ML13088A275
| ML13088A275 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/08/2013 |
| From: | Operations Branch I |
| To: | Entergy Nuclear Vermont Yankee |
| Jackson D | |
| Shared Package | |
| ML13017A074 | List: |
| References | |
| TAC U01898 | |
| Download: ML13088A275 (149) | |
Text
Question #1 Vermont Yankee LOI Exam Bank Ouestion Number 5878 Revision 1 Instructor Guide: LOT-OO-602 OPERATIONAL TRANSIENT PROCEDURES Objectives: CRO EO-3, EO-5
References:
OPOT-31l8, (page 4 Note)
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000150504 Respond to Recirculation Pump Trip 2027050201 Perform Flow Indication Check Prior to Startup (RX) or Recirc Pump Startup 295001 AK2.07 Knowledge of the interrelations between and the following 3.4 3.4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: (CPR 41.7, 45.8): Core flow indication Question:
A plant startup is in progress with the plant at 10% power when the 'A' recirc pump trips.
The 'A' recirc discharge valve (RV-53A) is SHUT by the CRO and then OPENED for 3 seconds.
Total jet pump flow as indicated on DPR/FR-2-3-91 is to the left of the natural circulation line on the power to flow map.
lAW OPOT-3118-0l Recirculation Pump Trip, what is the reason for this indication?
The flow summer is subtracting positive flow through the idle loop jet pumps.
discharge valve is not full open or recirculation pump field breaker opens after a single pump trip, the reverse flow summer is designed to compensate for the resulting reverse flow in the idle loop.
However, some single loop conditions than 5 mlblhr or 14 drive flow
in operating loop) result in positive flow through the idle jet pumps. If positive flow through the idle jet pumps occurs, actual core flow will be greater than the core flow indicated on the TOTAL JET PUMP FLOW RECORDER (DPRIFR 2 3 95).
- b. The flow summer is subtracting reverse Incorrect - Plausible as the summer is flow through the idle loop jet pumps.
providing a calculation input to the PIF map but it is the positive flow under these specific conditions.
- c. A jet pump mixer has been displaced.
Incorrect - Plausible due to transient, but this would cause an INCREASE in indicated jet pump total flow, though student could think that bypassing the core would result in less flow not understanding where measured. (see ON 3141)
- d. The recirculation flow comparator is Incorrect - plausible, The flow comparator compensating for the natural circulation in does not compensate for idle loop the idle loop.
operation.
Static Simulator Exams: None Last Revised: 1-29-13, BLS.
Question #2 Vermont Yankee LOI Exam Bank Question Number 7588 Revision 1 Instructor Guide: LOT-00-602 OPERATIONAL TRANSIENT PROCEDURES Objectives: K3.01
References:
OPOT-3122-01, Step 3.6 VY 2009 NRC exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2007020501 Respond to Loss of Normal Power 295003 AA2.04 Ability to determine and/or interpret the following as they 3.5 apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER: AA2.04 Question:
A Loss of Offsite power has occurred and the following conditions exist:
- 'A' Diesel Generator started and is supplying its bus
- 'B' Diesel Generator started but did. NOT close in on its bus due to a fault on the bus
- No buses have been cross-tied
- Access to the reactor building is restricted IA W OT 3122, Loss of Normal Power, which ONE of the following actions is required for supplying the Vital AC Bus and why is this action taken?
- a. Transfer the Vital MG to the AC Drive Incorrect - Incorrect there is no power motor to minimize station DC loads on the supply to 480 VAC Bus 8 (8B).
Station Battery.
Transfer the Vital AC Bus to its alternate Correct Response- - With the loss of 480 source to minimize station DC loads on the VAC Bus 8 (8B) the Vital AC MG set Station Battery.
swaps from the AC supply to the DC Supply to minimize the load on the station batteries OT 3122 directs to the
- II' supply.
- c. Adjust the 'A' EDG frequency as required Incorrect - Incorrect the A EDG supplies to obtain a steady state 59.7 to 60.5 Hz to 480 VAC Bus 9, adjusting voltage on that permit the Vital AC Bus to automatically EDG will have no effect.
transfer to the AC Drive.
- d. Adjust the 'A' EDG frequency as required Incorrect - Incorrect the A EDG supplies to obtain a steady state 59.7 to 60.5 Hz to 480 V AC Bus 9, adjusting voltage on that prevent the Vital AC Bus from EDG will have no effect.
automatically transferring to the DC Drive.
Static Simulator Exams: None Last Revised: 1-29-13, by Stewart, Brian
Question #3 Vermont Yankee LOI Exam Bank Question Number 995 Revision 1 Instructor Guide: LOT-00-263 DC ELECTRICAL DISTRIBUTION SYSTEM Objectives: K3.01, K3.02, K3.03
References:
OPON-3159-01, pages 2 & 3; OP 2145 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2007350404 Respond to a Loss of DC-l 295004 AA1.02 Ability to operate and/or monitor the following as they 3.8 4.1 apply to PARTIAL OR COMPLETE LOSS OF D.C.
POWER: (CFR 41.7, 45.6): Systems necessary to assure safe shutdown Question:
The plant has experienced a small break LOCA and LNP.
The EOPs have been entered.
- Both Emergency Diesel Generators (EDG) are running loaded
- High Pressure Coolant Injection (HPCI) is injecting at 2000 GPM
- Reactor Core Isolation Cooling (RCIC) is injecting at 350 GPM Subsequently, a loss of DC-l occurs.
How is the operation of HPCI, RCIC, and the EDGs affected?
- a. The HPCI and RCIC high level trips would Incorrect - control power is lost to the "B" not function.
EDG not the "A". Control power to the The control power to "A" EDG would be "A" EDG is DC-AS2.
lost.
- b. The HPCI high level trip would not Incorrect RCIC high level trip is also lost function, RCIC high level trip would be and the "B" EDG loses control power.
unaffected.
The control power to "A" EDG would be lost.
The control power to the "8" EDG would be lost.
The HPCI and RCIC high level trips would not function.
The control power to the "8" EDG would be lost.
Static Simulator Exams: None Last Revised: 1-29-13, 8LS Incorrect - HPCI high level trip is also lost Correct - HPCI and RCIC high level trip would not function. The control power to the "8" EDG would be lost.
Question #4 Vennont Yankee LOI Exam Bank Ouestion Number 1127 Revision 1 Instructor Guide: LOT-01-262 4 KV ELECTRICAL DISTRIBUTION SYSTEM Objectives: CRO 8
References:
OP 2142 Must integrate the following:
- Know the start of transfer logic
- Know sync check is required for fast transfer
- Understand residual bus transfer does not require a sync check Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Comprehension Task Associations 2627400401 Respond to Loss of Fast Transfer SYNCHRO Check Relay 295005 AA2.08 Ability to detennine andlor interpret the following as they 3.2 apply to MAIN TURBINE GENERATOR TRIP: AA2.08 Electrical distribution status.
Question:
- A reactor startup is in progress with the generator synchronized to the grid and operating at 40% power.
- Computer point D619 (Bus 1 Sync-check relay) prints out in the alann (LOSS) state.
- Ten minutes later, the main generator trips and locks out.
Based on the above, how does the A.C. electrical system respond?
Recirc MG 'B' drive motor breaker will trip, on bus undervoltage.
transfer of Bus 2 is satisfactory.
Bus 1 Residual bus transfer will occur.
Correct - Residual transfer does not require the sync-check.
- c. Reactor feedwater pump 'B' will trip when Incorrect - 'B' RFP is powered from bus 1 Bus 1 voltage decays to 1000 volts, and then it trips in 0.3 sec before Bus 1 after a 5 second to <1000 VAC
d'l Bus 1 Automatic fast transfer will occur.
Incorrect - Requires sync-check relay.
Static Simulator Exams: None Last Revised: 1-29-13, BLS
Question #5 Vermont Yankee LOI Exam Bank Question Number 3531 Revision 6 Instructor Guide: LOT-00-61O EOP-l, RPV CONTROL; EOP-2, ATWAS RPV CONTROL Objectives: CRO 3
References:
EOP-2 and study guide section 7 page 39; HCO-The operator must analyze the current reactivity conditions and conclude the present and future state to correctly determine the correct answer.
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 4 Question Level: Comprehension Task Associations 2000200501 Respond to ATWS Event( s) 295006 AKl.02 Knowledge of the operational implications of the 3.4 3.7 following concepts as they apply to SCRAM: (CFR 41.8 to 41.1 : Shutdown Question:
A failure to scram has occurred.
The crew is taking actions per EOP-2, ATWS RPV Control.
The following conditions exist:
- RPV pressure is being maintained 800-1000 psig with SRVs
- RPV level is being maintained -19 inches to +90 inches with feed pumps
- Initial SLC tank level was 92% when it was injected into the RPV The SLC tank level is currently 70%
- Rods are being inserted manually, with 40 rods still at position 48 lAW the EOP-2 study guide, which of the following statements is true?
cooldown should be started.
- d. The reactor is not shutdown until SLC tank level is 67% at which point a cooldown may be started.
Static Simulator Exams: None Last Revised: 1-29-13, BLS CSDBW injected which would be 62%
SLC tank level.
Incorrect - Hot SID Boron Weight definition is 20% which is more than met here by +5%.
Incorrect - At rated pressure the Rx is SID with HSDBW, not CSDBW.
Question #6 Vermont Yankee LOI Exam Bank Ouestion Number 7582 Revision 0 Instructor Guide: LOT 612 SHUTDOWN USING ALTERNATE SHUTDOWN METHODS Objectives: K3.03
References:
OPOP-ALTSD-3126, Rev 18 pg 6,8 and 51 VY 2009 NRC exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental KnowledgelMemory Task Associations 2000680504 Perform Shutdown Using Alternate Shutdown Methods Question:
IA W OPOP-ALTSD-3126, Shutdown Using Alternate Shutdown Methods, which ONE of the following occurs when the 4KV 1480V Switchgear transfer switches are placed in EMER and what is the reason for this transfer?
MOST automatic functions and system interlocks are defeated because a fire may cause inadvertent automatic actions.
Correct Response-OP-3126, P & L #1 Placing the RCIC, RHR, 4KV/480V Switchgear, or the DG transfer switches in EMER removes control function from the Control Room and defeats most automatic functions and system interlocks. OP-3126, PG 51, Local Operation of 4KV Bus 4 Breaker, states Place the alternate shutdown transfer switch to the emergency position and then place the emergency breaker control switch to the desired position. Ifnot shifted to alternate various automatic actions mayor may not occur as intended or they may occur inadvertently.
- b. ONLY breaker control functions from the Control Room are defeated because Appendix R requires that components must be controlled only from one area.
- c. ALL automatic functions remain available but system interlocks are defeated because operators have fewer indications and controls available to them during alternate shutdown.
- d. MOST automatic functions and system interlocks are available because Appendix R requires the majority of interlocks and automatic functions to remain functional.
Static Simulator Exams: None Last Revised: 2-4-13, by Stewart, Brian Incorrect - Most automatic functions and system interlocks are defeated and if not shifted to alternate various automatic actions mayor may not occur as intended or they may occur inadvertently.
Incorrect - Most automatic functions and system interlocks are defeated and if not shifted to EMERG various automatic actions mayor may not occur as intended or they may occur inadvertently.
Incorrect - Most automatic functions and system interlocks are defeated and if not shifted to alternate various automatic actions mayor may not occur as intended or they may occur inadvertently.
Question #7 Vennont Yankee LOI Exam Bank Ouestion Number 5677 Revision 1 Instructor Guide: LOT 603 OFF-NORMAL PROCEDURES - SIMULATOR Objectives: CRO 3g
References:
OPON-3147, pgs 2 & 3 VY 2009 NRC exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000110501 Respond to RBCCW Failure Question:
The running RBCCW pump has tripped and the standby pump did NOT automatically start The standby pump cannot be started lAW OPON-3147-01, Loss of RBCCW, which of the following components/systems must be shutdOWn/tripped?
- a. The Reactor Water Cleanup System AND the Recirculation Pumps ONLY.
- b. The Recirculation Pumps AND the operating CRD Pump ONLY.
- c. The operating CRD Pump AND the Reactor Water Cleanup System ONLY.
The Recirculation Pumps, the operating CRD Pump AND the Reactor Water Cleanup System.
Incorrect - All three components/systems must be shutdown.
Incorrect - All three components/systems must be shutdown.
Incorrect - All three components/systems must be shutdown.
Correct - RWCU must be shutdown/verified isolated and shutdown.
The CRD pumps supplying seal water and hi temperature effects on resin are an
Static Simulator Exams: None Last Revised: 1-29-13 by Stewart, Brian automatic isolation at 140°F). Recirc pump seals will be damaged and the recirc pumps are required to be shutdown within 2 minutes after RBCCW is lost. CRD pump bearings and reduction gear are cooled by RBCCW and must be manually shutdown to prevent damage.
Question #8 Vermont Yankee LOI Exam Bank Ouestion Number 2947 Revision 1 Instructor Guide: LOT-00-279 SERVICE AND INSTRUMENT AIR SYSTEM Objectives: CRO 5, AO 14
References:
OP 2190, pg 3 & 4 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Fundamental KnowledgelMemory Task Associations:
2007500404 Respond to Low Instrument Air, scram air header pressure Question:
A break at the outlet of the Station Air Receivers causes system pressure to slowly lower.
lAW OP-2190, Service and Instrument Air, which ONE of the following is the system response to maintain Instrument Air header pressure?
Justification
- a. The LAG air compressors will cycle on at Incorrect -The lag compressor cycles 85 psig and off at 90 psig.
between 95 and 100#.
- b. The LAG air compressors will cycle on at Incorrect - The lag compressor cycles 90 psig and off at 95 psig.
between 95 and 100#.
PCV-1 closes as air header pressure drops Correct Response-This is the system and is fully shut at 80 psig.
response to lowering inst. Air header pressure to maintain critical plant components by closing off the service air header.
Incorrect - PCV -1, air to the service air header vlv, closes to inst. Air
Iheader pressure.
I I Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #9 Vermont Yankee LOI Exam Bank Question Number 3541 Revision 1 Instructor Guide: LOT-00-601 OFF-NORMAL PROCEDURES Objectives: 3
References:
ON 3156 Justification: ON 3156 directs the use of Condensate Transfer through the CS system or CRD flow as one of the feed methods. CRD is not one of the available answers and the other systems are not procedurally directed.
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental KnowledgelMemory Task Associations 2000150501 Respond to a Loss of Shutdown Cooling 295021 AA1.01 Ability to operate and/or monitor the following as they 3.4 apply to LOSS OF SHUTDOWN COOLING: AAl.01 Reactor water Question:
Refueling is in progress.
A loss of shutdown cooling occurred with reactor coolant temperature at 155 0 F and rising slowly.
Based on the direction in ON-3156, Loss of Shutdown Cooling, the CRS directs a feed and bleed of the reactor vessel.
lAW ON 3156, Loss of Shutdown Cooling, what systems are used as the initial feed and bleed method?
Condensate transfer through the Core Spray system with RWCU letdown.
Condensate transfer through the Core Incorrect - Core spray is only used when Spray system and an open SRV.
the reactor cavity is NOT flooded.
Condensate transfer may be used with SRV's but only to stay <212° F.
with RWCU letdown.
the reactor cavity is NOT flooded.
- d. Injection by using Core Spray pumps and Incorrect - Core spray is only used when an open SRV.
the reactor cavity is NOT flooded. SRV's are only used to stay <212° F. This should not be used initially at 105° F.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #10 Vermont Yankee LOI Exam Bank Question Number 7321 Revision 1 Instructor Guide: LOT 620 REFUELING ACCIDENT ANALYSIS Objectives: EO 1
References:
OP 1100, Refuel Platform Operation Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2347240102/04 Perform Fuel Handling Operations Using the Auxiliary Hoist 295023 AA1.04 Ability to operate and/or monitor the following as they 3.4 3.7 apply to REFUELING ACCIDENTS: (CFR 41.7,45.6):
Radiation Question:
During a Refuel Outage, half-way through a Full Core Offload, the refueling crew notifies the Control Room that they dropped a fuel bundle and it is balancing over the edge of the cattle chute.
Using the following information:
- Refuel Floor radiation levels are normal
- Reactor Building radiation levels are normal
- Reactor Building Ventilation Exhaust radiation levels are normal Immediately following the incident, which of the following is a correct action for the refueling crew IA WOP 1100, Refuel Platform Operation?
- a. Attempt to move the fuel bundle to a stable Incorrect OP 1101, PIL #19 States that location and do not evacuate until directed under NO circumstances shall immediate by RP.
action be taken to recover or reposition a dropped fuel assembly_
Evacuate the Refuel Floor of all personnel Correct - IAW OP 1100, this is one of the immediately regardless of RP direction.
listed conditions to evacuate the refuel floor
- c. Move the bundle to a stable location and then evacuate the Refuel Floor of all personnel.
- d. Halt refueling operations and notify the RP Coordinator to initiate area monitoring and do not evacuate until directed by RP.
Static Simulator Exams: None Last Revised: 1-31-13 by BLS Incorrect - The conservative action to protect personnel is to evacuate the refuel.
floor.OP 1101, PIL #19 States that under NO circumstances shall immediate action be taken to recover or reposition a dropped fuel assembly.
Incorrect -The conservative action to protect personnel is to evacuate the refuel floor.
Question #11 Vermont Yankee LOR Exam Bank Question Number 1976-Revised Revision 2 System:
Instructor Guide: LOT-00-261 STANDBY GAS TREATMENT SYSTEM Objectives: K5.02, K6.08
References:
OE 3107 Appendix B, OPOP-SGT-2117 rev 01 Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Category: Limits & Controls Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000310501 Respond to Low Reactor Water Level 2610020101 Place the SBGT System in Standby Readiness Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: EA1.20 Standby treatmentiFR VS:
Question:
The plant was operating at 30% RTP with the "A" Train of SBGT in a standby lineup.
The plant scrammed due to a DW leak.
The DW pressure is currently 2.8 psig and steady with all DW RRUs in service.
lAW OP 2117 SBGT System, how did the following SBGT valves respond to the above event?
SGT-IA (SGT Inlet Bypass)
_(1)_
SGT-2A (SGT Inlet Isolation)
_(2)_
SGT-3A (SGT Discharge Isolation)
_(3L_
- a. (1) remained OPEN Incorrect - In a standby lineup, the 2A and (2)OPENep 3A are open. A PCIS group 3 signal was (3) OPEN e'O received and both trains of SBGT start. As a result, the lA valve will open.
- b. (1) remained CLOSED remained OPEN
(3) remained OPEN (1) OPENED (2) remained OPEN (3) remained OPEN
- d. (1) remained CLOSED (2) CLOSED (3) CLOSED Static Simulator Exams: None Last Revised: 2/5/2013 10:19:18 AM by BLS received and both trains of SBGT start. As a result, the lA valve will open.
Correct - In a standby lineup, the 2A and 3A are open. A PCIS group 3 signal was received and both trains of SBGT start. As a result, the lA valve will open.
Incorrect - In a standby lineup, the 2A and 3A are open. A PCIS group 3 signal was received and both trains of SBGT start. As a result, the lA valve will open.
Question #12 Vennont Yankee LOR Exam Bank Question Number Revised Revision 0 System: 295025 Instructor Guide:
Objectives:
References:
EOP Study guide, Section 13, pgs 12-17 of 54 Reference Open/Closed: Open, provide HCTL curve SRO Only: No Style:
Categc[y:
Question is heavily revised from Perry 2010 NRC exam Point Value: 1 Time to Complete (Minute~u: 1 Question Level: Comprehension Task Associations 295025 EA2.03 K&A: Ability to determine and/or interpret the following 3.9 as they apply to HIGH REACTOR PRESSURE:
Suppression pool temperature.
Question:
The plant was operating at rated power when a transient occurred that resulted in the following plant parameters:
- Reactor pressure: 1020 psig
- RPV level: 150 inches
- Torus level: 11 feet
- Torus temperature: 114 0 F Which one of the following conditions will cause the margin to the Heat Capacity Temperature Limit (HCTL) to improve?
AnswerIDistractor Justification
- a. Torus level lowers Incorrect - Lowering suppression pool level will reduce margin to HCL.
Common misinterpretation of HCTL graph depending on where the point is plotted.
- b. Torus temperature rises Incorrect - Raising suppression pool temperature reduces margin to HCL.
Common misinterpretation of HCTl
- c. RPV pressure rises Incorrect -Raising reactor will reduce margin to HCTL. Common misinterpretation of HCTl graph as VY uses high RPV pressure in the lower
! axis of the RPV pressure lowers Correct. lowering reactor pressure will move farther from HCTL.
Static Simulator Exams: None Last Revised: 2-27-13, BLS
Question #13 Vennont Yankee LOR Exam Bank Question Number New Revision 0 System: 295026 Instructor Guide: LOT-O Objectives:
References:
EOP Study Guide, Section 8, pg 23 of 43 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations Respond to High Torus Water Temperature Question:
A seismic event has caused the following plant conditions:
Reactor SCRAM signal on a GP I isolation SRV s are being used to control reactor pressure SRV 'c' is partially stuck open and the STA has indications it has broken a tailpipe DW pressure is 10 psig up slow Torus pressure is 12 psig up fast Torus temperature is 100° F up slow IA W EOP study guide, which of the following methods will be most effective in controlling TORUS pressure as torus temperature rises and why?
Torus spray due to convective cooling.
- b. Drywell spray due to evaporative cooling.
- c. Torus cooling due to convective cooling.
- d. Drywell spray due to convective cooling.
Static Simulator Exams: None Last Revised: 02-01-2013 by BLS Correct - Torus sprays will continue to be effective as torus temperature rises due to the convective of the Incorrect - Evaporative cooling is only present in a dry, hot environment. This is a saturated environment.
Incorrect - Torus cooling will work to control torus temperature but will have little effect on torus pressure.
Incorrect - Drywell spray will not be the most effective controlling torus pressure.
Question #14 Vermont Yankee LOI Exam Bank Question Number 3222 Revision 1 Instructor Guide: LOT-00-622 OE OVERVlEW Objectives: 8
References:
Provide Graph of Minimum Indicated Level -RPSIECCSffransients from EOP-l EOP-l and EOP-3 Minimum Indicated Level-RPSIECCSffransients EOP Study Guide Sect 13, pg 47 DP 0166 (Rev. 25) Pg. 7 VY 2009 NRC exam Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 4 Question Level: Analysis Task Associations 2000210501 Respond to High Drywell Temperature Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: (CFR 41.8 to 41.10): Reactor water level measurement Question:
A LOCA has occurred and the following conditions exist:
- All control rods have inserted
- Recirc pumps have tripped
- RPV Emergency Depressurization has just been commenced
- Drywell pressure is 5.3 psig
- RPV pressure is 700 psig and lowering
- Reference Leg Temperatures are reading 300 0 F IA W EOP-3, Primary Containment Control and DP 0166, Operations Department Standards, which of the following is the most accurate RPV level indication for the CURRENT conditions?
3-72A on CRP 9-5.
- b. +79 inches on RPS Level Indicator LI-2 3-57B on CRP 9-5.
+7 inches on ERFIS point WIDEM071, Compensated Rx Level Wide 70.
- d. +76 inches on Transient Level Indicator LR-2-3-68 on CRP 9-3.
Static Simulator Exams: None Last Revised: 2-4-13 by Stewart, Brian Indicated Level for RPSIECCSffransients curve. The minimum indicated level for the ECCS instruments with the Reference Leg at 300°F is greater than 81. Since the indicated ECCS level is 78" this level indicator cannot be used.
Incorrect -Based on the Minimum Indicated Level for RPSIECCSffransients curve. The minimum indicated level for the RPS instruments with the Reference Leg at 300°F is greater than 81. Since the indicated RPS level is 79", this level indicator cannot be used.
Correct -DP 0166 (page 7) states: "During rapid reactor de pressurization transients, the narrow range (NR) RPV level instruments may indicate high or off scale.
Because they are compensated, both Shroud and Wide Range level indications should be monitored.
Incorrect Transient level indicator LR-2 3-68 on CRP 9-3 is hot calibrated and will read> than actual level as the RPV is
Question #15 Vermont Yankee LOI Exam Bank Question Number 7553 Revision 2 Instructor Guide: LOT-00-223 PRIMARY CONTAINMENT DESIGN Objectives: A2.II
References:
EOP study guide, Section 8, pg 32 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: I Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000240501 Respond to Low Toms Water Level Question:
Given the following;
- Suppression Pool level is lowering due to a leak in the toms.
- The Reactor is shutdown in accordance with EOP-I, RPV Control.
IA W the EOP study guide, when the Suppression Pool level drops below 6.8 feet, which ONE of the following would occur?
- a. The SRV tailpipes become uncovered and Incorrect - The SRV tailpipes become Drywell to toms differential pressure rises. uncovered at 5.5 feet toms leveL
- b. The SRV tailpipes become uncovered and Incorrect - The SRV tailpipes become Drywell to toms differential pressure uncovered at 5.5 feet toms level.
lowers.
- c. The downcomer pipes become uncovered Incorrect - Once seven feet is reached, the and DryweU to toms differential pressure Differential pressure equalizes and will not rises.
rise.
The downcomer pipes become uncovered Correct Response-At seven feet in the SC, and Drywell to torus differential pressure the downcomer vent pipe uncovers causing lowers.
differential pressure to equalize.
Static Simulator Exams: None Last Revised: 1-29-13 by Stewart, Brian
Question #16 Vermont Yankee LOI Exam Bank Question Number 7312 Revision 1 Instructor Guide: LOT-00-610 EOP-l, RPV CONTROL; EOP-2, ATWAS RPV CONTROL Objectives: 2.4.18
References:
EOP study guide, section 7 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge/Memory Task Associations 2000200501 Respond to ATWS Event(s) 295031 EA2.02 Ability to determine and/or interpret the following as they 4.0 apply to REACTOR LOW' WATER LEVEL: EA2.02 Reactor nr",,,.,...
Question:
A Groupl isolation initiated a reactor SCRAM.
There was no control rod movement.
A high power ATWS condition exists.
The CRS has entered EOP-2, ATWS RPV Control.
RPV pressure: 1100 psig RPV water level: 165 inches Reactor power: 35%
IAW the EOP study guide for EOP-2, which ONE of the following is the most effective method of preventing or suppressing core instabilities during this event and why?
Incorrect inlet subcooling is reduced.
raise inlet subcooling.
RPV water level reduction to 90 inches to Correct Response - Water level reduction reduce inlet subcooling.
below FW sparger eliminates high core inlet subcooling reducing initiation and growth of oscillations.
- c. RPV pressure reduction below 1055 psig to raise inlet subcooling.
- d. RPV pressure reduction below 1055 psig to reduce inlet subcooling.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS Incorrect - Pressure reduction to <1055 psig is not the strategy for power reduction.
Incorrect - Pressure reduction to <1055 psig is not the strategy for power reduction.
Question #17 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 295037 Instructor Guide:
Objectives:
References:
EOP Study Guide, Section 7, pg 6 of 79 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value:
Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge Task Associations Knowledge of the specific bases for EOPs.
Question:
Given the following plant conditions:
An A TWS has occurred The MSIVs are currently OPEN The CRS is ordering actions lAW EOP-2, ATWS RPV Control lAW the EOP study guide, which ONE of the following is the correct bases for the CRS orders?
Inhibit ADS - To allow time for boron injection to shutdown the reactor before allowing system actuation as a later EOP strategy.
Inhibit ADS - Prevent ADS System actuation during intentional RPV level lowering and possible subsequent injection of cold, un-borated water.
Incorrect - We do not allow ADS system actuation during an A TWS to prevent a thermal transient on the RPV or reactivity transient on the core due to cold water ection.
Correct
- c. Implement OE 3107, Appendix P Maintain MSIVs OPEN by bypassing the high steam flows that occur during an ATWS with the mode switch out of Run.
- d. Implement OE 3107, Appendix P-Maintain MSIVs OPEN to provide for A TWS generated fission product scrubbing in the main condenser and filtering in AOG.
Static Simulator Exams: None Last Revised: 2-4-13, BLS Incorrect - The MSIV isolation that is bypassed is for RPV low water level to allow terminate and prevent actions later.
This is plausible because VY has a 40%
steam flow isolation with the mode switch out of Run.
Incorrect - The main condenser is maintained available as a heat sink to protect primary containment.
Question # 18 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 295038 Instructor Guide:
Objectives:
References:
OP 0105, pg 49 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutill: 1 Question Level: Analysis Task Associations Respond to Excessive Radiation Levels Question:
With a reactor startup in progress IA WOP 0105, Reactor Operations, the operation of the mechanical vacuum pump (hogger) may only be operated at _(1)_ because the discharge piping is _(2)_.
(1) <4% reactor power (2) only through a 2 minute delay pipe
- b. (1) <4% reactor power Incorrect - The discharge piping is rated (2) not rated for Hydrogen ignitions for hydrogen ignitions.
- c. (1) <1.5 times normal full power Incorrect - The discharge piping is rated background rads for hydrogen ignitions. 1.5 times NFPB is (2) only through a 2 minute delay pipe the system isolation.
- d. (1) <1.5 times normal full power Incorrect - The discharge piping is rated rads for
. 1.5 times NFPB is
(2) not rated for Hydrogen ignitions the system isolation.
Static Simulator Exams: None Last Revised: 2-11-13, BLS
Question #19 Vermont Yankee LOI Exam Bank Ouestion Number 5728 Revision 1 VY bank major revision Instructor Guide: LOT-00-286 FIRE PROTECTION SYSTEM Objectives: K5.03
References:
OP 2186 Section Z CAUTION Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Ouestion Level: Comprehension Task Associations 2867290401 Respond to Pyrotronics Panel Alarms 600000 AK3.04 Knowledge of the reasons for the following responses as 2.8 3.4 they apply to PLANT FIRE ON SITE:: Actions contained in the abnormal for fire on site Ouestion:
An electrical fire is burning in MCC-89A.
The fire brigade wants to use water to fight the fire in MCC-89A.
lAW OP 2186, Fire Suppression Systems, the MCC-89A _(1)_ be de-energized
_(2)_.
Incorrect - Electrical equipment involved
- 2. to prevent spurious operation of 'B' loop in, or in the vicinity of a fire, should be de RHR injection valves and recirc loop energized if possible, and only when so isolation valves.
directed by the Shift Manager.
- b. 1. MUST Incorrect - Electrical equipment involved
- 2. to avoid electric shock hazard to the fire in, or in the vicinity of a fire, should be de brigade members.
energized if possible, and only when so directed by the Shift Manager.
- c. l.SHOULD Incorrect - Electrical equipment involved
- 2. to prevent spurious operation of 'B' loop in, or in the vicinity of a fire, should be de RHR" valves and recirc if and when so
isolation valves.
directed by the Shift Manager.
- 1. SHOULD Correct Response-Electrical equipment
- 2. to avoid electric shock hazard to the ftre involved in, or in the vicinity of a ftre, brigade members.
should be de energized if possible, and only when so directed by the Shift
. Manager.
Static Simulator Exams: None Last Revised: 2-4-13 by Stewart, Brian
Question #20 Vennont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 700000 Instructor Guide:
Objectives:
References:
ARS 8-J-9, Safety Bus Volt. LO Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minute~u: 1 Question Level: Comprehension Task Associations Question:
A significant stonn in the area has caused an electrical grid disturbance.
The following plant conditions exist:
Reactor power is 100%
Unit Auxiliary Transformer is in service SAFETY BUS VOLTAGE LO (8-J-9) is alarming Bus 3 voltage = 2600 volts Bus 4 voltage =2400 volts All other plant systems are operating nonnally lAW ARS 8-J-9, SAFETY BUS VOLTAGE LO, what is the status of the 'A' and 'B' EDG?
Incorrect - <2900 volts on slu transfonners would make this correct, plausible.
Correct - No ECCS signal exists. LNP at <1925 volts.
I
'8' EDG secured in a standby lineup.
- d. 'A' EDG secured in a standby lineup_
Incorrect - balanced answer.
'8' EDG operating powering its bus.
I Static Simulator Exams: None Last Revised: 2-11-13, KM
Question #21 Vermont Yankee LOI Exam Bank Question Number 7316 Revision 6 Instructor Guide: LOT-00-206 HIGH PRESSURE COOLANT INJECTION Objectives: Al
References:
OP 2120; The operator must integrate that a HPCI start signal is not currently present but that a HPCI high level trip is in and has not been reset.
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Ouestion Level: Comprehension Task Associations 2067100401 Maintain Reactor Water Level with HPCI Knowledge of the interrelations between HIGH REACTOR WATER LEVEL and the following: AK2.05 HPCI:
Ouestion:
Given the following plant conditions:
- The mode switch is in SHUTDOWN following a turbine trip on high reactor water level
- Reactor water level is +130 inches and slowly lowering
- Drywell pressure is 1.9 psig and rising
- The white light 'HPCI System Ready' is OFF Given the above conditions, and without operator action, HPCI...
- a. WILL automatically initiate on just the Incorrect - It can be manually reset using high Drywell pressure signal.
the CRP 9-3 trip reset pushbutton but with no operator action the Hi DW pressure signal is blocked.
WILL initiate on the low-low Reactor Correct - Turbine trip at 177" will auto water level signal.
reset at 82.5".
WILL NOT automatically initiate on the Incorrect - Turbine trip at 177" will auto reset at 82.5" OR it can be reset
using the CRP 9-3 trip reset pushbutton.
- d. WILL NOT initiate on low-low Reactor Incorrect - With no operator action the Hi level OR high Drywell pressure signals.
DW pressure signal is blocked. Turbine trip at 177" will auto reset at 82.5".
Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #22 Vermont Yankee LOI Exam Bank Question Number 1390 Revision 3 Instructor Guide: LOT 202 REACTOR RECIRCULATION SYSTEM Objectives: 7
References:
OP 2110, Pg 5 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge/Memory Task Associations 2020020101 Adjust the Recirculation System Flow Using Individual Manual Control Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL: AKl.02 Recirculation pump net
've suction head: Plant-Question:
With the plant at 80% power a total loss of feedflow occurs generating a recirculation pump runback to minimum speed.
IAW OP-211O, Reactor Recirculation System, what is the reason for the runback?
- a. Minimize stress on CRD stub tubes and Incorrect - Stress is caused when starting incore housing welds.
an idle pump.
- b. Minimize flow induced vibration of Incorrect - Vibration occurs under high LPRMs and TIP tubes.
flows during refueling outages.
Prevent cavitation of the recirculation Correct - The feed flow runback is to pumps.
ensure recirc pump NPSH at reduced feed conditions.
- d. Prevent exceeding core thermal limits.
Incorrect - Thermal limits are protected through the use of scrams.
Static Simulator Exams: None
Last Revised: 1-29-13 by BLS
Question #23 Vennont Yankee LOR Exam Bank Question Number New Revision 0 System: 295014 Instructor Guide:
Objectives:
References:
OT 3110 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minute:§): 1 Question Level: Fundamental Knowledge Task Associations 295014 AK1.02 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTNITY ADDITION: AK1.02
3.3 Question
While raising reactor power from 97% CTP to 100% following a rod pattern adjustment the RO observes the recirc master controller output rising without operator action.
IA W OT 3110, Inadvertent Reactivity Addition, which ONE of the following is the required immediate operator action?
Place both individual recirc controllers to manual.
- b. Reduce the master controller setpoint to below transient level.
- c. Insert control rods using reverse order of the rapid shutdown sequence.
Correct - OT 3110 operator immediate actions state that the operator should take the individual recirc controllers to manual which should stop the power rise by disconnecting the master from the individual controllers.
Incorrect: This is a later follow-up step for other anomalies.
Incorrect: This would be used if the crew found themselves in a variety of other anomalies or than the
- d. Lockup the recirc scoop tubes before reactor power exceeds 100%.
Static Simulator Exams: None Last Revised: 2-5-13, KM MELLLA limits.
Incorrect: Scoop tube lockup lAW OP 2110 is and has been used for controller malfunctions at VY but typically only after
!I&C troubleshooting.
Question # 24 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System: 295015 Instructor Guide:
Objectives:
References:
Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations Question:
The plant was operating at 100% power.
An ATWS has occurred coincident with a loss of MCC-8A Annunciator APRM BUS AlB ALT Power Source (5-M-5) is NOT lit RPV pressure is 920# controlled using bypass valves RPV water level is 133 inches ARIJRPT was initiated, scram air header is depressurized but all rods are not inserted What indications are available to determine reactor power?
AnswerlDistractor Justification
- a. APRM 'E' and turbine first stage pressure. Incorrect - APRM not powered, 1 st stage pressure reads zero with the turbine tripped.
i Incorrect - APRM E has no power.
- c. APRM 'B' and turbine first stage pressure. Incorrect _1st stage pressure reads zero with the turbine tripped.
Correct.
Static Simulator Exams: none Last Revised: 2-4-13, KM
Question #25 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System: 295020 Instructor Guide:
Objectives:
References:
OP 2113 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge Task Associations 295020 AKl.Ol Knowledge of the operational implications of the 3.7 following concepts as they apply to INADVERTENT CONTAINMENT ISOLATION: AK1.01 Loss of normal heat sink Question:
Following a Reactor SCRAM and inadvertent Group 1 isolation, the CRS directs the BOP to reopen the MSIVs lAW OP 2113, Main Steam Operating Procedure.
lAW OP 2113, the _(1)_ MSIVs are opened first.
After equalizing upstream and downstream pressures then, if the bypass valves OPEN,
_(2)_ the setpoint of the turbine pressure regulators in service until the bypass valves are shut.
- a. (1) INBD (2) RAISE
- d. (1)OUTBD (2) LOWER Static Simulator Exams: None Last Revised: 2-5-13, KM Incorrect - OUTBD MSIVs opened first lAW OP 2113, pg 8.
Incorrect - OUTBD MSIVs opened first lAW OP 2113, pg 8.
Correct.
Incorrect Setpoint must be raised to close theTBVs.
Question # 26 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System: 295032 Instructor Guide:
Objectives:
References:
OP 2115 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minute.£.!: 1 Question Level: Comprehension Task Associations Respond to Containment Isolations 295032 EK2.04 Knowledge of the interrelations between HIGH 3.6 SECONDARY CONTAINMENT AREA TEMPERATURE and the following: EK2.04 PCISINSSSS Question:
The plant is operating at 100%
The following alarms are received:
5-H-3 STM TUNNEL TEMP CH A HI 5-1-3 STM TUNNEL TEMP CH B HI Steam leak: detection on CRP 9-21 confirms temperatures in the steam tunnel equal to 201°F and rising.
Which ONE of the following describes the actuation of PCIS Group 1 and Group 6 isolation signals lAW OP 2115, Primary Containment?
- a. Both Group 1 AND Group 6 isolation signals will actuate immediately.
- b. Both Group 1 AND Group 6 isolation signals will actuate in 35 minutes.
PCIS Group 1 isolation signal will actuate immediately.
- d. PCIS Group 6 isolation signal will actuate immediately.
Static Simulator Exams: None Last Revised: 2-4-13, KM Incorrect PCIS Group 6 has a 35 minute time delay.
Incorrect - PCIS Group 1 has no 35 minute time delay.
Correct.
Incorrect - pels Group 6 has a 35 minute time delay.
Question #27 Vermont Yankee LO I Exam Bank Ouestion Number 5731 Revision 5 Instructor Guide: LOT-01-223 PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS)
Objectives: KIO, Kll
References:
OPOP-SGT-2117, page 3 and ARS 5-H-I Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2737060101 Respond to Automatic Actions from Local Monitors 295034 EA1.02 Ability to operate andlor monitor the following as they 3.9 4.0 apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR 41.7,45.6):
Process radiation Question:
Reactor Building Ventilation Exhaust radiation monitor 'A' is bypassed by I&C for testing and is downscale.
The 'B' Reactor Building ventilation radiation monitor reading rises to 20 rnR!hr.
Which ONE of the following describes the required operator response lAW OPOP-SGT 2117, Standby Gas Treatment, if any?
- a. There should be no operator response since Incorrect - This is a logical action if the there is no trip.
student does not understand system Both channels are required for input.
operation during I&C testing.
Confirm PCIS Group 3 isolations and Correct Response - Student must know that SBGT system startup.
I&C keylocks only bypass upscale trips.
Two downscales on RB vent exhaust is an isolation signal or one upscale is an isolation. Only one key lock bypass is allowed in at time. RB
- d. Verify a half Group 3 isolation and no SBGT automatic start.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS ventilation will trip and isolate and SBGT will start.
Incorrect - This is a logical action if the student does not understand system operation during I&C testing.
Incorrect - This is a logical action if the student does not understand system operation during I&C testing.
Question #28 Vermont Yankee LOI Exam Bank Question Number 3553 Revision I Instructor Guide: LOT-00-218 AUTOMATIC DEPRESSURIZATION SYSTEM Objectives: K1.01
References:
OP 2122 Discussion ARS 3-A-7 Justification: ADS permissive RHRlCS running (ARS 3-A-7) setpoint is 100 psig using pump discharge pressure switches only.
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: I Time to Complete (Minutes): 2 Question Level: Fundamental KnowledgelMemory Task Associations 2187030101 Replace Automatic Blowdown System in Standby Following ADS Initiation 203000 Kl.06 Knowledge of the physical connections and/or causeeffect 3.9 relationships between RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) and the following: K1.06 Automatic Question:
lAW ARS 3-A-7, ADS PERMISSIVE RHRlCS RUNNING, which parameter(s) does ADS monitor to determine the status of the running RHR pump(s)?
RHR pump discharge pressure ONLY RHR pump discharge pressure AND pump breaker contacts
- c. RHR pump flow ONLY
- d. RHR pump flow AND pump breaker contacts
Static Simulator Exams: None Last Revised: 1-31-13 by BLS
Question #29 Vermont Yankee LOI Exam Bank Question Number 7129 Revision 1 Instructor Guide: LOT-00-205 RESIDUAL HEAT REMOVAL SYSTEM Objectives: Kl.07.b, K2.02.b, K5.02.b, K6.02.b, K12.01
References:
OP 2124 ON 3160 B-191301 Sheet 1300,1300A,1308 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000150501 Respond to a Loss of Shutdown Cooling Question:
The plant is shutdown with the 'A' loop of Shutdown Cooling in service.
lAW ON-3160, Loss of DC-2 and DC-3, which ONE of the following describes the reason why the plant loses Shutdown Cooling when DC-2 is lost?
RHR -17, RHR SID Cooling Suction Valve, closes resulting in a trip of the running RHR pump.
RHR -18, RHR SID Cooling Suction Val ve, closes resulting in a trip of the running RHR pump.
RHR-17, RHR SID Cooling Suction Valve, position indication is lost resulting in a trip of the running RHR pump.
- d.
in a Correct - Running RHR Pump logic will see RHR-17 as closed when DC-2 is lost (loss of sensing relay).
Incorrect - Running RHR Pump logic will see RHR -17 as closed when DC-2 is lost of
Static Simulator Exams: None Last Revised: 1-31-13 by BLS
Question #30 Vennont Yankee LOI Exam Bank Question Number New Revision 0 Instructor Guide: LOT-00-206 HIGH PRESSURE COOLANT INJECTION Objectives: K4.02, K4.04
References:
OP 2120, page 4 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Comprehension Task Associations 2067090401 Respond to Automatic HPCI System Trip or Isolation Question:
lAW OP 2120, HPCI System, which ONE of the following HPCI isolation signal(s) will automaticall y reset?
Correct Response: This auto-isolation does not seal in and is High HPCI area temperature ONLY.
Incorrect - HPCI area temperature will have to be reset BOTH low steam line pressure AND HPCI Incorrect - HPCI area temperature will have to be reset Incorrect This auto-isolation signal does not seal in and is Static Simulator Exams: None Last Revised: 2-14-13 by KM
Question #31 Vermont Yankee LOI Exam Bank Question Number 1309 Revision 5 Instructor Guide: LOT 607 EOP-3, PRIMARY CONTAINMENT CONTROL Objectives: 4
References:
Appendix B, BWROG-EPGs; EOP Study Guide section 8, page 34; EOP-3 Step PC/L-7 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental KnowledgelMemory Task Associations 2000240501 Respond to Low Torus Water Level Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM: K6.05 Suppression pool level:
BWR-2,3,4 Question:
The following conditions exist:
- A transient has resulted in a leak in the reactor vessel and a leak in the Torus
- HPCI is operating, maintaining RPV level 127 to 177 inches Torus water level has dropped to 7 feet and is continuing to lower IA W EOP-3, Primary Containment Control, what actions are performed and why?
Secure HPCI...
irrespective of whether adequate core Incorrect HPCI pump cavitation is not the cooling is assured, due to pump cavitation concern with low torus level.
concerns.
immediately due to the potential to over Correct - The HPCI exhaust will be pressurize primary containment with the uncovered and over pressurize containment HPCI exhaust.
if left in service.
lowering suction pressure.
the concern with low torus level.
- d. onl y when primary containment pressure Incorrect - With HPCI in operation and rises due to the HPCI exhaust.
torus level low, the exhaust will pressurize I I
and thereby threaten primary containment.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #32 Vermont Yankee LOI Exam Bank Question Number 6804 Revision 1 Instructor Guide: LOT-00-209 CORE SPRAY Objectives: K2
References:
OP 2123, Core Spray, page 3 LOT 209, TP5 CWD Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Analysis Task Associations 2000320501 Respond to a Loss of DC-I, 2, 3 209001 K4.08 Knowledge of LOW PRESSURE CORE SPRAY 3.8 SYSTEM design feature(s) and/or interlocks which provide for the following: K4.08 Automatic system initiation Question:
A transient has resulted in a reactor SCRAM and electrical fault causing a loss of Bus 4.
Degrading containment conditions has resulted in the following:
- Reactor pressure is at 325 psig
- Drywell pressure is at 2.8 psig IAWOP 2123 Core Spray system, what is the Core Spray system response?
- a. 'A' Core Spray pump will start and but its Incorrect - Loop 'A' pumps and valves
. injection valves will NOT open.
have lost power.
- b. ONLY the Loop'A' Core Spray pump will Incorrect - Bus 4 provides power to 'A' start and its injection valves will open.
loop pump and valve initiation logic. Only
'B' would have n('nllPr ONLY the Loop 'B' Core Spray pump will Correct - Only Loop 'B' pumps and valves start and its.
valves will have initiation n{"""",..
Incorrect - Loop 'B' pumps and valves still have power.
- d. 'B' Core Spray pump will start but its injection valves will NOT open.
Static Simulator Exams: None Last Revised: 1-29-31 by BLS
Question #33 Vermont Yankee LO I Exam Bank Question Number 481 Revision 1 Instructor Guide: LOT 211 STANDBY LIQUID CONTROL SYSTEM Objectives: K4.08, K8
References:
P&ID G-191171 OP 2114 Appendix "B", Since one squib valve has fired in this parallel system, there is now a flow path for either pump to inject.
UFSAR< Section 3.8.3 (Rev. 17)
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 4 Question Level: Comprehension Task Associations 2110050101 Inject Poison Solution into the Reactor Vessel 211000 K4.08 Knowledge of STANDBY LIQUID CONTROL SYSTEM 4.2 4.2 design feature(s) and/or interlocks which provide for the following: (CPR 41.7): System initiation upon operation of SBLC control switch Question:
An ATWS has occurred.
The CRS orders the injection of Standby Liquid Control (SLC).
- The Operator at the Controls (OATe) positions the SLC initiation switch to SYS.1.
- The SLC initiation switch is then positioned to SYS. 2.
- The "B" SLC pump starts, but SLC-14B does not fire.
IAWOP 2114, Operation of the Standby Liquid Control System, which ONE of the following is the SLC system flow and why?
- a. Zero, because the cross connect valve is Incorrect not a normal valve lineup.
closed.
- b. Zero, because SLC-14B did not fire.
Incorrect - flow still exists through the SLC-14A valve.
- c. Approximately 20 gpm due to the reverse flow through the "A" SLC pump.
Approximately 40 gpm because the opening of either squib valve will allow rated flow from either pump.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS Incorrect - No reverse flow exists.
Correct - with a pump running and Squib valve SLC-14A(B) fired flow will be indicated by red flow indicator light on (flow greater than 30 gpm).
Question # 34 Vennont Yankee LOR Exam Bank Ouestion Number New Revision 0 System: 211000 Instructor Guide:
Objectives:
References:
OP 2114, OP 4114 Reference Open/Closed: Closed SRO Only: No Style:
Categ(['Y:
Point Value: 1 Time to Complete (Minute:li: 2 Question Level: Comprehension Task Associations Fill the SLC Tank or Add Chemicals to the Tank Question:
Following an addition of boron to the SLC tank:
IAWOP 2114, Standby Liquid Control System, and OP 4114, Standby Liquid Control System Surveillance, a minimum of hours of mixing is required before sampling by the Chemistry Department.
Mixing of the SLC tank is perfonned by _(2)_.
- a. (1) 4 (2) opening SLC-22, SLC tank sparger instrument air supply, v.. tum open.
- h. (1) 4 (2) operating SLC tank heater control in MANUAL.
(1) 8 (2) opening SLC-22, SLC tank sparger instrument air supply, 1,4 tum open.
- d. (1) 8 (2) operating SLC tank heater control in MANUAL.
Static Simulator Exams:
Last Revised: 2-5-13, BLS Incorrect Too short a time for mixing.
Incorrect - Too short a time for mixing.
Correct.
Incorrect - SLC tank heater operation not required for mixing. Action for low tank temperature alarm (5-A-4).
Question # 35 Vermont Yankee LOR Exam Bank: Question Number New Revision 0 System: 212000 Instructor Guide:
Objectives:
References:
OPOP-ALTSD-3126 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes}: 2 Question Level: Fundamental Knowledge Task Associations Perform Shutdown from Outside the Control Room Question:
During a fire in the Control Room, the control room operators have exited the Control Room.
lAW OPOP-ALTSD-3126, Shutdown Using Alternate Shutdown Methods, what action(s) will Operator #3 take to SCRAM the reactor?
Trip both RPS MG supply breakers.
- c. Locally inject SLC.
Static Simulator Exams: None Last Revised: 2-4-13, KM Incorrect Not required by OP 3126.
Plausible method to remove power to RPS.
Incorrect - Not required by OP 3126.
Plausible method to remove power to RPS.
Incorrect - Not required by OP 3126.
Plausible action lAW OE 3107 Appendix I.
Correct - OP 3126 Attachment 3 Step 1 for Operation #3, an RO.
Question #36 Vermont Yankee LOI Exam Bank Question Number 668 Revision 1 Instructor Guide: LOT-02-215 INTERMED][ATE RANGE MONITORS (IRM)
Objectives: Kl.06, K 4.02
References:
CWD 789, 804, 805; OP-2131, IRM Channels, pg 1, The downscale rod block is bypassed with the IRM on range 1 or the mode switch in Run. Other RB's are bypassed by the MIS in Run.
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Comprehension Task Associations 2150230101 Operate the Neutron Monitoring System Question:
During a normal reactor shutdown, IRM (Intermediate Range Monitor) Channel "C" is indicating 30 on Range 6 and steady.
An inadvertent range down to Range 4 occurs.
IA W OP-2131, IRM Channels, which ONE of the following describes the plant response to this action?
- a. An IRM downscale alarm is received ONLY.
IRM rod blocks are bypassed on this range.
- b. An IRM upscale alarm and rod block ONLY are received.
An IRM rod block AND half-scram on RPS Channel "A" are received.
Incorrect - half scram also occurs. This is NOT a downscale condition.
Incorrect - half scram also occurs. This is NOT a downscale condition.
Correct - Ranging down two ranges will result in a 120/125 scale half scram on RPS channel "A" (IRM Hi-Hi) and a rod block (IRM Hi).
I
- d. An IRM rod block AND half-scram on Incorrect - Ranging down two ranges will RPS Channel uB It are received.
result in a 1201125 scale half scram on RPS channel "A" (IRM Hi-Hi) and a rod block (IRM Hi).
Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #37 Vermont Yankee LOI Exam Bank Question Number 292 Revision 5 Instructor Guide: LOT-01-215 SOURCE RANGE MONITORS (SRM)
Objectives: K 4.01. K4.04, K5.03
References:
OP 2130, page 3 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 2157170401 Respond to SRM System Alarms Question:
Given the following conditions:
- Reactor is subcritical
- Operations is performing control rod withdrawals for a reactor startup
- Reactor power is 75 counts per second (CPS) in the source range
- SRM Channel 'A' select switch light is illuminated on CRP 9-5 bench board
- The Operator at the Controls (OATC) depresses and holds the DRIVE OUT pushbutton IA W OP-2130, SRM Channels, which ONE of the following describes the plant response?
- a. The 'A' SRM detector will NOT withdraw Incorrect - Any SRM channel will generate due to the current power level.
a rod block if one of the following conditions exist: 1. Any SRM downscale (3 cps) or any SRM detector not fully inserted and the level indicator for that channel drops below 100 cps. (With all IRM range switches at position 3 or higher, these rod blocks are
The 'A' SRM detector will withdraw and a ROD WITHDRA W BLOCK will be generated.
- d. The 'A' SRM detector will withdraw until SRM DOWNSCALE annunciator is received and then stop.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS automatically.) 2. SRM count greater than the high setpoint unless the IRM range switches are on Range 8 or above. 3. SRM Inoperable.
Incorrect - Any SRM channel will generate a rod block if one of the following conditions exist: 1. Any SRM downscale (3 cps) or any SRM detector not fully inserted and the level indicator for that channel drops below 100 cps. (With all IRM range switches at position 3 or higher.
these rod blocks are bypassed automatically.) 2. SRM count greater than the high setpoint unless the IRM range switches are on Range 8 or above. 3. SRM Inoperable.
Correct - Any SRM channel will generate a rod block if one of the following conditions exist: 1. Any SRM downscale (3 cps) or any SRM detector not fully inserted and the level indicator for that channel drops below 100 cps. (With all IRM range switches at position 3 or higher.
these rod blocks are bypassed automatically.) 2. SRM count greater than the high setpoint unless the IRM range switches are on Range 8 or above. 3. SRM Inoperable.
Incorrect - Any SRM channel will generate a rod block if one of the following conditions exist: 1. Any SRM downscale (3 cps) or any SRM detector not fully inserted and the level indicator for that channel drops below 100 cps. (With all IRM range switches at position 3 or higher.
these rod blocks are bypassed automatically.) 2. SRM count greater than the high setpoint unless the IRM range switches are on Range 8 or above. 3. SRM Inoperable.
Question #38 Vermont Yankee LO[ Exam Bank Question Number 3154 Revision 2 Instructor Guide: LOT-01-215 SOURCE RANGE MONITORS (SRM)
Objectives: CRO 3,7
References:
OP 2130 pg 3 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge/Memory Task Associations 2150230101 Operate the Neutron Monitoring System 215004 A3.04 Ability to monitor automatic operations of the SOURCE 3.6 RANGE MONITOR (SRM) SYSTEM including: A3.04 control rod block status Question:
A reactor startup is in progress with the mode switch in START and HOT/STBY.
With SRM 'A' reading downscale, which of the following conditions will generate a rod block IA WOP 2130, SRM System?
SRM's are __(1)__, all __v_,___ and all IRM's are range
- a. (1) not fully inserted (2) SRMs but 'A' read 300-400 cps (3) 4 or 5.
(1) fully inserted (2) SRMs but 'A' read 300-400 cps (3) 1
- c. (1) not fully withdrawn with SRM 'A' bypassed (2) other SRMs read between 5 x 104 and 2 x 105 cps (3) 8
- d. (1) not fully inserted with SRM 'A' bypassed (2) other SRMs read 300-400 cps (3) 1 Static Simulator Exams: None Last Revised: 1-29-13 by BLS Incorrect -The SRM downscale rod block for SRM 'A' is bypassed for this condition because the IRMs are on range 3 or above with IRM's > range 4 then the detector not full in is bypassed.
Correct.
Incorrect -All SRM rod blocks are bypassed when the IRMs are on range 8 or above.
Incorrect -The SRM not full in rod block is bypassed when the SRMs are reading greater than 100 CPS.
Question #39 Vermont Yankee LOI Exam Bank Question Number 3892 Revision 1 Instructor Guide: LOT 215 AVERAGE POWER RANGE MONITOR (APRM)
Objectives: CRO 2d, 5
References:
LOT-05-215, Rev 13 ARS 5-M-5. This question meets the first part of the K&A statement. Asking an RO procedures to correct/control in beyond memory level question requirements.
Tech. Spec. LSSS 2. 1.A.1 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 2150230101 Operate the Neutron Monitoring System 2157150401 Respond to APRM System Alarms 215005 A2.05 Ability to (a) what is the impacts of the following on the 3.5 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those what isions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.05 Loss of recirculation flow Question:
Given the following conditions:
- A plant startup is in progress The Recirc flow input signal to the APRMs is 25%
- As Recirc flow is raised, the liB" Flow Converter/Comparator output remains at 25%
- Actual recirculation loop flows respond as designed What will be the FIRST effect on plant operation as recirculation flow continues to be raised?
AnswerlDistractor Justification
- a. A full SCRAM will occur due to flow Incorrect - The Flow Biased Scram signal biased neutron flux high.
for the "B" RPS Channel ARMs (I.e.
ARMs B, D, F) will remain unchanged as
- b. A half SCRAM will occur due to flow biased neutron flux high.
- c. A control rod block will occur due to a flow converter/comparator unit "inop" signal.
A control rod block will occur due to the flow converter/comparator unbalance condition.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS.
70.5% based on the failure of the "B" Flow Converter/Comparator. Flow will be increased to 32% on the "A" Flow Converter/Coparator before actual reactor power is increased to 70.5%. The 7%
difference between the 2 Converter/Coparator units will cause a comparator unbalance ROD BLOCK before actual power reaches the artificially low trip setpoints for APRMs B, D, F.
Incorrect - The Flow Biased Scram signal for the "B" RPS Channel ARMs (I.e.
ARMs B, D, F) will remain unchanged as 70.5% based on the failure of the liB" Flow Converter/Comparator. Flow will be increased to 32% on the "A" Flow Converter/Coparator before actual reactor power is increased to 70.5%. The 7%
difference between the 2 Converter/Coparator units will cause a comparator unbalance ROD BLOCK before actual power reaches the artificially low trip setpoints for APRMs B, D, F which would cause a half scram.
Incorrect - The inop flow converter/comparator rod block would occur if one of the comparators had lost Correct
Question #40 Vermont Yankee LOR Exam Bank Ouestion Number New Revision 0 System: 215005 Instructor Guide:
Objectives:
References:
OP 2132, APRM Channels Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Comprehension Task Associations Respond to APRM System Alarms 215005 A3.03 Ability to monitor automatic operations of the AVERAGE 3.3 POWER RANGE MONITOR !LOCAL POWER RANGE MONITOR SYSTEM including: A3.03 Meters and recorders Question:
The plant is operating at 100% with APRMs 'A' and 'F' bypassed.
Subsequently, 'F' APRM fails upscale.
lAW OP-2132, APRM Channels, which ONE of the following is the response of the APRM System indications?
AnswerlDistractor Jus tification
- a. 'F' APRM recorder does not respond.
Incorrect - The recorder continues to
'F' APRM benchboard High and High-respond. The lights will not work with the High lights turn ON.
APRM bypassed.
- b. 'F' APRM recorder does not respond.
Incorrect The recorder continues to
'F' APRM benchboard High and High-respond.
High lights remain OFF.
- c. 'F' APRM recorder responds.
'F' APRM benchboard High and High High lights tum ON.
'F' APRM recorder responds.
'F' APRM benchboard High and High High lights remain OFF.
Static Simulator Exams: None Last Revised: 2-13-13, KM Incorrect - The recorder continues to respond. The lights will not work with the APRM bypassed.
Correct - With the APRM bypassed the recorder continues to respond to system inputs but the lights do not.
Question # 41 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 217000 Instructor Guide:
Objectives:
References:
OP 2121, RCIC, App 'C' Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Analysis Task Associations 217000 K5.01 Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): K5.01 Indications of cavitation
2.6 Question
A seismic event has resulted in the following plant conditions:
An A TWS has occurred with 20 control rods at position 48 A break in the CST has the crew using RCIC for RPV level control with suction on the Torus RPV level is being controlled -19 to 177 inches HPCI is being aligned to the Torus Torus temperature is 125 0 F and rising SRVs are being used to control pressure With RCIC controller in automatic, the RO is observing turbine speed and flow oscillations with speed currently at 1900 rpm lAW OP 2121, RCIC System, what actions are you required to take?
- a. Leave the RCIC flow controller in AUTOMATIC.
Restore speed to >2000 rpm with setpoint tape.
Place the RCIC flow controller in MANUAL.
Restore speed to >2000 rpm with the manual knob.
- c. Secure RCIC regardless of adequate core cooling.
Static Simulator Exams: None Last Revised: 2-4-13, BLS Incorrect - RPM is low and lube oil to the turbine may be inadequate.
Correct - with speed and flow oscillations, RCIC must be placed in MANUAL. RPM should be restored to >2000 rpm for adequate lubrication.
Incorrect - RPM is low and lube oil to the turbine may be inadequate. RCIC may be operated in MANUAL.
Incorrect RPM is low and lube oil to the turbine may be inadequate. RCIC may be operated in MANUAL.
Question # 42 Vermont Yankee LOR Exam Bank Ouestion Number NEW Revision 0 System: 218000 Instructor Guide:
Objectives:
References:
OP 2122, ARS 3-A-2 and 3 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Analysis Task Associations Maintain Awareness of Plant and Equipment Status 218000 K6.03 Knowledge of the effect that a loss or malfunction of the 3.8 following will have on the AUTOMATIC DEPRESSURIZATION SYSTEM: K6.03 Nuclear boiler instrument Question:
A small break LOCA has occurred.
The following conditions are present:
DW pressure 10 psig rising slowly HPCI tripped on low oil pressure RPV water level has just lowered to 80 inches with RCIC injecting LT-2-3-72 'A' and 'c' are responding and providing level input to the ADS logic LT-2-3-72 'B' and 'D' have suffered a failure such that the level input from these transmitters is at 100 inches IAWOP 2122, ADS System, which of the following describes the response of the ADS system assuming that no operator action is taken?
TWO minutes have elapsed.
additional minutes are required to satisfy the ALL ADS valves will remain closed until Incorrect The logic has only just been TEN minutes have elapsed.
satisfied. Two additional minutes are required to satisfy the logic. Ten minutes is not correct because a high DW signal is
- c. SRV's 'A' and 'C' ONLY will open in Incorrect Cross channel redundancy TWO minute.
provides for full system actuation. Two additional minutes are required to satisfy the
- d. NO ADS valves will open.
Incorrect - The operator must understand the logic design basis inputs from various for the
. to function.
Static Simulator Exams: None Last Revised: 2-4-13, KM
Question # 43 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 223002 Instructor Guide:
Objectives:
References:
OP 2115, pg 55 of 57 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 223002 K3.07 Knowledge of the effect that a loss or malfunction of the 3.7 PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM SUPPLY SHUT -OFF will have on
- K3.07 Reactor Question:
While at 50% power a Group 1 isolation occurred.
RCIC was started manually to provide RPV pressure controL Subsequently, alarm 4-U-2, RCIC STEAM LINE A P HI, comes in and clears after 10 seconds.
Which one of the following describesl) RCIC status and 2) how RPV pressure responds?
- 1) RCIC isolated.
- b. 1) RCIC isolated.
- c. 1) RCIC is still in pressure control.
- d. 1) RCIC is still in pressure control.
Static Simulator Exams: None Last Revised: 2-5-13, BLS Correct - >300% for >5 seconds is a RCIC isolation. SRV lift pressure is 1080#.
Incorrect - The operator should attempt to isolate RCIC. SRV lift pressure is 1080#.
Incorrect - RCIC has isolated with a high flow signal in for >5 secs.
Incorrect - RCIC has isolated with a high flow signal in for >5 secs.
Question #44 Vennont Yankee LOI Exam Bank Question Number Revised Revision 0 Instructor Guide: LOT 239 MAIN STEAM SYSTEM Objectives: K6.05b
References:
OP 2122, ADS, UFSAR section 4.4-6 to 9 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Question is from 9 Mile Point 2010 NRC exam Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge/Memory Task Associations 2000180501 Respond to High Reactor Pressure Question:
Which one of the following describes the response of a SafetylRelief Valve (SRV) to a rising RPV pressure if a pneumatic supply to the valve is NOT available from any source?
A SafetylRelief Valve will...
- a. function in its pressure relief mode AND in its manual actuation mode.
function in its pressure relief mode but will NOT function in its manual actuation Incorrect - A pneumatic supply (accumulator l continuous) is required to lift in the manual actuation mode. Ifthe operator confuses the SRV with the Safety valve purpose then this would be a viable distracter.
Correct Response-A pneumatic supply is not required in the pressure relief mode. In the safety mode, whenever reactor pressure is greater than spring pressure the valve will open.
relief mode Incorrect - In the
and WILL function in its manual actuation mode.
- d. NOT function in its pressure relief mode OR in its manual actuation mode.
Static Simulator Exams: None Last Revised: 2-27-13 by BLS whenever reactor pressure is greater than spring pressure the valve will open. A pneumatic supply is NOT required.
Incorrect - In the pressure relief mode, whenever reactor pressure is greater than spring pressure the valve will open. A pneumatic supply is NOT required. If the operator does not understand the operation of an SRV relative to the internal pilot valve using either steam in its pressure relief mode and air/nitrogen in its manual actuation mode then this would be a viable distracter.
Question # 45 Vermont Yankee LOI Exam Bank Question Number New Revision 0 Instructor Guide: LOT-00-601 OFF-NORMAL PROCEDURES Objectives: RO EOl,EO 2
References:
ON 3174, OP2172 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000270501 Respond to a Loss of Feedwater 2007950501 Respond to a Loss of 120V/240V Instrument AC Bus Using on 3174 Question:
A momentary loss of Instrument AC occurs.
Which ONE of the following correctly identifies:
- 1) Feed System response and 2) operator action to be taken lAW ON 3174, Loss of 120V1240V Instrument AC Bus?
(Disregard the effects of the level transient.)
- a. 1) The "A" Feedwater level controller will automatically transfer to manual (lockup).
- 2) Verify or transfer the 'A' FRV to manual, verify the 'P' and 'V' output is the same and depress the lockup pushbutton.
- b. 1) The "A" AND Master Feedwater level controllers will automatically transfer to manual with 'A' FRV locked up.
- 2) Verify or transfer the 'A' FRV to manual, verify the 'P' and 'V' output is the same and depress the lockup pushbutton.
Then, transfer the Master controller to Incorrect - Should instrument AC be lost or the master controller output is lost. the B manuaVauto transfer station will transfer to manual at the called for value 6 seconds prior to the loss of power. This is indicative of a loss of vital for the 'A' FR V to lockup.
Incorrect This is indicative of a loss of Vital AC.
automatic.
- c. 1) The "B" AND Master Feedwater level controllers will automatically transfer to manual with 'B' FRV locked up.
- 2) Verify or transfer the 'B' FRV to manual, verify the 'P' and 'V' output is the same and depress the lockup pushbutton.
Then, transfer the Master controller to automatic.
- 1) The tlB" Feedwater level controller will automatically transfer to manual (lockup).
- 2) Verify or transfer the 'B' FRV to manual, verify the 'P' and 'V' output is the same and depress the lockup pushbutton.
Static Simulator Exams: None Last Revised: 2-5-13 by BLS Incorrect Should instrument AC be lost or the master controller output is lost, the B manual/auto transfer station will transfer to manual at the called for value 6 seconds prior to the loss of power.
Correct Response-Should instrument AC be lost or the master controller output is lost, the B manual/auto transfer station will transfer to manual at the called for value 6 seconds prior to the loss of power.
Question # 46 Vennont Yankee LOR Exam Bank Question Number New Revision 0 System: 261000 Instructor Guide:
Objectives:
References:
UFSAR pages 6.5-5 of 13 and 7.4-12 of 39 Reference Open/Closed: Closed SRO Only: No Style:
Categ<:.rry:
Point Value: 1 Time to Complete (Minute~u: 1 Question Level: Analysis Task Associations Place the SBGT System in Service Manually 261000 K3.04 Knowledge of the effect that a loss or malfunction of the 3.1 STANDBY GAS TREATMENT SYSTEM will have on following: K3.04 High pressure coolant injection system:
Plant-Question:
A plant transient occurred and HPCI was manually started in pressure controL
'A' SBGT was running to support HPCI operations and has tripped.
'B' SBGT will not start.
lAW VY UFSAR, how is the HPCI system affected?
Airborne radiation level will rise in the HPCIarea.
- b. HPCI will continue to run.
Airborne radiation level will stay approximately the same in the HPCI area.
- c. HPCI will trip.
Airborne radiation level will rise in the HPCI area.
- d. HPCI will trip.
Airborne radiation level will stay approximately the same in the HPCI area.
Static Simulator Exams: None Last Revised: BLS Correct - HPCI will run but the lack of SBGT flow on the condenser will allow some radioactive steam to leak into the room.
Incorrect - Airborne levels will rise due to HPCI condenser leakage.
Incorrect Airborne levels will rise. HPCI will not trip.
Incorrect - Airborne levels will rise. HPCI will not trip.
Question #47 Vermont Yankee LOR Exam Bank Question Number Revised Revision 0 System: 261 SGTS Standby Gas Treatment System Instructor Guide: LOT-00-261 STANDBY GAS TREATMENT SYSTEM Objectives: CRO-2f
References:
OP 2115, section 'D', page 34 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Category: Plant Proficiency Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge Task Associations 2610020101 Place the SBGT System in Standby Readiness Knowledge of the physical connections and/or causeeffect relationships between STANDBY GAS TREATMENT SYSTEM and the following: Primary containment Question:
The plant is operating at 100% reactor power, all systems are OPERABLE.
IAWOP 2115, Primary Containment, which ONE of the following describes the preferred primary containment venting path during normal operations?
Vent the _(1)_ through _(2)_with nitrogen makeup to _(3)_.
(1) Torus (2) 'A' Standby Gas Treatment Train (3) Drywell
- b. (1) Drywell Incorrect - The B train should only be used (2) 'B' Standby Gas Treatment Train per note in OP 2115 if the A train is (3) Torus unavailable.
- c. (1) Torus Incorrect - Both trains are only used for (2) BOTH Standby Gas Treatment Trains emergency venting lAW OE 3107, (3) Drywell EOP/SAG appendices.
- d. (1) Drywell Incorrect Both trains are only used for (2) BOTH Standby Gas Treatment Trains emergency venting IA W OE 3107, (3) Torus EOP/SAG appendices. Also, the normal vent path would be from the torus with N2 makeup to the drywelL Static Simulator Exams: None Last Revised: 212712013, BLS
Question #48 Vermont Yankee LOI Exam Bank Question Number 6215 Revision 2 Instructor Guide: LOT 602 OPERATIONAL TRANSIENT PROCEDURES Objectives: RO E02
References:
OPOT-3169-01 Higher cognitive justification, candidate must recognize the trip of the 12 breaker causes a loss of Bus-I, then understand hislher immediate actions is to insert a manual SCRAM Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Analysis Task Associations 2000270501 Respond to a Loss of Feedwater 2000330501 Respond to a Reactor SCRAM 2007900501 Respond to a Loss of Bus 1 Using ON 3169 2007910501 Respond to a Loss of Bus 2 Using ON 3170 Question:
The following conditions exist:
- Early in November, the plant is operating at 85% power
- The Start-up transformers have been removed from service for ground repair and a planned 7 day LCO has been entered.
The switching and tagging order consists of the following:
- Subsequently breaker 12 trips on differential over-current.
Based on the above, what operator action is the: PRIORITY?
- a. Verify an automatic SCRAM occurs, if not, insert a manual SCRAM and enter OT 3100.
Manually SCRAM the reactor and enter OT3100.
- c. Enter OT 3113, Reactor Low Level, and verify operation of RFP 'C' and Condensate Pumps 'B' and 'C'.
Insert a manual SCRAM ONLY if level drops below 140 inches.
- d. Enter OT 3176, Recirc Runback due to Condensate or Feedpump Trip, and verify the Recirc runback occurs on Recirc MG
'B' and Feedwater Master level controller sets down to 155 inches.
Static Simulator Exams: None Last Revised: 1-30-13 by BLS Incorrect - Plausible, as a candidate may believe a automatic SCRAM occurs, but in this instance only a 112 SCRAM occurs due to the loss of a RPS bus.
Correct Response - OT 3169, LOSS of Bus 1, requires an immediate manual SCRAM.
Incorrect -Plausible as these components are still operating, but the immediate response is to insert a manual SCRAM.
Incorrect -Plausible as these events would occur automatically at a higher power level, but the operator's immediate response is to insert a manual SCRAM.
Question #49 Vennont Yankee LOI Exam Bank Question Number 6717 Revision 2 Instructor Guide: LOT-03-262 RUPS Objectives: RO Objective #7
References:
CWO 33SA, OP-2143 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Analysis Task Associations 2627310101 Transfer MCC-89A(B) Power from RUPS to the Maintenance TIE 262002 K4.01 Knowledge of UNINTERRUPTABLE POWER SUPPLY 3.1 3.4 (A.C.I D.C.) design feature(s) and/or interlocks which provide for the following: (CFR 41.7): Transfer from n..""",r to alternate nr""",..
Question:
The plant simultaneously experienced a Loss of Coolant Accident (LOCA) and Loss of Nonnal Power (LNP).
Five minutes later the following plant conditions exist:
Reactor water level is 60 inches and slowly lowering Reactor pressure is 750 psig and slowly lowering DryweU pressure is 4.2 psig and slowly rising The 4<A" EDG failed to start All other equipment is operating as expected for the current plant conditions.
-B' EDG is running loaded IAW OP 2143, 480 Volt and Lower AC Systems, the UPS-IB Feeder Breaker is
_(1)_ and is operating on _(2)_.
Correct Response-UPS-IB Feeder breaker is opened based on low-low level <82.5" however, the "B" EDG is powering Bus 3 and 8 as designed, therefore after -13 the M contact shuts however the
- b. (1) OPEN (2)AC
- c.
(1) CLOSED (2) DC
- d. (1) CLOSED (2)AC Static Simulator Exams: None Last Revised: 2-27-13 by BLS UPS Feeder breaker remains open from low-low level signal keeping the UPS on DC Drive.
Incorrect - UPS-l B Feeder breaker is opened based on low-low level <82.5" however, the "B" EDG is powering Bus 3 and 8 as designed, therefore after -13 seconds, the M contact shuts however the UPS Feeder breaker remains open from low-low level signal keeping the UPS on DC Drive.
Incorrect - UPS-IB Feeder breaker is opened based on low-low level <82.5" however, the "B" EDG is powering Bus 3 and 8 as designed, therefore after -13 seconds, the M contact shuts however the UPS Feeder breaker remains open from low-low level signal keeping the UPS on DC Drive.
Incorrect - UPS-IB Feeder breaker is opened based on low-low level <82.5" however, the "B" EDG is powering Bus 3 and 8 as designed, therefore after -13 seconds, the M contact shuts however the UPS Feeder breaker remains open from low-low level signal keeping the UPS on DC Drive.
Question #50 Vermont Yankee LOI Exam Bank Question Number 6860 Revision 1 Instructor Guide: LOT-00-601 OFF-NORMAL PROCEDURES Objectives: RO E01, E03
References:
OPON-3159-01 2007 ILO Audit Exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Analysis Task Associations 2007350404 Respond to a Loss of DC-1 263000 K6.01 Knowledge of the effect that a loss or malfunction of the 3.2 following will have on the D.C. ELECTRICAL DISTRIBUTION: K6.01 A.C. electrical distribution Question:
The plant is operating at rated conditions when an LNP occurs.
The following annunciator and control panel indications are noted by the crew:
DC-1IDC-2 BKR TRIP (8-N-1)
BUS 1 CTRL PWR LOSS (8-Q-2)
Loss of power to TURB INE TRIP MTS-1 "white" light Loss of power to ECCS Analog Trip Cabinet 25-5B In addition to entering OT 3100, procedure_(1 is entered, and RPV level is established with _(2)_?
(1) OPON-3159-01, Loss of DC-1 Incorrect - A loss of DC-1 has occurred, (2) HPCI only RCIC is available for level control.
(1) OPQN-3159-01, Loss of DC-1 Correct Response: Bus 1 control power (2) RCIC loss alarm, with MTS-1 light out and loss of power to the 5B ECCS trip cabinet are
. of a loss of DC-I. Further
- c. (1) ON 3160, Loss of DC-2 and DC-3 (2) HPCI.
- d. (1) ON 3160, Loss of DC-2 and DC-3 (2) RCIC Static Simulator Exams: None Last Revised: 1-31-13 by BLS the operator must discern that HPCI is now unavailable so RCIC is the only high pressure injection system after an LNP.
Incorrect - A loss of DC-l (not DC-2) has occurred and only RCIC is available. A loss of DC-2/3 will result in NO alarms.
Incorrect - A loss of DC-l (not DC-2) has occurred. A loss of DC-2/3 will result in NO alarms.
Question #51 Vermont Yankee LOI Exam Bank Question Number 113 Revision 4 Instructor Guide: LOT-00-264 EMERGENCY DIESEL GENERATOR Objectives: K 4.01, A4.04
References:
OP 2126 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge/Memory Task Associations 2640060101 Shut Down a Diesel Generator 264000 Al.03 Ability to what is and/or monitor changes in parameters 2.8 2.9 associated with operating the EMERGENCY GENERATORS (DIESEl/JET) control including: (CFR 41.5/45.5): Operating voltages, currents, and Question:
Emergency Diesel Generator (EDG) "A" started automatically due to a Design Basis, Loss of Coolant Accident.
With EDG "A" operating and supplying power to its associated bus, which ONE of the following signals will stop the diesel?
Static Simulator Exams: None Last Revised: 113112013 by Stewart, Brian
Question # 52 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System: 300000 Instructor Guide-:
Objectives:
References:
OPON-3146-01, Att 1 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge Task Associations Respond to a Loss of Instrument Air Pressure Knowledge of the connections and I or cause effect relationships between INSTRUMENT AIR SYSTEM and the Kl.03 Containment air Question:
Which ONE of the following statements is true regarding MSIV AirlNitrogen supply?
The inboard MSIVs, MS-80A-D, are supplied with _(1)_ and the outboard MSIVs, MS-86A-D, are supplied with _(2)_ when the primary containment is (1) instrument air Incorrect - When inerted, the inboard (2) containment air MSIVs use CA and outboard MSIVs use (3) inerted IA.
(3) de-inerted
(3) inerted
(2) instrument air and inboard MSIV s use IA.
(3) de-inerted Static Simulator Exams:
Last Revised:
Question #53 Vennont Yankee LOI Exam Bank Question Number New Revision 0 Instructor Guide: LOT-00-602 OPERATIONAL TRANSIENT PROCEDURES Objectives: RO EOS
References:
OT 3165 Caution Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge/Memory Task Associations 2000620504 Respond to Loss of TBCCW 400000 A2.03 Ability to (a) what is the impacts ofthe following on the CCWS and (b) based on those what isions, use procedures to correct, control, or mitigate the consequences of those abnonnal
- A2.03 CCW 2.9
3.0 Question
An unrecoverable loss of TBCCW has occurred due to a loss of service water flow to the TBCCW heat exchangers.
IA W OT 3165, Loss of TBCCW, as temperatures rise the condensate and reactor feed pumps are secured due to elevated _(1)_ and pump swaps _(2)_ pennitted.
(1) thrust bearing temperatures due to a loss of cooling will require tripping running condensate (2) are NOT and feed pumps within approximately 10 minutes to prevent bearing damage.
Pump swaps are pennitted to maintain RPV water level.
(1) thrust bearing temperatures due to a Correct Response-Unrecoverable loss of loss of cooling TBCCW will require tripping running (2) are condensate and feed pumps within approximately 10 minutes to prevent bearing damage. Pump swaps are to maintain RPV water level.
TRU cooling (2) are NOT
- d. (1) area temperatures caused by a loss of TRU cooling (2) are Static Simulator Exams: None Last Revised: 2-4-13 by BLS will require tripping running condensate and feed pumps within approximately 10 minutes to prevent bearing damage. TRU coolers are not the concern. Pump swaps are permitted to maintain RPV water level.
Incorrect - Unrecoverable loss of TBCCW will require tripping running condensate and feed pumps within approximately 10 minutes to prevent bearing damage. TRU coolers are not the concern. Pump swaps are permitted to maintain RPV water level.
Question #54 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 201003 Instructor Guide:
Objectives:
References:
OPON 3145, Reference Open/Closed: Closed SRO Only: No Style:
Categc[y:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 201003 A2.07 Ability to (a) what is the impacts of the following on the 3.1 CONTROL ROD AND DRIVE MECHANISM; and (b) based on those use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.07 Loss of CRD drive water flow Question:
The following plant conditions exist:
'A' CRD pump is in service CRD flow control valve CRD-FCV-19A is. in AUTO Reactor power is -50%
What is the change in CRD drive water pressure if CRD-PCV -20, CRD Drive Water Pressure Control Valve, fails closed and determine the required action.
CRD drive water pressure -(1)_ and lAW OPON-3145-0l, Loss ofCRD Regulating Function, rod movement is suspended until CRD drive water pressure is restored to between _(2)_ above reactor pressure.
(2) 250-275 psig
- b. (1) rises Incorrect - Wrong control band (2) 300-325 psig
- c. (1) lowers Incorrect - Drive water pressure rises (2) 250-275 psig
- d. (1) lowers Incorrect Wrong control band (2) 300-325 psig Static Simulator Exams: None Last Revised: 2-4-13, KM
Question # 55 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 202001 Instructor Guide:
Objectives:
References:
OP 2110, Reactor Recirculation System, VY has RBCCW and TBCCW NOT a separate CCW system, therefore this meets the KIA.
Reference Open/Closed: Closed SRO Only: No Style:
Categ(rry:
Point Value: 1 Time to Complete (Minute:U: 1 Question Level: Fundamental Knowledge Task Associations Respond to Recirculation Pump Trip 202001 A2.22 Ability to (a) what is the impacts of the following on the 3.1 RECIRCULATION SYSTEM; and (b) based on those what isions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or
- A2.22 Loss of water Question:
While operating at rated power the plant has a total loss of RBCCW.
As recirculation system temperatures rise, the recire _(1)_ if _(2)_.
Enter _(3)_.
(1) drive breaker will trip (2) lube oil temperature rises to 202 0 F (3) OT 3118, Recirc Pump trip
- b. (1) drive breaker will trip (2) lube oil temperature rises to 182 0 F (3) OT 3118, Recirc Pump trip (1) seals will fail (2) seal cavity temperature rises to 162 0 F (3) OPON-3142-01, Recirc Pump Seal Failure
- d. (1) seals will fail (2) seal cavity temperature rises to 142 0 F (3) OPON-3142-01, Recirc Pump Seal Failure Static Simulator Exams: None Last Revised: 2-4-13, BLS Incorrect: > 210 F will trip the recirc drive breaker NOT the field breaker. OT 3118 is the procedure to enter for this event.
Incorrect: > 210 F will trip the recirc drive breaker. OT 3118 is the procedure to enter for this event.
Correct: The recirc seals are cooled by RBCCW. Seals will fail at > 160 F.
Incorrect: The recirc seals are cooled by RBCCW. Seals will fail at >160 F making this a good distracter.
Question #56 Vermont Yankee LOR Exam Bank Ouestion Number NEW Revision 0 System: 202002 Instructor Guide:
Objectives:
References:
OP 2110, reactor recirculation system Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minuten: 2 Question Level: Fundamental Knowledge Task Associations Transfer from Master Manual to Individual Manual Control Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: K4.02 Recirculation pump control: Plant-Question:
The plant is operating at 100% CTP.
A trip of 'A' Reactor feed pump occurs.
IAWOP 2110, Recirculation System, 'A' and 'B' individual recirculation controllers
_(1)_ and recirculation pump speed will runback to _(2)_.
IAnswerlDistractor IJustification
- a. (1) remain in AUTO (2) minimum
- b. (1) remain in AUTO (2) 40% demand signal
- c. (1) shift to MANUAL (2) minimum (1) shift to MANUAL (2) 40% demand signal Static Simulator Exams: None Last Revised: 2-13-13, KM Incorrect - The shift of the controller to manual is an important follow-up verification in OT 3175, Recirc runback.
Runback to minimum is on inadequate NPSH from <20% feed flow to the recirc from feed water.
Incorrect - The shift of the controller to manual is an important follow-up verification in OT 3175, Recirc runback. A RFP trip will result in a recirc runback to the 40%
tube manual is an important follow-up verification in OT 3175, Recirc runback. A RFP trip will result in a recirc runback to the 40% scoop tube position. Runback to minimum is on inadequate NPSH from
<20% feed flow to the recife system from feedwater.
Correct - The shift of the controller to manual is an important follow-up verification in OT 3175, Recife runback. A RFP trip will result in a recirc runback to the 40%
tube
Question #57 Vennont Yankee LOI Exam Bank Ouestion Number 1378 Major Revision 3 Instructor Guide: LOT 215 TRAVERSING IN-CORE PROBE (TIP)
Objectives: K4.01
References:
OP 2115 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Fundamental KnowledgelMemory Task Associations 2000 17050 1 Respond to Containment Isolations 215001 Kl.05 Knowledge of the physical connections andlor cause-effect 3.3 3.4 relationships between TRANVERSING IN-CORE PROBE and the following: (CFR 41.2 to 41.9 / 45.7 to
- 45.8): Primary containment isolation system: (Not-BWRI Question:
A full core Local Power Range Monitor (LPRM) calibration is in progress with the Traversing In-core Probe (TIP) System.
- A fault in the Feedwater Control System results in the tripping of all Feedwater Pumps
- Level lowers to 75 inches before Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI) inject and restore reactor water level Given these conditions, what (if any) AUTOMATIC actions associated with the TIP System will occur?
- b. ONLY the Shear Valve fires.
The TIP drive retracts the TIP detector AND the ball valve closes.
Static Simulator Exams: None Last Revised: 2-5-13 by BLS Incorrect -Group II causes isolation at 127 inches.
Incorrect -no response at 82.5, no auto shear.
Correct Response-Group II causes isolation at 127 inches.
Incorrect -no response at 82.5, no auto shear.
Question #58 Vermont Yankee LOI Exam Bank Question Number 5679 Revision 0 Instructor Guide: LOT-OO-607 EOP-3, PRIMARY CONTAINMENT CONTROL Objectives: CRO 1
References:
EOP, Study Guide, Vol 4, Section 8, page 5 of 43 New Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental KnowledgelMemory Task Associations 2000190501 Respond to High Torus Water Temperature bility to manually operate andlor monitor in the control room: A4.12 "".~,.,..."'"
Question:
EOP-3, Primary Containment Control, has been entered due to high torus water temperature and low torus level.
Torus level is currently 8.3 feet and lowering slowly.
Which ONE of the following is the preferred indication to be used to determine torus water temperature IA W the EOP study guide when RHR is in service in Torus Cooling?
ERFIS point M0621M064 of average torus water temperature.
- b. TI-16-19-33C torus water temperature CRP 9-3.
- c. TI-16-19-33A torus water temperature CRP9-3.
- d. LR 23-73, CSTfTorus level on CRP 9-3 Static Simulator Exams: None Last Revised: 02/0112013 by BLS Correct - This is the average torus water temperature just upstream of the RHR heat exchanger which will be the RHR suction from the torus.
Incorrect - These detectors could become uncovered if torus level drops to <8.5 feet and will only read torus air space temperature.
Incorrect These detectors could become uncovered if torus level drops to <8.5 feet and will only read torus air space temperature.
Incorrect - This recorder is a narrow range, 10.75 to 12 foot, while the stem conditions state we are at 8.3 feet and lowering
Question #59 Vermont Yankee LOI Exam Bank Question Number 7994 Revision 1 Instructor Guide: LOT-01-223 PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS)
Objectives: Al.Ol, A3.01, K4.06
References:
CWDs 1100-1123 OP 2115 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge/Memory Task Associations 2000170501 Respond to Containment Isolations 223001 A3.03 Ability to monitor automatic operations of the PRIMARY 3.4 CONTAINMENT SYSTEM AND AUXILIARIES including: A3.03 System indicating light and alarms Question:
The six Primary Containment Isolation System (PCIS) red lights on the vertical section of CRP 9-5, lower right hand comer, are illuminated.
Which ONE of the following is indicated by these six red lights?
- a. The valve position indications required to Incorrect - These lights due not receive an satisfy the Inadvertant Opening Protect input from valve position signals Logic (IOPL), for PCIS groups 1,2, and 3 are satisfied.
The control switches required to satisfy the Correct Response Inadvertant Opening Protect Logic (IOPL),
for PCIS groups 1,2, and 3 are in the CLOSED position.
Isolation signals associated with PCIS Incorrect - The lights are illuminated by 2, and 3 isolations are clear and the swiches in the closed which
the valves are in the OPEN position.
causes the valves to be closed also
- d. A pels Group 1, 2 and 3 isolation signal is present and the isolations can NOT be reset.
Incorrect These six lights are not affected by any isolation signal, only by control switch position.
Static Simulator Exams: None Last Revised: 5115/20123:11:33 PM by Brown, Scott
Question #60 Vermont Yankee LOI Exam Bank Ouestion Number 7589 Revision 0 Instructor Guide: LOT-00-607 EOP-3, PRIMARY CONTAINMENT CONTROL Objectives: Kl.03
References:
Provide DWSIL curve EOP Study Guide, Section 8, pg 186 of 346 VY 2009 NRC exam Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge Task Associations 2000210501 Respond to High DryweU Temperature 226001 K5.06 Knowledge of the operational implications of the following concepts as they apply to RHRfLPCI:
CONTAINMENT SPRAY SYSTEM MODE: K5.06 Vacuum breaker nn~'rot-1nn
2.6 Question
An accident occurred and Drywell pressure is 5 psig with Drywell temperature 340°F and rising.
Based upon these plant conditions and the Drywell Spray Initiation Limit Curve, lAW EOP study guide, what adverse conditions could result from drywell spray initiation?
The evaporative cooling pressure drop may result in de-inerting the drywell by vacuum breaker opening following initiation of drywell sprays.
- b. The delta pressure between the drywell and torus will prevent the vacuum breaker from functioning as designed.
- c. The evaporative cooling pressure drop following initiation of drywell sprays may result in exceeding torus design internal pressure.
- d. Lowering drywell pressure may reopen the SRVs, causing RPV pressure to drop below the saturation pressure for the current DW temperature.
Static Simulator Exams: None Last Revised: 2/512013 by Stewart, Brian Correct Response-- lAW EOP Study Guide, The DWSIL is a function of drywell pressure. It is utilized to preclude de-inertion following initiation of drywell sprays.
Incorrect - This is the bases for the level limit.
Incorrect - the vacuum breakers are designed to prevent exceeding the DW external pressure limit (2 psig).
Incorrect -The SRVs may open in lowering PC pressure, however PC temperature will also be lowering and the SRVs will close at a sufficient DIP to prevent falling below the saturation pressure for the new DW temperature.
Question #61 Vermont Yankee LOI Exam Bank Question Number 7574 Revision 1 Instructor Guide: LOT-00-233 NORMAL AND STANDBY FUEL POOL COOLING AND CLEANUP SYSTEM Objectives: Al.07
References:
OP-2179, P&L 8, pg 6 VY 2009 NRC exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge/Memory Task Associations 2337180104 Place the SFPC System in Operation 233000 Al.03 Ability to what is and/or monitor changes in parameters 3.1 associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including: Al.03 Pool Ouestion:
The plant has just resumed power operations following a refueling outage.
The following conditions exist:
One train of Normal Fuel Pool Cooling (NFPC) is in service aligned to the Spent Fuel Pool with maximum cooling water flow through the in-service heat exchanger.
River temperatures are unusually high resulting in high Service Water and Reactor Building Closed Cooling Water (RBCCW) temperatures.
All trains of NFPC and Standby Fuel Pool Cooling (SFPC) are available.
Spent Fuel Pool temperature is 139° F and rising.
In accordance with OP 2179, Standby Fuel Pool Cooling, and OPOP-NFPC-2184, Normal Fuel Pool Cooling System, which ONE of the following actions is required?
- a. Place the OTHER train of NFPC in service.
- b. Maintain ONE train of NFPC in service and place ONE train of SFPC in service.
Secure NFPC and place ONE train of SFPC in service.
- d. Maintain ONE train of NFPC in service and place BOTH trains of SFPC in service.
Static Simulator Exams: None Last Revised: 2-4-13 by Stewart, Brian Incorrect - SFPC needs to be placed in service and so NFPC must be secured. It is physically impossible for NFPC and SFPC to be in service on the Spent Fuel Pool at the same time.
Incorrect - SFPC needs to be placed in service and Normal FPC has to be secured.
It is physically impossible for NFPC and SFPC to be in service on the Spent Fuel Pool at the same time.
Correct Response-From OP-2179, P&L 8, Prior to the Spent Fuel Pool water temperature exceeding 140 0 F, secure the Normal FPC and place the SFPC System in service. SFPC is cooled by SW, FPC is cooled by RBCCW.
Incorrect - SFPC need to be placed in service. It is physically impossible for NFPC and SFPC to be in service on the Spent Fuel Pool at the same time.
Question #62 Vermont Yankee LOR Exam Bank Question Number 574 Revision 3 System: 249 MHC Main Turbine Mechanical Hydraulic Control System Instructor Guide: LOT-00-249 MECHANICAL HYDRAULIC CONTROL SYSTEM Objectives: A2.01
References:
OT 3115 Main Turbine Tech Manual Must know what effect the pressure detector failure has on the EPR and what the resulting MHC system response will be Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Cat~: Plant Proficiency Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 2000180501 Respond to High Reactor Pressure Question:
The plant is operating normally at 100% power when the pressure averaging manifold pressure transmitter for the EPR (PT-110-4) fails to an approximately 50% signal.
lAW OP 2113, Main and Auxiliary Steam, which ONE of the following describes automatic plant response to this event?
Control valves open, lowering RPV Incorrect - Control valves will get a closed pressure until MPR takes control.
signal.
- b. Control valves open, lowering RPV Incorrect Control valves will get a closed pressure until Group I isolation occurs.
signal.
- c. Control valves close, raising RPV pressure Incorrect - Control valves will close until until the reactor scrams on high pressure.
the MPR takes over at a higher reactor pressure.
Control valves close, raising RPV pressure until MPR takes control.
Static Simulator Exams: None Last Revised: 02/0112013 by BLS Correct Response - When the pressure averaging manifold pressure transmitter signal fails to 50%, the MHC system, through the EPR, will sense reactor pressure low and close the control valves.
This will cause actual RPV pressure to rise resulting in the raising of the MPR stroke until it takes over control of the torque bar from the EPR.
Question #63 Vennont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 259001 Instructor Guide:
Objectives:
References:
OPOT-3169-01, The operator must recall that 'AlB' RFP are powered from Bus 1 with the 'B' RFP RFP's powered from bus 2. Then, apply the given conditions with RFP and STBY to detennine the correct RFP configuration.
Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minute:il: 2 Question Level: Fundamental Knowledge Task Associations Question:
The station is starting up with power at 65%
'A' RFP is running
'B' RFP is in STANDBY
'C' RFP is running Subsequently a loss of Bus 1 occurs lAW OPOT-3169-01, Loss of Bus-I, what is the status ofRFP's?
AnswerlDistractor Justification
'B' RFP is running RFP would still be secured with no power.
'C' RFP is tripped
'C' RFP is powered from bus 2.
'B' RFP is in STBY from Bus 1 and would be tripped. 'C' RFP
'C' RFP is running is powered from bus 2 and should be running.
- c.
'B' RFP is running RFP would still be secured with no power.
'C' RFP is tripped
'C' RFP is powered from bus 2 and should I
, A' RFP is tripped
'B' RFP is in STBY
'C' RFP is running Static Simulator Exams: None Last Revised: 2-13-13, KM be running.
Correct - 'A' and 'B' RFP's are powered from Bus 1 and 'c' RFP is powered from Bus 2.
Question # 64 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 271000 Instructor Guide:
Obiectives:
References:
OPOP-AOG-2150; Alarm Response Sheet 6-H-l Reference Open/Closed: Closed SRO Only: No Style:
Cate~my:
Point Value: 1 Time to Complete (Minute:§}: 2 Question Level: Analysis Task Associations Respond to Condenser High Back Pressure 271000 K6.11 Knowledge of the effect that a loss or malfunction of the 3.2 following will have on the OFFGAS SYSTEM: K6.11 Condenser vacuum Question:
The plant is operating at 96% power coasting down for a refuel outage.
FCV-OG-516A is in-service throttled 60.8% open to control Offgas System Flow.
FCV-OG-516B is in-service throttled 100% open to control Offgas System Flow.
o Air in leakage results in rising Main Condenser backpressure o
As a result pressure in the Offgas System OG-IOO Line rises to 8.0 psig.
o Annunciator 6-H-l, AOG PRESS HI, is received Based on these Offgas System conditions the operator should verify:
automatically close.
- b. BOTH OG-S16A and OG-S16B will stay in their current position.
- c. OG-S16A will automatically close AND OG-S16B will stay in its current position.
- d. OG-S16B will automatically close AND OG-S16A will stay in its current position.
Static Simulator Exams: None Last Revised: 2-4-13, BLS Correct-lAW Alarm Response Sheet for Annunciator 6-H-1 and OP 21S0 (Discussion Section) high pressure in the OG-lOO Line at S.4 psig as sensed by 2 of 2 pressure switches OG-PS-102-21E and G will provide an automatic close signal to both OG-SI6A/B valves.
OG-S16A/B will get an auto close signal based on high pressure in the OG-100 Line. This is a plausible distractor if the operator does not interpret the OG 100 line isolation.
OG-S16A & B will get an auto close signal based on high pressure in the OG-100 Line. This is a plausible distractor because OT 3120 directs operator to reset and open OG-S16 valve to control main condenser backpressure.
Both OG-S16NB receive an auto close signal based on high pressure in the OG 100 Line. This is a plausible distractor because the OG-S16A valve will trip close on high pressure in the OG-100 Line and OT 3120 directs operator to reset and open OG-S16 valve to control main condenser sure.
Question #65 Vermont Yankee LOI Exam Bank Question Number 6758 Revision 2 Instructor Guide: LOT-00-601 OFF-NORMAL PROCEDURES Objectives: RO E02
References:
OP-2150 ON-3152 Automatic Action l.a Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental KnowledgelMemory Task Associations 2007090501 Respond to High Off-Gas Radiation Question:
The Advanced Off Gas System is operating with OG-145 (Dryer Skid) open and OG-146 (Adsorber Bed Bypass valves) closed when the Off Gas Radiation monitor, RAN-OG 3128, fails upscale.
IA W OPOP-AOG-2150, AOG System, with no operator action, which of the following will occur?
Both FCV-ll (stack isolation) and OG-3 (delay line drain) will close in 30 minutes.
Incorrect - Both close in 30 minutes when either OG-145 or 146 are shut.
Incorrect - Both close in 30 minutes when either OG-145 or 146 are shut.
Correct Response-Rad Level to Holdup and Stack, RAN OG 3127 and RAN OG 3128 will close OG FCV 11, Off Gas to Stack Isolation, at the stack and, Delay Pipe Solenoid Drain to Radwaste Bypass, OG 3 under the following conditions When.
the AOG skid and adsorber bed
bypass valves OG 145 or OG 146 are closed and either radiation monitor has a Hi Hi trip signal present for 30 minutes, or either radiation monitor downscale alarm is present or power switch in OFF for 30 minutes.
- d. Both FeV-ll (stack isolation) and OG-3 Incorrect - Both close in 30 minutes when (delay line drain) will close in 2 minutes.
either OG-145 or 146 are shut. This is the case when both OG-145 and 146 are initially open.
Static Simulator Exams: None Last Revised: 612812012 11:26:27 PM by Schulze, William H.
Question #66 Vennont Yankee LOI Exam Bank Question Number 5574 Revision 1 Instructor Guide: LOT-00-602 OPERATIONAL TRANSIENT PROCEDURES Objectives: CRO-5
References:
OT-3U9 Follow-up action Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 3 Question Level: Analysis Task Associations 2007250501 Respond to a Loss of Stator Cooling Ability to perfonn specific system and integrated plant procedures during all modes of plant operation.
Question:
jJ-'
00\\.)0/
With the plant at 30% power, a complete loss of Stator Cooling has QCCl:UTed:
lnmlediftte ~torastioas Rft'/?beea takerr:"
The SC TURBINE TRIP TIMER INITIATED alann has been energized for 68 seconds.
The FIRST operator action for this condition is to:
- a. Trip the turbine.
Incorrect lAW EN-OP-115, Conduct of Operations, Section 5.2 [1], the operator shall scram and then. the turbine.
Insert a manual scram, then confirm or initiate a turbine trip.
Correct Response If SC TURBINE TRIP TIMER INITIATED alann is in for longer than one minute and stator cooling is not recovered, then confinn or initiate a turbine trip. lAW EN-OP-II5, Conduct of Operations, Section 5.2 [1], the operator shall scram and then. the turbine.
- c. Rapidly reduce SIL changer to 32%.
Incorrect This is one way to unload the turbine load and but is not called for
- d. Reduce reactor power using the RS in this situation.
S.
Incorrect The alarm indicates a turbine trip should have occurred.
Static Simulator Exams: None Last Revised: 3129120126:10:56 PM by Schulze, William H.
Question #67 Vermont Yankee LOR Exam Bank Question Number 42 Major Revision 4 System: 344 ABNORM AbnormalJEmergency Operations Instructor Guide: LOT-00-608 EOP-5, RPV-ED; EOP-6, RPV FLOODING Objectives: A.2
References:
EOP Study Guide Reference Open/Closed: Open-Provide MSCP SRO Only: No Style: Multiple Choice Category: Limits & Controls Point Value: 1 Time to Complete (Minutes): 10 Question Level: Analysis Task Associations 2000310501 Respond to Low Reactor Water Level Ability to interpret reference materials, such as graphs, curves, tables, etc.
Question:
An A TWS has occurred.
NO injection or alternate injection systems are running.
Four rods are at notch 48.
RPV level is -25 inches.
RPV Emergency Depressurization is in progress.
IA W EOP-2, MSCP, in which ONE of the following sets of conditions, is adequate core cooling still maintained?
_(l)_SRV(s) open with RPV pressure _.(2)_ to maintain <_(3)_OF peak cladding temperature.
Correct - MSC pressure for 1 SRV open is 670#. IA W EOP basis document, as long as RPV pressure is > MSCP for the number of SRV's open then steam flow will ensure that fule clad temperatures will not exceed 1500 F of RPV leveL Incorrect - This is the wrong interpretation of the MSCP table.
(2) 195 (3) 2200
- d. (1) Four (2) 110 (3) 2200 Static Simulator Exams: None Last Revised: 2-4-13 by BLS of the MSCP table and 2200 is the ECCS acceptance criteria temperature making this a plausible distracter.
Incorrect - This is the wrong interpretation of the MSCP table and 2200 is the ECCS acceptance criteria temperature making this a plausible distracter.
Question # 68 Vermont Yankee LOR Exam Bank: Question Number New Revision 0 System:
Instructor Guide:
Objectives:
References:
OP 4152, The operator must understand the floor and equipment drain purposes as to which delta readings will produce identified and unidentified. Then, apply knowledge of the surveillance and calculate the GPM from the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> readings.
Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minute&),: 2 Question Level: Analysis Task Associations Perform Primary Containment Leak Rate Test Knowledge of Surveillance Procedures Question:
The following readings were recorded by the RO:
Floor drain sump Equipment drain sump Integrator Time Integrator Time (FQ 20-527)
(FQ 20-530) 857964 0600 34307656 0600 857921 0000 34307363 0000 lAW OP 4152, Equipment and Floor Drain Sump and Totalizer Surveillance, calculate the identified and unidentified leakage rates.
Identified leakage= 0.12 GPM Unidentified leakage= 0.81 GPM Identified leakage= 0.81 GPM Unidentified leakage= 0.12 GPM
- c. Identified leakage= 0.12 GPM Unidentified leakage= 0.93 GPM
- d. Identified leakage= 0.81 GPM Unidentified leakage= 0.93 GPM Static Simulator Exams: None Last Revised: 2-14-13, KM min=O.81 GPM for equipment (identified) leakage. 64-21=43/6hrs=7.16/60 min=O.12 GPM for floor Incorrect: Plausible because the operator may incorrectly think that the leakage rates into both sumps need to be added to calculate the unidentified rates.
Incorrect: Plausible if the operator doesn't understand the sump assignment or calculates incorrectly by using floor drain for identified rates.
Question # 69 Vennont Yankee LOR Exam Bank Ouestion Number New Revision 0 System:
Instructor Guide:
Objectives:
References:
Tech Specs Reference Open/Closed: Closed SRO Only: No Style:
Categq.a:
Point Value: 1 Time to Complete (Minute:§}: 2 Question Level: Comprehension Task Associations 3417040302/0 Ensure Technical SpecificationslTRMlODCM are Followed by Shift 3
Operations Crews Ability to recognize system parameters that are entry level conditions for Technical Question:
Which ONE of the following conditions requires entry into Tech Specs?
Reactor power _(1)_ % and Core flow PSIG __,_,__ %.
NOTE: COLR PowerlFlow map provided.
I I AnswerlDistractor Justification
- a. (1) 19 Incorrect: This is between the minimum
(2) 31 (1) 53 (2) 38
- c. (1) 55 (2)44
- d. (1) 75 (2) 56 Static Simulator Exams: None Last Revised: 2-14-13, BLS speed pump line and the natural circulation line. The reactor startup can be operated here and will under some low flow conditions.
Correct: The reactor is operating in the exclusion region which is a violation of Tech
3.6.1. Incorrect
The reactor is operating in the buffer region and should be maneuvered Incorrect: The reactor is operating above the MELLA region which is permissible but action.
Question #70 Vermont Yankee LOI Exam Bank Question Number 1389 Revision 1 Instructor Guide: LOT-00-202 REACTOR RECIRCULATION SYSTEM Objectives: K4.12
References:
T.S. 3.6.A.4, OP 2110 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental KnowledgelMemory Task Associations 2020040101 Startup a Recirc Pump with One Pump Already Running e of the bases in Technical Specifications for nditions for and s limits.
Question:
Which ONE of the following actions 1) is PROHIBITED by T.S. and OP 2110 and 2) why?
- a. 1) Operation of one reactor recirculation loop with greater than a 50° F temperature difference between the loops.
- 2) To minimize thermal shock to reactor vessel nozzles.
- b. 1) Operation of one reactor recirculation loop with greater than a 145 0 F temperature difference between the bottom head drain and the reactor saturation temperature.
- 2) Minimize bottom head drain to RWCU thermal stress.
- 1) Startup of an idle reactor recirculation loop with greater than a 50° F temperature difference between the idle and operating loop.
To minimize thermal shock to reactor Incorrect - The limit is on recirc pump starts with this delta temp.
Incorrect - The limit is on recirc pump starts with this delta temp.
Correct Response-In order to limit thermal shock to the reactor vessel nozzles and the bottom reactor head region on startup of an idle recirculation loop, two temperature limits have been established: The first
vessel nozzles.
- 1) Startup of an idle reactor recirculation loop with greater than a 145 0 F temperature difference between the bottom head drain and the idle loop.
- 2) Minimize bottom head drain to RWCU thermal stress.
Static Simulator Exams: None Last Revised: 2-4-13 by BLS thermal consideration requires coolant temperature in the idle loop to be within 50F of the operating loop prior to pump start. The second thermal consideration requires the bottom drain temperature to be within 145F of the reactor saturation start.
Incorrect - The thermal consideration requires the bottom drain temperature to be within 145 F of the reactor saturation temperature prior to pump start.
Question #71 Vennont Yankee LOI Exam Bank Question Number New Revision 0 Instructor Guide: LOT-01-400 OPERATIONS DEPARTMENT ADMINISTRATIVE PROCEDURES-2 Objectives: RO 9
References:
AP 0155, pg 4 definitions From PNPS 2010 NRC exam, heavily revised Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental KnowledgelMemory Task Associations 2000610504 Respond to Excessive Radiation Levels Question:
An ALERT has been declared.
The HPCI Pump is cavitating and must be tripped locally in a radiation field of 90 Rem per hour.
A 52 year old worker volunteers to perfonn the required manipulation.
He has 0 mrem accumulated dose for this calendar year.
IA W OP 3507, Emergency Radiation Exposure Control, what is the MAXIMUM dose he is authorized to receive for this task?
Static Simulator Exams: None
Last Revised: 0212712013 by BLS
Question #72 Vermont Yankee LOI Exam Bank Question Number 7556 Revision 3 Instructor Guide: LOT 601 OFF-NORMAL PROCEDURES Objectives: E07
References:
VY 2009 NRC exam OPON-3153-01 9 - 3 E6 OP-2182, P&L #1 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental KnowledgelMemory Task Associations 2000610504 Respond to Excessive Radiation Levels Generic 2.3.14 Knowledge of radiation or contamination hazards that may 3.4 3.8 arise during normal, abnormal, or emergency conditions or activities.
Question:
In accordance with OPON-3153-01, Excessive: Radiation Levels, which one of the following indicates a leak into the RBCCW system?
- a. Lowering of Fuel Pool water level causes a lowering suction pressure to the RBCCW pumps and a concurrently rising refuel floor radiation.
Hi radiation alarm on the RBCCW Process.
Radiation Monitor and rising level in the RBCCW Surge Tank.
A rise in the radiation levels in the vicinity of RBCCW or Incorrect - Lowering fuel pool level due to a leak in the FPC heat exchangers would cause a rise in RBCCW suction pressure due to the head of water.
Correct - Per ON-3153. If the RBCCW radiation monitor indicates a high radiation level: Isolate the RCU system and check surge tank level indication to determine if the leak has been isolated, If the RBCCW surge tank level continues to increase, shift to the standby fuel pool cooling heat exchanger and continue to monitor surge tank level.
Incorrect -Rising rad levels around RBCCW is a valid indication of a
and high temperatures on the operating CRDPump.
- d. Hi radiation alarm on the Service Water (SW) Process Radiation Monitor with concurrent indication of a RBCCW heat exchanger tube leak.
Static Simulator Exams: None Last Revised: 2-4-13 by BLS leak per OP-2182, P&L #1 Be aware of normal radiation levels in the vicinity of the system. Any appreciable rise in these radiation levels can indicate a possible leak into the RBCCW system. RBCCW supplies bearing and oil coolers on the CRD Pump, therefore, high CRD pump temperatures could indicate a lower RBCCW flow and not a leak into the RBCCW system.
Incorrect - A high radiation level in the SW system would indicate a leak into the SW system however by OP 2181 App B the SW system is maintained at a higher pressure than the RBCCW system, so leakage would be into the RBCCW system.
Question #73 Vermont Yankee LOR Exam Bank Question Number 2225 Revision 2 System:
Instructor Guide: LOT-00-61O EOP-l, RPV CONTROL; EOP-2, ATWAS RPV CONTROL Objectives: 2.4.1
References:
EOP Study Guide Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Ca~: Plant Proficiency Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000310501 Respond to Low Reactor Water Level Question:
Given the following conditions:
- Off-site power has been lost (LNP) and a large break LOCA has occurred
- The 'A' EDG failed to start
- DW pressure is 28 psig and slowly lowering
- Reactor pressure is 50 psig and lowering
- Reactor level is off scale low
- Reactor building HVAC exhaust radiation is 12 mrlhr The required actions are to enter EOP 1 and ___.
steam sure and can not*.
causes a loss of 4 KV Bus 4, and 3 of 6 low pressure ECCS pumps are without
",,,,,pr There are no conditions for
EOP 4 until RB fads is > 14 mrlhr.
RHR loop powered from each EDG, 2 RHR pumps will be running and injecting.
There are no entry conditions for EOP 4 until RB rads is > 14 mrlhr.
Static Simulator Exams: None Last Revised: 2-5-13 by BLS
Question # 74 Vennont Yankee LOR Exam Bank Question Number 1696 Revision 2 System: 344 ABNORM AbnonnallEmergency Operations Instructor Guide: LOT-00-611 EOP-4, SECONDARY CONTAINMENTIRADIOACTIVITY RELEASE CONTROL Objectives: RO-4
References:
VY EOP Man Vol 4 Justification: Water level is above max Nonnal Operating Water Level of I" in the RCIC room, which is an EOP-4 entry condition and 3158 entry condition.
Reference Open/Closed: Open SRO Only: No Style: Multiple Choice Category: Limits & Controls Point Value: 1 Time to Complete (Minutes): 4 Question Level: Analysis Task Associations 2007220501 Respond to Reactor Building High area TemperaturelWater Level Question:
A fire protection header rupture has resulted in 5 inches of water in the RCIC Room.
The leak has been isolated, all available sump pumps are operating and water levels in the space are slowly lowering.
For these conditions the crew is required to...
- a. enter ON-3158, Reactor Building High Area TemperaturelWaterLevel, ONLY.
- b. enter EOP-4, Secondary Containment and Radioactivity Release Control, ONLY.
- c. enter ON-3158 and enter into EOP-4later if water level cannot be reduced.
Incorrect - Good distractor as student will think actions to isolate are complete and levels lowering, no reason to go further in redundant Incorrect -Good distractor as student will think actions to isolate are complete and levels lowering, no reason to go further in a redundant Incorrect -Good distractor to a student that does not understand the basis, both are when hit the limits
regardless of status. Start in ON and progress to EOP as condition worsens would be a 10 ical se uence.
di*' enter ON-3158 and EOP-4 concurrently.
Correct Response-As required by entry conditions.
Static Simulator Exams: None Last Revised: 2-6-13 by BLS
Question # 75 Vermont Yankee LOI Exam Bank Question Number 2387 Revision 4 Instructor Guide: LOT-00-607 EOP-3, PRIMARY CONTAINMENT CONTROL Objectives: RO E03
References:
EOP Study Guide (Volume 4) section 8 page 23 Reference Open/Closed: Open, provide DWSIL curve SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 3450120102/0 Direct Manual Initiation of Containment Spray 3
Question:
In EOP-3, basis for initiating Drywell Sprays when Torus pressure exceeds 10 psig is.~_____.
- a. prevent the Drywell Spray Initiation Limit (DWSIL) curve from being exceeded.
ensure that the PCPL-A limit is not exceeded, due to excessive containment pressure.
prevent the cyclic condensation of steam (chugging), at the downcomer openings of the Drywell vents.
Incorrect - Drywell sprays are initiated when torus pressure exceeds the Suppression Chamber Spray Initiation Pressure (SCSIP) to preclude chugging-the cyclic condensation of steam at the downcomer of the vents.
Incorrect - Drywell sprays are initiated when torus pressure exceeds the Suppression Chamber Spray Initiation Pressure (SCSIP) to preclude chugging-the cyclic condensation of steam at the downcomer of the vents.
Correct Response-Drywell sprays are initiated when torus pressure exceeds the Suppression Chamber Spray Initiation Pressure (SCSIP) to preclude chugging-the cyclic condensation of steam at the downcomer of the available to
prepare for RPV-ED, if sprays are not effective.
Static Simulator Exams: None Last Revised: 2-6-13 by BLS when torus pressure exceeds the Suppression Chamber Spray Initiation Pressure (SCSIP) to preclude chugging-the cyclic condensation of steam at the downcomer openings of the drywell vents.
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