ML13106A192
| ML13106A192 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/22/2013 |
| From: | Operations Branch I |
| To: | Entergy Nuclear Vermont Yankee |
| Jackson D | |
| Shared Package | |
| ML12214A189 | List: |
| References | |
| TAC U01898 | |
| Download: ML13106A192 (144) | |
Text
Question #1 Vermont Yankee LOI Exam Bank Question Number 5878 Revision 1 Instructor Guide: LOT 602 OPERATIONAL TRANSIENT PROCEDURES Objectives: CRO EO-3, EO-5
References:
OPOT-3118, (page 4 Note)
Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Ouestion 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: (CFR 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-31 18-01 Recirculation Pump Trip, what is the reason for this indication?
The reverse flow summer is subtracting positive flow through the idle loop jet 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 s than 5 mlblhr or 14 drive flow
- b. The reverse flow summer is subtracting negative flow through the idle loop jet pumps.
- c. A jet pump mixer has been displaced.
- d. The recirculation flow comparator is compensating for the natural circulation in the idle loop.
Static Simulator Exams: None Last Revised: 1-29-13, BLS.
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).
Incorrect - Plausible as the summer is providing a calculation input to the P/F map but it is the positive flow under these specific conditions.
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)
Incorrect - plausible, The flow comparator does not compensate for idle loop operation.
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 S 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 lAW OT 3122, Loss of Normal Power, which lONE of the following actions is required for supplying the Vital AC Bus and why is this. action taken?
Incorrect - Incorrect there is no power motor to minimize station DC loads on the supply to 480 V AC 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: V AC 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 shifting to the alternate
- c. Adjust the 'A' EDG frequency as required to obtain a steady state 59.7 to 60.5 Hz to pennit the Vital AC Bus to automatically transfer to the AC Drive.
- d. Adjust the 'A' EDG frequency as required to obtain a steady state 59.7 to 60.5 Hz to prevent the Vital AC Bus from automatically transferring to the DC Drive.
Static Simulator Exams: None Last Revised: 1-29-13, by Stewart, Brian Incorrect - Incorrect the A EDG supplies 480 VAC Bus 9, adjusting voltage on that EDG will have no effect.
Incorrect - Incorrect the A EDG supplies 480 VAC Bus 9, adjusting voltage on that EDG will have no effect.
Question #3 Vermont Yankee LOI Exam Bank Ouestion Number 995 Revision 1 Instructor Guide: LOT 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 Ouestion:
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 "An. 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 "B" EDG would be lost.
The HPCI and RCIC high level trips would not function.
The control power to the "B" EDG would be lost.
Static Simulator Exams: None Last Revised: 1-29-13, BLS Incorrect - HPCI high level trip is also lost Correct - HPCI and RCIC high level trip would not function. The control power to the "B" EDG would be lost.
Question #4 Vermont Yankee LOI Exam Bank Question Number 1127 Revision 1 Instructor Guide: LOT-01-262 4 KV ELECTRICAL DISTRffiUTION 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 determine 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 alarm (LOSS) state.
- Ten minutes later, the main generator trips and locks out.
In this condition:
Recirc MG 'B' drive motor breaker will Incorrect - Powered from Bus 2. Fast 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. Bus 1 Automatic fast transfer will 0 correct - Requires sync-check relay.
Static Simulator Exams: None Last Revised: 1-29-13, BLS
Question #5 Vermont Yankee LOI Exam Bank Ouestion 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 AK1.02 Knowledge of the operational implications ofthe 3.4 3.7 following concepts as they apply to SCRAM: (CPR 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 SRV s
- 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 IA W the EOP-2 study guide, which of the following statements is true?
cool down should be started.
- d. The reactor is not shutdown until SLC tank level is 67% and a cooldown should 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 Question Number 7582 Revision 0 Instructor Guide: LOT-00-612 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:
lAW OPOP-ALTSD-3126, Shutdown Using Alternate Shutdown Methods, which ONE of the following occurs when the 4KV/480V 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. If not 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 Vermont Yankee LOI Exam Bank Question Number 5677 Revision 1 Instructor Guide: LOT-00-603 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 ofRBCCW, 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 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 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 Ouestion:
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?
- 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 Ouestion Number 3541 Revision 1 Instructor Guide: LOT 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 AAl.01 Ability to operate and/or monitor the following as they 3.4 apply to LOSS OF SHUTDOWN COOLING: AAl.Ol Reactor water Question:
Refueling is in progress.
0 A loss of shutdown cooling occurred with reactor coolant temperature at 155 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 What systems should be directed for use as the initial feed and bleed method?
Condensate transfer through the Core Spray system with RWCU letdown.
- b. Condensate transfer through the Core Incorrect Condensate transfer may be Spray system and an open SRV.
used with SRV's but only to stay <2120 F.
Core spray is only used when the reactor cavity is NOT flooded.
- c. Injection by using the Core Spray pumps Incorrect - Core spray is only used when with RWCU letdown.
the reactor 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 andlor 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 lAW OP 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 byRP.
action be taken to recover or reposition a dropped fuel assembly.
Evacuate the Refuel Floor of all personnel Correct - lAW OP 1100, this is one of the immediately regardless of RP direction.
listed conditions to evacuate the refuel floor
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 Vennont Yankee LOR Exam Bank Ouestion Number 1976-Revised Revision 2 System:
Instructor Guide: LOT-00-261 STANDBY GAS TREATMENT SYSTEM Objectives: K5.02, K6.0S
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 treatmentlFRVS: Plant-S""''i"'1
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.S psig and steady with all DW RRUs in service.
Based on plant conditions, and lAW OP 2117 SBGT System, what is the expected position of the following SBGT valves?
SGT-IA (SGT Inlet Bypass)
SGT-2A (SGT Inlet Isolation)
SGT-3A (SGT Discharge Isolation)
_(3L_
- a. (1) remains OPEN Incorrect - In a standby lineup, the 2A and (2) OPENS 3A are open. A PCIS group 3 signal was (3) OPENS received and both trains of SBGT start. As a result, the lA valve will open.
- b. (1) remains CLOSED remains OPEN
(3) remains OPEN (l)OPENS (2) remains OPEN (3) remains OPEN
- d. (1) remains CLOSED (2) CLOSES (3) CLOSES Static Simulator Exams: None Last Revised: 2/512013 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 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 295025 Instructor Guide:
Objectives:
References:
EOP Study guide, Section 6, pg 49 of 51 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 Containment Isolations 295025 EA2.05 Ability to determine and/or interpret the following as they 3.4 apply to HIGH REACTOR PRESSURE: EA2.05 Decay heat generation.
Question:
A reactor SCRAM occurs coincident with a Group 1 isolation.
Reactor pressure is 1050 psig and rising.
No Operator action is performed.
During the next hour, and lAW the EOP study guide, the rate of automatic SRV actuations will_{I)_ as Decay Heat _(2)_.
- a. (1) rise Incorrect - DH lowers following a scram.
(2) rises
- b. (1) rise Incorrect - As DH lowers SRV cycling will (2) lowers decrease.
- c. (1) lower Incorrect - DH lowers following a scram.
(2) rises Correct. As DH lowers SRV cycling will lowers decrease.
Static Simulator Exams: None Last Revised: 2-4-13. KM
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 (Minute~: 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 SR V s are being used to control reactor pressure SRV T' 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 lAW 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 the convective cooling.
- b. Drywell spray due to the evaporative cooling.
- c. Torus cooling due to the convective cooling.
- d. Drywell spray due to the 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 Vennont Yankee LOI Exam Bank Question Number 3222 Revision 1 Instructor Guide: LOT 622 OE OVERVIEW Objectives: 8
References:
Provide Graph of Minimum Indicated Level-RPSIECCSrrransients from EOP-l EOP-l and EOP-3 Minimum Indicated Level -RPSIECCSrrransients 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 295028 EK1.01 Knowledge of the operational implications of the 3.5 3.7 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
- DryweU pressure is 5.3 psig
- RPV pressure is 700 psig and lowering
- Reference Leg Temperatures are reading 300 0 F lAW 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.
+ 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 Vennont Yankee LOI Exam Bank Question Number 7553 Revision 2 Instructor Guide: LOT-00-223 PRIMARY CONTAINMENT DESIGN Objectives: A2.11
References:
EOP study guide, Section 8, pg 32 Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension Task Associations 2000240501 Respond to Low Torus Water Level 3.5
3.8 Question
Given the following:
- Suppression Pool level is lowering due to a leak in the torus.
- The Reactor is shutdown in accordance with EOP-1, RPV Control.
lAW 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 torus differential pressure rises. uncovered at 5.5 feet torus level.
- b. The SRV tailpipes become uncovered and Incorrect - The SRV tailpipes become Drywell to torus differential pressure uncovered at 5.5 feet torus level.
lowers.
- c. The downcomer pipes become uncovered Incorrect - Once seven feet is reached, the and Drywell to torus differential pressure Differential pressure equalizes and will not nses.
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-00-61O 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 KnowledgelMemory 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 ""POT" Question:
A Group 1 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%
lAW 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 sub cooling.
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 Question:
Given the following plant conditions:
An ATWS 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 - Prevent ADS System actuation during intentional RPV level lowering and possible subsequent injection of cold, un-borated water.
Inhibit ADS To allow time for boron Incorrect - We do not allow ADS system injection to shutdown the reactor before actuation during an ATWS to prevent a allowing system actuation as a later EOP thermal transient on the RPV or reactivity transient on the core due to cold water
- c. Implement OE 3107, Appendix P Maintain MSIV s OPEN by bypassing the high steam flows that occur during an ATWS.
- 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 injection.
Incorrect - The MSIV isolation that is bypassed is for RPV low water level to allow terminate and prevent actions later.
Incorrect - The main condenser is maintained available as a heat sink to protect primary containment.
Question # 18 Vennont Yankee LOR Exam Bank Ouestion 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 (Minutes): 1 Ouestion Level: Analysis Task Associations Respond to Excessive Radiation Levels Ouestion:
With a reactor startup in progress, lAW OP 0105, Reactor Operations, the operation of the mechanical vacuum pump (hogger) is allowed only under which ONE of the following conditions and for what reason?
The hogger may only be operated at _(1)_ with the _(2)_because the discharge piping is _(3)_.
(1) <4% reactor power (2) mode switch out of RUN (3) only through a 2 minute delay pipe (1) <4% reactor power (2) mode switch out of RUN (3) not rated for Hydrogen ignitions Correct - To operate below the system isolation setpoint and minimize rad release through the short delay pipe.
Incorrect - The discharge piping is rated for hydrogen ignitions.
background rads (2) hogger suction valve throttled (3) only through a 2 minute delay pipe
- d. (1) <1.5 times normal full power background rads (2) hogger suction valve throttled (3) not rated for Hydrogen ignitions Static Simulator Exams: None Last Revised: 2-11-13, BLS for hydrogen ignitions. 1.5 times NFPB is the system isolation. The Hugger suction valve is only throttled to minimize rad releases.
Incorrect - The discharge piping is rated for hydrogen ignitions. 1.5 times NFPB is the system isolation. The Hugger suction valve is only throttled to minimize rad releases.
Question #19 Vermont Yankee LOI Exam Bank Ouestion Number 5728 Revision 1 VY bank major revision Instructor Guide: LOT 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 Question 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 Question:
An electrical fire is burning in MCC-89A.
The fire brigade wants to use water to fight the fire in MCC-89A.
IAWOP 2186, Fire Suppression Systems, the MCC-89A _(1)_ be de-energized
_(2)_.
- a.
- 1. MUST 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. I.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 ection valves and recirc and when so
isolation valves.
directed by the Shift Manager.
- 1. SHOULD Correct Response-Electrical equipment
- 2. to avoid electric shock hazard to the fire involved in, or in the vicinity of a fire, 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 Ouestion 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 (Minutes): 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, predict 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.
'B' EDG secured in a standby lineup.
- d. 'A' EDG secured in a standby lineup.
Incorrect - balanced answer.
'B' EDG operating powering its bus.
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 Question Level: Comprehension Task Associations 2067100401 Maintain Reactor Water Level with HPCI 295008 AK2.05 Knowledge of the interrelations between HIGH 3.8 REACTOR WATER LEVEL and the following: AK2.05 HPCI: PI Question:
Given the following plant conditions:
- The mode switch is in SHUTDOWN following a turbine trip on high reactor water level
- Reactor water level +130 inches and slowly lowering
- Drywell pressure is 1.9 psig and rising
- The white light 'HPCI System Ready' is OFF For the above conditions, state the response of the HPCI system without operator action.
- a. WILL initiate on ONLY the high Drywell Incorrect - Turbine trip at 177" will auto pressure signal.
reset at 82.5" OR it can be manually reset using the CRP 9-3 trip reset pushbutton.
WILL initiate on ONLY the low-low Correct - Turbine trip at 177" will auto Reactor water level signal.
reset at 82.5".
- c. Automatically initiate on ONLY the high Incorrect -It can be manually reset using Drywell pressure signal.
the CRP 9-3 trip reset pushbutton but with no action the Hi DW
signal is blocked.
- 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: AK1.02 Recirculation pump net itive suction head: Plant-Question:
With the plant at 80% power a total loss of feedflow occurs.
As feed flow starts to drop the Reactor Recirculation pumps runback to minimum speed.
IA W OP-211O, Reactor Recirculation System, the reason for this runback is to accomplish which ONE of the following?
- 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 Vermont 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:il: 1 Question Level: Fundamental Knowledge Task Associations 295014 AKl.02 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY 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.
lAW OT 3110, Inadvertent Reactivity Addition, which ONE of the following is the required immediate operator action?
- b. Reduce the master controller setpoint to below 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:
Categ<rr,y:
Point Value: 1 Time to Complete (Minute,ti: 2 Question Level: Analysis Task Associations Question:
The plant was operating at 100% power.
An ATWS has occurred coincident with a loss of MCC-SA Annunciator APRM BUS AlB ALT Power Source (5-M-5) is NOT lit RPV pressure is 920# controlled using TBV's 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?
IAnswerlDistractor IJustification
- a. APRM 'E' and turbine first stage pressure. Incorrect - APRM not powered, 1 stage pressure reads zero with the turbine tripped.
Incorrect - APRM E has no power.
- c. APRM 'B' and turbine first stage pressure. Incorrect -1 stage pressure reads zero with the turbine tripped.
Correct.
Static Simulator Exams: none Last Revised: 2-4-13, KM
Question #25 Vennont Yankee LOR Exam Bank Ouestion 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 (Minute:il: 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: AKl.Ol Loss ofnonnal 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 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. (I)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 MSIV s opened first lAW OP 2113, pg 8.
Correct.
Incorrect - Setpoint must be raised to close the TBVs.
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 (Minutes): 1 Question Level: Comprehension Task Associations 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-J-3 STMTUNNEL TEMPCHB 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 predicts the status of PCIS Group 1 and Group 6 isolation signals IA WOP 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.
ONLY pels Group 1 isolation signal will actuate immediately.
- d. ONLY PCIS Group 6 isolation signal will actuate immediately.
Static Simulator Exams: None Last Revised: 2-4-13, KM Incorrect - pels Group 6 has a 35 minute time delay.
Incorrect - pels Group 1 has no 35 minute time delay.
Correct.
Incorrect - PCIS Group 6 has a 35 minute time delay.
Question #27 Vermont Yankee LOI Exam Bank Question Number 5731 Revision 5 Instructor Guide: LOT-01-223 PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS)
Objectives: K1O, Kl1
References:
OPOP-SGT-2117, page 3 and ARS 5-H-l 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 and/or 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 mRIhr.
Which ONE of the following describes the required operator response IA W 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 1 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: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge/Memory Task Associations 2187030101 Replace Automatic Blowdown System in Standby Following ADS Initiation Question:
lAW ARS 3-A-7, ADS PERMISSIVE RHRlCS RUNNING, which ONE of the following does the Automatic Depressurization System (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 Ouestion Number 7129 Revision 1 Instructor Guide: LOT-00-205 RESIDUAL HEAT REMOVAL SYSTEM Objectives: K1.07.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 Knowledge of electrical power supplies to the following:
41.7): Motor valves 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?
Valve, closes resulting in a trip of the running RHR pump.
Valve, closes resulting in a trip of the running RHR pump.
RHR-17, RHR SID Cooling Suction Correct - Running RHR Pump logic will Valve, position indication is lost resulting see RHR-17 as closed when DC-2 is lost in a trip of the running RHR pump.
(loss of sensing relay).
- d. RHR-18, RHR SID Cooling Suction Incorrect - Running RHR Pump logic will Valve, position indication is lost resulting see RHR-17 as closed when DC-2 is lost in a. of the RHR
Static Simulator Exams: None Last Revised: 1-31-13 by BLS
Question #30 Vermont 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 automatically 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-00-607 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 206000 K6.05 Knowledge of the effect that a loss or malfunction of the 3.5 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 Actions lAW EOP-3, Primary Containment Control, should be to perform which ONE of the following?
Secure HPCI...
- a. 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.
- c. if pump cavitation is observed due to lowering suction pressure.
- d. only when primary containment pressure rises due to the HPCI exhaust.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS Incorrect HPCI pump cavitation is not the concern with low torus level.
Incorrect With HPCI in operation and torus level low, the exhaust will pressurize and thereby threaten primary containment.
Question #32 Vermont Yankee LOI Exam Bank Question Number 6804 Revision 1 Instructor Guide: LOT 209 CORE SPRAY Objectives: K2
References:
OP 2123, Core Spray, page 3 LOT 209, TP5 CWO 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 Based on the above, and IA WOP 2123 Core Spray System, predict the Core Spray system response?
- a. Both Core Spray pumps will start and ALL Incorrect - Loop'A' pumps and valves injection valves will 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 would have nn,.,,,,r
start and its injection valves will open.
have initiation power.
- d. No Core Spray pumps will start and NO Incorrect - Loop 'B' pumps and valves still injection valves will open.
have power.
Static Simulator Exams: None Last Revised: 1-29-31 by BLS
Question #33 Vermont Yankee LOI Exam Bank Question Number 481 Revision 1 Instructor Guide: LOT-00-211 STANDBY LIQUID CONTROL SYSTEM Objectives: K4.08, K8
References:
P&ID 0-191171 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: (CFR 41.7): System initiation upon operation of SBLC control switch Question:
An "Anticipated Transient Without Scram" (ATWS) has occurred.
The CRS orders the injection of Standby Liquid Control (SLC).
- The Operator at the Controls (OATC) 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 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System: 211000 Instructor Guide:
Objectives:
References:
OP 2114, OP 4114 Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 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 tarue:
lAW OP 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 performed by __'_" ___
- a. (1) 4 (2) opening SLC-22, SLC tank sparger instrument air supply, 1,4 turn open.
- b. (1) 4 (2) operating SLC tank heater control in MANUAL.
(1) 8 (2) opening SLC-22, SLC tank sparger instrument air supply, 1,4 turn 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 Vennont 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:
Categctl:Y:
Point Value: 1 Time to Complete (Minute:il: 2 Question Level: Fundamental Knowledge Task Associations Perfonn Shutdown from Outside the Control Room 212000 2.4.34 Knowledge ofRO tasks perfonned outside the main control room during an emergency and the resultant effects.
4.2 Question
During a fire in the Control Room, the control room operators have exited the Control Room.
The SM directs Operator #3 to SCRAM the reactor from outside the Control Room.
lAW OPOP-ALTSD-3126, Shutdown Using Alternate Shutdown Methods, what actions are required to perfonn this task?
- c. Vent the overpiston volume for any HCU with control rod position NOT at 00.
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 H.
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 INTERMEDLA.TE 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.
lAW OP-2131, IRM Channels, which ONE of the following describes the plant response to this action?
- 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),
- d. An IRM rod block AND half-scram on Incorrect - Ranging down two ranges will RPS Channel "B" are received.
result in a 120/125 scale half scram on RPS channel "AU (IRM Hi-Hi) and a rod block (IRM Hi).
Static Simulator Exams: None Last Revised: 1-29-13 by BLS
Question #37 Vennont 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
~'I0J1j III I
2157170401 Respond to SRM System Alarms Question:
Given the following conditions:
- Reactor is subcritical
- Operations is perfonning 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 benchboard
- The Operator at the Controls (OATC) depresses and holds the DRIVE OUT pushbutton lAW 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 WITHDRAW 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 LOI 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 KnowledgelMemory Task Associations 2150230101 Operate the Neutron Monitoring System 215004 A3.04 Ability to monitor automatic operations of the SOURCE RANGE MONITOR (SRM) SYSTEM including: A3.04 control rod block status
3.6 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 lAW OP 2130, SRM System?
SRMs are not fully inserted, all SRMs but
'A' read 300-400 cps, and all IRMs are on range 4 or 5.
SRMs are fully inserted, all SRMs but 'A' read 300-400 cps, and all IRMs are on range 1.
SRMs are not fully withdrawn, SRM 'A' is bn>assed, all other SRMs read between 5 x 10 and 2 x 105 cps, and all IRMs are on
- 8.
- d. SRMs are not fully inserted, SRM 'A' is bypassed, all other SRMs read 300-400 cps, and all IRMs are on range 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 Vennont Yankee LOI Exam Bank Question Number 3892 Revision 1 Instructor Guide: LOT-05-215 AVERAGE POWER RANGE MONITOR (APRM)
Objectives: CRO 2d, 5
References:
LOT-05-215, Rev 13 ARS 5-M-5 Tech. Spec. LSSS 2.1.A.l 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 Alanns 215005 A2.05 Ability to (a) predict the impacts of the following on the 3.5 AVERAGE POWER RANGE MONITORJLOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal 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 "B" Flow Converter/Comparator output remains at 25%
- Actual recirculation loop flows respond as expected What will be the FIRST effect on plant operation as recirculation flow continues to be raised and what procedure should be used to address this condition?
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.
Respond lAW OT 3100, Reactor Scram.
ARMs B, D, F) will remain unchanged as 70.5% based on the failure of the "B" Flow
- b. A half SCRAM will occur due to flow biased neutron flux high.
Respond in accordance with OP 2134, Reactor Protection System.
- c. A control rod block will occur due to a flow converter/comparator unit "inop" signal.
Refer to ARS 5-M-5, APRM FLOW BIAS OFF-NORMAL.
A control rod block will occur due to the flow converter/comparator unbalance condition.
Refer to ARS 5-D-3, ROD WITHDRAW BLOCK.
Static Simulator Exams: None Last Revised: 1-29-13 by BLS.
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 "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 which would cause a half scram.
Incorrect - The inop flow converter/comparator rod block would occur if one of the comparators had lost power.
Correct
Question #40 Vermont Yankee LOR Exam Bank Question 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.
'F' APRM fails upscale.
lAW OP-2132, APRM Channels, which ONE of the following is the response of the APRM System indications?
'F' APRM recorder responds.
'F' APRM benchboard High and High High lights remain OFF.
Correct - With the APRM bypassed the recorder continues to respond to system inputs but the lights do not.
- b. 'F' APRM recorder does not respond.
'F' APRM benchboard High and High High lights remain OFF.
Incorrect - The recorder continues to respond.
- c. 'F' APRM recorder responds.
'F' APRM benchboard High and High-High lights turn ON.
- d. 'F' APRM recorder does not respond.
'F' APRM benchboard High and High-High lights turn ON.
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.
Incorrect The recorder continues to respond. The lights will not work with the APRM bypassed.
Question # 41 Vennont 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 (Minute~: 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 should you take?
Place the RCIC flow controller in MANUAL.
Restore flow to >2000 rpm with the manual knob.
- b. Leave the RCIC flow controller in AUTOMATIC.
Restore flow Restore flow to >2000 rpm with setpoint tape.
- c. Secure RCIC regardless of adequate core cooling.
Static Simulator Exams: None Last Revised: 2-4-13, BLS 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.
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 Vennont Yankee LOR Exam Bank Question 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 with the following parameters:
DW pressure 10 psig rising slowly RPV water level 80 inches lowering slowly HPCI tripped on low oil pressure RCIC is injecting Following ADS valve actuation, all RPV water level instruments (NR) fail high due to a rapid depressurization.
IAWOP 2122, ADS System, what is the status of the ADS valves and why?
All ADS valves remain OPEN because the Correct low-low water level signal from ECCS NR (LT-2-3-72 A-D) remains sealed in.
- b. All ADS valves remain OPEN because the Incorrect - Wrong level inst.
low-low water level signal from Transient NR (LT-2-3-68 A-D) remains sealed in.
- c. All ADS valves CLOSE because the low-Incorrect K6A1K7A seal in level signal.
low water level signal from ECCS NR (LT-2-3-72 A-D) resets.
- d. All ADS valves CLOSE because the low-Incorrect - K6A1K7A seal in level signal.
low water level signal from Transient NR (LT-2-3-68 A-D) resets.
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:
CategOI:Y:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations Respond to Containment Isolations 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 nU11lnn' K3.07 Reactor n""nr<>
Question:
A Group 1 isolation has occurred.
RCIC was started manually to provide RPV pn~ssure control.
Subsequently, alarm 4-U-2, RCIC STEAM LINE 6. P HI, comes in and clears after 10 seconds.
lAW the above alarm, predict the RCIC system response, and the operator actions (if any), and the RPV pressure response to the above conditions.
RCIC should have isolated.
Isolate RCIC.
RPV pressure will rise to the lowest SRV lift pressure of 1080#.
- b. RCIC should have isolated.
RPV pressure will rise to the lowest SRV lift pressure of 1090#.
- c. No RCIC isolation exists until both high flow channels are in alarm.
As RPV pressure lowers with RCIC in manual speed and flow will lower.
As RPV pressure lowers in AUTO, flow will stay the same.
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 - The operator should attempt to isolate RCIC. SRV lift pressure is 1080#.
Incorrect - The operator should attempt to isolate RCIC. SRV lift pressure is 1080#.
Question #44 Vermont Yankee LOI Exam Bank Ouestion Number 7421 Revision 3 Instructor Guide: LOT 239 MAIN STEAM SYSTEM Objectives: K6.05b
References:
LOT-OO-239, Main steam; EOP Study Guide Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental KnowledgelMemory Task Associations 2187010401 Inhibit Automatic Initiation of ADS Question:
Which design feature assists in preventing excessive SRV hydraulic thrust loading during a Group 1 isolation transient with repeated SRV cycling?
Four SRVs are utilized to spread the loading.
Incorrect - Distractor A is incorrect as the four valves are a redundant feature.
- b. The T-Quencher assembly.
Incorrect - This is incorrect as the T Quencher prevents excessive temperature loading on one area of the Torus.
The SRV tailpipe vacuum breakers.
Correct Response-On multiple lifts of the SRV's, water could be drawn up into the tailpipe and hydraulically damage the tailpipes.
- d. Safety valves as a back-up to the SRVs.
Incorrect The safety valves provide protection to the RPV with additional relief capacity.
Static Simulator Exams: None Last Revised: 2-4-13 by BLS
Question # 45 Vermont Yankee LOI Exam Bank Question Number New Revision 0 Instructor Guide: LOT 601 OFF-NORMAL PROCEDURES Objectives: RO E01,EO 2
References:
ON 3174, OP 2172 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 1240V Instrument AC Bus Using on 3174 Question:
A momentary loss of Instrument AC occurs.
Which ONE of the following correctly identifies the Feed System response and operator action to be taken lAW ON 3174, Loss of 120V1240V Instrument AC Bus?
(Disregard the effects of the level transient.)
Incorrect Should instrument AC be lost automatically transfer to manual (lockup).
or the master controller output is lost, the Verify or transfer the 'A' FRV to manual, B manual/auto transfer station will transfer verify the 'P' and 'V' output is the same to manual at the called for value 6 seconds and depress the lockup pushbutton.
prior to the loss of power.
- b. The flAil AND Master Feedwater level Incorrect - This is indicative of a loss of controllers will automatically transfer to Vital AC.
manual with 'A' FRV locked up.
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 automatic.
- c. The "B" AND Master Feedwater level controllers will automatically transfer to manual with 'B' FRV locked up.
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.
The "B" Feedwater level controller will automatically transfer to manual (lockup).
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 manuaVauto 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 manuaVauto transfer station will transfer to manual at the called for value 6 seconds prior to the loss of power.
Question # 46 Vermont 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:
Category:
Point Value: 1 Time to Complete (Minutes): 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.
IA W VY UFSAR predict the status of HPCI based on the above conditions.
AnswerlDistractor HPCI will continue to run.
Airborne radiation level will rise in the HPCI area.
- 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 HPClarea.
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 1148 Revision 1 System: 261 SGTS Standby Gas Treatment System Instructor Guide: LOT-00-261 STANDBY GAS TREATMENT SYSTEM Objectives: CRO-2f
References:
Tech Spec 4.7.B, Amendment 189 (Bases 4.7.B, pg 170), UFSAR 7.17.2 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 2157170401 Respond to SRM System Alarms Question:
Radioactive Iodine in the discharge of a SBOT train indicates a malfunction of which ONE of the following?
- b. HEPA filter Incorrect - The HEP A filter is for particulate. Iodine is removed by the charcoal filter.
- c. lKw electric heater Incorrect - Iodine is removed by the charcoal filter.
- d. Demister Incorrect - Iodine is removed by the charcoal filter.
Static Simulator Exams: None Last Revised: 2/5/2013, BLS
Question #48 Vermont Yankee LOI Exam Bank Question Number 6215 Revision 2 Instructor Guide: LOT-00-602 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 his/her 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 Us.ing ON 3170 Question:
The following conditions exist:
- Early in November, the plant is operating at 85% power
- The Start-up transformers are removed from service for ground repair and a planned 7 day Leo has been entered.
The switching and tagging order consists of the following:
- During the repair, breaker 12 trips on differential over-current.
Based on the electric plant lineup, what immediate action is required?
- a. Verify an automatic SCRAM occurs, if not insert a manual SCRAM and enter OT 3100.
Manually SCRAM the reactor and enter OT3100.
- c. Verify operation of RFP 'C' and Condensate Pumps 'B' and 'C'. Insert a manual SCRAM ONLY if level drops below 140 inches.
- d. Verify the Recirc runback occurs on Recire:
MG '8' and Feedwater Master level controller setpoint 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 amanual 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 Vermont Yankee LOI Exam Bank Question Number 6717 Revision 2 Instructor Guide: LOT-03-262 RUPS Objectives: RO Objective #7
References:
CWO 335A, 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 Question:
The plant simultaneously experienced a Loss of Coolant Accident (LOCA) and Loss of Normal Power (LNP).
The following plant conditions exist:
Reactor water level is 60 inches and slowly lowering Reactor pressure is 750 psig and slowly lowering Drywell pressure is 4.2 psig and slowly rising The "A" EDG failed to start All other equipment is operating as expected for the current plant conditions.
lAW OP 2143, 480 Volt and Lower AC Systems, which ONE of the following describes the current state ofthe UPS-IB System?
UPS-IB Feeder Breaker is...
OPEN and is operating on DC Drive 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 therefore after -13
- b. OPEN and is operating on AC Drive
- c. CLOSED and is operating on DC Drive
- d. CLOSED and is operating on AC Drive Static Simulator Exams: None Last Revised: 1-30-13 by BLS 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-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-I 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-I 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.
Question #50 Vermont Yankee LOI Exam Bank Ouestion Number 6860 Revision 1 Instructor Guide: LOT 601 OFF-NORMAL PROCEDURES Objectives: RO E01, E03
References:
OPON-3I59-01 2007 ILO Audit Exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: I Time to Complete (Minutes): I Question Level: Analysis Task Associations 2007350404 Respond to a Loss of DC-l 263000 K6.0I Knowledge of the effect that a loss or malfunction of the 3.2 following will have on the D.C. ELECTRICAL DISTRIBUTION: K6.0I A.C. electrical distribution Question:
Consider the following situation:
The plant is operating at rated conditions with ALL equipment operable and in a normal electrical plant Jineup when a LNP occurs.
The following annunciator and control panel indications are noted by the crew:
DC-IIDC-2 BKR TRIP (8-N-l)
BUS I CTRL PWR LOSS (8-Q-2)
Loss of power to TURBINE TRIP MTS-I "white" light Loss of power to ECCS Analog Trip Cabinet 25-5B In addition to entering OT 3100, which ONE of the following procedures is required to be entered, and how should RPV level be controlled?
Enter OPON-3159-01, Loss of DC-I, and Incorrect - A loss of DC-I has occurred, establish level control with HPCI only RCIC is available for level control.
EnterOPON-3I59-01, Loss of DC-I, and Correct Response: Bus I control power establish level control with RCIC.
loss alarm, with MTS-l out and loss
- c. Enter ON 3160, Loss of DC-2 and DC-3, and establish level control with HPCI.
- d. Enter ON 3160, Loss of DC-2 and DC-3, and establish level control with RCIC.
Static Simulator Exams: None Last Revised: 1-31-13 by BLS of power to the 5B ECCS trip cabinet are symptomatic of a loss of DC-I. Further, 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 Ouestion 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 predict 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 Ouestion:
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:
CategQry:
Point Value: 1 Time to Complete (Minute:il: 1 Question Level: Fundamental Knowledge Task Associations lIlWF'lE?E1'~
2000130501 Respond to a Loss of Instrument Air Pressure Knowledge of the connections and / or cause effect 2.8 relationships between INSTRUMENT AIR SYSTEM and the Kl.03 Containment air Question:
Which ONE of the following statements is true regarding MSIV AiriNitrogen 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 _(3)_.
- a. (1) instrument air Incorrect - When inerted, the inboard (2) containment air MSIV s use CA and outboard MSIV s use (3) inerted IA.
- b. (1) containment air Incorrect - When de-inerted, the MS IVs (2) instrument air uselA.
(3) de-inerted
(3) inerted
(2) instrument air Iand inboard MSIV s use IA.
(3) de-inerted Static Simulator Exams:
Last Revised:
Question #53 Vermont Yankee LOI Exam Bank: Question Number New Revision 0 Instructor Guide: LOT-00-602 OPERATIONAL TRANSIENT PROCEDURES Objectives: RO E05
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) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal
. 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 ofTBCCW, as temperatures rise the condensate and reactor feed pumps in the alarm condition are secured due to elevated _(1)_.
Pump swaps _(2)_ permitted.
(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.
- b. (1) thrust bearing temperatures due to a Incorrect - Unrecoverable loss of TBCCW 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 permitted to maintain RPV water level.
- c. (1) area temperatures caused by a loss of TRU cooling (2) are
- d. (1) area temperatures caused by a loss of TRU cooling (2) are NOT Static Simulator Exams: None Last Revised: 2-4-13 by BLS 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
- 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 Vennont 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:
Catego..ry:
Point Value: 1 Time to Complete (Minute:il: 2 Question Level: Analysis Task Associations 201003 A2.07 Ability to (a) predict the impacts of the following on the 3.1 CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal 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%
Predict the change in CRD drive water pressure if CRD-FCV-20, CRD Drive Water Pressure Control Valve, fails open and detennine the required action.
CRD drive water pressure _(1)_ and lAW OPON-3145-01, Loss ofCRD Regulating Function, rod movement is suspended until CRD drive water pressure is restored to between _(2)_ above reactor pressure.
AnswerlDistractor
- a. (1) rises (2) 250-275 psig
- b. (1) rises (2) 300-325 psig (1) lowers (2) 250-275 psig
- d. (1) lowers (2) 300-325 psig Static Simulator Exams: None Last Revised: 2-4-13, KM Incorrect - Drive water pressure lowers Incorrect - Wrong control band Correct - OPON-3145-01 step 6.7.1 Incorrect - Wrong control band
Question # 55 Vermont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 202001 Instructor Guide:
Objectives:
References:
OP 2110. Reactor Recirculation System Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 1 Question Level: Fundamental Knowledge Respond to Recirculation Pump Trip 202001 A2.22 Ability to (a) predict the impacts of the following on the 3.1 RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or
. A2.22 Loss of water Question:
During summer operations Service Water temperature is at 83° F.
What effect could this have on the recirculation system and what procedure would provide guidance?
Recirc drive breaker will trip if lube oil temperature rises to 212 0 F.
Enter OT 3118, Recire Pump trip.
Recirc drive breaker will trip if lube oil temperature rises to 182 0 F.
Enter OT 3118, Recirc Pump trip.
- c. Recire seals could fail if seal cavity temperature rises to 152 0 F.
Enter OPON-3142-01, Reeirc Pump Seal Failure.
- d. Recire seals could fail if seal cavity temperature rises to 132 0 F.
Enter OPON-3142-01, Recire Pump Seal Failure.
Static Simulator Exams: None Last Revised: 2-4-13, BLS
> 210 F will trip the recirc drive breaker.
OT 3118 is the procedure to enter for this event.
> 210 F will trip the recirc drive breaker.
OT 3118 is the procedure to enter for this event.
The recire seals are cooled by RBCCW.
Seals will fail at >160 F making this a good distracter.
The recirc seals are cooled by RBCCW.
Seals will fail at >160 F making this a good distracter.
Question #56 Vennont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 202002 Instructor Guide:
Objectives:
References:
OP 2110, reactor recirculation system Reference Open/Closed: Closed SRO Only: No Style:
Categ<rry:
Point Value: 1 Time to Complete (Minute~: 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- 'np'£'1t-1 Question:
The plant is operating at 100% CTP.
A trip of 'A' Reactor feed pump occurs.
lAW OP 2110, Recirculation System, predict the status of the recirculation system.
'A' and 'B' individual recirculation controllers _(1)_.
Recirculation pump speed will runback to _(2)_.
- 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 action in OT 3175, Recirc runback. Runback to minimum is on inadequate NPSH from
<20% feed flow to the recirc system from feedwater.
Incorrect - The shift of the controller to manual is an important follow-up action in OT 3175, Recirc runback. A RFP trip will result in a recirc runback to the 40% scoop tube Incorrect - The shift of the controller to manual is an important follow-up action 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 recirc from feedwater.
Correct The shift of the controller to manual is an important follow-up action in OT 3175, Recirc runback. A RFP trip will result in a recirc runback to the 40% scoop tube
Question #57 Vennont Yankee LOI Exam Bank Question Number 1378 Major Revision 3 Instructor Guide: LOT-04-215 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 2000170501 Respond to Containment Isolations 215001 K1.05 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 are expected to occur?
No automatic response occurs because a Hi Incorrect -Group II causes isolation at 127 DW signal is NOT present.
inches.
- b. ONLY the Shear Valve fires when reactor water level lowers to 82.5 inches.
The TIP drive retracts the TIP detector AND the ball valve closes when reactor water level lowers to 127 inches.
- d. The TIP drive retracts the TIP detector AND the ball valve closes when reactor water level lowers to 127 inches AND the Shear Valve fires when reactor water level lowers to 82.5 inches.
Static Simulator Exams: None Last Revised: 2-5-13 by BLS 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-00-607 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 Ability 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 temperature.
- b. TI-16-19-33C torus water temperature CRP 9-3.
- c. TI-16-19-33A torus water temperature CRP 9-3.
- d. The higher ofTI-16-19-33 A or C.
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 - These detectors could become uncovered if torus level drops to <8.5 feet and will only read torus air space temperature.
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 KnowledgelMemory 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?
ition.
- b. 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.
- c. Isolation signals associated with PCIS Group 1,2, and 3 isolations are clear and the valves are in the OPEN
present and the isolations can NOT be by any isolation signal, only by control reset.
switch osition.
Static Simulator Exams: None Last Revised: 5/15/2012 3:11:33 PM by Brown, Scott
Question #60 Vennont Yankee LOI Exam Bank Question Number 7589 Revision 0 Instructor Guide: LOT 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 R:aiI~~liI 2000210501 Respond to High Drywell Temperature 226001 K5.06 Knowledge of the operational implications of the 2.6 following concepts as they apply to RHRlLPCI:
CONTAINMENT SPRAY SYSTEM MODE: K5.06 Vacuum breaker n...."'....,h 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, IA W 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 will reopen the SRVs, causing RPV pressure to drop below the saturation pressure for the current DW temperature.
Static Simulator Exams: None Last Revised: 2/5/2013 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 dryweU 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 SRV s 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 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 KnowledgelMemory Task Associations 1IB!'_~~~1J1'11~~~1i1 2337180104 Place the SFPC System in Operation 233000 Al.03 Ability to predict and/or monitor changes in parameters 3.1 associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including: Al.03 Pool Question:
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.
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 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 Category: Plant Proficiency Point Value: 1 Time to Complete (Minutes): 2 Question Level: Analysis Task Associations 2000180501 Respond to High Reactor Pressure 241000 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, plant response to this event would be which ONE of the following?
- a. 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 800 psig in RUN Group I.
signal.
Control valves close, raising RPV pressure Correct Response - When the pressure until MPR takes control.
averaging manifold pressure transmitter signal fails to 50%, the MHC system, the will sense reactor
pressure low and close the control valves.
- d. 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.
Static Simulator Exams: None Last Revised: 02/0112013 by BLS
Question #63 Vermont 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 determine the correct RFP configuration.
Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Fundamental Knowledge 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 IA W OPOT-3169-01, Loss of Bus-I, which ONE of the following is the correct combination of reactor feed pumps left running?
(Note: Disregard any level transient or operator actions)
'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 still secured from Bus 1 and would be tripped. 'C' RFP
'c' RFP is running is powered from bus 2 and should be
'A' RFP is trl1'\\np/"l
'B' RFP is still secured
'C' RFP is running
- d. 'A' RFP is running
'B' RFP is running
'C' RFP is tripped Static Simulator Exams: None Last Revised: 2-13-13, KM from Bus 1 and 'c' RFP is powered from Bus 2.
Incorrect -'A' RFP would be tripped. 'B' RFP would still be secured with no power.
'c' RFP is powered from bus 2 and should be
Question # 64 Vennont Yankee LOR Exam Bank Question Number NEW Revision 0 System: 271000 Instructor Guide:
Objectives:
References:
OPOP-AOG-2150; Alarm Response Sheet 6-H-l Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 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 from a leaking vacuum breaker results in rising Main Condenser backpressure.
o As a result pressure in the Offgas System OG-100 Line rises to 6.0 psig.
o Annunciator 6-H-l, AOG PRESS HI, is received Based on these Offgas System conditions the operator should verify:
AnswerlDistractor BOTH OG-516A and OG-516B will automatically close.
- b. BOTH OG-516A and OG-516B will stay in their current position.
- c. ONLY OG-516A will automatically close and OG-516B will stay in its current position.
- d. ONLY OG-516B will automatically close and OG-516A will stay in its current position.
Static Simulator Exams: None Last Revised: 2-4-13, BLS Justification Correct-lAW Alarm Response Sheet for Annunciator 6-H-1 and OP 2150 (Discussion Section) high pressure in the OG-IOO Line at 5.4 psig as sensed by 2 of 2 pressure switches OG-PS-102-21E and G will provide an automatic close signal to both OG-516A/B valves.
OG-516A/B will get an auto close signal based on high pressure in the OG-l 00 Line. This is a plausible distractor if the operator does not interpret the OG 100 line isolation OG-516A & B will get an auto close signal based on high pressure in the OG-1oo Line. This is a plausible distractor because OT 3120 directs operator to reset and open OG-516 valve to control main condenser backpressure.
Both OG-516A1B receive an auto close signal based on high pressure in the OG 100 Line. This is a plausible distractor because the OG-516A valve will trip close on high pressure in the OG-1oo Line and OT 3120 directs operator to reset and open OG-516 valve to control main condenser
Question #65 Vennont Yankee LOI Exam Bank Question Number 6758 Revision 2 Instructor Guide: LOT 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:
Consider the following situation:
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.
lAW OPOP-AOG-2150, AOG System, with no operator action, which of the following will occur?
- a. FCV -11 (stack isolation) will close in 2 minutes, OG-3 (delay line drain) will close immediatel
- b. FCV -11 (stack isolation) will close in 30 minutes, OG-3 (delay line drain) will close 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 conditions When
the AOG dryer 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-11 (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: 6/28/2012 11 :26:27 PM by Schulze, William H.
Question #66 Vermont Yankee LOI Exam Bank Question Number 3128 Revision 0 Instructor Guide: LOT-01-4oo OPERATIONS DEPARTMENT ADMINISTRATIVE PROCEDURES-2 Objectives: CRO-l
References:
DP 0166, Operations Standards Used in LOI 2000 RO Audit Exam (8/00) and 1999 NRC RO Exam Reference Open/Closed: Closed SRO Only: No Style: Multiple Choice Point Value: 1 Time to Complete (Minutes): 2 Question Level: Comprehension Task Associations 2997270301 Follow Operating Instructions and Procedures Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Question:
Given the following conditions:
- The plant is operating at 100% power
- A pressure regulator malfunction has resulted in rising reactor pressure
- Reactor pressure has reached 1060 psig on multiple indicators/channels
- There has been NO response from the Reactor Protection System (RPS) lAW DP 0166, Operations Department Standards, the Control Room Operator should:
Inform the Control Room Supervisor Correct - lAW DP 0166, the RO has the (CRS) of the scram failure, while authority to scram the plant.
concurrentl y inserting a manual scram.
- b. Immediately insert a manual scram by Incorrect - Only use this method if the depressing the ARIIRPT pushbuttons.
manual scram pushbuttons don't work.
- c. Inform the Control Room Supervisor Incorrect It is not necessary to wait for of the condition, and insert a CRS direction.
manual scram at his direction.
- d. Immediately take the EPR to lower, to Incorrect - This is not the prescribed reduce RPV pressure.
method.
Static Simulator Exams: None Last Revised: 211112013 by BLS
Question #67 Vermont Yankee LOR Exam Bank Question Number 42 Major Revision 4 System: 344 ABNORM AbnormallEmergency Operations Instructor Guide: LOT 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 Cat~: 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 as 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?
Incorrect - This is the wrong interpretation of the MSCP table.
Incorrect This is the wrong interpretation of the MSCP table.
Static Simulator Exams: None Last Revised: 2-4-13 by BLS
Question # 68 Vennont 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 (Minutes): 2 Question Level: Analysis Task Associations erfonn 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 Vermont Yankee LOR Exam Bank Question Number New Revision 0 System:
Instructor Guide:
Objectives:
References:
Tech Specs Reference Open/Closed: Closed SRO Only: No Style:
Category:
Point Value: 1 Time to Complete (Minutes): 2 Question Level: Comprehension Task Associations 3417040302/0 Ensure Technical SpecificationslTRMlODCM are Followed by Shift 3
Operations Crews Question:
IA W VY Technical Specifications, which ONE is a correct description of the minimum reactor coolant pressure which would be a Tech Spec safety limit violation?
Greater than __l_PSIG RPV steam space pressure which is equivalent to
__-___ PSIG at the lowest elevation of the reactor coolant system.
- a.
- b. 1. 1295 2.1335
- 1. 1335 2.1375
- d. 1. 1375
- 2. 1415 Static Simulator Exams: None Last Revised: 2-14-13, BLS Incorrect: 1250 is just over the setpoint of the VY safety valves and is the ASME code Incorrect: 1335 at the lower coolant system elevation is a distractor.
Correct: ASME code is 1250 # X 110%
which is 1375 at the lower coolant system elevation. Accounting for the head of water in the system the steam space sure would be 1335.
Incorrect: Plausible if the operator recalls 1375 # and recalls the 40# delta between
,..,,..,.,..11,,,\\,,,,,,,.. elevations.
Question #70 Vermont Yankee LOI Exam Bank Ouestion Number 1389 Revision 1 Instructor Guide: LOT 202 REACTOR RECIRCULATION SYSTEM Objectives: K4.12
References:
T.S. 3.6.AA, OP 2110 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 2020040101 Startup a Recirc Pump with One Pump Already Running Ouestion:
Which ONE of the following actions is PROHIBITED by Vermont Yankee Technical Specifications and the administrative limits of OP 2110, Reactor Recirculation System?
- a. Operation of two reactor recirculation Incorrect - The limit is on recirc pump loops with greater than a 50° F temperature starts with this delta temp.
difference between the
- b. Operation of two reactor recirculation loops with greater than a 145° F temperature difference between the bottom head drain and the reactor saturation Startup of an idle reactor recirculation loop with greater than a 50° F temperature difference between the idle and operating loop 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 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
- d. Startup of an idle reactor recirculation loop with greater than a 145 0 F temperature difference between the bottom head drain and the idle Static Simulator Exams: None Last Revised: 2-4-13 by BLS requires the bottom drain temperature to be within 145F of the reactor saturation start.
requires the bottom drain temperature to be within 145 F of the reactor saturation start.
Question #71 Vermont Yankee LO! Exam Bank Ouest ion Number 7322 Revision 0 Instructor Guide: LOT-01-400 OPERATIONS DEPARTMENT ADMINISTRATIVE PROCEDURES-2 Objectives: RO 9
References:
AP 0155, pg 4 definitions 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 independent verification by a second operator is normally required to verify alignments of safety related components, but does NOT have to be performed if an excessive radiation dose would be received.
IA W AP 0155, Current System Valve and Breaker Lineup and Identification, which ONE of the following is the threshold limit for when the independent verification may be waived when the dose received would exceed:
Static Simulator Exams: None Last Revised: 02/0112013 by BLS
Question #72 Vermont Yankee LOI Exam Bank Question Number 7556 Revision 3 Instructor Guide: LOT-00-601 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 Knowledge/Memory 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:
Consider the following:
In accordance with OPON-3153-01, Excessive Radiation Levels, which one of the following indications would alert an operator of a possible leak into the Reactor Building Closed Cooling Water (RBCCW) system?
A rise in suction pressure to the RBCCW Incorrect - There is no correlation between Pumps and a concurrently lowering of the a lowering fuel pool level and rising Fuel Pool water level.
RBCCW suction......""...."'..""
Hi radiation alarm on the RBCCW Process Correct - Per ON-3153, If the RBCCW Radiation Monitor and rising level in the radiation monitor indicates a high radiation RBCCW Surge Tank.
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.
of RBCCW system piping or components 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 RBCCW piping is a valid indication of a 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 Category: Plant Proficiency Point Value: 1 Time to Complete (Minutes): 1 Question Level: Comprehension 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 The required actions are to enter EOP 1 and ___.
steam and can not*. ect.
causes a loss of 4 KV Bus 4, and 3 of 6 low pressure ECCS pumps are without power.
RHR loop powered from each EDG, 2 RHR pumps will be running and injecting.
There are no entry conditions for EOP 4.
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 1" 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 III
~I I.
2007220501 Respond to Reactor Building High area Temperature/Water Level Generic Knowledge of how abnomlal operating procedures are 3.8 4.5 used in with EOPs.
Question:
A fire protection header rupture has resulted in 5 inches of water in the RCIC Room.
The leak has been isolated and all available sump pumps are operating to reduce levels in the space.
For these conditions:
- a. Entry into ON-3158, Reactor Building Incorrect - Good distractor as student will High Area Temperature/Water Level, think actions to isolate are complete and ONLY, is required as the leak has been levels lowering, no reason to go further in isolated.
redundant
- b. Entry into EOP-4, Secondary Containment Incorrect -Good distractor as student will and Radioactivity Release Control, ONLY" think actions to isolate are complete and is required because EOP action takes levels lowering, no reason to go further in over ON a redundant
- c. Entry into ON-3158, Reactor Building Incorrect -Good distractor to a student that High Area Temperature/Water Level, is does not understand the basis, both are and into EOP-4 when hit the limits
Containment and Radioactivity Release Control, will be required only if water level cannot be reduced or the leak cannot be isolated.
Entry into ON-3158, Reactor Building High Area TemperaturelWater Level, and EOP-4, Secondary Containment and Radioactivity Release Control, is required because EOP's and ON's are implemented concurrently when entry conditions are met.
Static Simulator Exams: None Last Revised: 2-6-13 by BLS regardless of status. Start in ON and progress to EOP as condition worsens would be a logical sequence.
Correct Response-As required by entry conditions.
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, Primary Containment Control, the Pressure Control Leg gives direction to spray the Drywell, when Torus pressure exceeds 10 psig.
The basis for initiating Drywell Sprays when Torus pressure exceeds this value is to __
- a. prevent the Drywell Spray Initiation Limit (DWSIL) curve from being exceeded.
- b. ensure that the PCPL-A limit is not exceeded, due to excessive containment pressure.
prevent the cyclic condensation of steam (chugging), at the down comer 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 to
- d. ensure that enough time is available to prepare for RPV -ED, if sprays are not effective.
Static Simulator Exams: None Last Revised: 2-6-13 by BLS 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.