ML022490094
| ML022490094 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/15/2002 |
| From: | Gosekamp M Entergy Nuclear Vermont Yankee |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 05000271/02-301 05000271/02-301 | |
| Download: ML022490094 (101) | |
Text
MASTER EXAMINATION AND ANSWER KEY LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: 2002 SROU Exam Exam Activity Code:
Date Exam Prepared: 1 July 2002 Date Exam Taken: 12 August 2002 Prepared By Date Approved By Date Form TDD-5.2.2 Rev. 8, 09/00
2002 SROU Exam Question No. 1 Exam Bank Question No.: 1238 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO 2 Question Level: Comprehension Select the correct answer:
Reactor Power is 100% when an automatic scram signal is received. There is no rod movement but all other plant parameters remain normal. An EAL for a Site Area Emergency (SAE) requires "Automatic and Manual SCRAM signals present". Which of the following signals must also be tried and fail in order to declare a Site Area Emergency?
Scram pushbuttons and ARI!RPT Correct Response -
pushbuttons
- b. Scram pushbuttons and mode switch to Incorrect - The mode switch can not be shutdown thrown to insert a manual scram with power level greater than 40%.
- c. Automatic ARI/RPT signal and ARI/RPT Incorrect - The failure of the automatic pushbuttons ARI/RPT is not considered in the EAL classification.
- d. Automatic ARIJRPT signal and mode Incorrect - The mode switch can not be switch to shutdown thrown to insert a manual scram with power level greater than 40%.
References:
K/A 295006 Higher Level: Must integrate the following:
- A SAE requires failure of manual scram signal
- Manual scram signals are only those that can be done by the 9-5 operator of the board
- The mode switch causes a manual scram signal
- The mode switch also causes a Group I isolation when > 40% steam flow and thus can not be done Task Associations e
TaskthlM M
3440190302/03 Classify Emergency Events Requiring Emergency Coordinator (Emergency Plan)
Knowledge and Abilities Associations ystem K/ No.. Stament § g'
,Egg.
295006 2.4.29 Knowledge of the emergency plan (CFR 43.5, 45.11)
RB6 4RO 2.6 4.0 Static Simulator Exams: None Last Revised: 06/26/2002 8:00:27 AM by Fagan, Frank N.
2002 SROU Exam Question No. 2 Exam Bank Question No.: 3531 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
A failure to scram has occurred and the crew is taking actions per EOP-2, ATWS RPV Control.
The following conditions exist:
RPV pressure being maintained 800-1000 psig with SRVs RPV level being maintained -22" to +90" with feedpumps 20% SLC Tank level has been injected into the RPV Rods are being inserted manually, 40 rods still at position 48 Which of the following statements is true?
a.1 The reactor is shutdown and will remain Correct Response - Hot SD Boron Weight shutdown if pressure is maintained within definition current limits.
- b. The reactor is not shutdown since more Incorrect - Hot SD Boron Weight than one rod is not fully inserted.
definition
- c. The reactor is shutdown and cooldown Incorrect - Cannot cooldown until may now commence.
CSDBW injected
- d. The reactor will not be shutdown until the Incorrect - At rated pressure the Rx is S/D Cold Shutdown Boron Weight has been with HSDBW injected.
References:
EOP-2 Used in LOI 1999 RO Exam - Bacala (5/99)
Must integrate the following:
- Vessel at normal pressure is considered hot
- Required percent boron weight for hot shutdown
- Definition of shutdown Task Associations 2000200501 Respond to ATWS Event(s)
Knowledge and Abilities Associations Sym KANo. Stutmewnt magi 295006 AKi1.02 Shutdown margin 3.4 3.7 Static Simulator Exams: None Last Revised: 07/09/2002 2:41:28 PM by Fagan, Frank N.
2002 SROU Exam Question No. 3 Exam Bank Question No.: 3930 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO-2, 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Given the following conditions:
- The plant is operating at 100% power
- Reactor pressure is slowly increasing
- The EPR is controlling reactor pressure Select the FIRST action that should be taken by the CRO for these conditions.
- a. Manually scram the reactor.
Incorrect -
- b. Control pressure via the Bypass Valve Incorrect -
Opening Jack.
- c. Reduce the MPR setpoint.
Incorrect -
I.
Turn off power to the EPR.
Correct Response - OT 3116 I.A.
References:
OT 3116, Reactor High Pressure Task Associations Nu Th0-
"k Title 2000180501 Respond to High Reactor Pressure Knowledge and Abilities Associations 295007 AK1.04 Turbine load R.
2R.
2.7 2.8 Static Simulator Exams: None Last Revised: 07/09/2002 2:41:47 PM by Fagan, Frank N.
2002 SROU Exam Question No. 4 Exam Bank Question No.: 1821 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: 2 Question Level: Comprehension Select the most correct answer:
The plant is shutdown with the "A" RHR loop in shutdown cooling. The SW system is lost and Reactor Pressure rises to 160 psig. How will the RHR system respond?
Axswr/israto W,
stiication
will open, and the RHR pump will continue to run.
b RHR 17 & 18 will close and the Loop A Correct Response RHR pump will trip.
- c. RHR 17 & 18 will remain open and the Incorrect -
RHR pump will trip.
pump will continue to run.
References:
OP 2124 Must integrate the following:
- High pressure causes a Group 4 isolation
- Suction valves closing causes a pump trip Task Associations 2T0ask Nube Task Ttle 2057090101 Operate the RHR System in the Shutdown Cooling Mode Knowledge and Abilities Associations Systm K/A" No Statement 295007 AK3.05 Low pressure system isolation 3.0 3.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:42: 10 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 5 Exam Bank Question No.: 1390 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: 7 Question Level: Fundamental Knowledge/Memory Select the correct answer:
With the plant at 100% power a total loss of feedflow occurs. As vessel level starts to drop the Reactor Recirculation pumps runback to 20% speed. The reason for this runback is to prevent:
idle pump.
- b. flow induced vibration of LPRMs and TIP Incorrect - vibration occurs under high tubes.
flows during refueling outages.
- c. cavitation of the recirculation pumps.
Correct Response
- d. exceeding core thermal limits.
Incorrect - thermal limits are protected through the use of scrams.
References:
OP 2110 Task Associations 2020020101 Adjust the Recirculation System Flow Using Individual Manual Control Knowledge and Abilities Associations 295009 AK3.01 Recirculation pump run back: Plant-Specific RO& SW 3.2 3.3 Static Simulator Exams: None Last Revised: 06/26/2002 6:40:49 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 6 Exam Bank Question No.: 3897 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A LOCA has occurred and due to a high temperature, torus cooling is required. To accomplish this the "CTMT SPRAY VLV LPCI SIG BYPASS" (pistol grip) switch has to be placed in MANUAL to:
- a. allow the RHR Heat Exchanger Bypass Incorrect - this is auto-bypassed 1 minute Valve (RHR-65A1B) to be closed after the LOCA signal
- b. allow the Low Pressure Coolant Injection Incorrect - The UPS Bypass switch in (LPCI) injection valves to be closed.
block allows this function for the 27A/B.
- c. allow starting of the RHRSW Pumps.
Incorrect - The RHRSW pumps have a keylock switch that allows this.
allow the RHR System to be realigned to Correct Response torus cooling if reactor water level is above
-48 inches.
References:
OP 2124, Residual Heat Removal System Task Associations Tas NuberTaskTitl 2057080101 Startup the RHR System in the Torus Spray Mode 2057190101 Startup the RHR System in the Torus Cooling Mode 2057220101 Startup the RHR System in the Drywell Spray Mode Knowledge and Abilities Associations 295013 AK2.01 Suppression pool cooling RO,
.SR 3.6 3.7 Static Simulator Exams: None Last Revised: 07/09/2002 2:42:35 PM by Fagan, Frank N.
2002 SROU Exam Question No. 7 Exam Bank Question No.: 5566 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
A small break LOCA occurs with the following parameters:
- DW Pressure 8 psig
- RPV Water Level 135"
- RPV Pressure 860 psig RHR Pump "A" is placed in torus cooling due to a high torus temperature. A large break LOCA occurs resulting in an RPV water level of -200".
What is the status of RHR-65A, Hx Bypass Valve, and the torus cooling lineup?
- a. RHR-65A opens and torus cooling lineup Incorrect -
isolated
- b. RHR-65A opens and torus cooling lineup Incorrect -
unaffected
- c. RHR-65A remains closed and torus Correct Response cooling lineup isolated
- d. RHR-65A remains closed and torus Incorrect -
cooling lineup unaffected
References:
OP 2124 Must integrate the following:
- 65A previously overridden and closed (1 min)
- Torus cooling valves previously overridden open
- Torus valves driven closed on -48" Task Associations T0sk1Nu1 tasp itle S
2057190101 Startup the RHR System in the Torus Cooling Mode Knowledge and Abilities Associations S $ystem KIA'9 N,
S ta em ent 295013 AA1.01 Suppression pool cooling 3.9 3.9 Static Simulator Exams: None Last Revised: 07/01/2002 1:24:17 PM by Fagan, Frank N.
2002 SROU Exam Question No. 8 Exam Bank Question No.: 5598 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: CRO 3h Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant is operating at 100% power when the A Recirc pump ramps up to 100% speed. The thermal limit that is most significantly challenged by this event is:
- a. LHGR Incorrect -
- b. MCPR Correct Response
- c. APLHGR Incorrect -
- d. MFLPD Incorrect -
References:
OP 2429 Task Associations Tak'umer Tas Titlmer X 2 t fr r'"<d 2027050101 Local Scoop Tube Positioner Control 3452010102/03 Use ERFIS to Monitor Thermal Limits Knowledge and Abilities Associations Syst0m KAN.
Siolata on ot fuen ta limits 295014 AA2.04 Violation of fuel thermal limits R N' SRO 4.1 4.4 Static Simulator Exams: None Last Revised: 07/01/2002 8:47:20 AM by Fagan, Frank N.
2002 SROU Exam Question No. 9 Exam Bank Question No.: 1272 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-212 Objective: SRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which one of the following reactor scrams occurs in anticipation of a positive reactivity addition?
=
ser/isractor 0ii:
0tSgtjil040 Jutfcation0 t;xtj g t;:
- g ~
- a. Low Vessel level Incorrect -
- b. Turbine Stop Valve closure Correct Response
- c. High Drywell pressure Incorrect -
- d. High Scram Discharge Volume Incorrect -
References:
Tech Spec Bases Task Associations 3410330302/03 Evaluate Plant Conditions and Coordinate Appropriate Actions per Plant Technical Specifications/TRM in the Event a Limiting Safety System Setting is reached and/or exceeded Knowledge and Abilities Associations Sste KiA No.
tatemnt 295014 AK3.01 Reactor SCRAM 4.1 4.1 Static Simulator Exams: None Last Revised: 06/24/2002 1:45:38 PM by Fagan, Frank N.
2002 SROU Exam QuestionNo. 10 ExamBank QuestionNo.: 3941 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-612 Objective: A4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
While performing the initial actions of OP 3126 (Shutdown Using Alternate Shutdown Methods) from 75% power, the Operator is directed to place the "A" RHR Pump control switch in PULL-TO-LOCK.
Considering that this pump will be used for reactor water level control and/or shutdown cooling, which of the following is the reason for this switch manipulation prior to leaving the Control Room?
The Control Room switch for the "A" RHR Pump is placed in PULL-TO-LOCK...
An'w
^/D a
Justification
- a. to meet the interlock for the RHR Incorrect -
Alternate Shutdown Transfer Switches required for local control.
- b. to ensure that the pump does not start and Incorrect -
meet the logic for Automatic Depressurization System actuation.
- c. to prevent pump starts until the RHR Incorrect -
Shutdown Cooling Isolation Valves (RHR-17 / 18) are open for a suction path.
7 to ensure that the pump does not start Correct Response without minimum flow protection during transfer to local control.
References:
OP 3126, Shutdown Using Alternate Shutdown Methods Task Associations Task Num be Taskf Ti~Wtle~
2000680504 Perform Shutdown Using Alternate Shutdown Methods 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations Sy0tem KAN.
DStatement 2950 16 AK3.03 Disabling control room controls RO, SR 3.5 3.7 Static Simulator Exams: None Last Revised: 07/01/2002 10:39:17 AM by Fagan, Frank N.
2002 SROU Exam Question No. 11 Exam Bank Question No.: 3539 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-612 Objective: A5 Question Level: Comprehension Select the correct answer:
The control room has been abandoned and a shutdown is being conducted from outside the control room. Reactor pressure is currently 800 psig. A direction is given to commence a cooldown. The correct method to accomplish this is to:
(OP 3126, App C, fig. 1, is enclosed)
_ nswerstmcor Justifi'ation
- a. Reduce pressure gradually over the next Incorrect - Don't reduce press gradually hour by opening SRVs. At the end of the hour, pressure should be 325 psig.
- b. Reduce pressure gradually over the next Incorrect - Don't reduce press gradually hour by opening SRVs. At the end of the and wrong pressure-exceeds I00F/hr hour, pressure should be 250 psig.
- c. Reduce pressure to 250 psig by opening an Incorrect - Press exceeds 100F/hr SRV and maintain pressure 250 psig
+100/-0 psig.
- d. Reduce pressure to 325 psig by opening an Correct Response - Per OP 3126 App C SRV and maintain pressure 325 psig
+100/-0 psig.
References:
OP 3126 Appendix C Used in LOI 1999 RO Exam - Bacala (5/99)
Must integrate the following:
- Determine 1 000F limit applies
- Calculate current temp and temp at cooldown Task Associations 2007400501 Control RPV Pressure Using Bypass Valves, HPCI, RCIC, SRVS, RWCU, Steam Line Drains Knowledge and Abilities Associations System
/AAN.0 Seactem prent ure 2950 16 AA2.03 Reactor pressure RW SRO 4.3 4.4 Static Simulator Exams: None Last Revised: 07/09/2002 2:43:49 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 12 Exam Bank Question No.: 3312 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-611 Objective: SCRO 3 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- A fuel leak occurs and as a result the reactor is manually scrammed.
- Due to the fuel leak, ARM #6 and ARM #7 areas radiation levels reach 1200 mR/hr and 1250 mR/hr respectively.
- The south Scram Discharge Volume vent and drain valves have failed open and cannot be closed.
(EOP-4 is a required student reference.)
Under these conditions, Emergency RPV depressurization is:
- a. not required since the CRD HCU north and Incorrect - Different areas south areas are considered the same area.
required in order to limit the release of Correct Response - Two areas above
'S,5I radioactivity into the secondary containment.
max safe from a primary system
-M I requires an RPV-ED
- c. required to allow the scram to be reset and Incorrect - Scram reset is not dependent the primary system leak isolated.
on RPV-ED
- d. not required since there is no primary system Incorrect -Primary system directly discharging into secondary containment.
connected to RPV
References:
EOP-4 Must integrate the following:
- Requires procedure implementation of EOP-4, multiple decisions
- Requires correct reading of Table "O" of EOP-4
- Recognize SDV drains to RB Equip drain sump which is in Secondary Containment Task Associations 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations 295017 2.4.07 Knowledge of event based EOP mitigation strategies (CFR 3.1 3.8 41.10, 43.5, 45.13)
Static Simulator Exams: None Last Revised: 07/09/2002 2:44:12 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 13 Exam Bank Question No.: 3954 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-611 Objective: SRO 4 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- The plant is operating at 75% power
- Radioactivity is being released from a primary leak into secondary containment
- EOP-4 (Secondary Containment Control) has been entered Which one of the following EOP-4 actions would send unfiltered water/air to the environment?
- a. Operating available sump pump Incorrect -
- b. Operating available RRUs Incorrect -
d Restarting RB HVAC Correct Response
References:
K/A 295017 2000 SRO Audit Exam and 1999 NRC SRO Exam Must integrate the following:
Leakage into secondary containment would be into the Rx Bldg sumps and air. The Rx Bldg RRUs only circulate air internally. The sump pumps would discharge to radwaste. Only normal ventillation discharges to the outside.
Task Associations Task N um 0r Tk tle 2000170501 Respond to Containment Isolations 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations Syste K/- A N.Stafemen 295017 AK1.02 Protection of the general public R3.
SRO 3.8 4.3 Static Simulator Exams: None Last Revised: 07/09/2002 2:44:34 PM by Fagan, Frank N.
2002 SROU Exam Question No. 14 Exam Bank Question No.: 1343 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-234 Objective: CRO 4; SCRO 6 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which conditions listed below require evacuation of the Refueling Floor?
- 1. Doubling of SRM counts.
- 2. A dropped fuel assembly.
- 3. High airborne activity alarms in the reactor building on the 345 level.
- 4. Unanticipated decrease in Reactor Cavity level.
- 5. High radiation alarms on the Rx Building 303 level area rad monitors.
a w rDi;ticto, 2
and
- 5.
incocti -
- a. 1, 2 and 5.
Incorrect -
- b. 1, 4and 5.
Incorrect -
- c. 3, 4 and 5.
Incorrect -
2, 3 and 4.
Correct Response
References:
OP 1101 Task Associations TXsk Num ber Task Titlev 2997270301 Follow Operating Instructions and Procedures 3410290302/03 Supervise Refueling Operations as SRO on Refuel Floor Knowledge and Abilities Associations Ss5tm2 xK/ N
- o.
Staret t
haz 295023 AKl.0l Radiation exposure hazards RO SRO 3.6 4.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:44:53 PM by Fagan, Frank N.
2002 SROU Exam Question No. 15 Exam Bank Question No.: 3900 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-234 Objective: CRO-1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant is shutdown for refueling, with the Mode Switch in REFUEL. Which of the following describes the interlocks associated with rod withdrawal during refueling activities?
Answer/hstractor ustnifiatinN
- a. Control rod withdrawal is prevented Incorrect -
anytime the Refueling Platform is over the core.
- b. A control rod withdrawal block will be Incorrect -
inserted if one rod is fully withdrawn (Notch 48), and a second rod is withdrawn past Notch 02.
- c. A control rod withdrawal block will be Correct Response inserted anytime one rod is not fully inserted and a second rod is selected.
- d. With the Reactor Mode Switch transferred Incorrect -
to STARTUP/HOT STANDBY, no control rod withdrawal interlocks would be in effect.
References:
None Task Associations 2010030201 Conduct Refueling Interlocks Functional Test/CRD Maintenance Knowledge and Abilities Associations Sy5tem KAKW R
NS/oR.
Stemro and info a
295023 ALK2.04 RMCS/Rod control and inform~ation ;sy~stem RO SRO 3.2 3.4 Static Simulator Exams: None Last Revised: 07/09/2002 2:45:07 PM by Fagan, Frank N.
2002 SROU Exam Question No. 16 Exam Bank Question No.: 5567 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-607 Objective: SRO 4 Question Level: Comprehension Select the correct answer:
The plant is in the EOPs with the following conditions:
- Torus level - 11 ft
- DW Temp 1500F
- Drywell/Torus pressure is increasing Which one of the following would be the first Drywell/Torus pressure where containment integrity could no longer be assured?
- a. +2 psid DW/Torus Differential Pressure Incorrect -
- b. 10 psig DW pressure Incorrect -
- c. 25 psig Torus pressure Incorrect -
d 65 psig Torus pressure Correct Response
References:
EOP 3 Basis document Must integrate the following:
- PCPL-A graph maintains containment integrity
- Utilizing the PCPL-A graph determines we are in the unsafe region Task Associations Task Number U
Tas Tteii 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations 295024 EK1.01 Drywell integrity: Plant-specific 4.1 SR 4.1 4.2 Static Simulator Exams: None Last Revised: 06/28/2002 8:00:05 AM by Fagan, Frank N.
2002 SROU Exam Question No. 17 Exam Bank Question No.: 3563 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO 1 Question Level: Comprehension Select the correct answer:
A small steam leak inside the drywell has caused the following plant conditions to exist:
Drywell Pressure: 3.1 psig, rising slowly Drywell Temperature: 1671F, rising slowly Reactor Water Level: 142", steady Reactor Building Ventilation Exhaust Radiation: 1.2 mr/hr, steady Assuming all plant equipment operated as designed, what is the present status of Secondary Containment Atmosphere?
Ans er/Dsrt
<9i-00 IJstifia!eion
- a. At a positive pressure, being exhausted Incorrect -
through a filtered and monitored path.
b At a negative pressure, being exhausted Correct Response through a filtered and monitored path.
- c. At a positive pressure, being exhausted Incorrect -
through an unfiltered and unmonitored path.
- d. At a negative pressure, being exhausted Incorrect -
through an unfiltered and unmonitored path.
References:
OP 2117 OP 4116 1999 NRC RO Exam - Bacala Must integrate the following:
DW press above 2.5 psig results in RB HVAC being isolated and SGT running with suction on the RB. SGT is designed to maintain a negative pressure in the RB and it's discharge is filtered and monitored.
Task Associations 2000070501 Respond to Containment Hi Pressure 2000170501 Respond to Containment Isolations Knowledge and Abilities Associations Sytem K/
No.
STAme't 295024 EK2.17 Auxiliary building isolation logic: Plant-specific 3.0 3.3 Static Simulator Exams: None Last Revised: 07/09/2002 2:45:41 PM by Fagan, Frank N.
2002 SROU Exam Question No. 18 Exam Bank Question No.: 221 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-212 Objective: 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which of the following plant conditions will result in an automatic ARI/RPT actuation?
13 IAnserDstaoo Justificataon
- a. RPV Pressure - 1100 psig for 10 seconds Incorrect -
Rx Power-30%
- b. RPV Pressure - 850 psig for 5 seconds Incorrect -
RPV Water Level - 88 inches for 10 seconds
- c. RPV Water Level - 80 inches for 5 seconds Incorrect -
Rx Power - 2%
Rd RPV Pressure - 1200 psig for 3 seconds Correct Response RPV Water Level - 86 inches for 5 seconds
References:
OP 2110 Task Associations tak0Number Task Tidtl e c
SCRAM 2000330501 Respond to a Reactor SCRAM Knowledge and Abilities Associations System K/A o.0 StaTemen S Plant-specific 295025 EAl.07 ARIJRPT/ATWS: Plant-specific 4.1 4.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:45:54 PM by Fagan, Frank N.
2002 SROU Exam Question No. 19 Exam Bank Question No.: 3548 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-607 Objective: SRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
If torus temperature or RPV pressure cannot be maintained below the Heat Capacity Temperature Limit, EOP-3, Primary Containment Control, requires RPVED. This action is performed to avoid:
- a. damaging SRV downstream piping during Incorrect - Unrelated to SRV tailpipes RPV Emergency Depressurization.
- b. loss of all RPV level instruments after Incorrect - Level instrumentation affected RPV Emergency Depressurization.
by drywell temp c
overpressurizing the Primary Containment Correct Response - Highest torus temp during RPV Emergency Depressurization.
which does not exceed PCPL-A on RPVED
- d. excessive hydrodynamic loading on Incorrect - Hydrodynamic loading on downcomer piping during RPV Emergency downcomers not relevant to HCTL Depressurization.
References:
EOP 3 Study Guide Task Associations 2000190501 Respond to High Torus Water Temperature 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations Sy'stem K/A No Statement 295026 EK2.03 Suppression chamber pressure: Mark-I&II RO 36RO 3.2 3.6 Static Simulator Exams: None Last Revised: 07/09/2002 2:46:09 PM by Fagan, Frank N.
2002 SROU Exam Question No. 20 Exam Bank Question No.: 5557 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-308 Objective: SRO 1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
During normal operations the Tech Spec torus maximum temperature limit is
'F. This limit insures the suppression pool doesn't approach
a 90; 170 Correct Response
- b. 90; 212 Incorrect -
- c.
120; 170 Incorrect -
- d.
120; 212 Incorrect -
References:
Tech Spec 3.7.A K/A 295026 Task Associations Task Number Task Title 3410320302/03 Evaluate Plant System Performance and Coordinate Appropriate Actions per Technical Specifications in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations 295026 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for Technical Specifications (CFR 43.2, 43.3, 45.3) 3.4 4.0 Static Simulator Exams: None Last Revised: 06/26/2002 7:21:08 PM by Fagan, Frank N.
2002 SROU Exam Question No. 21 Exam Bank Question No.: 3861 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Given the following conditions:
- The plant has experienced a failure to scram (ATWS)
- Reactor water level is being deliberately lowered to reduce power Regardless of reactor power, level must NOT be lowered less than to ensure
-Anser/Distrtor Ju0.;000 0stification::0j eS020 n000Ad
'k'DSS~SihS 0
- a. +6"; thermal hydraulic instabilities Incorrect -
(oscillations) will not occur
- b. +6"; inadvertent low pressure ECCS starts Incorrect -
will not occur
-C. 1-22"; adequate core cooling is maintained Correct Response during the ATWS
- d. -22"; the narrow range water level variable Incorrect -
leg instrument tap is not uncovered
References:
Task Associations Task Number TaskTtle 2000310501 Respond to Low Reactor Water Level 3107120502/03 Direct Terminate and Prevent Injection into RPV from all Sources Knowledge and Abilities Associations IS
' W A> Ml
&0 \\Sh f
I0 I System K/A N.0 Statement 295031 EA2.02 Reactor power RO]:
SRo 4.0 4.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:46:31 PM by Fagan, Frank N.
2002 SROU Exam Question No. 22 Exam Bank Question No.: 3603 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-622 Objective: CRO la Question Level: Comprehension Select the correct answer:
A LOCA has occurred and all rods are in. Reactor water level is low and can not be maintained in the normal band. The crew has entered the EOPs and are attempting to achieve Adequate Core Cooling (ACC). Which one of the following ensures ACC?
an III %Wspt'rotr Justifi c=tio
- a. LPCI injecting at 7,000 gpm and vessel Incorrect -
level is at -28".
b C.S. injecting at 3,300 gpm and vessel Correct Response level is at -40".
- c. HPCI injecting at 4,000 gpm and vessel Incorrect -
level is at -47".
- d. RCIC injecting at 400 gpm and vessel Incorrect -
level is at -6".
References:
EOP Study Guide Definitions Justification: A C.S. System must be injecting at > 3250 gpm and level > -48" for ACC.
Regardless of injection flow, TAF is ACC. TAF is now defined at +6". ACC for steam cooling is -22".
Task Associations 2000310501 Respond to Low Reactor Water Level Knowledge and Abilities Associations Sst em K/
o ttment Sy953 EIWK.0 Spa co o in 295031 EK3.03 Spray cooling Ito ' SR So 4.1 4.4 Static Simulator Exams: None Last Revised: 07/09/2002 2:46:43 PM by Fagan, Frank N.
2002 SROU Exam Question No. 23 Exam Bank Question No.: 5558 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
The SCRO has entered EOP 2 for an ATWS. After repeated manual scrams the rods are partially inserted. There has been no boron injected and the SS wants to start a cooldown. Which one of the following can be used to determine the reactor is shutdown?
- a. APRM downscale lights Incorrect - APRM downscale lights indicate less than or equal to 2% power but not a shutdown condition.
Fully withdrawn SRMs, decreasing count Correct Response rates and a negative period
- c. LPRM downscale lights Incorrect -
- d. Fully withdrawn IRMs, decreasing count Incorrect - With IRMs withdrawn, the rates and range switches on range 8 point of adding heat (Range 7) can not be determined.
References:
EOP 2 Basis document Must integrate the following:
The APRM/LPRM downscale lights come on at low powers, will be on when shutdown, but don't indicate a shutdown condition. The IRMs must be below the point of adding heat which can not be determined when withdrawn.
Task Associations Tak Number Takite H 3
3440380302/03 Direct Shift Personnel Actions to Ensure Plant Safety During off Normal Conditions Knowledge and Abilities Associations System S
K/A Ni6 S tatemen 295037 EA1.06 Neutron monitoring system 4.1 4.1 Static Simulator Exams: None Last Revised: 07/01/2002 1:02:22 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 24 Exam Bank Question No.: 1059 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-611 Objective: SRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A steam leak is reported in the Heater Bay which has set off the Stack Gas Rad Mon Sys Trbl Alarm. While attempting to determine if actions to isolate the leak have been successful, a report is received that the Turbine Building HVAC is shutdown.
Which of the following should be performed?
RAnswer/Jistactr
- SEJ
- Xi.
- !a:u!.ustin:ficat~
WUV0:A gX;-Ais
- a. Leave the Turbine Building HVAC Incorrect -
shutdown to minimize the release from the Turbine Building.
- b. Leave the Turbine Building HVAC Incorrect -
shutdown since no direction is provided.
- c. Restart the Turbine Building HVAC to Incorrect -
filter the turbine building atmosphere and minimize radiological release.
dRestart the Turbine Building HVAC to Correct Response provide a monitored, elevated radiological release.
References:
EOP-4 Task Associations 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Knowledge and Abilities Associations System; K/A No Statement SR0 ^ASW 295038 2.4.07 Knowledge of event based EOP mitigation strategies (CFR 3.1 3.8 41.10, 43.5, 45.13)
Static Simulator Exams: None Last Revised: 07/09/2002 2:47:09 PM by Fagan, Frank N.
2002 SROU Exam Question No. 25 Exam Bank Question No.: 5559 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-607 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
The EOPs have been entered and the following steady state conditions exist:
Drywell 02 - unavailable Drywell H2 - 0.7%
Torus 02 - 5%
Torus H2 - 0.4%
Using the attached EOP-3, the containment should be purged with nitrogen:
A h0mediately based upon current conditions Correct Response
- b. After sampling results for Drywell 02 are Incorrect -
obtained
- c. After Torus H2 exceeds 0.5%
Incorrect -
- d. Before Torus H2 exceeds 0.5%
Incorrect -
References:
EOP 3 Must integrate the following:
The request for DW 02 results is not a hold point. The procedure is held for a combination of H2 and 02. Even without the DW 02, the hold point criteria is met, which requires purge.
Task Associations 345050 1 0 2/0 D irect P urge/Vn of the Containm t B d
u li n 3450150102/03 Direct Purge/Vent of the Containment Building Knowledge and Abilities Associations 500000 EA2.02 Oxygen monitoring system availability Ro SRO 3.0 3.5 Static Simulator Exams: None Last Revised: 06/28/2002 8:03:32 AM by Fagan, Frank N.
2002 SROU Exam Question No. 26 Exam Bank Question No.: 5560 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-01-624 Objective: SRO 2 Question Level: Comprehension Select the correct answer:
The SAGs have been entered and the containment has the following conditions:
Drywell H2 - 5%
Drywell 02 - 5%
Torus H2 - 7%
Torus 02 - 4%
Utilizing the attached SAG-2, determine which, if any, action level is required for the drywell.
- a. No action Incorrect -
- b. Action 1 Incorrect -
- c. Action 2 Incorrect -
d&. Action 3 Correct Response
References:
SAG-2 Must integrate the following:
Oxygen concentration meets the threshold of greater than or equal to 5%. With Torus H2 greater than or equal to 6% Action 3 is required regardless of drywell H2 concentration.
Task Associations Task Number Tas Title 3100080502/03 Implement SAG-1 and SAG-2 Knowledge and Abilities Associations Syste K/An No. Statement RO SROX 0X 0;
000 0;04kd0it0
^
500000 EA1.06 Drywell sprays 3.3 3.4 Static Simulator Exams: None Last Revised: 06/26/2002 8:06:47 AM by Fagan, Frank N.
2002 SROU Exam Question No. 27 Exam Bank Question No.: 3538 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The following conditions exist:
Main condenser backpressure: 5.4" Hg and rising rapidly Circ water in OPEN cycle CRO is reducing Reactor Power with recirc flow at 9%/min Annunciator 9-5-K-8, "STOP/CTRL VLV FAST CLOSURE BYP" is energized TB AO reports visible damage to the LP turbine exhaust boot and the sound of air rushing through The SCRO directs the crew to transfer station loads, scram the reactor, then trip the turbine.
These actions are required because:
- a. The resulting backpressure-induced Incorrect -
vibration will cause rotor bowing.
- b. An automatic turbine trip, due to high Incorrect - A turbine trip will not cause a backpressure, will cause a scram in this scram condition.
Turbine blade damage may result from Correct Response - Per GEK excessive exhaust pressure.
- d. Maintaining backpressure < 14" HgA will Incorrect - The MSIVs will be shut with preserve the main condenser as a heat sink. backpressure above 12" HgA
References:
OT 3120 1999 NRC RO Exam - Bacala Task Associations TaskNumber Task iTit le 2000080501 Respond to a Loss of Condenser Vacuum Knowledge and Abilities Associations System IA30 N0 Statement RO6 S Re 295002 2.1.06 Ability to supervise and assume a management role during 2.1 4.3 plant transients and upset conditions (CFR 43.5, 45.12, 45.13)
Static Simulator Exams: None Last Revised: 07/09/2002 2:47:35 PM by Fagan, Frank N.
2002 SROU Exam Question No. 28 Exam Bank Question No.: 3544 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 1, 4 Question Level: Comprehension Select the correct answer:
The ACRO notes the following indications in the Control Room:
EPR and MPR white lights on CRP 9-7 OFF Feed pump recirc valve position indication on CRP 9-6 OFF Main transformer cooling indicating lights on CRP 9-7 OFF RCIC system valve position indication on CRP 9-4 OFF Select the most appropriate operator action and basis from the list below.
swer iser JiWus aion HS
- a. A reactor scram will be required to unload Correct Response - Actions based upon the transformers before they overheat.
loss of DC-2 & DC-3
- b. An SAE must be declared due to a Incorrect -
sustained loss of CR annunciators.
- c. The "A" and "B" Feed Pumps must be Incorrect -
tripped locally since they receive their power from Bus 1.
- d. The MSIVs shall be closed immediately to Incorrect -
control pressure since both MPR and EPR will fail due to the low pressure condition.
References:
OT 3160 Must integrate the following:
-Synthesize the above indications to determine a loss of DC-2 occurred and comply with loss of DC-2 procedure Task Associations 2000320501 Respond to a Loss of DC-1, 2, 3 Knowledge and Abilities Associations Syte K/A N StatementO=
295004 AA2.04 System lineups 3.2 3.3 Static Simulator Exams: None Last Revised: 07/09/2002 2:47:49 PM by Fagan, Frank N.
2002 SROU Exam Question No. 29 Exam Bank Question No.: 5568 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-263 Objective: CRO 6 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant is at 100% power with the following conditions:
- RHR "A" Pump inop, in PTL (Pull to Lock)
- RHR "B" Pump running in Torus cooling
- RHRSW "D" Pump running in Torus cooling
- RHRSW "D" Pump has just lost DC control power If an LNP were to occur, what is the status of the RHRSW "D" Pump breaker?
- a. Breaker will trip, because AC control Incorrect -
power is still available.
- b. Breaker will trip, because the breaker Incorrect -
charging springs remain charged.
- c. Breaker will not trip, because RHR "A" Incorrect -
Pump is in PTL.
- d. Breaker will not trip, because it requires Correct Response DC control power.
References:
None Task Associations Task Number Task Title 2627390401 Respond to Loss of DC Control Power to a 4KV Bus Knowledge and Abilities Associations 295004 AK3.01 Load shedding: Plant-Specific RON SRO 2.6 3.1 Static Simulator Exams: None Last Revised: 06/26/2002 8:25:50 AM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 30 Exam Bank Question No.: 5584 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 2 & 3 Question Level: Comprehension Select the correct answer:
The plant is at 100% power when a scram signal is received. The CRO reports RPS failed to deenergize, the scram valves remain shut, no rod motion occurred and power remains at 100%.
Which one of the following EOP actions for control rod insertion will result in a turbine/generator trip?
a.App D, Vent the Scram Air header Correct Response - Causes turbine trip on low air pressure
- b. App E, Individual Control Rod Scrams Incorrect -
- c. App G, Manual Insertion of Individual Incorrect -
- d. App BB, Increase CRD Cooling Water Incorrect -
Pressure
References:
Must integrate the following:
- Affect on Turbine with respect to OE 3107 appendices
- Scram Air Header trip on turbine Task Associations akN er Ts Title i00 3101070502/03 Direct Bypassing of Group I Isolation Signals Knowledge and Abilities Associations y~stem K
NoStatement 9R,0' R
-S 295005 2.4.07 Knowledge of event based EOP mitigation strategies (CFR 3.1 3.8 41.10, 43.5, 45.13)
Static Simulator Exams: None Last Revised: 07/09/2002 2:48:07 PM by Fagan, Frank N.
2002 SROU Exam Question No. 31 Exam Bank Question No.: 1127 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-262 Objective: CRO 8 Question Level: Comprehension Select the correct answer:
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:
- a. Recirc MG B drive motor breaker will trip, Incorrect - Powered from Bus 2. Fast on bus undervoltage.
transfer of Bus 2 is satisfactory.
ib.0 Bus 1 Residual bus transfer will occur.
Correct Response - Residual transfer does not require the sync-check.
- c. Reactor Feedwater Pump A will trip when Incorrect - Trips in 0.3 sec Bus 1 voltage decays to 1000 volts, after a 5 second time-delay.
- d. Bus 1 Automatic fast transfer will occur.
Incorrect - Requires sync-check relay
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 Task Associations qTask Nuber Tk Tite' 2627400401 Respond to Loss of Fast Transfer SYNCHRO Check Relay Knowledge and Abilities Associations System AK/ANo.0 eStateimal dntibui 295005 AK2.08 A.C. electrical distribution Rp
'SRO 3.2 3.3 Static Simulator Exams: None Last Revised: 07/09/2002 2:48:24 PM by Fagan, Frank N.
2002 SROU Exam Question No. 32 Exam Bank Question No.: 5563 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-223 Objective: CRO 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant is at 100% power when the FW reg valves lockup. The valves drift open and level increases. The RFPs fail to trip. After tripping the RFPs, water level continues to rise.
What is the required action on the rising water level?
- a. When level reaches 177", shut HPCI/RCIC Incorrect -
15 and 16.
- b. When level reaches 200", shut all MSIVs.
Correct Response
- c. When level reaches 200", shut HPCI/RCIC Incorrect -
15 and 16.
- d. When level reaches 230", shut all MSIVs Incorrect -
and shut HPCI/RCIC 15 and 16.
References:
None Task Associations Ta Num er Takitle 2000170501 Respond to Containment Isolations 2047110401 Respond to Automatic RWCU System Isolation Knowledge and Abilities Associations 295008 AK2.04 PCIS/NSSS: Plant-Specific Static Simulator Exams: None Last Revised: 07/01/2002 8:56:34 AM by Fagan, Frank N.
3.1 3.3
2002 SROU Exam Question No. 33 Exam Bank Question No.: 5569 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 5 Question Level: Comprehension Select the correct answer:
The plant is at 100% power when a loss of feedwater occurs. Level drops to 82.5" and level is automatically restored. As level rises, HPCI fails to trip on high reactor water level. All other systems respond normally.
Which of the following could become flooded if HPCI continues to inject?
Answr/Di<tro Justifig4 cation l
- a. Main Turbine Casing Incorrect - Group 1 isolated turbine
References:
Must integrate the following:
At 82.5" a Group 1 isolation occurs and isolates the MSIVs. Both SJAEs and Main Turbine are isolated by MSIV closure. RCIC tripped at 177" and isolated itself from flooding. Only the SRVs can be flooded since they are used for pressure control.
Task Associations T)ask e
as Title 2067100401 Maintain Reactor Water Level with HPCI Knowledge and Abilities Associations Sguystem KIA Nro., SataemenlL ?S::1t
- .,!e.
295008 AK3.05 1PCI turbine trip: Plant-Specific R O; SRO 3.5 3.6 Static Simulator Exams: None Last Revised: 06/26/2002 8:35:26 AM by Fagan, Frank N.
2002 SROU Exam Question No. 34 Exam Bank Question No.: 2387 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-607 Objective: 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
In the PC pressure leg of EOP-3, operators are instructed to spray the DW when torus pressure exceeds 10 psig. The reason DW sprays are initiated beyond this pressure is to:
M nsWer/Distractor
~ Justifiatio
- a. Ensure DWSIL curve is not exceeded.
Incorrect -
- b. Ensure PCPLA is not exceeded.
Incorrect -
Sc Prevent chugging in the downcomer.
Correct Response
- d. Ensure enough time is available to prepare Incorrect -
to RPVED if sprays are not effective.
References:
EOP-3; EOP Study Guide Task Associations Task Number0 Task 2000070501 Respond to Containment Hi Pressure 3450120102/03 Direct Manual Initiation of Containment Spray Knowledge and Abilities Associations ystem KA No. S tatemen't 295012 AA2.02 Drywell pressure 3.9 SRO 3.9 4.1f~
Static Simulator Exams: None Last Revised: 07/09/2002 2:48:48 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 35 Exam Bank Question No.: 3936 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-216 Objective: CRO-i id Question Level: Comprehension Select the correct answer:
During a loss of coolant accident, the following conditions exist:
- Reference leg temperature is 350'F
- Reactor pressure is 50 psig Which one of the following describes the accuracy and trending capabilities of reactor water level indication for the given conditions?
Water level indication is:
=
swer/Di Itract r
AJusif PIat RIn ly A NOT providing accurate reactor water Correct Response level NOR level trend information.
- b. providing accurate reactor water level Incorrect -
AND level trend information.
- c. NOT providing accurate reactor water Incorrect -
level, BUT level trend is reliable.
- d. providing accurate reactor water level, Incorrect -
BUT level trend is NOT reliable.
References:
EPG/SAG Caution 1 Used in LOI 2000 SRO Audit Exam (8/00) and 1999 NRC SRO Exam Must integrate the following:
- Calculate the saturation conditions in the drywell
- Utilize caution #1 to determine level accuracy Task Associations 2000210501 Respond to High Drywell Temperature Knowledge and Abilities Associations System KA No.':'
Statem~ZN W
IEnt 29012 A' 0
Pressure/temperature relat inshi p 295012 AK.1 Pressure/temperature relationship Roflil-SRO 3.3 3.5 Static Simulator Exams: None Last Revised: 07/02/2002 9:38:59 AM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 36 Exam Bank Question No.: 5583 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-276 Objective: CRO I Question Level: Fundamental Knowledge/Memory Select the correct answer:
A SW break has occurred and SW header pressure falls to 30 psig. Which of the following loads will be isolated?
- a. RBCCW Heat Exchangers and Generator Incorrect -
Hydrogen Coolers
- b. RBCCW Heat Exchangers and Steam Incorrect -
Tunnel RRUs RR MG Set Lube Oil Coolers and Correct Response Generator Hydrogen Coolers
Tunnel RRUs
References:
OP 2181; ON 3148 Must integrate the following:
- Low service header pressure causes an isolation
- The isolation removes only certain components Task Associations Task Numbe Taskond tite ' Ls o Sv Water 2000300501 Respond to a Loss of Service Water Knowledge and Abilities Associations System K/AlN.0 SAftemnte 295018 AA1.03 Affected systems so as to isolate damaged portions 3.3 3.4 Static Simulator Exams: None Last Revised: 06/28/2002 8:15:29 AM by Fagan, Frank N.
2002 SROU Exam Question No. 37 Exam Bank Question No.: 1344 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: 3 Question Level: Comprehension Select the most correct answer:
A loss of shutdown cooling has occurred due to a loss of all available RHR pumps. SDC restart is unsuccessful.
In accordance with ON 3156, "Loss of Shutdown Cooling", what mode of operation for the RWCU system is required?
A-fsweiVDisfitratrJstfcto
Operation bReactor Letdown Correct Response
- c. Reactor Bottom Head Drain Line flush Incorrect -
- d. RCU Filter Demin Bypass with Return to Incorrect -
Vessel
References:
ON 3156 Task Associations Task Numbern T ts Tit le of S d
Cooling 2000150501 Respond to a Loss of Shutdow Coling Knowledge and Abilities Associations S yste m 1K A N o. State m ent 295021 AK3.04 Maximizing reactor water cleanup flow 1W0 SRO 3.3 3.4 Static Simulator Exams: None Last Revised: 07/09/2002 2:49:13 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 38 Exam Bank Question No.: 3946 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO-2 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- The plant is in Cold Shutdown
- Reactor coolant temperature is 190'F
- The reactor vessel head is installed
- The RHR lineup is as follows:
-- The "A" Loop is in shutdown cooling with the "C" RHR Pump in service
-- The "B" Loop is in torus cooling with the "D" RHR Pump in service
-- The "A" and "B" RHR Pumps are NOT available
- Reactor water level is lowering, and has reached 77 inches Assuming no Operator actions are taken, what is the expected response of the RHR and RHRSW to these conditions?
AnPh/ishtractor:
f pi; I :g<g i<if fV
>g Jutification t5g ' 000: 0
Incorrect -
b The "C" RHR and both RHRSW pumps trip. The "D" Correct Response RHR pump continues to operate.
Incorrect -
The "D" RHR and its associated RHRSW pump continue to operate.
Incorrect -
References:
OP 2124, Residual Heat Removal System Must integrate the following:
- A level of 127" causes a Group IV isolation
- RHR 17 & 18 valves go closed
- Any RHR pump without a clear suction path trips (RHR C)
- 82.5" is a LOCA signal if Rx <350#
- LOCA signal trips RHRSW Task Associations 2000150501 Respond to a Loss of Shutdown Cooling Knowledge and Abilities Associations 295021 AK2.04 Component cooling water systems: Plant-Specific 3.0 3.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:49:26 PM by Fagan, Frank N.
2002 SROU Exam Question No. 39 Exam Bank Question No.: 3948 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO-3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Given the following conditions:
- The plant is conducting a startup, with the Mode Switch in STARTUP/HOT STBY
- Plant pressure is 700 psig
- Control Rod 34-35 (at "Notch 10") has an Accumulator Trouble alarm in due to accumulator low pressure
- The "B" CRD Pump is tagged out
- The "A" CRD Pump has just tripped
- An additional accumulator trouble alarm comes in (NOT within a 9 rod array for 34-35)
What, if any, are the required actions for these conditions?
- a. No actions required Incorrect -
- b. Place the plant in Hot Shutdown within 12 Incorrect -
hours
- c. Place the plant in Cold Shutdown within Incorrect -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- d. Insert a manual reactor scram Correct Response
References:
ON 3145, Loss of CRD Regulating Function Task Associations Tak Ndumer Tak iW t leR 2007280501 Respond to Loss of CRD Regulating Malfunction Knowledge and Abilities Associations 295022 AK1.01 Reactor pressure vs. rod insertion capability Static Simulator Exams: None Last Revised: 07/09/2002 2:49:48 PM by Fagan, Frank N.
3.3 3.4
2002 SROU Exam Question No. 40 Exam Bank Question No.: 1818 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-01-624 Objective: SRO/DM 4; TSC/EOF 4 Question Level: Comprehension Select the correct answer:
An accident occurred 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago, and the following conditions exist:
(Students will be given EOP-3)
RPV pressure is 50 psig and steady All SRV switches are in OPEN Drywell pressure is 3 psig and steady Drywell temperature is 2750F and rising slowly Based upon these plant conditions, what adverse conditions could result from drywell spray initiation?
n_ e/itat JX iius tI ca ton
- a.
The evaporative cooling pressure drop may Correct Response - DWSIL allows this result in drywell pressure going to limit but will not exceed it.
atmospheric.
- b. The evaporative cooling pressure drop may Incorrect - DWSIL prevents exceeding this result in exceeding design differential limit pressure between the torus and drywell.
- c.
The steam produced by initiating drywell Incorrect - Sprays condense steam and sprays could over-pressurize the reduce pressure.
containment.
- d. Spraying into such a hot environment may Incorrect - Brittle fractures occur with cold cause brittle fracture of the containment temperatures.
liner.
References:
EOP Study Guide Must integrate the following:
- Utilizing the DWSIL graph recognizes DW pressure is in unsafe region
- If sprayed in unsafe region we would create an evaporative cooling effect Task Associations TaskNumbr Tak Title 3100080502/03 Implement SAG-1 and SAG-2 Knowledge and Abilities Associations S5yste K/)A N Wo.Statement Ma 295028 EAl1.01 Drywell spray: Mark-I&II RO8 SRO 3.'8 3.9 Static Simulator Exams: None Last Revised: 07/09/2002 2:50:02 PM by Fagan, Frank N.
2002 SROU Exam Question No. 41 Exam Bank Question No.: 5585 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
The plant is at 100% power with all systems operational and in a normal lineup. A LOCA occurs, all systems respond as designed and initiate injection into the vessel.
The following conditions exist:
- Torus level 15 ft and rising
- RPV pressure 35 psig and lowering
- RPV water level 95 inches and rising slowly What system should be terminated to prevent a continued torus level increase?
AnweriPtActo Jusificatioln
- c. Condensate Correct Response - Outside source of injection
- d. Core Spray Incorrect - Not aligned to CST normally
References:
EOP 3 Justification:
Must integrate the following:
Level rise must be coming from outside sources. HPCI & RCIC are isolated on low pressure.
CS can be aligned to outside source but normally done only in outages. Only Condensate is aligned to an outside source of water.
Task Associations Tas Number T
Ti=e 2000230501 Respond to High Torus Water Level Knowledge and Abilities Associations
'Syste iK/ N Sta tem gent
.9 I 295029 EA2.03 Drywell/containment water level 3.4 3.5 Static Simulator Exams: None Last Revised: 07/02/2002 9:39:19 AM by Fagan, Frank N.
2002 SROU Exam Question No. 42 Exam Bank Question No.: 3906 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO-7, 8 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- The plant is operating at 70% power
- HPCI is running for a surveillance test
- The "A" SBGT train is running to support HPCI operation
- The "B" SBGT train was secured after HPCI was started
- A valid Refuel Floor High Radiation signal is received
- All plant systems respond as designed
- No Operator actions are taken Which of the following is the expected response of SBGT for these conditions?
begin processing the Reactor Building atmosphere after the HPCI Gland Seal Exhauster discharge isolates.
b The "B" SBGT Train will not start. The "A" SBGT Train will Correct Response begin processing the Reactor Building atmosphere along with the HPC1 Gland Seal Exhauster discharge.
- c. The "B" SBGT Train starts and begins processing the Reactor Incorrect -
Building atmosphere. The "A" SBGT Train will trip and isolate as part of the HPCI Gland Seal Exhauster discharge isolation.
- d. The "B" SBGT Train starts and begins processing the Reactor Incorrect -
Building atmosphere. The "A" SBGT Train will divert to process the HPCI Gland Seal Exhauster discharge exclusively.
References:
OP 2117, Standby Gas Treatment Must integrate the following:
- Only way to shutdown train with an auto signal is to place in P-T-L
- P-T-L disables all other starts
- The HPCI flowpath does not isolate on a radiation auto start Task Associations Tk Nk Title 2610010101 Perform Lineups on the SBGT System Knowledge and Abilities Associations Sytem K
N.I StI N-emenMtI 295033 EK1.03 Radiation releases R9 SRO4 3.9 4.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:50:24 PM by Fagan, Frank N.
2002 SROU Exam Question No. 43 Exam Bank Question No.: 5587 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-062 Objective: 1 Question Level: Comprehension Select the correct answer:
Reactor Building ventilation has isolated on high exhaust radiation levels. All valves have isolated but the status of "A" Rx Bldg Supply Fan can not be determined. There are no red/green indications in the control room nor locally. Using the attached CWD Sheet 1394, determine that cause for the loss of all indication could come from an open breaker at or
- a. MCC 7D; one blown fuse at coordinates F-Incorrect -
3
- b. MCC 7D; two blown resistors at Incorrect -
coordinates A/B-3/4
- c. MCC 1 A; one blown fuse at coordinates Correct Response F-3
- d. MCC 10A; two blown resistors at Incorrect -
coordinates AIB-3/4
References:
K/A 295034 Must integrate the following:
Light indication is powered through resistors but each set of lights has its own resistors. A loss of one set would not affect the other lights. The fuse would interrupt the control power that feeds all light indications. Also, while 2 MCCs are indicated, only one shows breaker contacts.
The other is an interlock with the B fan.
Task Associations Task Number Ask Tle 2887210401 Respond to a Loss of Reactor Building Ventilation Knowledge and Abilities Associations 295034 2.2.15 Ability to identify and utilize as-built and configuration change documentation to ascertain expected current plant configuration and operate the plant (CFR 43.3, 45.13) 2.2 2.9 Static Simulator Exams: None Last Revised: 06/28/2002 8:23:53 AM by Fagan, Frank N.
2002 SROU Exam Question No. 44 Exam Bank Question No.: 3311 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A trip of the "A" Reactor Recirculation Pump has occurred. The plant is operating in the Buffer Region of the Power/Flow Map, the "B" Reactor Recirculation Pump is at 70% speed and Solomon is NOT available.
Which ONE of the following is REQUIRED?
Exit the Buffer Region by:
AnswerDi*t"co0 Jusitl ititttio i
ficatioN
- a. manually scramming the reactor.
Incorrect -
- b. inserting control rods using the spiral Incorrect -
outward pattern.
- c. increasing the speed of the "B" Reactor Incorrect -
Recirculation Pump.
inserting control rods using the Rapid Correct Response Shutdown Sequence.
References:
Pilgrim 97 NRC Exam OT 3117 Task Associations 2010100101 Tsk Title "N~
Operate the Control Rod Drive System to Shut Down the Reactor Knowledge and Abilities Associations Systi K/ A No. Staement 202002 K1.10 Rod pattern 2.5 2.6 Static Simulator Exams: None Last Revised: 07/01/2002 9:32:25 AM by Fagan, Frank N.
2002 SROU Exam Question No. 45 Exam Bank Question No.: 5586 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2, 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The RHR system is operating in LPCI mode due to a LOCA.
cool the pump room and _
is required to cool the pump seals.
is required by the RRU to
~NAns~owerDsrcol J~1~~Alat,~ustifiation -~~I~~~Z~ 1~R
- b. RBCCW; Service Water Incorrect -
- c. Service Water; RBCCW Correct Response
- d. Service Water; Service Water Incorrect -
References:
None Task Associations Task Numbe TaskTtle 2050010101 Perform Lineups of the Residual Heat Removal System Knowledge and Abilities Associations S ystem K/A No. Sta
- te e n t
.0 203000 K1.16 Component cooling water systems RO 3S.
3.1 3.2 Static Simulator Exams: None Last Revised: 07/01/2002 1:17:37 PM by Fagan, Frank N.
2002 SROU Exam Question No. 46 Exam Bank Question No.: 1183 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CR0 2/ SE 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant has experienced a DBA LOCA concurrent with an LNP. The Emergency Diesel Generators have just powered busses 3 and 4. It is expected that RHR system response will be:
Ans
/D~istrlto Jus 60it tifctio*n a
RHR pumps A & D start immediately, C & Correct Response B start 5 seconds later.
- b. RHR pumps C & B start immediately, A & Incorrect -
D start 10 seconds later.
- c. RHR pumps A & C start immediately, B & Incorrect -
D start 5 seconds later.
- d. RHR pumps A & D start immediately, C & Incorrect -
B start 10 seconds later.
References:
OT 3122 Task Associations 2057160101 Shut Down the RHR System after LPCI Initiation Knowledge and Abilities Associations Syste K/A No. Statement 203000 K6.01 A.C. electrical power S
SR O 3.6 3.7 Static Simulator Exams: None Last Revised: 07/09/2002 2:50:59 PM by Fagan, Frank N.
2002 SROU Exam Question No. 47 Exam Bank Question No.: 1851 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-209 Objective: 1,7,8 Question Level: Comprehension The "A" core spray loop is running in the full flow test mode for a scheduled surveillance test. A major leak develops in one loop of the recirculation system, the reactor quickly depressurizes to approximately 500 psig and DW pressure increases to 20 psig.
Determine the "A" Core Spray response to the above conditions.
- a. Core Spray Injection valve (CS-12A) will open, Incorrect -
Test Bypass valve (CS-26A) will close, and Minimum Flow valve (CS-5A) will open.
b.0 Core Spray Injection valve (CS-12A) will remain closed, Correct Response Test Bypass valve (CS-26A) will close, and Minimum Flow valve (CS-5A) will open.
- c. Core Spray Injection valve (CS-12A) will open, Incorrect -
Test Bypass valve (CS-26A) will close, and Minimum Flow valve (CS-5A) will remain closed.
- d. Core Spray Injection valve (CS-12A) will remain closed, Incorrect -
Test Bypass valve (CS-26A) will close, and Minimum Flow valve (CS-5A) will remain closed.
References:
OP 2123 Must integrate the following:
A DW press of greater than or equal to 2.5 psig causes an initiation signal. The system realigns to inject but the injection valve must also see less than or equal to 350 psig to open. With the 12A and 26A closed, the 5A will meet its permissive of less than 300 gpm with an auto initiation signal present.
Task Associations 2090020201 Perform ECCS Integrated Initiation Test Knowledge and Abilities Associations System K/0 N upSt mient flow 20900 1 K4.05 Pump minimum flow ROm SRO 2.6 2.6 Static Simulator Exams: None Last Revised: 07/09/2002 2:51:11 PM by Fagan, Frank N.
2002 SROU Exam Question No. 48 Exam Bank Question No.: 5564 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-209 Objective: CRO Ic Question Level: Comprehension Select the correct answer:
With the plant operating at 100% power, the following occurs:
- "B" CORE SPRAY HEADER d/p HIGH annunciates.
- Core Spray leak detection indication reads +4 psid.
All other plant parameters are normal A short time later a Main Steam Line break occurs. Inventory loss is occurring at a rate of 3000 gpm. If "B" Core Spray was used to ensure Adequate Core Cooling (ACC), it would be:
- a. ineffective for both core submergence and Incorrect -
spray cooling.
b effective for core submergence only.
Correct Response
- c. effective for both core submergence and Incorrect -
spray cooling.
- d. effective for spray cooling only.
Incorrect -
References:
LOT-00-209 Must integrate the following:
The alarm indicates a break between the shroud and vessel. The spray header can not be relied on for ACC. However, with a MSL break CS can be used to flood up the shroud, jet pumps and thus the core. The leak of 3000 gpm is less than the CS capability.
Task Associations Task Nuber Task TitleMI 2097010401 Maintain Reactor Water Level with Core Spray Knowledge and Abilities Associations Syste K/~-A No-. Statmen 209001 K5.04 Heat removal (transfer) mechanisms RtOX SA9SROG 2.8 2.9 Static Simulator Exams: None Last Revised: 07/01/2002 12:48:36 PM by Fagan, Frank N.
2002 SROU Exam Question No. 49 Exam Bank Question No.: 3664 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The following plant conditions exist:
SLC System 1 injecting to the RPV RPV pressure is 1100 psig and dropping slowly 4 SRVs open RWCU in service All rods at position 48 MSIVs closed The CRO must immediately:
Asier/
PON Dy istc tor
%h H" stlli' 0Ju stiicati
- a. drive control rods.
Incorrect - Must wait for SCRO direction to drive control rods
- b. reduce pressure with bypass valves.
Incorrect - MSIVs shut I isolate RWCU.
Correct Response - RWCU should be isolated automatically
- d. start SLC System 2.
Incorrect - It is possible that the RWCU isolation failure was caused by the SLC switch and using SLC 2 might work, but it would require securing SLC injection which is undesirable
References:
EOP-2 K/A 211000 Used in LOI 1999 RO Exam - Bacala (5/99)
Task Associations Task Nu r
Tad.
Te itl 2000200501 Respond to ATWS Event(s) 2110050101 Inject Poison Solution into the Reactor Vessel Knowledge and Abilities Associations 211000 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures (CFR 41.10, 43.5, 45.13)
RO3 SW 3.0 4.0 Static Simulator Exams: None Last Revised: 07/09/2002 2:51:31 PM by Fagan, Frank N.
2002 SROU Exam Question No. 50 Exam Bank Question No.: 3512 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-211 Objective: 2b, 2d Question Level: Fundamental Knowledge/Memory Select the correct answer:
A failure to SCRAM coincident with a loss of Bus 9 occurs. The SCRO has ordered Standby Liquid Control (SLC) injected. The CRO positions the SLC initiation switch to SYS 1. Predict the expected SLC system response.
- a. SLC-14A squib valve will fire and the "A" Incorrect -
SLC pump will start
- b. SLC-14A squib valve will fire and the "A" Incorrect -
SLC pump will not start
- c. SLC-14A squib valve will not fire and the Incorrect -
"A" SLC pump will start d SLC-14A squib valve will not fire and the Correct Response "A" SLC pump will not start
References:
None Task Associations 211005 1
Injec Poite so SGig, te j
XEgg<=
2110050101 Inject Poison Solution into the Reactor Vessel Knowledge and Abilities Associations 211000 K2.02 Explosive valves 3.1 3.2 Static Simulator Exams: None Last Revised: 06/26/2002 7:25:55 PM by Fagan, Frank N.
2002 SROU Exam Question No. 51 Exam Bank Question No.: 3892 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-05-215 Objective: CRO 2d, 5 Question Level: Comprehension Select the correct answer:
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?
MsNIMo J, ust7ifiato
- a. A full scram will occur due to flow biased Incorrect -
neutron flux high.
b A control rod block will occur due to a Correct Response flow converter/comparator out of limits trip.
- c. A control rod block will occur due to a Incorrect -
flow converter/comparator unit "inop" signal.
- d. A half scram will occur due to flow biased Incorrect -
neutron flux high.
References:
Must integrate the following:
An increase in actual flow will increase the output of the "A" Flow Converter/Comparator. The lowest point a flow biased rod block could happen would be 42%. When flow increases to approximately 32%, the comparators will have a 7% mismatch. The mismatch causes an out of limits trip which causes a rod block. The inop is only caused by a loss of power.
Task Associations Tq R.^N^
^ber 3s itl&,
2157150401 Respond to APRM System Alarms Knowledge and Abilities Associations 0%tm lKIA"o4 KS 't,6p^^^
E 215005 A3.06 Maximum disagreement between flow comparator channels: Plant-Specific 3.0 3.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:51:50 PM by Fagan, Frank N.
2002 SROU Exam Ouestion No. 52 Exam Bank Question No.: 3522 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-05-215 Objective: CRO 5 Question Level: Comprehension Select the correct answer:
The reactor is operating at 50% power with the following LPRM status for "E" APRM:
A Level LPRMs 3
B Level LPRMs 5
C Level LPRMs 2
D Level LPRMs 3
LPRM 5B-08-09 which is assigned to "E" APRM fails downscale. I&C recommends bypassing the failed LPRM.
Predict the plant response when the LPRM is bypassed.
- a. "LPRM DOWNSCALE" alarm clears only Incorrect -
- b. Control Rod Block only Incorrect -
- c. Half Scram only Incorrect -
W Control Rod Block and a Half Scram Correct Response
References:
T.S. Table 3.1.1 and 3.2.5 Must integrate the following:
- Calculate the # of LPRMs
-Determine B & E APRMs require 13 (others need 8)
- Less than 13 LPRMs causes an Inop
- An Inop causes both a 1/2 scram and rod block Task Associations 2150230101 Operate the Neutron Monitoring System Knowledge and Abilities Associations 215005 A4.04 LPRM back panel switches, meters and indicating lights 3.2 3.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:52:02 PM by Fagan, Frank N.
2002 SROU Exam Question No. 53 Exam Bank Question No.: 5573 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-405 Objective: CRO 8 Question Level: Comprehension Select the correct answer:
RCIC has been periodically tripping on a spurious high level signal. I&C desires to disable this signal for approximately a year until the next outage. During the 10CFR50.59 screening process, it should be determined that it require a change to Tech Specs and the final approval authority would be the _
-Ans
==;:istno.
6f}lcail
- a. does; NRC Correct Response
- b. does; Plant Manager Incorrect -
- c. does not; NRC Incorrect -
- d. does not; Plant Manager Incorrect -
References:
K/A 217000 AP 6002 Must integrate the following:
177" is a Tech Spec required setpoint for the high level trip. If disabled, RCIC would be declared inoperable in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. RCIC would be in a 14 day LCO. A longer period of time requires a Tech Spec change. The NRC has final approval authority for Tech Spec changes.
Task Associations
-aiNme T}_ask Titge.
$St~
- 9.
K g...vi gs w ji 3410390302/03 Authorize or Effect Setpoint Changes Knowledge and Abilities Associations y'RMoNWffi N'............o 217000 2.2.10 Knowledge of the process for determining if the margin of 1.9 3.3 safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment (CFR 43.3, 45.13)
Static Simulator Exams: None Last Revised: 06/25/2002 11:57:50 AM by Fagan, Frank N.
2002 SROU Exam Question No. 54 Exam Bank Question No.: 5575 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
The plant has the following conditions:
- All rods in
- Main Steam line break in the Turbine Bldg
- MSIVs have failed to isolate
- Rx Level +82.5" and decreasing at 5"/min
- Rx Pressure - 900 psig ADS will initiate after and the RO should be directed to ADS initiation.
a.w=
2minutes;inhibit Inc6r
- a. 2 minutes; inhibit Incorrect -
- b. 2 minutes; allow Incorrect -
- c.
10 minutes; allow Incorrect -
4, 10 minutes; inhibit Correct Response -
References:
EOP-1 Must integrate the following:
Break outside of containment enables 8 minute timer. 2 minute timer enabled after 8 minute timer. Level at +30" when 2 min timer starts. EOP-1 directs ADS timer inhibited. RPVED doesn't occur until +6".
Task Associations 3101100502/03 Inhibit Auto Initiation of ADS Knowledge and Abilities Associations elt~~j rx 44en~lg R
0 lgM.wp WiwiStv0 218000 A2.02 Large break LOCA 3.5 3.6 Static Simulator Exams: None Last Revised: 06/26/2002 7:27:25 PM by Fagan, Frank N.
2002 SROU Exam Question No. 55 Exam Bank Question No.: 3951 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-288 Objective: CRO-5 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- Drywell pressure is 2.0 psig and slowly rising due to a small leak
- Drywell cooling has been maximized IAW OT-3 111 (High Drywell Pressure)
- Eight drywell RRUs are currently running
- Drywell pressure subsequently reaches 2.5 psig and an LNP occurs The RRUs will:
- a. automatically shift to lA/B & 2A/B Incorrect -
running, and 3A/B & 4A/B off, and may be shifted to all eight running after a time delay.
- b. trip and can be restarted by the Operator Correct Response after bypassing/resetting trip logics.
- c. continue to run until manually shifted by Incorrect -
the Operator.
- d. trip and cannot be restarted until drywell Incorrect -
pressure is lowered to less than 2.0 psig.
References:
OP 2115, Primary Containment Used in LOI 2000 RO Audit Exam (8/00)
Must integrate the following:
- LNP causes loss of power to Buses 8 & 9
- Buses 8 & 9 supply DW RRUs
- Diesels repower Buses 8 & 9
- RRUs trip on 2.5 psig and load shed on LNP Task Associations 2000070501 Respond to Containment Hi Pressure Knowledge and Abilities Associations 223001m K2.A N9: StaementP 223001 K2.08 Containment cooling air handling units: Plant-Specific K
I If'i.
fA, :
2.7 3.O 2.7 3
Static Simulator Exams: None Last Revised: 07/09/2002 2:52:25 PM by Fagan, Frank N.
2002 SROU Exam Question No. 56 Exam Bank Question No.: 495 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-229 Objective: CRO 2,5,8,10,11 Question Level: Comprehension Select the correct answer:
During normal plant operation at 100% power, drywell-to-torus dP has reached 1.9 psid and is rising slowly. No indications of coolant leakage are present, and the dP rise is attributed to the Nitrogen Supply System. Which of the following conditions would cause the rising dP?
- a. The nitrogen purge supply pressure control Incorrect -
valve (PCV-1-156-10) is too far open and needs throttling in the CLOSE direction.
- b. The nitrogen purge supply pressure control Incorrect -
valve (PCV-1-156-10) is not open far enough and needs throttling in the OPEN direction.
c The nitrogen makeup pressure control Correct Response
$ valve (PCV-1-156-3) is too far open and needs throttling in the CLOSE direction.
- d. The nitrogen makeup pressure control Incorrect -
valve (PCV-1-156-3) is not open far enough and needs throttling in the OPEN direction.
References:
OP 2119 Must integrate the following:
During normal operations PCV-1-156-10 is kept closed and the line isolated. PCV-1-156-3 is normally kept throttled and the pressure control is on the supply line rather than the vent line, thus it must be throttled closed.
Task Associations 2230030101 Perform Containment Makeup Knowledge and Abilities Associations 223001 K6.08 Containment atmospheric control Static Simulator Exams: None Last Revised: 07/09/2002 2:52:36 PM by Fagan, Frank N.
3.3 3.4
2002 SROU Exam Question No. 57 Exam Bank Question No.: 5600 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO 2 Question Level: Comprehension Select the correct answer:
Following a power transient a line break occurs downstream of RV-39 and RV-40, Sample Isolation Valves. The reactor is scrammed and EOPs are entered to mitigate the event.
The following conditions exist:
- Containment radiation - 1200 R/hr
- RV-39 and RV-40 fail to isolate
- a. Declare an Alert (A-1-b)
Incorrect -
- b. Declare a Site Area Emergency (S-2-a)
Incorrect -
- c. Declare a Site Area Emergency (S-3-a)
Incorrect -
I Declare a General Emergency (G-2-a)
Correct Response - 3 barrier loss
References:
OP 2113 Must integrate the following:
- All three barriers lost
- Correctly apply AP 3125 Task Associations s
ufoXm.
K i,:f
.av 2000170501 Respond to Containment Isolations 2997270301 Follow Operating Instructions and Procedures Knowledge and Abilities Associations 223002 K1.06 Recirculation system 2.9 3.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:52:52 PM by Fagan, Frank N.
2002 SROU Exam Question No. 58 Exam Bank Question No.: 1081 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-223 Objective: 6, 10, 11, Question Level: Comprehension Select the correct answer:
A refuel floor high radiation has been received. The refuel floor radiation monitor indicates a reading of 120 mr/hr.
Using ERFIS the "ISOL" icon is demanded and the "ISOLATION GROUPS AND VALVES DISPLAY" is displayed.
EFIS should show a Group 3A/B indication color of and a Group 3A/B valves indicating RED; GREEN Correct Response - Group displays change to RED when signal is present, back panel valve icons change from red (open) to green (closed) following isolation
- b. GREEN; RED Incorrect -
- c. GREEN; GREEN Incorrect -
- d. RED; RED Incorrect -
References:
OP 2115 Must integrate the following:
The setpoint for a Group 3 isolation is 100 mr/hr. When ERFIS receives an isolation signal, it turns from green to red. The valves indicate as they normally would, green for shut and red for open. A Group 3 signal causes the valves to go closed so they should indicate green.
Task Associations 200017050 Respon to Containmet Ilations 2000170501 Respond to Containment Isolations Knowledge and Abilities Associations 223002 A1.03 SPDS/ERIS/CRIDS/GDS: Plant-Specific AR.
Ssw 2.5 2.8 Static Simulator Exams: None Last Revised: 07/09/2002 2:53:16 PM by Fagan, Frank N.
2002 SROU Exam Question No. 59 Exam Bank Question No.: 3859 Revision: I Point Value: 1 SRO Only: No Instructor Guide:
Objective:
Question Level: Fundamental Knowledge/Memory Select the correct answer:
A fully qualified Vermont Yankee radiation worker with all previous exposure history on file has received 2355 mrem through the month of September for 2001.
Which of the following is the remaining Total Effective Dose Equivalent (TEDE) exposure this individual is allowed to receive during the final quarter (three months) of 2001? Assume no authorizations to exceed Vermont Yankee administrative limits have been received.
lm l-~-.
1-
^.-
==. M-A goY Mlm 3
"I _
- a.
1145 mrem Incorrect -
- b. 1645 mrem Incorrect -
2145 mrem Correct Response
- d. 2645 mrem Incorrect -
References:
AP 0506, Personnel Monitoring, (Discussion Section)
K/A 226001 Used in LOI 2000 RO Audit Exam (8/00) and 1999 NRC RO Exam Task Associations 2990100301 Apply Radiation and Contamination Safety Procedures Knowledge and Abilities Associations 226001 2.3.02 Knowledge of facility ALARA program (CFR 41.12, 43.4, 2.5 2.9 45.9, 45.10)
Static Simulator Exams: None Last Revised: 07/09/2002 2:53:29 PM by Fagan, Frank N.
2002 SROU Exam Question No. 60 Exam Bank Question No.: 3694 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-249 Objective: CRO 4 Question Level: Comprehension Select the correct answer:
The plant is operating normally at 100% power when the Speed Load Changer fails in the lower direction.
With this failure Reactor power will due to a(n) in feedwater heating.
~i~fad.,t+WS
______________________;__:__OWN0__a increase; decrease Correct Response -
- b. increase; increase Incorrect -
- c. decrease; decrease Incorrect -
- d. decrease; increase Incorrect -
References:
Must integrate the following:
Control valves will close and the bypass valves will open. With the bypass valves open, FW heating will decrease resulting in colder FW and a positive reactivity addition.
Task Associations 2450120101 Shutdown the Turbine Generator Knowledge and Abilities Associations Sytm NW S
'1 s
241000 K3.01 Reactor power Sa S4.1 4.1 4.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:53:46 PM by Fagan, Frank N.
2002 SROU Exam Question No. 61 Exam Bank Question No.: 5576 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO 4 Question Level: Comprehension Select the correct answer:
A Group 3 isolation signal is received and then clears. SBGTs start and all Group 3 valves close.
The Group 3 valves are backed up, including the Rx Bldg HVAC supply and exhaust dampers (HVAC-9, 10, 11 and 12). The SBGT-IA/B control switches are left in Auto/Close. If you attempted to reset the Group 3 isolation you would expect the isolation to and Rx Bldg DP to
- a. NOT reset; decrease Incorrect -
- b. NOT reset; remain the same Incorrect -
W reset; decrease Correct Response -
- d. reset; remain the same Incorrect -
References:
Must integrate the following:
A Group 3 causes a trip of normal RBHVAC. SBGT 1A & 1B come open upon a Group 3 signal but are normally closed. They are not part of the Group 3 reset IOPL logic and thus the Group 3 can be reset. Once reset the valves go closed. With no RBHVAC and SBGT no longer drawing a suction then Rx Bldg DP decreases.
Task Associations 2610020101 Place the SBGT System in Standby Readiness Knowledge and Abilities Associations
^ ides W '0S~N-- MQg lS ~
llg Alvin,,~
1911
- All, 261000 A1.04 Secondary containment differential pressure 3.0 3.3 Static Simulator Exams: None Last Revised: 06/28/2002 8:36:33 AM by Fagan, Frank N.
2002 SROU Exam Question No. 62 Exam Bank Question No.: 5565 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO 8 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The SBGT system is in normal standby lineup when a total loss of air occurs. If a SBGT auto initiation occurs, you would expect the air operated SBGT valves to be:
01.'.
HimN }'D
'I '
'Y d
.. w C0 z
a lined up properly.
Correct Response
- b. failed as is.
Incorrect -
- c. all closed.
Incorrect -
- d. all open.
Incorrect -
References:
None Task Associations 2600 1
P m Le on te SBT Ss tem, 2610010101
'Perform Lineups on the SBG'T System Knowledge and Abilities Associations Systiem
.K/.iNs.. Siat^.mle 261000 A3.03 Valve operation g ( ! Vg ammOMMl MA..
M D
3.0 2.9 Static Simulator Exams: None Last Revised: 07/09/2002 2:54:07 PM by Fagan, Frank N.
2002 SROU Exam Question No. 63 Exam Bank Question No.: 5577 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-263 Objective: SRO 1; CRO 7d Question Level: Comprehension Select the correct answer:
The plant is in normal 100% power operations. A loss of AC electrical power occurs for the "B" Main Station Battery Charger (BC-1-1B). It is determined this charger will require 7 days to repair. This loss affects battery bus and will require ARa I M =.tiXa d
N ip,
- a. DC-3; a 3 day LCO and plant shutdown Incorrect -
Ib. DC-3; a 3 day LCO until the spare charger Correct Response - Charger feeds DC-2 is placed in service which normally feeds DC-3. Tech Specs requires only one charger for Bus DC-2.
- c. DC-lAS; a 3 day LCO and plant shutdown Incorrect -
- d. DC-lAS; a 3 day LCO until the spare Incorrect -
charger is placed in service
References:
Tech Specs; OP 2145 Must integrate the following:
BC-l-lB feeds DC-2 which normally feeds DC-3. Tech Specs requires a charger for "B" Batteries but there is a space charger available.
Task Associations
.B.ONd, KRGE W-NM 4l0
.9 0
t},021~
k 34 10320302/03 Evaluate Plant System Performance and Coordinate Appropriate Actions per Technical Specifications in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations lw M611 w.T§?w W M-d'0 S2stem1 KA electricl distributio 262001 3.03 D.C. electrical distribution 2.9 3.2 Static Simulator Exams: None Last Revised: 07/01/2002 1:21:30 PM by Fagan, Frank N.
2002 SROU Exam Question No. 64 Exam Bank Question No.: 3157 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-262 Objective: CRO id Question Level: Fundamental Knowledge/Memory Select the correct answer:
During normal power operation, the outside operator informs the Control Room that the "High Pressure Cylinder" pressure on ATB 79-40 is 390 psig and decreasing with the compressor running. WHICH ONE (1) of the following states the consequences of this condition?
- a. Breaker will trip and lockout if pressure Incorrect -
continues to fall.
- b. Breaker will respond to manual trip signals Incorrect -
but fail to respond to automatic trip signals.
- c. Breaker will respond to automatic trip Incorrect -
signals but fail to respond to manual trip signals.
Breaker has lost all tripping capability.
Correct Response
References:
OP 2140 APP A Task Associations 2627330401 Respond to Automatic Operation of Components in the 345KV Switchyard Knowledge and Abilities Associations 262001 K5.02 Breaker control "a SRO 2.6 2.9 Static Simulator Exams: None Last Revised: 06/26/2002 11:54:07 AM by Fagan, Frank N.
2002 SROU Exam Question No. 65 Exam Bank Question No.: 1166 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-02-224 Objective: CRO/SE 2; FND1,2 Question Level: Comprehension Select the correct answer:
The Reactor Building Exhaust Fan trips the standby exhaust fan fails to start and the supply fan fails to trip.
Predict the response of the Reactor Building to this condition.
- a. The personnel access doors which will Incorrect - Personnel access doors are blow open during an overpressure designed to stay closed to maintain condition.
secondary containment integrity and are not designed to provide overpressure protection.
- b. The building is designed for this condition. Incorrect -
- c. SBGT initiates and maintains a negative Incorrect -SBGT will not initiate pressure.
automatically.
d The blowout panels in the refuel floor Correct Response walls blow out.
References:
FSAR Ch. 5.3 Must integrate the following:
- An overpressure condition will occur
- Press > Blowout Panels setpoint of 0.5 psig Task Associations Tak uber T~k~Title 0
2007260501 Respond to Natural Phenomena Knowledge and Abilities Associations 290001 K4.02 Protection against overpressurization: Plant-System 3.4 3.5 Static Simulator Exams: None Last Revised: 07/01/2002 8:19:08 AM by Fagan, Frank N.
2002 SROU Exam Question No. 66 Exam Bank Question No.: 1409 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-611 Objective: 2 Question Level: Comprehension Select the correct answer:
EOP-4, Secondary Containment Control, provides the following direction:
IF Reactor Building HVAC isolates AND Reactor Building vent exhaust is less than 14 mr/hr THEN restart Reactor Building HVAC defeating interlocks (Appendix AA).
Appendix AA is implemented and RB Ventilation is restored. Predict the response to vent exhaust reading of 30 mr/hr and the status of secondary containment pressure.
= swrDtaor Justific,2tion, I
- a. RB HVAC will trip and isolate, secondary Correct Response - Appendix AA does not containment will remain negative.
bypass vent rad monitor isolation. SBGT will start and maintain secondary containment
containment will remain positive.
isolation bypassed, secondary containment will remain negative.
isolation bypassed, secondary containment will remain positive.
References:
EOP-4 Must integrate the following:
- Appendix AA does not bypass rad isolation
- 30 mr/hr exceeds rad isolation
- SBGT maintains negative environment Task Associations MM }
22BERM s
j6le 7 2
2887210401 Respond to a Loss of Reactor Building Ventilation 3105010502/03 Direct Response to Secondary Containment Unexpected area Temperature Above Max Normal Operating Temperature 3105020502/03 Direct the Response to Reactor Building Ventilation Exhaust Radiation Level Above 14 MR/HR Knowledge and Abilities Associations 290001 A2.04 High airborne radiation O.,W 3.4 3.7 Static Simulator Exams: None Last Revised: 07/09/2002 2:54:31 PM by Fagan, Frank N.
2002 SROU Exam Question No. 67 Exam Bank Question No.: 5591 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: SRO 4 Question Level: Comprehension Select the correct answer:
The plant is in an ATWS at 40% power and EOP 2 has been entered. The crew is implementing Appendix G, "Manually Insert Individual Control Rods:, but is unable to bypass the RWM because of a mechanical problem with the keylock switch.
Predict the effect this will have on future rod motion.
' hserPIsfr j3 ui On
- a. Rod motion will be permitted without Incorrect -
interruption.
- b. Rod motion will be blocked immediately.
Incorrect -
- c. Rod motion will continue as the Rapid Incorrect -
Shutdown Sequence is used during Appendix G.
- d. Rod motion will be blocked when reactor Correct Response power is less than 20% power.
References:
K/A 201001 Must integrate the following:
At less than 20% power the RWM enforces rod blocks. These blocks only affect the directional control valves on the HCUs. Scram venting and cooling water pressure do not go through the directional control valves.
Task Associations 3101010502/03 Direct Rod Insertion JAW EOP-2 Knowledge and Abilities Associations 201001 2.2.33 Knowledge of procedures and limitations involved in initial core loading (CFR 43.6) 2.2 2.9 Static Simulator Exams: None Last Revised: 07/01/2002 10:3 8:48 AM by Fagan, Frank N.
2002 SROU Exam Question No. 68 Exam Bank Question No.: 709 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-02-201 Objective: CRO lh, 3; FND 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Select the condition which will cause the full core display DRIFT light to illuminate.
- a. When driving in a rod using Emergency IN Incorrect -
- b. Scramming a rod from 9-16 Correct Response
- c. Driving a rod in and Rod Sequence Timer Incorrect -
Stalls
- d. While driving out a rod using notch Incorrect -
override
References:
None Task Associations
~Ts ubr>akT Tk m
o MM, I 2010050401 Respond to Rod Drift Alarm Knowledge and Abilities Associations Sy~ena K/A~o.
ta~IBM, 214000 K5.01 Reed switches Static Simulator Exams: None Last Revised: 07/09/2002 2:54:49 PM by Fagan, Frank N.
2.7 2.8
2002 SROU Exam Question No. 69 Exam Bank Question No.: 3470 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- RHR Loop B (pump D) is in torus cooling
- Indicated flow is 5800 gpm
- The minimum flow valve has just failed open due to a short Actual total flow to the torus is expected to and total cooling to the torus is expected to ASSUME NO OPERATOR ACTIONS
- a. decrease; remain the same Incorrect -
- b. decrease; decrease Incorrect -
- c. remain the same; remain the same Incorrect -
& remain the same; decrease Correct Response
References:
Drawing G-191172 OP 2124 Must integrate the following:
The minimum flow valve comes before the heat exchanger and thus decreases available cooling flow but returns flow to the torus and thus doesn't change total flow.
Task Associations 2057190101 Startup the RHR System in the Torus Cooling Mode Knowledge and Abilities Associations 219000 K4.05 Pump minimum flow protection 30 3.SRO 3.0 3.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:55:01 PM by Fagan, Frank N.
2002 SROU Exam Question No. 70 Exam Bank Question No.: 3750 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-02-224 Objective: SRO 1 (LOT-00-308)
Question Level: Comprehension Select the correct answer:
Which of the below would require the immediate suspension of fuel handling activities?
AOhS~w 4itcor Jasiftioiii p.as09gt.68ig;j
- a. The loss of one train of SBGT for greater Incorrect - The loss of one SBGT would than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> restrict fuel movement only after 7 days.
(TS 3.7.B.3.b)
- b. The loss of one power supply to Reactor Incorrect - The loss of a power supply to Building Exhaust radiation monitor Rx Bldg Vent Rad monitor will cause a GP 3 isolation. This will not restrict fuel handling activities.
- c. Loss of both Reactor Building exhaust fans Incorrect - The loss of both Rx Bldg fans due to a spurious Group 3 isolation would result in the isolation of HVAC 9, 10, 11, 12. Not a restriction on fuel handling activities.
- d. Both Railroad door airlock gaskets being Correct Response-Both RR airlock declared inoperable gaskets being declared inoperable would result in a loss of secondary containment which would result in the immediate
}cessation of fuel handling activities.
References:
TS 3.7.C is a required reference for this question.
Must integrate the following:
The Railroad doors are part of secondary containment and are required for operability of secondary containment. In turn the seals are required for the doors to be operable. A loss of seals thus causes a loss of secondary containment. With secondary containment lost, all fuel movements must stop.
Task Associations 2237660204 Perform Reactor Building Railroad Airlock Air System Leakage Test 2617040204 Perform Secondary Containment Capacity Test Knowledge and Abilities Associations 234000 2.1.11 Knowledge of less than one hour technical specification action statements for systems (CFR 43.2, 45.13) 3.0 3.8 Static Simulator Exams: None Last Revised: 07/09/2002 2:55:13 PM by Fagan, Frank N.
2002 SROU Exam Question No. 71 Exam Bank Question No.: 5578 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
The plant is at normal 100% power operations. RFP "C" is tagged out for maintenance but all other equipment is operable. Which of the following describes the appropriate immediate actions if a loss of Bus 1 were to occur?
Ya Insert a Manual Scram Correct Response -
- b. Close RR "A" Pump Discharge Valve RV-Incorrect -
53A
- c. Reduce "B" Recirc speed to 70%
Incorrect -
- d. Initiate stability monitoring Incorrect -
References:
OT 3113 Must integrate the following:
Loss of Bus 1 causes a loss of RFP A & B. RFP C is tagged out and does not auto start. OT 3113 requires a scram as an immediate action. Other choices are not immediate actions.
Task Associations
- g?
go.
E,,
g
.0l alwlaRON 2000270501 Respond to a Loss of Feedwater 3440370302/03 Analyze Indications to Determine that an Off Normal Plant Event is in Progress Knowledge and Abilities Associations System L
oA N
ssfAt
. ec alo 259001 A2.06 Loss of A.C. electrical power R0aw Sko^Baa; u 3.2 3.2 Static Simulator Exams: None Last Revised: 06/27/2002 10:14:08 AM by Fagan, Frank N.
2002 SROU Exam Question No. 72 Exam Bank Question No.: 3562 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-259 Objective: CR0 5f Question Level: Comprehension Select the correct answer:
A failure to scram has occurred and the crew is taking actions per EOP-2, ATWS RPV control.
Reactor water level has been reduced to less than 90" using OE 3107, appendix GG, Terminate and Prevent. The master feedwater level controller and both individual feedwater regulating valve controllers were left in BALANCE.
What is the expected position of the feedwater regulating valves (FW-12A/B) in this condition?
LEI J r/pisfrat lustf ition
W I
- a. Oscillating between full open and full shut Incorrect - Level below 127" is the as a result of steam pressure fluctuations.
dominant effect b
Open as a result of feed flow being Correct Response terminated and prevented.
- c. Locked in mid position due to loss of Incorrect -
signal while terminated and prevented.
References:
OE 3107 app GG Must integrate the following:
Terminate and prevent closes the blocking valves. The FRVs will not have flow through them but will still respond as if they controlled flow. With level normally set at 160" there is a 70" difference between setpoint and actual level. Additionally, the controller would still be in 3 element control and the steam flow to feed flow mismatch would be 100%. All these would drive the FRVs open.
Task Associations 2000310501 Respond to Low Reactor Water Level Knowledge and Abilities Associations
_ysteri W N 9ame 259001 A3.07 FWRV position 3SRO.
1~3.2 3.2 Static Simulator Exams: None Last Revised: 07/09/2002 2:55:30 PM by Fagan, Frank N.
2002 SROU Exam Question No. 73 Exam Bank Question No.: 5579 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-612 Objective: A.3 Question Level: Comprehension Select the correct answer:
RCIC is operating to make up water to the vessel when a loss of DC-2 occurs. What is the RCIC response?
- a. RCIC isolation logic activates, RC-15 Incorrect -
closes
- b. RCIC controller fails low, injection ceases Incorrect -
RCIC continues to inject, all RCIC trips Correct Response are lost except overspeed and low oil pressure
- d. RCIC Turbine trips on overspeed Incorrect -
References:
Must integrate the following:
- DC-2 supplies RCIC valves and trip logic
- RCIC valves are motor operated
- The RCIC controller is from vital AC
- Oil pressure and overspeed trips are mechanical Task Associations T as k
Nmbe Task Title^
M 2177030101 Operate RCIC System from RCIC Alternate Shutdown Panel CP-82-1 Knowledge and Abilities Associations 263000 K3.03 Systems with D.C. components (i.e. valves, motors, solenoids, etc.)
Static Simulator Exams: None Last Revised: 07/01/2002 9:41:39 AM by Fagan, Frank N.
3.4 3.8
2002 SROU Exam Question No. 74 Exam Bank Question No.: 3153 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-271 Objective: SCRO1,2 SE 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
WHICH ONE (1) of the following actions is required if BOTH of the Plant Stack radiation monitors, RM-17-156/157, fail DOWNSCALE?
seta~ tor K
i
- " s A
- a. Releases may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Incorrect -
provided the AOG system is not bypassed AND the AOG system noble gas activity monitor is operable.
II, Releases may continue provided that grab Correct Response 3
samples are taken once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the samples are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. Releases may continue for 30 days Incorrect -
provided the AOG system is not bypassed AND the AOG system noble gas activity monitor is operable.
- d. Releases may continue for up to 7 days Incorrect -
provided that grab samples are taken once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the samples are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and these samples indicate that releases remain below.16 Ci/sec and boundary doses remain below 500 mRem/yr whole body and 3000 mRem/year skin.
References:
TS Table 3.9.2, Note 2 Task Associations 3410320302/03 Evaluate Plant System Performance and Coordinate Appropriate Actions per Technical Specifications in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations System K/A 1 l"M I
271000 A4.05 Station radioactive release rate 3.2 3.9 Static Simulator Exams: None Last Revised: 07/09/2002 2:55:48 PM by Fagan, Frank N.
2002 SROU Exam Question No. 75 Exam Bank Question No.: 3914 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-273 Objective: CRO 2b Question Level: Comprehension Select the correct answer:
Given the following conditions:
- The plant is operating at 100% power
- The keylock bypass switch for "AOG Inlet to Final Delay Pipe Rad Monitor," RAN-OG-3128, is in BYPASS
- RAN-OG-3127 has lost power and failed downscale
- Both "AOG Start-up Bypass Valves," AOG-145/146, are closed The Main Stack Isolation valve (FCV-1 1) will:
- a. not isolate with RAN-OG-3128 in Incorrect -
BYPASS
- b. begin to isolate in 2 minutes.
Incorrect -
begin to isolate in 30 minutes.
Correct Response
- d. begin to isolate in 45 minutes.
Incorrect -
References:
OP 2150, Advanced Off Gas System and Air Evacuation Equipment Must integrate the following:
Only one monitor is required for an isolation. A failed downscale monitor is an isolation signal.
If the bypass valves were open a 2 minute timer would activate. However, if the bypass valves are closed, a 30 minute timer activates.
Task Associations 2737060101 Respond to Automatic Actions from Local Monitors Knowledge and Abilities Associations StOKAO.M Ninent SPI 272000 K2.03 Stack gas radiation monitoring system 2.5 2.8 Static Simulator Exams: None Last Revised: 07/09/2002 2:56:00 PM by Fagan, Frank N.
2002 SROU Exam Question No. 76 Exam Bank Question No.: 3590 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-272 Objective: CRO 2; SCRO 2; SE 2; AO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The ARM DNSCL and the TURBINE BLDG RAD HI annunciators have just alarmed. ARM
- 24, TURBINE BLDG TURBINE DECK, has both its upscale and downscale lights energized.
No other ARM's are alarming. This situation indicates that:
- a. the installed bug source is exposed.
Incorrect -
- b. the indicator/trip unit has been placed to Incorrect -
ZERO.
there was a momentary loss of power to Correct Response the indicator/trip unit.
- d. the detector has lost argon gas pressure.
Incorrect -
References:
OP 2135 Task Associations 2727150401 Rcespond to ARM Alarms Knowledge and Abilities Associations System
}N.
ttm Nt I
272000 K6.03 A.C. power 2.8 3.0 Static Simulator Exams: None Last Revised: 07/09/2002 2:56:16 PM by Fagan, Frank N.
2002 SROU Exam Question No. 77 Exam Bank Question No.: 5590 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-286 Objective: CRO 2d Question Level: Fundamental Knowledge/Memory Select the correct answer:
A Control Room fire panel alarm for the Hydrogen shed and a visual report of a fire in the Hydrogen shed are received. Upon Shift Supervisor instructions, manual spray is initiated from which of the following locations?
wERDI
^INusuttong Remote pull box outside of Control Room Correct Response
- b. Remote pull box inside of Control Room Incorrect -
- c. Remote pull box outside South wall of new Incorrect -
warehouse
- d. Remote pull box inside South wall of new Incorrect -
warehouse
References:
None Task Associations 2867290401 Respond to Pyrotronics Panel Alarms 3440140302/03 Coordinate Response to a Fire Emergency Knowledge and Abilities Associations 286000 K1.05 Main generator hydrogen system: Plant-Specific RO SKO 3.1 3.1 Static Simulator Exams: None Last Revised: 06/28/2002 9:02:56 AM by Fagan, Frank N.
2002 SROU Exam Question No. 78 Exam Bank Question No.: 3591 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-286 Objective: 2b Question Level: Fundamental Knowledge/Memory Select the correct answer:
The Fire Brigade is fighting a fire in the south warehouse. The Electric Fire Pump started and immediately tripped on overcurrent. The Diesel Fire Pump is running and supplying the fire system with system pressure at 90 psig.
The overcurrent trip of the Electric Fire Pump is reset. Which one of the following describes the system response?
- a. The Electric Fire Pump starts and the Incorrect -
Diesel Fire Pump continues to run.
- b. The Electric Fire Pump starts and the Incorrect -.
Diesel Fire Pump stops.
g The Electric Fire Pump remains in standby Correct Response and the Diesel Fire Pump continues to run.
- d. The Electric Fire Pump remains in standby Incorrect -
and the Diesel Fire Pump stops.
References:
OP 2186 Task Associations 2990090301 Report Abnormal Parameters or Conditions 3447100302/03 Initiate Investigation of Abnormal and Emergency Conditions Knowledge and Abilities Associations 286000 K5.05 Diesel operators 3 N.....
3.0 3.1 Static Simulator Exams: None Last Revised: 07/09/2002 2:56:35 PM by Fagan, Frank N.
2002 SROU Exam Question No. 79 Exam Bank Question No.: 3679 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Control room ventilation is in a normal lineup with Control Room Supply Fan SAC-1A running.
A rupture of the instrument air system occurs. Instrument air header pressure has dropped to 0 psig.
How will control room ventilation respond?
A Afi e
Wistr.c}or IMMIXti'T h"io t1
- a. SAC-lA will trip and its discharge damper Incorrect -
remains open.
l}. SAC-lA will continue to run and its Correct Response discharge damper fails shut.
- c. SAC IA will continue to run and its Incorrect -
discharge damper remains open.
- d. SAC-1A will trip and its discharge damper Incorrect -
fails shut.
References:
ON 3146 1999 NRC RO Exam - Bacala Task Associations 2000130501 Respond to a Loss of Instrument Air Pressure Knowledge and Abilities Associations
§ 21 6,.,.KiM^.' T=.Y t
H e
sSb' M
System IA No Wtgte 290003 A1.04 Control room pressure 2.5 i 2.8l 2.5g 2.8E 1 Static Simulator Exams: None Last Revised: 07/09/2002 2:56:47 PM by Fagan, Frank N.
2002 SROU Exam Question No. 80 Exam Bank Question No.: 1136 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-04-215 Objective: 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The reactor operator has just received a SCRAM on Rx low level and noticed a red light for the TIP system on the mimic on CRP 9-3. This is:
- a. a normal condition since the ball valves are Incorrect -
normally open.
- b. a normal condition since the shear valves Incorrect -
are normally open.
WN an abnormal condition since the ball valves Correct Response should be closed.
- d. an abnormal condition since the shear Incorrect -
valves should be closed.
I
References:
None Task Associations TakN e
Tespnk Til e a
I os 2000 170501 Respond to Containment Isolations Knowledge and Abilities Associations HI e x
/A N.
L
,em..
215001 K6.04 Primary containment isolation system: Mark-I&II (Not-BWR1) 3.1 3.4 Static Simulator Exams: None Last Revised: 07/09/2002 2:56:59 PM by Fagan, Frank N.
2002 SROU Exam Question No. 81 Exam Bank Question No.: 5581 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-233 Objective: CRO IE Question Level: Comprehension Select the correct answer:
A seismic event has caused a loss of the Vernon Dam. For the next 7 days, what systems are used for cooling the fuel pool?
00%
wR /Dis`
- ctor,
~
usti
- a. RBCCW through the Normal Fuel Pool Incorrect -
Cooling System
- b. RBCCW through the Standby Fuel Pool Incorrect -
Cooling System
- c. R-HRSW through the Normal Fuel Pool Incorrect -
Cooling System X RHRSW through the Standby Fuel Pool Correct Response Cooling System
References:
OP 2179 Must integrate the following: Loss of the Vernon Dam means river water is lost, results in loss of SW and loss of RBCCW. RHRSW available through suction from deep basin and can supply SDC and FPC together.
Task Associations Ta~~Nbe tl Tas T
.l p
7^^i 27 1.80 P
th SFP System
.i Orion 2337180104 Place the SFPC System in Operation Knowledge and Abilities Associations 233000 K4.07 Supplemental heat removal capability 2.7
.SR9 2.7 2.9~
Static Simulator Exams: None Last Revised: 07/01/2002 8:15:29 AM by Fagan, Frank N.
2002 SROU Exam Question No. 82 Exam Bank Question No.: 3172 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO lb Question Level: Fundamental Knowledge/Memory Select the correct answer.
Electrical Maintenance desires to deenergize the DC-1 power supplies to the MSIVs for troubleshooting.
WHICH ONE (1) of the following would be the effect of a loss of DC on the MSIVs?
- a. All 4 inboard MSIVs will drift closed over Incorrect -
the next 5 minutes.
- b. All MSIVs will close in 3-5 seconds Incorrect -
W All MSIVs will operate normally Correct Response
- d. All 4 outboard MSIVs will drift closed Incorrect -
over the next 5 minutes.
References:
K/A 239001 Task Associations 2390030101 Operate the Main Steam Isolation Valves Knowledge and Abilities Associations System
.KtA~o.tat"iei 239001 2.2.17 Knowledge of the process for managing maintenance activities during power operations (CFR 43.5, 45.13) 2.3 3.5 Static Simulator Exams: None Last Revised: 07/09/2002 2:57:17 PM by Fagan, Frank N.
2002 SROU Exam Question No. 83 Exam Bank Question No.: 5597 Revision: 6 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-256 Objective: CRO lo Question Level: Comprehension Select the correct answer:
A plant startup is underway. The Turbine/Generator has just been synched to the grid. The Generator is loaded and reactor power is 15%.
If a Turbine trip were to occur the reactor would valve would and condensate quench spray
- a.
scram, open Incorrect -
- b. scram, remain closed Incorrect -
- c. remain operating, open Incorrect -
- d. remain operating, remain closed Correct Response
References:
OP 0105 Must integrate the following: A turbine trip causes a C.V. fast closure. A fast closure scrams the reactor when >= 30% power. The closure of the CVs will cause the BVs to open. Each BV can pass 10% steam flow and are staged. Only #1 and #2 BVs open and quench spray does not open until #5 BV opens. #1-#4 BVs discharge under the water and won't affect vacuum.
Task Associations 273WN01 Fl Operting I 2997270301 Follow Operating Instutons and Procedures Knowledge and Abilities Associations SystIm K/A7N A,S enl~
Mtz 256000 A1.10 Condenser vacuum 3.1 3.1 Static Simulator Exams: None Last Revised: 07/01/2002 3:56:37 PM by Fagan, Frank N.
2002 SROU Exam Question No. 84 Exam Bank Question No.: 5593 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-262 Objective: SRO 1 Question Level: Comprehension Select the correct answer:
While operating at 95% power, the unit auxiliary transformer and the 4160 volt tie line to Vernon Hydroelectric Station become INOPERABLE. WHICH ONE of the following describes the maximum length of time allowed before a Tech Spec required action must be taken?
N swr~
Dlsta4Qt;~.
g i
h 0i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Correct Response
- b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Incorrect -
- c. 7 days Incorrect -
- d. Indefinitely Incorrect -
References:
TS 4.10.B.3.a Must integrate the following: the aux transformer is an offsite power source and the Vernon tie line is not (for the purposes of Tech Specs). The loss of one off-site source requires the verification of the other source (plus other components).
Task Associations Task!f~e Taki~
forMEN o^WM.
W
- HIM, ji g
MMSS.T.. Sw 2627330401 Respond to Automatic Operation of Components in the 345KV Switchyard 3410320302/03 Evaluate Plant System Performance and Coordinate Appropriate Actions per Technical Specifications in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations a
kg t deS 0~
g' "M M201 0
2.1.11 Knowledge of less than one hour technical specification action statements for systems (CFR 43.2, 45.13) 3.0 3.8 Static Simulator Exams: None Last Revised: 07/09/2002 2:57:37 PM by Fagan, Frank N.
2002 SROU Exam Question No. 85 Exam Bank Question No.: 1795 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-264 Objective: SRO lb Question Level: Comprehension Select the correct answer:
The plant is at 100% power. The "A" RHR pump has been inoperable for the past three (3) days.
The "B" Diesel Generator has just failed its monthly surveillance.
Determine which one of the following statements describes the most limiting conditions for operation imposed by the situation outlined above?
Anwertt
'Wisn 1cMM1113/4 KENNtfi ationW
- a. The reactor can continue operations for four (4) Incorrect -
days, then must be placed in COLD SHUTDOWN in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. The reactor can continue operations for seven Incorrect -
(7) days, then must be placed in COLD SHUTDOWN in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
f A reactor shutdown shall be initiated, and the Correct Response reactor shall be in COLD SHUTDOWN in 24 E hours.
- d. The reactor can continue operations for the next Incorrect -
seven (7) days, provided at least one off-site transmission line, one startup transformer, and the Vernon line remain operable.
References:
T.S. 3.5.H Must integrate the following:
The "A" RHR Pump is supplied by Bus 4. Bus 4 is supplied by the "A" DG. Tech Specs requires the associated LPCI/Cont Spray systems to be operable.
Task Associations 34 10320302/03 Evaluate Plant System Performance and Coordinate Appropriate Actions per Technical Specifications in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations 0
2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for Technical Specifications (CFR 43.2, 43.3, 45.3) 3.4 4.0 Static Simulator Exams: None Last Revised: 07/01/2002 1:22:30 PM by Fagan, Frank N.
2002 SROU Exam Question No. 86 Exam Bank Question No.: 3720 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-201 Objective: 5 Question Level: Comprehension Select the correct answer:
The 'A' CRD pump is operating normally and the flow control valve is in AUTO. Which of the following best describes the changes in CRD system if controller malfunction causes the Flow Control Valve to fail closed?
- a. Charging water pressure and drive water Incorrect -
pressure increase.
- b. Charging water pressure and drive water Incorrect -
pressure decrease.
- c. Drive water pressure and cooling water Incorrect -
pressure increase.
d Drive water pressure and cooling water Correct Response pressure decrease.
References:
Must integrate the following:
- Water and drive water come downstream of the FCV
- Both CW and DW pressures are manually controlled
- A change in total flow affects pressure Task Associations 2010090101 Position Control Rods as Directed by SS at Power Knowledge and Abilities Associations 0
2.1.28 Knowledge of the purpose and function of major system components and controls (CFR 41.7)
Static Simulator Exams: None Last Revised: 07/09/2002 2:57:56 PM by Fagan, Frank N.
3.m 3.2 3.3
2002 SROU Exam Question No. 87 Exam Bank Question No.: 3853 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-400 Objective: CRO 9 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which of the following shall be documented on a Lineup Deviation Form?
The "A" RHR Heat Exchanger Inlet Valve (RHR-23A) has been repositioned:
. as required and documented by a Caution Correct Response Tagging Order.
- b. as required and directed by a surveillance Incorrect -
test.
- c. as required and documented by a White Incorrect -
Tagging Order.
- d. by an AO who is standing by to return the Incorrect -
valve to its original position in accordance with the system operating procedure.
References:
AP 0155, Current System Valve and Breaker Lineup and Identification Used in LOI 2000 RO Audit Exam (8/00) and 1999 NRC RO Exam Task Associations 2050010101 Perform Lineups of the Residual Heat Removal System Knowledge and Abilities Associations Syste' K/ASF~l.'T.S No.0' Stat nei4i RO 0
2.1.29 Knowledge of how to conduct and verify valve lineups 3.4 3.3 (CFR 41.10, 45.1, 45.12)
Static Simulator Exams: None Last Revised: 07/09/2002 2:58:08 PM by Fagan, Frank N.
2002 SROU Exam Question No. 88 Exam Bank Question No.: 5555 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-300 Objective: CRO 3; SCRO 2, 6 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A coupling check is performed whenever a rod is initially withdrawn to position 48. Which one of the following is an indication of an uncoupled rod during this check?
CI If flca^K" 11 1
- a. The 48 indication disappears and the rod Correct Response: OP 0105
'2 display window goes dark.
- b. The 48 indication disappears and the rod Incorrect - Window turns green when rod display window goes to double red dash.
is full in.
- c. The 48 indication flashes and the rod Incorrect - The 48 will never flash, and the display window goes to double red dash.
window turns green when full in.
- d. The 48 indication flashes and the rod Incorrect - The 48 never flashes.
display goes dark.
References:
OP 0105 Task Associations
.1;5impmi
'mm, MEM9 10 Mgtrwg HERM 2010060101 Operate Control Rods Using Notch Override 2010060201 Conduct Control Rod Coupling Integrity Test Knowledge and Abilities Associations 0
2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation (CFR 45.2, 45.6) 3.9 4.0 Static Simulator Exams: None Last Revised: 07/09/2002 2:58:27 PM by Fagan, Frank N.
2002 SROU Exam Question No. 89 Exam Bank Question No.: 3856 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-308 Objective: CRO 3,5 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which of the following combinations of reactor power and pressure indicate violation of a Safety Limit?
Ans
_r/Dfsfradfifiia ii
- a. Reactor power 38%
Incorrect - allowed to exceed 25% power Reactor pressure 850 psig when greater than 800 psia (785.3 psig).
- b. Reactor power 30%
Incorrect - allowed to exceed 25% power Reactor pressure 820 psig when greater than 800 psia (785.3 psig).
Reactor power 28%
Correct Response Reactor pressure 780 psig
- d. Reactor power 20%
Incorrect - can not exceed 25% power if Reactor pressure 750 psig less than 800 psia (785.3 psig)
References:
VY Tech Specs Used in LOI 2000 RO Audit Exam (8/00) and 1999 NRC RO Exam Task Associations 2990150301 Apply Tech Spec Requirements Knowledge and Abilities Associations 0
2.2.22 Knowledge of limiting conditions for operations and safety 3.4 4.1 limits (CFR 43.2, 45.2)
Static Simulator Exams: None Last Revised: 07/01/2002 10:49:39 AM by Fagan, Frank N.
2002 SROU Exam Question No. 90 Exam Bank Question No.: 146 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-239 Objective: SRO 1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
An MSIV surveillance results in a full closure time for MS-80A of 2.8 seconds.
Which one of the following is correct in regards to this time?
- a. The time is acceptable since it is faster Incorrect -
than required to limit offsite release.
- b. The time is unacceptable since it is too Incorrect -
slow to limit offsite release.
- c. The time is acceptable since it is slow Incorrect -
enough to limit the pressure rise on a closure of all MSIVs.
The time is unacceptable since it is too fast Correct Response to limit the pressure rise on a closure of all MSIVs.
References:
FSAR Chapter 14 Tech Spec 3.7.1.2 Task Associations 2007200501 Respond to Reactor Instability 2390030101 Operate the Main Steam Isolation Valves Knowledge and Abilities Associations 0
2.2.25 Knowledge of bases in technical specifications for limiting 2.5 conditioned for operations and safety limits (CFR 43.2)
Static Simulator Exams: None Last Revised: 07/09/2002 2:58:46 PM by Fagan, Frank N.
3.7
2002 SROU Exam Question No. 91 Exam Bank Question No.: 3587 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-234 Objective: CRO 1 Question Level: Comprehension Select the correct answer:
The plant is in a refueling outage with the mode switch in refuel and all rods inserted. The refuel bridge crew has used the grapple to pick up a fuel bundle. They start to move towards the core when the control room operator withdraws a control rod. When the bridge reaches the core area:
eNWO/L I
Ah d atio..
the bridge stops and a hoist raise block is Correct Response generated.
- b. the bridge stops and a hoist lower block is Incorrect -
generated.
- c. the bridge continues but a hoist raise block Incorrect -
is generated.
- d. the bridge continues and the hoists remain Incorrect -
References:
Justification: Higher Level The conditions for a platform travel block and a hoist block coincide in this case with the conditions of: any grapple/hoist loaded, not all rods in and platform near/over the core. The grapple is loaded with the weight of the fuel bundle. The platform travel stops since it is moving towards the core. If the platform was moving away from the core then travel would continue.
Task Associations 2347110201 Perform Functional Test of Refueling Interlocks Knowledge and Abilities Associations System K/A No. Statement 3
3
<2 I 0
2.2.27 Knowledge of the refueling process (CFR 43.6, 45.13) 2.6 3.5 Static Simulator Exams: None Last Revised: 07/09/2002 2:58:56 PM by Fagan, Frank N.
2002 SROU Exam Question No. 92 Exam Bank Question No.: 3852 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-402 Objective: SCRO 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A Temporary Modification (TM) has been approved and installed on a plant system. Eight weeks later, it has been determined that changes to the modification are needed.
Which of the following describes how this change shall be accomplished?
- a. The current TM shall be restored Incorrect -
(removed) and a new TM incorporating the changes shall be approved and installed.
After determining the level of the required Correct Response change (minor or major), the current TM shall be modified.
- c. The current TM shall be restored Incorrect -
(removed) and a Minor Modification incorporating the changes shall be approved and installed.
- d. After determining the level of the required Incorrect -
change, an Vermont Yankee Design Change (VYDC) shall be approved and initiated.
References:
AP 0020, Control of Temporary and Minor Modifications Task Associations 3410110302/03 Approve Temporary Modifications Knowledge and Abilities Associations 0
2.2.11 Knowledge of the process for controlling temporary changes (CFR 41.10, 43.3, 45.13) 2.5 3.4 Static Simulator Exams: None Last Revised: 06/26/2002 7:50:49 PM by Fagan, Frank N.
2002 SROU Exam Question No. 93 Exam Bank Question No.: 3336 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-404 Objective: SCRO 16 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which of the following describes the personnel frisking requirements while working in a Zone 3 Hot Particle Area?
- a. Personnel working in the area must Incorrect -
perform a frisk every half hour and may continue work indefinitely if survey readings are satisfactory.
- b. Personnel working in the area must Incorrect -
perform a frisk at least every hour and may continue working indefinitely if survey readings are satisfactory.
Personnel working in the area must Correct Response - Actions in AP 0517 perform a frisk after one hour and must I M=exit after two hours and perform a whole body frisk in the nearest PCM-1B.
- d. Personnel working in the area must Incorrect -
perform a frisk every two hours and must exit after four hours and perform a whole body frisk in the nearest PCM-1B.
References:
AP 0517 Task Associations TkNiie TkT 2990100301 Apply Radiation and Contamination Safety Procedures Knowledge and Abilities Associations 0
2.3.10 Ability to perform procedures to reduce excessive levels of 2.9 radiation and guard against personnel exposure (CFR 43.4, 45.10)
Static Simulator Exams: None Last Revised: 07/09/2002 2:59:15 PM by Fagan, Frank N.
NW3 3.3
2002 SROU Exam Question No. 94 Exam Bank Question No.: 5595 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-266 Objective: SRO 2 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Per OP 2610, "Liquid Waste Disposal", which one of the following would require the Shift Supervisor's or SCRO's permission to be granted and noted on the Discharge Permit?
- a. Routine House Heating Boiler Blowdowns Incorrect -
- b. MUD System Filter Discharges Incorrect -
- c. Continuous Discharge of RWCU Demins Incorrect -
to the Waste Sample Tanks Batch Discharge of Waste Sample Tanks Correct Response to the Condensate Storage Tank
References:
OP 2610 Task Associations R,
Z pia gg RRfig msm0' Z
w Z5_
2.'E v=~
3410120302/03 Approve Radioactive Waste Discharge/Release Permits Knowledge and Abilities Associations E
tM.
A~ u}
rS>i;Er7i4'Wifi i !~;i.} _i290i.:gp0^zpu N:;<.
a is:",ff"A.
H
<-IM 1:.
,5.
-yi I4=E ~g
............ A,
§
" I i}
}Aaemag nU.N 0
2.3.06 Knowledge of the requirements for reviewing and approving release permits (CFR 43.4, 45.10)
R 3SR.1 2.1 3.1 Static Simulator Exams: None Last Revised: 06/28/2002 9:55:37 AM by Fagan, Frank N.
2002 SROU Exam Question No. 95 Exam Bank Question No.: 1772 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-02-400 Objective: SCRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
Which one of the following are responsible for administrative control of the keys to locked high radiation doors?
- ~ ~~~
~
i0u='.nl0
^
- l.
§ l
't e
>W,l 22 g,
l5 l
Shift Supervisor and the Radiation Correct Response Protection Manager
- b. Security Shift Supervisor and Radiation Incorrect - per DP 0161 it is the Shift Protection Manager Supervisor and the Radiation Protection Manager
- c. Security Shift Supervisor and the Senior Incorrect -per DP 0161 it is the Shift RP Technician Supervisor and the Radiation Protection Manager
- d. Shift Supervisor and the Senior RP Incorrect -per DP 0161 it is the Shift Technician Supervisor and the Radiation Protection Manager
References:
DP 0161 Tech. Specs. Paragraph 6.5.B Task Associations 3420090302/03 Approve Radiation Work Permits Knowledge and Abilities Associations A Sy^tEm K/ Nob=
..=.'S.tatemenX 0
2.3.01 Knowledge of 10 CFR 20 and related facility radiation control requirements (CFR 41.12, 43.4, 45.9, 45.10)
ROE, SRO 2.6 3.0 Static Simulator Exams: None Last Revised: 01/16/2002 3:39:16 PM by Fagan, Frank N.
2002 SROU Exam Question No. 96 Exam Bank Question No.: 5588 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-404 Objective: SRO 1 Question Level: Comprehension Select the correct answer:
An AO has a routine plant task that requires him to be in a 50 mr/hr field for 30 minutes. Which one of the following would result in the greatest reduction in total man-rems for this job?
0f 1
=0, "1"
0"11
" 'l if 11ro Ofl 0
f
- a. Use 2 AOs working 15 minutes each Incorrect - 2 AOs would still pick up 25 mr total X Install 2" of lead shielding that reduces Correct Response - 1" reduces total to 12.5 radiation levels by 1/2 for each inch of lead mr; 2nd inch reduces total to 6.25 mr
- c. Install valve reach rods that would allow Incorrect - 25 mr/hr x 0.5 hrs = 12.5 mr the AO to work in a 25 mr/hr field for 30 minutes
- d. Utilize remote operated valves that would Incorrect - 50 mr/hr x 1 hr/60 min x 12 min reduce his stay time to 12 minutes in a 50
= 10 mr mr/hr field
References:
AP 6047 Must integrate the following:
The concepts of time, distance and shielding must be analyzed to determine how each applies in the ability to reduce the total man rems for a job as opposed to an individual.
Task Associations Task NEEii k TitleR
> <m v
fif m
imilif 3410380302/03 Interpret and Ensure Compliance with Plant Administrative Procedures During Normal and off Normal Plant Operations Knowledge and Abilities Associations ISys e m M IN6.
m ng
~MRC E
0 2.3.02 Knowledge of facility ALARA program (CFR 41.12, 43.4, 2.5 45.9, 45.10)
Static Simulator Exams: None Last Revised: 06/28/2002 9:56:46 AM by Fagan, Frank N.
ERO 2.9
2002 SROU Exam Question No. 97 Exam Bank Question No.: 2692 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-626 Objective: CRO 5 Question Level: Comprehension Select the correct answer:
During an RPV-ED, the SRV's failed to open. The SCRO directs the BOP to implement Appendix "CC" RPV Venting via MSIVs.
During the implementation of Appendix "CC", the BOP fails to place the control switches for RV-39 and RV-40 to CLOSE. As a result the Group I SYS 1 and SYS 2 Reset Permissive lights on CRP 9-5 are not lit. The remaining steps involving jumper installation are completed correct.
Will the MSIVs and the MSL Drain Valves open in this condition?
can not be opened.
b: MSIVs can be opened, MSL Drain Valves Correct Response X can be opened.
Valves can be opened.
Valves can not be opened.
References:
EOP-3, OE 3107 Appendix CC Task Associations 2007730501 Perform RPV Venting Via MSIV'S Knowledge and Abilities Associations 0
2.4.08 Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs (CFR 41.10, 43.5, 45.13) 3.0 3.7 Static Simulator Exams: None Last Revised: 07/09/2002 2:59:44 PM by Fagan, Frank N.
2002 SROU Exam Question No. 98 Exam Bank Question No.: 675 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CR0/SE Obj. 1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
The plant has experienced a Recirc Pump trip. The RO reports APRMs are oscillating between 62% and 77% power. Which of the following should be directed?
rDistr
^4=tificdtion i
- a. Increase running Recirc Pump speed Incorrect -
- b. Decrease running Recirc Pump speed Incorrect -
- c. Insert rods per rapid shutdown sequence Incorrect -
cE Insert rods by manual scram Correct Response
References:
OT 3117 Task Associations
.M EM IR RUNm_?. RU M^^
CL D
M'"'
'=
0'$tt 2007200501 Respond to Reactor Instability Knowledge and Abilities Associations 0
2.4.11 Knowledge of abnormal condition procedures (CFR 41.10, 3.4 3.6 43.5, 45-13)
Static Simulator Exams: None Last Revised: 07/01/2002 9:48:38 AM by Fagan, Frank N.
2002 SROU Exam Question No. 99 Exam Bank Question No.: 3865 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-400 Objective: CRO-1 Question Level: Comprehension Select the correct answer:
Given the following conditions:
- The plant is operating at 100% power
- A feedwater level control malfunction has resulted in lowering reactor water level
- Reactor water level has reached +120 inches
- There has been NO response from the Reactor Protection System (RPS)
What are the EXPECTED Control Room Operator actions for these conditions?
Insert a manual scram while concurrently Correct Response informin the Supervisory Control Room X Operator (SCRO) of the actions being taken.
- b. Insert a manual scram only after verifying Incorrect -
the RPS failure using two separate indications.
- c. Inform the Supervisory Control Room Incorrect -
Operator (SCRO) of the condition, and insert a manual scram when directed.
- d. Perform an immediate power reduction to Incorrect -
raise reactor water level to above the scram setpoint as soon as possible.
References:
DP 0166, Operations Standards Used in LOI 2000 RO Audit Exam (8/00) and 1999 NRC RO Exam Task Associations Hi0i1=r//.
2's,S t0lE-E '
':. 2.iW 2997270301 Follow Operating Instructions and Procedures Knowledge and Abilities Associations 0
2.4.15 Knowledge of communication procedures associated with 3.0 EOP implementation (CFR 41.10, 45.13)
Static Simulator Exams: None Last Revised: 07/09/2002 3:00:01 PM by Fagan, Frank N.
3.5
2002 SROU Exam QuestionNo. 100 Exam BankQuestionNo.: 5596 Revision: 1 PointValue: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO 5 Question Level: Fundamental Knowledge/Memory Select the correct answer:
A reactor scram and MSIV isolation have occurred. Torus cooling is in service and the SRVs are being cycled to control reactor pressure. Which one of the following alarms would be unexpected and indicate a problem?
E
.s'igD' raetor,.
3aXiol
- a. Rx Relief/Safety Vlv Temp Hi (3-B-4)
Incorrect - SRV tail pipe temp of 230'F
- 7) activates on pressure
- c. Rx Relief Vlv Open (3-A-1)
Incorrect - 2 of 3 tailpipe pressure switches activate at 40 psig
& Rx Relief Vlv Bellows Leakage (3-B-1)
Correct Response - Crack in bellows allowing it to pressurize. May not open SRV automatically on a high reactor pressure.
References:
Alarm Response Sheets Task Associations itasNun
'n~T~kit"e 2007400501 Control RPV Pressure Using Bypass Valves, HPCI, RCIC, SRVS, RWCU, Steam Line Drains Knowledge and Abilities Associations Syse</
- p.
SStatementA~9 0
2.4.46 Ability to verify that the alarms are consistent with the plant conditions (CFR 43.5, 45.3, 45.12) 3.5 3.6 Static Simulator Exams: None Last Revised: 07/01/2002 10:51:37 AM by Fagan, Frank N.