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{{#Wiki_filter:Final Submittal (Blue Paper) FINAL RO WRITTEN EXAMINATION AND REFERENCES ES-401 Site-Specific RO Written Examination Cover Sheet Form ES-401-7 u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: "/'D Izoo'6 Facility/Unit:  
{{#Wiki_filter:Final Submittal (Blue Paper)
\<./ \ __ 2.. Region: I D II III D IV D Reactor Type: W D CE D BW D GE Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent I Brunswick NRC RO Exam November 2008 Name: A-.ar.1IJ)
FINAL RO WRITTEN EXAMINATION AND REFERENCES
Date:
 
: 1. Ae C 0 26. A B
ES-401                         Site-Specific RO Written Examination                       Form ES-401-7 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
* 0 51. A
Date:       "/'D Izoo'6                               Facility/Unit: flrut\6w'~ \<./         \ __ 2..
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Region:           I D   II ~  III D IV D           Reactor Type: W D CE D BW D GE ~
* 0 27. A
Start Time:                                           Finish Time:
* C 0 52. A B C
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins.
* 3. A
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
* C 0 28.
Applicant's Signature Results Examination Value                                                                               Points Applicant's Score                                                                               Points Applicant's Grade                                                                             Percent I
* B C 0 53.
 
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Brunswick NRC RO Exam November 2008 Name:   A-.ar.1IJ)                       Date: .'~I 1.
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: 1. Which one of the following identifies the component manipulations that will raise CRD drive water header differential pressure indication at Panel P603? A. throttle open Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 B. throttle open Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 C. throttle closed Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 D. throttle closed Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 Page 1 of 75
B B
: 2. Unit Two is operating at rated pressure.
C C
While placing the 2B Recirculation Pump in service a complete failure of the #1 seal occurs. #1 seal cavity pressure is 1000 psig. Which one of the following identifies the expected system indications for this failure? A. #2 seal cavity pressure is 500 psig; PUMP B SEAL STAGING FLOW HI/LO annunciator in alarm B. #2 seal cavity pressure is 500 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm C. #2 seal cavity pressure is 1000 psig; PUMP B SEAL STAGING FLOW HIILO annunciator in alarm D. #2 seal cavity pressure is 1000 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm Page 2 of 75
0 0
: 3. Given the following plant conditions on Unit One: Reactor water level Reactor pressure Vessel Injection (reference provided)  
* 0
-25 inches 55 psig 4500 gpm from RHR In accordance with 001-37.4, Reactor Vessel Control Procedure Basis Document, which one of the following identifies the current status of Adequate Core Cooling and the operational implications of these conditions?
: 12.       B   C 0         37. A   B       0         62.     B C     0
A. Adequate Core Cooling is met; Clad temperatures are expected to remain between 1500&deg; F and 1800&deg; F. B. Adequate Core Cooling is met; Clad temperatures are expected to remain F C. Adequate Core Cooling is NOT met; Clad temperatures are expected to exceed 1800&deg; F D. Adequate Core Cooling is NOT met; Clad temperatures are expected to remain F Page 3 of 75
: 13. A   B
: 4. Which one of the following pumps is powered from 4KV E-Bus E2? A. 1A RHR Pump B. 2C RHR Pump C. 10 RHR SW Booster Pump D. 2B RHR SW Booster Pump Page 4 of 75
* 0         38.
: 5. During accident conditions, suppression pool level has dropped below -6.5 feet. Which one of the following identifies the required action for HPCI, including the basis for the action, in accordance with PCCP and 001-37.8, Primary Containment Control Procedure Basis Document?
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: 1. Which one of the following identifies the component manipulations that will raise CRD drive water header differential pressure indication at Panel P603?
A. throttle open Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 B. throttle open Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 C. throttle closed Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 D. throttle closed Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 Page 1 of 75
: 2. Unit Two is operating at rated pressure. While placing the 2B Recirculation Pump in service a complete failure of the #1 seal occurs.
  #1 seal cavity pressure is 1000 psig.
Which one of the following identifies the expected system indications for this failure?
A. #2 seal cavity pressure is 500 psig; PUMP B SEAL STAGING FLOW HI/LO annunciator in alarm B. #2 seal cavity pressure is 500 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm C. #2 seal cavity pressure is 1000 psig; PUMP B SEAL STAGING FLOW HIILO annunciator in alarm D. #2 seal cavity pressure is 1000 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm Page 2 of 75
: 3. Given the following plant conditions on Unit One:
Reactor water level       -25 inches Reactor pressure           55 psig Vessel Injection           4500 gpm from RHR (reference provided)
In accordance with 001-37.4, Reactor Vessel Control Procedure Basis Document, which one of the following identifies the current status of Adequate Core Cooling and the operational implications of these conditions?
A. Adequate Core Cooling is met; Clad temperatures are expected to remain between 1500&deg; F and 1800&deg; F.
B. Adequate Core Cooling is met; Clad temperatures are expected to remain   ~1500&deg;  F C. Adequate Core Cooling is NOT met; Clad temperatures are expected to exceed 1800&deg; F D. Adequate Core Cooling is NOT met; Clad temperatures are expected to remain   ~1800&deg;  F Page 3 of 75
: 4. Which one of the following pumps is powered from 4KV E-Bus E2?
A. 1A RHR Pump B. 2C RHR Pump C. 10 RHR SW Booster Pump D. 2B RHR SW Booster Pump Page 4 of 75
: 5. During accident conditions, suppression pool level has dropped below -6.5 feet.
Which one of the following identifies the required action for HPCI, including the basis for the action, in accordance with PCCP and 001-37.8, Primary Containment Control Procedure Basis Document?
A. Terminate HPCI irrespective of adequate core cooling to prevent primary containment overpressurization.
A. Terminate HPCI irrespective of adequate core cooling to prevent primary containment overpressurization.
B. Terminate HPCI irrespective of adequate core cooling to prevent exceeding Heat Capacity Temperature Limit. C. Maintain HPCI operation if required to maintain adequate core cooling because core cooling takes priority over primary containment integrity.
B. Terminate HPCI irrespective of adequate core cooling to prevent exceeding Heat Capacity Temperature Limit.
D. Maintain HPCI operation if required to maintain adequate core cooling because the turbine exhaust flowrate is within the capacity of containment vent system. Page 5 of 75
C. Maintain HPCI operation if required to maintain adequate core cooling because core cooling takes priority over primary containment integrity.
: 6. Unit Two plant conditions following an automatic initiation of ADS are as follows: Reactor level Reactor Pressure Core Spray pumps ADS SRV's -20 inches 400 psig and lowering 2A and 2B pumps running 7 ADS valves OPEN with control switches in AUTO A dual unit loss of off-site power occurs and all DGs tie onto their respective E buses. Which one of the following predicts how the ADS valves will respond during the loss of offsite power and subsequent re-energization of power to the E-busses?
D. Maintain HPCI operation if required to maintain adequate core cooling because the turbine exhaust flowrate is within the capacity of containment vent system.
Page 5 of 75
: 6. Unit Two plant conditions following an automatic initiation of ADS are as follows:
Reactor level             -20 inches Reactor Pressure          400 psig and lowering Core Spray pumps          2A and 2B pumps running ADS SRV's                7 ADS valves OPEN with control switches in AUTO A dual unit loss of off-site power occurs and all DGs tie onto their respective E buses.
Which one of the following predicts how the ADS valves will respond during the loss of offsite power and subsequent re-energization of power to the E-busses?
A. remain open when the LOOP initially occurs; remain open after the E-Busses are re-energized.
A. remain open when the LOOP initially occurs; remain open after the E-Busses are re-energized.
B. close when the LOOP initially occurs; remain closed after the E-Busses are re-energized.
B. close when the LOOP initially occurs; remain closed after the E-Busses are re-energized.
C. close when the LOOP initially occurs; re-open 83 seconds after the Core Spray pumps restart. D. close when the LOOP initially occurs; re-open immediately after the Core Spray pumps restart. Page 6 of 75
C. close when the LOOP initially occurs; re-open 83 seconds after the Core Spray pumps restart.
: 7. Following a DBA LOCA on Unit Two, plant conditions are as follows: Reactor water level Reactor pressure Torus temperature Suppression Chamber pressure Torus level 2A Core Spray pump flow 2B Core Spray pump flow 2A RHR pump flow 2B RHR pump flow (reference provided) 55 inches and rising 150 psig 220 0 F 10.5 psig -43 inches 5000 gpm 2000 gpm 8000 gpm 6000 gpm Which one of the following identifies the ECCS pump(s) that is/are operating within the associated NPSH limit(s)?
D. close when the LOOP initially occurs; re-open immediately after the Core Spray pumps restart.
Page 6 of 75
: 7. Following a DBA LOCA on Unit Two, plant conditions are as follows:
Reactor water level               55 inches and rising Reactor pressure                   150 psig Torus temperature                 220 0 F Suppression Chamber pressure       10.5 psig Torus level                       -43 inches 2A Core Spray pump flow           5000 gpm 2B Core Spray pump flow           2000 gpm 2A RHR pump flow                   8000 gpm 2B RHR pump flow                   6000 gpm (reference provided)
Which one of the following identifies the ECCS pump(s) that is/are operating within the associated NPSH limit(s)?
A. 2B CS Pump ONLY B. All CS and RHR pumps C. 2A CS and 2B CS ONLY D. 2B CS, 2A RHR and 2B RHR ONLY Page 7 of 75
A. 2B CS Pump ONLY B. All CS and RHR pumps C. 2A CS and 2B CS ONLY D. 2B CS, 2A RHR and 2B RHR ONLY Page 7 of 75
: 8. Which one of the following methods is available to determine level in the SLC Tank following a loss of all air systems? A. Direct the AO to valve in the local sight glass to obtain the level. B. Have the AO read the level gauge on the local instrument rack. C. Use the indication on the Level/Power Control ERFIS Screen. D. Direct the AO to measure the distance from the surface of the liquid to the top of the SLC Tank. Page 8 of 75
: 8. Which one of the following methods is available to determine level in the SLC Tank following a loss of all air systems?
: 9. OPT-01.1.6, Reactor Protection System Manual Scram Test, is in progress.
A. Direct the AO to valve in the local sight glass to obtain the level.
The Reactor Scram System A pushbutton has been depressed.
B. Have the AO read the level gauge on the local instrument rack.
Which one of the following choices completes the statement below? The alarm(s) that will occur is/are _____ ' The RPS channel(s) that is/are de-energized is/are _____ ' A. REACTOR MANUAL SCRAM SYS A only A3 only B. REACTOR MANUAL SCRAM SYS A only A1, A2 and A3 C. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A3 only D. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A1, A2 and A3 Page 9 of 75
C. Use the indication on the Level/Power Control ERFIS Screen.
: 10. Which one of the following identifies the parameter that provides a direct input into the RPS logic (Le., does not actuate a turbine trip logic first)? A. Control Valve Position L VDT B. EHC Low Header Discharge Pressure C. ETS (Emergency Trip System) Pressure D. RETS (Relayed Emergency Trip Supply) Pressure Page 10 of 75
D. Direct the AO to measure the distance from the surface of the liquid to the top of the SLC Tank.
: 11. TIP traces are in progress with all TIP drawer Mode Switches in Auto. A small steam leak in containment causes drywell pressure to rise to 2.7 psig. Which -one of the following predicts the final TIP ball valve position indication(s) and also identifies all available location(s) for verifying their position?
Page 8 of 75
A. Red light indication illuminated on the Back Panel P607 ONLY. B. White Valve Light illuminated on each TIP drawer at Back Panel P607 ONLY. C. Red light indication illuminated on both the P601 Panel and the Back Panel P607. D. Green light indication illuminated on the P601 Panel and a white Valve Light illuminated on each TIP drawer at Back Panel P607. Page 11 of 75
: 9. OPT-01.1.6, Reactor Protection System Manual Scram Test, is in progress. The Reactor Scram System A pushbutton has been depressed.
: 12. Unit One is commencing a startup with all SRM's fully inserted and reading approximately 1 x 10 5 cps. The IRM's are reading the following:
Which one of the following choices completes the statement below?
IRMA IRMB IRMC IRMD 20 on Range 1 28 on Range 1 21 on Range 2 25 on Range 1 IRME IRMF IRMG IRMH 21 on Range 1 19 on Range 1 23 on Range 2 20 on Range 1 The operator takes the range switch for IRM B from Range 1 to Range 3. Which one of the following identifies the status of the IRM B downscale white light at P601 and also identifies the annunciator alarm(s) status for this condition?
The alarm(s) that will occur is/are _ _ _ _ _ '
A. White light illuminated; ROD OUT BLOCK alarm only. B. White light illuminated; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms. C. White light extinguished; ROD OUT BLOCK alarm only. D. White light extinguished; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms. Page 12 of 75
The RPS channel(s) that is/are de-energized is/are _ _ _ _ _ '
: 13. A reactor startup is in progress following a mid cycle forced outage in accordance with OGP-02, Approach to Criticality and Pressurization of the Reactor. The operator notes the following SRM readings:
A. REACTOR MANUAL SCRAM SYS A only A3 only B. REACTOR MANUAL SCRAM SYS A only A1, A2 and A3 C. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A3 only D. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A1, A2 and A3 Page 9 of 75
SRM Channel A SRM Channel B SRM Channel C SRM Channel D AlllRMs are on Range 4. 6.0 x 10 5 cps 1.0 x 10 5 cps 7.0 x 10 4 cps 8.0 x 10 4 cps Which one of the following alarms will occur? A. ROD OUT BLOCK Alarm only B. SRM UPSCALE / INOP Alarm only C. SRM UPSCALE / INOP and ROD OUT BLOCK Alarms D. ROD OUT BLOCK and NEUTRON MaN SYS TRIP Alarms Page 13 of 75
: 10. Which one of the following identifies the parameter that provides a direct input into the RPS logic (Le., does not actuate a turbine trip logic first)?
: 14. Unit Two is operating at 100% rated power. Which one of the following plant transients will cause the APRM aDA displays to automatically shift to the stability screen? A. FW-V120, FW Htrs 4 & 5 Byp Vlv, is inadvertantly opened B. Control Rod drifting into the core C. "A" Recirculation Pump Trip D. Inadvertant HPCI injection Page 14 of 75
A. Control Valve Position LVDT B. EHC Low Header Discharge Pressure C. ETS (Emergency Trip System) Pressure D. RETS (Relayed Emergency Trip Supply) Pressure Page 10 of 75
: 11. TIP traces are in progress with all TIP drawer Mode Switches in Auto.
A small steam leak in containment causes drywell pressure to rise to 2.7 psig.
Which -one of the following predicts the final TIP ball valve position indication(s) and also identifies all available location(s) for verifying their position?
A. Red light indication illuminated on the Back Panel P607 ONLY.
B. White Valve Light illuminated on each TIP drawer at Back Panel P607 ONLY.
C. Red light indication illuminated on both the P601 Panel and the Back Panel P607.
D. Green light indication illuminated on the P601 Panel and a white Valve Light illuminated on each TIP drawer at Back Panel P607.
Page 11 of 75
: 12. Unit One is commencing a startup with all SRM's fully inserted and reading approximately 1 x 105 cps. The IRM's are reading the following:
IRMA     20 on   Range 1         IRME      21 on Range 1 IRMB      28 on   Range 1         IRMF       19 on Range 1 IRMC      21 on   Range 2          IRMG      23 on Range 2 IRMD      25 on  Range  1          IRMH      20 on Range 1 The operator takes the range switch for IRM B from Range 1 to Range 3.
Which one of the following identifies the status of the IRM B downscale white light at P601 and also identifies the annunciator alarm(s) status for this condition?
A. White light illuminated; ROD OUT BLOCK alarm only.
B. White light illuminated; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms.
C. White light extinguished; ROD OUT BLOCK alarm only.
D. White light extinguished; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms.
Page 12 of 75
: 13. A reactor startup is in progress following a mid cycle forced outage in accordance with OGP-02, Approach to Criticality and Pressurization of the Reactor.
The operator notes the following SRM readings:
SRM Channel   A       6.0 x 10 5 cps SRM  Channel  B      1.0 x 105 cps SRM Channel    C      7.0 x 104 cps SRM  Channel  D      8.0 x 104 cps AlllRMs are on Range 4.
Which one of the following alarms will occur?
A. ROD OUT BLOCK Alarm only B. SRM UPSCALE / INOP Alarm only C. SRM UPSCALE / INOP and ROD OUT BLOCK Alarms D. ROD OUT BLOCK and NEUTRON MaN SYS TRIP Alarms Page 13 of 75
: 14. Unit Two is operating at 100% rated power.
Which one of the following plant transients will cause the APRM aDA displays to automatically shift to the stability screen?
A. FW-V120, FW Htrs 4 & 5 Byp Vlv, is inadvertantly opened B. Control Rod drifting into the core C. "A" Recirculation Pump Trip D. Inadvertant HPCI injection Page 14 of 75
: 15. Unit Two is at rated power when a faulty CST level instrument initiates a false low CST level input to the RCIC logic. RCIC SUCT XFER CST LO LVL annunciator is received.
: 15. Unit Two is at rated power when a faulty CST level instrument initiates a false low CST level input to the RCIC logic. RCIC SUCT XFER CST LO LVL annunciator is received.
Which one of the following identifies the correct RCIC system suction valves response?
Which one of the following identifies the correct RCIC system suction valves response?
Suppression Pool Suction Valves, E51-F029 and E51-F031, ______ _ CST Suction Valve, E51-F010, _______ _ A. immediately auto open; begins to close when both suppression pool suction valves are not full closed. B. immediately auto open; begins to close after both suppression pool suction valves are full open. C. begin to open when CST suction valve is not full open; immediately auto closes. D. begin to open only after the CST suction valve is full closed; immediatley auto closes. Page 15 of 75
Suppression Pool Suction Valves, E51-F029 and E51-F031, _ _ _ _ _ __
: 16. Following a small steam line break in the drywell, plant conditions are as follows: Drywell Pressure Drywell Average Air Temp. Torus Pressure Reactor Pressure Reactor Water Level HPCI System RCIC System 20.8 psig 292 0 F 19.0 psig 675 psig 100 inches Unavailable Started at LL2 and injecting Which one of the following identifies the current status of the ADS Initiation Timer and what operator action must be taken in accordance with PCCP? ADS Initiation Timer started; Before Drywell Average Air temperature reaches 300 0 F, ________ _ A. has; Drywell Spray is required B. has not; Drywell Spray is required C. has; Emergency Depressurization is required D. has not; Emergency Depressurization is required Page 16 of 75
CST Suction Valve, E51-F010, _ _ _ _ _ _ __
: 17. Unit Two is operating at full power. 28 RHR and 28 RHR SW pumps have been placed in Suppression Pool Cooling to lower torus temperature.
A. immediately auto open; begins to close when both suppression pool suction valves are not full closed.
A subsequent LOCA causes reactor water level to drop rapidly. Plant conditions are as follows: Drywell Pressure Torus Pressure Reactor Pressure Reactor water level E11-F0488 18.1 psig 13.7 psig 885 psig 36 inches Closed Which one of the following describes the effect these conditions will have on the status of Suppression Pool Cooling? A. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will auto open 8. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will remain closed C. ONLY the 28 RHR SW Pump will trip E 11-F0488 will auto open D. ONLY the 28 RHR SW Pump will trip E11-F0488 will remain closed Page 17 of 75
B. immediately auto open; begins to close after both suppression pool suction valves are full open.
C. begin to open when CST suction valve is not full open; immediately auto closes.
D. begin to open only after the CST suction valve is full closed; immediatley auto closes.
Page 15 of 75
: 16. Following a small steam line break in the drywell, plant conditions are as follows:
Drywell Pressure               20.8 psig Drywell Average Air Temp.       292 0 F Torus Pressure                  19.0 psig Reactor Pressure                675 psig Reactor Water Level            100 inches HPCI System                    Unavailable RCIC System                    Started at LL2 and injecting Which one of the following identifies the current status of the ADS Initiation Timer and what operator action must be taken in accordance with PCCP?
ADS Initiation Timer             started; Before Drywell Average Air temperature reaches 300 0 F, _ _ _ _ _ _ _ __
A. has; Drywell Spray is required B. has not; Drywell Spray is required C. has; Emergency Depressurization is required D. has not; Emergency Depressurization is required Page 16 of 75
: 17. Unit Two is operating at full power.
28 RHR and 28 RHR SW pumps have been placed in Suppression Pool Cooling to lower torus temperature.
A subsequent LOCA causes reactor water level to drop rapidly.
Plant conditions are as follows:
Drywell Pressure             18.1 psig Torus Pressure              13.7 psig Reactor Pressure            885 psig Reactor water level          36 inches E11-F0488                    Closed Which one of the following describes the effect these conditions will have on the status of Suppression Pool Cooling?
A. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will auto open
: 8. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will remain closed C. ONLY the 28 RHR SW Pump will trip E 11-F0488 will auto open D. ONLY the 28 RHR SW Pump will trip E11-F0488 will remain closed Page 17 of 75
: 18. During an ATWS, circuit alterations are performed per EOP-SEP-1 0, Circuit Alteration Procedure, to prevent a Group I Isolation from occurring.
: 18. During an ATWS, circuit alterations are performed per EOP-SEP-1 0, Circuit Alteration Procedure, to prevent a Group I Isolation from occurring.
Which one of the following Group I Isolation signals is defeated by this circuit alteration and how is the alteration physically accomplished?
Which one of the following Group I Isolation signals is defeated by this circuit alteration and how is the alteration physically accomplished?
A. Low Reactor Water Level; Installing jumpers B. Low Condenser Vacuum; Installing jumpers C. Low Reactor Water Level; Bypass Switch D. Low Condenser Vacuum; Bypass Switch Page 18 of 75
A. Low Reactor Water Level; Installing jumpers B. Low Condenser Vacuum; Installing jumpers C. Low Reactor Water Level; Bypass Switch D. Low Condenser Vacuum; Bypass Switch Page 18 of 75
: 19. Unit One is performing OGP-02, Approach to Criticality and Pressurization of the Reactor, with the following plant conditions:
: 19. Unit One is performing OGP-02, Approach to Criticality and Pressurization of the Reactor, with the following plant conditions:
MSIVs are open Inboard Drain Isolation valve, B21-F016, is open Outboard Drain Isolation valve, B21-F019, is open Which one of the following identifies the plant response to opening the feeder breaker to 1A RPS MG set? A. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize.
MSIVs are open Inboard Drain Isolation valve, B21-F016, is open Outboard Drain Isolation valve, B21-F019, is open Which one of the following identifies the plant response to opening the feeder breaker to 1A RPS MG set?
The B21-F016 closes. B. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize.
A. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize. The B21-F016 closes.
The B21-F019 closes. C. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize.
B. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize. The B21-F019 closes.
The B21-F016 closes. D. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize.
C. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize. The B21-F016 closes.
The B21-F019 closes. Page 19 of 75
D. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize. The B21-F019 closes.
Page 19 of 75
: 20. On Unit Two, the SRO directs the RO to place drywell sprays in service per OEOP-01-SEP-02, Drywell Spray Procedure.
: 20. On Unit Two, the SRO directs the RO to place drywell sprays in service per OEOP-01-SEP-02, Drywell Spray Procedure.
During the execution of SEP-02, SW-V111, Conv SW to Vital Header Vlv, trips on magnetics and remains in the full closed position.
During the execution of SEP-02, SW-V111, Conv SW to Vital Header Vlv, trips on magnetics and remains in the full closed position.
Which one of the following describes the impact this failure will have on RHRlDrywell Spray system and also identifies the required operator actions in accordance with SEP-02? A. loss of cooling water to RHR Room Coolers only; Open SW-V117, Nuc SW to Vital Header Vlv. B. loss of cooling water to RHR Room Coolers only; Open SW-V118, Vital Header Crosstie Vlv. C. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V117, Nuc SW to Vital Header Vlv. D. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V118, Vital Header Crosstie Vlv. Page 20 of 75
Which one of the following describes the impact this failure will have on RHRlDrywell Spray system and also identifies the required operator actions in accordance with SEP-02?
: 21. Following a dual unit Loss Of Offsite Power, which one of the following is the first makeup source to be used for filling the fuel pool in accordance with OAOP-38.0, Loss of Fuel Pool Cooling? A. Demin water header stations B. Fire Protection Hose Stations C. Condensate transfer pumps D. Emergency Diesel Makeup Pump via hoses Page 21 of 75
A. loss of cooling water to RHR Room Coolers only; Open SW-V117, Nuc SW to Vital Header Vlv.
B. loss of cooling water to RHR Room Coolers only; Open SW-V118, Vital Header Crosstie Vlv.
C. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V117, Nuc SW to Vital Header Vlv.
D. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V118, Vital Header Crosstie Vlv.
Page 20 of 75
: 21. Following a dual unit Loss Of Offsite Power, which one of the following is the first makeup source to be used for filling the fuel pool in accordance with OAOP-38.0, Loss of Fuel Pool Cooling?
A. Demin water header stations B. Fire Protection Hose Stations C. Condensate transfer pumps D. Emergency Diesel Makeup Pump via hoses Page 21 of 75
: 22. A reactor scram has occurred with the following plant conditions:
: 22. A reactor scram has occurred with the following plant conditions:
Reactor Pressure Drywell Pressure EHC Pumps 1100 psig 2.5 psig Tripped Which one of the following systems is available and allowed for use in accordance with RVCP to stabilize pressure below 1050 psig? A. HPCI B. RCIC C. Main Steam Line Drains D. Main Turbine Bypass Valves Page 22 of 75
Reactor Pressure         1100 psig Drywell Pressure         2.5 psig EHC Pumps                Tripped Which one of the following systems is available and allowed for use in accordance with RVCP to stabilize pressure below 1050 psig?
: 23. Which one of the following describes the effect that a loss of E8 will have on the Unit Two Safety Relief Valve (SRV) system? A. Inability to manually operate SRV's from the RTGB B. Inability to manually operate SRV's from the RSDP c. Loss of SRV position indication on the RTGB D. Loss of SRV position indication on the RSDP Page 23 of 75
A. HPCI B. RCIC C. Main Steam Line Drains D. Main Turbine Bypass Valves Page 22 of 75
: 24. Unit Two is in power ascension following a refueling outage. Reactor power is currently 22%. The generator has been synchronized with the grid. Load Limit is set to 110% GP-04, Increasing Turbine Load to Rated Power, directs increasing turbine Load Set to 100%. (reference provided)
: 23. Which one of the following describes the effect that a loss of E8 will have on the Unit Two Safety Relief Valve (SRV) system?
If the RO adjusts Turbine Load Set to 90%, which one of the following predicts how the plant will respond as reactor power is raised? A. When turbine load exceeds 90%, reactor pressure will increase and cause a reactor scram. B. When reactor power reaches 100% then turbine load will be 100%. C. When turbine load exceeds 90%, bypass valves will open to control turbine inlet pressure.
A. Inability to manually operate SRV's from the RTGB B. Inability to manually operate SRV's from the RSDP
: c. Loss of SRV position indication on the RTGB D. Loss of SRV position indication on the RSDP Page 23 of 75
: 24. Unit Two is in power ascension following a refueling outage.
Reactor power is currently 22%.
The generator has been synchronized with the grid.
Load Limit is set to 110%
GP-04, Increasing Turbine Load to Rated Power, directs increasing turbine Load Set to 100%.
(reference provided)
If the RO adjusts Turbine Load Set to 90%, which one of the following predicts how the plant will respond as reactor power is raised?
A. When turbine load exceeds 90%, reactor pressure will increase and cause a reactor scram.
B. When reactor power reaches 100% then turbine load will be 100%.
C. When turbine load exceeds 90%, bypass valves will open to control turbine inlet pressure.
D. When turbine load reaches 90%, bypass valves will open causing a Group I Isolation.
D. When turbine load reaches 90%, bypass valves will open causing a Group I Isolation.
Page 24 of 75
Page 24 of 75
: 25. With Unit Two operated at rated power, the 2A Feedwater Heater level reaches the Hi Hi Level setpoint due to a failed Feedwater Heater level control valve. Which one of the following choices completes the statement below? The Moisture Removal Valves will open to drain the extraction steam lines to the ______ and final feedwater temperature to the reactor will ______ _ A. Condenser; Increase B. Condenser; Decrease C. Heater Drain Deaerator; Increase D. Heater Drain Deaerator; Decrease Page 25 of 75
: 25. With Unit Two operated at rated power, the 2A Feedwater Heater level reaches the Hi Hi Level setpoint due to a failed Feedwater Heater level control valve.
: 26. Reactor pressurization is in progress per OGP-02, Approach to Criticality and Pressurization of the Reactor. The feedwater system is aligned as follows: RFP A is in Service RFP A Recirc Valve (FW-FV-V46) is open Reactor Pressure is 400 psig SULCV (FW-LV-3269) in Auto Feedwater Heater 4A and 4B inlet isolation valves are closed FW-FV-177, Feedwater Recirc Valve, throttled open with 0.5 Mlbm/hr. Which one of the following choices predicts the automatic response of the SULCV and also completes the caution statement in accordance with GP-02? If the operator throttles FW-FV-177 in the open direction, the SULCV will automatically throttle in the direction.
Which one of the following choices completes the statement below?
Opening the FW-FV-177 more than the _____ may cause feedwater line depressurization and loss of flow to the reactor vessel. A. open RFP A Recirc Valve B. closed RFP A Recirc Valve C. open SULCV D. closed SULCV Page 26 of 75
The Moisture Removal Valves will open to drain the extraction steam lines to the
______ and final feedwater temperature to the reactor will _ _ _ _ _ __
A. Condenser; Increase B. Condenser; Decrease C. Heater Drain Deaerator; Increase D. Heater Drain Deaerator; Decrease Page 25 of 75
: 26. Reactor pressurization is in progress per OGP-02, Approach to Criticality and Pressurization of the Reactor.
The feedwater system is aligned as follows:
RFP A is in Service RFP A Recirc Valve (FW-FV-V46) is open Reactor Pressure is 400 psig SULCV (FW-LV-3269) in Auto Feedwater Heater 4A and 4B inlet isolation valves are closed FW-FV-177, Feedwater Recirc Valve, throttled open with 0.5 Mlbm/hr.
Which one of the following choices predicts the automatic response of the SULCV and also completes the caution statement in accordance with GP-02?
If the operator throttles FW-FV-177 in the open direction, the SULCV will automatically throttle in the             direction. Opening the FW-FV-177 more than the
_ _ _ _ _ may cause feedwater line depressurization and loss of flow to the reactor vessel.
A. open RFP A Recirc Valve B. closed RFP A Recirc Valve C. open SULCV D. closed SULCV Page 26 of 75
: 27. Unit Two is operating at rated power with the following containment parameters:
: 27. Unit Two is operating at rated power with the following containment parameters:
Drywell Pressure Torus Pressure 0.8 psig 1.2 psig Torus venting is placed in service per 20P-1 0, Standby Gas Treatment System Operating Procedure.
Drywell Pressure       0.8 psig Torus Pressure          1.2 psig Torus venting is placed in service per 20P-1 0, Standby Gas Treatment System Operating Procedure.
Which one of the following identifies the SBGT alignment and also identifies how containment pressure will initially respond as the torus is being vented? A. Align flow through both SBGT trains; Drywell Pressure will lower at the same rate as Torus Pressure.
Which one of the following identifies the SBGT alignment and also identifies how containment pressure will initially respond as the torus is being vented?
B. Align flow through both SBGT trains; Drywell Pressure will remain steady. c. Align flow through one SBGT train only; Drywell Pressure will lower at the same rate as Torus Pressure.
A. Align flow through both SBGT trains; Drywell Pressure will lower at the same rate as Torus Pressure.
D. Align flow through one SBGT train only; Drywell Pressure will remain steady. Page 27 of 75
B. Align flow through both SBGT trains; Drywell Pressure will remain steady.
: 28. Unit Two is operating at rated power with UPS in its normal alignment.
: c. Align flow through one SBGT train only; Drywell Pressure will lower at the same rate as Torus Pressure.
Subsequently, offsite power is lost. DG3 and DG4 are unavailable.
D. Align flow through one SBGT train only; Drywell Pressure will remain steady.
No electrical buses have been cross-tied.
Page 27 of 75
Which one of the following choices completes the statements below? The UPS Primary Inverter is currently being fed from DC Switchboard
: 28. Unit Two is operating at rated power with UPS in its normal alignment. Subsequently, offsite power is lost. DG3 and DG4 are unavailable. No electrical buses have been cross-tied.
_____ _ If the Primary Inverter fails, _______ _ A. 2A. UPS loads will be de-energized.
Which one of the following choices completes the statements below?
: 8. 2B. UPS loads will be de-energized.
The UPS Primary Inverter is currently being fed from DC Switchboard _ _ _ _ __
C. 2A. UPS will auto transfer to an alternate source. D.2B. UPS will auto transfer to an alternate source. Page 28 of 75
If the Primary Inverter fails, _ _ _ _ _ _ __
A. 2A.
UPS loads will be de-energized.
: 8. 2B.
UPS loads will be de-energized.
C. 2A.
UPS will auto transfer to an alternate source.
D.2B.
UPS will auto transfer to an alternate source.
Page 28 of 75
: 29. Unit One is operating at full power with the following plant conditions:
: 29. Unit One is operating at full power with the following plant conditions:
Suppression Pool RHR RHRSW 96&deg; F due to HPCI Surveillance B Loop in SPC (B/D pumps running) B Loop in service (B/D pumps running) A Loss of Offsite Power (LOOP) occurs on both Units and DG2 fails to start. Which one of the following identifies the impact of the LOOP on the 1-E 11-F024B and the 1 D RHR Pump and also identifies the required action in accordance with OAOP-36.1, Loss of any 4160V Buses or 480V E-Buses, to support EOP actions? A. 1-E11-F024B Valve only has lost power. Crosstie E2 to E4. B. 1-E11-F024B Valve only has IO'st power. Crosstie E1 to E2. C. 1-E11-F024B Valve and the 1 D RHR pump have lost power. Crosstie E2 to E4. D. 1-E11-F024B Valve and the 1 D RHR pump have lost power. Crosstie E1 to E2. Page 29 of 75
Suppression Pool             96&deg; F due to HPCI Surveillance RHR                          B Loop in SPC (B/D pumps running)
: 30. Unit Two is operating at 30% reactor power when a complete loss of the Vital UPS System occurs. Which one of the following describes how this loss will affect RFPT operation?
RHRSW                        B Loop in service (B/D pumps running)
A. RTGB trip pushbutton function is lost. B. overspeed trip circuit will lose power causing RFPT Trip. c. vibration instrumentation will lose power causing RFPT Trip. D. RFPT woodward control trip circuits will be powered from their redundant power supplies.
A Loss of Offsite Power (LOOP) occurs on both Units and DG2 fails to start.
Which one of the following identifies the impact of the LOOP on the 1-E 11-F024B and the 1D RHR Pump and also identifies the required action in accordance with OAOP-36.1, Loss of any 4160V Buses or 480V E-Buses, to support EOP actions?
A. 1-E11-F024B Valve only has lost power.
Crosstie E2 to E4.
B. 1-E11-F024B Valve only has IO'st power.
Crosstie E1 to E2.
C. 1-E11-F024B Valve and the 1D RHR pump have lost power.
Crosstie E2 to E4.
D. 1-E11-F024B Valve and the 1D RHR pump have lost power.
Crosstie E1 to E2.
Page 29 of 75
: 30. Unit Two is operating at 30% reactor power when a complete loss of the Vital UPS System occurs.
Which one of the following describes how this loss will affect RFPT operation?
A. RTGB trip pushbutton function is lost.
B. overspeed trip circuit will lose power causing RFPT Trip.
: c. vibration instrumentation will lose power causing RFPT Trip.
D. RFPT woodward control trip circuits will be powered from their redundant power supplies.
Page 30 of 75
Page 30 of 75
: 31. Which one of the following choices completes the statements below regarding how a total loss of UPS will affect the Digital Feedwater Level Control System Controllers.
: 31. Which one of the following choices completes the statements below regarding how a total loss of UPS will affect the Digital Feedwater Level Control System Controllers.
Level Setpoint adjustment is _____ _ Level Setdown ______ occur following a reactor scram. A. available; will B. available; will not C. not available; will D. not available; will not Page 31 of 75
Level Setpoint adjustment is _ _ _ _ __
: 32. Which one of the following is the power supply to the Outboard MSIV's DC solenoids on Unit One? A. Diy 1 Switchboard 21A. B. Diy 2 Switchboard 22B. C. Diy 1 Switchboard 1 A. D. Diy 2 Switchboard 1 B. Page 32 of 75
Level Setdown_ _ _ _ _ _ occur following a reactor scram.
A. available; will B. available; will not C. not available; will D. not available; will not Page 31 of 75
: 32. Which one of the following is the power supply to the Outboard MSIV's DC solenoids on Unit One?
A. Diy 1 Switchboard 21A.
B. Diy 2 Switchboard 22B.
C. Diy 1 Switchboard 1A.
D. Diy 2 Switchboard 1B.
Page 32 of 75
: 33. Unit Two experiences a Loss of Off-Site Power (LOOP) with DG4 under clearance.
: 33. Unit Two experiences a Loss of Off-Site Power (LOOP) with DG4 under clearance.
Which one of the following predicts the NSW and CSW pump response when the DG3 ties to bus E3? A. NSW pump 2A and CSW pump 2A start immediately.
Which one of the following predicts the NSW and CSW pump response when the DG3 ties to bus E3?
B. NSW pump 2A and CSW pump 2A start after a 5 second time delay. C. NSW pump 2A starts immediately and CSW pump 2A does not start. D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not start. Page 33 of 75
A. NSW pump 2A and CSW pump 2A start immediately.
: 34. Unit Two is operating at rated power with the A SJAE train in service at Full Load. A clearance tagging error results in the closure of the SJE-V15, Recombiner Preheater Steam Supply Valve followed by the following alarm: RECOMBINER INLET TEMPERATURE LOW Which one of the following describes the effect these conditions will have on Main Condenser vacuum and downstream Hydrogen concentrations?
B. NSW pump 2A and CSW pump 2A start after a 5 second time delay.
Main Condenser vacuum will -------Hydrogen concentrations will* ______ _ A. remain steady; increase B. remain steady; decrease C. degrade; increase D. degrade; decrease Page 34 of 75
C. NSW pump 2A starts immediately and CSW pump 2A does not start.
: 35. Which one of the following identifies the power supplies for the Electric Driven Fire Pump? The normal power supply is from: A. E2, with an automatic transfer to E4 on loss of power B. E4, with an automatic transfer t9 E2 on loss of power C. E2, must be manually transfered to E4 on loss of power D. E4, must be manually transfered to E2 on loss of power Page 35 of 75
D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not start.
: 36. A plant transient and subsequent safety relief valve malfunction results in reactor steam dome pressure reaching 1300 psig. Which one of the following choices completes the following statements?
Page 33 of 75
: 34. Unit Two is operating at rated power with the A SJAE train in service at Full Load.
A clearance tagging error results in the closure of the SJE-V15, Recombiner Preheater Steam Supply Valve followed by the following alarm:
RECOMBINER INLET TEMPERATURE LOW Which one of the following describes the effect these conditions will have on Main Condenser vacuum and downstream Hydrogen concentrations?
Main Condenser vacuum will - - - - - - -
Hydrogen concentrations will* _ _ _ _ _ __
A. remain steady; increase B. remain steady; decrease C. degrade; increase D. degrade; decrease Page 34 of 75
: 35. Which one of the following identifies the power supplies for the Electric Driven Fire Pump?
The normal power supply is from:
A. E2, with an automatic transfer to E4 on loss of power B. E4, with an automatic transfer t9 E2 on loss of power C. E2, must be manually transfered to E4 on loss of power D. E4, must be manually transfered to E2 on loss of power Page 35 of 75
: 36. A plant transient and subsequent safety relief valve malfunction results in reactor steam dome pressure reaching 1300 psig.
Which one of the following choices completes the following statements?
Reactor vessel design pressure ____ been exceeded.
Reactor vessel design pressure ____ been exceeded.
Tech Spec 2.1.2, Reactor Coolant System Pressure Safety Limit ____ been exceeded.
Tech Spec 2.1.2, Reactor Coolant System Pressure Safety Limit _ _ _ _ been exceeded.
A. has; has B. has; has not C. has not; has D. has not; has not Page 36 of 75
A. has; has B. has; has not C. has not; has D. has not; has not Page 36 of 75
: 37. Unit Two is operating at 19% power with the turbine on the turning gear when the following indications are observed:
: 37. Unit Two is operating at 19% power with the turbine on the turning gear when the following indications are observed:
SJAE Trains AOG System Outlet Flow Condenser Vacuum Steam Seal header pressure Both in half load 80 scfm and slowly rising Slowly lowering o psig Which one of the following identifies the required operator action in acordance with OAOP-37, Low Condenser Vacuum? A. Place B SJAE in full load B. Start the mechanical vacuum pump C. Throttle open MVD-S2, Steam Seal Bypass Valve D. Throttle open the SJAE Condensate Recirculation Valve, CO-FV-49 Page 37 of 75
SJAE Trains                         Both in half load AOG System Outlet Flow             80 scfm and slowly rising Condenser Vacuum                    Slowly lowering Steam Seal header pressure          o psig Which one of the following identifies the required operator action in acordance with OAOP-37, Low Condenser Vacuum?
: 38. A LOCA occurs on Unit One concurrent with a LOOP on both Units. A DG3 lockout occurs due to a protective relay actuation.
A. Place B SJAE in full load B. Start the mechanical vacuum pump C. Throttle open MVD-S2, Steam Seal Bypass Valve D. Throttle open the SJAE Condensate Recirculation Valve, CO-FV-49 Page 37 of 75
Which one of the following is the response of the Unit One Low Pressure ECCS systems? There will be injection from ____ of Core Spray. There will be injection from two RHR pumps in ___ _ A. both loops only one loop 8. only one loop only one loop C. both loops both loops D. only one loop both loops Page 38 of 75
: 38. A LOCA occurs on Unit One concurrent with a LOOP on both Units.
: 39. Which one of the following is the effect of a loss of the 24 VDC power supply located in RPS Analog Trip Cabinet A 1? A. A1 remains energized from B1 B. A 1 remains energizes from A2 C. A 1 loses power and trip functions occur D. A 1 loses power and trip functions do not occur Page 39 of 75
A DG3 lockout occurs due to a protective relay actuation.
: 40. Which one of the following identifies the reason that the Turbine Bypass Valves will open following a main turbine trip from full power? A. Prevent overspeeding of the main turbine during the coastdown.
Which one of the following is the response of the Unit One Low Pressure ECCS systems?
B. Prevent over pressurization of the MSR cross-over piping. c. Prevent over pressurization of the reactor vessel. D. Prevent rupture of the LP Turbine rupture discs. Page 40 of 75
There will be injection from _ _ _ _ of Core Spray.
: 41. Which one of the following Scram Immediate Operator actions has a different setpoint between Unit One and Unit Two? A. Tripping of the main turbine. B. Tripping of the first feed pump. C. Master level controller setpoint setdown. D. Placing the reactor mode switch to Shutdown.
There will be injection from two RHR pumps in _ _ __
A. both loops only one loop
: 8. only one loop only one loop C. both loops both loops D. only one loop both loops Page 38 of 75
: 39. Which one of the following is the effect of a loss of the 24 VDC power supply located in RPS Analog Trip Cabinet A 1?
A. A1 remains energized from B1 B. A 1 remains energizes from A2 C. A 1 loses power and trip functions occur D. A 1 loses power and trip functions do not occur Page 39 of 75
: 40. Which one of the following identifies the reason that the Turbine Bypass Valves will open following a main turbine trip from full power?
A. Prevent overspeeding of the main turbine during the coastdown.
B. Prevent over pressurization of the MSR cross-over piping.
: c. Prevent over pressurization of the reactor vessel.
D. Prevent rupture of the LP Turbine rupture discs.
Page 40 of 75
: 41. Which one of the following Scram Immediate Operator actions has a different setpoint between Unit One and Unit Two?
A. Tripping of the main turbine.
B. Tripping of the first feed pump.
C. Master level controller setpoint setdown.
D. Placing the reactor mode switch to Shutdown.
Page 41 of 75
Page 41 of 75
: 42. Unit One was operating at full power when a scram ocurred due to a loss of drywell cooling with the following plant conditions.
: 42. Unit One was operating at full power when a scram ocurred due to a loss of drywell cooling with the following plant conditions.
Reactor water level Drywell pressure High Level Trip A High Level Trip B High Level Trip C 155 inches (slowly lowering) 2.1 psig (slowly rising) Amber light extinguished Amber light illuminated Amber light illuminated Which one of the following is the status of the reactor feed pumps and HPCI system? The Reactor feed pump turbines:
Reactor water level                 155 inches (slowly lowering)
A. are running and HPCI is injecting to the vessel. B. are tripped, but HPCI is still injecting to the vessel. C. are running, but HPCI is tripped. D. and HPCI are both tripped. Page 42 of 75
Drywell pressure                    2.1 psig (slowly rising)
High Level Trip A                    Amber light extinguished High Level Trip B                    Amber light illuminated High Level Trip C                    Amber light illuminated Which one of the following is the status of the reactor feed pumps and HPCI system?
The Reactor feed pump turbines:
A. are running and HPCI is injecting to the vessel.
B. are tripped, but HPCI is still injecting to the vessel.
C. are running, but HPCI is tripped.
D. and HPCI are both tripped.
Page 42 of 75
: 43. Unit One is at rated power when a scram signal is received.
: 43. Unit One is at rated power when a scram signal is received.
Reactor water level drops and RWCU isolates.
Reactor water level drops and RWCU isolates.
Line 193: Line 421:
A. Fuel Zone (N036/N037) instruments only B. Wide range (N026A1B) instruments only C. Both Fuel Zone (N036/N037) and Wide Range (N026A1B) instruments D. Neither Fuel Zone (N036/N037) nor Wide Range (N026A1B) instruments were available.
A. Fuel Zone (N036/N037) instruments only B. Wide range (N026A1B) instruments only C. Both Fuel Zone (N036/N037) and Wide Range (N026A1B) instruments D. Neither Fuel Zone (N036/N037) nor Wide Range (N026A1B) instruments were available.
Page 43 of 75
Page 43 of 75
: 44. Unit Two was operating at 100% power when a steam line break caused drywell pressure to rise. Which one of the following identifies the norrmal temperature relationship between compensated and uncompensated level instrument legs and also identifies the level instruments that will first be affected as drywell temperature rises due to the steam leak? A. The compensated level instrument legs are at a higher temperature than the uncompensated legs, the compensated level instrument legs will boil first. 8. The uncompensated level instrument legs are at a higher temperature than the compensated legs, the uncompensated level instrument legs will boil first. c. Both instrument legs are at the same temperature.
: 44. Unit Two was operating at 100% power when a steam line break caused drywell pressure to rise.
The compensated level instrument legs will boil first. D. Both instrument legs are at the same temperature.
Which one of the following identifies the norrmal temperature relationship between compensated and uncompensated level instrument legs and also identifies the level instruments that will first be affected as drywell temperature rises due to the steam leak?
The uncompensated level instrument legs will boil first. Page 44 of 75
A. The compensated level instrument legs are at a higher temperature than the uncompensated legs, the compensated level instrument legs will boil first.
: 45. A turbine trip and reactor scram occurs on Unit One. The following indications are on the full core display: Green Lights Lit Red lights Lit 136 rods one rod Which one of the following choices completes the statements below? RWM Shutdown Confirmation Screen will display __ _ The reactor remain shutdown under all conditions without boron. ---A. Shutdown:
: 8. The uncompensated level instrument legs are at a higher temperature than the compensated legs, the uncompensated level instrument legs will boil first.
NO will B. Shutdown:
: c. Both instrument legs are at the same temperature. The compensated level instrument legs will boil first.
NO will not c. Shutdown:
D. Both instrument legs are at the same temperature. The uncompensated level instrument legs will boil first.
YES will D. Shutdown:
Page 44 of 75
YES will not Page 45 of 75
: 45. A turbine trip and reactor scram occurs on Unit One. The following indications are on the full core display:
: 46. While reducing reactor pressure to place Shutdown Cooling in service in accordance with OAOP-32.0, Plant Shutdown from Outside Control Room, the following reactor pressure readings were recorded at the indicated times: 1200 1 000 psig 1300 425 psig 1400 100 psig 1500 25 psig (reference provided)
Green Lights Lit     136 rods Red lights Lit       one rod Which one of the following choices completes the statements below?
RWM Shutdown Confirmation Screen will display _ __
The reactor - - - remain shutdown under all conditions without boron.
A. Shutdown: NO will B. Shutdown: NO will not
: c. Shutdown: YES will D. Shutdown: YES will not Page 45 of 75
: 46. While reducing reactor pressure to place Shutdown Cooling in service in accordance with OAOP-32.0, Plant Shutdown from Outside Control Room, the following reactor pressure readings were recorded at the indicated times:
1200   1000 psig 1300   425 psig 1400   100 psig 1500   25 psig (reference provided)
Which one of the following choices completes the following statement?
Which one of the following choices completes the following statement?
The reactor cooldown rate specified in OAOP-32.0:
The reactor cooldown rate specified in OAOP-32.0:
A. has not* been exceeded B. was exceeded between 1200 and 1300 C. was exceeded between 1300 and 1400 D. was exceeded between 1400 and 1500 Page 46 of 75
A. has not* been exceeded B. was exceeded between 1200 and 1300 C. was exceeded between 1300 and 1400 D. was exceeded between 1400 and 1500 Page 46 of 75
: 47. Unit Two is operating at rated power when the TCC-TV-607, MG Set Oil Cooler 2A Temperature Control Valve, fails to the closed position.
: 47. Unit Two is operating at rated power when the TCC-TV-607, MG Set Oil Cooler 2A Temperature Control Valve, fails to the closed position.
Which one of the following describes how this loss of cooling will affect the Recirculation MG Sets? When the high lube oil temperature in the fluid drive reaches: A. 190&deg; F the scoop tube will lock and the drive motor breaker remains closed. B. 190&deg; F the drive motor breaker will trip and the SCOOP tube will lock. C. 210&deg; F the scoop tube will lock and the drive motor breaker remains closed. D. 210&deg; F the drive motor breaker will trip and the scoop tube will lock. Page 47 of 75
Which one of the following describes how this loss of cooling will affect the Recirculation MG Sets?
: 48. Which one of the following identifies the signal(s) that will initiate the Backup Nitrogen System, including the reason for the Backup Nitrogen System? A. Low Reactor Building Instrument Air header or Core Spray LOCA signal. Ensures operability of ADS valves and Inboard MSIV's. B. Core Spray LOCA signal ONLY. Ensures operability of ADS valves and Inboard MSIV's. C. Low Reactor Building Instrument Air header or Core Spray LOCA signal. Ensures operability of ADS valves and the Hardened Wetwell Vent Valves. D. Core Spray LOCA signal ONLY. Ensures operability of ADS valves and the Hardened Wetwell Vent Valves. Page 48 of 75
When the high lube oil temperature in the fluid drive reaches:
A. 190&deg; F the scoop tube will lock and the drive motor breaker remains closed.
B. 190&deg; F the drive motor breaker will trip and the SCOOP tube will lock.
C. 210&deg; F the scoop tube will lock and the drive motor breaker remains closed.
D. 210&deg; F the drive motor breaker will trip and the scoop tube will lock.
Page 47 of 75
: 48. Which one of the following identifies the signal(s) that will initiate the Backup Nitrogen System, including the reason for the Backup Nitrogen System?
A. Low Reactor Building Instrument Air header or Core Spray LOCA signal.
Ensures operability of ADS valves and Inboard MSIV's.
B. Core Spray LOCA signal ONLY.
Ensures operability of ADS valves and Inboard MSIV's.
C. Low Reactor Building Instrument Air header or Core Spray LOCA signal.
Ensures operability of ADS valves and the Hardened Wetwell Vent Valves.
D. Core Spray LOCA signal ONLY.
Ensures operability of ADS valves and the Hardened Wetwell Vent Valves.
Page 48 of 75
: 49. Unit One shutdown is in progress with the following plant conditions:
: 49. Unit One shutdown is in progress with the following plant conditions:
RWCU is in service. Recirc Pump B is running. SDC A Loop has been lost. Feed and bleed has been established.
RWCU is in service.
Reactor Coolant Temperature is 190 0 F and lowering slowly. Given this condition in progress, which one of the following identifies the PREFERRED indication to use to determine vessel metal temperature response in accordance with 1 PT-01. 7, Heatup/Cooldown Monitoring, including the reason? A. Bottom head metal temperature; metal temperature response leads the coolant temperature response during a cooldown.
Recirc Pump B is running.
SDC A Loop has been lost.
Feed and bleed has been established.
Reactor Coolant Temperature is 190 0 F and lowering slowly.
Given this condition in progress, which one of the following identifies the PREFERRED indication to use to determine vessel metal temperature response in accordance with 1PT-01. 7, Heatup/Cooldown Monitoring, including the reason?
A. Bottom head metal temperature; metal temperature response leads the coolant temperature response during a cooldown.
B. Bottom head metal temperature; coolant temperature response leads the metal temperature response during a cooldown.
B. Bottom head metal temperature; coolant temperature response leads the metal temperature response during a cooldown.
C. Bottom drain coolant temperature; metal temperature response leads the coolant temperature response during a cooldown.
C. Bottom drain coolant temperature; metal temperature response leads the coolant temperature response during a cooldown.
D. Bottom drain coolant temperature; coolant temperature response leads the metal temperature response during a cooldown.
D. Bottom drain coolant temperature; coolant temperature response leads the metal temperature response during a cooldown.
Page 49 of 75
Page 49 of 75
: 50. Which one of the following is the primary containment pressure limit and the required action before this limit is reached in accordance with PCCP? A. 62 psig Vent primary containment irrespective of offsite release rate B. 62 psig Vent primary containment only if offsite release rate do not exceed aDCM limits C. 70 psig Vent primary containment irrespective of offsite release rate D. 70 psig Vent primary containment only if offsite release rate do not exceed aDCM limits Page 50 of 75
: 50. Which one of the following is the primary containment pressure limit and the required action before this limit is reached in accordance with PCCP?
: 51. Unit Two is operating at rated power with EHC Pressure Regulator B out of service. Pressure Regulator A output fails low. (Reference provided)
A. 62 psig Vent primary containment irrespective of offsite release rate B. 62 psig Vent primary containment only if offsite release rate do not exceed aDCM limits C. 70 psig Vent primary containment irrespective of offsite release rate D. 70 psig Vent primary containment only if offsite release rate do not exceed aDCM limits Page 50 of 75
Which one of the following identifies how reactor pressure will respond and also identifies the availability of the bypass valves following the reactor scram? A. Reactor pressure will decrease and a scram will occur on a Group I Isolation.
: 51. Unit Two is operating at rated power with EHC Pressure Regulator B out of service.
Bypass valves are not available using the Bypass Valve Jack. B. Reactor pressure will increase and a scram will occur on high pressure.
Pressure Regulator A output fails low.
Bypass valves will still be available using the Bypass Valve Jack. C. Reactor pressure will decrease and a scram will occur on a Group I Isolation.
(Reference provided)
Bypass valves will still be available using the Bypass Valve Jack. D. Reactor pressure will increase and a scram will occur on high pressure.
Which one of the following identifies how reactor pressure will respond and also identifies the availability of the bypass valves following the reactor scram?
Bypass valves are not available using the Bypass Valve Jack. Page 51 of 75
A. Reactor pressure will decrease and a scram will occur on a Group I Isolation.
Bypass valves are not available using the Bypass Valve Jack.
B. Reactor pressure will increase and a scram will occur on high pressure.
Bypass valves will still be available using the Bypass Valve Jack.
C. Reactor pressure will decrease and a scram will occur on a Group I Isolation.
Bypass valves will still be available using the Bypass Valve Jack.
D. Reactor pressure will increase and a scram will occur on high pressure.
Bypass valves are not available using the Bypass Valve Jack.
Page 51 of 75
: 52. Unit One failed to scram with the following plant conditions:
: 52. Unit One failed to scram with the following plant conditions:
Reactor Power RPV Water Level RPV Pressure Suppression Pool 3% -55 inches (N036) 800 psig 115 0 F Which one of the following actions, if any, is required to open suppression pool cooling valves (E 11-F024 and E 11-F028)?
Reactor Power       3%
A. Place the Think Switch to Manual only. B. No overrides are necessary.
RPV Water Level     -55 inches (N036)
RPV Pressure        800 psig Suppression Pool    1150 F Which one of the following actions, if any, is required to open suppression pool cooling valves (E 11-F024 and E 11-F028)?
A. Place the Think Switch to Manual only.
B. No overrides are necessary.
: c. Place the Think Switch to Manual first and then bypass the 2/3rd core height interlock.
: c. Place the Think Switch to Manual first and then bypass the 2/3rd core height interlock.
D. Bypass the 2/3rd core height interlock first and then place the Think Switch to Manual. Page 52 of 75
D. Bypass the 2/3rd core height interlock first and then place the Think Switch to Manual.
: 53. Unit Two is operating at power with a leaking SRV. The ERFIS indication for the Suppression Pool Temperature has just turned RED. Which one of the following identifies the temperature when ERFIS first turns RED and also identifies which procedure that must be entered? A. 95 0 F PCCP B. 105 0 F PCCP C. 95 0 F OAOP-14.0, Abnormal Primary Containment Conditions D. 105 0 F OAOP-14.0, Abnormal Primary Containment Conditions Page 53 of 75
Page 52 of 75
: 54. Conditions on Unit Two have degraded to where the Drywell Air Temperature is 340 0 F. Which one of the following identifies the components whose enviromental qualification is affected by this temperature in accordance with 001-37.8, Primary Containment Control Procedure Basis Document?
: 53. Unit Two is operating at power with a leaking SRV. The ERFIS indication for the Suppression Pool Temperature has just turned RED.
Which one of the following identifies the temperature when ERFIS first turns RED and also identifies which procedure that must be entered?
A. 95 0 F PCCP B. 105 0 F PCCP C. 95 0 F OAOP-14.0, Abnormal Primary Containment Conditions D. 105 0 F OAOP-14.0, Abnormal Primary Containment Conditions Page 53 of 75
: 54. Conditions on Unit Two have degraded to where the Drywell Air Temperature is 340 0 F.
Which one of the following identifies the components whose enviromental qualification is affected by this temperature in accordance with 001-37.8, Primary Containment Control Procedure Basis Document?
A. Inboard MSIV solenoids B. SRV solenoids C. Torus to Drywell Vacuum Breakers D. CAC 4409 and 4410 Hydrogen Analyzers Page 54 of 75
A. Inboard MSIV solenoids B. SRV solenoids C. Torus to Drywell Vacuum Breakers D. CAC 4409 and 4410 Hydrogen Analyzers Page 54 of 75
: 55. Which one of the following is the suppression pool level when a manual reactor scram is first required including the required action in accordance with PCCP? A. -5.5 feet Anticipation of Emergency Depressurization is required.
: 55. Which one of the following is the suppression pool level when a manual reactor scram is first required including the required action in accordance with PCCP?
A. -5.5 feet Anticipation of Emergency Depressurization is required.
B. -5.5 feet Emergency Depressurization is required C. -6.5 feet Anticipation of Emergency Depressurization is required.
B. -5.5 feet Emergency Depressurization is required C. -6.5 feet Anticipation of Emergency Depressurization is required.
D. -6.5 feet Emergency Depressurization is required Page 55 of 75
D. -6.5 feet Emergency Depressurization is required Page 55 of 75
: 56. During a low reactor water level emergency on Unit One, the Reactor Vessel Control Procedure directs the operator to enter the Steam Cooling Procedure.
: 56. During a low reactor water level emergency on Unit One, the Reactor Vessel Control Procedure directs the operator to enter the Steam Cooling Procedure.
Which one of the following describes the reason Steam Cooling Procedure is performed?
Which one of the following describes the reason Steam Cooling Procedure is performed?
The Steam Cooling Procedure utilizes steam cooling heat transfer ____ _ injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed of. A. with 1500 B. with 1800 C. without 1500 D. without 1800 Page 56 of 75
The Steam Cooling Procedure utilizes steam cooling heat transfer _ _ _ __
injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed             of.
A. with 1500 B. with 1800 C. without 1500 D. without 1800 Page 56 of 75
: 57. Which one of the following statements identifies the reason SCCP directs emergency depressurization based on temperature in accordance with 001-37.9, Secondary Containment Control Procedure Basis Document?
: 57. Which one of the following statements identifies the reason SCCP directs emergency depressurization based on temperature in accordance with 001-37.9, Secondary Containment Control Procedure Basis Document?
The reason the emergency depressurization is performed due to secondary containment temperature is to: A. preserve personnel access into the reactor building.
The reason the emergency depressurization is performed due to secondary containment temperature is to:
A. preserve personnel access into the reactor building.
B. ensure ODCM site boundary dose limits are not exceeded.
B. ensure ODCM site boundary dose limits are not exceeded.
C. prevent damage to equipment required for safe shutdown.
C. prevent damage to equipment required for safe shutdown.
D. prevent an unmonitored release. Page 57 of 75
D. prevent an unmonitored release.
Page 57 of 75
: 58. During the execution of emergency operating procedures, the operator has restarted Reactor Building HVAC per OEOP-01-SEP-04, Reactor Building HVAC Restart Procedure.
: 58. During the execution of emergency operating procedures, the operator has restarted Reactor Building HVAC per OEOP-01-SEP-04, Reactor Building HVAC Restart Procedure.
Which one of the following subsequent conditions would cause the Reactor Building Supply and Exhaust Isolation Dampers to reclose? A. Reactor water level lowers below LL2. B. Drywell pressure rises above 1.7 psig. C. PROCESS OFF-GAS VENT PIPE RAD HI-HI alarm is received.
Which one of the following subsequent conditions would cause the Reactor Building Supply and Exhaust Isolation Dampers to reclose?
A. Reactor water level lowers below LL2.
B. Drywell pressure rises above 1.7 psig.
C. PROCESS OFF-GAS VENT PIPE RAD HI-HI alarm is received.
D. REACTOR BUILDING VENT EXHAUST TEMP HI alarm is received.
D. REACTOR BUILDING VENT EXHAUST TEMP HI alarm is received.
Page 58 of 75
Page 58 of 75
: 59. The unit is in an ATWS with the following conditions:
: 59. The unit is in an ATWS with the following conditions:
SLC Tank Reactor Water Level Reactor Power 30% and lowering Being maintained 60 to 90 inches APRMs downscale Which one of the following choices completes the statement below in accordance with LPC? Hot Shutdown Boron Injection Weight been injected and RPV water level ____ required to be raised at this tank level. A. has is B. has is not C. has not is D. has not is not Page 59 of 75
SLC Tank                         30% and lowering Reactor Water Level              Being maintained 60 to 90 inches Reactor Power                    APRMs downscale Which one of the following choices completes the statement below in accordance with LPC?
: 60. Unit Two is operating under accident conditions with the following plant conditions due to a steam leak on HPCI: Reactor Water Level Reactor Pressure Injection sources available Offsite Release HPCI Room Temperatures Suppression Pool Temperature  
Hot Shutdown Boron Injection Weight               been injected and RPV water level
-20 inches 900 psig HPClonly Alert declared 140 0 F 130 0 F Which one of the following identifies the required HPCI operation action in accordance with RRCP and also identifies the reason for taking the action? A. HPCI should be left running It is required to be operated by the EOP's B. HPCI should be isolated It should have isolated on room high temperature C. HPCI should be left running Steam leak detection was overridden per RVCP D. HPCI should be isolated To prevent damage to the HPCI pump due to high suppression pool temperatures Page 60 of 75
_ _ _ _ required to be raised at this tank level.
: 61. During normal full power operation of Unit Two the following alarms and indications are noted: SERVICE AIR PRESS LOW alarm RB INSTR AIR RECEIVER 2A PRESS LOW RB INSTR AIR RECEIVER 2B PRESS LOW Instrument Air header pressure Service Air header pressure Sealed In Not in Alarm Not in Alarm 100 psig 100 psig Which one of the following actions is required in accordance with OAOP-20, Pneumatic System Failures?
A. has is B. has is not C. has not is D. has not is not Page 59 of 75
A. Start SBGT. B. Close the manual Noninterruptible Isolation Valves. C. Close the Service Air isolation valves, PV-706-1 and PV-706-2.
: 60. Unit Two is operating under accident conditions with the following plant conditions due to a steam leak on HPCI:
D. Close the Reactor Building Isolation Dampers. Page 61 of 75
Reactor Water Level             -20 inches Reactor Pressure                 900 psig Injection sources available     HPClonly Offsite Release                 Alert declared HPCI Room Temperatures           140 0 F Suppression Pool Temperature     130 0 F Which one of the following identifies the required HPCI operation action in accordance with RRCP and also identifies the reason for taking the action?
A. HPCI should be left running It is required to be operated by the EOP's B. HPCI should be isolated It should have isolated on room high temperature C. HPCI should be left running Steam leak detection was overridden per RVCP D. HPCI should be isolated To prevent damage to the HPCI pump due to high suppression pool temperatures Page 60 of 75
: 61. During normal full power operation of Unit Two the following alarms and indications are noted:
SERVICE AIR PRESS LOW alarm                     Sealed In RB INSTR AIR RECEIVER 2A PRESS LOW               Not in Alarm RB INSTR AIR RECEIVER 2B PRESS LOW               Not in Alarm Instrument Air header pressure                   100 psig Service Air header pressure                       100 psig Which one of the following actions is required in accordance with OAOP-20, Pneumatic System Failures?
A. Start SBGT.
B. Close the manual Noninterruptible Isolation Valves.
C. Close the Service Air isolation valves, PV-706-1 and PV-706-2.
D. Close the Reactor Building Isolation Dampers.
Page 61 of 75
: 62. Which one of the following identifies the exact location of the RBCCW liquid process radiation detector (D12-RM-K606) and the function(s) it provides?
: 62. Which one of the following identifies the exact location of the RBCCW liquid process radiation detector (D12-RM-K606) and the function(s) it provides?
A. RBCCW pump suction header; alarm function only B. RBCCW pump suction header; alarm and isolation function C. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm function only D. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm and isolation function Page 62 of 75
A. RBCCW pump suction header; alarm function only B. RBCCW pump suction header; alarm and isolation function C. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm function only D. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm and isolation function Page 62 of 75
: 63. The SS has determined that the control room personnel must don SCBAs (Scott AP50) due to smoke in the control room from a plant fire on site. Which one of the following is an indication that a SCBA is low on air? A. Air regulator bypass valve fails open. B. Air regulator bypass valve fails closed. C. Audible high pitched beep emitting from face piece. D. Vibralert alarm in the regulator that vibrates the face piece. Page 63 of 75
: 63. The SS has determined that the control room personnel must don SCBAs (Scott AP50) due to smoke in the control room from a plant fire on site.
: 64. Generator MVARs are indicating 0 MVARs. Which one of the following identifies the actions required to restore MVARs to the limits specified in OP-27, Generator and Excitation System Operating Procedure?
Which one of the following is an indication that a SCBA is low on air?
Coordinate with the Load Dispatcher to either: A. Raise the auto voltage regulator or place a capacitor bank in service B. Lower the auto voltage regulator or place a capacitor bank in service C. Raise the auto voltage regulator or remove a capacitor bank from service D. Lower the auto voltage regulator or remove a capacitor bank from service Page 64 of 75
A. Air regulator bypass valve fails open.
B. Air regulator bypass valve fails closed.
C. Audible high pitched beep emitting from face piece.
D. Vibralert alarm in the regulator that vibrates the face piece.
Page 63 of 75
: 64. Generator MVARs are indicating 0 MVARs.
Which one of the following identifies the actions required to restore MVARs to the limits specified in OP-27, Generator and Excitation System Operating Procedure?
Coordinate with the Load Dispatcher to either:
A. Raise the auto voltage regulator or place a capacitor bank in service B. Lower the auto voltage regulator or place a capacitor bank in service C. Raise the auto voltage regulator or remove a capacitor bank from service D. Lower the auto voltage regulator or remove a capacitor bank from service Page 64 of 75
: 65. A grid disturbance occurs with the following Unit Two plant parameters:
: 65. A grid disturbance occurs with the following Unit Two plant parameters:
Generator Load Generator Reactive Load Generator Gas Pressure (Reference provided) 980 MWe 160 MVARs, out 50 psig Which one of the following identifies all of the available options that will place the Unit within the Estimated Capability Curve? A. Raise Gas Pressure or lower MWe. B. Raise Gas Pressure or raise MVARs. C. Raise Gas Pressure only. D. Lower MWe only. Page 65 of-75
Generator Load                     980 MWe Generator Reactive Load             160 MVARs, out Generator Gas Pressure             50 psig (Reference provided)
Which one of the following identifies all of the available options that will place the Unit within the Estimated Capability Curve?
A. Raise Gas Pressure or lower MWe.
B. Raise Gas Pressure or raise MVARs.
C. Raise Gas Pressure only.
D. Lower MWe only.
Page 65 of-75
: 66. Which one of the following identifies two activities when two-handed operations are allowed, without prior SCO approval, in accordance 001-01.02, Shift Routines and Operating Practices?
: 66. Which one of the following identifies two activities when two-handed operations are allowed, without prior SCO approval, in accordance 001-01.02, Shift Routines and Operating Practices?
A. Continuous rod movement Inserting a manual scram. B. Dual purge fan start is desired for primary containment ventilation for personnel entry Placing RHR in suppression pool cooling. C. Synchronizing the DG to its bus Continuous rod movement.
A. Continuous rod movement Inserting a manual scram.
D. Dual purge fan start is desired for primary containment ventilation for personnel entry Inserting a manual scram. Page 66 of 75
B. Dual purge fan start is desired for primary containment ventilation for personnel entry Placing RHR in suppression pool cooling.
: 67. Initial reactor power is at 80%. Which one of the following identifies two situations that require a PA announcement in accordance with OAP-50, Site Command, Control, and Communications Procedure, or 001-01.02, Shift Routines and Operating Practices?
C. Synchronizing the DG to its bus Continuous rod movement.
A. Placing Hydrogen Water Chemistry in service Fire in the Service Water Building B. Power reduction to 76% Fire in the DG2 cell C. AOP-22, Grid Instability entry Starting 2B Condensate Pump D. Power increase to 90% Opening the Reactor Feed Pump recirc valve Page 67 of 75
D. Dual purge fan start is desired for primary containment ventilation for personnel entry Inserting a manual scram.
: 68. While reviewing Display 820, Powerplex Heat Sal/Core Mon Results, the Reactor Operator notes that one of the Feedwater flow values is cyan (blue). Which one of the following identifies the meaning of this color coding in accordance with 001-72, Plant Process Computer System Operating System? The process parameter:
Page 66 of 75
A. is displaying bad data. S. is displaying expired data. C. is exceeding a high alarm limit. D. has a substitute value inserted.
: 67. Initial reactor power is at 80%.
Which one of the following identifies two situations that require a PA announcement in accordance with OAP-50, Site Command, Control, and Communications Procedure, or 001-01.02, Shift Routines and Operating Practices?
A. Placing Hydrogen Water Chemistry in service Fire in the Service Water Building B. Power reduction to 76%
Fire in the DG2 cell C. AOP-22, Grid Instability entry Starting 2B Condensate Pump D. Power increase to 90%
Opening the Reactor Feed Pump recirc valve Page 67 of 75
: 68. While reviewing Display 820, Powerplex Heat Sal/Core Mon Results, the Reactor Operator notes that one of the Feedwater flow values is cyan (blue).
Which one of the following identifies the meaning of this color coding in accordance with 001-72, Plant Process Computer System Operating System?
The process parameter:
A. is displaying bad data.
S. is displaying expired data.
C. is exceeding a high alarm limit.
D. has a substitute value inserted.
Page 68 of 75
Page 68 of 75
: 69. An ATWS has occurred on Unit One with the following plant conditions:
: 69. An ATWS has occurred on Unit One with the following plant conditions:
Reactor Water Level Injection Systems Reactor Power Control Rods SRVs Suppression Pool Temp. 130 inches (stable) CRD APRM downscale lights are illuminated 19 rods failed to insert All closed 92&deg; F Which one of the following choices completes the statement below in accordance with LPC? Reactor Recirculation pumps _____ required to be tripped and the SLC Pumps ____ required to be started. A. are not are not B. are not are C. are are not D. are are Page 69 of 75
Reactor Water Level         130 inches (stable)
Injection Systems          CRD Reactor Power              APRM downscale lights are illuminated Control Rods                19 rods failed to insert SRVs                        All closed Suppression Pool Temp.      92&deg; F Which one of the following choices completes the statement below in accordance with LPC?
Reactor Recirculation pumps _ _ _ _ _ required to be tripped and the SLC Pumps
_ _ _ _ required to be started.
A. are not are not B. are not are C. are are not D. are are Page 69 of 75
: 70. Given the following alarm criteria:
: 70. Given the following alarm criteria:
a trip setpoint that is important to reactor safety, or a condition requiring prompt action by the operator, or a condition that requires additional manning at the control panels Which one of the following identifies the annunciator window designation for this criteria in accordance with 001-01.08, Control of Equipment and System Status? A. Red background with blue bar B. Red Background with red bar C. Red Background with yellow bar D. Amber background with yellow bar Page 70 of 75
a trip setpoint that is important to reactor safety, or a condition requiring prompt action by the operator, or a condition that requires additional manning at the control panels Which one of the following identifies the annunciator window designation for this criteria in accordance with 001-01.08, Control of Equipment and System Status?
: 71. Which one of the following identifies the Unit differences for the CREV system control and indications at the RTGB? A. Unit One has indication and controls Unit Two has no indication or control B. Unit One has indication only Unit Two has indication and controls C. Unit One has no indication or control Unit Two has indication and controls D. Unit One has indication and controls Unit Two has indication only Page 71 of 75
A. Red background with blue bar B. Red Background with red bar C. Red Background with yellow bar D. Amber background with yellow bar Page 70 of 75
: 71. Which one of the following identifies the Unit differences for the CREV system control and indications at the RTGB?
A. Unit One has indication and controls Unit Two has no indication or control B. Unit One has indication only Unit Two has indication and controls C. Unit One has no indication or control Unit Two has indication and controls D. Unit One has indication and controls Unit Two has indication only Page 71 of 75
: 72. Considering a 31 day surveillance frequency, which one of the following is last day that the surveillance can be performed and still meet the requirements of Technical Specifications?
: 72. Considering a 31 day surveillance frequency, which one of the following is last day that the surveillance can be performed and still meet the requirements of Technical Specifications?
The last day the surveillance must be performed by is within ____ of the previous performance of the surveillance.
The last day the surveillance must be performed by is within ____ of the previous performance of the surveillance.
A. 32 days B. 38 days C. 45 days D. 62 days Page 72 of 75
A. 32 days B. 38 days C. 45 days D. 62 days Page 72 of 75
: 73. During performance of 201-03.02, Control Operator Daily Surveillance Report, the following SJAE Off-Gas Radiation Monitor readings are recorded:
: 73. During performance of 201-03.02, Control Operator Daily Surveillance Report, the following SJAE Off-Gas Radiation Monitor readings are recorded:
D12-RM-K601A D12-RM-K601 B 110 mr/hr 50 mr/hr A local survey instrument positioned at the alternate channel check survey point for SJAE Radiation Monitor BReads 80 mr/hr. (reference provided)
D12-RM-K601A                       110 mr/hr D12-RM-K601 B                     50 mr/hr A local survey instrument positioned at the alternate channel check survey point for SJAE Radiation Monitor BReads 80 mr/hr.
(reference provided)
Which one of the following characterizes this deviation and also identifies the required action, if any, in accordance with 201-03.02.
Which one of the following characterizes this deviation and also identifies the required action, if any, in accordance with 201-03.02.
A. The deviation is conservative The channel check criteria is met and no other actions are required.
A. The deviation is conservative The channel check criteria is met and no other actions are required.
Line 284: Line 601:
Page 73 of 75
Page 73 of 75
: 74. A valve lineup is to be performed in an area that has the following conditions:
: 74. A valve lineup is to be performed in an area that has the following conditions:
Area temperature Area radiation 115 0 F 40 mr/hr Independent verification of this valve lineup is expected to take 0.5 hour. Which one of the following choices completes the statement below in accordance with OPS-NGGC-1303, Independent Verification?
Area temperature         1150 F Area radiation           40 mr/hr Independent verification of this valve lineup is expected to take 0.5 hour.
Independent verification of this lineup, based on the above conditions, may be waived because of -----A. both extreme temperature and excessive dose B. excessive dose only C. extreme temperature only D. either extreme temperature or excessive dose Page 74 of 75
Which one of the following choices completes the statement below in accordance with OPS-NGGC-1303, Independent Verification?
Independent verification of this lineup, based on the above conditions, may be waived because of - - - - -
A. both extreme temperature and excessive dose B. excessive dose only C. extreme temperature only D. either extreme temperature or excessive dose Page 74 of 75
: 75. Which one of the following requires Health Physics Window notification prior to starting the evolution in accordance with 10P-14.0, Reactor Water Cleanup System Operating Procedure?
: 75. Which one of the following requires Health Physics Window notification prior to starting the evolution in accordance with 10P-14.0, Reactor Water Cleanup System Operating Procedure?
A. RWCU Reject Operation For Vessel Chemistry to radwaste B. Precoat of a RWCU filter C. Backwash of a RWCU filter only D. Transfer of the Backwash Receiving Tank to radwaste only Page 75 of 75 Brunswick NRC RO Exam November 2008 Date: ______ _ Name: -------------
A. RWCU Reject Operation For Vessel Chemistry to radwaste B. Precoat of a RWCU filter C. Backwash of a RWCU filter only D. Transfer of the Backwash Receiving Tank to radwaste only Page 75 of 75
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Brunswick NRC RO Exam November 2008 Name:                                Date: _ _ _ _ _ __
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Latest revision as of 16:50, 12 March 2020

302 Final RO Written Exam and References
ML090270025
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Text

Final Submittal (Blue Paper)

FINAL RO WRITTEN EXAMINATION AND REFERENCES

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: "/'D Izoo'6 Facility/Unit: flrut\6w'~ \<./ \ __ 2..

Region: I D II ~ III D IV D Reactor Type: W D CE D BW D GE ~

Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent I

Brunswick NRC RO Exam November 2008 Name: A-.ar.1IJ) Date: .'~I 1.

2.

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1. Which one of the following identifies the component manipulations that will raise CRD drive water header differential pressure indication at Panel P603?

A. throttle open Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 B. throttle open Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 C. throttle closed Flow Control Valve C11-F002 or throttle open Drive Pressure Valve C11-PCV-F003 D. throttle closed Flow Control Valve C11-F002 or throttle closed Drive Pressure Valve C11-PCV-F003 Page 1 of 75

2. Unit Two is operating at rated pressure. While placing the 2B Recirculation Pump in service a complete failure of the #1 seal occurs.
  1. 1 seal cavity pressure is 1000 psig.

Which one of the following identifies the expected system indications for this failure?

A. #2 seal cavity pressure is 500 psig; PUMP B SEAL STAGING FLOW HI/LO annunciator in alarm B. #2 seal cavity pressure is 500 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm C. #2 seal cavity pressure is 1000 psig; PUMP B SEAL STAGING FLOW HIILO annunciator in alarm D. #2 seal cavity pressure is 1000 psig; OUTER SEAL LEAKAGE FLOW DETECTION HI annunciator in alarm Page 2 of 75

3. Given the following plant conditions on Unit One:

Reactor water level -25 inches Reactor pressure 55 psig Vessel Injection 4500 gpm from RHR (reference provided)

In accordance with 001-37.4, Reactor Vessel Control Procedure Basis Document, which one of the following identifies the current status of Adequate Core Cooling and the operational implications of these conditions?

A. Adequate Core Cooling is met; Clad temperatures are expected to remain between 1500° F and 1800° F.

B. Adequate Core Cooling is met; Clad temperatures are expected to remain ~1500° F C. Adequate Core Cooling is NOT met; Clad temperatures are expected to exceed 1800° F D. Adequate Core Cooling is NOT met; Clad temperatures are expected to remain ~1800° F Page 3 of 75

4. Which one of the following pumps is powered from 4KV E-Bus E2?

A. 1A RHR Pump B. 2C RHR Pump C. 10 RHR SW Booster Pump D. 2B RHR SW Booster Pump Page 4 of 75

5. During accident conditions, suppression pool level has dropped below -6.5 feet.

Which one of the following identifies the required action for HPCI, including the basis for the action, in accordance with PCCP and 001-37.8, Primary Containment Control Procedure Basis Document?

A. Terminate HPCI irrespective of adequate core cooling to prevent primary containment overpressurization.

B. Terminate HPCI irrespective of adequate core cooling to prevent exceeding Heat Capacity Temperature Limit.

C. Maintain HPCI operation if required to maintain adequate core cooling because core cooling takes priority over primary containment integrity.

D. Maintain HPCI operation if required to maintain adequate core cooling because the turbine exhaust flowrate is within the capacity of containment vent system.

Page 5 of 75

6. Unit Two plant conditions following an automatic initiation of ADS are as follows:

Reactor level -20 inches Reactor Pressure 400 psig and lowering Core Spray pumps 2A and 2B pumps running ADS SRV's 7 ADS valves OPEN with control switches in AUTO A dual unit loss of off-site power occurs and all DGs tie onto their respective E buses.

Which one of the following predicts how the ADS valves will respond during the loss of offsite power and subsequent re-energization of power to the E-busses?

A. remain open when the LOOP initially occurs; remain open after the E-Busses are re-energized.

B. close when the LOOP initially occurs; remain closed after the E-Busses are re-energized.

C. close when the LOOP initially occurs; re-open 83 seconds after the Core Spray pumps restart.

D. close when the LOOP initially occurs; re-open immediately after the Core Spray pumps restart.

Page 6 of 75

7. Following a DBA LOCA on Unit Two, plant conditions are as follows:

Reactor water level 55 inches and rising Reactor pressure 150 psig Torus temperature 220 0 F Suppression Chamber pressure 10.5 psig Torus level -43 inches 2A Core Spray pump flow 5000 gpm 2B Core Spray pump flow 2000 gpm 2A RHR pump flow 8000 gpm 2B RHR pump flow 6000 gpm (reference provided)

Which one of the following identifies the ECCS pump(s) that is/are operating within the associated NPSH limit(s)?

A. 2B CS Pump ONLY B. All CS and RHR pumps C. 2A CS and 2B CS ONLY D. 2B CS, 2A RHR and 2B RHR ONLY Page 7 of 75

8. Which one of the following methods is available to determine level in the SLC Tank following a loss of all air systems?

A. Direct the AO to valve in the local sight glass to obtain the level.

B. Have the AO read the level gauge on the local instrument rack.

C. Use the indication on the Level/Power Control ERFIS Screen.

D. Direct the AO to measure the distance from the surface of the liquid to the top of the SLC Tank.

Page 8 of 75

9. OPT-01.1.6, Reactor Protection System Manual Scram Test, is in progress. The Reactor Scram System A pushbutton has been depressed.

Which one of the following choices completes the statement below?

The alarm(s) that will occur is/are _ _ _ _ _ '

The RPS channel(s) that is/are de-energized is/are _ _ _ _ _ '

A. REACTOR MANUAL SCRAM SYS A only A3 only B. REACTOR MANUAL SCRAM SYS A only A1, A2 and A3 C. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A3 only D. REACTOR MANUAL SCRAM SYS A and REACTOR AUTO SCRAM SYS A A1, A2 and A3 Page 9 of 75

10. Which one of the following identifies the parameter that provides a direct input into the RPS logic (Le., does not actuate a turbine trip logic first)?

A. Control Valve Position LVDT B. EHC Low Header Discharge Pressure C. ETS (Emergency Trip System) Pressure D. RETS (Relayed Emergency Trip Supply) Pressure Page 10 of 75

11. TIP traces are in progress with all TIP drawer Mode Switches in Auto.

A small steam leak in containment causes drywell pressure to rise to 2.7 psig.

Which -one of the following predicts the final TIP ball valve position indication(s) and also identifies all available location(s) for verifying their position?

A. Red light indication illuminated on the Back Panel P607 ONLY.

B. White Valve Light illuminated on each TIP drawer at Back Panel P607 ONLY.

C. Red light indication illuminated on both the P601 Panel and the Back Panel P607.

D. Green light indication illuminated on the P601 Panel and a white Valve Light illuminated on each TIP drawer at Back Panel P607.

Page 11 of 75

12. Unit One is commencing a startup with all SRM's fully inserted and reading approximately 1 x 105 cps. The IRM's are reading the following:

IRMA 20 on Range 1 IRME 21 on Range 1 IRMB 28 on Range 1 IRMF 19 on Range 1 IRMC 21 on Range 2 IRMG 23 on Range 2 IRMD 25 on Range 1 IRMH 20 on Range 1 The operator takes the range switch for IRM B from Range 1 to Range 3.

Which one of the following identifies the status of the IRM B downscale white light at P601 and also identifies the annunciator alarm(s) status for this condition?

A. White light illuminated; ROD OUT BLOCK alarm only.

B. White light illuminated; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms.

C. White light extinguished; ROD OUT BLOCK alarm only.

D. White light extinguished; Both ROD OUT BLOCK and REACTOR AUTO SCRAM SYS B alarms.

Page 12 of 75

13. A reactor startup is in progress following a mid cycle forced outage in accordance with OGP-02, Approach to Criticality and Pressurization of the Reactor.

The operator notes the following SRM readings:

SRM Channel A 6.0 x 10 5 cps SRM Channel B 1.0 x 105 cps SRM Channel C 7.0 x 104 cps SRM Channel D 8.0 x 104 cps AlllRMs are on Range 4.

Which one of the following alarms will occur?

A. ROD OUT BLOCK Alarm only B. SRM UPSCALE / INOP Alarm only C. SRM UPSCALE / INOP and ROD OUT BLOCK Alarms D. ROD OUT BLOCK and NEUTRON MaN SYS TRIP Alarms Page 13 of 75

14. Unit Two is operating at 100% rated power.

Which one of the following plant transients will cause the APRM aDA displays to automatically shift to the stability screen?

A. FW-V120, FW Htrs 4 & 5 Byp Vlv, is inadvertantly opened B. Control Rod drifting into the core C. "A" Recirculation Pump Trip D. Inadvertant HPCI injection Page 14 of 75

15. Unit Two is at rated power when a faulty CST level instrument initiates a false low CST level input to the RCIC logic. RCIC SUCT XFER CST LO LVL annunciator is received.

Which one of the following identifies the correct RCIC system suction valves response?

Suppression Pool Suction Valves, E51-F029 and E51-F031, _ _ _ _ _ __

CST Suction Valve, E51-F010, _ _ _ _ _ _ __

A. immediately auto open; begins to close when both suppression pool suction valves are not full closed.

B. immediately auto open; begins to close after both suppression pool suction valves are full open.

C. begin to open when CST suction valve is not full open; immediately auto closes.

D. begin to open only after the CST suction valve is full closed; immediatley auto closes.

Page 15 of 75

16. Following a small steam line break in the drywell, plant conditions are as follows:

Drywell Pressure 20.8 psig Drywell Average Air Temp. 292 0 F Torus Pressure 19.0 psig Reactor Pressure 675 psig Reactor Water Level 100 inches HPCI System Unavailable RCIC System Started at LL2 and injecting Which one of the following identifies the current status of the ADS Initiation Timer and what operator action must be taken in accordance with PCCP?

ADS Initiation Timer started; Before Drywell Average Air temperature reaches 300 0 F, _ _ _ _ _ _ _ __

A. has; Drywell Spray is required B. has not; Drywell Spray is required C. has; Emergency Depressurization is required D. has not; Emergency Depressurization is required Page 16 of 75

17. Unit Two is operating at full power.

28 RHR and 28 RHR SW pumps have been placed in Suppression Pool Cooling to lower torus temperature.

A subsequent LOCA causes reactor water level to drop rapidly.

Plant conditions are as follows:

Drywell Pressure 18.1 psig Torus Pressure 13.7 psig Reactor Pressure 885 psig Reactor water level 36 inches E11-F0488 Closed Which one of the following describes the effect these conditions will have on the status of Suppression Pool Cooling?

A. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will auto open

8. 28 RHR and 28 RHR SW pumps remain running E11-F0488 will remain closed C. ONLY the 28 RHR SW Pump will trip E 11-F0488 will auto open D. ONLY the 28 RHR SW Pump will trip E11-F0488 will remain closed Page 17 of 75
18. During an ATWS, circuit alterations are performed per EOP-SEP-1 0, Circuit Alteration Procedure, to prevent a Group I Isolation from occurring.

Which one of the following Group I Isolation signals is defeated by this circuit alteration and how is the alteration physically accomplished?

A. Low Reactor Water Level; Installing jumpers B. Low Condenser Vacuum; Installing jumpers C. Low Reactor Water Level; Bypass Switch D. Low Condenser Vacuum; Bypass Switch Page 18 of 75

19. Unit One is performing OGP-02, Approach to Criticality and Pressurization of the Reactor, with the following plant conditions:

MSIVs are open Inboard Drain Isolation valve, B21-F016, is open Outboard Drain Isolation valve, B21-F019, is open Which one of the following identifies the plant response to opening the feeder breaker to 1A RPS MG set?

A. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize. The B21-F016 closes.

B. The AC solenoids on the Inboard MSIVs and the DC solenoids on the Outboard MSIVs de-energize. The B21-F019 closes.

C. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize. The B21-F016 closes.

D. The DC solenoids on the Inboard MSIVs and the AC solenoids on the Outboard MSIVs de-energize. The B21-F019 closes.

Page 19 of 75

20. On Unit Two, the SRO directs the RO to place drywell sprays in service per OEOP-01-SEP-02, Drywell Spray Procedure.

During the execution of SEP-02, SW-V111, Conv SW to Vital Header Vlv, trips on magnetics and remains in the full closed position.

Which one of the following describes the impact this failure will have on RHRlDrywell Spray system and also identifies the required operator actions in accordance with SEP-02?

A. loss of cooling water to RHR Room Coolers only; Open SW-V117, Nuc SW to Vital Header Vlv.

B. loss of cooling water to RHR Room Coolers only; Open SW-V118, Vital Header Crosstie Vlv.

C. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V117, Nuc SW to Vital Header Vlv.

D. loss of cooling water to RHR Room Coolers and RHR Pump Seal Coolers; Open SW-V118, Vital Header Crosstie Vlv.

Page 20 of 75

21. Following a dual unit Loss Of Offsite Power, which one of the following is the first makeup source to be used for filling the fuel pool in accordance with OAOP-38.0, Loss of Fuel Pool Cooling?

A. Demin water header stations B. Fire Protection Hose Stations C. Condensate transfer pumps D. Emergency Diesel Makeup Pump via hoses Page 21 of 75

22. A reactor scram has occurred with the following plant conditions:

Reactor Pressure 1100 psig Drywell Pressure 2.5 psig EHC Pumps Tripped Which one of the following systems is available and allowed for use in accordance with RVCP to stabilize pressure below 1050 psig?

A. HPCI B. RCIC C. Main Steam Line Drains D. Main Turbine Bypass Valves Page 22 of 75

23. Which one of the following describes the effect that a loss of E8 will have on the Unit Two Safety Relief Valve (SRV) system?

A. Inability to manually operate SRV's from the RTGB B. Inability to manually operate SRV's from the RSDP

c. Loss of SRV position indication on the RTGB D. Loss of SRV position indication on the RSDP Page 23 of 75
24. Unit Two is in power ascension following a refueling outage.

Reactor power is currently 22%.

The generator has been synchronized with the grid.

Load Limit is set to 110%

GP-04, Increasing Turbine Load to Rated Power, directs increasing turbine Load Set to 100%.

(reference provided)

If the RO adjusts Turbine Load Set to 90%, which one of the following predicts how the plant will respond as reactor power is raised?

A. When turbine load exceeds 90%, reactor pressure will increase and cause a reactor scram.

B. When reactor power reaches 100% then turbine load will be 100%.

C. When turbine load exceeds 90%, bypass valves will open to control turbine inlet pressure.

D. When turbine load reaches 90%, bypass valves will open causing a Group I Isolation.

Page 24 of 75

25. With Unit Two operated at rated power, the 2A Feedwater Heater level reaches the Hi Hi Level setpoint due to a failed Feedwater Heater level control valve.

Which one of the following choices completes the statement below?

The Moisture Removal Valves will open to drain the extraction steam lines to the

______ and final feedwater temperature to the reactor will _ _ _ _ _ __

A. Condenser; Increase B. Condenser; Decrease C. Heater Drain Deaerator; Increase D. Heater Drain Deaerator; Decrease Page 25 of 75

26. Reactor pressurization is in progress per OGP-02, Approach to Criticality and Pressurization of the Reactor.

The feedwater system is aligned as follows:

RFP A is in Service RFP A Recirc Valve (FW-FV-V46) is open Reactor Pressure is 400 psig SULCV (FW-LV-3269) in Auto Feedwater Heater 4A and 4B inlet isolation valves are closed FW-FV-177, Feedwater Recirc Valve, throttled open with 0.5 Mlbm/hr.

Which one of the following choices predicts the automatic response of the SULCV and also completes the caution statement in accordance with GP-02?

If the operator throttles FW-FV-177 in the open direction, the SULCV will automatically throttle in the direction. Opening the FW-FV-177 more than the

_ _ _ _ _ may cause feedwater line depressurization and loss of flow to the reactor vessel.

A. open RFP A Recirc Valve B. closed RFP A Recirc Valve C. open SULCV D. closed SULCV Page 26 of 75

27. Unit Two is operating at rated power with the following containment parameters:

Drywell Pressure 0.8 psig Torus Pressure 1.2 psig Torus venting is placed in service per 20P-1 0, Standby Gas Treatment System Operating Procedure.

Which one of the following identifies the SBGT alignment and also identifies how containment pressure will initially respond as the torus is being vented?

A. Align flow through both SBGT trains; Drywell Pressure will lower at the same rate as Torus Pressure.

B. Align flow through both SBGT trains; Drywell Pressure will remain steady.

c. Align flow through one SBGT train only; Drywell Pressure will lower at the same rate as Torus Pressure.

D. Align flow through one SBGT train only; Drywell Pressure will remain steady.

Page 27 of 75

28. Unit Two is operating at rated power with UPS in its normal alignment. Subsequently, offsite power is lost. DG3 and DG4 are unavailable. No electrical buses have been cross-tied.

Which one of the following choices completes the statements below?

The UPS Primary Inverter is currently being fed from DC Switchboard _ _ _ _ __

If the Primary Inverter fails, _ _ _ _ _ _ __

A. 2A.

UPS loads will be de-energized.

8. 2B.

UPS loads will be de-energized.

C. 2A.

UPS will auto transfer to an alternate source.

D.2B.

UPS will auto transfer to an alternate source.

Page 28 of 75

29. Unit One is operating at full power with the following plant conditions:

Suppression Pool 96° F due to HPCI Surveillance RHR B Loop in SPC (B/D pumps running)

RHRSW B Loop in service (B/D pumps running)

A Loss of Offsite Power (LOOP) occurs on both Units and DG2 fails to start.

Which one of the following identifies the impact of the LOOP on the 1-E 11-F024B and the 1D RHR Pump and also identifies the required action in accordance with OAOP-36.1, Loss of any 4160V Buses or 480V E-Buses, to support EOP actions?

A. 1-E11-F024B Valve only has lost power.

Crosstie E2 to E4.

B. 1-E11-F024B Valve only has IO'st power.

Crosstie E1 to E2.

C. 1-E11-F024B Valve and the 1D RHR pump have lost power.

Crosstie E2 to E4.

D. 1-E11-F024B Valve and the 1D RHR pump have lost power.

Crosstie E1 to E2.

Page 29 of 75

30. Unit Two is operating at 30% reactor power when a complete loss of the Vital UPS System occurs.

Which one of the following describes how this loss will affect RFPT operation?

A. RTGB trip pushbutton function is lost.

B. overspeed trip circuit will lose power causing RFPT Trip.

c. vibration instrumentation will lose power causing RFPT Trip.

D. RFPT woodward control trip circuits will be powered from their redundant power supplies.

Page 30 of 75

31. Which one of the following choices completes the statements below regarding how a total loss of UPS will affect the Digital Feedwater Level Control System Controllers.

Level Setpoint adjustment is _ _ _ _ __

Level Setdown_ _ _ _ _ _ occur following a reactor scram.

A. available; will B. available; will not C. not available; will D. not available; will not Page 31 of 75

32. Which one of the following is the power supply to the Outboard MSIV's DC solenoids on Unit One?

A. Diy 1 Switchboard 21A.

B. Diy 2 Switchboard 22B.

C. Diy 1 Switchboard 1A.

D. Diy 2 Switchboard 1B.

Page 32 of 75

33. Unit Two experiences a Loss of Off-Site Power (LOOP) with DG4 under clearance.

Which one of the following predicts the NSW and CSW pump response when the DG3 ties to bus E3?

A. NSW pump 2A and CSW pump 2A start immediately.

B. NSW pump 2A and CSW pump 2A start after a 5 second time delay.

C. NSW pump 2A starts immediately and CSW pump 2A does not start.

D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not start.

Page 33 of 75

34. Unit Two is operating at rated power with the A SJAE train in service at Full Load.

A clearance tagging error results in the closure of the SJE-V15, Recombiner Preheater Steam Supply Valve followed by the following alarm:

RECOMBINER INLET TEMPERATURE LOW Which one of the following describes the effect these conditions will have on Main Condenser vacuum and downstream Hydrogen concentrations?

Main Condenser vacuum will - - - - - - -

Hydrogen concentrations will* _ _ _ _ _ __

A. remain steady; increase B. remain steady; decrease C. degrade; increase D. degrade; decrease Page 34 of 75

35. Which one of the following identifies the power supplies for the Electric Driven Fire Pump?

The normal power supply is from:

A. E2, with an automatic transfer to E4 on loss of power B. E4, with an automatic transfer t9 E2 on loss of power C. E2, must be manually transfered to E4 on loss of power D. E4, must be manually transfered to E2 on loss of power Page 35 of 75

36. A plant transient and subsequent safety relief valve malfunction results in reactor steam dome pressure reaching 1300 psig.

Which one of the following choices completes the following statements?

Reactor vessel design pressure ____ been exceeded.

Tech Spec 2.1.2, Reactor Coolant System Pressure Safety Limit _ _ _ _ been exceeded.

A. has; has B. has; has not C. has not; has D. has not; has not Page 36 of 75

37. Unit Two is operating at 19% power with the turbine on the turning gear when the following indications are observed:

SJAE Trains Both in half load AOG System Outlet Flow 80 scfm and slowly rising Condenser Vacuum Slowly lowering Steam Seal header pressure o psig Which one of the following identifies the required operator action in acordance with OAOP-37, Low Condenser Vacuum?

A. Place B SJAE in full load B. Start the mechanical vacuum pump C. Throttle open MVD-S2, Steam Seal Bypass Valve D. Throttle open the SJAE Condensate Recirculation Valve, CO-FV-49 Page 37 of 75

38. A LOCA occurs on Unit One concurrent with a LOOP on both Units.

A DG3 lockout occurs due to a protective relay actuation.

Which one of the following is the response of the Unit One Low Pressure ECCS systems?

There will be injection from _ _ _ _ of Core Spray.

There will be injection from two RHR pumps in _ _ __

A. both loops only one loop

8. only one loop only one loop C. both loops both loops D. only one loop both loops Page 38 of 75
39. Which one of the following is the effect of a loss of the 24 VDC power supply located in RPS Analog Trip Cabinet A 1?

A. A1 remains energized from B1 B. A 1 remains energizes from A2 C. A 1 loses power and trip functions occur D. A 1 loses power and trip functions do not occur Page 39 of 75

40. Which one of the following identifies the reason that the Turbine Bypass Valves will open following a main turbine trip from full power?

A. Prevent overspeeding of the main turbine during the coastdown.

B. Prevent over pressurization of the MSR cross-over piping.

c. Prevent over pressurization of the reactor vessel.

D. Prevent rupture of the LP Turbine rupture discs.

Page 40 of 75

41. Which one of the following Scram Immediate Operator actions has a different setpoint between Unit One and Unit Two?

A. Tripping of the main turbine.

B. Tripping of the first feed pump.

C. Master level controller setpoint setdown.

D. Placing the reactor mode switch to Shutdown.

Page 41 of 75

42. Unit One was operating at full power when a scram ocurred due to a loss of drywell cooling with the following plant conditions.

Reactor water level 155 inches (slowly lowering)

Drywell pressure 2.1 psig (slowly rising)

High Level Trip A Amber light extinguished High Level Trip B Amber light illuminated High Level Trip C Amber light illuminated Which one of the following is the status of the reactor feed pumps and HPCI system?

The Reactor feed pump turbines:

A. are running and HPCI is injecting to the vessel.

B. are tripped, but HPCI is still injecting to the vessel.

C. are running, but HPCI is tripped.

D. and HPCI are both tripped.

Page 42 of 75

43. Unit One is at rated power when a scram signal is received.

Reactor water level drops and RWCU isolates.

Which one of the following level indicators, if any, was indicating on scale and available for use when RWCU isolated?

A. Fuel Zone (N036/N037) instruments only B. Wide range (N026A1B) instruments only C. Both Fuel Zone (N036/N037) and Wide Range (N026A1B) instruments D. Neither Fuel Zone (N036/N037) nor Wide Range (N026A1B) instruments were available.

Page 43 of 75

44. Unit Two was operating at 100% power when a steam line break caused drywell pressure to rise.

Which one of the following identifies the norrmal temperature relationship between compensated and uncompensated level instrument legs and also identifies the level instruments that will first be affected as drywell temperature rises due to the steam leak?

A. The compensated level instrument legs are at a higher temperature than the uncompensated legs, the compensated level instrument legs will boil first.

8. The uncompensated level instrument legs are at a higher temperature than the compensated legs, the uncompensated level instrument legs will boil first.
c. Both instrument legs are at the same temperature. The compensated level instrument legs will boil first.

D. Both instrument legs are at the same temperature. The uncompensated level instrument legs will boil first.

Page 44 of 75

45. A turbine trip and reactor scram occurs on Unit One. The following indications are on the full core display:

Green Lights Lit 136 rods Red lights Lit one rod Which one of the following choices completes the statements below?

RWM Shutdown Confirmation Screen will display _ __

The reactor - - - remain shutdown under all conditions without boron.

A. Shutdown: NO will B. Shutdown: NO will not

c. Shutdown: YES will D. Shutdown: YES will not Page 45 of 75
46. While reducing reactor pressure to place Shutdown Cooling in service in accordance with OAOP-32.0, Plant Shutdown from Outside Control Room, the following reactor pressure readings were recorded at the indicated times:

1200 1000 psig 1300 425 psig 1400 100 psig 1500 25 psig (reference provided)

Which one of the following choices completes the following statement?

The reactor cooldown rate specified in OAOP-32.0:

A. has not* been exceeded B. was exceeded between 1200 and 1300 C. was exceeded between 1300 and 1400 D. was exceeded between 1400 and 1500 Page 46 of 75

47. Unit Two is operating at rated power when the TCC-TV-607, MG Set Oil Cooler 2A Temperature Control Valve, fails to the closed position.

Which one of the following describes how this loss of cooling will affect the Recirculation MG Sets?

When the high lube oil temperature in the fluid drive reaches:

A. 190° F the scoop tube will lock and the drive motor breaker remains closed.

B. 190° F the drive motor breaker will trip and the SCOOP tube will lock.

C. 210° F the scoop tube will lock and the drive motor breaker remains closed.

D. 210° F the drive motor breaker will trip and the scoop tube will lock.

Page 47 of 75

48. Which one of the following identifies the signal(s) that will initiate the Backup Nitrogen System, including the reason for the Backup Nitrogen System?

A. Low Reactor Building Instrument Air header or Core Spray LOCA signal.

Ensures operability of ADS valves and Inboard MSIV's.

B. Core Spray LOCA signal ONLY.

Ensures operability of ADS valves and Inboard MSIV's.

C. Low Reactor Building Instrument Air header or Core Spray LOCA signal.

Ensures operability of ADS valves and the Hardened Wetwell Vent Valves.

D. Core Spray LOCA signal ONLY.

Ensures operability of ADS valves and the Hardened Wetwell Vent Valves.

Page 48 of 75

49. Unit One shutdown is in progress with the following plant conditions:

RWCU is in service.

Recirc Pump B is running.

SDC A Loop has been lost.

Feed and bleed has been established.

Reactor Coolant Temperature is 190 0 F and lowering slowly.

Given this condition in progress, which one of the following identifies the PREFERRED indication to use to determine vessel metal temperature response in accordance with 1PT-01. 7, Heatup/Cooldown Monitoring, including the reason?

A. Bottom head metal temperature; metal temperature response leads the coolant temperature response during a cooldown.

B. Bottom head metal temperature; coolant temperature response leads the metal temperature response during a cooldown.

C. Bottom drain coolant temperature; metal temperature response leads the coolant temperature response during a cooldown.

D. Bottom drain coolant temperature; coolant temperature response leads the metal temperature response during a cooldown.

Page 49 of 75

50. Which one of the following is the primary containment pressure limit and the required action before this limit is reached in accordance with PCCP?

A. 62 psig Vent primary containment irrespective of offsite release rate B. 62 psig Vent primary containment only if offsite release rate do not exceed aDCM limits C. 70 psig Vent primary containment irrespective of offsite release rate D. 70 psig Vent primary containment only if offsite release rate do not exceed aDCM limits Page 50 of 75

51. Unit Two is operating at rated power with EHC Pressure Regulator B out of service.

Pressure Regulator A output fails low.

(Reference provided)

Which one of the following identifies how reactor pressure will respond and also identifies the availability of the bypass valves following the reactor scram?

A. Reactor pressure will decrease and a scram will occur on a Group I Isolation.

Bypass valves are not available using the Bypass Valve Jack.

B. Reactor pressure will increase and a scram will occur on high pressure.

Bypass valves will still be available using the Bypass Valve Jack.

C. Reactor pressure will decrease and a scram will occur on a Group I Isolation.

Bypass valves will still be available using the Bypass Valve Jack.

D. Reactor pressure will increase and a scram will occur on high pressure.

Bypass valves are not available using the Bypass Valve Jack.

Page 51 of 75

52. Unit One failed to scram with the following plant conditions:

Reactor Power 3%

RPV Water Level -55 inches (N036)

RPV Pressure 800 psig Suppression Pool 1150 F Which one of the following actions, if any, is required to open suppression pool cooling valves (E 11-F024 and E 11-F028)?

A. Place the Think Switch to Manual only.

B. No overrides are necessary.

c. Place the Think Switch to Manual first and then bypass the 2/3rd core height interlock.

D. Bypass the 2/3rd core height interlock first and then place the Think Switch to Manual.

Page 52 of 75

53. Unit Two is operating at power with a leaking SRV. The ERFIS indication for the Suppression Pool Temperature has just turned RED.

Which one of the following identifies the temperature when ERFIS first turns RED and also identifies which procedure that must be entered?

A. 95 0 F PCCP B. 105 0 F PCCP C. 95 0 F OAOP-14.0, Abnormal Primary Containment Conditions D. 105 0 F OAOP-14.0, Abnormal Primary Containment Conditions Page 53 of 75

54. Conditions on Unit Two have degraded to where the Drywell Air Temperature is 340 0 F.

Which one of the following identifies the components whose enviromental qualification is affected by this temperature in accordance with 001-37.8, Primary Containment Control Procedure Basis Document?

A. Inboard MSIV solenoids B. SRV solenoids C. Torus to Drywell Vacuum Breakers D. CAC 4409 and 4410 Hydrogen Analyzers Page 54 of 75

55. Which one of the following is the suppression pool level when a manual reactor scram is first required including the required action in accordance with PCCP?

A. -5.5 feet Anticipation of Emergency Depressurization is required.

B. -5.5 feet Emergency Depressurization is required C. -6.5 feet Anticipation of Emergency Depressurization is required.

D. -6.5 feet Emergency Depressurization is required Page 55 of 75

56. During a low reactor water level emergency on Unit One, the Reactor Vessel Control Procedure directs the operator to enter the Steam Cooling Procedure.

Which one of the following describes the reason Steam Cooling Procedure is performed?

The Steam Cooling Procedure utilizes steam cooling heat transfer _ _ _ __

injection to maximize the time peak clad temperatures in the uncovered portion of the core do not exceed of.

A. with 1500 B. with 1800 C. without 1500 D. without 1800 Page 56 of 75

57. Which one of the following statements identifies the reason SCCP directs emergency depressurization based on temperature in accordance with 001-37.9, Secondary Containment Control Procedure Basis Document?

The reason the emergency depressurization is performed due to secondary containment temperature is to:

A. preserve personnel access into the reactor building.

B. ensure ODCM site boundary dose limits are not exceeded.

C. prevent damage to equipment required for safe shutdown.

D. prevent an unmonitored release.

Page 57 of 75

58. During the execution of emergency operating procedures, the operator has restarted Reactor Building HVAC per OEOP-01-SEP-04, Reactor Building HVAC Restart Procedure.

Which one of the following subsequent conditions would cause the Reactor Building Supply and Exhaust Isolation Dampers to reclose?

A. Reactor water level lowers below LL2.

B. Drywell pressure rises above 1.7 psig.

C. PROCESS OFF-GAS VENT PIPE RAD HI-HI alarm is received.

D. REACTOR BUILDING VENT EXHAUST TEMP HI alarm is received.

Page 58 of 75

59. The unit is in an ATWS with the following conditions:

SLC Tank 30% and lowering Reactor Water Level Being maintained 60 to 90 inches Reactor Power APRMs downscale Which one of the following choices completes the statement below in accordance with LPC?

Hot Shutdown Boron Injection Weight been injected and RPV water level

_ _ _ _ required to be raised at this tank level.

A. has is B. has is not C. has not is D. has not is not Page 59 of 75

60. Unit Two is operating under accident conditions with the following plant conditions due to a steam leak on HPCI:

Reactor Water Level -20 inches Reactor Pressure 900 psig Injection sources available HPClonly Offsite Release Alert declared HPCI Room Temperatures 140 0 F Suppression Pool Temperature 130 0 F Which one of the following identifies the required HPCI operation action in accordance with RRCP and also identifies the reason for taking the action?

A. HPCI should be left running It is required to be operated by the EOP's B. HPCI should be isolated It should have isolated on room high temperature C. HPCI should be left running Steam leak detection was overridden per RVCP D. HPCI should be isolated To prevent damage to the HPCI pump due to high suppression pool temperatures Page 60 of 75

61. During normal full power operation of Unit Two the following alarms and indications are noted:

SERVICE AIR PRESS LOW alarm Sealed In RB INSTR AIR RECEIVER 2A PRESS LOW Not in Alarm RB INSTR AIR RECEIVER 2B PRESS LOW Not in Alarm Instrument Air header pressure 100 psig Service Air header pressure 100 psig Which one of the following actions is required in accordance with OAOP-20, Pneumatic System Failures?

A. Start SBGT.

B. Close the manual Noninterruptible Isolation Valves.

C. Close the Service Air isolation valves, PV-706-1 and PV-706-2.

D. Close the Reactor Building Isolation Dampers.

Page 61 of 75

62. Which one of the following identifies the exact location of the RBCCW liquid process radiation detector (D12-RM-K606) and the function(s) it provides?

A. RBCCW pump suction header; alarm function only B. RBCCW pump suction header; alarm and isolation function C. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm function only D. Upstream of RCC-V28, Drywell Cooling Water Header Isolation Valve; alarm and isolation function Page 62 of 75

63. The SS has determined that the control room personnel must don SCBAs (Scott AP50) due to smoke in the control room from a plant fire on site.

Which one of the following is an indication that a SCBA is low on air?

A. Air regulator bypass valve fails open.

B. Air regulator bypass valve fails closed.

C. Audible high pitched beep emitting from face piece.

D. Vibralert alarm in the regulator that vibrates the face piece.

Page 63 of 75

64. Generator MVARs are indicating 0 MVARs.

Which one of the following identifies the actions required to restore MVARs to the limits specified in OP-27, Generator and Excitation System Operating Procedure?

Coordinate with the Load Dispatcher to either:

A. Raise the auto voltage regulator or place a capacitor bank in service B. Lower the auto voltage regulator or place a capacitor bank in service C. Raise the auto voltage regulator or remove a capacitor bank from service D. Lower the auto voltage regulator or remove a capacitor bank from service Page 64 of 75

65. A grid disturbance occurs with the following Unit Two plant parameters:

Generator Load 980 MWe Generator Reactive Load 160 MVARs, out Generator Gas Pressure 50 psig (Reference provided)

Which one of the following identifies all of the available options that will place the Unit within the Estimated Capability Curve?

A. Raise Gas Pressure or lower MWe.

B. Raise Gas Pressure or raise MVARs.

C. Raise Gas Pressure only.

D. Lower MWe only.

Page 65 of-75

66. Which one of the following identifies two activities when two-handed operations are allowed, without prior SCO approval, in accordance 001-01.02, Shift Routines and Operating Practices?

A. Continuous rod movement Inserting a manual scram.

B. Dual purge fan start is desired for primary containment ventilation for personnel entry Placing RHR in suppression pool cooling.

C. Synchronizing the DG to its bus Continuous rod movement.

D. Dual purge fan start is desired for primary containment ventilation for personnel entry Inserting a manual scram.

Page 66 of 75

67. Initial reactor power is at 80%.

Which one of the following identifies two situations that require a PA announcement in accordance with OAP-50, Site Command, Control, and Communications Procedure, or 001-01.02, Shift Routines and Operating Practices?

A. Placing Hydrogen Water Chemistry in service Fire in the Service Water Building B. Power reduction to 76%

Fire in the DG2 cell C. AOP-22, Grid Instability entry Starting 2B Condensate Pump D. Power increase to 90%

Opening the Reactor Feed Pump recirc valve Page 67 of 75

68. While reviewing Display 820, Powerplex Heat Sal/Core Mon Results, the Reactor Operator notes that one of the Feedwater flow values is cyan (blue).

Which one of the following identifies the meaning of this color coding in accordance with 001-72, Plant Process Computer System Operating System?

The process parameter:

A. is displaying bad data.

S. is displaying expired data.

C. is exceeding a high alarm limit.

D. has a substitute value inserted.

Page 68 of 75

69. An ATWS has occurred on Unit One with the following plant conditions:

Reactor Water Level 130 inches (stable)

Injection Systems CRD Reactor Power APRM downscale lights are illuminated Control Rods 19 rods failed to insert SRVs All closed Suppression Pool Temp. 92° F Which one of the following choices completes the statement below in accordance with LPC?

Reactor Recirculation pumps _ _ _ _ _ required to be tripped and the SLC Pumps

_ _ _ _ required to be started.

A. are not are not B. are not are C. are are not D. are are Page 69 of 75

70. Given the following alarm criteria:

a trip setpoint that is important to reactor safety, or a condition requiring prompt action by the operator, or a condition that requires additional manning at the control panels Which one of the following identifies the annunciator window designation for this criteria in accordance with 001-01.08, Control of Equipment and System Status?

A. Red background with blue bar B. Red Background with red bar C. Red Background with yellow bar D. Amber background with yellow bar Page 70 of 75

71. Which one of the following identifies the Unit differences for the CREV system control and indications at the RTGB?

A. Unit One has indication and controls Unit Two has no indication or control B. Unit One has indication only Unit Two has indication and controls C. Unit One has no indication or control Unit Two has indication and controls D. Unit One has indication and controls Unit Two has indication only Page 71 of 75

72. Considering a 31 day surveillance frequency, which one of the following is last day that the surveillance can be performed and still meet the requirements of Technical Specifications?

The last day the surveillance must be performed by is within ____ of the previous performance of the surveillance.

A. 32 days B. 38 days C. 45 days D. 62 days Page 72 of 75

73. During performance of 201-03.02, Control Operator Daily Surveillance Report, the following SJAE Off-Gas Radiation Monitor readings are recorded:

D12-RM-K601A 110 mr/hr D12-RM-K601 B 50 mr/hr A local survey instrument positioned at the alternate channel check survey point for SJAE Radiation Monitor BReads 80 mr/hr.

(reference provided)

Which one of the following characterizes this deviation and also identifies the required action, if any, in accordance with 201-03.02.

A. The deviation is conservative The channel check criteria is met and no other actions are required.

B. The deviation is conservative Initiate a W/R to evaluate the deviation.

C. The deviation is non-conservative Declare SJAE Radiation Monitor A inoperable.

D. The deviation is non-conservative Declare SJAE Radiation Monitor B inoperable.

Page 73 of 75

74. A valve lineup is to be performed in an area that has the following conditions:

Area temperature 1150 F Area radiation 40 mr/hr Independent verification of this valve lineup is expected to take 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Which one of the following choices completes the statement below in accordance with OPS-NGGC-1303, Independent Verification?

Independent verification of this lineup, based on the above conditions, may be waived because of - - - - -

A. both extreme temperature and excessive dose B. excessive dose only C. extreme temperature only D. either extreme temperature or excessive dose Page 74 of 75

75. Which one of the following requires Health Physics Window notification prior to starting the evolution in accordance with 10P-14.0, Reactor Water Cleanup System Operating Procedure?

A. RWCU Reject Operation For Vessel Chemistry to radwaste B. Precoat of a RWCU filter C. Backwash of a RWCU filter only D. Transfer of the Backwash Receiving Tank to radwaste only Page 75 of 75

Brunswick NRC RO Exam November 2008 Name: Date: _ _ _ _ _ __

1. ABC D 26. ABC D 51. ABC D
2. ABC D 27. ABC D 52. ABC D
3. ABC D 28. ABC D 53. ABC D
4. ABC D 29. ABC D 54. ABC D
5. ABC D 30. ABC D 55. ABC D
6. ABC D 31. ABC D 56. ABC D
7. ABC D 32. ABC D 57. ABC D
8. ABC D 33. ABC D 58. ABC D
9. ABC D 34. ABC D 59. ABC D
10. ABC D 35. ABC D 60. ABC D
11. ABC D 36. ABC D 61. ABC D
12. ABC D 37. ABC D 62. ABC D
13. ABC D 38. ABC D 63. ABC D
14. ABC D 39. ABC D 64. ABC D
15. ABC D 40. ABC D 65. ABC D
16. ABC D 41. ABC D 66. ABC D
17. ABC D 42. ABC D 67. ABC D
18. ABC D 43. ABC D 68. ABC D
19. ABC D 44. ABC D 69. ABC D
20. ABC D 45. ABC D 70. ABC D
21. ABC D 46. ABC D 71. ABC D
22. ABC D 47. ABC D 72. ABC D
23. ABC D 48. ABC D 73. ABC D
24. ABC D 49. ABC D 74. ABC D
25. ABC D 50. ABC D 75. ABC D
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