ML14170B026
| ML14170B026 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/18/2014 |
| From: | NRC/RGN-II/DRMA |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-424/14-301, 50-425/14-301 | |
| Download: ML14170B026 (108) | |
Text
Name:
NRC RO Exam Student Test Start Time:
Stop Time:
List of SRO References 1 19111-C, ECA-1.1 Loss of Emergency Coolant Table in step 7.b Recirculation (page 7 of 49) 2 19111-C, ECA-1.1 Loss of Emergency Coolant Table 1 (page 45 of 49)
Recirculation Figure 1 (page 46 of 49) 3 11840-1, Main Turbine Electro-Hydraulic Control (EHC) System Alignment 4 DWG 1X4DB194, EHC Hydr. Power Unit 5 Core Operating Limits Report, VEGP Unit 1 Cycle 18, Figure 3, Rod Bank Insertion Limits versus % of Rate Thermal Power 6 Plant Computer Data (2 screenshots)
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ROD INSERTION LIMIT MONITOR RoLls-Royce Main Alarms Graphcs Irendsloarsletc Ecint List Print Help Mn Menu I__Grcj Trends Apps Reports System ISPDS RCS Turbine Point Search MODEl SHUTDOWN ROD STUCK ROD OFF TOP
\) j1\LV ROD INSERTION ROD BANK LOW LIMIT SEQUENCE V ALARM 1 NORI4 I_
ROD INSERTION ROD TO BANK LOW LOW LIMIT DEMAND DEVIATION ALARM NORMAL CONTROL BANK D ROD TO ROD WITHDRAWAL DEV TAT ION No RMAL NORMAl..
ROD BANK ROD TO ROD AVG UPDATE STATUS DLV IATION UP DATED VIViI RCS DL Z LOW LOW-LOW LIMIT LIMIT T0403 83.1 T0423 T0443 32.7 T0463 83.1 HOMELPrev]Back]J V MENU U UHISTORYl MODE 1 IPRIM,BACK
__L LV Ready YNO 5imulator CPIJ 5 TTOI 1 WK=007/WIN=O1 SEC LVLO3
P002 ROOMTECHSPECROUNDS Page DESCRIPTION VALUE UNITS CNMT NARROW RANGE PRESS *
- 0.10 PSIG NSCW SUPPLY HEADER TEMP TRAIN A TEMP 7i6 DEC F NSCW SUPPLY HEADER TRAIN B TEMP :67.3 DEG F CNMT LEVEL 2 TEMP 122 DEC F CNMT LEVEL C TEMP 114 DEC F CNMT LEVEL B TEMP 115 DEC F AVERAGE CNMT TEMP 117 DEC F CNMT SOUTH SUMP LEVEL 21.0 INCHES REACTOR CAVITY SUMP LEVEL 21.4 INCHES CNMT NORTH SUMP LEVEL 16.3 INCHES PRI MET TWR 1OM 15 MIN AVE WEND SPEED 2.6 MPH PRI MET TWR 60M 15 MIN AVE WEND SPEED 6.2 MPH PRI MET TWR 1OM 15 MIN AVE WIND DIR 156 DEGREES PRI MET TWR 60H 15 MIN AVE WEND DIR 136 DEGREES PRI MET TOWER 60-1OM 15 MIN AVE DELTA TEMP 0.615 DEC F
1.
Given the following:
- Unit 1 is at 100% reactor power.
Which one of the following completes the following statement?
The Rod Control Logic Cabinet is energized from _(l)_ or _(2)_.
_( 1 )_ _(2)_
A. Vital 125 VDC Panel Vital 120 VAC Panel (1ADI 1) (1AY1A)
B. Vital 125 VDC Panel Regulated 120 VAC Instrument Panel (1AD11) (INYS)
C. lAMGSetviaa Vital 120 VAC Panel 120 VAC transformer (1AY1A)
D. IA MG Set via a Regulated 120 VAC Instrument Panel 120 VAC transformer (INYS)
Page 1 of 75
2.
Initial condition:
- Unit I is at 8% reactor power.
Current condition:
- I NAA de-energizes due to a fault on the bus.
Which one of the following completes the following statement?
When conditions stabilize, _(1)_ flow on lFl-414, RCS Flow Loop 1 will be observed, and the reactor _(2)_ automatically trip due to the event.
_(l)_ _(2)_
A. 113% will B. -113% will NOT C. 6% will D. 6% will NOT Page 2 of 75
3.
Initial conditions:
- Unit I is at 100% reactor power.
- VCT level is 50%.
- VCT makeup control is in automatic.
Current condition:
- VCT level transmitter, 1LT-112, fails high.
Assuming no operator action, which one of the following completes the following statements?
VCT Divert Valve, 1 LV-1 12A, is aligned to the _(1)_.
If actual VCT level lowers to 29%, automatic makeup _(2)_ occur.
(1 )_
A. PRT will B. PRT will NOT C. RHUT will D. RHUT will NOT Page 3 of 75
4.
Initial conditions:
- Unit 1 is in Mode 5 with solid plant conditions.
- RHR Train B is in service aligned to low pressure letdown.
- RHR Train A is in standby.
- CCP A is in service.
Current condition:
- Instrument air header depressurizes due to an air line break.
Which one of the following completes the following statement?
With no operator action, RCS pressure will _(1)_,
and per 18028-C, Loss of Instrument Air, to mitigate the pressure transient, the crew
_(2)_ stop RHR pump B.
_(1) _(2)
A. increase will B. increase will NOT C. decrease will D. decrease will NOT Page 4 of 75
5.
Initial conditions:
- Unit 1 is at 95% reactor power with a power ascension in progress.
- CBD is at 200 steps.
Current conditions:
- ALB1O-D06 ROD DEV is received.
- CBD rod M12 DRPI indicates 109 steps.
- 18003-C, Rod Control System Malfunction, is entered.
- Reactor power has been lowered per 18003-C guidance.
Which one of the following completes the following statement?
Per 18003-C, control rod M12 is considered _(1)_,
and per 18003-C, the reason for the power reduction is to minimize _(2)_ heat rates and power distribution variances.
_(1 )_ _(2)_
A. dropped core B. dropped local C. misaligned core D. misaligned local Page 5 of 75
6.
Initial conditions:
- Unit I is in Mode 6 for refueling.
- RHR pump B is in service.
- RHR pump A is tagged out.
Current conditions:
RHR pump B is stopped to place a fuel assembly in the vicinity of the RCS hot leg nozzle.
- Chemistry requests permission to make a chemical addition to the RCS.
Which one of the following completes the following statement?
Per Tech Spec 3.9.5, Residual Heat Removal (RHR) and Coolant Circulation High -
Water Level, the Chemistry technician _(1)_ allowed to make the chemical addition to the RCS, and per Tech Spec 3.9.5, RHR pump B _(2)_ required to be returned to service no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from being stopped.
(1) _(2)_
A. is is B. is is NOT C. is NOT is D. is NOT is NOT Page 6 of 75
7.
Initial conditions:
- Unit 1 experienced a LOCA.
- 19012-C, Post-LOCA Cooldown and Depressurization, is in progress.
- Both RHR pumps are stopped.
- RCS temperature and pressure are stable.
- Containment pressure is 4.2 psig and slowly lowering.
Current conditions:
- CCP A was stopped three minutes ago per 19012-C.
- SIP B is stopped per 19012-C.
- Subcooling is 29°F and lowering.
Which one of the following completes the following statements?
When CCP A is stopped, RCS subcooling margin will initially _(1)_.
Based on the current conditions, the OATC _(2) required to restart an ECCS pump.
_(1 )_ _(2)_
A. increase is B. increase is NOT C. decrease is D. decrease is NOT Page 7 of 75
8.
At time 0100:
- Unit 1 reactor tripped.
At time 0530:
- Safety Injection occurred.
- All RCPs were stopped.
At time 0730:
- RVLIS Full Range is 73% and stable.
- 19111-C, Loss of Emergency Coolant Recirculation, Step 18b RNO is in progress:
Step 18b RNO. Establish minimum ECCS flow to remove decay heat by performing the following:
- 1) Determine minimum ECCS flow required using the following:
TABLE 1 orFIGURE1.
- 2) Throttle ECCS flow to minimum value.
Which one of the following completes the following statement?
Based on the current conditions, the active fuel (1)_ covered, and the crew is required to throttle ECCS flow to approximately (2)_ per Step 18b RNO.
REFERENCES PROVIDED
_(1)_
A. is 225 gpm B. is 320 gpm C. is NOT 225 gpm D. is NOT 320 gpm Page 8 of 75
9.
Initial conditions:
- Unit I is in Mode 5 with solid plant conditions.
- Pressurizer bubble is being established.
Current conditions:
- A transient results in an RCS pressure spike.
- ALB12-E02 PRZR REL TANK HI PRESS is received.
- ALB12-E03 PRZR REL TANK HI TEMP is received.
Which one of the following completes the following statement?
The RHR pump _(1)_ relief valve lifting caused the PRT high pressure condition, and per 13004-1, Pressurizer Relief Tank Operation, recirculation through the RCDT heat exchanger to lower PRT temperature is expected to take approximately _(2).
_(l) _(2)_
A. discharge 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. discharge 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. suction 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. suction 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Page 9 of 75
10.
Initial condition:
- Unit 1 is operating at 55% reactor power with a plant startup in progress.
Current conditions:
- Both Unit 1 RATs de-energize.
- Both DGs start and re-energize their respective bus.
- No other switchyard components are affected.
Which one of the following completes the following statement?
With no operator action, one minute after the RATs de-energize, the Reactor Trip Breakers will be _(1),
and DRPI _(2)_ be available to check control rod positions.
(1 )_
A. open will B. open will NOT C. closed will D. closed will NOT Page 10 of75
11.
Initial conditions:
- Unit 1 is at 100% reactor power.
- CCW Train A is in service.
- Multiple CCW Train A low pressure and low flow alarms annunciate, then clear.
- No other alarms were received.
Current conditions:
- CCW Train A pressure and flow are stable.
- 18020-C, Loss of Component Cooling Water, is entered.
Which one of the following completes the following statement?
A CCW Train A pump has experienced a _(1)_,
and the standby CCW Train A pump _(2)_ auto start in response to CCW low header pressure.
_(1 )_ _(2)_
A. locked rotor did B. locked rotor did NOT C. sheared shaft did D. sheared shaft did NOT Page 11 of75
12.
Given the following:
- Unit 1 experienced a small break LOCA.
- 19012-C, Post-LOCA Cooldown and Depressurization, is in progress.
- RCS pressure is 1315 psig and stable.
- Containment pressure is 3.5 psig.
Which one of the following completes the following statement?
19012-C requires a minimum SG NR level of _(1)_,
and natural circulation flow _(2)_ used in conjunction with break flow to accomplish decay heat removal.
_(1)_ _(2)_
A. 10% is B. 10% is NOT C. 32% is D. 32% is NOT Page 12 of 75
13.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- PORV-455A starts leaking by.
- OATC observes pressurizer pressure indicating 2205 psig and slowly lowering.
- No operator action has been taken.
Which one of the following completes the following statement?
Based on the current conditions, the pressurizer backup heaters _(1)_ be energized, and if pressure lowers to 2185 psig, both PORV block valves _(2)_ receive a close signal.
_(1 )_ _(2)_
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Page 13 of75
14.
Initial condition:
- Unit 1 is at 100% reactor power.
Current condition:
- 1 NBO1-05, Pressurizer Heater Back-Up Gr-A, breaker trips open.
Which one of the following completes the following statement?
Tech Spec 3.4.9, Pressurizer, requires two groups of pressurizer heaters with _(1 )_
capacity of >150 kW, and Pressurizer Heater Back-Up Gr-A _(2)_ a Tech Spec required group of heaters.
_(1)_ _(2)_
A. a total is B. a total is NOT C. each having a is D. each having a is NOT Page 14 of 75
15.
Initial condition:
- Unit 1 experienced a reactor trip and SI.
Current conditions:
- The OATC aligns ECCS for Cold Leg Recirculation.
- RCS pressure is 1450 psig.
- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.
Which one of the following completes the following statements?
Prior to the LOCA, each RHR pump is aligned for injection into _(1)_ Cold Legs.
Following alignment to Cold Leg Recirculation, SIPs _(2) providing injection flow to the core.
_(1 )_
A. 2 are B. 2 are NOT C. 4 are D. 4 are NOT Page 15 of 75
16.
Initial conditions:
- Unit I is at 50% reactor power.
- RCS pressure is 2235 psig.
- Pressurizer level control is selected to CH 459 I 461.
- All pressurizer heaters are manually energized.
Current condition:
- Pressurizer level transmitter, I LT-461, fails low.
- No operator action has been taken.
Which one of the following completes the following statement?
I LV-460, Letdown Isolation Valve, _(1 )_ close, and the pressurizer backup heaters are _(2)_.
_(1 )_ _(2)_
A. will energized B. will de-energized C. will NOT energized D. will NOT de-energized Page 16 of75
17.
Given the following:
- Unit 1 is at 100% reactor power.
Which one of the following completes the following statement?
The _(1)_ Reactor Trip protects against Departure from Nucleate Boiling (DNB),
and the Trip Setpoint _(2) in response to lowering pressurizer pressure.
_(1 )_ _(2)_
A. OT delta T remains unchanged B. OT delta T decreases C. OP delta T remains unchanged D. OP delta T decreases Page 17of75
18.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- The bistable(s) for Containment Pressure Channel I (1 PT-937) are de-energized.
- No Tech Spec actions have been taken.
Which one of the following completes the following statement?
The minimum number of additional channels required to initiate an actuation signal on High-i is_(i)_,
and the minimum number of additional channels required to initiate an actuation signal on High-3 is _(2)_.
(1 )_ _(2)
A. 1 1 B. 1 2 C. 2 1 D. 2 2 Page 18 of 75
19.
Initial condition:
- Unit 1 is at 100% reactor power and stable.
The following DRPI alarms and indications are observed:
- ALB1O-D05 RPI URGENT ALARM is lit.
- ALB1O-C05 RPI NON URGENT ALARM is lit.
- ALB1 0-E05 ROD AT BOTTOM is lit.
- Control rod H8 Rod Bottom LED is lit.
- Control rod H8 General Warning LED is flashing.
- Data A and Data B Failure LEDs are flashing.
- No other alarms are received.
Which one of the following completes the following statements?
Control rod H8 _(1)_.
Automatic rod motion and manual rod motion _(2)_ inhibited.
_(1 )_ _(2)_
A. dropped are B. dropped are NOT C. did NOT drop are D. did NOT drop are NOT Page 19of75
20.
Initial condition:
- Unit I is at 100% reactor power.
Current conditions:
- A spurious turbine runback occurs and is terminated at 70% reactor power.
- ALBIO-F06 DELTA FLUX DEVIATION is received.
Which one of the following completes the following statement?
Per Tech Spec 3.2.3, Axial Flux Difference (AFD), the AFD is considered outside limits when a minimum of _(1)_ OPERABLE Power Range NI channels indicate outside AFD limits, and based on current conditions, per Tech Spec 3.2.3, further reduction in thermal power
_(2)_ required.
_(1)_ _(2)_
A. 1 is B. I isNOT C. 2 is D. 2 isNOT Page 20 of 75
21.
Initial condition:
- Unit 1 is at 100% reactor power.
Current condition:
- ALBO8-E03 RCP I VIBRATION ALERT is received.
Which one of the following completes the following statement?
Per the applicable Annunciator Response Procedure, the operators are directed to monitor the RCP vibration readings on the _(1)_,
and per 13003-1, Reactor Coolant Pump Operation, the RCP maximum operating limit for frame vibration is _(2) mils.
_(1 )_ _(2)_
A. plant computer 5 B. plant computer 20 C. local vibration monitoring panel 5 D. local vibration monitoring panel 20 Page2l of 75
22.
Initial condition:
- Unit I is at 100% reactor power.
Current condition:
- CVCS makeup capability is lost.
Which one of the following completes the following statements?
As VCT level begins to slowly lower, VCT pressure is _(1). maintained.
If VCT pressure were to lower from 25 to 18 psig, RCP seal #1 leak-off flow rates would _(2)_.
_(1 )_ _(2)_
A. automatically decrease B. automatically increase C. manually decrease D. manually increase Page 22 of 75
23.
Given the following:
- Unit 1 is in Mode 3 following a steam line break in containment.
- Only Train A containment cooling units are available.
- Containment temperature is 241°F and slowly rising.
- Containment pressure is 11 psig and slowly rising.
Which one of the following completes the following statement?
SG NR level instruments on the QMCB will indicate _(1)_ than actual level, and the instrument inaccuracies _(2)_ a direct result of changes in containment pressure.
_(1)_ _(2)_
A. lower are B. lower are NOT C. higher are D. higher are NOT Page 23 of 75
24.
Given the following:
- Unit 1 requires Emergency Boration.
- Shift Supervisor directs Emergency Boration through the BIT flow path.
Which one of the following completes the following statement?
For the selected Emergency Boration flow path, 13009-1, CVCS Reactor Makeup Control System, directs the operator to establish a minimum flow rate to the RCS greater than _(1)_ gpm, and the boron concentration for the source used above is required to be between
_(2)_ ppm.
_(1 )_ _(2)_
A. 30 2400 2600 B. 30 7000 7700 C. 87.5 2400-2600 D. 87.5 7000-7700 Page 24 of 75
25.
Given the following:
- Unit I reactor trip and SI occurred due to a LOCA.
- Containment Spray (CS) actuated.
Which one of the following completes the following statement?
During the ECCS injection phase, CS pumps and ECCS pumps _(1 )_ suction header(s) penetrating the RWST, and the CS pump& sump suction valves _(2)_ automatically open on LO-LO RWST level.
_(1 )_ _(2)_
A. share a common will B. share a common will NOT C. have separate will D. have separate will NOT Page 25 of 75
26.
Given the following:
- An SI occurred and has NOT been reset.
- An LOSP occurs a few minutes later.
- 1AAO2 is powered from DG1A.
- 1BAO3 is powered from DG1B.
While the DGs are operating, an electrical perturbation results in the following:
- DG1A 186A lockout relay energizes (Generator Differential).
- DGI B 186B lockout relay energizes (Phase Overcurrent).
Which one of the following describes the current condition of the Containment Spray discharge valves?
1HV-9001A, Containment Spray Pump A Discharge Isolation, _(1) have power available, and 1 HV-9001 B, Containment Spray Pump B Discharge Isolation, _(2)_ have power available.
_(1 )_ _(2)_
A. does does B. does does NOT C. does NOT does D. does NOT does NOT Page 26 of 75
27.
Initial conditions:
- Unit 1 is at 100% reactor power.
- One group of pressurizer backup heaters is energized in manual.
- Pressurizer pressure control is selected to OH 455 I 456.
Current condition:
- Pressurizer pressure transmitter, 1 PT-455, fails low.
Which one of the following completes the following statement?
In response to the failure, the remaining pressurizer backup heaters will _(1)_,
and the pressurizer spray valve controllers will demand full _(2)_ position.
_(1 )_ _(2)_
A. energize open B. energize closed C. remain off open D. remain off closed Page 27 of 75
28.
Initial conditions:
- Unit 1 is at 100% reactor power.
- Containment Spray pump A is tagged out.
Current conditions:
- Large break LOCA occurs.
- 19010-C, Loss of Reactor or Secondary Coolant, is in progress.
- Containment Spray pump B trips.
- Containment pressure is 22 psig.
- Containment hydrogen concentration is 5.1%.
Which one of the following completes the following statement?
The preferred method for reducing containment hydrogen concentration is _(1)_ the containment atmosphere, and a(n) _(2)_ path entry condition exists for 19251-C, Response to High Containment Pressure.
_(1 )_ _(2)_
A. diluting red B. diluting orange C. purging red D. purging orange Page 28 of 75
29.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- ATWT is in progress.
- The reactor trip and bypass breakers will NOT open locally.
Which one of the following completes the following statement?
Per 19211-C, Response to Nuclear Power Generation I ATWT, the Control Rod Drive MG Set _(1)_ breakers will be opened, and P-4 _(2)_ be generated when the MG set breakers are locally opened.
_(1 )_
A. input will B. input will NOT C. output will D. output will NOT Page 29 of 75
30.
Initial conditions:
- Unit I reactor startup is in progress.
- Critical data is being collected per 12003-C, Reactor Startup (Mode 3 to Mode 2).
Current condition:
- Intermediate Range N35 fails bottom of scale.
Which one of the following completes the following statement?
Based on the current conditions, the SR BLOCK PERMISSIVE P-6 light on the BPLB
_(1) remain lit, and placing the affected channels Level Trip switch in BYPASS per 18002-C, Nuclear Instrumentation System Malfunction, aligns NI _(2)_ power to the SSPS input relay.
_(1)_ _(2)_
A. will control B. will instrument C. will NOT control D. will NOT instrument Page 30 of 75
31.
Given the following:
- Unit 1 is in Mode 6.
- Preparation for fuel movement is in progress in the Fuel Handling Building.
- The following radiation monitors are in service:
- ARE-2532A1B, Fuel Handling Building Effluent Radiogas Monitors
- 1 RE-008, Fuel Handling Building Area Monitor Which one of the following completes the following statement?
ARE-2532A1B (1)_ be monitored and the alarm setpoints adjusted from the SRDC panel, and 1 RE-008 _(2)_ be monitored and the alarm setpoints adjusted from the SRDC panel.
_(1)_ _(2)_
A. can can B. can can NOT C. can NOT can D. can NOT can NOT Page 31 of75
32.
Initial conditions:
- Unit 1 experienced a SGTR.
- 1 9030-C, Steam Generator Tube Rupture, is in progress.
- 1NAA is de-energized due to a bus fault.
- AFW flow to all intact SGs is approximately 50 gpm.
- All intact SG NR levels are approximately 40% and stable.
Current condition:
- Crew is preparing to perform a maximum rate cooldown.
Which one of the following completes the following statements?
Per 19030-C, prior to initiating a maximum rate cooldown, AFW flow to intact SGs
_(1)_ required to be raised.
The cooldown is initiated per Step 17 using _(2)_.
_(1)_ _(2)_
A. is ARVs B. is steam dumps C. is NOT ARVs D. is NOT steam dumps Page 32 of 75
33.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- Unit 1 reactortrips.
- RTB B fails to open.
Which one of the following completes the following statement?
With no operator action, RCS temperature will be controlled at approximately _(1)_
by the _(2)_.
_(1 )_ _(2)
A. 557° F steam dumps B. 557° F ARVs C. 559° F steam dumps D. 559° F ARVs Page 33 of 75
34.
Initial conditions:
- Unit 1 is at 100% reactor power.
- Train A sequencer simulated software sequence test is in progress per 1 3540A-1, Safety Features Sequencer System Train A.
- Containment Coolers #1, 2, 5, and 6 are running in high speed.
Current conditions:
- A steam line rupture occurs on SGs #1 and 2.
- In 3 seconds the following parameter trends occur:
- SG pressures lower from 900 psig to 600 psig.
- Containment pressure has risen to 14 psig.
- Reactor trip, Safety Injection, and Steam Line Isolation occur.
Which one of the following completes the following statement?
The Steam Line Isolation was initiated by _(1)_,
and Train A Containment Coolers will be running in _(2)_ speed.
_(1 )_ _(2)_
A. containment High-2 high B. containment High-2 low C. SG low pressure high D. SG low pressure low Page 34 of 75
35.
Given the following:
- Unit I is at 25% reactor power.
- Power ascension is in progress.
Which one of the following completes the following statement?
As turbine load is increased while maintaining Tavg on program, main steam header pressure will _(1)_,
and the method used to maintain Tavg on program during the power increase that results in the MOST negative MTC is (2)_.
A. (1) decrease (2) control rod withdrawal with boron concentration held constant B. (1) decrease (2) boron concentration reduction with control rod position held constant C. (1) increase (2) control rod withdrawal with boron concentration held constant D. (1) increase (2) boron concentration reduction with control rod position held constant Page 35 of 75
36.
At time 1100:
- Unit 1 is at 11% reactor power.
- The Control Room is evacuated due to a fire per 18038-1, Operation From Remote Shutdown Panels.
- MFP A is tripped prior to exiting the Control Room.
At time 1105:
- Personnel established local control of all components per 18038-1.
- SG NR levels have lowered to 55%.
- Shift Supervisor gives direction to, Verify all AFW pumps running.
Which one of the following completes the following statement?
The MDAFW Pumps _(1)_ require manual start, and the TDAFW Pump _(2)_ require manual start.
_(1 )_ _(2)_
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Page 36 of 75
37.
Given the following:
- 19100-C, Loss of All AC Power, is in progress on Unit 1.
- The crew is performing Step 29, Depressurize intact SGs to 300 psig.
- UO could NOT stop depressurizing SGs at 300 psig.
- All SGs reach 175 psig before the depressurization is stopped.
Which one of the following completes the following statement?
A potential exists for _(1)_ to occur, which could result in immediate _(2)_.
A. (1) nitrogen injection from the accumulators (2) core uncovery B. (1) nitrogen injection from the accumulators (2) disruption of natural circulation flow C. (1) voiding in the reactor vessel (2) core uncovery D. (1) voiding in the reactor vessel (2) disruption of natural circulation flow Page 37 of 75
38.
Initial condition:
- Loss of off-site power has occurred.
Current condition:
- 19002-C, Natural Circulation Cooldown, is in progress.
Which one of the following completes the following statements?
Loop deltaT is expected to _(1) as natural circulation flow is first being established.
The number of available CRDM fans _(2)_ affect the required RCS subcooling that must be maintained during the 19002-C natural circulation cooldown.
_(1 )_ _(2)_
A. rise does B. rise does NOT C. lower does D. lower does NOT Page 38 of 75
39.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- An LOSP occurs.
- 19100-C, Loss of All AC Power, is in progress.
- 1DD1 bus voltage is 103 VDC and lowering.
Which one of the following completes the following statement?
Per 19100-C, 1DDI _(1)_ required to be removed from service at this time, and the reason for removing 1 DD1 from service is to prevent _(2)_.
_(1) _(2)_
A. is battery damage B. is an excessive buildup of hydrogen C. is NOT battery damage D. is NOT an excessive buildup of hydrogen Page 39 of 75
40.
Given the following conditions:
- Unit 1 reactor power is being raised from 30% to 50%.
Which one of the following completes the following statement?
As reactor power increases, the BFRVs will continue to open until _(1)_ reaches 40%, and subsequently the BFRVs will _(2)_.
A. (1) first stage turbine power (2) remain as-is B. (1) first stage turbine power (2) fully close C. (1) steam flow (2) remain as-is D. (1) steam flow (2) fully close Page 40 of 75
41.
Given the following:
- Unit I CVCS mixed bed demin resin transfer is in progress.
- A valve failure causes a liquid release on C level of the Auxiliary Building, which results in airborne radioactivity.
Which one of the following completes the following statement?
The airborne radioactivity release will be monitored by _(1)_,
and the running Auxiliary Building HVAC units (2)_ automatically trip.
A. (1) ARE-0014, Waste Gas Processing System Effluent Monitor (2) will NOT B. (1) 1RE-12442C, Plant Vent Radiogas Particulate (Low Range)
(2) will NOT C. (1) ARE-0014, Waste Gas Processing System Effluent Monitor (2) will D. (1) 1 RE-i 2442C, Plant Vent Radiogas Particulate (Low Range)
(2) will Page 41 of 75
42.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- A reactor trip occurs due to a feedwater transient.
- ALB13-E04 FWI SI OR P14 SG HI-HI LVL is received.
Which one of the following completes the following statements?
The MFPs _(1)_ automatically trip.
In order to open the BFIVs, the reactor trip breakers _(2)_ required to be cycled.
_(1)_ _(2)_
A. do are B. do are NOT C. do NOT are D. do NOT are NOT Page 42 of 75
43.
Radiation monitors are as follows:
- 1 RE-002, Containment Low Range Area Monitor
- 1 RE-003, Containment Low Range Area Monitor
- 1 RE-2565, Containment Vent Monitor Initial conditions:
- Unit 1 is in Mode 6.
- Core offload is in progress.
Current condition:
- ALBO6-EO1 CNMT VENT ISO ACTUATION is received.
Which one of the following completes the following statement?
A high radiation level of 15 mrem/hour has been exceeded on _(1)_,
and the high radiation condition _(2)_ latch in on the SRDC panel.
_(1 )_ _(2)_
A. 1 RE-00211 RE-003 does B. IRE-OO2I1RE-003 does NOT C. 1 RE-2565 does D. 1 RE-2565 does NOT Page 43 of 75
44.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- An electrical fault results in the following indications:
- 1 HV-5106, TDAFW Steam Admission Valve, red and green handswitch lights are out.
- 1 FV-5132 and 5134, MDAFW SGs #2 and 3 Discharge Throttle Valves, red, green, and white lights are out.
Which one of the following completes the following statement?
A loss of Train C (1) power has occurred, and a loss of Train B _(2)_ power has occurred.
_(1 )_ _(2)_
A. 125 VDC 480 VAC B. 125 VDC 125 VDC C. 480 VAC 480 VAC D. 480 VAC 125 VDC Page 44 of 75
45.
Initial conditions:
- Unit 1 is at 100% reactor power
- IAY2A is de-energized.
Current condition:
- Safety Injection is actuated.
Which one of the following completes the following statement?
DGIA_(1)_ automatically start, and the Train A sequencer _(2)_ run the Safety Injection load sequence.
_(1)_ _(2)_
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Page 45 of 75
46.
Initial conditions:
- Unit 1 is at 100% reactor power.
- DG1A is tagged out for maintenance.
- 1CY1A is powered by its alternate supply.
Current condition:
- Unit 1 experiences an LOSP.
Which one of the following completes the following statement?
The alternate supply for 1CYIA is a(n) _(1)_,
and immediately following the LOSP, 1CY1A will be _(2)_.
_(1)_ _(2)_
A. inverter energized B. inverter de-energized C. regulated transformer energized D. regulated transformer de-energized Page 46 of 75
47 Initial condition:
- Unit I is at 100% reactor power.
Current conditions:
- Unit 1 reactor is tripped.
- 19100-C, Loss of All AC Power, is in progress.
Which one of the following completes the following statement?
In order to control the TDAFW discharge valves to SGs #1 and 4 from the main control room, battery _(1)_ power must be conserved, and to minimize battery drain, 1-PDIC-5180A, TDAFW pump speed controller, _(2)_
permitted to be used to control TDAFW flow to the SGs.
_(1 )_ _(2)_
A. IADIB is B. 1AD1B is NOT C. 1CDIB is D. 1CD1B is NOT Page 47 of 75
48.
Given the following:
- Unit 1 is at 100% reactor power.
- DG1A is in its normal standby alignment.
Which one of the following completes the following statement?
Handswitch 1HS.-4414B, DSL GEN 1A UNIT/PARALLEL, was taken to the (1)_
position when placing DGIA in standby alignment, and its associated blue indicating light is _(2)_.
_( 1 )_
A. unit lit B. unit NOT lit C. parallel lit D. parallel NOT lit Page 48 of 75
49.
Initial condition:
- Unit I is at 7% reactor power.
Current condition:
- Instrument air line to IFV-0121, CVCS Charging Flow Control Valve, is severed.
Which one of the following completes the following statement?
With no operator action, seal injection flow to the RCPs will (1)_,
and a reactor trip _(2)_ occur on pressurizer level.
_(1)_ _(2)_
A. increase will B. increase will NOT C. decrease will D. decrease will NOT Page 49 of 75
50.
Given the following:
- Unit 1 is in a refueling outage.
- Core reload is in progress.
- The personnel air lock is being used for access.
- The equipment hatch is open.
- Designated personnel are available to close the equipment hatch and airlock.
Which one of the following completes the following statements?
Per Tech Spec 3.9.4, Containment Penetrations, _(1)_ personnel air lock door(s) must be capable of being closed.
Per Tech Spec 3.9.4, the equipment hatch must be capable of being closed by a minimum of _(2)_ bolts.
_(1 )_ _(2)_
A. 1 4 B. 1 8 C. 2 4 D. 2 8 Page 50 of 75
51.
Initial condition:
- Unit I Waste Gas Decay Tank release is in progress.
Current condition:
- ARE-0014, Waste Gas Processing Effluent Monitor, is in intermediate alarm.
- No operator action has been taken.
Which one of the following completes the following statement?
ARV-0014, Plant Vent Radwaste Gas, isolation valve is_(1)_,
and the position of ARV-0014 can be verified _(2)_.
A. (1) open (2) on the IPC in the Control Room B. (1) open (2) locally on the Gaseous Waste Panel C. (1) closed (2) on the IPC in the Control Room D. (1) closed (2) locally on the Gaseous Waste Panel Page 51 of 75
52.
TR title as follows:
- TR 13.3.6, Fuel Handling Building Post Accident Ventilation Actuation Instrumentation (common system)
Initial conditions:
- Fuel movement is in progress in Unit 1 spent fuel pool.
- ARE-2533A1B, Fuel Handling Building Effluent Radiogas Monitor, is QOS.
- ARE-2532A1B, Fuel Handling Building Effluent Radiogas Monitor, is in service.
Current conditions:
- I RE-008, Fuel Handling Building Area Monitor, detector fails high.
- Chemistry has removed 1 RE-008 from service.
Which one of the following completes the following statement?
The personnel in the SFP area _(1)_ alerted to the failed detector by an audible alarm, and per TR 13.3.6, 1 RE-008 _(2)_ required to be in service for movement of irradiated fuel in the SFP.
_(1 )_ _(2)_
A. were is B. were is NOT C. were NOT is D. were NOT is NOT Page 52 of 75
53.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- IRE-1950, ACCW- Liquid, radiation level trends up and then stabilizes.
- ACCW surge tank level increases slightly and then stabilizes.
Which one of the following completes the following statement?
A _(l) heat exchanger tube leak has occurred, and the ACCW surge tank level stabilized due to an automatic isolation of the flow path due to high _(2)_.
_(1 )_
A. letdown flow B. letdown temperature C. thermal barrier flow D. thermal barrier temperature Page 53 of 75
54.
Initial conditions:
- Unit I is at 100% reactor power.
- ACCW pump #1 is running.
- ACCW pump #2 is in standby.
Current conditions:
- An SI occurred and has been reset.
- 5 minutes later, RAT lA experiences a fault.
- DGIA re-energizes 1AAO2 and completes the load sequence.
Which one of the following completes the following statement?
Based on the given sequence of events, ACCW pump #1 _(1)_ be running, and ACCW pump #2 _(2)_ be running.
_(1 )_ _(2)_
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Page 54 of 75
55.
Initial condition:
- Unit I is at 100% reactor power.
Current condition:
- 18017-C, Abnormal Grid Disturbances / Loss of Grid, Section A for Degraded Grid Conditions, is in progress.
Which one of the following completes the following statement?
Per 18017-C, the DGs are (1)_ to ensure availability, and the Main Generator is operated within the acceptable region of the reactive capability curve to prevent damage to the (2)_ windings.
A. (1) maintained in standby alignment (2) Main Generator B. (1) maintained in standby alignment (2) Reserve Auxiliary Transformer C. (1) started and carrying the 1E buses (2) Main Generator D. (1) started and carrying the I E buses (2) Reserve Auxiliary Transformer Page 55 of 75
56.
Initial conditions:
- Unit 1 is at 100% reactor power.
- Air Compressors #1 and #3 are in service.
Current conditions:
- ALBO1-C06 SERVICE AIR HDR LO PRESS is received.
- 1 P1-9377, Service Air Header Pressure, on the QMCB lowered to 92 psig and is now stable at 105 psig.
- No operator action has been taken.
Which one of the following completes the following statement?
All air compressors in AUTO-PTL _(1)_ currently running, and 1-PV-9375, Service Air Dryer Inlet Isolation Valve, _(2)_ closed.
_(1 )_ _(2)_
A. are is B. are is NOT C. are NOT is D. are NOT is NOT Page 56 of 75
57.
Initial condition:
- Unit I at 100% reactor power.
Current condition:
- The running fire water jockey pump trips.
Which one of the following completes the following statement?
The standby fire water jockey pump _(1)_ automatically start as fire header pressure lowers, and the electric fire pumps automatic start setpoint is _(2)_ psig.
_(1)_ _(2)_
A. will 95 B. will 110 C. will NOT 95 D. will NOT 110 Page 57 of 75
58.
Initial conditions:
- LOCA has occurred on Unit 1.
- 19000-C, Reactor Trip or Safety Injection, is entered.
- Verification of Immediate Operator Actions is complete.
- Containment pressure is 23.8 psig.
Current conditions:
- ALBO6-D06 CNMT SPRAY ACTUATION is NOT lit.
- ALB06-E06 CNMT ISO PHASE A ACTUATION is NOT lit.
Which one of the following completes the following statement?
The first required action in 19000-C to be performed by the crew is to actuate _(1)_,
and this action will be taken using _(2)_ direction.
_(l )_ _(2)_
A. CIA Foldout Page B. CIA OATC Initial Actions C. Containment Spray Foldout Page D. Containment Spray OATC Initial Actions Page 58 of 75
Given the following:
- A LOCA with SI actuation occurred on Unit 1.
- SI can NOT be reset.
Which one of the following completes the following statement?
The CIA signal _(1)_ be reset, and the CVI signal _(2)_ be reset.
_(1 )_ _(2)_
A. can can B. can can NOT C. can NOT can D. can NOT can NOT Page 59 of 75
60.
Initial condition:
- Unit 1 is in Mode 3.
Current condition:
- Operators are preparing to withdraw the shutdown banks per 12003-C, Reactor Startup (Mode 3 to Mode 2).
Which one of the following completes the following statement?
Per 12003-C, the crew is required to notify _(1)_ of the reactor startup prior to Mode 2 entry, and a Mode 2 log entry is required when _(2)_ bank withdrawal commences.
A. (1) the Power Control Center by GenComm Web (2) control B. (1) plant personnel by page announcement (2) control C. (1) the Power Control Center by GenComm Web (2) shutdown D. (1) plant personnel by page announcement (2) shutdown Page 60 of 75
61.
Initial condition:
- Unit I is at 100% reactor power.
Current conditions:
- ARE-2532A, FHB Effluent Radiogas, fails high.
- ALBO5-C03 HIGH RADIATION ALARM is received.
Which one of the following completes the following statement?
When ALBO5-C03 is received, Train B FHB Post Accident Filter Unit _(1) automatically start, and when the FHB Isolation Reset handswitch is taken to RESET, the white light illuminating alerts the operator that the actuation signal _(2)_ present.
_( 1 )_
A. will is B. will is NOT C. will NOT is D. will NOT is NOT Page 61 of75
62.
Given the following:
- Unit 1 Control Room is being evacuated due to a fire.
- The operating crew is fully staffed.
Which one of the following completes the following statement?
Per 18038-1, Operation From Remote Shutdown Panels, the _(1)_ will be dispatched to Shutdown Panel C (TDAFW Pump Room),
and the preferred method for establishing communications between all stations is via
_(2)_.
_(2)_
A. Unit Operator sound powered telephones (red box)
B. Unit Operator bridge phone extension 3145, codes 123#or234#
C. Systems Operator sound powered telephones (red box)
D. Systems Operator bridge phone extension 3145, codes 1 23# or 234#
Page 62 of 75
63.
Initial conditions:
- Unit I is at 45% reactor power.
- EHC Pump A discharge filter #8 is in service.
EHC Pump A discharge filter #4 is tagged out for replacement.
Current conditions:
- The following EHC Pump A discharge filter #4 valve tags are ready for release:
l-1615-U4-592, EHC HYD PUMP A DISCH FILTER #4 INLET ISO l-1615-U4-593, EHC HYD PUMP A DISCH FILTER #4 OUTLET ISO
- EHC Pump A discharge filter #8 is to remain in service.
Which one of the following completes the following statement?
Both valves will be _(1)_ after the tagout is released to standby alignment, and if EHC pressure were to lower to 1000 psig, the reactor _(2)_ trip.
REFERENCES PROVIDED
_(1) _(2)_
A. OPEN would B. OPEN would NOT C. CLOSED would D. CLOSED would NOT Page 63 of 75
64.
Procedure title as follows:
- 14807A-1, Train A Motor Driven Auxiliary Feedwater Pump and Check Valve Inservice and Response Time Test At time 1000:
- Unit 1 is at 7% reactor power with a startup in progress.
- MDAFW pump A discharge valves, IHV-5137 and 1HV-5139, to the SGs are closed by the UO to perform a surveillance per 14807A-1.
At time 1005:
- MDAFW pump A is started.
At time 1010:
MDAFW pump A is stopped.
At time 1015:
- Train A MDAFW system is returned to normal standby alignment.
Which one of the following completes the following statement?
During performance of the surveillance and per Tech Spec 3.7.5, Auxiliary Feedwater (AFW) System, the UO would track an LCO not met (out-of-service) time of _(1)_
minutes, and if a Train A MDAFW actuation signal were received during the surveillance when the discharge valves were closed, the valves would _(2)_.
_(1 )_
A. 10 automatically open B. 10 remain closed C. 15 automatically open D. 15 remain closed Page 64 of 75
65.
Initial conditions:
- Unit 1 is in Mode 5.
- RCS level has been lowered to 192 feet to remove the reactor head.
- ALARA briefing is in progress for closing the Equipment Hatch.
Current conditions:
- The Unit Operator is performing a surveillance that specifies an Independent Verification (IV) of a manual valve inside containment.
- The area where the valve is located has the following conditions:
- Airborne contamination is 0.1 DAC.
- The operator is expected to receive 15 mrem of dose while performing the IV.
Per NMP-GM-005-002, Human Performance Tools Instruction, which one of the following identifies the reason for waiving the IV?
A. l5mremexposure B. Plant Mode of operation C. RCS at reduced inventory D. 0.1 DAC airborne contamination Page 65 of 75
66.
Initial condition:
- Unit 1 is at 11% reactor power with a startup in progress following a refueling outage.
Current condition:
- ALBI5-CO1 HIGH RADIATION ALARM is received due to SG tube leakage.
Which one of the following completes the following statement?
1RE-0724, Steam Line Radiation, _(l)_ available to monitor SG activity, and the monitor is designed to detect _(2)_ radiation.
_(1 )_ _(2)
A. is noble gas B. is nitrogen-16 C. is NOT noble gas D. is NOT nitrogen-16 Page 66 of 75
67 Initial condition:
- Unit 1 and Unit 2 are at 100% reactor power.
Current conditions:
- Unit 1, ALBO5-C03 HIGH RADIATION ALARM is received.
- 1RE-12116, Control Room Air Intake Radiogas Monitor (Train A), red indication light is illuminated on the SRDC.
- Unit 2 has no radiation monitor in alarm.
Which one of the following completes the following statement?
The Unit 1, Train B CREFS unit _(1)_ automatically start, and the Unit 2, Train B CREFS unit _(2)_ automatically start.
_(1 )_ _(2)
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Page 67 of 75
68.
Given the following:
- Both Unit 1 and Unit 2 are at 100% reactor power.
- A fire occurs in the Fuel Handling Building as a result of a seismic event.
Which one of the following completes the following statement?
The (1)_ pumps and piping are designed to provide firefighting water following the seismic event, and per 13903-C, Fire Protection System Operation, the seismic flow path _(2)_ be automatically aligned.
_(1) _(2)_
A. NSCW will B. NSCW will NOT C. Diesel fire will D. Diesel fire will NOT Page 68 of 75
69.
Initial conditions:
- Unit 1 is at 100% reactor power.
- ALB13-A01 STM GEN 1 FLOW MISMATCH is received.
Current conditions:
- RCS pressure is 2237 psig and rising.
- Main generator output is 1225 MWe and rising.
Which one of the following completes the following statements?
Based on the current conditions, a (1)_ line break is in progress.
Per 10020-C, EOP and AOP Rules of Usage, isolating the main steam lines on a secondary fault (2)_ an approved early operator action.
A. feed is B. feed is NOT C. steam is D. steam is NOT Page 69 of 75
70.
Initial condition:
- 19010-C, Loss of Reactor or Secondary Coolant, is in use.
Current conditions:
- Step 11, Check if ECCS flow should be reduced, is in progress with the following conditions:
- RCS pressure is 1335 psig and stable.
- Pressurizer level is 30% and stable.
- CETCs are 550° F.
- The highest WR Thot is 540°F.
- Containment pressure is 4.5 psig.
- All SG NR levels are <10% with 200 gpm AFW flow to each SG.
Which one of the following completes the following statement?
Based on the current conditions, ECCS flow _(1)_ be reduced because _(2).
A. (1) can (2) all termination criteria have been satisfied B. (1) can NOT (2) pressurizer level and RCS subcooling do not meet termination criteria C. (1) can NOT (2) RCS subcooling and secondary heat sink do not meet termination criteria D. (1) can NOT (2) pressurizer level is the only termination criterion not met Page 70 of 75
71.
Initial condition:
- The crew is performing 19112-C, LOCA Outside Containment.
Current condition:
- RCS pressure is 1500 psig.
Which one of the following completes the following statement?
Per 19112-C, the first system to be isolated from the RCS to attempt leak isolation is
_(1)_,
and per 19112-C, to determine if the leak is isolated, the operator is directed to check for rising RCS _(2)_.
_(1 )_ _(2)_
A. SI subcooling B. SI pressure C. RHR subcooling D. RHR pressure Page 71 of 75
72.
Initial conditions:
- Unit I reactor tripped.
- 19231-C, Response to Loss of Secondary Heat Sink, is in use.
- Bleed and Feed has been initiated.
- 1AAO2 is faulted.
- SIP B is running.
- 1PORV-455 is CLOSED.
- 1PORV-456 is OPEN.
Current conditions:
- ALBO7-C06 CHARGING PUMP OVERLOAD TRIP is received.
- ALBO7-B06 CHARGING LINE HI/LO FLOW is received.
- CCP B handswitch green and amber lights are lit.
Which one of the following completes the following statement?
Per 19231-C, the minimum requirement for the RCS Feed path _(1)_ met, and the Reactor Head vents must be (2)_ to delay core uncovery.
_(1 )_ _(2)
A. is opened B. is verified closed C. is NOT opened D. is NOT verified closed Page 72 of 75
73.
Initial condition:
- A steam line break inside containment occurred on Unit 1.
Current conditions:
- RCS cold leg temperature is slowly lowering.
- RCS pressure is slowly lowering.
- 19241-C, Response to Imminent Pressurized Thermal Shock Condition, is in progress.
Which one of the following completes the following statement?
Per 19241-C major operator actions, the in-progress RCS cooldown _(1)_ required to be stopped, and the in-progress RCS depressurization _(2) required to be stopped.
_(1 )_ _(2)_
A. is is B. is is NOT C. is NOT is D. is NOT is NOT Page 73 of 75
74.
Initial conditions:
- Large break LOCA occurred on Unit 1.
- Containment pressure is 23 psig.
- Both Containment Spray (CS) Pumps are running.
- RWST level is 26% and lowering.
- Four Containment Coolers are running in low speed.
Current conditions:
- 19111-C, Loss of Emergency Coolant Recirculation, is in progress.
- The crew is at the step to Determine Containment Spray requirements.
Which one of the following completes the following statement?
Per 19111-C, for the current conditions, _(1)_ CS pump(s) is(are) required to be running, and when a CS pump is stopped, its discharge valve _(2)_ automatically close.
REFERENCES PROVIDED
_(1)..... _(2)_
A. 0 will B. 0 will NOT C. 1 will D. 1 will NOT Page 74 of 75
75.
Given the following:
- Large break LOCA is in progress on Unit 1.
- 1 RE-002, 1 RE-003, 1 RE-005, and 1 RE-006, Containment Area Radiation, are in high alarm.
- 19013-C, Transfer to Cold Leg Recirculation, is in progress.
- The crew just completed realigning Containment Spray suctions.
Which one of the following completes the following statement?
Per 19013-C, if dose rates will not allow reading local suction and discharge pressure indications, proper operation of Containment Spray shall be verified by observing containment _(1)_ lowering, and per 19010-C, Loss of Reactor or Secondary Coolant, Containment Spray is required to remain in the recirculation mode for no less than _(2)_ hours.
_(1 )_ _(2)
A. pressure 1.5 B. pressure 2 C. temperature 1.5 D. temperature 2 Page 75 of 75
Name:
NRC SRO Exam Student Test Start Time:
Stop Time:
1.
Procedure titles as follows:
- 18003-C, Rod Control System Malfunction
- 19000-C, Reactor Trip or Safety Injection
- NMP-EP-1 1 0-GLO3, VEGP EALS lCs, Threshold Values And Basis Initial conditions:
- Unit 1 reactor startup is in progress per 12003-C, Reactor Startup (Mode 3 to Mode 2).
- Source range instruments, Nl-31/32, each indicate 100 cps.
Current conditions:
- When CBA rods are withdrawn to 50 steps, they continue to step outward after the Rod Motion Switch is released.
- 18003-C is entered.
- Nl-31/32 each indicate 1000 cps.
- The reactor did NOT trip using the first reactor trip handswitch.
- The reactor tripped using the second reactor trip handswitch.
Which one of the following completes the following statements?
Per 18003-C, following the reactor trip, the operating crew will _(1)_ 19000-C.
An emergency classification threshold value _(2)_ been exceeded per NMP-EP-1 10-GLO3.
REFERENCES PROVIDED
_(1 )_ _(2)_
A. initiate has B. initiate has NOT C. goto has D. goto has NOT Page 1 of 25
2.
Initial conditions:
- Unit 1 reactor power lowered due to an inadvertent turbine runback.
- ALB1O-C04 ROD BANK LO LIMIT was received.
- ALB1O-D04 ROD BANK LO-LO LIMIT was received.
Current conditions:
- Main turbine load has been stabilized.
- RCS Tavg is 2°F below Tref.
- The OATC has requested a 2-step rod withdrawal for temperature control.
Which one of the following completes the following statement?
Based on the current conditions and using the Plant Computer data provided, ALB1 O-D04 _(1 )_ valid, and based on the current conditions and NMP-OS-OO1, Reactivity Management Program, guidance, the Shift Supervisor is _(2)_ to authorize a 2-step control rod withdrawal for Tavg control.
REFERENCES PROVIDED
_(1 )_ _(2)_
A. is allowed B. is NOT allowed C. is NOT allowed D. is NOT NOT allowed Page 2 of 25
3.
Initial conditions:
- Unit 1 experienced a small break LOCA.
- 19000-C, Reactor Trip or Safety Injection, is in progress.
- Loop 3 RCS Tcold instrumentation is NOT available.
Current condition:
- RCS pressure is 1350 psig and slowly lowering.
Which one of the following completes the following statement?
Stopping the RCPs is required to minimize the risk of _(1)_,
and per the Bases of Tech Spec 3.3.3, Post Accident Monitoring (PAM) Instrumentation, for diverse indication of Loop 3 RCS Tcold temperature, the operator _(2)_ directed to use Loop 3 steam generator pressure.
_(1 )_ _(2)_
A. core uncovery is B. core uncovery is NOT C. RCP damage is D. RCP damage is NOT Page 3 of 25
4.
Procedure titles as follows:
- 19000-C, Reactor Trip or Safety Injection
- 13003-1, Reactor Coolant Pump Operation
- 18005-C, Partial Loss of Flow Initial condition:
- Unit us at 16% reactor power with a startup in progress.
Current conditions:
- ALBO8-A04 RCP 1 NO. 2 SEAL LKOF HI FLOW is received.
- ALBO8-A05 RCP 1 CONTROLLED LKG HI/LO FLOW is received.
- lFl-160A, #1 Seal Leak-Off, for RCP #1 is indicating 6.0 gpm.
Which one of the following completes the following statement?
RCP #1, seal _(1 )_ has failed, and per 13003-1, the Shift Supervisor will direct the crew to _(2)_.
_(1) _(2)_
A. #1 initiate 18005-C B. #1 trip the reactor and initiate 19000-C C. #2 initiate 18005-C D. #2 trip the reactor and initiate 19000-C Page 4 of 25
5.
Initial conditions:
- Unit 1 is at 100% reactor power.
- COW pump #5 is tagged out for maintenance.
- 1-LSLL-1854, CCW Surge Tank level switch for COW pump #3, has failed.
- ALBO2-A05 COW TRAIN A SURGE TK LO-LO LVL is received.
Current conditions:
- ALB02-A06 COW TRAIN A LO HDR PRESS is received.
- ALBO2-B06 CCW TRAIN A LO FLOW is received.
Which one of the following completes the following statement?
Based on the current conditions, the Demin Water Makeup Valve to the OCW Train A Surge Tank _(1)_ automatically opened, and per Tech Spec 3.7.7, Component Cooling Water (CCW) System, Train A COW is declared _(2)_.
_(1)_ _(2)_
A. has OPERABLE B. has inoperable C. has NOT OPERABLE D. has NOT inoperable Page 5 of 25
6.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- ALB12.-F01 PRZR SAFETY RELIEF DISCH HI TEMP is received.
- PRT level, temperature, and pressure are all increasing.
- CVCS charging flow is 122 gpm.
- All RCP seal injection and #1 seal return flows are within normal operating range.
- CVCS letdown is isolated.
- Pressurizer level is 55% and stable.
Which one of the following completes the following statement?
Per Tech Spec 3.4.13, RCS Operational Leakage, the RCS leakage is classified as (1)_,
and per NMP-EP-110, Emergency Classification Determination and Initial Action, the Shift Manager is required to declare as a minimum a(n) _(2)_.
REFERENCES PROVIDED
_(1)_ _(2)_
A. identified NOUE B. identified Alert C. unidentified NOUE D. unidentified Alert Page 6 of 25
7.
Initial conditions:
- Unit 1 is at 100% reactor power.
- Containment Cooler #1 high speed fan breaker trips.
Current conditions:
- ALB01-E06 CNMT HI TEMP is received.
- IPC data for containment temperature is collected.
Which one of the following completes the following statement?
Based on the IPC data provided, the Tech Spec Surveillance for containment temperature (Tech Spec SR 3.6.5.1) _(1)_ within Tech Spec limits, and per the applicable ARP and SOP, the crew is required, as a minimum, to _(2)_.
REFERENCES PROVIDED A. (1) is (2) start one additional Containment Cooler B. (1) is (2) stop Containment Cooler #2, then start an additional pair of Containment Coolers C. (1) is NOT (2) start one additional Containment Cooler D. (1) is NOT (2) stop Containment Cooler #2, then start an additional pair of Containment Coolers Page 7of25
8.
At time 1055:
- Unit 1 is in Mode 5.
- Containment integrity is NOT established.
- Pressurizer level is 27%.
- All Pressurizer Safety Valves are removed.
At time 1100:
- An LOSP occurs.
- DG1A trips on overspeed.
- RHR pump B will NOT start following the load sequence.
- RCS temperature is 200°F and increasing.
Which one of the following completes the following statement?
At time 1115, the Shift Manager must declare a(n) _(l)_ per NMP-EP-1 10, Emergency Classification Determination and Initial Action, and per NMP-EP-1 11, Emergency Notifications, the NRC is required to be notified of the declaration no later than time _(2)_.
REFERENCES PROVIDED (1 )_ _(2)_
A. NOUE 1200 B. NOUE 1215 C. Alert 1200 D. Alert 1215 Page 8 of 25
9.
At time 1000:
- Unit 1 is at 100% reactor power.
At time 1005:
- ALBO4-A03 ACCW RCP 1 CLR LOW FLOW is received.
- ALB04-A04 ACCW RCP I CLR OUTLET HI TEMP is received.
- 18022-C, Loss of Auxiliary Component Cooling Water, is entered.
At time 1007:
- RCP #1 seal water inlet temperature is 220°F and rising at 1°F per minute.
- RCP #1 motor stator winding temperature is 307°F and rising at 1°F per minute.
Which one of the following completes the following statement?
_(1)_ temperature is the first parameter which will require stopping the RCP, and after the reactor is tripped, the Shift Supervisor directs the OATC to stop the affected RCP per _(2)_ direction.
A. (1) Motorstatorwinding (2) 18022-C, Loss of Auxiliary Component Cooling Water B. (1) Motor stator winding (2) 19000-C, Reactor Trip or Safety Injection C. (1) Seal water inlet (2) 18022-C, Loss of Auxiliary Component Cooling Water D. (1) Seal water inlet (2) 19000-C, Reactor Trip or Safety Injection Page 9 of 25
10.
Initial condition:
- Unit 1 reactor trip and SI occurred.
Current conditions:
- 1901 1-C, SI Termination, Step 21, is in progress to evaluate if a bubble exists in the pressurizer.
- Controlling pressurizer level channel, I LT-459, fails low.
- Actual pressurizer level is 92% and slowly rising.
Which one of the following completes the following statement?
Per 10020-C, EOP and AOP Rules of Usage, the Shift Supervisor _(1 )_ direct the use of 18001-C, Systems Instrumentation Malfunction, guidance to restore pressurizer heaters to service while performing 19011-C actions, and in response to actual pressurizer level, the Shift Supervisor _(2)_ required to transition to 19261-C, Response to High Pressurizer Level.
_( 1 )_
A. may is NOT B. may is C. may NOT is NOT D. may NOT is Page 100f25
11.
At time 1000:
- Unit 1 is in Mode 6.
- Source Range Nl-31/32 each indicate -1O cps.
At time 1005:
- QMCB SR Nl-32 meter is indicating bottom of scale.
- All protection channel I bistable lights are lit.
- ALB34-CO1 12OVAC PANELS IBYIB IBY2B TROUBLE is received.
At time 1015:
- SR Nl-32 is re-energized from 1 NLP39.
- Functional Testing has been performed with satisfactory results.
Which one of the following completes the following statements?
Per Tech Spec LCO 3.9.3, Nuclear Instrumentation, _(1)_ Source Range channels are required to be OPERABLE.
At time 1015, Source Range channel N 1-32 _(2)_ considered OPERABLE per the Tech Spec 3.9.3 Bases.
_(1 )_ _(2)_
A. 1 is B. 1 isNOT C. 2 is D. 2 isNOT Page 11 of25
12.
Procedure 13719-1, Spent Fuel Pool Cooling and Purification, sections as follows:
- Section 4.2.2, SEP Makeup from the RWST through the SEP Purification Loop
- Section 4.2.4, SFP Makeup from the RMWST Initial conditions:
- Unit 1 is defueled.
- Transfer canal is drained for transfer cart inspection.
- Spent fuel shuffle is in progress in the FHB.
Current conditions:
- ALBO5-E02 SPENT FUEL PIT LO LEVEL is received.
- Personnel in the FHB report SEP level is slowly lowering.
- 18030-C, Loss of Spent Fuel Pool Level or Cooling, is entered.
Which one of the following completes the following statement?
To mitigate the consequences of the event, the Shift Supervisor is required to direct makeup to the SEP using 13719-1, Section _(1)_,
and per the Bases of Tech Spec 3.7.15, Fuel Storage Pool Water Level, maintaining the required minimum water level in the SEP _(2)_ ensure adequate iodine decontamination factors are met for a fuel handling accident.
(1 )_ _(2)
A. 4.2.2 does B. 4.2.2 does NOT C. 4.2.4 does D. 4.2.4 does NOT Page 12 of25
13.
At time 1000:
- Unit I is at 100% reactor power.
- 18009-C, Steam Generator Tube Leak, is in progress.
- SG sample results indicate high activity on SG #1.
At time 1020:
- IRE-0724, Steam Line Rad Monitor, indicates 105 gpd.
- 1RE-0810, SJAE Exhaust Rad Monitor, indicates 120 gpd.
- 1 RE-0724 ROC is 55 gpd/hour.
- 1 RE-081 0 ROC is 60 gpd/hour.
Which one of the following completes the following statement?
Per Tech Spec 3.4.13, RCS Operational Leakage, the primary to secondary leakage
_(1)_ exceed the limit, and per 18009-C, the Shift Supervisor is required to initiate _(2)_ to lower reactor power.
_(1 )_ _(2)_
A. does 18013-C, Rapid Power Reduction B. does 12004-C, Power Operation (Mode 1)
C. does NOT 18013-C, Rapid Power Reduction D. does NOT 12004-C, Power Operation (Mode 1)
Page 13 of 25
14.
Procedure titles are as follows:
- 18034-1, Loss of Class 1 E 125 VDC Power
- 19000-C, Reactor Trip or Safety Injection Initial condition:
- Unit I is at 100% reactor power.
Current conditions:
- All Train A MSIV red and green handswitch lights extinguish.
- All Train A MFIV red and green handswitch lights extinguish.
- RTB A red and green lights extinguish.
- RCP #1 1 E breaker red and green handswitch lights extinguish.
- Channel I TSLB bistable lights illuminate.
Which one of the following completes the following statement?
The Shift Supervisor _(1) required to enter 18034-1, and the Shift Supervisor _(2)_ required to enter 19000-C.
_(1 )_ _(2)_
A. is is B. is is NOT C. is NOT is D. is NOT is NOT Page 14 of 25
15.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- The Shift Supervisor discovers the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Channel Check for Train A NSCW basin level, iLl-i 606, was missed.
- The last performance of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Channel Check was 0030 on 5-1 1-14.
- Time of discovery of the missed surveillance was 1700 on 5-12-14.
- A risk evaluation will NOT be performed.
Which one of the following describes the status of the applicable LCO?
A. The LCO was NOT met as of 0030 on 5-12-14.
B. The LCO was NOT met as of 0630 on 5-12-14.
C. The LCO is met provided the missed surveillance is performed satisfactorily no later than 1700 on 5-13-14.
- 0. The LCO is met provided the missed surveillance is performed satisfactorily no later than 2300 on 5-13-14.
Page 15 of25
16.
Initial conditions:
- Unit 1 is at 100% reactor power.
- SI Pump A is tagged out.
Current conditions:
- Train B NSCW supply header pressure is 75 psig and lowering.
- Train B NSCW supply header flow is 25,000 gpm.
- Train B NSCW return header flow is 10,000 gpm.
- 18021-C, Loss of Nuclear Service Cooling Water System, is entered.
Which one of the following completes the following statement?
Per 18021-C, the crew is required to (1) the standby Train B NSCW pump, and after completing the actions of 18021-C, the Shift Supervisor will determine per 10008-C, Recording Limiting Conditions for Operation, that a LOSF (2) exist.
_( I )_ _(2)_
A. start does B. start does NOT C. place in PTL does D. place in PTL does NOT Page 16 of25
17.
Initial condition:
- Unit 1 is at 100% reactor power.
Current conditions:
- The following reactor coolant Dose Equivalent 1-131 trends are recorded:
TIME ACTIVITY (iCiIqm) 1130 0.8 1145 1.1 1200 1.3 1215 1.6 Which one of the following completes the following statement?
The first time that Tech Spec LCO 3.4.16, RCS Specific Activity, is NOT met is
_(1)_,
and per the Bases of Tech Spec 3.4.16, RCS Specific Activity, the required action to reduce RCS Tavg below 500° F if the gross specific activity is exceeded is to prevent opening of the _(2)_.
_(1 )_ _(2)_
A. 1145 Atmospheric Relief Valves B. 1145 Main Steam Safety Valves C. 1215 Atmospheric Relief Valves D. 1215 Main Steam Safety Valves Page 17of25
18.
Given the following:
- Unit 1 is at 100% reactor power.
Which one of the following completes the following statement?
Per Tech Spec 3.7.16, Secondary Specific Activity, the specific activity of the secondary coolant shall be (1)_ pCi/gm Dose Equivalent 1-131, and operating within this limit ensures that the off-site dose will be limited to within a small fraction of the 10 CFR 100 dose guideline values in the event of a _(2)_.
_(1 )_ _(2)_
A. 0.1 steam line break B. 0.1 loss of all AC power C. 1.0 steam line break D. 1.0 loss of all AC power Page 18 of25
19.
Given the following:
- Unit 1 is at 3% reactor power and increasing following an outage.
- Unit 2 is at 100% reactor power.
- The Shift Manager and the following assigned personnel are in the control room:
Unit I Unit 2 Shift Supervisor Shift Supervisor Reactivity Management SRO I NPO 2 NPOs*
(*) NPO Individual with a Reactor Operator License.
Which one of the following completes the following statement?
Per TR 15.1, Unit Staffing, the total number of NPOs assigned _(1)_ meet the minimum required for the given conditions, and per NMP-OS-001, Reactivity Management Program, any changes to the Unit I reactivity plan must be approved by the _(2)_.
_(1)_ _(2)_
A. does Reactivity Management SRO B. does Shift Supervisor C. does NOT Reactivity Management SRO D. does NOT Shift Supervisor Page 19 of25
20.
Initial condition:
- ALB34-D01 125 VDC SWGR 1ADI TROUBLE is received due to a bus ground.
Current conditions:
- Per NMP-AD-002, Problem Solving and Troubleshooting Guidelines, a troubleshooting plan has been written.
- As part of the plan, operations personnel will open various breakers and maintenance personnel will open links to measure resistance inside the IAD1 panel.
Which one of the following completes the following statement?
This type of Troubleshooting Monitoring is called _(1 )_,
and the tracking of the equipment out-of-service time while troubleshooting IADI is the responsibility of the (2)_ Department.
A. (1) Intrusive (2) Maintenance B. (1) Intrusive (2) Operations C. (1) Non-Intrusive (2) Maintenance D. (1) Non-Intrusive (2) Operations Page 20 of 25
21.
Given the following:
- Unit 1 is at 100% reactor power.
- The following RWST parameters are recorded:
Temperature is 47°F.
Level is 93%.
Which one of the following completes the following statement?
Tech Spec action is required for RWST _(1)_,
and the Tech Spec Basis for this parameter limit is to ensure _(2)_.
A. (1) Level (2) sufficient borated water to support the ECCS during the injection phase of a design basis main steam line break B. (1) Level (2) sufficient borated water to support the ECCS during the injection phase of a design basis loss of coolant accident C. (1) Temperature (2) that the amount of cooling provided from the RWST during the heatup phase of a main steam line break is consistent with safety analysis assumptions D. (1) Temperature (2) that the amount of cooling provided from the RWST during the heatup phase of a main feed line break is consistent with safety analysis assumptions Page 21 of 25
22.
Initial condition:
- A General Emergency has been declared.
Current conditions:
- A first responder is briefed to rescue an injured worker.
- Health Physics estimates the first responder will receive 11 rem TEDE dose while performing the rescue.
Which one of the following completes the following statement?
Per 91301-C, Emergency Exposure Guidelines, the dose received by the first responder during the rescue _(1 )_ be added to the responders occupational non-emergency exposure, and the lowest level of approval required to authorize the first responders rescue exposure is the _(2)_.
_(1 )_
A. will Health Physics Supervisor B. will Emergency Director C. will NOT Health Physics Supervisor D. will NOT Emergency Director Page 22 of 25
23.
Given the following:
- A Systems Operator (SO) will make multiple entries into AB-A-33 to place the CVCS cation demineralizer in service.
- The SO will use RWP 14-0108 (red RWP).
- The SO will exceed the Annual Administrative 4000 mrem per year TEDE limit during the task.
Which one of the following completes the following statement?
The SO _(1) required to receive an ALARA briefing prior to each AB-A-33 entry, and per NMP-HP-001, Radiation Protection Standard Practices, the _(2)_ is the lowest level of approval required to exceed the Administrative dose limit.
_(1 )_ _(2)_
A. is Health Physics Manager B. is Plant Manager C. is NOT Health Physics Manager D. is NOT Plant Manager Page 23 of 25
24.
At time 1000:
- Unit 1 is in Mode 6.
At time 1005 the following alarms are received:
- ALB32-D02 RESV AUX XFMR 1 NXRA HI SIDE PHOC LOR TRIP
- ALB32-E02 RESV AUX XFMR 1 NXRB HI SIDE PHOC LOR TRIP
- ALB35-A1O DG1A TRIP OVERSPEED
- ALB35-F1O DG1A EMERGENCY START
-ALB36-AO1 416OVSWGR 1AAO2 TROUBLE
- ALB37-AO1 4160V SWGR IBAO3 TROUBLE alarms, then subsequently clears.
- ALB38-F1O DG1B EMERGENCY START Current time is 1025:
Based on the current time, which one of the following is the correct Emergency Classification required to be declared?
REFERENCES PROVIDED A. Alert Emergency (CA3)
B. Alert Emergency (SA5)
C. Notification of Unusual Event (SUI)
D. Notification of Unusual Event (CU3)
Page 24 of 25
25.
Initial conditions:
- Unit 1 experienced a LOCA.
- 19111-C, Loss of Emergency Coolant Recirculation, was entered.
- RCS cooldown to cold shutdown has been initiated.
- RWST level is 8% and slowly lowering.
Current condition:
- Critical Safety Function Status Tree (CSFST) is ORANGE on Integrity.
Which one of the following completes the following statement?
The crew is required to _(1 )_,
and then the Shift Supervisor _(2)_ required to transition to 19241-C, Response to Imminent Pressurized Thermal Shock Condition.
A. (1) stop all pumps taking suction from the RWST (2) is B. (1) reduce ECCS flow from the RWST to one running train (2) is C. (1) stop all pumps taking suction from the RWST (2) is NOT D. (1) reduce ECCS flow from the RWST to one running train (2) is NOT Page 25 of 25
ANSWER KEY REPORT for NRC RO Exam Test Form: 0 Answers ID Points Type 0 -
1 001K2.03 1 1.00 MCS D 2 003A3.04 1 1.00 MCS D 3 004K6.09 1 1.00 MCS D 4 005A2.02 1 1.00 MCS B 5 005AK3.05 1 1.00 MCS D 6 005K5.09 1 1.00 MCS C 7 006A1.06 1 1.00 MCS C 8 006G2.4.47 1 1.00 MCS A 9 007A2.02 1 1.00 MCS D 10 007EA2.06 1 1.00 MCS C 11 008A1.03 1 1.00 MCS C 12 009EK2.03 1 1.00 MCS A 13 010A3.02 1 1.00 MCS A 14 010K6.02 1 1.00 MCS C 15 O11EK2.02 1 1.00 MCS C 16 011K6.03 1 1.00 MCS B 17 012K5.01 1 1.00 MCS B 18 013K6.01 1 1.00 MCS D 19 014A1.02 1 1.00 MCS D 20 015A2.04 1 1.00 MCS C 21 OI5AAI.23 1 1.00 MCS C 22 022AK3.01 1 1.00 MCS B 23 022K3.02 1 1.00 MCS D 24 024AG2.2.22 1 1.00 MCS C 25 026K1.01 1 1.00 MCS B 26 026K2.02 1 1.00 MCS C 27 027AK2.03 1 1.00 MCS B 28 028K1.01 1 1.00 MCS B 29 029EG2.4.34 1 1.00 MCS D 30 033AG2.2.44 1 1.00 MCS A 31 034A4.01 1 1.00 MCS B 32 038EA2.05 1 1.00 MCS B 33 039K4.02 1 1.00 MCS C 34 040AG2.2.36 1 1.00 MCS D 35 045K5.17 1 1.00 MCS B 36 054AA 1.02 1 1.00 MCS C 37 055EK1.02 1 1.00 MCS B 38 056AK1.01 1 1.00 MCS A 39 057AK3.01 1 1.00 MCS A 40 059A4.03 1 1.00 MCS D 41 059AK2.02 1 1.00 MCS B 42 059K4.19 1 1.00 MCS A 43 061AA2.03 1 1.00 MCS A 44 061K2.01 1 1.00 MCS A 45 062K3.02 1 1.00 MCS B 46 062K4.07 1 1.00 MCS D 47 063A1.01 1 1.00 MCS C Wednesday, May 28, 2014 8:10:53 AM
ANSWER KEY REPORT for NRC RO Exam Test Form: 0 Answers
- ID Points Type 0 48 064G2.1.31 1 1.00 MCS A 49 065AA2.08 1 1.00 MCS B 50 069AA2.02 1 1.00 MCS A 51 071A3.03 1 1.00 MCS B 52 072K3.02 1 1.00 MCS B 53 073K1.01 1 1.00 MCS C 54 076K2.04 1 1.00 MCS A 55 077AK3.02 1 1.00 MCS A 56 078A4.01 1 1.00 MCS B 57 086K4.02 1 1.00 MCS D 58 103A2.03 1 1.00 MCS C 59 103K1.08 1 1.00 MCS A 60 G2.1.14 1 1.00 MCS B 61 G2.1.28 1 1.00 MCS A 62 G2.1.8 1 1.00 MCS C 63 G2.2.15 1 1.00 MCS C 64 G2.2.23 1 1.00 MCS C 65 G2.3.13 1 1.00 MCS A 66 G2.3.15 1 1.00 MCS D 67 G2.3.5 1 1.00 MCS B 68 G2.4.25 1 1.00 MCS B 69 G2.4.45 1 1.00 MCS A 70 WEO2EA1.03 1 1.00 MCS B 71 WEO4EK1.03 1 1.00 MCS D 72 WEO5EA1.02 1 1.00 MCS A 73 WEO8EKI.02 1 1.00 MCS B 74 WE11G2.1.25 1 1.00 MCS D 75 WEI6EK2.02 1 1.00 MCS A SECTION 1 (75 items) 75.00 Wednesday, May 28, 2014 8:10:53 AM 2
ANSWER KEY REPORT for NRC SRO Exam Test Form: 0 Answers
- ID Points Type 0 1 OOIAA2.04 1 1.00 MCS D 2 001G2.1.19 1 1.00 MCS A 3 003G2.4.3 1 1.00 MCS A 4 004G2.2.44 1 1.00 MCS B 5 008A2.02 1 1.00 MCS D 6 008AG2.4.41 1 1.00 MCS A 7 022G2.1.19 1 1.00 MCS B 8 025AG2.4.30 1 1.00 MCS D 9 026AA2.06 1 1.00 MCS A 10 028AG2.4.8 1 1.00 MCS A 11 032AA2.03 1 1.00 MCS C 12 033A2.03 1 1.00 MCS A 13 055G2.1.23 1 1.00 MCS C 14 058AA2.03 1 1.00 MCS A 15 062AG2.2.12 1 1.00 MCS C 16 076A2.02 1 1.00 MCS C 17 076AG2.4.47 1 1.00 MCS B 18 G2.1.34 1 1.00 MCS A 19 G2.1.37 1 1.00 MCS B 20 G2.2.20 1.00 MCS B 21 G2.2.25 1 1.00 MCS B 22 G2.3.4 1 1.00 MCS D 23 G2.3.7 1 1.00 MCS B 24 G2.4.46 1 1.00 MCS D 25 WEIIEA2.02 1 1.00 MCS A SECTION 1(25 items) 25.00 Wednesday, May 28, 2014 8:12:31 AM