ML023020109
| ML023020109 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/30/2002 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-334/02-301 50-334/02-301 | |
| Download: ML023020109 (243) | |
Text
U. S. Nuclear Regulatory Commission Site-Specific Written Examination Annlitcant Information Name: Region: I Date: Facility/Unit: BVPS-1 License Level: RO Reactor Type: Westinghouse PWR Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value 100L Points Applicant's Score Points Applicant's Grade Percent
BVPS-1LOT5 NRC EXAM Reactor Operator
- 1. A B C D 26. A B C D
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BVPS-1 LOT5 NRC EXAM Reactor Operator
- 51. A B C D 76. A B C D
- 52. A B C D 77. A B C D
- 53. A B C D 78. A B C D
- 54. A B C D 79. A B C D
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- 65. A B C D 90. A B C D
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- 67. A B C D 92. A B C D
- 68. A B C D 93. A B C D
- 69. A B C D 94. A B C D
- 70. A B C D 95. A B C D
- 71. A B C D 96. A B C D
- 72. A B C D 97. A B C D
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- 74. A B C D 99. A B C D
- 75. A B C D 100. A B C D
________________________________________________________________ .1 3
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 001 Given the following conditions:
- The Unit is at 85% power. All systems are in NSA.
- A Control Bank "D", Group 2 rod drops to the bottom of the core.
- The plant is stabilized, the cause of the failure identified and repaired.
Which one of the following describes the method for retrieving the dropped rod in accordance with I OM-1.4.X, RCCA Or RCCA Group Misalignment?
A. All rods in group 2 except the affected rod are disconnected. Control Bank "D", Group 1 rods remain connected. The Group 2 Step Counter is set to the dropped rod position prior to retrieval. The affected rod is withdrawn until the Group 2 Step Counter matches the Group 1 Step Counter.
B. All rods in Control Bank "D", Group I and Group 2, except the affected rod are disconnected. The Step Counter for Group 2 is set to the dropped rod position. The Step Counter for Group 1 is left at its current position. The affected rod is withdrawn until Group 1 and Group 2 Demand are equal.
C. All rods in Control Bank "D", Group 1 and Group 2, except the affected rod are disconnected. The Step Counters for Group I and Group 2 are set to the dropped rod position. The affected rod is withdrawn until the Step Counters match the initial bank position.
D. All rods in group 2 except the affected rod are disconnected. Control Bank "D", Group I rods remain connected. The Step Counters for Group 1 and Group 2 are set to the dropped rod position. The affected rod is withdrawn until the Step Counters match the initial bank position.
I
EXAM BVPS-1 LOT5 NRC BVPS-1 LOT5 NRC EXAM Reactor Operator Question 002 The plant is operating at 100% power, NSA when the following indications are observed.
"* Control Bank "D"rod F-6 position indicates '0' steps.
"* Rod bottom rod drop alarm is received.
If rod F-6 is the only rod bottom light lit and the plant remains on-line, which one of the following describes the INITIAL automatic response of the CVCS?
A. Letdown flow is increased.
B. Letdown flow is decreased.
C. Charging flow is increased.
D. Charging flow is decreased.
2
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 003 Given the following conditions:
- The plant is in Mode 3.
- A reactor startup is in progress.
- Shutdown Bank "A" is fully withdrawn.
- Shutdown Bank "B" is being withdrawn.
- The following annunciator is received in the Control Room:
o [A3-82], REACTOR COOL PP BRG OIL RESERVOIR LOW
- The startup is stopped while a Containment entry is made to investigate.
The operator in containment reports a large oil leak in the vicinity of "IA" RCP.
Which one of the following describes the action required?
A. Trip "IA" RCP and refer to the alarm response procedure for "IA" RCP low flow.
B. Trip the reactor, trip "IA" RCP and refer to the alarm response procedure for "IA" RCP low flow.
C. Trip the reactor, perform Immediate Manual Actions of E-0, Reactor Trip Or Safety Injection, trip "IA" RCP and continue in E-0. I D. Monitor "IA" RCP bearing temperatures. If any bearing temperature exceeds 275 0 F, trip the RCP and refer to the alarm response procedure for RCP bearing high temperature.
3
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 004 The following conditions exist for starting a Reactor Coolant Pump (RCP):
- Local Lift Oil Pump control switch in 'AUTO'.
- RCP control switch placed in 'START' and released.
Which one of the following describes the sequence of events that will take place to start the RCP?
A. Lift Oil Pump starts. After 50 seconds, RCP starts. 2 minutes later the Lift Oil Pump stops.
B. Lift Oil Pump starts. After 2 minutes, RCP starts. 50 seconds later the Lift Oil Pump stops.
C. After 50 seconds the Lift Oil Pump starts. 2 minutes later the RCP starts.
50 seconds, the Lift Oil Pump stops.
D. After 50 seconds the Lift Oil Pump starts. After 50 seconds the RCP starts. 2 minutes later the Lift Oil Pump stops.
4
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 005 The Unit is operating at 100% power NSA, when [LT-1 CH-1 12], VCT Level Transmitter fails high.
After an extended period of operation, the following conditions result.
"* [A3-53], VOLUME CONTROL TANK LEVEL HIGH-LOW alarms.
"* VCT level indicates approximately 5%.
Assuming NO action by the crew, which one of the following describes the plant response?
A. Charging pump suctions from the VCT remain open; the RWST suction valves remain closed.
B. Charging pump suctions from the VCT will close; the RWST suction valves remain closed.
C. Charging pump suctions from the VCT remain open; the RWST suction valves also open on low VCT level.
D. Charging pump suctions from the VCT will close; the RWST suction valves open on low VCT level.
5
EXAM BVP S-I LOTS NRC BVIPS-1 LOT5 NRC EXAM Reactor Operator Question 006 The operating crew is performing a dilution in preparation for rod withdrawal to criticality.
If Keff is approximately .99 when the dilution is started, at what point in the dilution can the crew determine that Keff is approximately .995?
A. When the Source Range counts double from their initial value.
B. When there is a stable startup rate with no change in the dilution flow rate.
C. When Control Bank "A"control rods are withdrawn from the core.
D. When the Source Range counts double 2 - 3 times from their initial value.
6
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 007 Given the following conditions:
- An ATWS has occurred.
- The operating crew is performing the actions of FR-S.1, Response To Nuclear Power Generation/ATWS.
Which one of the following describes the required operation of the AFW System and why?
A. Operate all available AFW pumps to establish total flow of 355 gpm; to maintain minimum heat sink and restore SG levels.
B. Operate motor driven AFW pumps only to establish total flow of 355 gpm; to minimize effects of RCS cooldown on reactivity.
C. Operate all available AFW pumps to establish total flow of 630 gpm; to maintain minimum heat sink and restore SG levels.
D. Operate motor driven AFW pumps only to establish total flow of 630 gpm; to minimize effects of RCS cooldown on reactivity.
7
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 008 Given the following conditions:
"* The Unit was operating at 100% power.
"* A PORV failed open.
"* The reactor has tripped on low Pressurizer pressure.
"* Pressurizer pressure stabilizes at 1700 psig.
Plant status is as follows:
"* All control rods are fully inserted.
"* Status light "S Inj Act Sig" NOT LIT at Panel 62, C-4.
- Normally running charging pump is in service.
- Standby charging pump not running,
- NO LHSI pumps running.
- CIA NOT actuated.
- CIB NOT actuated.
- Main steam lines NOT isolated.
- Feedwater Isolation Signal NOT actuated.
Which one of the following describes the required manual operator actions?
Manually initiate both trains of ...
A. Safety Injection.
B. Safety Injection and CIB.
C. Safety Injection, CIB, and Main Steam Line Isolation.
D. Safety Injection, CIB, Main Steam Line Isolation, and CIA.
8
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 009 Which one of the following contains BOTH conditions that will result in indicated reactor power being LOWER than actual reactor power?
A. Source Range pulse height discrimination set too LOW.
Intermediate Range compensating voltage set too LOW.
B. Source Range pulse height discrimination set too HIGH.
Intermediate Range compensating voltage set too HIGH.
C. Source Range pulse height discrimination set too LOW.
Intermediate Range compensating voltage set too HIGH.
D. Source Range pulse height discrimination set too HIGH.
Intermediate Range compensating voltage set too LOW.
9
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 010 Following a Unit trip, Intermediate Range Startup rate is approximately -1/3 decade per minute on both channels.
Current indication on Intermediate Range channels are as follows:
- N35 = 5E 7 amps
- N36 = 2E- amps Based upon the above indications, which one of the following describes the sequence for Source Range Channel N-31 and N-32 energization?
A. Both Source Range channels will energize when N-35 reaches its setpoint.
B. Both Source Range channels will energize when N-36 reaches its setpoint.
C. N-31 will energize when N-35 reaches its setpoint. N-32 will energize when N-36 reaches its setpoint.
D. N-31 will energize when N-36 reaches its setpoint. N-32 will energize when N-35 reaches its setpoint.
10
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 011 Given the following conditions:
"* The Unit is in Mode 1. All systems are in NSA.
"* All Tavg channels are approximately 30 F higher than Tref.
Which one of the following modes on the Rod Control System Mode Selector Switch will provide the FASTEST rod speed if rod motion is demanded?
A. Manual B. Automatic C. Control Bank "A" D. Shutdown Bank"A" 11
BVPS-1LOT5 NRC EXAM Reactor Operator Question 012 Given the following conditions:
"* A Reactor Trip has occurred from 100% power.
"* Actions of E-0, Reactor Trip Or Safety Injection are being performed.
"* The operating crew is checking if SI flow should be terminated when it is determined that RCS subcooling on the ICCM is less than the required 43 0 F Which one of the following describes the method used to determine whether RCS subcooling is adequate?
A. Minimum required subcooling is determined using the SPDS; actual RCS subcooling is calculated by the IPC.
B. Actual RCS subcooling is determined using PRZR pressure and T-hot; minimum required subcooling is determined by the SPDS.
C. Minimum required subcooling is determined using an EOP Attachment; RCS subcooling is determined using PRZR pressure and T-hot.
D. RCS subcooling is determined using the ICCM; minimum required subcooling is determined using an EOP attachment.
12
BVPS-1LOT5 NRC EXAM Reactor Operator Question 013 Which one of the following correctly completes the following description of CRDM Shroud Cooling Fan operation?
With all plant systems in their normal alignments, [1VS-F-2C], CRDM Shroud Fan would start in the if [1VS-F-2A], CRDM Shroud Fan is NOT racked in on bus _ , and the diesel loading sequence signal is received.
A. auto mode; 8N B. auto mode; 8P C. manual mode; 8N D. manual mode; 8P 13
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 014 Given the following conditions:
"* A loss of offsite power has occurred.
", All equipment has started and is operating as designed.
Which one of the following describes how Containment temperature is controlled under these conditions?
A. All Containment Air Recirculation Fans automatically sequence onto the EDGs.
B. Containment Air Recirculation Fans will automatically start when their control switches are placed in 'AUTO AFTER STOP'.
C. Containment Air Recirculation Fans must be manually started as necessary to control containment temperature.
D. Containment Air Recirculation Fans "A" and "B" automatically sequence onto the EDGs. Fan "C" must be manually started on the bus it is aligned to.
14
BVPS-1LOT5 NRC EXAM Reactor Operator Question 015 The Unit is operating at 80% power. All systems are in NSA.
Smoke is detected in the vicinity of MCCI-E5, and as a result the operating crew de-energizes MCCI-E5.
Subsequently, a LOCA inside Containment results in a Reactor Trip, Safety Injection and a Containment Spray actuation.
Which one of the following describes the response of the Quench Spray System?
Quench Spray Pump...
A. "A"starts and injects. "B"starts but does not provide spray flow.
B. "B"starts and injects. "A"starts but does not provide spray flow.
C. "A" and "B"both start, but neither train provides spray flow.
D. "A"and "B"both start and both trains provide spray flow.
15
BVPS-1LOT5 NRC EXAM Reactor Operator Question 016 Given the following conditions:
- A LOCA has occurred.
- The following engineered safeguards actuations have initiated:
"o SI "o CIA o CIB o MSLI
- All equipment is operating as designed.
Which one of the following is the MINIMUM necessary to electrically stop a Quench Spray Pump?
A. Reset SI only.
B. Reset CIB only.
C. Reset SI and CIA. (Both required).
D. Reset SI, CIA and CIB. (All required).
16
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 017 Given the following conditions:
"* Following a Reactor Trip due to a complete loss of CCR, all RCPs are stopped.
"* All systems are operating as designed.
Which one of the following describes the response of the core exit TCs following trip of the RCPs?
Core exit temperature initially and then A. rises; drops B. drops; rises C. rises; stabilizes D. drops; stabilizes 17
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 018 With the Unit operating at 80% power, all systems in NSA, [1WR-P-1A], Reactor Plant River Water Pump trips. As a consequence, Reactor Plant River Water is available to the...
A. "B" LHSI Pump [1 SI-P-1 B] only.
B. "B" HHSI Pump [I CH-P-1 B] only.
C. "A" LHSI Pump [ISI-P-1A] and the "B" LHSI Pump [1 SI-P-1 B].
D. "A" HHSI Pump [1CH-P-1A] and the "B" HHSI Pump [1CH-P-1B].
18
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 019 Given the following conditions:
, A LOCA has occurred.
- Pressurizer level is stable at 58%.
- RCS pressure is stable at 1680 psig.
- The Unit Supervisor determines that a Charging/HHSI pump can be stopped in accordance with EOP Attachment 7-A, Criteria For Stopping 1 Of 2 Running Charging/HHSI Pumps, Subcooled Conditions.
When the RO stops the Charging/HHSI Pump, which one of the following describes the Pressurizer level response?
A. PRZR level will remain at its current value.
B. PRZR level will rise until charging is realigned to the VCT.
C. PRZR level will drop until normal charging and letdown are restored.
D. PRZR level will drop until RCS pressure stabilizes at a lower value, then will stabilize.
19
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 020 Given the following:
- The Unit is operating at 90% power with all systems in NSA.
- [GW-TK-1A], Gaseous Waste Decay Tank discharge is in progress.
S[1 GW-F-1 A], GW Disposal Blower is operating.
- [TV-1 GW- 03], GW Decay Tank Disch to CTWR Valve is open.
- [TV-1 GW-1 03A2], GW Decay Tank Bleed Valve is open.
- [1 GW-D-I -1A], GW Disposal Damper associated with the "A" GW Disposal Blower [1GW-F-I A] is open.
Then, [RM-1 GW-1 08B], GW Disposal Blower Discharge Radiation Monitor alarms on High-High gaseous activity.
Which one of the following completely describes the Gaseous Waste System automatic response?
A. [1GW-F-1A], GW Disposal Blower trips.
B. [1 GW-D-I -I A], GW Disposal Damper shuts.
C. Valve [-V-1 GW- 03] and valve [TV-1 GW- 03A2] shut.
D. Blower [1GW-F-1A] trips and damper [1GW-D-1 -IA] shuts.
20
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 021 The Unit is operating at 80% power with all systems in NSA, when a Small Break LOCA in containment results in a Reactor Trip and SI Signal.
- 4160 Volt Emergency Bus "1AE" supply breaker from offsite power trips.
- No. 1 EDG fails to start.
Which one of the following describes the status of the charging pumps?
Charging Pump "A" ; Charging Pump "B" A. running; running B. not running; running C. running; not running D. not running; not running 21
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 022 Given the following conditions:
- A loss of offsite power has occurred.
- RCPs cannot yet be started.
- The RO is depressurizing using auxiliary spray.
- Pressurizer level rapidly rises from 24% to 66%.
Which one of the following describes the reason for the Pressurizer level increase?
A. Loss of Secondary Heat Sink.
B. Portions of the RCS have reached saturation temperature.
C. HHSI flow is refilling the Pressurizer as RCS pressure drops.
D. Cooldown rate is not high enough to maintain Pressurizer level with auxiliary spray in service.
22
BVPS-1LOT5 NRC EXAM Reactor Operator Question 023 Given the following:
- A Unit startup is in progress and all nuclear instrumentation is observed to be operating normally.
- Power Range Channel N-43 is indicating 11%.
- Power Range Channels N-41, N-42 and N-44 are indicating 9%.
Which one of the following is correct concerning Reactor Protection System trips?
A. Power Range, high setpoint trip and Source Range high flux trip are enabled.
B. Power Range, low setpoint trip and Source Range high flux trip are disabled.
C. Power Range, high setpoint trip and Intermediate Range high flux trip are enabled.
D. Power Range, low setpoint trip and Intermediate Range high flux trip are disabled.
23
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 024 Given the following conditions:
- The Unit was operating at 68% power.
- An automatic Reactor Trip occurred.
- The cause of the trip was determined to be an instrument failure.
Which one of the following input failures caused the Reactor Trip?
A. The Loop "A" high pressure side flow input failed high.
B. The Loop "A" high pressure side flow input failed low.
C. One Loop "A" low pressure side flow input failed high.
D. One Loop "A"low pressure side flow input failed low.
24
BVPS-1LOT5 NRC EXAM Reactor Operator Question 025 Given the following conditions:
- The Unit is at 100% power. All systems are in NSA.
- [PT-1 MS-446], First Stage Pressure is selected for Tref input to Rod Control System. It begins to fail DOWNSCALE.
Assuming NO action by the crew, which one of the following primary plant parameters will initially INCREASE as a result of the transmitter failure?
A. Charging flow B. RCS Tavg C. Reactor power D. RCS loop Delta-T 25
BVPS-1LOT5 NRC EXAM Reactor Operator Question 026 Given the following conditions:
- A Unit startup is in progress with the main steam stop valves closed.
- The operating crew is preparing to warm up the main steam lines.
Which one of the following actions will cause "A" SG pressure to INCREASE in this plant configuration?
A. Decrease SG Atmospheric Dump Valve controller output.
B. Decrease SG Atmospheric Dump Valve controller setpoint.
C. Increase Main Steam Dump pressure controller output.
D. Increase Main Steam Dump pressure controller setpoint.
26
BVPS-1LOT5 NRC EXAM Reactor Operator Question 027 Given the following conditions:
- A Large Break LOCA has occurred.
- Both hydrogen recombiners are in service.
- The following Control Room annunciator alarm light turns 'OFF':
o [A2-18], A-HYDROGEN RECOMBINER RUNNING Which one of the following describes the effect on the removal of hydrogen from Containment?
A. Hydrogen concentration will remain below 4% with only one recombiner in operation.
B. Hydrogen concentration will rise above 4% but remain below 13% with only one recombiner in operation.
C. Hydrogen concentration will remain below 4% only if the Containment Purge System is placed in service in addition to the recombiner.
D. Hydrogen concentration will remain below 4% only if Containment Spray is placed in service in addition to the recombiner.
27
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 028 The Unit is in Mode 1. All systems are in NSA.
Which one of the following describes the normal operation of the Spent Fuel Pool Purification System?
A. Two purification circulating pumps take suction from the spent fuel pool skimmers. Each pump discharges through a separate filter and ion exchanger.
B. Either or both of two purification circulating pumps take suction from submerged piping in the Spent Fuel Pool. Each pump discharges through a separate filter and a common ion exchanger.
C. One purification circulating pump takes suction on submerged piping in the Spent Fuel Pool. The other pump is aligned for RWST purification.
Each pump discharges through separate filters and ion exchangers.
D. One purification pump takes suction from the spent fuel pool skimmers.
The other pump is aligned for RWST purification. Each pump discharges through separate filters and ion exchangers.
28
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 029 Given the following conditions:
- A Unit startup is in progress following a mid-cycle outage.
- The reactor is critical at 1 E8 amps.
A condenser steam dump valve fails partially open.
Assuming NO action by the operating crew, which one of the following describes the immediate effect on the plant?
A. RCS Temperature INCREASES; Power INCREASES B. RCS Temperature DECREASES; Power INCREASES C. RCS Temperature INCREASES; Power DECREASES D. RCS Temperature DECREASES; Power DECREASES 29
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 030 Which one of the following conditions will PREVENT the No. 1 EDG output breaker from closing to energize 4KV Bus "IAE" following a loss of power?
A. [ACB-1A10], Emergency Bus "IAE" Feeder Breaker has an undervoltage trip.
B. [ACB-1A10], Emergency Bus "IAE" Feeder Breaker has an overcurrent trip.
C. [ACB-41C], Normal 4KV Bus "IA" Feeder Breaker has an overcurrent trip with bus "IAE" normal feeder breaker control switch position in 'Auto After Close'.
D. [ACB-41C], Normal 4KV Bus "IA" Feeder Breaker has an undervoltage trip with bus "IAE" normal feeder breaker control switch position in 'Auto After Close'.
30
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 031 Given the following conditions:
- The Unit is in Mode 6.
- RHR is in service.
- RCS temperature is 139 0 F.
- RCS drain down is in progress in preparation for refueling.
[MOV-1 RH-758], RHR Heat Exchanger Flow Control Valve begins to drift in the closed direction due to an electrical problem.
Assuming NO action by the operating crew, which one of the following describes the effect of this failure on plant operation?
A. RCS cooldown to a temperature below the RCS boron solubility limit.
B. Loss of NPSH to the operating RHR pump due to increased temperature.
C. OPPS actuation due to overpressurization of the RCS.
D. Loss of RHR letdown and uncontrolled RCS level increase.
31
BVPS-1LOT5 NRC EXAM Reactor Operator Question 032 Given the following conditions:
- The Unit is in Mode 4.
Which one of the following describes the flow limits placed on the CCR System in this alignment, and the method used to determine actual flow?
A. Total CCR system flow is limited to 4500 gpm. The actual flow is determined by adding the flows on the 8 inch, 14 inch, and 24 inch CCR headers.
B. Each CCR pump is limited to a total of 6500 gpm. The actual flow is determined by adding the flows on the 8 inch, 14 inch, and 24 inch CCR headers.
C. Total CCR flow through the RHR heat exchanger is 4500 gpm. The actual flow is determined directly from the 24 inch CCR header.
D. Total CCR flow through the RHR heat exchanger is 6500 gpm. The actual flow is determined directly from the 24 inch CCR header.
32
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 033 Surveillance Verification Log L5 is being performed for the 0000 - 0800 shift.
The RO determines that the NIS Cabinet power range indication is NOT within allowable limits.
Per 1 OM-54.1.A, Station Logs, which one of the following describes how this is required to be documented in the L5 log?
A. Circle all readings in red pen that are not in compliance. Unit Supervisor must initial the L5 log in the time column next to the unsatisfactory check.
B. Circle all readings in red pen that are not in compliance. Details of the unsatisfactory check must be documented in the remarks section. Unit Supervisor must review the log at least once every shift.
C. Mark 'UNSAT' in the time column opposite the unsatisfactory check.
Record details of the check in the remarks section. Unit Supervisor must review the log prior to end of shift.
D. Mark 'UNSAT' in the time column opposite the unsatisfactory check.
Record details of the check in the remarks section. Unit Supervisor must initial the L5 log in the time column next to the UNSAT comment.
33
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 034 Given the following:
- [IQS-MR-1A], Refueling Water Refrigeration Unit is 'ON'.
- One refueling water recirculation pump is running in 'SLOW'.
- [TS-1 QS200A2], Refrigeration Unit Operating Thermostat is actuated.
Using the diagram provided, which one of the following describes the status of the refueling water refrigeration unit?
[1QS-MR-IA], Refueling Water Refrigeration Unit is...
A. started, and liquid line solenoid is energized to open.
B. stopped, and liquid line solenoid is energized to close.
C. started, and liquid line solenoid is deenergized to open.
D. stopped, and liquid line solenoid is deenergized to close.
34
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 035 Given the following conditions:
- The Unit has been at 100% power for 3 weeks. All systems are in NSA.
- A controlled power reduction to 50% is to be performed.
Using the references provided and maintaining control rods at their current position, which one of the following describes the MINIMUM amount of boric acid required to initially maneuver the plant to 50% power?
A. 900 gallons B. 1100 gallons C. 1300 gallons D. 1500 gallons 35
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 036 When performing an OST, which one of the following conditions PROHIBITS the use of 'N/A' in the sign-off spaces provided?
A. Performance of partial tests.
B. Inability to perform the OST as written.
C. Performing an OST that pre-establishes conditions for non-performance of steps.
D. Performance of steps that cannot be performed due to plant conditions, but do not change the intent of the procedure.
36
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 037 Given the following conditions:
- A reactor startup is in progress.
- Control Bank A"N withdrawal is in progress.
- The last two I/M plots indicate that criticality will be achieved on Control Bank "B"at approximately 100 steps.
- Estimated Critical Position is Control Bank "C"at 144 steps.
Per 1 OM-50.4.D, Reactor Startup From Mode 3 To Mode 2, which one of the following actions is required for these conditions?
A. Trip the reactor and initiate emergency boration.
B. Stop the startup and determine whether criticality will be within 500 pcm of the ECP prior to proceeding.
C. Insert all control banks to zero steps, verify shutdown margin and recalculate the ECP.
D. Continue the startup to obtain one additional 1I/M data point to validate the accuracy of the plot.
37
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 038 Given the following conditions:
- The control rod full out position is 230 steps.
- The required bank overlap for the current fuel cycle is 102 steps.
During rod withdrawal, when Control Bank "B" reaches full out position, what will be the position of Control Bank "C"?
A. 000 steps B. 102 steps C. 128 steps D. 230 steps 38
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 039 The Unit Supervisor has directed a Unit shutdown based on RCS activity exceeding TS 3.4.8 limits.
In the event of a subsequent SGTR, which one of the following actions is designed to limit the release of radioactivity?
A. MSIVs are closed.
B. SG atmospheric dump valve setpoints are raised.
C. RCS is cooled down below 500 0 F.
D. Maximum condensate polishers are placed in service.
39
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 040 The Unit is in Mode 5. Preparations are being made to enter Containment.
Per I OM-44C.4.A, Containment Purge Supply And Exhaust System Startup, which one of the following describes the correct sequence for initiating a containment purge to the ventilation vent?
A. Open supply and exhaust dampers, start [IVS-F-5], CNMT Purge Exhaust Fan. If desired, start [1VS-HV-5], CNMT Purge Vent Sup Fan after ensuring the NORMAL/REFUELING control switch is in the 'NORMAL' position.
B. Open supply and exhaust dampers, start [1VS-F-5], CNMT Purge Exhaust Fan. If desired, start [1VS-HV-5], CNMT Purge Vent Sup Fan after ensuring the NORMAL/REFUELING control switch is in the 'REFUELING' position.
C. Start [1VS-F-5], CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers are open. Place the NORMAL/REFUELING control switch in the
'NORMAL' position, and start [1VS-HV-5], CNMT Purge Vent Sup Fan.
D. Start [1VS-F-5], CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers are open. Place the NORMAL/REFUELING control switch in the
'REFUELING' position, and start [1VS-HV-5], CNMT Purge Vent Sup Fan.
40
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 041 Who, by title, can authorize a person to receive a radiation dose in excess of the Beaver Valley Administrative TEDE limits per 1/2-ADM-1 631, Exposure Control?
A. Site Senior Vice President B. Plant General Manager C. Superintendent, Operations D. Manager, Health Physics 41
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 042 The Unit is at 97% power. All systems are in NSA.
The RO withdraws control rods 2 steps for Tavg control. When the In-Hold-Out switch is released, rod motion continues.
The following alarms are received:
- [A4-46], Tavg Deviation from Tref
- [A4-51], Loop Tavg High The rod motion stops prior to any operator action occurring.
Which one of the following describes an INITIAL reactivity effect of the rod motion?
A. The positive reactivity added by FTC and MTC result in a higher total power defect.
B. The negative reactivity added by FTC and MTC result in a higher total power defect.
C. The positive reactivity added by FTC and MTC result in a lower total power defect.
D. The negative reactivity added by FTC and MTC result in a lower total power defect.
42
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 043 Given the following conditions:
The Unit is at 100% power with all systems in NSA.
- [A4-97], ROD CONTROL SYSTEM NON-URGENT ALARM illuminates.
- [A4-126], ROD BOTTOM ROD DROP is illuminated.
- One Control Bank "D" rod is indicating '0' steps.
- The RO places rod control in 'MANUAL'.
- Other Control Room annunciators illuminate as expected for plant conditions.
- Reactor power indicates as follows:
o N41 -100.1%
o N42- 103.3%
o N43- 100.1%
o N44-94.7%
Which one of the following interlocks or protective features must be cleared before automatic rod withdrawal may be reinstated?
A. The Rod Control System Non-Urgent condition must be cleared.
B. The 'Loop OP Delta T Auto Turbine Runback Block Auto Rod Withdrawal' circuitry must be reset.
C. The 'NIS Power Range High Setpoint Overpower Rod Stop Block Auto Rod W/D' must be cleared.
D. The 'Power Range Channel Deviation' must be cleared at the NIS Comparator and Rate Drawer.
43
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 044 Given the following conditions:
A load rejection has occurred from 100% power. The plant has stabilized at 82%
power.
"* The RO determines that 2 Control Bank "D"rods did not move during the load rejection.
"* The rods are approximately 16 steps above the remainder of Control Bank "D".
"* The Rod Control System Urgent Failure and Non-Urgent Failure alarms are NOT lit.
Which one of the following describes the required action for this condition?
A. Initiate a boration to increase shutdown margin by an amount equal to the stuck rod worth, and align the remainder of Control Bank "D"rods with the stuck rods.
B. Initiate boration to increase shutdown margin by an amount determined by the shutdown margin OST and commence a plant shutdown to Mode 3.
C. Trip the reactor and initiate safety injection to borate the RCS to achieve adequate shutdown margin.
D. Trip the reactor and commence emergency boration in accordance with FR-S.1, Response To Nuclear Power Generation/ATWS.
44
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 045 The Unit is at 60% power.
- [1SI-P-1A], LHSI Pump is out of service.
- [1 QS-P-1 A], Quench Spray Pump is out of service.
A Large Break LOCA occurs. The operating crew takes action in accordance with E-I, Loss Of Reactor Or Secondary Coolant.
The following conditions currently exist:
- Containment pressure 32 psig, DECREASING slowly
- RCS pressure 100 psig, STABLE
- Pressurizer level Offscale LOW All actuations have occurred as required.
With the reference provided, if the RWST was at its minimum level for operability when the event occurred, what is the approximate MINIMUM time before transition to ES-1.3, Transfer To Cold Leg Recirculation is required?
A. One hour B. Two hours C. Three hours D. Four hours 45
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 046 Which one of the following describes the operation of RCPs during the performance of FR-C.1, Response To Inadequate Core Cooling?
A. If RCPs are available, they are started early in the event to provide forced flow ONLY if seal injection and CCR are available.
B. If RCPs are available, they are started early in the event to provide forced flow EVEN IF seal injection and CCR are NOT available.
C. At least I RCP is started to provide forced flow and mixing of RCS water after secondary depressurization has resulted in Sl accumulator injection.
D. At least 1 RCP is started to provide forced flow of the RCS when secondary depressurization is ineffective in restoring adequate core cooling.
46
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 047 Given the following conditions:
- An ATWS has occurred.
- The operating crew is performing the actions of FR-S.1, Response To Nuclear Power Generation/ATWS.
- The RO has initiated emergency boration.
- All equipment has operated as designed.
- SI is NOT actuated.
- RCS pressure is 2210 psig and trending DOWN.
- Tavg is 5670 F and trending DOWN.
Which one of the following describes plant response to initiation of the boration?
A. Boric Acid Tank level will drop at a rate approximately equal to charging flow.
B. Volume Control Tank level will drop at a rate approximately equal to charging flow.
C. Refueling Water Storage Tank level will drop at a rate approximately equal to charging flow.
D. Pressurizer level will rise at a level approximately equal to charging flow.
47
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 048 Given the following conditions:
- The Unit is in Mode 5.
S[I CC-E-1 A], CCR Heat Exchanger is in service.
- [TCV-1 CC-100], CCR Temperature Control Valve is in 'MANUAL'.
- The operating CCR pump trips on overcurrent.
- There are no CCR pumps in standby.
Prior to any action by the operating crew, which one of the following describes system temperature response at the outlet of 1CC-E-1A over the next 10 seconds?
A. River Water temperature will RISE.
CCR temperature will RISE.
B. River Water temperature will DROP.
CCR temperature will DROP.
C. River Water temperature will RISE.
CCR temperature will DROP.
D. River Water temperature will DROP.
CCR temperature will RISE.
48
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 049 Given the following conditions:
"* Reactor Trip testing is in progress on Train "A.
"* Reactor Trip Breaker uA" is open.
"* Reactor Trip Bypass Breaker "A" is closed.
"* A transient occurs requiring a reactor trip.
"* The RO attempts to manually trip the reactor but the reactor does NOT trip.
Which one of the following describes a failure that has contributed to the reactor trip failure?
A. Reactor Trip Breaker "B" Undervoltage Trip coil failed to energize.
B. Reactor Trip Breaker "B" Shunt Trip coil failed to deenergize.
C. Reactor Trip Bypass Breaker "A" Undervoltage Trip coil failed to deenergize.
D. Reactor trip Bypass Breaker "B" Shunt Trip coil failed to energize.
49
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 050 Given the following conditions:
"* The Unit is operating at 80% power when air leakage into the condenser resulted in a rising condenser backpressure.
"* A load reduction is initiated at a rate of 5% per minute in accordance with AOP-1.51.1, Emergency Shutdown.
"o Five minutes after the load reduction was commenced, condenser backpressure has risen to 5.5 In. Hg. Abs.
"o Ten minutes after the load reduction was commenced, condenser backpressure has risen to 6 In. Hg. Abs. and is continuing to slowly rise.
What operator action is required?
A. Trip the reactor and go to E-0, Reactor Trip Or Safety Injection.
B. Trip the turbine and go to AOP-1.26.1, Turbine And Generator Trip.
C. Continue the load reduction and place a priming ejector (Hogger) into service.
D. Continue the load reduction. A priming ejector (Hogger) should not be placed into service.
50
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 051 Given the following conditions:
"* A loss of power to 120 VAC Vital Bus IIhas occurred.
"* The operating crew is attempting to restore power to the bus.
Per 1OM-38.4.AAC, Vital Bus IITrouble, which one of the following describes the reason for placing the Vital Bus Transfer Toggle Switch in the 'TO BYPASS' position under these circumstances?
A. Allows operation of the inverter manual bypass switch.
B. Provides for manual transfer of the inverter static switch.
C. Bypasses the inverter synchronization relay to allow re-energization of the inverter from its normal source.
D. Isolates the inverter static switch from the alternate power source in the case of a vital bus inverter failure.
51
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 052 Annunciator [Al 1-123], MOTOR DRIVEN FIRE PUMP RUNNING is in alarm and is valid. This indicates a fire in which one of the following areas:
A. Main Transformer B. Cable Tray Mezzanine C. Diesel Generator Building "A7 D. Turbine Generator Bearings and Enclosure 52
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 053 Given the following conditions:
- A small fire has developed in the Control Room.
- The Shift Manager has determined that a Control Room evacuation is required.
- A manual reactor trip has been initiated and all control rods have been verified fully inserted.
Which one of the following describes the MINIMUM action required to verify Turbine Trip?
A. Verify turbine throttle valves all closed or verify governor valves all closed prior to exiting the Control Room.
B. Verify turbine throttle valves all closed and verify governor valves all closed prior to exiting the Control Room.
C. Verify turbine throttle valves all closed or verify governor valves all closed in the Turbine Building prior to manning the Emergency Shutdown Panel.
D. Verify turbine throttle valves all closed and verify governor valves all closed in the Turbine Building prior to manning the Emergency Shutdown Panel.
53
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 054 Given the following conditions:
- The Unit was operating at 100% power.
- A Reactor Trip occurred due to a LOCA.
- All Safety Injection Systems FAILED to operate.
- FR-C.1, Response To Inadequate Core Cooling has been entered.
"o The Unit Supervisor has directed the depressurization of all intact SGs to 150 psig using the condenser steam dumps.
"o All MSIVs are open and the condenser is available.
"o The steam dump controller (AM-1 MS-464B) is in manual.
"o The steam dump control mode selector switch is in the STM PRESS position, and SG depressurization is underway.
"o PRZR pressure is > 1950 psig, and the Block Steamline SI Switches have NOT been placed in the 'BLOCK' position.
"o As the SG depressurization progresses, the steam flow automatically stops.
Which one of the following has caused the steam flow to stop?
A. Steam generator pressure has reached 150 psig, or containment isolation due to exceeding 1.5 psig pressure setpoint in containment.
B. Steam header pressure has dropped below the setpoint on AM-1 MS-464B, or Tavg is below 541 OF and no action has been taken to defeat the Tavg interlock.
C. Tavg is below 541 OF and no action has been taken to defeat the Tavg interlock, or main steamline isolation due to exceeding the low steam pressure rate sensitive setpoint.
D. Containment isolation due to exceeding 1.5 psig pressure setpoint in containment, or steam header pressure has dropped below the setpoint on AM-1 MS-464B.
54
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 055 Given the following conditions:
- A Reactor Trip and Safety Injection have occurred.
- The operating crew was performing the actions of E-1, Loss Of Reactor Or Secondary Coolant.
- The Unit Supervisor was concerned about conflicting indications and entered ES-0.0, Rediagnosis.
- There is an increasing trend on [RM-1MS-101], Auxiliary Feed Pump Turbine Exhaust Monitor and [RM-1 MS-I OOA], Main Steam Safety Valve Effluent Monitor.
Which one of the following describes how the operating crew will transition to the correct procedure?
A. Go directly to the appropriate E-3 or ECA-3 series procedure.
B. Return to E-0 diagnostic steps to verify indications that will confirm the event in progress.
C. Return to E-1 step in effect and use the Symptomatic Response/Unexpected Conditions page to direct entry to E-3.
D. Direct Chemistry sample of SGs to confirm radiation monitor readings prior to making a determination of appropriate procedure entry.
55
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 056 Given the following conditions:
- A Main Steam line Break has occurred.
- All equipment actuated as required.
- The operating crew has isolated the faulted SG.
- SI, CIA, and CIB have been reset.
- RCS pressure is 1775 psig and rising slowly.
- There are NO other indications of RCS leakage.
Which one of the following describes the sequence of steps to terminate SI?
A. Stop 1 HHSI pump.
Check RCS pressure stable and align normal charging.
Stop BOTH LHSI pumps.
B. Stop 1 HHSI pump.
Check RCS pressure stable and align normal charging.
Stop 1 LHSI pump. Ensure RCS pressure remains stable, then stop the second LHSI pump.
C. Align normal charging.
Check RCS pressure stable and stop 1 HHSI pump.
Stop BOTH LHSI pumps.
D. Align normal charging.
Check RCS pressure stable and stop I HHSI pump.
Stop 1 LHSI pump. Ensure RCS pressure remains stable, then stop the second LHSI pump.
56
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 057 Given the following conditions:
- A Small Break LOCA has occurred outside containment.
- ECA-1.2, LOCA Outside Containment has been entered.
- RCS pressure is slowly dropping.
- One HHSI pump is injecting.
As valves are being closed in an effort to identify and isolate the leak, a second HHSI pump is made available; the pump is started and is injecting.
RCS pressure begins slowly rising.
Which one of the following is correct regarding adherence to the EOPs?
The operating crew is to...
A. continue in ECA-1.2 until Mode 4 can be entered.
B. continue in ECA-1.2 until break isolation is verified using other means.
C. exit ECA-1.2 and transition to E-A, Loss Of Reactor Or Secondary Coolant.
D. exit ECA-1.2 and transition to ECA-1.1, Loss Of Emergency Coolant Recirculation.
57
BVPS-1LOT5 NRC EXAM Reactor Operator Question 058 The Unit is operating at 100% power when the following conditions occur:
- A PRZR spray valve sticks open and PRZR pressure has lowered to 1800 psig.
- Reactor Trip Breakers are 'SHUT'.
- Neutron flux is NOT dropping.
Which one of the following describes an Immediate Manual Action?
A. Verify auxiliary feedwater status.
B. Verify main steam line isolation.
C. Isolate condenser steam dump valves.
D. Initiate emergency boration of the RCS.
58
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 059 Pressurizer Relief Tank pressure indicates 15 psig on PI-1 RC-472. The operating crew suspects that a PORV opened inadvertently and is now stuck partially open.
Which one of the following indications confirm that a PORV is stuck partially open?
0 A. PORV relief line temperature stabilized at 213 F. PRZR safety relief line temperatures indicate 180 0 F and very slowly rising.
0 B. PORV relief line temperature stabilized at 250 F. PRZR safety relief line temperatures indicate 217°F and very slowly rising.
0 C. PORV relief line temperature stabilized at 213 F. PRZR safety relief line temperatures indicate 11 0°F and stable.
0 D. PORV relief line temperature stabilized at 250 F. PRZR safety relief line temperatures indicate 11 0°F and stable.
59
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 060 Given the following conditions:
- The Unit is at 100% power, steady state. All systems are in NSA.
- Pressurizer level is on program and stable.
- Pressurizer pressure is 2235 psig and stable.
- Charging flow on FI-CH-122 indicates 90 GPM.
A malfunction results in the loss of Pressurizer heaters. When heaters are restored, the following conditions exist:
- Pressurizer level is on program and stable.
- Pressurizer pressure is 2000 psig.
Which one of the following describes the approximate value for charging flow indication on FI-1 CH-1 22?
A. 0 GPM B. 80 GPM C. 90 GPM D. 100 GPM 60
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 061 Given the following conditions:
- A reactor startup is in progress.
11 amps.
- Both Intermediate Range channels indicate approximately 5 E-
- Source Range Channel N-31 fails DOWNSCALE.
Which one of the following describes the required operator response and the reason for the response?
A. Suspend the reactor startup; with only one source range channel operable, the minimum required Source Range High Flux Trip protection is not met.
B. Continue the reactor startup; with only one source range channel operable; 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to restore two channels to service.
C. Suspend the reactor startup; source range channels are not required to trip the reactor; however, the source range monitoring functions must be available.
D. Continue the reactor startup; the Intermediate Range Neutron Flux Trip and the Power Range Neutron Flux-Low Trip provide the necessary core protection.
61
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 062 Given the following conditions:
- A Small Break LOCA has occurred.
- Safety Injection pumps have been stopped.
- Normal charging is aligned.
- The crew is depressurizing the RCS using normal spray.
Which one of the following describes the strategy and the basis for the continuing depressurization?
A. Maximize subcooling to ensure continued RCP operation.
B. Minimize subcooling to reduce RCS break flow.
C. Maximize subcooling to prevent a challenge to the Core Cooling Critical Safety Function.
D. Minimize subcooling to ensure Pressurizer level remains above the lower limit to allow heater operation during the RCS cooldown.
62
NRC EXAM BVPS-1 LOT5 BVPS-1 LOT5 NRC EXAM Reactor Operator Question 063 Given the following conditions:
The Unit is at 100% power. All systems are in NSA.
The following alarms are received in the Control Room:
((RM-1 SV-1 00], Condenser Air Ejector Vent High
- [RM-BD-101], High Capacity SG Blowdown High-High
((RM-1 MS-1 02A], N-16 Steam Generator "A" Leak Monitor High-High RM-BD-1 01 and RM-1 MS-1 02A are stable at or near their alarm setpoints.
RM-1 SV-1 00 is stable above the High alarm setpoint.
Which one of the following describes the significance of the alarm status listed above?
A. The two radiation monitors in High-High alarm provide the threshold for tripping the reactor and initiating Safety Injection.
B. The alarm status of the radiation monitors give an approximate value for RCS primary-to-secondary leak rate.
C. The rate of increase of any of the three radiation monitors provides the threshold for tripping the reactor and initiating Safety Injection.
D. The alarm status of the radiation monitors determines the course of action taken for charging and letdown to provide an accurate estimate of the leak rate.
63
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 064 Given the following conditions:
"* The Unit was operating at 100% power when a Reactor Trip occurred on low Pressurizer pressure.
"* A Steam Generator Tube Rupture was diagnosed and E-3, Steam Generator Tube Rupture was entered.
"* E-3, Step No. 31, "Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage" is being performed (attached).
Given the following control room indications:
- SG "C" blowdown sample indicates high radiation.
- SG "C"NR level is 32% and dropping.
- Feed flow has been isolated to SG "C".
- SG "A" and "B"levels are slowly lowering.
- PRZR level is 63% and rising.
Which one of the following describes the operator action?
A. Depressurize RCS.
B. Lower charging flow.
C. Turn on PRZR heaters.
D. Depressurize RCS and lower charging flow.
64
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 065 The Unit is at 50% power during a power increase to 100%.
The following alarms are received in the Control Room:
1IA, IB, IC SG Level Deviation 1IA, 1B, 1C SG Level Low The PO determines the following for all 3 SGs:
- SG level is DECREASING.
- Steam flow is STABLE.
- Feed flow is DECREASING.
- Feedwater Regulating Valve positions are all going OPEN.
Assuming NO action has been taken by the operating crew, which one of the following events is the cause of these indications?
A. Secondary Load Rejection B. Loss of Feedwater C. [PT-1 MS-446], First Stage Pressure Transmitter failed LOW D. [PT-1 MS-446], First Stage Pressure Transmitter failed HIGH 65
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 066 The Unit is operating at 60% power when the following alarms are received.
- [A9-100], 125VDC BATTERY CHGR 1 FAILURE
- [A9-98], 125VDC BUS 1 VOLTAGE LOW Several minutes after the alarms are received:
- The Unit continues to operate at 60% power.
- Control power remains available to EDG No.1 and 4160V Bus "IAE".
1125VDC BUS 1 voltage indicates approximately 124VDC.
- [BAT-CHGI -1], Station Battery Charger Breaker has been verified closed and 480V MCC1 -E9 is energized.
For the given indications, which one of the following describes the 125VDC Bus I status?
A. Station Battery has failed. Battery Charger 1 is supplying the bus.
B. Battery Charger 1 has failed. Station Battery is supplying 125VDC Bus 1.
C. Station Battery and Battery Charger 1 have failed. 125VDC Bus 1 is deenergized.
D. Battery Charger I and Station Battery are operating normally. Battery Charger 1 is supplying 125VDC Bus 1.
66
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 067 Given the following conditions:
- The Unit was operating at 100% power when a steam line break occurred.
- A high containment pressure condition resulted in a Reactor Trip signal.
However, the reactor failed to trip automatically or manually.
- All other equipment functions as designed.
- Containment pressure is 3.5 psig and RISING.
- The operating crew is performing actions of FR-S.1, Response To Nuclear Power Generation/ATWS.
Which one of the following describes the plant status when verifying emergency boration is established?
A. One charging pump running; [MOV-1 CH-350], Emergency Boration Isolation Vlv 'OPEN'; Boric Acid Transfer Pump [1 CH-P-2A (21B)] in 'FAST' speed.
B. Two charging pumps running; [MOV-1CH-350], Emergency Boration Isolation Vlv 'OPEN'; Boric Acid Transfer Pump [1 CH-P-2A (2B)] in 'FAST' speed.
C. One charging pump running; [MOV-1 CH-1 15B (D)], RWST to Chg Pumps Suct Vlv 'OPEN'; [MOV-1 CH-1 15C (E)], VCT Outlet to Chg Pumps Suct Vlv 'CLOSED', and [MOV-1SI-867A, C, (B)(D)], BIT Isol VIvs 'OPEN'.
D. Two charging pumps running; [MOV-1CH-1 15B (D)], RWST to Chg Pumps Suct Vlv 'OPEN'; [MOV-1 CH-1 15C (E)], VCT Outlet to Chg Pumps Suct Vlv 'CLOSED', and [MOV-1 SI-867A, C, (B)(D)], BIT Isol Vlvs 'OPEN'.
67
NRC EXAM BVP S-I LOT5 BVPS-1 LOT5 NRC EXAM Reactor Operator Question 068 Given the following conditions:
- A loss of heat sink has occurred.
- The operating crew is establishing RCS 'Bleed and Feed' in accordance with FR-H.1, Loss Of Secondary Heat Sink.
Which one of the following describes the consequences of the PORV failures?
A. A Red Path on the Core Cooling Critical Safety Function will develop due to loss of RCS inventory with no available makeup.
B. RCS 'Feed and Bleed' cooling must be established to ensure sufficient SI flow at the operable PORV setpoint.
C. The RCS may not depressurize quickly enough to ensure sufficient SI flow to provide RCS heat removal, and other RCS openings may have to be established.
D. 'Bleed and Feed' cooling of the RCS must be terminated and secondary depressurization to inject condensate pump flow must be immediately initiated.
68
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 069 Given the following conditions:
- The Unit is in Mode 6. All systems are in NSA.
- Refueling in progress. The Containment equipment hatch is closed.
"o [RIS-1RM-104A], Containment Purge Exhaust Monitor is in High-High alarm.
"o Containment Purge Supply and Exhaust Fans trip.
"o Containment Evacuation Alarm is sounding.
Which one of the following indications will provide direct confirmation of the event in progress?
A. [RIS-1 RM-215A], Containment Particulate Monitor B. [RIS-1VS-103A], Fuel Building Ventilation Exhaust Monitor C. [RIS-1VS-107A], Elevated Release Particulate Monitor D. [RM-1 RM-218A], Control Room Radiation Monitor 69
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 070 As directed by ECA-0.0, Loss Of All AC Power, the operating crew places the charging pumps in Pull-To-Lock.
The defeat of the charging pump automatic start is to prevent...
A. an uncontrolled over-pressurization of the RCS, and the resulting increased loss of RCS inventory through the RCP seals when power is restored.
B. an excessive cooldown of the RCS due to injection of cold RWST water when power is restored.
C. the unnecessary use of water that may be needed for long term recovery.
D. a LOCA caused by thermal shock of the RCP seals when power is restored.
70
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 071 The Unit is operating at 100% power, NSA when the following alarms are received:
[PI-1 SA-1 01A/B], Station Air Compressor Receiver Pressures indicate 85 psig, and
[PI-1 SA-101], Station Air Main Header Pressure indicates 80 psig and stable.
Which one of the following indicates the plant response?
A. Both station air compressors running; [TV-1SA-105], Station Air Header Isolation Valve open.
B. One station air compressor running; [TV-1 SA-1 05], Station Air Header Isolation Valve open.
C. One station air compressor running; [TV-1 SA-1 05], Station Air Header Isolation Valve closed.
D. Both station air compressors running; [TV-1 SA-1 05], Station Air Header Isolation Valve closed.
71
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 072 The Unit is operating at 100% power when BOTH of the running condensate pumps trip.
Which one of the following describes the Main Feed Pump response?
A. 1FW-P-1A and 1FW-P-1B trip immediately.
B. 1FW-P-1A and IFW-P-1B trip after an 8 second delay.
C. 1FW-P-1 A trips after an 8 second delay; 1FW-P-1 B trips immediately.
D. 1FW-P-1 B trips after an 8 second delay; 1FW-P-1 A trips immediately.
72
NRC EXAM BVPS-1 LOTS BVPS-1 LOT5 NRC EXAM Reactor Operator Question 073 Given the following conditions:
- The Unit is operating at 90% power. All systems are in NSA.
"* "A" Main Feed Pump has tripped.
- The PO determines that the heater drain pumps and condensate pumps are operating normally.
Which one of the following actions is required in accordance with AOP-1.24.1, Loss Of Main Feedwater?
A. Trip the reactor and enter E-0, Reactor Trip Or Safety Injection.
B. Reduce turbine load to less than 60% in accordance with AOP-1.51.1, Emergency Shutdown.
C. Check the proper operation of [FCV-1 FW-1 50A], Main Feed Pump "A" Recirculation Valve.
D. Determine if suction pressure is adequate to attempt restart of "A" Main Feed Pump.
"73
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 074 Which one of the following will automatically trip [1 FW-P-1 A], Main Feedwater Pump?
A. 2 out of 3 Lo-Lo level in any SG.
B. Reactor Trip coincident with Low Tavg.
C. 1FW-P-1A lube oil pressure at 4 psig.
D. [MOV-1 FW- 50A], FW Pump Discharge Valve shut.
74
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 075 While shutting down the plant during severe weather conditions, a Reactor Trip occurs from 90% power due to a loss of power to the Unit Station Service Transformer.
The following conditions exist.
- The plant is in natural circulation.
- MSIVs are closed.
- All SG wide range levels are approximately 35%.
Assuming NO operator action, if [MOV-1 FW-1 51 E], Auxiliary Feed Throttle Valve begins drifting open, the initial response of SG pressure is to and level rise above 81%.
A. drop; will B. drop; will not C. rise; will not D. rise; will 75
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 076 A Reactor Trip occurs from 100% power due to a loss of main feedwater.
The following conditions exist:
"* All RCPs are running.
"* The turbine driven AFW pump is in service feeding all 3 SGs.
"* Both motor driven AFW pumps tripped upon startup and remain unavailable.
"* The turbine driven AFW pump speed has begun to slowly lower due to a malfunctioning governor.
Which one of the following describes the impact on Pressurizer level ifthe turbine driven AFW pump speed CONTINUES to lower?
Pressurizer level...
A. rises due to increased primary to secondary heat transfer.
B. rises due to decreased primary to secondary heat transfer.
C. lowers due to increased primary to secondary heat transfer.
D. lowers due to decreased primary to secondary heat transfer.
76
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 077 Given the following conditions:
"* Unit 1 is at 100% power. All systems are in NSA.
", A batch discharge of the contents of [1 LW-TK-7A], Steam Generator Drain Tank 7A is in progress.
"* [RM-1 LW-1 04A], Liquid Waste Effluent Monitor has generated a High High radiation signal.
How will this affect the Liquid Waste Disposal System?
A. The Liquid Waste Effluent Trip Valve, TV-LW-1 05 receives an open signal and the Liquid Waste Effluent Low Range Flow Control Valve, FCV-LW 104-1 closes.
B. The running steam generator drain tank pump will stop and the Liquid Waste Effluent Low Range Flow Control Valve, FCV-LW-1 04-1 closes.
C. The running steam generator drain tank pump will stop and the Liquid Waste Effluent High Range Flow Control Valve, FCV-LW-104-2 closes.
D. Both the Liquid Waste Effluent High and Low Range Flow Control Valves, FCV-LW-104-1 and FCV-LW-104-2 and the Liquid Waste Effluent Trip Valve, TV-LW-105 receive a signal to close.
77
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 078 Unit I is operating at 100% with all systems in NSA.
- Unit 2 waste gas surge tank is being transferred to [1 GW-TK-1 B], Unit 1 Waste Gas Decay Tank.
. [A2-25], GASEOUS WASTE DECAY TANK 1 B PRESSURE HIGH is alarming.
0 1 GW-TK-1 B pressure indicates 65 psig.
Per 1OM-1 9.4.B, Running With Unit 2 GW Surge TK Aligned To Unit 1 GW Decay Tk, which one of the following actions is required and why?
A. Place GW-TK-1A in service to prevent the Unit 2 overhead gas compressor from stalling.
B. Place GW-TK-1 C in service to prevent overpressure on the Unit 2 waste gas surge tank.
C. Place GW-TK-1A in service to maintain 02 analyzer within its operating limits.
D. Place GW-TK-1 C in service to equalize pressure and reseat 1GW-TK-1 B relief valve.
78
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 079 Given the following conditions:
- Unit 1 is in Mode 4.
- A Unit shutdown is in progress.
S[1 GW-TK-1 B], Waste Gas Decay Tank discharge is in progress.
- [RM-1 GW-1 08A], Radiation Monitor is in High-High alarm.
Which one of the following will occur?
A. [TV-1 GW- 03B2], GW Decay Tank Bleed Valve closes.
[FCV-1 GW-1 05], Decay Tank Bleed Control Valve closes.
B. [TV-1 GW- 03], GW Tank Discharge To Cooling Tower Valve closes.
[TV-1 GW- 1 OB], GW Decay Tank Sample Valve closes.
C. [TV-1 GW- 03B2], GW Decay Tank Bleed Valve closes.
[rV-1 GW- 03], GW Tank Discharge To Cooling Tower Valve closes.
D. [TV-1GW-103B2], GW Decay Tank Bleed Valve closes.
[TV-1 GW-1 OB], GW Decay Tank Sample Valve closes.
79
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 080 A precaution contained in 1OM-1 7.2.A, Liquid Waste Disposal System states that two tanks containing radioactive liquid cannot be discharged at the same time.
Which one of the following describes the reason for this precaution?
A. The discharge permit for discharging the contents of a liquid waste tank is based upon a dilution rate which includes cooling tower blowdown rate of both units.
B. Pipe size restrictions in the effluent line could result in an overpressure condition if more than 1 waste tank pump is in operation.
C. The limit prevents excessive wear on the foot valve in the discharge structure due to high flow rates.
D. The common discharge point is only provided with a limited amount of dilution flow from the Unit 1 cooling tower blowdown.
80
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 081 The Unit is operating at 100% power, NSA when a HIGH radiation signal is received on [RM-1 RM-218A (8)], Control Room Area Monitors.
Which one of the following describes the component response for the Unit 1 Control Room Ventilation System?
A. One Control Room Emergency Supply Fan, 1VS-F41A (B) starts immediately.
B. The Control Room Air Intake Dampers, 1VS-D-40-1A (B) shut immediately.
C. One Control Room Emergency Supply Fan, 1VS-F41A (B) starts after a time delay.
D. The Control Room Air Exhaust Dampers, 1VS-D-40-1C (D) shut after a time delay.
81
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 082 Given the following conditions:
- A Reactor Trip from 100% power has occurred as a result of a Small Break LOCA.
- HHSI pumps are running.
- LHSI pumps are running.
- Quench Spray pumps are running.
Subsequently, a fault on 125V DC Distribution Panel 2 results in a loss of 125V DC power to all loads serviced by the panel.
Which one of the following describes the impact on the AC electrical system?
4KV loads on 4160V Bus...
A. "IDF" immediately trip; loads on 4160V Bus "IAE" also immediately trip.
B. "IAE" continue to operate; loads on 4160V Bus " DF" also continue to operate.
C. "I DF" continue to operate; however, loads on 4160V Bus "IAE" immediately trip.
D. "IAE" continue to operate; however, loads on 4160V Bus "1DF" immediately trip.
82
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 083 Given the following conditions:
- The Unit is at 100% power with all systems in NSA.
- 4KV Bus "IAE"feeder breaker "lA0"tripped open.
- No faults exist on the "IAE" bus.
- No. 1 EDG failed to start manually or automatically.
After determining the cause of the EDG start failure, which one of the following actions is required prior to attempting to restart the No. 1 EDG?
A. Cycle the 125VDC control power to No. 1 EDG output breaker "1E9".
B. Cycle the No. 1 EDG manual start switch to 'STOP' and back to 'AUTO'.
C. Place the control switch for breaker "IAI0" in the 'OPEN' position.
D. Simultaneously depress both 'STOP' pushbuttons for No. 1 EDG.
83
BVPS-1LOT5 NRC EXAM Reactor Operator Question 084 Given the following conditions:
- Unit 1 is in Mode 6.
- Unit 2 is in Mode 1 with all systems in NSA.
- Movement of irradiated fuel is ongoing in the Unit 1 Containment.
- [RM-1 RM-218A], Control Room Area Monitor has failed LOW.
- The FAIL light for the radiation monitor is 'OFF'.
In accordance with Technical Specification 3.3.3.1 (attached), what action, if any, is required for the above conditions?
A. No action is required because the monitor is not required to be operable for this condition.
B. Within ONE hour the respective Unit 2 Control Room monitor train shall be verified operable.
C. Within ONE hour, verify that RM-1 RM-2118B, Control Room Area Monitor is operable.
D. Within ONE hour, suspend all operations involving movement of irradiated fuel.
84
BVP S-1 LOT5 NRC EXAM Reactor Operator Question 085 The following alarms are received in the Control Room:
- [All -65], DIESEL GEN BLDG A FIRE
- [All-81], DIESEL GEN BLDG A FIRE PROT SYSTEM TROUBLE Which one of the following describes the operation of the Fire Protection System?
The "A" Diesel Generator Building...
A. Sprinkler System will discharge immediately.
B. C02 System will discharge immediately.
C. Sprinkler System will discharge in 30 seconds.
D. C02 System will discharge in 30 seconds.
85
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 086 Given the following conditions:
- A load rejection has occurred.
- Reactor power is currently 65%.
- Tavg is 60 F higher than Tref.
How many banks of condenser steam dump valves will either be open or partially open?
A. 1 B. 2 C. 3 D. 4 86
LOT5 NRC EXAM BVPS-1 BVPS-1 LOT5 NRC EXAM Reactor Operator Question 087 Given the following conditions:
"* The Unit was operating at 28% power.
"* All offsite power was lost.
"* All equipment functioned as designed.
Which one of the following describes the approximate steady-state T-cold value 30 minutes following the loss of power?
A. 541OF B. 543 0 F C. 547 0 F D. 551OF 87
BVPS-1LOT5 NRC EXAM Reactor Operator Question 088 Given the following conditions:
- A Reactor Trip and Safety Injection have occurred.
- The crew is performing EOP Attachment 1-K, Verification Of Automatic Actions.
- CIB has just occurred.
If all equipment functions as designed, which one of the following describes the status of River Water System Pumps?
A. No pumps running.
B. One pump running.
C. Two pumps running.
D. Two pumps running with two Auxiliary River Water System pumps running.
88
BVPS-1 BVPS-1 LOT5 NRC EXAM Reactor Operator Question 089 With the Unit in Mode 1 and all systems in NSA, a loss of cooling water to the station air compressors will directly result in which one of the following?
A. Low cooling water pressure trip at less than 85 psig.
B. Low oil temperature trip at less than 175 0 F.
C. High outlet air temperature trip at greater than 4250 F.
D. High oil pressure trip at greater than 20 psig.
89
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 090 Given the following conditions:
- The Unit is in Mode 3. All systems are in NSA.
- The following annunciator is received in the Control Room:
o [A3-73], REACT COOL PP THERMAL BARRIER COOL WATER DISCH FLOW HIGH
Which one of the following describes the effect of this failure on the operation of "IA" RCP?
A. "IA" RCP must be tripped immediately.
B. TV-ICC-107A must be opened within 5 minutes or "IA" RCP must be tripped.
C. "IA" RCP must be tripped within 5 minutes regardless of TV-ICC-107A position.
D. "IA" RCP must be tripped only if seal injection is also lost for greater than 5 minutes.
90
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 091 Given the following:
- The reactor has failed to trip automatically when required and can NOT be manually tripped.
- The main turbine is tripped.
- All AFW pumps are running.
- Emergency boration is in progress.
- PRZR pressure is 2335 psig.
- The PRZR PORV's do NOT automatically open.
Which one of the following is the reason for reducing RCS pressure at this point in the transient?
A. To prevent the rapid RCS overpressurization transient expected with most ATWS events.
B. To minimize primary-to-secondary leakage until further recovery actions can be taken, in the case of the most limiting ATWS event, a SGTR.
C. To allow enough borated flow into the RCS to ensure the addition of negative reactivity to the core.
D. To add negative reactivity from the RCS pressure coefficient of reactivity as the RCS is depressurized.
91
LOT5 NRC BVPS-1 EXAM BVPS-1 LOT5 NRC EXAM Reactor Operator Question 092 An alarm is received in the Control Room. The instrument that feeds the alarm also feeds a system control action.
The operating crew believes that a false indication has caused the alarm.
Per 1/20M-48.1.D, Operations Shift Rules Of Practice, which one of the following describes the required response to the indication?
A. Do not believe the alarm indication. Ifthe control action is in the conservative direction, no action is necessary. Ifthe control action may result in a plant trip, take manual control of the system.
B. Believe the alarm indication. Ifthe control action is in the conservative direction, no action is necessary unless the instrument or alarm is determined to be false by at least two independent crew members.
C. Do not believe the alarm indication. Place the affected controller in manual and determine which failure has occurred in accordance with the Alarm Response Procedure.
D. Believe the alarm indication. Ifthe control action is in a conservative direction, no action is necessary unless two redundant instruments monitoring the same parameter determine that the control action is being caused by a failed instrument.
92
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 093 A Unit startup is in progress per 1OM-52.4.A, Raising Power From 5% To Full Load Operation when a loss of instrument air occurs. The operators are performing AOP-1.34.1, Loss Of Station Instrument Air when the main feedwater regulating valves close and a reactor trip occurs.
Which one of the following describes the procedure transitions for this event?
A. 1OM-52.4.A usage is suspended. AOP-1.34.1 is completed followed by entry to E-0, Reactor Trip Or Safety Injection.
B. 1OM-52.4.A usage is suspended. AOP-1.34.1 is performed until a RED or ORANGE path condition requires entry to a functional recovery procedure.
C. E-0, Reactor Trip Or Safety Injection is entered and exited when directed to another specific procedure. AOP-1.34.1 may be performed to aid in plant recovery.
D. ES-0. 1, Reactor Trip Response is entered and exited when directed to procedure and step in effect. AOP-1.34.1 may be performed to aid in plant recovery.
93
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 094 Per 1/20M-48.2.C, Adherence And Familiarization To Operating Procedures, when responding to multiple annunciators in the Control Room, which one of the following lists the alarm groups in order of highest to lowest priority?
A. First Out, RPS/ESF Signals, Radiation Monitors, Vital Busses B. RPS/ESF Signals, Radiation Monitors, Vital Busses, First Out C. Vital Busses, First Out, RPS/ESF Signals, Radiation Monitors D. First Out, Vital Busses, RPS/ESF Signals, Radiation Monitors 94
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 095 Given the following conditions:
- A Reactor Trip has occurred due to a loss of offsite power.
- The operating crew is performing actions of ES-0.2, Natural Circulation Cooldown.
- RVLIS is NOT available.
- The crew has commenced RCS depressurization to 1950 psig.
- RCS pressure is 2080 psig and trending DOWN.
- RCS Tavg is 5481F and STABLE.
- Pressurizer Level is 5% and trending DOWN.
Which one of the following actions will be required?
A. Continue depressurization to 1950 psig and block Safety Injection.
B. Initiate Safety Injection and go to E-0, Reactor Trip Or Safety Injection.
C. Stop the cooldown, Block SI, and initiate depressurization to 1950 psig.
D. Stop the depressurization and go to ES-0.4, Natural Circulation With Steam Void In Vessel (Without RVLIS).
95
EXAM BVPS-1 LOT5 NRC BVPS-1 LOT5 NRC EXAM Reactor Operator Question 096 Given the following conditions:
- The reactor has tripped due to a loss of offsite power.
- The operating crew has transitioned to ES-0.3, Natural Circulation Cooldown With Steam Void In Vessel (With RVLIS) due to steam void formation in the reactor vessel.
While performing this procedure, which one of the following conditions requires the crew to stop the cooldown and raise RCS pressure?
A. Pressurizer level rises to 90%.
B. RVLIS Dynamic Range indication drops below 100%.
C. RCS cooldown cannot be maintained less than 250 F/Hr.
D. RVLIS Full Range indication drops below 77%.
96
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 097 The Unit was at 100% power when the following occurs:
- Reactor Trip, all rods fully inserted.
- Loop 1 SG pressure is 400 psig and continuing to lower rapidly.
- Loop 2 and 3 SG pressures are stable at 800 psig.
- Containment pressure is 12 psig and rising.
Which one of the following describes the valves that are needed to operate to terminate steam flow?
A. [TV-1MS-101A], Main Steam Isolation Valve or [NRV-1MS-101A], Non Return Valve.
B. [rV-1MS-101A], Main Steam Isolation Valve or [NRV-1 MS-1 01B and C],
Non-Return Valves.
C. [-V-1MS-101B and C], Main Steam Isolation Valves or [NRV-1 MS-1 01A],
Non-Return Valve D. [TV-1 MS-1 01 B and C], Main Steam Isolation Valves or [NRV-1 MS-1 01 B and C], Non-Return Valves 97
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 098 Following a Small Break LOCA, the operating crew is performing actions of FR-P.1, Response To Imminent Pressurized Thermal Shock.
Which one of the following describes the difference in SI termination criteria for FR-P. 1 as opposed to the criteria in ES-i. 1, Safety Injection Termination?
The criterion in FR-P.1 is...
A. less restrictive to allow for a faster reduction in RCS pressure.
B. more restrictive to allow for a more controlled reduction in RCS pressure.
C. less restrictive because subsequent RCP restart is likely to cause propagation of any existing flaw in the reactor vessel walls.
D. more restrictive because subsequent RCP restart is likely to result in an increased RCS inventory loss.
98
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 099 The Unit was operating at 100% power when a Small Break LOCA in containment resulted in a Reactor Trip and Safety Injection actuation.
Which one of the following describes the SEQUENCE of automatic actions as Containment pressure increases, peaking at 11 psig?
A. CIB initiated; main steamlines isolated; Recirc Spray pumps started.
B. CIB initiated; Recirc Spray pumps started; main steamlines isolated.
C. Main steamlines isolated; CIB initiated; Recirc Spray pumps started.
D. Main steamlines isolated; Recirc Spray pumps started; CIB initiated.
99
BVPS-1 LOT5 NRC EXAM Reactor Operator Question 100 Given the following conditions:
A LOCA has occurred. Due to ECCS failures, the operating crew is performing the actions of FR-C.2, Response To Degraded Core Cooling.
The crew is depressurizing SGs to facilitate SI accumulator injection.
Which one of the following Critical Safety Functions could potentially exhibit a RED condition based upon the actions taken in FR-C.2?
A. Subcriticality B. Core Cooling C. Heat Sink D. Integrity 100
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Critical Boron Concentration vs Burnup HFP, ARO, Equilibrium Xenon Unit 1, Cycle 15 1,600
" 1,400
-o 1,200 m
, 800 (I) o 600 -44
., 400 200 "D CL (D bOY 4I/ Iv A,' ý, N' Nb NA N Cycle Burnup (MWD/MTU) 8
HZP Differential Boron Worth vs Boron Concentration Unit 1, Cycle 15
-6.5 150 MWD/MTU 10000 MWD/MTU
.-7.0 0.
18740 MWD/MTU m
E 0
w 00 0
0
'-8.0 0
I I -8.5 4 a~(
'V Oe oA V ~~
-9.0 CD 8
-9.5 CA)
ND Cil 0, Boron Concentration (ppm)
CD 0
CURVE BOOK - BVPS I CB-21 Record Type # A9.345D POWER DEFECT vs PERCENT POWER at BOL, MOL, and EOL Unit 1, Cycle 15
-3000 I II III II IA 0 ppm
-2800 200 ppm
-2600 I 1, 1. 1I 1I 1IAu I I I YI 400 ppm
-2400 - - ---- - - -
600 ppm 4 1 11
-2200 800 ppm If] I 1-1ý
-2000 u I 1000 ppm 1200 ppm "j -1800 CL -6K 04++ 9- 4+-:: 1400 ppm t-1600 I A I I M:
---- --- 1600 ppm 1800 ppm
-1400 2000 ppm 0 -1 6r] I I 1+hk 9+/- -
0- -1200 ........ +
+Hj+
IKE
-1000 X:o I AI I II II II I
-800 .. ... .. .. . IL I ... .. .. . I 1. , . 11 . . . . 1.
-600 t##
-400 -LLLLL
-200 0 HHHHH -------- :LL 0 10 20 30 40 50 60 70 80 90 100 Power Level (percent of full power)
FM TRAINING USE -ONLY Issue 15 Rev 0
Boron Worth vs Burnup ARO, HFP, Critical Boron Unit 1, Cycle 15
-6.2
. . . I I L I
-6.4
-6.6 C E -7.0
-7.2, .
00 3..7.4 C I I' N CC 0 -7.6 ----- i
-7.8 '" ".
-8.0 77E 0 C
CD) B n W... I I oC
-44%)
Burnup (MWD/MTU) 0RO
CURVE BOOK - BVPS 1 CB-30 Ri-cord Tvoe #9A.345D 1000 ---- 17.1 2000 900 i 15.1. 1900 32.6 800 13.7 1800 - 30.9 700 ---- 12.0 1700 -29.1 C
e C 600 10.3 o 1600 -
.-.-. 27.4.
' u F-I I-J C)
U LU 25-.7 500 -8.6 C) 1500 iF I,-, .I I-.
1100 6.9 '5 I400 - 24.0 C k-
,..J .UuJ C):
a1- -:-
C) 300 5.1 1300 22.3 200 3.04 1200 -20.6 100 1.71 1100 - -18.9 0' 0.0 1000 - 17.1 BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP i ISSUE 15 REV 0
CURVE BOOK- BVPS I CB-31
....3000 Record Type--#9A.345D 0
.700 600 1500 3600 3000 2500 V 4 17000-Ci2100 - 300 8.33 (7000-Cf/ 2100
- 100200 o -2000 I
-- 150 S 2000 1900 50~
- 1500 c 600 80 70 ca 60 0 - - 50
-1000 3000 30 50 150 .20
-- 15 10 00 BORON ADDITION (refer to figure CB-36 for correction factors)
(refer to 1OM-6.5.B.6, Table 6-6, "RCS Volume")
FOR TRAINING uE ONLY, DISSUE 15 REV 2 BYP UNT ~I
CURVE BOOK - BVPS I CB-32 Record Type #9A.345D
- iO 60 S100 500 55
- 50 300
- 500 '10 300 35 30 27
-1000 20( 2-*
21 dc aOOX (7000-C) dt 1H is1 I8--
s C
40 C
io -1500 100 - 12 IL I
90 80 S10 a-
-2000 70 40 d- 60
- 7 50 - 6
-2500 '10-
-S5 AA 2U5 25-
-3000 - 3 BORON ADDITION RATE.
(refer to figure CB-36 for correction factors)
(refer to IOM-6.5.B.6, Table 6-6, "RCS Volume")
FOR TRAINING USE I ONLY VISSUE 15 REV 2 BYP INT iI
CURVE BOOK - BVPS I CB-33 Record Type #9A.345D 10
- Is
- 20
- 30
- 40 8.33 In " Cl*f)
- 50
-- 60 80 100 1.
-200 2 3
2oo S
30 50-
-- 000 100 ISO0 200 300 5000
-2000
-3000 PPH BORON DILUTION PPM 8RON so (C - Cf) 0ILUTION IN COOLANT WATER GAL.
(Ci), (i ) -
BORON DILUTION (refer to figure CB-36 for correction factors)
(refer to IOM-6.5.B.6, Table 6-6, "RCS Volume")
- OR TRAINING USE ONLY CIOWNRLLED IBVpa MllT I]
ISSUE 15 REV 2
CURVE BOOK - BVPS I CB-34 Record Type #9A.3450 1- 3000 700- 200 2000 400 300 - so 1500 200 j so
-- 000
-- 10 00
-- o
-100
- 70 90 So00 s
_40 dc 500CY -- 80 30 dt N 70 20- 60 15 200 10 so I0-0
-- 00 q -
s0 30 60 2 0o 5 -.
-- 120 30 COOLANT DILUTION RATE PPMIHR
-- 20 (dc!4t) -- 15 Is 10 10 PPM BORON DILUTION WATER I1N COOLANT FLOW1.0P1 (C) M,)
BORON DILUTION RATE (refer to figure CB.36 for correction factors)
(refer to IOM-6.5.B.6, Table 6-6, "RCS Volume")
+ FORImMT iIN INGUSO1m UF+N- ILY
CURVE BOOK - BVPS I CB-36 Record Type #9A.345D NOMOGRAPH CORRECTION FACTORS I Plant Conditions Correction Factor Pressure T (AVG) (K)
(psig) (°F) Pressurizer Level (See Note)
I 2235 547-570 Normal Operating 1.00 1600 500 No-Load 1.05 1200 450 No-Load 1.10 800 400 No-Load 1.16 400 350 No-Load 1.18 400 300 No-Load 1.20 400 300 Solid Water 1.35 400 200 No-Load 1.28 400 200 Solid Water 1.40 400 100 Solid Water 1.47 NOTE: CORRECTION FACTORS ARE APPLIED AS FOLLOWS:
(a) Boron Addition and Dilution Total Volume Nomographs V(Corrected) = K x V(Nomograph)
(b) Boron Addition and Dilution Rate Nomographs dc I dc dt (Corrected) K x dt (Nomograph)
FOR TRAININGUSE ONLY ISSUE 15 REV 0
i Jo
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RI-q 0
OX 1 =4 N (Yb-fL --I v t;,Iivt I = --ýFC-W - -S,U/
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SYMPTOMATIC RESPONSE/UNEXPECTED CONDITIONS E-3 (Issue IC, Revision 2)
- 1. SI REINITIATION CRITERIA Manually operate SI pumps and align valves as necessary and GO TO ECA-3.1,
"*SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired", Step 1, if EITHER condition listed below occurs:
- On ICCM RCS subcooling based on core exit TCs - LESS THAN 46F [54F FOR ADVERSE CNMT] (If less, refer to Attachment 6-A)
.. PRZR level - CANNOT BE MAINTAINED GREATER THAN 18% [37% FOR ADVERSE CNMT]
- 2. SECONDARY INTEGRITY CRITERIA GO TO E-2, Faulted Steam Generator Isolation", Ste p 1, if any SG pressure is dropping in an uncontrolled manner or has completely depressurized, and has not been isolated unless needed for RCS cooldown.
- 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION GO TO ES-1.3, 'Transfer Cold Leg Recirculation", Step 1, if RWST level reduces to less than 19 FEET.
- 4. AFW SUPPLY SWITCHOVER CRITERION Monitor PPDWST CWT-TK-1O0 for AFW pumps supply. Upon reaching low level alarm, 27.5 FEET, refer to Attachment 2-H for makeup.
- 5. MULTIPLE TUBE RUPTURE CRITERIA RETURN TO E-3, "Steam Generator Tube Rupture", Step 1, if any intact SG level rises in an uncontrolled manner or any intact SG has abnormal radiation.
- 6. ADVERSE CONTAINMENT CRITERIA
-OR
- CNMT radiation on [RM-lRM-219A(B)] - GREATER THAN 1E+5 R/HR
-OR 0 Integrated CNMT radiation - GREATER THAN 1E+6 R FMTANNG USE ONL'
BVPS - EOP 1OM-53A. 1.E-3(ISS1C) i STEP] ACTION/EXPECTED RESPONSE j RESPONSE NOT OBTAINIED I CAUTION RCS and ruptured SGs pressures must be maintained less than the ruptured SGs atmospheric steam dump setpoint to prevent offsite releases.
NOTE When letdown is in service, charging flow should be maintained greater than 30 GPM to ensure adequate letdown cooling and prevent letdown from flashing to steam.
Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondarv Leaka
- a. Perform appropriate actions from table:
RUPTURED SG NR LEVEL RISING DROPPING OFFSCALE HIGH i
LESS THAN 32% "* Raise Raise "* Raise charging
[0 ADVERSE charging flow charging flow Depressurize R flow "* Maintain RCS &
RCS using ruptured SGs Step 31.b pressures equal P
R BETWEEN 32% Depressurize RCS Turn ON Maintain RCS &
Z [50% ADVERSE using Step 31.b PRZR ruptured SGs R CNMT] AND 50% heaters pressures equal L
E BETWEEN 50%
- Depressurize Turn ON Maintain RCS &
V AND 75% (61% RCS using PRZR ruptured SGs E ADVERSE CNMT] Step 31.b heaters pressures equal L
- Lower charging flow GREATER THAN Lower charging Turn ON Maintain RCS &
75% [614 flow PRZR ruptured SGs ADVERSE CNMTJ heaters pressures equal I I (step continued next page) 1E3 5/31102 29 of 39 FOR TRAININ -USEONLY
INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
- a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
- b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
- c. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
FOR TPRAINN USE ONLJ BEAVER VALLEY - UNIT 1 3/4 3-33 Amendment No. 129
TABLE 3.3-6 DPR- 66 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT(3) RANGE ACTION
- 1. AREA MONITORS
- a. Deleted
- b. Containment
- i. Purge & Exhaust 2 (2) < 1.6 x 103 cpm 10 -106 cpm 22 Isolation (RMVS 104 A & B) ii. Area (RM-RM-219 2 1,2,3 & 4 < 1.5 x 104 R/hr 1 - 7 R/hr 35 A & B)
- c. Control Room Isolation 2 1,2,3,4 < .47 mR/hr 10-2 _ 103 41 (RM-RM-218 A & B) and (4) mR/hr
- 2. PROCESS MONITORS
- a. Containment C i. Gaseous Activity 1 1,2,3 & 4 N/A 10 - 106 cpm 20 RCS Leakage Detection (RM 215B)
Particulate Activity 1 1,2,3 & 4 N/A 10 _ 106 cpm 20 ii.
RCS Leakage Detection (RM 215A)
- b. Deleted r0 z - UNIT 1 3/4 3-34 Amendment No. 246 BEAVER VALLEY
DPR-66 TABLE 3.3-6 (Continued)
TABLE NOTATIONS (1) (Not used)
(2) During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.
(3) Above background.
(4) During movement of irradiated fuel assemblies and during movement of fuel assemblies over irradiated fuel assemblies.
ACTION STATEMENTS ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 21 This Action is not used.
ACTION 22 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 35 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
a) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and b) Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
ACTION 41 - a) With the number of Unit 1 OPERABLE channels one less than the Minimum Channels OPERABLE requirement:
- 1. Verify the respective Unit 2 control room radiation monitor train is OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 31 days.
R TRAINING USE ONLY BEAVER VALLEY - UNIT 1 3/4 3-35 Amendment No. 246
TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTION 41 (Continued)
- 2. With the respective Unit 2 control room radiation monitor train inoperable, suspend all operations involving movement of irradiated fuel assemblies and movement of fuel assemblies over irradiated fuel assemblies within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore the Unit 1 control room radiation monitor to OPERABLE status within 7 days or isolate the control room from the outside atmosphere by closing all series air intake and exhaust isolation dampers, unless the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.
b) With no Unit 1 control room radiation monitors OPERABLE:
- 1. Verify both Unit 2 control room radiation monitors are OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 31 days.
- 2. With either Unit 2 control room radiation monitor inoperable, suspend all operations involving movement of irradiated fuel assemblies and movement of fuel assemblies over irradiated fuel assemblies within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore the respective Unit 1 control room radiation monitor train to OPERABLE status within 7 days or isolate the control room from the outside atmosphere by closing all series air intake and exhaust isolation dampers, unless the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.
- 3. With no Unit 2 control room radiation monitors OPERABLE, immediately isolate the combined control room by closing all series air intake and exhaust isolation dampers and be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours.
FOR TRAINING. USE ONLY BEAVER VALLEY - UNIT 1 3/4 3-35a Amendment No. 241
U. S. Nuclear Regulatory Commission Site-Specific Written Examination ADplicant Information Name: Region: I Date: Facility/Unit: BVPS-1 License Level: SRO Reactor Type: Westinghouse PWR Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value 100L Points Applicant's Score Points Applicant's Grade Percent
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BVPS-1 LOT5 NRC EXAM Senior Reactor Operator
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BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 001 Given the following conditions:
"* The Unit is at 85% power. All systems are in NSA.
"* A Control Bank "D", Group 2 rod drops to the bottom of the core.
"* The plant is stabilized, the cause of the failure identified and repaired.
Which one of the following describes the method for retrieving the dropped rod in accordance with 1OM-1.4.X, RCCA or RCCA Group Misalignment?
A. All rods in group 2 except the affected rod are disconnected. Control Bank "D", Group 1 rods remain connected. The Group 2 Step Counter is set to the dropped rod position prior to retrieval. The affected rod is withdrawn until the Group 2 Step Counter matches the Group 1 Step Counter.
B. All rods in Control Bank "D", Group 1 and Group 2, except the affected rod are disconnected. The Step Counter for Group 2 is set to the dropped rod position. The Step Counter for Group 1 is left at its current position. The affected rod is withdrawn until Group 1 and Group 2 Demand are equal.
C. All rods in Control Bank "D", Group 1 and Group 2, except the affected rod are disconnected. The Step Counters for Group 1 and Group 2 are set to the dropped rod position. The affected rod is withdrawn until the Step Counters match the initial bank position.
D. All rods in group 2 except the affected rod are disconnected. Control Bank "D", Group 1 rods remain connected. The Step Counters for Group 1 and Group 2 are set to the dropped rod position. The affected rod is withdrawn until the Step Counters match the initial bank position.
I
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 002 The plant is operating at 100% power, NSA when the following indications are observed.
"* Control Bank "D" rod F-6 position indicates '0' steps.
"* Rod bottom rod drop alarm is received.
If rod F-6 is the only rod bottom light lit and the plant remains on-line, which one of the following describes the INITIAL automatic response of the CVCS?
A. Letdown flow is increased.
B. Letdown flow is decreased.
C. Charging flow is increased.
D. Charging flow is decreased.
2
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 003 Given the following conditions:
"* The plant is in Mode 3.
"* A reactor startup is in progress.
"* Shutdown Bank "A7 is fully withdrawn.
"* Shutdown Bank "B" is being withdrawn.
"* The following annunciator is received in the Control Room:
o [A3-82], REACTOR COOL PP BRG OIL RESERVOIR LOW
"* The startup is stopped while a Containment entry is made to investigate.
The operator in containment reports a large oil leak in the vicinity of "IA" RCP.
Which one of the following describes the action required?
A. Trip "IA" RCP and refer to the alarm response procedure for "IA" RCP low flow.
B. Trip the reactor, trip "IA" RCP and refer to the alarm response procedure for "1A" RCP low flow.
C. Trip the reactor, perform Immediate Manual Actions of E-0, Reactor Trip Or Safety Injection, trip "IA" RCP and continue in E-0.
D. Monitor "IA" RCP bearing temperatures. If any bearing temperature exceeds 2750 F, trip the RCP and refer to the alarm response procedure for RCP bearing high temperature.
3
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 004 The following conditions exist for starting a Reactor Coolant Pump (RCP):
"* Local Lift Oil Pump control switch in 'AUTO'.
"* RCP control switch placed in 'START' and released.
Which one of the following describes the sequence of events that will take place to start the RCP?
A. Lift Oil Pump starts. After 50 seconds, RCP starts. 2 minutes later the Lift Oil Pump stops.
B. Lift Oil Pump starts. After 2 minutes, RCP starts. 50 seconds later the Lift Oil Pump stops.
C. After 50 seconds the Lift Oil Pump starts. 2 minutes later the RCP starts.
50 seconds, the Lift Oil Pump stops.
D. After 50 seconds the Lift Oil Pump starts. After 50 seconds the RCP starts. 2 minutes later the Lift Oil Pump stops.
4
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 005 The Unit is operating at 100% power NSA, when [LT-1 CH-1 12], VCT Level Transmitter fails high.
After an extended period of operation, the following conditions result.
"* [A3-53], VOLUME CONTROL TANK LEVEL HIGH-LOW alarms.
"* VCT level indicates approximately 5%.
Assuming NO action by the crew, which one of the following describes the plant response?
A. Charging pump suctions from the VCT remain open; the RWST suction valves remain closed.
B. Charging pump suctions from the VCT will close; the RWST suction valves remain closed.
C. Charging pump suctions from the VCT remain open; the RWST suction valves also open on low VCT level.
D. Charging pump suctions from the VCT will close; the RWST suction valves open on low VCT level.
5
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 006 The operating crew is performing a dilution in preparation for rod withdrawal to criticality.
If Keff is approximately .99 when the dilution is started, at what point in the dilution can the crew determine that Keff is approximately .995?
A. When the Source Range counts double from their initial value.
B. When there is a stable startup rate with no change in the dilution flow rate.
C. When Control Bank "A" control rods are withdrawn from the core.
D. When the Source Range counts double 2 - 3 times from their initial value.
6
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 007 Given the following conditions:
"* An ATWS has occurred.
"* The operating crew is performing the actions of FR-S.1, Response To Nuclear Power Generation/ATWS.
"* All SG narrow range levels are offscale LOW.
Which one of the following describes the required operation of the AFW System and why?
A. Operate all available AFW pumps to establish total flow of 355 gpm; to maintain minimum heat sink and restore SG levels.
B. Operate motor driven AFW pumps only to establish total flow of 355 gpm; to minimize effects of RCS cooldown on reactivity.
C. Operate all available AFW pumps to establish total flow of 630 gpm; to maintain minimum heat sink and restore SG levels.
D. Operate motor driven AFW pumps only to establish total flow of 630 gpm; to minimize effects of RCS cooldown on reactivity.
7
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 008 Given the following conditions:
"* The Unit was operating at 100% power.
"* A PORV failed open.
"* The reactor has tripped on low Pressurizer pressure.
"* Pressurizer pressure stabilizes at 1700 psig.
Plant status is as follows:
"* All control rods are fully inserted.
"* Status light "S Inj Act Sig" NOT LIT at Panel 62, C-4.
"* Normally running charging pump is in service.
"* Standby charging pump NOT running,
" NO..LHSI pumps running.
"* CIA NOT actuated.
"* CIB NOT actuated.
"* Main steam lines NOT isolated.
"* Feedwater Isolation Signal NOT actuated.
Which one of the following describes the required manual operator actions?
Manually initiate both trains of ...
A. Safety Injection.
B. Safety Injection and CIB.
C. Safety Injection, CIB, and Main Steam Line Isolation.
D. Safety Injection, CIB, Main Steam Line Isolation, and CIA.
8
EXAM BVP S-i LOT5 NRC BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 009 Which one of the following contains BOTH conditions that will result in indicated reactor power being LOWER than actual reactor power?
A. Source Range pulse height discrimination set too LOW.
Intermediate Range compensating voltage set too LOW.
B. Source Range pulse height discrimination set too HIGH.
Intermediate Range compensating voltage set too HIGH.
C. Source Range pulse height discrimination set too LOW.
Intermediate Range compensating voltage set too HIGH.
D. Source Range pulse height discrimination set too HIGH.
Intermediate Range compensating voltage set too LOW.
9
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 010 Following a Unit trip, Intermediate Range Startup rate is approximately -1/3 decade per minute on both channels.
Current indication on Intermediate Range channels are as follows:
"* N35 = 5E 7 amps
"* N36 = 2E- amps Based upon the above indications, which one of the following describes the sequence for Source Range Channel N-31 and N-32 energization?
A. Both Source Range channels will energize when N-35 reaches its setpoint.
B. Both Source Range channels will energize when N-36 reaches its setpoint.
C. N-31 will energize when N-35 reaches its setpoint. N-32 will energize when N-36 reaches its setpoint.
D. N-31 will energize when N-36 reaches its setpoint. N-32 will energize when N-35 reaches its setpoint.
10
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 011 Given the following conditions:
"* The Unit is in Mode 1. All systems are in NSA.
"* All Tavg channels are approximately 30 F higher than Tref.
Which one of the following modes on the Rod Control System Mode Selector Switch will provide the FASTEST rod speed if rod motion is demanded?
A. Manual B. Automatic C. Control Bank "A" D. Shutdown Bank "A" 11
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 012 Given the following conditions:
- A Reactor Trip has occurred from 100% power.
- Actions of E-0, Reactor Trip Or Safety Injection are being performed.
- The operating crew is checking if SI flow should be terminated when it is determined that RCS subcooling on the ICCM is less than the required 431F.
Which one of the following describes the method used to determine whether RCS subcooling is adequate?
A. Minimum required subcooling is determined using the SPDS; actual RCS subcooling is calculated by the IPC.
B. Actual RCS subcooling is determined using PRZR pressure and T-hot; minimum required subcooling is determined by the SPDS.
C. Minimum required subcooling is determined using an EOP Attachment; RCS subcooling is determined using PRZR pressure and T-hot.
D. RCS subcooling is determined using the ICCM; minimum required subcooling is determined using an EOP attachment.
12
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 013 Which one of the following correctly completes the following description of CRDM Shroud Cooling Fan operation?
With all plant systems in their normal alignments, [1VS-F-2C], CRDM Shroud Fan would start in the if [1VS-F-2A], CRDM Shroud Fan is NOT racked in on bus _ , and the diesel loading sequence signal is received.
A. auto mode; 8N B. auto mode; 8P C. manual mode; 8N D. manual mode; 8P 13
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 014 Given the following conditions:
- A loss of offsite power has occurred.
- All equipment has started and is operating as designed.
Which one of the following describes how Containment temperature is controlled under these conditions?
A. All Containment Air Recirculation Fans automatically sequence onto the EDGs.
B. Containment Air Recirculation Fans will automatically start when their control switches are placed in 'AUTO AFTER STOP'.
C. Containment Air Recirculation Fans must be manually started as necessary to control containment temperature.
D. Containment Air Recirculation Fans "A" and "B" automatically sequence onto the EDGs. Fan "C" must be manually started on the bus it is aligned to.
14
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 015 The Unit is operating at 80% power. All systems are in NSA.
Smoke is detected in the vicinity of MCCI-E5, and as a result the operating crew de-energizes MCCI-E5.
Subsequently, a LOCA inside Containment results in a Reactor Trip, Safety Injection and a Containment Spray actuation.
Which one of the following describes the response of the Quench Spray System?
Quench Spray Pump...
A. "A" starts and injects. "B" starts but does not provide spray flow.
B. "B" starts and injects. "A" starts but does not provide spray flow.
C. "A" and "B" both start, but neither train provides spray flow.
D. "A" and "B" both start and both trains provide spray flow.
15
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 016 Given the following conditions:
"* A LOCA has occurred.
"* The following engineered safeguards actuations have initiated:
o SI "o CIA "o CIB "o MSLI
"* All equipment is operating as designed.
Which one of the following is the MINIMUM necessary to electrically stop a Quench Spray Pump?
A. Reset SI only.
B. Reset CIB only.
C. Reset SI and CIA. (Both required).
D. Reset SI, CIA and CIB. (All required).
16
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 017 Given the following conditions:
"* Following a Reactor Trip due to a complete loss of CCR, all RCPs are stopped.
"* All systems are operating as designed.
Which one of the following describes the response of the core exit TCs following trip of the RCPs?
Core exit temperature initially and then A. rises; drops B. drops; rises C. rises; stabilizes D. drops; stabilizes 17
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 018 With the Unit operating at 80% power, all systems in NSA, [1WR-P-1A], Reactor Plant River Water Pump trips. As a consequence, Reactor Plant River Water is available to the...
A. "B" LHSI Pump [1 SI-P-I B] only.
B. "B" HHSI Pump [1 CH-P-1 B] only.
C. "A" LHSI Pump [1SI-P-1A] and the "B" LHSI Pump [1SI-P-1B].
D. "A" HHSI Pump [ICH-P-1A] and the "B" HHSI Pump [1 CH-P-1 B].
18
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 019 Given the following conditions:
"* A LOCA has occurred.
"* The operating crew is performing actions of ES-1.2, Post LOCA Cooldown And Depressurization.
"* Pressurizer level is stable at 58%.
- RCS pressure is stable at 1680 psig.
- The Unit Supervisor determines that a Charging/HHSI pump can be stopped in accordance with EOP Attachment 7-A, Criteria For Stopping I Of 2 Running Charging/HHSI Pumps, Subcooled Conditions.
When the RO stops the Charging/HHSI Pump, which one of the following describes the Pressurizer level response?
A. PRZR level will remain at its current value.
B. PRZR level will rise until charging is realigned to the VCT.
C. PRZR level will drop until normal charging and letdown are restored.
D. PRZR level will drop until RCS pressure stabilizes at a lower value, then will stabilize.
19
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 020 Given the following:
- The Unit is operating at 90% power with all systems in NSA.
- [GW-TK-IA], Gaseous Waste Decay Tank discharge is in progress.
- [1GW-F-1A], GW Disposal Blower is operating.
- [TV-1 GW-1 03], GW Decay Tank Disch to CTWR Valve is open.
- [TV-1 GW-103A2], GW Decay Tank Bleed Valve is open.
S[1 GW-D-1 -I A], GW Disposal Damper associated with the "A' GW Disposal Blower [I GW-F-1 A] is open.
Then, [RM-1 GW-1 08B], GW Disposal Blower Discharge Radiation Monitor alarms on High-High gaseous activity.
Which one of the following completely describes the Gaseous Waste System automatic response?
A. [1 GW-F-1 A], GW Disposal Blower trips.
B. [1 GW-D-I -I A], GW Disposal Damper shuts.
C. Valve [TV-1 GW-1 03] and valve [TV-1 GW-1 03A2] shut.
D. Blower [1GW-F-1A] trips and damper [1GW-D-I -1 A] shuts.
20
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 021 The Unit is operating at 80% power with all systems in NSA, when a Small Break LOCA in containment results in a Reactor Trip and SI Signal.
- 4160 Volt Emergency Bus "1AE" supply breaker from offsite power trips.
0 No. 1 EDG fails to start.
Which one of the following describes the status of the charging pumps?
Charging Pump "A7 ; Charging Pump "B" A. running; running B. not running; running C. running; not running D. not running; not running 21
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 022 Given the following conditions:
"* A loss of offsite power has occurred.
"* RCS cooldown is being performed in accordance with ES-0.2, Natural Circulation Cooldown.
"* RCPs cannot yet be started.
"* The RO is depressurizing using auxiliary spray.
"* Pressurizer level rapidly rises from 24% to 66%.
Which one of the following describes the reason for the Pressurizer level increase?
A. Loss of Secondary Heat Sink.
B. Portions of the RCS have reached saturation temperature.
C. HHSI flow is refilling the Pressurizer as RCS pressure drops.
D. Cooldown rate is not high enough to maintain Pressurizer level with auxiliary spray in service.
22
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 023 Given the following:
- A Unit startup is in progress and all nuclear instrumentation is observed to be operating normally.
- Power Range Channel N-43 is indicating 11%.
- Power Range Channels N-41, N-42 and N-44 are indicating 9%.
Which one of the following is correct concerning Reactor Protection System trips?
A. Power Range, high setpoint trip and Source Range high flux trip are enabled.
B. Power Range, low setpoint trip and Source Range high flux trip are disabled.
C. Power Range, high setpoint trip and Intermediate Range high flux trip are enabled.
D. Power Range, low setpoint trip and Intermediate Range high flux trip are disabled.
23
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 024 Given the following conditions:
"* The Unit was operating at 68% power.
"* An automatic Reactor Trip occurred.
"* The cause of the trip was determined to be LOW flow in RCS Loop "A".
"* The cause of the trip was determined to be an instrument failure.
Which one of the following input failures caused the Reactor Trip?
A. The Loop "A" high pressure side flow input failed high.
B. The Loop "A" high pressure side flow input failed low.
C. One Loop "A" low pressure side flow input failed high.
D. One Loop "A" low pressure side flow input failed low.
24
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 025 Given the following conditions:
- The Unit is at 100% power. All systems are in NSA.
- [PT-1 MS-446], First Stage Pressure is selected for Tref input to Rod Control System. It begins to fail DOWNSCALE.
Assuming NO action by the crew, which one of the following primary plant parameters will initially INCREASE as a result of the transmitter failure?
A. Charging flow B. RCS Tavg C. Reactor power D. RCS loop Delta-T 25
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 026 Given the following conditions:
- A Unit startup is in progress with the main steam stop valves closed.
- The operating crew is preparing to warm up the main steam lines.
Which one of the following actions will cause "A" SG pressure to INCREASE in this plant configuration?
A. Decrease SG Atmospheric Dump Valve controller output.
B. Decrease SG Atmospheric Dump Valve controller setpoint.
C. Increase Main Steam Dump pressure controller output.
D. Increase Main Steam Dump pressure controller setpoint.
26
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 027 Given the following conditions:
"* A Large Break LOCA has occurred.
"* Both hydrogen recombiners are in service.
"* The following Control Room annunciator alarm light turns 'OFF':
o [A2-18], A-HYDROGEN RECOMBINER RUNNING Which one of the following describes the effect on the removal of hydrogen from Containment?
A. Hydrogen concentration will remain below 4% with only one recombiner in operation.
B. Hydrogen concentration will rise above 4% but remain below 13% with only one recombiner in operation.
C. Hydrogen concentration will remain below 4% only if the Containment Purge System is placed in service in addition to the recombiner.
D. Hydrogen concentration will remain below 4% only if Containment Spray is placed in service in addition to the recombiner.
27
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 028 The Unit is in Mode 1. All systems are in NSA.
Which one of the following describes the normal operation of the Spent Fuel Pool Purification System?
A. Two purification circulating pumps take suction from the spent fuel pool skimmers. Each pump discharges through a separate filter and ion exchanger.
B. Either or both of two purification circulating pumps take suction from submerged piping in the Spent Fuel Pool. Each pump discharges through a separate filter and a common ion exchanger.
C. One purification circulating pump takes suction on submerged piping in the Spent Fuel Pool. The other pump is aligned for RWST purification.
Each pump discharges through separate filters and ion exchangers.
D. One purification pump takes suction from the spent fuel pool skimmers.
The other pump is aligned for RWST purification. Each pump discharges through separate filters and ion exchangers.
28
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 029 Given the following conditions:
- A Unit startup is in progress following a mid-cycle outage.
- The reactor is critical at 1E8 amps.
A condenser steam dump valve fails partially open.
Assuming NO action by the operating crew, which one of the following describes the immediate effect on the plant?
A. RCS Temperature INCREASES; Power INCREASES B. RCS Temperature DECREASES; Power INCREASES C. RCS Temperature INCREASES; Power DECREASES D. RCS Temperature DECREASES; Power DECREASES 29
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 030 Which one of the following conditions will PREVENT the No. 1 EDG output breaker from closing to energize 4KV Bus "IAE" following a loss of power?
A. [ACB-1A10], Emergency Bus "IAE" Feeder Breaker has an undervoltage trip.
B. [ACB-1Al 0], Emergency Bus "IAE" Feeder Breaker has an overcurrent trip.
C. [ACB-41C], Normal 4KV Bus "IA" Feeder Breaker has an overcurrent trip with bus "1AE" normal feeder breaker control switch position in 'Auto After Close'.
D. [ACB-41C], Normal 4KV Bus "1A" Feeder Breaker has an undervoltage trip with bus "1AE" normal feeder breaker control switch position in 'Auto After Close'.
30
NRC EXAM BVPS-ILOT5 BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 031 Given the following conditions:
"* The Unit is in Mode 6.
"* RHR is in service.
"* RCS temperature is 139 0 F.
"* RCS boron concentration is 1822 ppm.
"* RCS drain down is in progress in preparation for refueling.
[MOV-1 RH-758], RHR Heat Exchanger Flow Control Valve begins to drift in the closed direction due to an electrical problem.
Assuming NO action by the operating crew, which one of the following describes the effect of this failure on plant operation?
A. RCS cooldown to a temperature below the RCS boron solubility limit.
B. Loss of NPSH to the operating RHR pump due to increased temperature.
C. OPPS actuation due to overpressurization of the RCS.
D. Loss of RHR letdown and uncontrolled RCS level increase.
31
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 032 Given the following conditions:
"* The Unit is in Mode 4.
"* RCS cooldown is in progress on RHR Train "B".
"* CCR Train "A" and Train "B" are aligned to provide cooling water to RHR.
Which one of the following describes the flow limits placed on the CCR System in this alignment, and the method used to determine actual flow?
A. Total CCR system flow is limited to 4500 gpm. The actual flow is determined by adding the flows on the 8 inch, 14 inch, and 24 inch CCR headers.
B. Each CCR pump is limited to a total of 6500 gpm. The actual flow is determined by adding the flows on the 8 inch, 14 inch, and 24 inch CCR headers.
C. Total CCR flow through the RHR heat exchanger is 4500 gpm. The actual flow is determined directly from the 24 inch CCR header.
D. Total CCR flow through the RHR heat exchanger is 6500 gpm. The actual flow is determined directly from the 24 inch CCR header.
32
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 033 Surveillance Verification Log L5 is being performed for the 0000 - 0800 shift.
The RO determines that the NIS Cabinet power range indication is NOT within allowable limits.
Per 1OM-54. 1.A, Station Logs, which one of the following describes how this is required to be documented in the L5 log?
A. Circle all readings in red pen that are not in compliance. Unit Supervisor must initial the L5 log in the time column next to the unsatisfactory check.
B. Circle all readings in red pen that are not in compliance. Details of the unsatisfactory check must be documented in the remarks section. Unit Supervisor must review the log at least once every shift.
C. Mark 'UNSAT' in the time column opposite the unsatisfactory check.
Record details of the check in the remarks section. Unit Supervisor must review the log prior to end of shift.
D. Mark 'UNSAT' in the time column opposite the unsatisfactory check.
Record details of the check in the remarks section. Unit Supervisor must initial the L5 log in the time column next to the UNSAT comment.
33
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 034 Given the following:
"* [1QS-MR-1A], Refueling Water Refrigeration Unit is 'ON'.
"* One refueling water recirculation pump is running in 'SLOW'.
"* [TS-1 QS20OA21, Refrigeration Unit Operating Thermostat is actuated.
Using the diagram provided, which one of the following describes the status of the refueling water refrigeration unit?
[1QS-MR-1A], Refueling Water Refrigeration Unit is...
A. started, and liquid line solenoid is energized to open.
B. stopped, and liquid line solenoid is energized to close.
C. started, and liquid line solenoid is deenergized to open.
D. stopped, and liquid line solenoid is deenergized to close.
34
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 035 Given the following conditions:
"* The Unit has been at 100% power for 3 weeks. All systems are in NSA.
"* RCS boron concentration is 1100 ppm.
"* A controlled power reduction to 50% is to be performed.
Using the references provided and maintaining control rods at their current position, which one of the following describes the MINIMUM amount of boric acid required to initially maneuver the plant to 50% power?
A. 900 gallons B. 1100 gallons C. 1300 gallons D. 1500 gallons 35
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 036 Regarding Technical Specification SAFETY LIMITS, which one of the following core limitations does the OT Delta-T Reactor Trip prevent exceeding?
A. Power Density (KW/ft)
B. Departure from Nucleate Boiling (DNB)
C. Total Core Power D. Axial Flux Difference (AFD) 36
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 037 Given the following conditions:
- A reactor startup is in progress.
- Control Bank "A" withdrawal is in progress.
- The last two I/M plots indicate that criticality will be achieved on Control Bank "B" at approximately 100 steps.
- Estimated Critical Position is Control Bank "C" at 144 steps.
Per 1 OM-50.4.D, Reactor Startup From Mode 3 To Mode 2, which one of the following actions is required for these conditions?
A. Trip the reactor and initiate emergency boration.
B. Stop the startup and determine whether criticality will be within 500 pcm of the ECP prior to proceeding.
C. Insert all control banks to zero steps, verify shutdown margin and recalculate the ECP.
D. Continue the startup to obtain one additional 1/M data point to validate the accuracy of the plot.
37
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 038 Given the following conditions:
"* The control rod full out position is 230 steps.
"* The required bank overlap for the current fuel cycle is 102 steps.
During rod withdrawal, when Control Bank "B" reaches full out position, what will be the position of Control Bank "C"?
A. 000 steps B. 102 steps C. 128 steps D. 230 steps 38
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 039 The Unit Supervisor has directed a Unit shutdown based on RCS activity exceeding TS 3.4.8 limits.
In the event of a subsequent SGTR, which one of the following actions is designed to limit the release of radioactivity?
A. MSIVs are closed.
B. SG atmospheric dump valve setpoints are raised.
C. RCS is cooled down below 5000 F.
D. Maximum condensate polishers are placed in service.
39
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 040 The Unit is in Mode 5. Preparations are being made to enter Containment.
Per 1 OM-44C.4.A, Containment Purge Supply And Exhaust System Startup, which one of the following describes the correct sequence for initiating a containment purge to the ventilation vent?
A. Open supply and exhaust dampers, start [1VS-F-5], CNMT Purge Exhaust Fan. If desired, start [1VS-HV-5], CNMT Purge Vent Sup Fan after ensuring the NORMAL/REFUELING control switch is in the 'NORMAL' position.
B. Open supply and exhaust dampers, start [1VS-F-5], CNMT Purge Exhaust Fan. If desired, start [1VS-HV-5], CNMT Purge Vent Sup Fan after ensuring the NORMAL/REFUELING control switch is in the 'REFUELING' position.
C. Start [1VS-F-5], CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers are open. Place the NORMAL/REFUELING control switch in the
'NORMAL' position, and start [IVS-HV-5], CNMT Purge Vent Sup Fan.
D. Start [1VS-F-5], CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers are open. Place the NORMAL/REFUELING control switch in the
'REFUELING' position, and start [IVS-HV-5], CNMT Purge Vent Sup Fan.
40
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 041 Who, by title, can authorize a person to receive a radiation dose in excess of the Beaver Valley Administrative TEDE limits per 1/2-ADM-1 631, Exposure Control?
A. Site Senior Vice President B. Plant General Manager C. Superintendent, Operations D. Manager, Health Physics 41
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 042 The Unit is at 97% power. All systems are in NSA.
The RO withdraws control rods 2 steps for Tavg control. When the In-Hold-Out switch is released, rod motion continues.
The following alarms are received:
"* [A4-46], Tavg Deviation from Tref
"* [A4-51], Loop Tavg High The rod motion stops prior to any operator action occurring.
Which one of the following describes an INITIAL reactivity effect of the rod motion?
A. The positive reactivity added by FTC and MTC result in a higher total power defect.
B. The negative reactivity added by FTC and MTC result in a higher total power defect.
C. The positive reactivity added by FTC and MTC result in a lower total power defect.
D. The negative reactivity added by FTC and MTC result in a lower total power defect.
42
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 043 Given the following conditions:
The Unit is at 1.00% power with all systems in NSA.
"* [A4-97], ROD CONTROL SYSTEM NON-URGENT ALARM illuminates.
"* [A4-126], ROD BOTTOM ROD DROP is illuminated.
"* One Control Bank "D" rod is indicating '0' steps.
"* The RO places rod control in 'MANUAL'.
"* Other Control Room annunciators illuminate as expected for plant conditions.
"* Reactor power indicates as follows:
"o N41 -100.1%
"o N42 - 103.3%
"o N43 - 100.1%
"o N44 - 94.7%
Which one of the following interlocks or protective features must be cleared before automatic rod withdrawal may be reinstated?
A. The Rod Control System Non-Urgent condition must be cleared.
B. The 'Loop OP Delta T Auto Turbine Runback Block Auto Rod Withdrawal' circuitry must be reset.
C. The 'NIS Power Range High Setpoint Overpower Rod Stop Block Auto Rod W/D' must be cleared.
D. The 'Power Range Channel Deviation' must be cleared at the NIS Comparator and Rate Drawer.
43
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 044 Given the following conditions:
A load rejection has occurred from 100% power. The plant has stabilized at 82%
power.
"* The RO determines that 2 Control Bank "D" rods did not move during the load rejection.
"* The rods are approximately 16 steps above the remainder of Control Bank "D".
"* The Rod Control System Urgent Failure and Non-Urgent Failure alarms are NOT lit.
Which one of the following describes the required action for this condition?
A. Initiate a boration to increase shutdown margin by an amount equal to the stuck rod worth and align the remainder of Control Bank "D" rods with the stuck rods.
B. Initiate boration to increase shutdown margin by an amount determined by the shutdown margin OST and commence a plant shutdown to Mode 3.
C. Trip the reactor and initiate safety injection to borate the RCS to achieve adequate shutdown margin.
D. Trip the reactor and commence emergency boration in accordance with FR-S. 1, Response To Nuclear Power Generation/ATWS.
44
BVPS-l LOT5 NRC EXAM Senior Reactor Operator Question 045 The Unit is at 60% power.
S [ISI-P-1A], LHSI Pump is out of service.
S [1 QS-P-1 A], Quench Spray Pump is out of service.
A Large Break LOCA occurs. The operating crew takes action in accordance with E-A, Loss Of Reactor Or Secondary Coolant.
The following conditions currently exist:
0 Containment pressure 32 psig, DECREASING slowly 0 RCS pressure 100 psig, STABLE 0 Pressurizer level Offscale LOW All actuations have occurred as required.
With the reference provided, if the RWST was at its minimum level for operability when the event occurred, what is the approximate MINIMUM time before transition to ES-1.3, Transfer To Cold Leg Recirculation is required?
A. One hour B. Two hours C. Three hours D. Four hours 45
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 046 Which one of the following describes the operation of RCPs during the performance of FR-C.1, Response To Inadequate Core Cooling?
A. If RCPs are available, they are started early in the event to provide forced flow ONLY if seal injection and CCR are available.
B. If RCPs are available, they are started early in the event to provide forced flow EVEN IF seal injection and CCR are NOT available.
C. At least 1 RCP is started to provide forced flow and mixing of RCS water after secondary depressurization has resulted in SI accumulator injection.
D. At least 1 RCP is started to provide forced flow of the RCS when secondary depressurization is ineffective in restoring adequate core cooling.
46
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 047 Given the following conditions:
"* An ATWS has occurred.
"* The operating crew is performing the actions of FR-S.1, Response To Nuclear Power Generation/ATWS.
"* The RO has initiated emergency boration.
"* All equipment has operated as designed.
"* SI is NOT actuated.
- RCS pressure is 2210 psig and trending DOWN.
- Tavg is 567 0 F and trending DOWN.
Which one of the following describes plant response to initiation of the boration?
A. Boric Acid Tank level will drop at a rate approximately equal to charging flow.
B. Volume Control Tank level will drop at a rate approximately equal to charging flow.
C. Refueling Water Storage Tank level will drop at a rate approximately equal to charging flow.
D. Pressurizer level will rise at a level approximately equal to charging flow.
47
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 048 Given the following conditions:
- The Unit is in Mode 5.
- [1CC-E-1A], CCR Heat Exchanger is in service.
- [TCV-1CC-100], CCR Temperature Control Valve is in 'MANUAL'.
0 The operating CCR pump trips on overcurrent.
e There are no CCR pumps in standby.
Prior to any action by the operating crew, which one of the following describes system temperature response at the outlet of 1 CC-E-1 A over the next 10 seconds?
A. River Water temperature will RISE.
CCR temperature will RISE.
B. River Water temperature will DROP.
CCR temperature will DROP.
C. River Water temperature will RISE.
CCR temperature will DROP.
D. River Water temperature will DROP.
CCR temperature will RISE.
48
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 049 Given the following conditions:
"* Reactor Trip testing is in progress on Train "A".
"* Reactor Trip Breaker "A"is open.
"* Reactor Trip Bypass Breaker "A"is closed.
"* A transient occurs requiring a reactor trip.
"* The RO attempts to manually trip the reactor but the reactor does NOT trip.
Which one of the following describes a failure that has contributed to the reactor trip failure?
A. Reactor Trip Breaker "B" Undervoltage Trip coil failed to energize.
B. Reactor Trip Breaker "B" Shunt Trip coil failed to deenergize.
C. Reactor Trip Bypass Breaker "A" Undervoltage Trip coil failed to deenergize.
D. Reactor trip Bypass Breaker "B"Shunt Trip coil failed to energize.
49
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 050 Given the following conditions:
"* The Unit is at 100% power. All systems are in NSA.
"* A Steam Line Break occurs downstream of MSIV "A".
"* A Main Steam Line Isolation Signal is generated.
Which one of the following describes the maximum allowable closure time of the MSIVs and the associated reason?
A. The MSIVs must close within 5 seconds to limit the pressure rise inside containment.
B. The MSIVs must close within 5 seconds to minimize the reactivity effects of the RCS cooldown.
C. The MSIVs must close within 30 seconds to limit the pressure rise inside containment.
D. The MSIVs must close within 30 seconds to minimize the reactivity effects of the RCS cooldown.
50
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 051 Given the following conditions:
"* The Unit is operating at 100% power. All systems are in NSA.
"* The following alarm is received in the Control Room:
o [Al-10], VITAL BUS 1 TROUBLE
"* The operating crew determines that NI Rack Channel 1 is deenergized.
"* DC Bus 1 locally indicates 125 volts.
Which one of the following actions is required?
A. Trip the reactor; enter E-0, Reactor Trip Or Safety Injection.
B. Trip the reactor; enter E-0 and defeat containment pressure bistable channel 1 to inhibit CIB.
C. Restore Vital Bus 1 by bypassing the inverter; control plant parameters manually as necessary in accordance with 1 OM-38.4.AAA, Vital Bus 1 Trouble.
D. Restore Vital Bus 1 by aligning to DC Bus 1; remove inverter from service and restore letdown in accordance with 1OM-38.4.AAA, Vital Bus 1 Trouble.
51
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 052 Annunciator [Al 1-123], MOTOR DRIVEN FIRE PUMP RUNNING is in alarm and is valid. This indicates a fire in which one of the following areas:
A. Main Transformer B. Cable Tray Mezzanine C. Diesel Generator Building WAU D. Turbine Generator Bearings and Enclosure 52
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 053 Given the following conditions:
"* A small fire has developed in the Control Room.
"* The Shift Manager has determined that a Control Room evacuation is required.
"* A manual reactor trip has been initiated and all control rods have been verified fully inserted.
Which one of the following describes the MINIMUM action required to verify Turbine Trip?
A. Verify turbine throttle valves all closed or verify governor valves all closed prior to exiting the Control Room.
B. Verify turbine throttle valves all closed and verify governor valves all closed prior to exiting the Control Room.
C. Verify turbine throttle valves all closed or verify governor valves all closed in the Turbine Building prior to manning the Emergency Shutdown Panel.
D. Verify turbine throttle valves all closed and verify governor valves all closed in the Turbine Building prior to manning the Emergency Shutdown Panel.
53
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 054 Given the following conditions:
"* The Unit was operating at 100% power.
"* A Reactor Trip occurred due to a LOCA.
"* All Safety Injection Systems FAILED to operate.
"* FR-C.1, Response To Inadequate Core Cooling has been entered.
"o The Unit Supervisor has directed the depressurization of all intact SGs to 150 psig using the condenser steam dumps.
"o All MSIVs are open and the condenser is available.
"o The steam dump controller (AM-1 MS-464B) is in manual.
"o The steam dump control mode selector switch is in the STM PRESS position, and SG depressurization is underway.
"o PRZR pressure is > 1950 psig, and the Block Steamline SI Switches have NOT been placed in the 'BLOCK' position.
"o As the SG depressurization progresses, the steam flow automatically stops.
Which one of the following has caused the steam flow to stop?
A. Steam generator pressure has reached 150 psig, or containment isolation due to exceeding 1.5 psig pressure setpoint in containment.
B. Steam header pressure has dropped below the setpoint on AM-1 MS-464B, or Tavg is below 541 OF and no action has been taken to defeat the Tavg interlock.
C. Tavg is below 541OF and no action has been taken to defeat the Tavg interlock, or main steamline isolation due to exceeding the low steam pressure rate sensitive setpoint.
D. Containment isolation due to exceeding 1.5 psig pressure setpoint in containment, or steam header pressure has dropped below the setpoint on AM-1 MS-464B.
54
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 055 Given the following conditions:
"* A Reactor Trip and Safety Injection have occurred.
"* The operating crew was performing the actions of E-1, Loss Of Reactor Or Secondary Coolant.
" The Unit Supervisor was concerned about conflicting indications and the crew entered ES-0.0, Rediagnosis.
" There is an increasing trend on [RM-1MS-101], Auxiliary Feed Pump Turbine Exhaust Monitor and [RM-1 MS-1 OQA], Main Steam Safety Valve Effluent Monitor.
Which one of the following describes how the operating crew will transition to the correct procedure?
A. Go directly to the appropriate E-3 or ECA-3 series procedure.
B. Return to E-0 diagnostic steps to verify indications that will confirm the event in progress.
C. Return to E-1 step in effect and use the Symptomatic Response/Unexpected Conditions page to direct entry to E-3.
D. Direct Chemistry sample of SGs to confirm radiation monitor readings prior to making a determination of appropriate procedure entry.
55
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 056 Given the following conditions:
"* A Main Steam Line Break has occurred.
"* All equipment actuated as required.
"* The operating crew has isolated the faulted SG.
"* The Unit Supervisor has directed transition to ES-1.1, SI Termination.
"* SI, CIA, and CIB have been reset.
"* RCS pressure is 1775 psig and rising slowly.
"* There are NO other indications of RCS leakage.
Which one of the following describes the sequence of steps to terminate SI?
A. Stop 1 HHSI pump.
Check RCS pressure stable and align normal charging.
Stop BOTH LHSI pumps.
B. Stop 1 HHSI pump.
Check RCS pressure stable and align normal charging.
Stop 1 LHSI pump. Ensure RCS pressure remains stable, then stop the second LHSI pump.
C. Align normal charging.
Check RCS pressure stable and stop 1 HHSI pump.
Stop BOTH LHSI pumps.
D. Align normal charging.
Check RCS pressure stable and stop 1 HHSI pump.
Stop 1 LHSI pump. Ensure RCS pressure remains stable, then stop the second LHSI pump.
56
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 057 In accordance with Technical Specifications, which one of the following conditions will result in the declaration of at least one INOPERABLE control rod?
A. AFD exceeding operating limits.
B. A rod bottom light remains extinguished after a reactor trip.
C. Control Bank "D" rods are trippable but cannot be moved electrically.
D. One Control Bank uDS" rod indicates 210 steps with Control Bank "D" demand at 200 steps.
57
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 058 The Unit is operating at 100% power when the following conditions occur:
"* A PRZR spray valve sticks open and PRZR pressure has lowered to 1800 psig.
"* Reactor Trip Breakers are 'SHUT'.
"* Neutron flux is NOT dropping.
Which one of the following describes an Immediate Manual Action?
A. Verify auxiliary feedwater status.
B. Verify main steam line isolation.
C. Isolate condenser steam dump valves.
D. Initiate emergency boration of the RCS.
58
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 059 Pressurizer Relief Tank pressure indicates 15 psig on PI-1 RC-472. The operating crew suspects that a PORV opened inadvertently and is now stuck partially open.
Which one of the following indications confirm that a PORV is stuck partially open?
A. PORV relief line temperature stabilized at 213 0 F. PRZR safety relief line temperatures indicate 180°F and very slowly rising.
B. PORV relief line temperature stabilized at 2500 F. PRZR safety relief line temperatures indicate 217°F and very slowly rising.
C. PORV relief line temperature stabilized at 213 0 F. PRZR safety relief line temperatures indicate 11 0°F and stable.
D. PORV relief line temperature stabilized at 250 0 F. PRZR safety relief line temperatures indicate 1 10OF and stable.
59
BVPS-1 LOTS NRC EXAM BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 060 Given the following conditions:
"* The Unit is at 100% power, steady state. All systems are in NSA.
"* Pressurizer level is on program and stable.
"* Pressurizer pressure is 2235 psig and stable.
"* Charging flow on FI-CH-122 indicates 90 GPM.
A malfunction results in the loss of Pressurizer heaters. When heaters are restored, the following conditions exist:
"* Pressurizer level is on program and stable.
"* Pressurizer pressure is 2000 psig.
Which one of the following describes the approximate value for charging flow indication on FI-1 CH-1 22?
A. 0 GPM B. 8O GPM C. 90 GPM D. 100 GPM 60
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 061 Given the following conditions:
"* A reactor startup is in progress.
11
"* Both Intermediate Range channels indicate approximately 5 E- amps.
"* Source Range Channel N-31 fails DOWNSCALE.
Which one of the following describes the required operator response and the reason for the response?
A. Suspend the reactor startup; with only one source range channel operable, the minimum required Source Range High Flux Trip protection is not met.
B. Continue the reactor startup; with only one source range channel operable; 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to restore two channels to service.
C. Suspend the reactor startup; source range channels are not required to trip the reactor; however, the source range monitoring functions must be available.
D. Continue the reactor startup; the Intermediate Range Neutron Flux Trip and the Power Range Neutron Flux-Low Trip provide the necessary core protection.
61
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 062 Given the following conditions:
- A Small Break LOCA has occurred.
- Safety Injection pumps have been stopped.
- Normal charging is aligned.
- The crew is depressurizing the RCS using normal spray.
Which one of the following describes the strategy and the basis for the continuing depressurization?
A. Maximize subcooling to ensure continued RCP operation.
B. Minimize subcooling to reduce RCS break flow.
C. Maximize subcooling to prevent a challenge to the Core Cooling Critical Safety Function.
D. Minimize subcooling to ensure Pressurizer level remains above the lower limit to allow heater operation during the RCS cooldown.
62
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 063 The Unit is at 100% power. All systems are in NSA.
The following alarms are received in the Control Room:
"* [RM-1 SV-100], Condenser Air Ejector Vent High
"* [RM-BD-101], High Capacity SG Blowdown High-High
"* [RM-1 MS-1 02A], N-16 Steam Generator "AK Leak Monitor High-High RM-BD-101 and RM-1 MS-1 02A are stable at or near their alarm setpoints.
RM-1 SV-1 00 is stable above the High alarm setpoint.
Which one of the following describes the significance of the alarm status listed above?
A. The two radiation monitors in High-High alarm provide the threshold for tripping the reactor and initiating Safety Injection.
B. The alarm status of the radiation monitors give an approximate value for RCS primary-to-secondary leak rate.
C. The rate of increase of any of the three radiation monitors provides the threshold for tripping the reactor and initiating Safety Injection.
D. The alarm status of the radiation monitors determines the course of action taken for charging and letdown to provide an accurate estimate of the leak rate.
63
BVPS-ILOT5 NRC EXAM Senior Reactor Operator Question 064 Given the following conditions:
"* The Unit was operating at 100% power when a Reactor Trip occurred on low Pressurizer pressure.
"* A Steam Generator Tube Rupture was diagnosed and E-3, Steam Generator Tube Rupture was entered.
"* E-3, Step No. 31, "Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage" is being performed (attached).
Given the following control room indications:
"* SG "C" blowdown sample indicates high radiation.
"* SG "C" NR level is 32% and dropping.
"* Feed flow has been isolated to SG "C".
"* SG "A" and "B" levels are slowly lowering.
"* PRZR level is 63% and rising.
Which one of the following describes the operator action?
A. Depressurize RCS.
B. Lower charging flow.
C. Turn on PRZR heaters.
D. Depressurize RCS and lower charging flow.
64
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 065 The Unit is at 50% power during a power increase to 100%.
The following alarms are received in the Control Room:
"* 1A, 1B, 1C SG Level Deviation
"* 1A, IB, IC SG Level Low The PO determines the following for all 3 SGs:
"* SG level is DECREASING.
"* Steam flow is STABLE.
"* Feed flow is DECREASING.
"* Feedwater Regulating Valve positions are all going OPEN.
"* Feedwater header pressure is approximately 950 psig and trending DOWN slowly.
Assuming NO action has been taken by the operating crew, which one of the following events is the cause of these indications?
A. Secondary Load Rejection B. Loss of Feedwater C. [PT-1 MS-446], First Stage Pressure Transmitter failed LOW D. [PT-1 MS-446], First Stage Pressure Transmitter failed HIGH 65
BVPS-ILOT5 NRC EXAM BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 066 Given the following conditions:
- The Unit is at 100% power. All systems are in NSA.
- The following annunciators are received in the Control Room:
o [A9-97], 125VDC BUS 1 DC SUPPLY ACB OVERCURRENT TRIP o [A9-98], 125VDC BUS 1 VOLTAGE LOW o [A9-100], 125VDC BATTERY CHGR 1 FAILURE
- 125 Volt DC Bus 1 voltage indicates '0' volts.
- The operating crew enters AOP-1.39.1, Loss Of 125VDC Bus.
Which one of the following describes the action required for this condition?
A. Perform 1OM-39.4.AAI, 125VDC Bus 1 Voltage Low to restore DC Bus 1.
B. Enter E-0, Reactor Trip Or Safety Injection and concurrently perform 1OM-39.4.AAI upon completion of Immediate Manual Actions.
C. Enter E-0, Reactor Trip Or Safety injection and perform 1 OM-39.4.AAI when directed to go to procedure and step in effect at the completion of ES-0. 1, Reactor Trip Response.
D. Perform 1OM-39.4.G, Loss Of Battery Charger to restore power to DC Bus 1.
66
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 067 Given the following conditions:
"* A Steam generator Tube Rupture has occurred on the UAK SG.
"* All equipment is operating as designed.
"* "A"SG has been isolated. The following indications exist:
"o "A" SG pressure is 1000 psig and trending UP.
"o "A" SG NR level is 55% and trending UP.
Which one of the following describes how pressure will be controlled on KA" SG prior to completion of the RCS depressurization?
A. Manually at the condenser steam dump pressure setpoint.
B. Automatically at the first SG safety valve setpoint.
C. Automatically with the SG atmospheric dump valve controller in 'Manual'.
D. Manually by performing secondary depressurization to cool down the RCS below initial target temperature.
67
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 068 Given the following conditions:
"* A loss of heat sink has occurred.
"* The operating crew is establishing RCS 'Bleed and Feed' in accordance with FR-H.1, Loss Of Secondary Heat Sink.
"* The RO opens one PORV. He reports that the other two PORVs will NOT open.
Which one of the following describes the consequences of the PORV failures?
A. A Red Path on the Core Cooling Critical Safety Function will develop due to loss of RCS inventory with no available makeup.
B. RCS 'Feed and Bleed' cooling must be established to ensure sufficient SI flow at the operable PORV setpoint.
C. The RCS may not depressurize quickly enough to ensure sufficient SI flow to provide RCS heat removal, and other RCS openings may have to be established.
D. 'Bleed and Feed' cooling of the RCS must be terminated and secondary depressurization to inject condensate pump flow must be immediately initiated.
68
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 069 Given the following conditions:
"* The Unit is in Mode 6. All systems are in NSA.
"* Refueling in progress. The Containment equipment hatch is closed.
"o [RIS-1RM-104A], Containment Purge Exhaust Monitor is in High-High alarm.
"o Containment Purge Supply and Exhaust Fans trip.
"o Containment Evacuation Alarm is sounding.
Which one of the following indications will provide direct confirmation of the event in progress?
A. [RIS-1 RM-215A], Containment Particulate Monitor B. [RIS-1VS-103A], Fuel Building Ventilation Exhaust Monitor C. [RIS-IVS-107A], Elevated Release Particulate Monitor D. [RM-1 RM-218A], Control Room Radiation Monitor 69
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 070 As directed by ECA-0.0, Loss Of All AC Power, the operating crew places the charging pumps in Pull-To-Lock.
The defeat of the charging pump automatic start is to prevent...
A. an uncontrolled over-pressurization of the RCS, and the resulting increased loss of RCS inventory through the RCP seals when power is restored.
B. an excessive cooldown of the RCS due to injection of cold RWST water when power is restored.
C. the unnecessary use of water that may be needed for long term recovery.
D. a LOCA caused by thermal shock of the RCP seals when power is restored.
70
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 071 Given the following conditions:
"* The Unit is at 100% power. All systems are in NSA.
"* [TV-I CH-200B], Letdown Orifice Isolation Valve is aligned for service.
"* [LT-1 RC-459], Pressurizer Level Transmitter fails offscale LOW.
"* The RO places the PRZR Level Channel Selector Switch to the correct position.
Which one of the following describes the effect on the plant and the additional action required to stabilize the plant?
A. Letdown flow will indicate 60 GPM. Turn off backup heaters and adjust charging flow as necessary.
B. Letdown flow will indicate 0 GPM. Manually energize backup heaters as necessary and establish excess letdown.
C. Letdown flow will indicate 60 GPM. Turn off backup heaters and establish excess letdown.
D. Letdown flow will indicate 0 GPM. Manually energize backup heaters as necessary and establish normal letdown.
71
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 072 The operating crew is responding to a loss of heat sink per FR-H.1, Response To Loss Of Secondary Heat Sink.
"* All SG wide range levels are offscale LOW.
"* RCS 'Bleed and Feed' has been established.
"* RCS temperature is approximately 588°F and rising slowly.
Which one of the following describes the preferred method of initiating auxiliary feedwater flow for these conditions?
A. Feed 1 SG at the highest possible rate to reestablish SG inventory and secondary heat sink.
B. Feed all SGs at the highest possible rate to establish conditions for natural circulation.
C. Feed 1 SG at the minimum required flow to prevent possible SG tube failures.
D. Feed all SGs at the minimum required flow to establish a controllable cooldown rate and prevent loss of RCS inventory.
72
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 073 Given the following conditions:
0 The Unit is in Mode 1 at 100% power.
- The operating crew is performing 1OM-15.4.H, Securing A CCR Pump Or Placing The Spare CCR Pump In Service During Two Pump Operation, with the following system status:
"o [1CC-P-1B], Component Cooling Pump is running.
"o [ICC-P-IC], Component Cooling pump is racked on the "IAE" 4KV Bus.
"o [1CC-P-1A], Component Cooling Pump control switch is in Pull-To-Lock.
A loss of offsite power then occurs. No. 2 EDG fails to start.
Two minutes later, the RO announces that annunciator [A6-35], PRI COMP COOL PUMP DISCH PRESS LOW is lit.
Which one of the following is causing annunciator A6-35 to be lit?
A. PCV-ICC-100, CCR pressure control valve has failed closed.
B. 1CC-P-I C control switch is in 'After Start'.
C. ICC-P-1A is still racked on the "IAE" 4KV Bus.
D. "IAE" 4KV Stub Bus tie breaker 1 E5 has opened as designed.
73
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 074 Given the following conditions:
"* A LOCA has occurred.
"* The operating crew is performing actions contained in E-1, Loss Of Reactor Or Secondary Coolant.
" The following conditions currently exist:
"o All SI equipment is operating as required.
"o RCS pressure is 80 psig.
"o The STA informs you of the following Critical Safety Function Orange Path conditions:
"* Integrity
"* Containment Which one of the following describes the correct response to these indications?
A. Enter FR-P.1, Response To Imminent Pressurizer Thermal Shock Condition. Take action to stop RCS cooldown and reduce RCS pressure.
When directed, enter FR-Z.1, Response To High Containment Pressure.
B. Enter FR-P. 1, Response To Imminent Pressurizer Thermal Shock Condition. Ensure LHSI flow is consistent with RCS pressure. Transition to FR-Z.1, Response To High Containment Pressure.
C. Enter FR-Z.1, Response To High Containment Pressure. When action is complete, transition to FR-P.1, Response To Imminent Pressurizer Thermal Shock Condition. Take action to stop RCS cooldown and reduce RCS pressure, then return to E-1.
D. Enter FR-Z.1, Response To High Containment Pressure. When action is complete, transition to FR-P.1, Response To Imminent Pressurizer Thermal Shock Condition. Ensure LHSI flow is consistent with RCS pressure, then return to E-1.
74
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 075 Given the following conditions:
- A Reactor Trip has occurred due to loss of offsite power.
- The operating crew is performing actions of ES-0.2, Natural Circulation Cooldown.
- Train "A" of RVLIS is out of service.
- The crew has commenced RCS cooldown and depressurization.
"o RCS pressure is 1780 psig and trending DOWN.
"o RCS Tavg is 448 0 F and trending DOWN.
"o The RO determines that a safety valve on SG "A" is partially failed open.
"o RCS cooldown rate is approximately 40 0F/Hr and can NOT be reduced.
"o Pressurizer level is 35% and trending UP slowly.
Which one of the following actions will be required in accordance with ES-0.2?
A. Repressurize the RCS to minimize void growth.
B. Initiate Safety Injection and transition to E-2, Faulted Steam Generator Isolation.
C. Transition to ES-0.3, Natural Circulation Cooldown With Steam Void In Vessel (With RVLIS).
D. Transition to ES-0.4, Natural Circulation Cooldown with Steam Void In Vessel (Without RVLIS).
75
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 076 Given the following conditions:
"* The reactor has tripped.
"* A loss of offsite power subsequently occurs.
"* The operating crew has transitioned to ES-0.2, Natural Circulation Cooldown.
"* Letdown is isolated and cannot be restored.
"* The RO is commencing boration to shutdown boron concentration.
Which one of the following describes the method of ensuring sufficient boration under these conditions?
A. Commence cooldown to allow additional inventory addition and maintain Pressurizer level greater than 22%.
B. Maintain a small amount of Pressurizer spray flow to ensure mixing of Pressurizer and RCS.
C. Allow Pressurizer level to rise to no higher than 75% to accommodate the boric acid volume required.
D. Commence depressurization using normal spray flow to allow for additional RCS makeup flow from CVCS.
76
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 077 The Control Room has been evacuated due to a fire. The operating crew is performing the actions of 1OM-56C.4.B, Alternate Safe Shutdown Outside Control Room, using Train "B" equipment.
SG narrow range (NR) levels are 10% and trending DOWN in all 3 SGs.
Which one of the following describes the preferred method of maintaining secondary heat sink?
A. Maintain SG levels 25 - 50% NR by manually increasing Steam Driven Aux Feedwater Pump speed OR by manually throttling [HCV-1 MS-1 04],
Residual Heat Release Valve.
B. Maintain SG levels 25 - 50% WR by manually increasing Steam Driven Aux Feedwater Pump speed OR manually throttling [PCV-1 MS-1 01 A, B, C], SG Atmospheric Dump Valves.
C. Maintain SG levels greater than 50% NR by operating the Dedicated Auxiliary Feedwater Pump OR by manually throttling [HCV-1 MS-1 04],
Residual Heat Release Valve.
D. Maintain SG levels greater than 50% WR by operating the Dedicated Auxiliary Feedwater Pump QOR manually throttling [PCV-1 MS-1 01A,B,C],
SG Atmospheric Dump Valves.
77
EXAM BVPS-1 LOTS NRC BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 078 The Unit has sustained a main steam line break affecting all 3 SGs.
The operating crew is currently performing ECA 2.1, Uncontrolled Depressurization Of All Steam Generators.
The crew has throttled AFW flow to 50 gpm to each SG to minimize the RCS cooldown. Safety Injection Termination Criteria is NOT met.
The following conditions exist:
SG Level Pressure SG "A" 19% WR SLOWLY .1 320 psig DECREASING SG "B" 18% WR SLOWLY *, 310 psig DECREASING SG "C" 26% WR SLOWLY 1 380 psig INCREASING Which one of the following describes the required action and the reason for the action?
A. Transition to E-2, Faulted Steam Generator Isolation because there is an intact SG available.
B. Transition to FR-H.1, Loss Of Secondary Heat Sink because there is a RED condition on the Heat Sink Status Tree.
C. Transition to E-3, Steam Generator Tube Rupture because there is an unexplained increase in SG level.
D. Continue with ECA 2.1, Uncontrolled Depressurization Of All Steam Generators because Safety Injection termination is not complete.
78
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 079 Given the following conditions:
"* The Unit is at 100% power.
"* A discharge of [LW-TK-7A], SG Drains Tank is in progress.
"* The following alarms are received:
o [A4-71], Radiation Monitoring High o [A4-72], Radiation Monitoring High-High
"* [RM-1 LW- 04], Liquid Waste Effluent Monitor is the initiating alarm.
The PAB Operator reports that the local High-High alarm for RM-1 LW- 04 is lit.
All flow control valves and trip valves in the effluent line are open.
Which one of the following actions will be required next?
A. Direct the RO to place the liquid waste discharge to cooling tower blowdown mode control switch, HSS-1 LW-3 to 'OFF'.
B. Request Health Physics perform a calibration check or flash the detector with a portable source to determine validity of the alarm.
C. Request Health Physics immediately sample the tank contents to verify the release permit calculations.
D. Direct the PAB Operator to locally open the tank recirculation valve to stop the discharge.
79
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 080 Given the following conditions:
"* A LOCA has occurred.
"* "A" Train safety injection equipment is operating as required.
"* "B" Train is deenergized and safety injection equipment can NOT be started.
"* The Unit Supervisor has announced transition to E-1, Loss Of Reactor Or Secondary Coolant.
"* The Critical Safety Function Status Trees indicate the following:
"o Subcriticality Green "o Core Cooling Orange "o Heat Sink Yellow "o Integrity Orange "o Containment Orange "o Inventory Yellow Which one of the following actions shall be taken?
A. Transition to FR-C.1, Response To Inadequate Core Cooling.
B. Transition to FR-C.2, Response To Degraded Core Cooling.
C. Transition to FR-Z.1, Response To High Containment Pressure.
D. Continue in E-1 until transition to ES-1.2, Post-LOCA Cooldown And Depressurization to restore RCS inventory with available safety injection equipment.
80
BVPS-ILOT5 NRC EXAM Senior Reactor Operator Question 081 Given the following conditions:
"* The Unit is at 68% power.
"* A loss of station instrument air has occurred.
"* The operating crew is performing the actions of AOP-1.34.1, Loss Of Station Instrument Air.
"* The following alarm is received in the Control Room:
o [A1-56], STEAMLINE STOP VALVE NOT FULLY OPEN The crew trips the reactor and enters E-0, Reactor Trip Or Safety Injection. The cause is identified and station instrument air pressure has stabilized at 50 psig.
Which one of the following describes how Tavg will be controlled in E-Q?
A. Condenser steam dumps in 'Plant Trip' Mode B. Condenser steam dumps in 'Pressure Control' Mode C. Steam generator atmospheric dump valves D. Steam generator safety valves 81
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 082 Given the following conditions:
"* The Unit is performing a plant heat up with RCS temperature at 175 0 F.
"* RCS heat up rate is 5 0F per hour and will be maintained at this rate until no-load temperature is achieved.
"* It is reported that [1QS-38], QS Chem Inj PP 4A & 4C Suct Isol Valve is locked shut.
In accordance with the reference provided, what action, if any, is the minimum required to satisfy Technical Specifications?
A. Immediately reduce RCS temperature to less than 140 0 F.
B. Open and lock open 1QS-38 within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
C. Open and lock open 1 QS-38 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
D. No actions are required, this is the required position for 1QS-38.
82
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 083 Given the following conditions:
"* The Unit is operating at 90% power. All systems are in NSA.
"* "A"Main Feed Pump has tripped.
"* The PO determines that the heater drain pumps and condensate pumps are operating normally.
"* The Unit Supervisor refers to AOP-1.24.1, Loss Of Main Feedwater.
Which one of the following actions is required in accordance with AOP-1.24.1, Loss Of Main Feedwater?
A. Trip the reactor and enter E-0, Reactor Trip Or Safety Injection.
B. Reduce turbine load to less than 60% in accordance with AOP-1.51.1, Emergency Shutdown.
C. Check the proper operation of [FCV-1 FW-150A], Main Feed Pump "A" Recirculation Valve.
D. Determine if suction pressure is adequate to attempt restart of "A" Main Feed Pump.
83
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 084 Given the following conditions:
- Unit 1 is in Mode 6.
- Unit 2 is in Mode 1 with all systems in NSA.
- Movement of irradiated fuel is ongoing in the Unit 1 Containment.
- [RM-1 RM-218A], Control Room Area Monitor has failed LOW.
- The FAIL light for the radiation monitor is 'OFF'.
In accordance with Technical Specification 3.3.3.1 (attached), what action, ifany, is required for the above conditions?
A. No action is required because the monitor is not required to be operable for this condition.
B. Within ONE hour the respective Unit 2 Control Room monitor train shall be verified operable.
C. Within ONE hour, verify that RM-1 RM-218B, Control Room Area Monitor is operable.
D. Within ONE hour, suspend all operations involving movement of irradiated fuel.
84
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 085 The Unit is in Mode 1. All systems are in NSA.
Which one of the following conditions requires the EARLIEST action in accordance with Technical Specifications?
A. [CH-TK-1A], Boric Acid Storage Tank boron concentration is 6800 ppm.
B. Refueling Water Storage Tank boron concentration is 2355 ppm.
C. LHSI Pump "A" is inoperable.
D. Charging Pump "A" suction flow path from the RWST is inoperable.
85
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 086 Given the following conditions:
- The Unit is at 100% power. All systems are in NSA.
- The following annunciator is received in the Control Room:
o [A4-9], PRESSURIZER CONTROL PRESS HIGH The RO determines that [PI-1 RC-445], Pressurizer Pressure Transmitter is failing HIGH.
Assuming NO action by the crew, which one of the following describes the plant response?
A. One PORV will open.
B. Two PORVs will open.
C. Backup heaters will deenergize and spray valves will open.
D. Backup heaters will deenergize, spray valves will open, and 1 PORV will open.
86
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 087 Given the following conditions:
"* The Unit is in Mode 1.
"* Spent Fuel is being loaded into shipping casks in the Spent Fuel Pool area.
Health Physics reports that a cask has been dropped. Immediately following the report, the Fuel Building evacuation alarm sounds.
[RM-1 VS-1 03A and B], Fuel Building Ventilation Exhaust Monitors are in alarm.
Based on the above conditions, which one of the following actions is required by AOP-1.49.1, Irradiated Fuel Damage?
A. Initiate site evacuation.
B. Manually initiate Control Room isolation.
C. Reset CREBAPS and verify Control Room ventilation automatically realigns.
D. Align leak collection exhaust flow to the main filter banks using the Containment Purge System.
87
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 088 Given the following conditions:
"* The Unit is at 100% power. All systems are in NSA.
"* [PI-1SA-101], Station Air Main Header Pressure has been slowly decreasing and is indicating 98 psig.
"* The operating crew enters AOP-1.34.1, Loss Of Station Instrument Air.
"* Both station air compressors are running. No reports of air leakage have been received.
Which one of the following actions will be performed next in accordance with AOP-1.34.1?
A. Bypass the instrument air dryers.
B. Verify that the diesel air compressor has started.
C. Verify [TV-I SA-1 05], Station Air Compressor Header Isolation Valve is closed.
D. Trip the reactor and enter E-0, Reactor Trip Or Safety Injection.
88
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 089 Given the following conditions:
- You are required to make an entry to a Locked High Radiation Area.
- The job is planned to take 20 minutes to complete with 5 minutes transit time each way.
- Transit path radiation levels are 400 mr/hr.
- Work area radiation levels are 1200 mr/hr.
Which one of the following conditions describes your eligibility to perform this task?
A. You may perform this task provided you are signed onto a High Radiation Area RWP.
B. You may not perform this task because you will exceed the BVPS TEDE limit.
C. You may perform this task provided you meet the requirements for a Planned Special Exposure (PSE).
D. You may not perform the task because your current year to date exposure is already within 80% of the BVPS Administrative TEDE Limit.
89
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 090 Given the following conditions:
"* The Unit was at 100% power when a turbine trip and loss of power to both 4KV emergency busses occurs.
"* BOTH emergency diesel generators failed to start.
"* Reactor power indicates 95% and stable.
"* SG safety valves are open.
Which one of the following describes the procedure usage for this event?
A. Enter E-0, Reactor Trip Or Safety Injection. If reactor trip cannot be verified, transition to FR-S.1, Response To Nuclear Power Generation/ATWS to initiate emergency boration.
B. Enter E-0, Reactor Trip Or Safety Injection. If reactor trip cannot be verified, initiate emergency boration to shut down the reactor. Enter FR-S. 1 when directed to monitor CSF Status Trees upon restoration of power.
C. Enter ECA-0.0, Loss Of All AC Power. If reactor trip cannot be verified, transition to FR-S.1 to initiate emergency boration.
D. Enter ECA-0.0, Loss Of All AC Power. If reactor trip cannot be verified, continue in the EOP. Transition to FR-S.1 when directed to monitor CSF Status Trees upon restoration of power.
90
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 091 An event has occurred resulting in a Site Area Emergency.
Health Physics assistance is required for a task being performed in the Auxiliary Building.
Which one of the following Emergency Response Facilities will supply Radiation Control personnel to support the task?
A. Control Room B. Technical Support Center C. Operations Support Center D. Emergency Operations Facility 91
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 092 An oil spill has occurred at the site.
Approximately 10 gallons of diesel fuel oil was spilled in the containment area around the Diesel Fuel Oil Storage Tank.
Which one of the following correctly describes the personnel/agencies that must be notified in accordance with AOP-1/2.75.6, Oil Spill?
A. BVPS Environmental Services B. Nuclear Regulatory Commission C. Pennsylvania Department of Environmental Protection D. Operations Manager and Plant General Manager 92
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 093 A Unit startup is in progress per 1OM-52.4.A, Raising Power From 5% To Full Load Operation when a loss of instrument air occurs. The operators are performing AOP-1.34.1, Loss Of Station Instrument Air when the main feedwater regulating valves close and a reactor trip occurs.
Which one of the following describes the procedure transitions for this event?
A. 1 OM-52.4.A usage is suspended. AOP-1.34.1 is completed followed by entry to E-0, Reactor Trip Or Safety Injection.
B. 1OM-52.4.A usage is suspended. AOP-1.34.1 is performed until a RED or ORANGE path condition requires entry to a functional recovery procedure.
C. E-0, Reactor Trip Or Safety Injection is entered and exited when directed to another specific procedure. AOP-1.34.1 may be performed to aid in plant recovery.
D. ES-0.1, Reactor Trip Response is entered and exited when directed to procedure and step in effect. AOP-1.34.1 may be performed to aid in plant recovery.
93
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 094 Given the following conditions:
"* The Unit is operating at 100% power.
"* No. 1 EDG has been out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and is expected to return to service in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
" It is discovered that there is no documentation of the last monthly surveillance on the No. 2 EDG. The most recent documentation is 47 days old.
Which one of the following actions, if any, is required?
A. Perform the missing surveillance to verify the operability of No. 2 EDG within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or take additional action in accordance with TS 3.8.2.1.
B. Perform the missing surveillance to verify the operability of No. 2 EDG within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or take additional action in accordance with TS 3.8.1 .1.
C. Declare No. 2 EDG inoperable and immediately take action in accordance with TS 3.0.3.
D. No action required. Because the EDGs are on a staggered test basis, No.
2 EDG is still within the required time interval for operability determination.
94
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 095 Given the following:
"* Planned Maintenance on a system requires a portion of the system to be taken out of service for several days.
"* A fire hose will be installed to bypass the affected portion of the system.
"* The changes to and operation of the system will be considered extensive.
"* The changes to the system for this maintenance are one-time only.
Which one of the following document alterations is to be used for this evolution?
A. Temporary Procedure B. Significant Change Procedure Revision C. Simple Change Procedure Revision D. Procedure Correction 95
BVPS-1 LOT5 NRC EXAM BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 096 Given the following conditions:
- You are the Shift Manager.
- The Control Room is being evacuated due to a fire.
- Control can NOT be established from the Emergency Shutdown Panel.
- 1OM-56C.4.B, Alternate Safe Shutdown Outside Control Room is being implemented using Train "A" equipment.
Which one of the following describes the method used to direct shutdown activities once the Control Room is evacuated?
A. Proceed to the Fire Brigade Room, turn over Emergency Director responsibility to the STA, initiate contact with Operations personnel by radio, and proceed to the Backup Indicating Panel to monitor plant parameters.
B. Proceed to the Technical Support Center and direct Operations activities using the "Appendix R" phone.
C. Perform the appropriate procedure to align plant equipment and proceed to the Backup Indicating Panel to monitor plant parameters and direct action using the radio or "Appendix R" phone.
D. Proceed to the Operations Support Center until the Emergency Response Organization is activated, and then report to the Fire Brigade Room to direct activities using the "Appendix R" phone.
96
BVPS-1LOT5 NRC EXAM Senior Reactor Operator Question 097 The reactor is tripped. Safety Injection is actuated. All equipment is operating as designed.
Which one of the following describes the reason that RCPs are tripped on RCS to highest SG Delta-P?
A. Operation of RCPs with Delta-P less than minimum may mask subsequent SGTRs and give false indication of adequate RCS inventory.
B. Low RCS to SG Delta-P is an indication that a LOCA is in progress for which continued operation will result in damage to the RCPs.
C. RCP operation during loss of RCS pressure caused by a SBLOCA may result in core uncovery if the RCPs were tripped later in the event.
D. Once RCS pressure is below SG pressure, ECCS flow provides more efficient RCS heat removal. Operation of the RCPs may impede the RCS inventory recovery provided by ECCS.
97
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 098 Given the following conditions:
"* The Unit is in Mode 5.
"* A loss of RHR has occurred.
"* The operating crew has been unable to maintain an RHR pump operating and is preparing to repressurize the RCS in preparation for providing heat removal with "A" SG.
"* The crew is directed to check OPPS in service prior to pressurizing the RCS.
"* RCS pressure is 290 psig and rising slowly.
"* RCS temperature is 195 0 F and rising slowly.
Which one of the following satisfies the Technical Specification requirement for checking OPPS in service under these conditions?
A. One PORV armed for OPPS. PORV should be closed.
B. One PORV armed for OPPS. PORV should be open.
C. Two PORVs armed for OPPS. PORVs should be closed.
D. Two PORVs armed for OPPS. PORVs should be open.
98
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 099 Given the following conditions:
"* A LOCA has occurred.
"* Safety Injection was lost and containment radiation increased to 3E+5 R/Hr.
"* Safety Injection has been reestablished and containment radiation is now 2E+3 R/Hr and trending DOWN.
Which one, if any, of the following describes the correct use of Adverse Containment parameter values for this event?
A. Not required during any part of this transient.
B. Required when the dose rate limit was exceeded, but are no longer required when the dose rate is below the limit.
C. Required as soon as the dose rate limit was exceeded, and remain in effect for the duration of the event because the total integrated dose is unknown.
D. Required as soon as the dose rate limit was exceeded, and remain in effect for the duration of the event because since the dose rate limit was exceeded, the total integrated dose was also exceeded.
99
BVPS-1 LOT5 NRC EXAM Senior Reactor Operator Question 100 Given the following conditions:
"* A Small Break LOCA has occurred.
"* The operating crew is performing the actions of ES-1.2, Post LOCA Cooldown And Depressurization.
"* Both LHSI pumps have been stopped.
"* One HHSI pump has been stopped.
"* Normal charging is aligned.
"* The crew is depressurizing the RCS.
"* When the depressurization is stopped, the following conditions exist:
"o RCS subcooling is 40°F and trending DOWN.
"o Pressurizer level is 18% and trending DOWN.
Based on these indications, what actions are required?
A. Isolate letdown. Check to ensure Pressurizer level stabilizes above 18%.
B. Manually start SI pumps as necessary to regain subcooling.
C. Reinitiate SI and verify all safeguards equipment has actuated.
D. Increase RCS pressure using Pressurizer heaters to regain subcooling.
100
0-1 Io co.
- I
.1 I- I
- I
-I p, I w.j
- 1 IN 0 II
Critical Boron Concentration vs Burnup HFP, ARO, Equilibrium Xenon Unit 1, Cycle 15 1,600 0 E 1,400 CL I')
)
o 1,200
(' I
.1 S1,000
=<
)
800 if 0
0 600
- '- 400
(*
(D 200 C-)
0 a.
-4 C') 0 CD Q$ 0s
& 0 & , sp c? 9oc~61 0w CD 1N.ý ctý, l 0 .i Cycle Burnup (MWD/MTU) CA)
HZP Differential Boron Worth vs Boron Concentration Unit 1, Cycle 15
-6.5 ii 11111 ii ii ii iii iI lii I III I Iii[II 1111111 I I I 150 MW /T 10000 MWD/MTU E-7.0 0 C
0 18740 MWD/MTU m
-*7.5 Ir IIIIIIL 00 1.1 j 4-11 11 111 LL
-lLLL 0 0
r -8.0 IIIIII-1.4- 1 i i i i 1 .1 1.114-4-4 4 1 ,-1 ...1.I.-H I I i i i . .... ..I , , , II III 0
60 Ul) 0
,-8.
-9.0 I 2L 0.
CD
-t 0
-9.5 cn 0-,
CD a,
0 Boron Concentration (ppm)
U
CURVE BOOK - BVPS I CB-21 Record Type # A9.345D POWER DEFECT vs PERCENT POWER at BOL, MOL, and EOL Unit 1, Cycle 15
-3000 0 ppm TA
-2800 200 ppm
+
I I till][ I +
IT II I It it -V _2ý4+11A
-2600
++
+1 400 ppm
... ... M MIF 4:1:m
-2400 + 600 ppm 11 t i l l
+H+ --+H+-- 4+ 1H+ f --#4T - it 11
-2200 800 ppm Hit""' --- 44H+++ -H+F+l -4+H+H+t
+ till -- ++4++
t i l l I I I II Iiii t i ll f i ll I till
-2000 1000 ppm
+++ It- -----
-+H+ + +1+-F _44+ All 1200 ppm "r= -1800 - 11111I1I11 st i l l I .9 Ii II I I..
I ll .
II.
- " H iiiii H ii .... ..... I. .... All f II IAul 4,'H4:F+,
Hiiiiii Will 1400 ppm
- -1600 It I l i l l II 4T TEV 1600 ppm
+
H ii ý1 pill 1800 ppm D -1400 HiMs + t i l l 1 11 1 2000 ppm T #
0 -- 4+4--- 4 0.. -1200 4+1 --- 4 oooo #:F
-1000 T: 44-11111111+
-800 i
_:+/-H+Hjf
-- ------- TI ::+FF[+H4+
-#4
-600 I....... ..... . ............
-ut, 6.ý e 4+4ý o"I I I I I IlL 400 .I .
Hit!- +1+ + +
t il l I Il l
-200 ILL T T
0 0 10 20 30 40 50 60 70 80 90 100 Power Level (percent of full power)
FOR TRAINING USE ONLY Issue 15 Rev 0
Boron Worth vs Burnup ARO, HFP, Critical Boron Unit 1, Cycle 15
-6.2
-6.4 0 -6.6 T*- I ,,,,
a.-6.8 III i I
-7.0 E -7.2 0
M-7.4 INI t
0 C
0 -7.6
-7.8 0D 0
-8.0 C
- 0 CD 0, -8.2 CD B p(
mco Burnup (MWDIMTU)
CURVE BOOK - BVPS I CB-30 Record Tvwe #9A.345D 1000-7 17.1 2000 r- 3q. 3 900 - 15.4 1900 --- 32.6 800 ý- 13.7 1800 - 30.9 700 -I- 12.0 1700 - - 29.1 0
a.. ,.. CD c:)
600 10.3 o C 1600 .-- 27.4 -_J u tJ I
tLJ uJ co 500 8.6 , 1- 1500 - 25-.7 ,
C CD) 1 400 6.9 C C-1) 1400 " "
2q.o0 .
-- uJO cl-C-t C.,
300 5.1 1300 22.3 200 - 3.11 1200 - S20.6 100 i- 1.71 il00 -'-' 18.9 0 - - 0.0 1000 - - 17.1 BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP "ISSUE15 REV 0
CURVE BOOK - BVPS I CB-31 Record Type #9A-345D 3000
-700
-600 4500
- 500 3600
-'400 3000
- 2500
,, _14 8.33 ::
(7-in 2100 -
- 300
"-200
,.1 1500 (3 - 2000 IS
_5
-s 900 S - 100 *
'3 90 ~
- 1500 40 600 - - 80 .
-70
- 0 - 60 .
so a 50 "
a-300-
-%- 1000 30 150- 20
- 5OO 15 100 L 10 10 BORON ADDITION (refer to figure CB-36 for correction factors)
(refer to 1OM-6.5.B.6, Table 6-6, "RCS Volume") I FOR TRAINING E 0NLY COTROLLED ISSUE 15 REV 2 BYPO UNOT iI
CURVE BOOK - BVPS I CB-32 Record Type #9A.345D
- 10
- 00 60 500 55 so 00 -45
-500 300 1-- 35
-30
-27
-1000 200 S2'
-21 dc 52-* (7000-C) dt H ISO 5-8
- a i- U;
,-)
-1500 100 -- 12 IA 0 90 80 a-0C 70 2000 60 7 50 6 15
-2500 30 25-K
-3000 3 BORON ADDITION RATE.
(refer to figure CB-36 for correction factors)
FOR TRAINING USE ONLY I (refer to O1M6.5.-B.6, Table 6-6, "RCS Volume")
CONTROIILLEDii BVPS I1 O ISSUE 15 REV 2
CURVE BOOK - BVPS I CB-33 Record Type IM9A345D Ii' 1'
Is
-15 I0-7 20
- 30 30 50
-- '0 so W 8.33 Cf
- 50
-- 60 100--
80 100 300 I .5 -I 500
-200 2 3
5 1000 I0 15
- 500 20 30 3000 50-5000
I000 too 200 10.000 300 500 30,000
-2000 E,3000 BORON DILUTION 50,000 PPm soORON (C 1i - Cf) DILUTION IN COOLANT WATER GAL.
(CO) (v,)
BORON DILUTION (refer to figure CB-36 for correction factors)
(refer to I OM-6.5.B.6, Table 6-6, "RCS Volume") I FOR TRAINING USE ONLY BISSUE 15 REV 2 BP ~UNT II
CURVE BOOK - BVPS I CB-34 Record Type #9A.345D
-- 3000 700 200 Soo.
S2000 400
- 1500 300 I so 200
- 1000 1so 100 -- 100 70 90
- 500 50 -"80 30 dc S00 CY 30 dt H 70 20 60 15
- 200 50 -- 50
.7=
5- '10
- 100 4
- 60 -3 30
- 60 2 i S 5 0 1 5.5
- 0 1 20 S30 COOLANT 01LI rtON RATE
(,i*lr. IAIPPNIHR 20 Is I5 10 F- 10 PPM BORON IN COOLANT OILUTION WATER FLOW,.OPX (C)
(Y)
BORON DILUTION RATE (refer to figure CB-36 for correction factors)
(refer to IOM-6.5.B.6, Table,6-6, "RCS Volume")
FR ING USEJONL
CURVE BOOK - BVPS I CB-36 Record Type #9A.345D NOMOGRAPH CORRECTION FACTORS Plant Conditions Correction Factor Pressure T (AVG) (K)
(psig) (OF) Pressurizer Level (See Note) 2235 547-570 Normal Operating 1.00 1600 500 No-Load 1.05 1200 450 No-Load 1.10 800 400 No-Load 1.16 400 350 No-Load 1.18 400 300 No-Load 1.20 400 300 Solid Water 1.35 400 200 No-Load 1.28 400 200 Solid Water 1.40 400 100 Solid Water 1.47 NOTE: CORRECTION FACTORS ARE APPLIED AS FOLLOWS:
(a) Boron Addition and Dilution Total Volume Nomographs V(Corrected) = K X V(Nomograph)
(b) Boron Addition and Dilution Rate Nomographs dc 1 de dt (Corrected) K x dt (Nomograph)
FOR TR NUSEONLY ISSUE 15 REV 0
_ _ ~ ~ 1-C zi zztz L zL r
-t fr __ -
__ V ii
-- 1- -i I ME WI! t WIii z' 4
+
F 1
14 :11 4
T I
1 -
on
_ I
__ -- 4
__ 4 7
___ ____ I I I 2 J
I t _ I _____ __ _____________
IF _ 2- ;ytybfJL j__-YLAr- =11VI
SYMPTOMATIC RESPONSE/UNEXPECTED CONDITIONS E-3 (Issue IC, Revision 2)
- 1. SI REINITIATION CRITERIA Manually operate SI pumps and align valves as necessary and GO TO ECA-3.1,
"*SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired', Step 1, if EITHER condition listed below occurs:
- On ICCM RCS subcooling based on core exit TCs - LESS THAN 46F [54F FOR ADVERSE CNMT] (If less, refer to Attachment 6-A)
.. PRZR level - CANNOT BE MAINTAINED GREATER THAN 18% [37% FOR ADVERSE CNMT]
- 2. SECONDARY INTEGRITY CRITERIA GO TO E-2, Faulted Steam Generator Isolation", Step 1, if any SG pressure is dropping in an uncontrolled manner or has completely depressurized, and has not been isolated unless needed for RCS cooldown.
- 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION GO TO ES-1.3, "Transfer Cold Leg Recirculation", Step 1, if RWST level reduces to less than 19 FEET.
- 4. AFW SUPPLY SWITCHOVER CRITERION Monitor PPDWST (WT-TK-1O] for AFW pumps supply. Upon reaching low level alarm, 27.5 FEET, refer to Attachment 2-H for makeup.
- 5. MULTIPLE TUBE RUPTURE CRITERIA RETURN TO E-3, "Steam Generator Tube Rupture", Step 1, if any intact SG level rises in an uncontrolled manner or any intact SG has abnormal radiation.
- 6. ADVERSE CONTAINMENT CRITERIA
"* CNMT pressure - GREATER THAN 5.0 PSIG
-OR
"* CNMT radiation on [RM-1RM-219A(B)] - GREATER THAN 1E+5 R/HR
-OR
"* Integrated CNMT radiation - GREATER THAN 1E+6 R FOR TRhANIN USE ONL
BVPS - LOP EOM-53A. 1.E-3(ISS1C)
Number Title E-3 Steam Generator Tube Rupture Issue 1C Revision 2 STEPi I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED CAUTION RCS and ruptured SGs pressures must be maintained less than the ruptured SGs atmospheric steam dump setpoint to prevent offsite releases.
..... 11---------------------
When letdown is in service, charging flow should be maintained greater than 30 GPM to ensure adequate letdown cooling and prevent letdown from flashing to steam.
i^I A* Control RCS Pressure And Charaing FlOW I0 Minimize tS--Iu-ac0.uarua
- a. Perform appropriate actions from table:
RUPTURED SG NR LEVEL RISING DROPPING OFFSCALE HIGH
-v I. I LESS THAN 32% "* Raise Raise 0 Raise flow charging S50% ADVERSE charging flow charging
- Depressurize flow
- Maintain RCS &
NMT] ruptured SGs RCS using Step 31.b pressures equal P
R BETWEEN 32% Depressurize RCS Turn ON Maintain RCS &
Z [50% ADVERSE using Step 31.b PRZR ruptured SGs R CNMT] AND 50% heaters pressures equal L Maintain RCS &
E BETWEEN 50% a Depressurize Turn ON AND 754 (61% RCS using PRZR ruptured SGs V pressures equal E ADVERSE CNMT] Step 31.b heaters L . Lower charging flow GREATER THAN Lower charging Turn ON Maintain RCS &
75% [614 flow PRZR ruptured SGs ADVERSE CNMTI heaters pressures equal
- I _________________________ I ________________ a (step continued next page) 1E3 5131/02 29 of 39 FO TRA UINISE ONLY I
CONTAINMENT SYSTEMS CHEMICAL ADDITION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 The chemical addition system shall be OPERABLE with:
- a. A chemical addition tank containing at least 4700 gallons of between 19.5 and 20 percent by weight NaOH solution, and
- b. Two chemical injection subsystems each capable of adding NaOH solution from the chemical addition tank to a containment quench spray system pump flow.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one chemical addition subsystem inoperable, restore the subsystem to OPERABLE status within 72 hours or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the chemical addition subsystem to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.3 The chemical addition system shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. By verifying, that on recirculation flow, each pump develops a flow between 25 and 35 gpm when tested pursuant to Specification 4.0.5.
FOR TRAINNG USE ONLY BEAVER VALLEY - UNIT 1 3/4 6-15 Amendment No. 163
INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
- a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
- b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
- c. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
FOR TRAININUSE ONLY BEAVER VALLEY - UNIT 1 3/4 3-33 Amendment No. 129
TABLE 3.3-6 DPR-66 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT(3) RANGE ACTION
- 1. AREA MONITORS
- a. Deleted I
- b. Containment
- i. Purge & Exhaust 2 (2) : 1.6 x 103 cpm 10- 106 cpm 22 Isolation (RMVS 104 A & B) ii. Area (RM-RM-219 2 1,2,3 & 4 *1.5 x 104 R/hr 1 - 107 R/hr 35 A & B)
- c. Control Room Isolation 2 1,2,3,4 < .47 mR/hr 10-2 _ 103 41 va (RM-RM-218 A & B) and (4) mR/hr
- 2. PROCESS MONITORS
Particulate Activity 1 1,2,3& 4 N/A 10 - 106 cpm 20 ii.
RCS Leakage Detection Co (RM 215A) m b. Deleted 0
z-BEAVER VALLEY - UNIT 1 3/4 3-34 Amendment No. 246
DPR-66 TABLE 3.3-6 (Continued)
TABLE NOTATIONS (1) (Not used)
(2) During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.
(3) Above background.
(4) During movement of irradiated fuel assemblies and during movement of fuel assemblies over irradiated fuel assemblies.
ACTION STATEMENTS ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 21 This Action is not used.
ACTION 22 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 35 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
a) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and b) Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
ACTION 41 - a) With the number of Unit 1 OPERABLE channels one less than the Minimum Channels OPERABLE requirement:
- 1. Verify the respective Unit 2 control room radiation monitor train is OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 31 days.
OR TRAIN'I USE ONLY BEAVER VALLEY - UNIT 1 3/4 3-35 Amendment No. 246
TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTION 41 (Continued)
- 2. With the respective Unit 2 control room radiation monitor train inoperable, suspend all operations involving movement of irradiated fuel assemblies and movement of fuel assemblies over irradiated fuel assemblies within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore the Unit 1 control room radiation monitor to OPERABLE status within 7 days or isolate the control room from the outside atmosphere by closing all series air intake and exhaust isolation dampers, unless the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.
b) With no Unit 1 control room radiation monitors OPERABLE:
- 1. Verify both Unit 2 control room radiation monitors are OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 31 days.
- 2. With either Unit 2 control room radiation monitor inoperable, suspend all operations involving movement of irradiated fuel assemblies and movement of fuel assemblies over irradiated fuel assemblies within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore the respective Unit 1 control room radiation monitor train to OPERABLE status within 7 days or isolate the control room from the outside atmosphere by closing all series air intake and exhaust isolation dampers, unless the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.
- 3. With no Unit 2 control room radiation monitors OPERABLE, immediately isolate the combined control room by closing all series air intake and exhaust isolation dampers and be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
FOR TRAINING USE ONLY BEAVER VALLEY - UNIT 1 3/4 3-35a Amendment No. 241