 - In Jeopardy CI-2 CTPC-1 Which one of the following identifies the correct performance order?
A. RC-1, MVAC-2, MVDC-2, & IC-2
B. MVAC-2, MVDC-1, HR-2, & IC-2
C. MVAC-2, HR-2, IC-2 & PC7
D. MVAC-2, HR-2, MVDC-1 & RC-1
Answer: B
130
Given the following plant conditions: An excessive steam demand event is in progress with a S/G safety valve open. S/G #2 has been determined to be the affected S/G. Is there a concern with continuing to feed the affected S/G following an ESD event?
A. Yes, it will cause the RCS to cool down further and affect reactivity.
B. No, it will minimize the rebound effect.
C. Yes, it will fill the S/G and cover the tubes.
D. No, it will minimize the need for auxiliary feedwater.
Answer: A
131
Which one of the following describes the operation of AFN-P01 following a loss of PKA-D21 in which PKA-D21 can NOT be re-energized? Control power must be shifted to the 'A' battery...
A. output to restore remote operation of both the breaker and suction valves.
B. output to restore remote operation of the breaker.
C. charger output to restore remote operation of the AFN-P01 breaker.
D. charger output to restore remote operation of both the breaker and suction valves.
Answer: C
132
All of the following conditions are acceptable reasons to exit the LOAF procedure after initally entering it EXCEPT....
A. A Loss of Offsite Power occurs concurrently with a Loss of All Feed.
B. Diagnosis of the Loss of All Feedwater can not be confirmed.
C. The feedwater line break can not be isolated from the Steam Generator.
D. The STA completes the safety function status sheet and determines that all of the acceptance criteria are not met.
Answer: A
133
The following plant conditions exist: The reactor is tripped. A small break LOCA is in progress. A loss of all Feedwater is in progress. Pressurizer level is 35%. Pressurizer pressure is 2275 psia and rising. Which one of the following would be an indication that RCS voiding is occurring?
A. RCS pressure increase when pressurizer spray is initiated.
B. Pressurizer level decrease when letdown flow is raised.
C. Pressurizer level increase when pressurizer spray is activated.
D. RCS pressure decrease when pressurizer heaters are energized.
Answer: C
134
SG # 1 has been isolated following a SGTR, and the following conditions exist: 1A and 2A RCPs are operating. Th 520°F. SG 1 level 65% NR and slowly trending up. SG 1 pressure 950 psia and slowly trending up. Pressurizer pressure 1200 psia. The RCS should be depressurized to:
A. 850 psia
B. 1100 psia
C. 950 psia
D. 1000 psia
Answer: B
135
Given the following conditions: A SGTR has occurred on SG 2. RCS pressure is 1600 psia. SIAS has actuated, providing adequate flow. Thot is 565°F. Tcold is 562°F. RCPs in operation SBCS is controlling SG pressure at 1150 psia. Level is rising in SG 2. The CRS directs depressurizing the RCS. Based on current conditions and applying the SGTR strategy, determine the RCS pressure to use as the initial target.
A. 1450 psia
B. 1135 psia
C. 1200 psia
D. 1300 psia
Answer: A
136
The LOOP EOP directs an MSIS be manually initiated to...
A. ensure an ESD does not occur.
B. protect the main feed pumps.
C. protect the main condenser.
D. ensure steam is available for AFA-P01 operation.
Answer: C
137
The following plant conditions exist: The reactor is tripped A LOCA is in progress Pressurizer level is 35% RVLMS is inoperable RCS voiding is occurring Which one of the following would be an indication that the RCS void has reached the outlet plenum?
A. Saturated conditions on RCS loop temperatures.
B. HPSI flow decreases.
C. Pressurizer level increases.
D. RCS pressure decrease when pressurizer heaters are energized.
Answer: A
