ML13123A314
| ML13123A314 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/01/2012 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Southern California Edison Co |
| LAURA HURLEY | |
| References | |
| 50-206/10-10, 50-361/10-10, 50-362/10-10 50-206/OL-10, 50-361/OL-10, 50-362/OL-10 | |
| Download: ML13123A314 (332) | |
Text
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 G 2.1.32 Importance Rating 3.8 Reactor Coolant Pump System: Ability to explain and apply system limits and precautions Proposed Question: Common 1 In accordance with SO23-3-1.7, Reactor Coolant Pump Operations, what is the lowest Mode of Operation in which the 4th RCP may be started?
A. Mode 2 B. Mode 3 C. Mode 4 D. Mode 5 Proposed Answer: B Page 1 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:
A. Plausible if thought that Mode 2 was the lowest Mode of Operation above 400°F.
B. Correct. The only requirement for starting the 4th RCP which pertains to Mode of Operation is RCS temperature must be greater than 400°F. Mode 3 is the lowest Mode of Operation at that temperature.
C. Plausible if thought that the 4th RCP could be started between 200°F and 350°F.
D. Plausible if thought that the 4th RCP could be started with RCS temperature less than 200°F.
Technical Reference(s) TS Definitions Table 1.1-1 Attached w/ Revision # See SO23-3-1.7, RCP Operations Comments / Reference Proposed references to be provided during examination: None Learning Objective: 54994 - Given an operational condition addressed by a procedural precaution, limitation, or administrative requirement, state the limiting condition and the basis for that limiting condition of the Reactor Coolant System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
TS Definitions Table 1.1-1 Comments /
Reference:
SO23-3-1.7, RCP Operations Revision # 38 Page 3 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 004 A3.03 Importance Rating 2.9 Chemical and Volume Control System: Ability to monitor automatic operation of the CVCS, including: Ion Exchange Bypass Proposed Question: Common 2 Ion Exchanger Bypass Valve, TV-0224B, is in AUTO / ION EXCHANGE.
- 1. What is the lowest letdown temperature at which TV-0224B will automatically bypass the Ion Exchangers?
- 2. What is the highest letdown temperature at which TV-0224B will automatically realign to the Ion Exchange position?
A. 1. 140°F
- 2. 128°F B. 1. 140°F
- 2. 138°F C. 1. 150°F
- 2. 128°F D. 1. 150°F
- 2. 138°F Proposed Answer: B Explanation:
A. Plausible as the valve closes at 140°F, however the valve will reopen at 138°F.
B. Correct.
C. Plausible as resin damage can begin to occur at 150°F, however the valve closes at 140°F.
D. Plausible as resin damage can begin to occur at 150°F, however the valve closes at 140°F.
Additionally, the valve reopen setpoint of 138°F is correct.
Technical Reference(s) SD-SO23-390, CVCS System Description Attached w/ Revision # See Comments / Reference Page 4 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination:
Learning Objective: 56037 - DESCRIBE the operation of the following Letdown and Charging Subsystem components, including function, location, and specific features including type, capacity, and power supplies where applicable: TV-0224B Question Source: Bank #
Modified Bank # x (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3 55.43 Page 5 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-390, CVCS System Description Revision # 20 Page 6 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Original Question Which of the following is the LOWEST temperature that automatically bypasses flow from TV-0224B, Ion Exchanger Bypass Valve?
A. 120°F.
B. 130°F.
C. 140°F.
D. 150°F.
Page 7 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 K2.01 Importance Rating 3.0 Residual Heat Removal System: Knowledge of bus power supplies to the following: RHR Pumps Proposed Question: Common 3 Which ONE of the following correctly states the power supplies for Unit 2 LPSI Pumps P-015 and P-016?
P-015 P-016 A. 2A04 2A04 B. 2A04 2A06 C. 2A06 2A04 D. 2A06 2B06 Proposed Answer: B Explanation:
A. Plausible as P-015 is powered from 2A04, however P-016 is powered from 2A06.
B. Correct.
C. Plausible as each pump is powered from a different 1E 4kV bus, however the power supplies are reversed.
D. Plausible as P-016 is powered from 2A06, however P-015 is powered from 2A04.
Technical Reference(s) SD-SO23-740, Shutdown Cooling System Attached w/ Revision # See Description Comments / Reference Proposed references to be provided during examination: None Page 8 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 53010 - DESCRIBE the operation of the following Shutdown Cooling System components, including function, location, and specific features including type, capacity, and power supplies where applicable: LPSI Pumps and Containment Spray Pumps Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SD-SO23-740, Shutdown Cooling System Revision # 20 Description Page 9 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006 A1.06 Importance Rating 3.6 Emergency Core Cooling System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Subcooling Margin Proposed Question: Common 4 Given the following conditions:
- A Unit 2 shutdown is in progress from 100% power.
- During the shutdown, a Reactor trip occurred due to a Loss of Coolant Accident concurrent with a Loss of Offsite Power.
The following plant conditions exist:
- Emergency Diesel Generators are operating normally.
- RCS Tcold is 537°F and slowly lowering.
- RCD Thot is 540°F and slowly lowering.
- Pressurizer Pressure 1100 psia and stable.
- Pressurizer Level 32% and slowly rising.
- Reactor Vessel Head Level indicates 2 voids.
- Core Exit Temperatures are 548°F and slowly lowering.
Which ONE of the following parameters will NOT allow performance of HPSI Throttle/Stop?
A. Pressurizer Level.
B. RCS Temperature.
C. Subcooling Margin.
D. Reactor Vessel Head Level.
Proposed Answer: C Explanation:
Page 10 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 A. Plausible if thought that Pressurizer level needed to be restored to its shutdown setpoint of 38%,
however 30% and not lowering is the requirement for Pressurizer level.
B. Plausible since FS-7 AER step states, RCS Cooldown NOT in progress, however as long as 40 GPM boration is in progress, Throttle/Stop criteria is satisfied.
C. Correct. Psat / Tsat for 1100 psia is ~ 556°F, REPCET is 548°F, therefore the RCS is 8°F subcooled. 20°F subcooled is required.
D. Plausible if thought that the Vessel Head must be full, however it is the Vessel Plenum which must be full.
Technical Reference(s) SO23-12-11, EOI Supporting Attachments Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: 53955 - As the RO, perform HPSI throttle/stop action.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 11 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-11, EOI Supporting Attachments Revision # 14 Page 12 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007 K4.01 Importance Rating 2.6 Pressurizer Relief/Quench Tank System: Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following:
Quench tank cooling.
Proposed Question: Common 5 Per SO23-3-1.11, Quench Tank Operations, which ONE of the following alignments is used to cool the Quench Tank?
The Quench Tank is...
A. drained to the Containment Sump and refilled with Primary Makeup Water.
B. vented to the Waste Gas System while the contents cool to ambient temperature.
C. drained to the Reactor Coolant Drain Tank and refilled with Primary Makeup Water.
D. vented and drained to the Radwaste Primary Tank using the Reactor Coolant Drain Tank Pumps.
Proposed Answer: C Explanation:
A. Plausible because the Quench Tank is filled with Primary Makeup Water, however it is not drained to the Containment Sump.
B. Plausible because this is the method to lower Quench Tank pressure, however this is not how the Quench Tank is cooled.
C. Correct.
D. Plausible because venting and draining is the method to lower Quench Tank pressure, however this is not how the Quench Tank is cooled.
Technical Reference(s) SO23-3-1.11, Quench Tank Operations Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: 107885 - OPERATE the Quench Tank to maintain normal level and pressure.
Question Source: Bank # x Page 13 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2009 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 10 55.43 Comments /
Reference:
SO23-3-1.11, Quench Tank Operations Revision # 11 Page 14 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007 A3.01 Importance Rating 2.7 Pressurizer Relief/Quench Tank System: Ability to monitor automatic operation of the PRTS, including: Components which discharge to the PRT Proposed Question: Common 6 Quench Tank level is rising. Which ONE of the following annunciators would assist the operator in determining why this is occurring?
A. 56C46, RCP Intergasket Leakage.
B. 50A35, Reactor Vessel Seal Leakage.
C. 56B59, RCP Bleedoff Relief Valve Leaking.
D. 57B36, SIT Drain Line Relief Valve Leaking.
Proposed Answer: C Explanation:
A. Plausible if thought that RCP Intergasket Leakage drains to the Quench Tank, however it drains to the Reactor Coolant Drain Tank.
B. Plausible if thought that Reactor Vessel Seal leakage drains to the Quench Tank, however it drains to the Reactor Coolant Drain Tank.
C. Correct.
D. Plausible if thought that SIT Drain Line Relief Valves drain to the Quench Tank, however they drain to the Reactor Coolant Drain Tank.
Technical Reference(s) SD-SO23-360, RCS System Description Attached w/ Revision # See SD-SO23-650, Coolant Radwaste System Comments / Reference Description Proposed references to be provided during examination:
Learning Objective: 56698 - DESCRIBE the operation of alarms associated with the Reactor Coolant System, including setpoints, possible causes, and effects on system or overall plant operation.
Page 15 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3 55.43 Page 16 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
References:
SD-SO23-360, RCS System Description Revision # 21 Comments /
Reference:
SD-SO23-650, Coolant Radwaste System Revision # 13 Description Page 17 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 008 A2.02 Importance Rating 3.2 Component Cooling Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level.
Proposed Question: Common 7 Given the following conditions on Unit 2:
- Train A CCW/SWC is in service.
- CCW Pump P-025 is aligned to Train A and running.
- The Letdown Heat Exchanger and Non-Critical Loop are aligned to Train A.
- T-003 level is 60% and rising when the 22 responds to an unrelated annunciator.
Which ONE of the following:
- 2. What mitigating actions would be required?
Train A CCW Surge Tank T-003 A. 1. level transmitter reference leg will fill with water causing the Non-Critical Loop to isolate.
- 2. Place Train B CCW/SWC in service and transfer the Non-Critical Loop per SO23-13-7, Loss of CCW/SWC.
B. 1. level rise will cause overall system pressure to rise and trip the running CCW pump on high discharge pressure.
- 2. Place Train B CCW/SWC in service and transfer the Non-Critical Loop per SO23-13-7, Loss of CCW/SWC.
C. 1. level transmitter reference leg will fill with water causing the Non-Critical Loop to isolate.
- 2. Lower T-003 level to restore Surge Tank level and pressure to the normal operating bands and reopen Train A Non-Critical Loop isolation valves per SO23-2-17, CCW Operations.
Page 18 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 D. 1. level rise will cause overall system pressure to rise and trip the running CCW pump on high discharge pressure.
- 2. Lower T-003 level to restore Surge Tank level and pressure to the normal operating bands and restart CCW Pump P-025 per SO23-2-17, CCW Operations.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as surge tank level rise will increase system pressure and potentially will exceed design CCW pump discharge pressure, however the CCW pump does not have a high discharge pressure trip.
C. Plausible because the ref leg will fill and isolate the NCL however the reference leg would have to be drained prior to restoring the Train A NCL. Additionally, this would require entry into 13-7.
D. Plausible as surge tank level rise will increase system pressure and potentially will exceed design CCW pump discharge pressure, however the CCW pump does not have a high discharge pressure trip.
Technical Reference(s) SO23-2-17, CCW Operations Attached w/ Revision # See SO23-13-7, Loss of CCW/SWC Comments / Reference SD-SO23-400, CCW System Description Proposed references to be provided during examination:
Page 19 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 55657 - DESCRIBE the effect of the following Component Cooling Water System conditions/operations: High CCW Surge Tank level Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 20 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-2-17, CCW Operations Revision # 40 Comments /
Reference:
SD-SO23-400, CCW System Description Revision # 23 Comments /
Reference:
SD-SO23-400, CCW System Description Revision # 23 Page 21 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Page 22 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010 K5.02 Importance Rating 2.6 Pressurizer Pressure Control System: Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:
Constant enthalpy expansion through a valve Proposed Question: Common 8 Given the following conditions:
- Pressurizer pressure is 2250 psia.
- Quench Tank pressure is 3 psig.
Which ONE (1) of the following temperatures is the expected response to leakage of a Pressurizer Safety Valve as indicated on tail pipe temperature indicators TI-107 and TI-108?
A. 150°F B. 185°F C. 222°F D. 256°F Proposed Answer: C Explanation:
A. Incorrect. Plausible if the Mollier Diagram is misread and 3 psia is used instead of 18 psia (3 psig).
B. Incorrect. Plausible if thought that the constant enthalpy throttling process was carried across to the intersection of the Saturation Line.
C. Correct. Steam Tables and Mollier Diagram confirm that a horizontal line (constant enthalpy throttling process) taken from primary pressure (2250 psia) on the saturation curve to where it intersects the line for 3 psig (or ~18 psia) in the Quench Tank is in the wet vapor region and therefore at a saturation temperature of 222°F.
D. Incorrect. Plausible if the Mollier Diagram is misread and 18 psig is used instead of 18 psia.
Technical Reference(s) Steam Tables Attached w/ Revision # See Mollier Diagram Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: 116234 - Apply saturated and superheated steam tables in solving liquid-vapor Page 23 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 problems.
Question Source: Bank #
Modified Bank # x (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 14 55.43 Comments /
Reference:
Bank question from 2011 NRC Exam, Question Revision #
- 8 Given the following plant conditions:
- Reactor Coolant System pressure is 2000 PSIA.
- Pressurizer steam temperature is 636ºF.
- A Pressurizer Relief Valve is leaking to the Quench Tank.
- Quench Tank pressure is 20 PSIG.
What is the temperature of the fluid entering the Quench Tank?
A. 212ºF.
B. 228ºF.
C. 259ºF.
D. 636ºF.
Page 24 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012 A1.01 Importance Rating 2.9 Reactor Protection System: Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: Trip setpoint adjustment.
Proposed Question: Common 9 Unit 2 is operating at 50% power with the following condition:
- SBCS valves 2HV8424 and 2HV8425 are out of service (planned repair time, several weeks).
What is the maximum value the Loss of Load permissive setpoints should be set to for these conditions in accordance with SO23-3-2.18, Steam Bypass Control System Operation?
A. 22.5%
B. 27.5%
C. 32.5%
D. 50%
Proposed Answer: C Explanation:
A. Plausible as each in-service SBCS valve can accept 11.25% of heat rejection, however the primary system can also handle 10%.
B. Plausible if thought that at 50% power, the maximum setpoint would be 27.5% (50% - 22.5%, as opposed to 55% - 22.5% which would be correct).
C. Correct.
D. Plausible if thought that since Reactor power is less than the normal full capacity of SBCS no setpoint reduction would be required, however 32.5% is the desired setpoint for the listed conditions.
Technical Reference(s) SO23-3-2.18, Steam Bypass Control Attached w/ Revision # See System Operation Comments / Reference Page 25 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: 54348 - DESCRIBE the cause/effect relationships associated with the following Steam Bypass Control System conditions/operations: EFFECT on plant operation of removing a Steam Bypass line from service.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4 55.43 Comments /
Reference:
SO23-3-2.18, Steam Bypass Control System Revision # 23 Operation Page 26 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012 A4.06 Importance Rating 4.3 Reactor Protection System: Ability to manually operate and/or monitor in the control room: Reactor trip breakers Proposed Question: Common 10 Given the following conditions on Unit 3:
- The CRS has directed a manual Reactor trip.
- The 21 has depressed all four Reactor Trip Pushbuttons.
- Reactor Trip Pushbuttons 3 and 4 failed to open their respective Reactor Trip Circuit Breakers (RTCBs).
What is effect on the RTCBs given the listed conditions?
A. ONLY RTCBs 1, 2, 3, and 4 are open.
B. ONLY RTCBs 1, 2, 5, and 6 are open.
C. RTCBs 1, 2, 3, and 4 opened initially. RTCBs 5, 6, 7, and 8 opened due to the subsequent CPC aux trip.
D. RTCBs 1, 2, 5, and 6 opened initially. RTCBs 3, 4, 7, and 8 opened due to the subsequent CPC aux trip.
Proposed Answer: B Explanation:
A. Plausible if thought that Rx Trip Pushbuttons 1 and 2 open RTCBs 1, 2, 3, and 4, however they open 1, 2, 5, and 6.
B. Correct. Rx Trip Pushbuttons 1 and 2 open RTCBs 1, 2, 5, and 6.
C. Plausible if thought that Rx Trip Pushbuttons 1 and 2 open RTCBs 1, 2, 3, and 4 and that half the rods would insert into the core. This would open the the remaining RTCBs due to an aux trip, however no CEAs will drop in this situation.
D. Plausible because Rx Trip Pushbuttons 1 and 2 open RTCBs 1, 2, 5, and 6, however no CEAs will drop in this situation thus resulting in no aux trip to open the other RTCBs..
Page 27 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-510, CEDMCS System Attached w/ Revision # See Description Comments / Reference SO23-3-5, RTCB Operability Testing Proposed references to be provided during examination:
Learning Objective: 56622 - DESCRIBE the response of the Plant Protection System to failures and alarms, including possible causes, effects on the system or overall plant, and operator actions to mitigate the effects.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 6 55.43 Page 28 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-510, CEDMCS System Description Revision # 11 Comments /
Reference:
Question Explanation Rx Trip pushbuttons 1 and 2 will open RTCBs 1, 2, 5, and 6. All four CEDM UV coils will remain energized via RTCBs 3, 4, 7, and 8.
Page 29 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-3.5, RTCB Operability Testing Revision # 20 Comments /
Reference:
SO23-3-3.5, RTCB Operability Testing Revision # 20 Page 30 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 K1.16 Importance Rating 2.9 Engineered Safety Features Actuation System: Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: MRSS Proposed Question: Common 11 Which of the following Main Steam System valves receive a close signal on a Main Steam Isolation Signal but NOT on a Containment Isolation Actuation Signal?
- 1. HV-8205, E-088 Main Steam Isolation Valve
- 2. HV-8419, E-088 Atmospheric Dump Valve
- 3. HV-8201, E-088 Steam to AFW Pump P-140 Isolation Valve A. 3 only.
B. 1 and 2 only.
C. 1 and 3 only.
D. 2 and 3 only.
Proposed Answer: D Page 31 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:
A.
Technical Reference(s) SD-SO23-720, ESFAS System Description Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 95875 - STATE the functions and design bases of the engineered safety features actuation system (ESFAS).
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 32 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-720, ESFAS System Description Revision # 8 Page 33 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 34 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 35 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 36 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 37 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 38 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 022 K3.02 Importance Rating 3.0 Containment Cooling System: Knowledge of the effect that a loss or malfunction of the CCS will have on the following: Containment instrumentation readings Proposed Question: Common 12 Given the following conditions:
- A loss of Normal Containment Cooling is in progress.
- Containment temperature and pressure are slowly rising.
How does a rise in Containment temperature and pressure affect indicated Pressurizer level?
Pressurizer level will indicate...
A. less than actual level due to the rise in Containment pressure.
B. greater than actual level due to the rise in Containment pressure.
C. less than actual level due to the rise in Containment temperature.
D. greater than actual level due to the rise in Containment temperature.
Proposed Answer: D Explanation:
A. Plausible as this is true for a pressure instrument, however this is not correct for a level instrument.
B. Plausible as level will indicate higher than actual level, however it is due to Containment temperature, not Containment pressure.
C. Plausible if thought that the increase in temperature would raise the D/P, however the D/P is lower in this case.
D. Correct.
Technical Reference(s) General Physics Sensors Handout Attached w/ Revision # See Page 39 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments / Reference Proposed references to be provided during examination:
Learning Objective: 81447 - INTERPRET instrumentation and controls utilized in the Containment System.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2006 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 3 55.43 Comments /
Reference:
General Physics Sensors Handout Revision # 4 Page 40 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
General Physics Sensors Handout Revision # 4 Page 41 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026 K1.02 Importance Rating 4.1 Containment Spray System: Knowledge of the physical connections and/or cause / effect relationships between the CSS and the following systems: Cooling water Proposed Question: Common 13 What is the primary source of cooling water to the Containment Spray Pump motors?
A. Nuclear Service Water System.
B. Component Cooling Water Critical Loop.
C. Component Cooling Water Non-Critical Loop.
D. Recirculation Flow from the discharge of the Containment Spray Pump.
Proposed Answer: B Explanation:
A. Plausible as the NSW System provides cooling to several pumps in the Safety Equipment Building, but not the Containment Spray Pumps.
B. Correct.
C. Plausible as the Containment Spray Pumps are cooled by CCW, but from the critical loop.
D. Plausible as recirculation flow provides some cooling to the Containment Spray Pump seals, however this is not the primary source of cooling to the pumps.
Technical Reference(s) SD-SO23-740, Containment Spray System Attached w/ Revision # See Description Comments / Reference SD-SO23-400, Component Cooling Water
System Description
SD-SO23-450, Nuclear Service Water
System Description
Proposed references to be provided during examination: None Learning Objective: 55656 - STATE the names of the systems interfacing with the Component Cooling Water System and DESCRIBE the flowpath and purpose of the interconnection.
Page 42 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments /
Reference:
SD-SO23-450, Nuclear Service Water System Revision # 10 Description Page 43 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-400, Component Cooling Water Revision # 22
System Description
Page 44 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-740, SI/CS System Description Revision # 20 Page 45 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 039 K5.08 Importance Rating 3.6 Main and Reheat Steam System: Knowledge of the operational implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity.
Proposed Question: Common 14 Given the following conditions:
- Unit 3 has been operating at 95% power for 7 days.
- Steam Driven Auxiliary Feedwater Pump (AFW) P-140 is started for maintenance to perform a packing adjustment.
Which ONE of the following describes the automatic plant response to this evolution?
A. The rise in steam demand will lower RCS Tc causing a slight power rise.
B. Main Feed Pump speed will lower due to the additional feedwater being supplied from AFW P-140.
C. The injection of colder feedwater to the S/Gs will cause RCS Tc to lower resulting in a slight power rise.
D. Main Turbine Governor Valves will throttle open slightly to compensate for the steam being diverted to AFW P-140.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible if P-140 was supplying water to the S/Gs, however there is not an available path for P-140 to inject water into the S/Gs given the listed conditions (P-140 discharge valves HV-4705 and HV-4706 are normally closed at power).
C. Plausible if P-140 was supplying water to the S/Gs, however there is not an available path for P-140 to inject water into the S/Gs given the listed conditions.
D. Plausible because the governor valves will throttle closed if steam pressure or frequency rises, however the valves do not throttle open for a reduction in steam pressure or frequency.
Page 46 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-780, Aux Feedwater System Attached w/ Revision # See Description Comments / Reference SO23-10-3, Operation of the Turbine Control and Protection System Proposed references to be provided during examination:
Learning Objective: 102445 - EXPLAIN the interlaces between the Main Steam System and other plant systems.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4, 5 55.43 Page 47 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-780, Aux Feedwater System Revision # 14 Description Comments /
Reference:
SO23-3-2.38, DCS Operations Revision # 10 Page 48 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059 K3.03 Importance Rating 3.5 Main Feedwater System: Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs Proposed Question: Common 15 Given the following conditions:
- Unit 3 is operating at 100% power.
- Condensate Pump P-053 is out of service for maintenance.
- Heater Drain Pump P-058 suddenly trips.
Which ONE of the following correctly states the automatic plant response and the effect on S/G levels?
A. Both MFW Pumps will trip on Lo Suction Pressure, the Reactor will trip on Low S/G Level, Reactor Trip Override will control AFW flow to maintain S/G levels between 21 and 26% NR.
B. Both S/G levels will initially lower, both MFW Pumps speed will rise to restore S/G levels to the FWCS Master Controller setpoint of 68%, the MFW Pumps will remain operating at the new higher speed.
C. Both MFW Pumps will trip on Lo Suction Pressure, the Reactor will trip on Low S/G Level, Emergency Feed Actuation System will actuate and maintain S/G levels on the cycling relays between 21 and 26% NR.
D. Both S/G levels will initially lower, both Feedwater Regulating Valves will modulate open to restore S/G levels to the FWCS Master Controller setpoint of 68%, the Feedwater Regulating Valves will remain at the more open position.
Proposed Answer: C Explanation:
A. Plausible as both MFW Pumps will trip on lo suction pressure, however EFAS will maintain SG levels, not RTO. RTO only controls main feed flow.
B. Plausible because S/G levels will lower and MFW Pump speed will rise, however at 100% Reactor power this event is unsustainable and the Reactor will trip.
Page 49 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Correct.
D. Plausible because S/G levels will lower and MFW Pump speed will rise, however at 100% Reactor power this event is unsustainable and the Reactor will trip.
Technical Reference(s) SD-SO23-260, Main Feedwater Pump, Attached w/ Revision # See Turbine and Turbine Controls System Comments / Reference Description SD-SO23-240, Condensate System Description Proposed references to be provided during examination:
Learning Objective: 60787 - ANALYZE normal and abnormal operations of the Condensate and Feedwater System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4, 5 55.43 Comments /
Reference:
SD-SO23-260, Main Feedwater Pump, Turbine Revision # 17 and Turbine Controls System Description Comments /
Reference:
SD-SO23-240, Condensate System Description Revision # 20 Page 50 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 51 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059 A2.12 Importance Rating 3.1 Main Feedwater System: Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves Proposed Question: Common 16 Given the following conditions:
- Unit 3 has just tripped from 100% power.
- Following Step 2 of SPTAs, the 32 noticed that S/G E-089 Feedwater Control Valve, FV-1111, failed in its pre-trip position due to mechanical binding.
Which ONE of the following describes the automatic plant response to this failure and what action will the 32 take to mitigate this failure?
- 1. S/G E-089 level will...
- 2. The 32 will close S/G E-089 A. 1. rise until the S/G is full.
- 2. Main Feedwater Block Valve, HV-4051.
B. 1. rise until the S/G is full.
- 2. Main Feedwater Isolation Valve, HV-4052.
C. 1. rise to the pre-trip value of 67% NR and stabilize.
- 2. Main Feedwater Block Valve, HV-4051.
D. 1. rise to the pre-trip value of 67% NR and stabilize.
- 2. Main Feedwater Isolation Valve, HV-4052.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as S/G level will rise until the S/G is full, however the correct mitigating action is to close Page 52 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 HV-4051. Closing HV-4052 would stop the S/G level rise, however it would completely stop main feedwater flow to the S/G.
C. Plausible as the S/Gs were at 67% NR level prior to the trip and the FRV failed to the same position it was when level was 67%, however steam flow lowers significantly so the same feedflow as before the trip would be excessive and fill the S/G.
D. Plausible as the S/Gs were at 67% NR level prior to the trip and the FRV failed to the same position it was when level was 67%, however steam flow lowers significantly so the same feedflow as before the trip would be excessive and fill the S/G. Additionally, closing HV-4052 would stop the S/G level rise, however it would completely stop main feedwater flow to the S/G.
Technical Reference(s) OSM-14, Operations Department Attached w/ Revision # See Expectations Comments / Reference Proposed references to be provided during examination:
Learning Objective: 54047 - For each of the Feedwater Control System malfunctions listed above, DESCRIBE the action taken by the operator in response to the malfunction.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4 55.43 Page 53 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
OSM-14, Operations Department Expectations Revision # 13 Comments /
Reference:
OSM-14, Operations Department Expectations Revision # 13 Page 54 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation: The reason for closing HV-4051 instead of HV-4052 (as it pertains to P&P actions) is because HV-4051 is in series with the feed reg valve. The FRV should have closed automatically due to the Reactor Trip Override signal but since it didnt and the FRV is mechanically bound, the block valve, HV-4051, must be closed. This satisfies the placing equipment in the required status when the AUTO function has failed criteria, stopping flow through the FRV while maintaining minimal flow via the feed reg bypass valve.
Page 55 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061 K6.01 Importance Rating 2.5 Auxiliary/Emergency Feedwater System: Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners Proposed Question: Common 17 Given the following conditions:
An electrical fault has caused AFW Pump P-140 Woodward 505 Turbine Controller to deenergize. What is the impact to P-140 in the event the pump receives an auto-start signal?
The failure of the Woodward 505 Turbine Controller will cause A. HV-4716, P-140 Turbine Stop Valve, to fail in the fully open position. P-140 will trip on overspeed.
B. HV-4700, P-140 Turbine Governor Valve, to fail in the fully open position. P-140 will trip on overspeed.
C. HV-4716, P-140 Turbine Stop Valve, to fail in the fully closed position. P-140 will only operate in Local-Manual control.
D. HV-4700, P-140 Turbine Governor Valve, to fail in the fully closed position. P-140 will only operate in Local-Manual control.
Proposed Answer: B Explanation:
A. Plausible as failure of HV-4716 to the fully open position would cause the pump to trip on overspeed, and HV-4716 sends a signal to the Woodward controller to raise P-140 from zero speed to idle speed, however this valve is not controlled by the Woodward controller.
B. Correct.
C. Plausible as P-140 could only be operated in Local-Manual if HV-4716 failed fully closed, and HV-4716 sends a signal to the Woodward controller to raise P-140 from zero speed to idle speed, however the Woodward controller does not control HV-4716.
D. Plausible as HV-4700 is controlled by the Woodward governor and will fail in the as-is position, however this valve is normally in the fully open position.
Page 56 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-SD-780, AFW System Description Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 80952 - ANALYZE normal and abnormal operations of the Auxiliary Feedwater System Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 57 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-SD-780, AFW System Description Revision # 15 Comments /
Reference:
SO23-SD-780, AFW System Description Revision # 15 Page 58 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 A4.03 Importance Rating 2.8 AC Electrical Distribution System: Ability to manually operate and/or monitor in the control room: Synchroscope, including an understanding of running and incoming voltages Proposed Question: Common 18 Given the following conditions:
- Unit 2 was operating at 100% Reactor power when the Reactor tripped due to a Loss of Offsite Power.
- The 22 is preparing to parallel Train A EDG, 2G002, with the grid following a restoration of off-site power.
- 2G002 is supplying 1E 4kV Bus 2A04 in isochronous and loaded to 40% capacity.
- 2G002 voltage is slightly higher than grid voltage.
- The synchroscope is rotating slowly in the slow direction.
- 1. How would 2G002 speed need to be adjusted to make the parallel, per SO23-2-13, Diesel Generator Operation?
- 2. What is the impact on 2G002 loading if the parallel is made with 2G002 voltage higher than grid voltage?
A. 1) 2G002 speed needs to be lowered.
- 2) KVAR loading on 2G002 will rise.
B. 1) 2G002 speed needs to be lowered.
- 2) KW loading on 2G002 will rise.
C. 1) 2G002 speed needs to be raised.
- 2) KVAR loading on 2G002 will rise.
D. 1) 2G002 speed needs to be raised.
- 2) KW loading on 2G002 will rise.
Proposed Answer: C Explanation:
Page 59 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 A. Plausible as 2G002 speed would have to be lowered if paralleling with the UAT, however in this condition the parallel would be with the RAT.
B. Plausible as 2G002 speed would have to be lowered if paralleling with the UAT, however in this condition the parallel would be with the RAT. Additionally, KVAR loading on 2G002 will rise due to the difference in voltage, not KW load.
C. Correct.
D. Plausible as 2G002 speed would have to be raised, however KVAR loading on 2G002 will rise due to the difference in voltage, not KW load.
Technical Reference(s) SO23-2-13, Diesel Generator Operation Attached w/ Revision # See SO23-6-2, Transferring of 4kV Buses Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53492 - ANALYZE normal and abnormal operations of the Emergency Diesel Generators (EDGs) System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5 55.43 Comments /
Reference:
SO23-2-13, Diesel Generator Operation Revision # 57 Page 60 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-2-13, Diesel Generator Operation Revision # 57 Comments /
Reference:
SO23-6-2, Transferring of 4kV Buses Revision # 19 Page 61 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 K3.02 Importance Rating 4.1 AC Electrical Distribution System: Knowledge of the effect that a loss or malfunction of the AC distribution system will have on the following: EDG Proposed Question: Common 19 Which ONE of the following describes an immediate effect on Train A Emergency Diesel Generator 2G002 upon a loss of 1E 480V Loadcenter 2B24?
A loss of A. power to Train A EDG Control Panel L-160.
B. control power to Train A EDG 2G002 Output Breaker.
C. power to Train A EDG Air Compressors C012A and C012B.
D. power to Train A EDG AC Lube Oil Circulating Pumps P-996 and P-997.
Proposed Answer: D Explanation:
A. Plausible since L-160 is powered from 1E DC Bus D1 and the bus D1 battery charger is powered from B24, however this effect will not be immediate.
B. Plausible since the 2G002 output breaker control power is supplied from 1E DC Bus D1 and the bus D1 battery charger is powered from B24, however this effect will not be immediate.
C. Plausible if thought that the compressors are powered from motor control center BD which is powered from B24, however the compressors are powered from MCC BDX.
D. Correct. P-996 and P-997 are powered from MCC BD which is powered from B24.
Technical Reference(s) SD-SO23-140 1E and Non-1E 125 and 250 Attached w/ Revision # See VDC Systems Comments / Reference SD-SO23-120 6.9kV, 4.16kV and 480V Electrical Distribution Systems SD-SO23-750 Emergency Diesel Generators Page 62 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination:
Learning Objective: 52795 - EXPLAIN the interfaces between the Emergency Diesel Generators (EDGs) System and other plant systems.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 63 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-140 1E and Non-1E 125 and 250 Revision # 22 VDC Systems Page 64 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-120 6.9kV, 4.16kV and 480V Electrical Revision # 23 Distribution Systems Comments /
Reference:
SD-SO23-120 6.9kV, 4.16kV and 480V Electrical Revision # 23 Distribution Systems This chart shows the control power source for breakers on load center switchboards. The EDG output breaker is located on A04 and thus gets its control power from DC Bus D1.
Page 65 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-750 Emergency Diesel Generators Revision # 21 Comments /
Reference:
SD-SO23-750 Emergency Diesel Generators Revision # 21 Comments /
Reference:
SD-SO23-750 Emergency Diesel Generators Revision # 21 Page 66 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063 K4.01 Importance Rating 2.7 DC Electrical Distribution System: Knowledge of DC electrical system design feature(s) and / or interlock(s) which provide for the following: Manual/automatic transfers of control Proposed Question: Common 20 Given the following conditions:
- Unit 2 is operating at 100% Reactor power.
- Annunciator window 63A37, 2D5 125 VDC Bus Trouble, actuated 1 minute ago.
- 2D5 voltage is 115 VDC and lowering.
If 2D5 voltage lowers to less than 107 VDC, what will be the impact to Non-1E Instrument Bus 2Q0612?
A. 2Q0612 will de-energize until it is manually transferred to 1E 480V Motor Control Center BRB.
B. Inverter Y005 static switch will automatically realign 2Q0612 to 1E 480V Motor Control Center BRB. 2Q0612 will remain energized.
C. 2Q0612 will de-energize until it is manually transferred to Non-1E 120 VAC Distribution Panel, 2Q069.
D. Inverter Y005 static switch will automatically realign 2Q0612 to Non-1E 120 VAC Distribution Panel, 2Q069. 2Q0612 will remain energized.
Proposed Answer: B Explanation:
A. Plausible if thought that Y005 has to be manually transferred to BRB, however this transfer is automatic when D5 lowers to 107 VDC.
B. Correct.
C. Plausible as Q069 is an alternate source of power and must be manually aligned, however in this case, Y005 would auto transfer to BRB.
D. Plausible as Y005 will auto transfer to an alternate source of power and Q069 is an alternate source of power, however the auto transfer is to BRB.
Page 67 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-130, 1E and Non-1E 120 VAC Attached w/ Revision # See System Description Comments / Reference SO23-6-17.1, Non-1E UPS 120 VAC Instrument and Control Power Proposed references to be provided during examination:
Learning Objective: 52528 - DISCUSS the operation of the Non 1E Instrument and Control UPS System including controls, instrumentation, interlocks, capacity, power supplies and system response to component failures.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 68 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-130, 1E and Non-1E 120 VAC System Revision # 16 Description Comments /
Reference:
SD-SO23-130, 1E and Non-1E 120 VAC System Revision # 16 Description Comments /
Reference:
SO23-6-17.1, Non-1E UPS 120 VAC Instrument Revision # 36 and Control Power Page 69 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-130, 1E and Non-1E 120 VAC System Revision # 16 Description Page 70 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-130, 1E and Non-1E 120 VAC System Revision # 16 Description Page 71 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064 A1.03 Importance Rating 3.2 Emergency Diesel Generator System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Operating voltages, currents, and temperatures Proposed Question: Common 21 Given the following sequence of events:
- Unit 2 is operating at 100% Reactor power.
- Unit 3 is in Mode 3 with all systems available.
- An inadvertent Safety Injection (SIAS) actuation occurs on Unit 2.
- Unit 2 tripped five (5) minutes after the inadvertent SIAS, causing switchyard voltage to lower to 205 kV.
- This results in ALL 1E 4kV buses indicating 4000V on BOTH Units.
Which ONE of the following signals will be generated to initiate the transfer of the Unit 2 1E 4kV buses to their respective Emergency Diesel Generators?
A. Loss Of Voltage Signal (LOVS)
B. Safety Injection Actuation Signal (SIAS)
C. Sustained Degraded Voltage Signal (SDVS)
D. Degraded Grid Voltage with SIAS Signal (DGVSS)
Proposed Answer: C Explanation:
A. Plausible because low voltage will initiate a transfer of the 1E buses to their diesels, however 4000V is not low enough to initiate a LOVS.
B. Plausible because a SIAS will start the EDGs and would transfer the 1E buses to the EDGs if voltage was lost, however the low voltage condition occurred 5 minutes after the SIAS.
C. Correct.
D. Plausible because this would be the case if the SIAS and trip were within 5 seconds, however the unit tripped 5 minutes after the SIAS.
Page 72 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-4, Operation During Major System Attached w/ Revision # See Disturbances Comments / Reference SO2-15-63.B, Train A Switchgear Alarm Response Procedure Proposed references to be provided during examination:
Learning Objective: 56264 - DESCRIBE the operation of the following 1E 4.16 KV Electrical System controls, and interlocks associated with the degraded voltage system Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2008 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 73 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-4, Operation During Major System Revision # 21 Disturbances Comments /
Reference:
SO2-15-63.B, Train A Switchgear Alarm Revision # 24 Response Procedure Page 74 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 073 G 2.4.4 Importance Rating 4.5 Process Radiation Monitoring System: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Proposed Question: Common 22 Given the following conditions on Unit 3 at full power:
- Train A CCW/SWC is in service with the Letdown HX and Non-Critical Loops aligned.
- The 32 notices Train A Surge Tank level is rising at a rate of .75 gpm.
- Annunciator window 61A09, U2 & COMMON INSTRUMENT FAILURE, has just gone into alarm.
Based on the listed conditions, which of the following AOI entry conditions are met?
- 1. SO23-13-7, Loss of CCW/SWC.
- 2. SO23-13-14, Reactor Coolant Leak.
- 3. SO23-13-11, Inadvertent Dilution or Boration.
A. 1 and 2 only.
B. 1 and 3 only.
C. 2 and 3 only.
D. 1, 2 and 3.
Proposed Answer: A Explanation:
A. Correct. Although the minimum leak rate for an RCS leak is > 1 gpm, the VCT level would be lowering at a rate of ~ 1 % per hour which satisfies the RCS Leak AOI entry condition.
B. Plausible if thought that the leakage is too low to enter the RCS Leak procedure and that the leak in the CCW HX could cause an inadventent dilution.
Page 75 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Plausible if thought that the leakage was too small to require entry into Loss of CCW/SWC and if thought that the leak in the CCW HX could cause an inadventent dilution.
D. Plausible as 1 and 2 are correct, however no inadvertent dilution would occur since letdown pressure is higher than CCW pressure.
Technical Reference(s) SO23-13-7, Loss of CCW/SWC Attached w/ Revision # See SO23-13-14, Reactor Coolant Leak Comments / Reference SO23-13-11, Inadvertent Dilution or Boration Proposed references to be provided during examination:
Learning Objective: 54359 - RECOGNIZE off normal and emergency conditions and respond using the appropriate Alarm Response, Abnormal or Emergency Operating Instruction to return the plant to a stable condition Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 76 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Page 77 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-14, Reactor Coolant Leak Revision # 18 Page 78 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-11, Inadvertent Dilution or Boration Revision # 20 Page 79 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 A4.02 Importance Rating 2.6 Service Water System: Ability to manually operate and/or monitor in the control room: SWS valves Proposed Question: Common 23 Which ONE (1) of the following describes the operation of the Train A Saltwater Cooling Heat Exchanger Outlet Valve, HV-6497?
HV-6497 ____(1)____ when Saltwater Cooling Pump P-307 is auto started and ____(2)____ when SWC Pump P-307 is stopped.
A. 1. will automatically open
- 2. will automatically close B. 1. will automatically open
- 2. must be manually closed C. 1. must be manually opened
- 2. will automatically close D. 1. must be manually opened
- 2. must be manually closed Proposed Answer: B Explanation:
A. Incorrect. Plausible because the valve will automatically open upon SWC Pump auto start, however, there is no automatic closure associated with this valve.
B. Correct. The CCW/SWC Heat Exchanger Outlet Valve will automatically open when the SWC Pump is started but must be manually closed when the pump is stopped.
C. Incorrect. Plausible because the valve can be manually opened upon SWC Pump auto start, however, there is no automatic closure associated with this valve.
D. Incorrect. Plausible because the valve can be manually opened upon SWC Pump start, and the valve must be manually closed when the pump is stopped.
Technical Reference(s) SO23-2-8, Salt Water Cooling System Attached w/ Revision # See Operation Comments / Reference Proposed references to be provided during examination:
Page 80 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 60305 - DESCRIBE the configuration and operational characteristics of Salt Water Cooling System components.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2009 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments /
Reference:
SO23-2-8, Salt Water Cooling System Operation Revision # 38 Page 81 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 G 2.1.27 Importance Rating 3.9 Service Water System: Knowledge of system purpose and/or function Proposed Question: Common 24 Which ONE of the following is a function of the Saltwater Cooling System?
A. To transfer heat removed from various turbine plant components to the Circulating Water System.
B. To remove heat from Reactor Auxiliary Systems carrying radioactive or potentially radioactive fluids.
C. To remove heat from air conditioning cooling coils which are in service during normal plant operation.
D. To transfer heat from the Component Cooling Water System to the ultimate heat sink during normal power generation, startup, shutdown and cooldown.
Proposed Answer: D Explanation:
A. Plausible as the SWC system does provide cooling functions, however this is the function of the Turbine Plant Cooling Water System.
B. Plausible as the SWC system does provide cooling functions, however this is the function of the Component Cooling Water System.
C. Plausible as the SWC system does provide cooling functions, however this is the function of the Normal Chilled Water System.
D. Correct.
Page 82 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-800, Normal Chilled Water Attached w/ Revision # See System Description Comments / Reference SD-SO23-530, Turbine Plant Cooling Water
System Description
SD-SO23-400, Component Cooling Water
System Description
SD-SO23-410, Saltwater Cooling System Description Proposed references to be provided during examination:
Learning Objective: 60301 - STATE the functions and design bases of the Salt Water Cooling System and components.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Page 83 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-800, Normal Chilled Water System Revision # 13 Description Comments /
Reference:
SD-SO23-530, Turbine Plant Cooling Water Revision # 11
System Description
Comments /
Reference:
SD-SO23-400, Component Cooling Water Revision # 22
System Description
Comments /
Reference:
SD-SO23-410, Saltwater Cooling System Revision # 10 Description Page 84 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 K1.03 Importance Rating 3.3 Instrument Air System: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Containment air Proposed Question: Common 25 Which one of the following components located inside containment uses Instrument Air as its motive force?
A. Pressurizer Spray Valve, PV-0100A B. Safety Injection Tank Outlet Valve, HV-9340 C. Letdown Heat Exchanger Outlet Valve, HV-9267 D. Containment Emergency Sump Outlet Valve, HV-9304 Proposed Answer: A Explanation:
A. Correct B. Plausible because the SIT fill and drain valves are air operated, however HV-9340 is motor operated.
C. Plausible because the other 3 letdown isolation valves are all air operated, however HV-9267 is motor operated.
D. Plausible because the RWST Outlet valves (normal supply of water the SI pumps) are air operated, however HV-9304 is motor operated.
Technical Reference(s) SD-SO23-360, RCS System Description Attached w/ Revision # See SD-SO23-390, CVCS System Description Comments / Reference SD-SO23-740, SIAS/CS/SDC System Description Proposed references to be provided during examination:
Learning Objective: 72867 - ANALYZE normal and abnormal operations of the Instrument and Respiratory & Service Air Systems.
Page 85 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments /
Reference:
SD-SO23-360, RCS System Description Revision # 21 Comments /
Reference:
SD-SO23-390, CVCS System Description Revision # 20 Comments /
Reference:
SD-SO23-740, SIAS/CS/SDC System Revision # 20 Description Page 86 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-740, SIAS/CS/SDC System Revision # 20 Description Page 87 of 87 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 A3.01 Importance Rating 3.1 Instrument Air System: Ability to monitor automatic operation of the IAS, including: Air pressure Proposed Question: Common 26 Instrument Air Compressors are in the following alignment:
- C001 is set for lead
- C002 is set for lag 1
- C003 is set for lag 2 Instrument Air header pressure has lowered to 89 psig and has stabilized.
What is the status of the Instrument Air Compressors?
A. All Air Compressors are running at 100% load.
B. C001 and C002 are running at 100% load, C003 is unloaded.
C. C001 and C002 are running at 100% load, C003 is running at 50% load.
D. C001 is running at 100% load, C002 is running at 50% load, C003 is unloaded.
Proposed Answer: C Explanation:
A. Plausible if thought that all compressors are running fully loaded when pressure drops below 90 psig, however this will not happen until 86 psig.
B. Plausible if thought that C003 would be unloaded at 89 psig, however C003 will remain 50%
loaded until pressure rises to 90 psig.
C. Correct.
D. Plausible as C001 will be loaded to 100% and one compressor will be at 50%, however C003 will be at 50% and C002 will be fully loaded.
Technical Reference(s) SD-SO23-570, Instrument Air System Attached w/ Revision # See Description Comments / Reference Page 1 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination:
Learning Objective: 72865 - DESCRIBE the configuration and operational characteristics of Instrument and Respiratory & Service Air Systems components.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4 55.43 Comments /
Reference:
SD-SO23-570, Instrument Air System Revision # 19 Description Page 2 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103 K4.06 Importance Rating 3.1 Containment System: Knowledge of containment system design feature(s) and/or interlock(s) which provide for the following: Containment isolation system Proposed Question: Common 27 When set points are reached, which of the following will initiate an automatic Containment Isolation Actuation Signal?
A. ONLY wide range Containment Pressure transmitters PT-0352-1, -2, -3, -4.
B. ONLY narrow range Containment Pressure transmitters PT-0351-1, -2, -3, -4.
C. Wide range Containment Pressure transmitters PT-0352-1, -2, -3, -4, OR Containment Airborne Radiation Monitors RE-7804/7807.
D. Narrow range Containment Pressure transmitters PT-0351-1, -2, -3, -4, OR Containment Airborne Radiation Monitors RE-7804/7807.
Proposed Answer: B Explanation:
A. Plausible because only containment pressure transmitters actuate an auto CIAS, however it is the narrow range transmitters which perform this function.
B. Correct.
C. Plausible because RE-7804/7807 actuate an auto CPIS (Containment Purge Isolation Signal),
however they do not actuate CIAS.
D. Plausible because RE-7804/7807 actuate an auto CPIS (Containment Purge Isolation Signal),
however they do not actuate CIAS.
Technical Reference(s) SD-SO23-720, ESFAS System Description Attached w/ Revision # See SD-SO23-690, Radiation Monitor System Comments / Reference Description SO23-13-18, RPS Malfunction AOI Proposed references to be provided during examination:
Learning Objective: 95875 - State the functions and design bases of the engineered safety features Page 3 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 actuation system (ESFAS).
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SD-SO23-720, ESFAS System Description Revision # 8 Comments /
Reference:
SD-SO23-690, Radiation Monitor System Revision # 18 Description Page 4 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-18, RPS Malfunction AOI Revision # 14 Page 5 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103 A2.05 Importance Rating 2.9 Containment System: Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Emergency Containment Entry Proposed Question: Common 28 Given the following conditions while preparing to perform an Emergency Containment Entry:
- Containment pressure is 3.2 psig.
- Containment average temperature is 125°F.
- Containment nitrogen concentration is 82%.
- Containment oxygen concentration is 17%.
Which ONE (1) of the following:
- 1. Identifies the impact on performing an Emergency Containment entry?
- 2. What action should be taken given the conditions listed?
A. 1. An Emergency Containment entry CAN be performed.
- 2. Reduce Containment temperature by placing Containment Emergency Cooling Units in service per SO23-1-4.1, Containment Emergency Cooling.
B. 1. An Emergency Containment entry CANNOT be performed.
- 2. Reduce Containment pressure to less than 3 psig per SO23-1-4.2, Containment Purge and Recirculation Filtration System, Attachment 6, Operation of the Containment Mini-Purge System.
C. 1. An Emergency Containment entry CAN be performed.
- 2. Don a Self-Contained Breathing Apparatus per SO23-3-2.34, Containment Access Control, with oxygen level less than or equal to 19.5%.
D. 1. An Emergency Containment entry CANNOT be performed.
- 2. Reduce Containment nitrogen concentration to 80% by purging one volume from Containment per SO23-3-2.34, Containment Access Control.
Proposed Answer: B Page 6 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:
A. Plausible because average Containment temperature is greater than 105°F which requires implementing Containment Emergency Cooling; however, Containment pressure is too high for entry at this time. Tech Spec LCO 3.6.5 requires temperature to be 120°F in MODES 1 to 4.
B. Correct. With Containment pressure greater than 3 psig, Containment entry is not allowed.
Placing the Containment Mini-Purge in operation is required because a direct of venting of Containment is only allowed if pressure is less than 1 psig.
C. Plausible because donning self-contained breathing apparatus is required at this oxygen concentration, however, Containment pressure is too high for an emergency entry to be performed.
D. Plausible because the emergency entry cannot be performed and this could be the action for high nitrogen, however, there is no specific concentration value for nitrogen (only oxygen) and Containment pressure is still too high.
Technical Reference(s) SO23-1-4.1, Containment Emergency Attached w/ Revision # See Cooling Comments / Reference SO23-1-4.2, Containment Purge and Recirculation Filtration System SO23-3-2.34, Containment Access Control Proposed references to be provided during examination:
Learning Objective: 81443 - EXPLAIN the importance of the Containment System with regard to plant safety.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2011 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 9 55.43 Comments /
Reference:
SO23-1-4.1, Containment Emergency Cooling Revision # 17 Page 7 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-2.34, Containment Access Control Revision # 28 Comments /
Reference:
SO23-3-2.34, Containment Access Control Revision # 28 Page 8 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-1-4.2, Containment Purge and Revision # 35 Recirculation Filtration System Page 9 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 029 K1.02 Importance Rating 3.3 Containment Purge System: Knowledge of the physical connections and/or cause effect relationships between the Containment Purge System and the following systems: Containment Radiation Monitor Proposed Question: Common 29 Upon receipt of a high radiation alarm:
- 1. Containment Airborne Radiation Monitor RE-7804 will
- 2. Containment Purge Stack Radiation Monitor RE-7828 will A. 1. initiate a Containment Purge Isolation Signal.
- 2. initiate a Containment Purge Isolation Signal.
B. 1. initiate a Containment Purge Isolation Signal.
- 2. close ONLY the four outside Containment Purge Isolation Valves.
C. 1. close ONLY the four outside Containment Purge Isolation Valves.
- 2. initiate a Containment Purge Isolation Signal.
D. 1. close ONLY the four outside Containment Purge Isolation Valves.
- 2. close ONLY the four outside Containment Purge Isolation Valves.
Proposed Answer: B Explanation:
A. Plausible as RE-7804 will initiate a CPIS, however RE-7828 will only close the four outside valves.
B. Correct.
C. Plausible as the rad monitors will perform the two listed functions, however the functions are reversed.
D. Plausible as RE-7828 will only close the four outside valves, however RE-7804 will initiate a CPIS.
Page 10 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-690 Radiation Monitoring System Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 103328 - EXPLAIN the interfaces between the Radiation Monitoring System and other plant systems.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9 55.43 Comments /
Reference:
SD-SO23-690 Radiation Monitoring System Revision # 18 Page 11 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 002 A3.03 Importance Rating 4.4 Reactor Coolant System: Ability to monitor automatic operation of the RCS, including: Pressure, temperatures, and flows Proposed Question: Common 30 Given the following conditions:
- Unit 2 is operating at 100% Reactor power.
- All Charging Pumps are in AUTO.
- The Backup Charging Pumps Selector switch is in the P-192 / P-190 position.
- Pressurizer Lo-Lo Level Heater Cutout Channel Selector is in the X and Y position.
- The selected Pressurizer Level Control Channel transmitter, LT-0110-1, has failed as-is.
- Subsequently, the Reactor tripped.
With NO operator action, what is the expected condition of Pressurizer heaters and Charging pumps 3 minutes after the trip?
A. All Pressurizer heaters will be OFF; ONLY Charging Pump P-191 will be running.
B. All Pressurizer heaters will be OFF; Charging Pumps P-190, P-191 and P-192 will be running.
C. ONLY Channel X 1E Pressurizer heater will be ON; ONLY Charging Pump P-191 will be running.
D. ONLY Channel X 1E Pressurizer heater will be ON; Charging Pumps P-190, P-191 and P-192 will be running.
Proposed Answer: A Explanation:
A. Correct. All heaters with the exception of the Train A 1E heater will turn off due to the shrinkage of the Pressurizer and LT-0110-2 indicating < 23.1%. The Train A 1E heater will be deenergized due to the shrinkage of the S/Gs and subsequent EFAS actuation which deenergizes both 1E heaters.
B. Plausible as all heaters will be off, however only charging pump P-191 will be running since the selected level transmitter is indicating higher than the post-trip setpoint of 38%.
Page 12 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Plausible as only charging pump P-191 will be running, however all pressurizer heaters will be off.
D. Plausible as the channel X heater wont trip initially, however the EFAS which will occur will trip the channel X heater. Additionally, the two backup charging pumps will not start due to the failed level transmitter.
Technical Reference(s) SO23-13-27, Pressurizer Pressure and Attached w/ Revision # See Level Malfunctions Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56417 - DESCRIBE the operation of Pressurizer Pressure Control System components, instrumentation, controls and alarms including function, location, interlocks, capacity and power supplies where applicable Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 13 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-27, Pressurizer Pressure and Level Revision # 7 Malfunctions Page 14 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-27, Pressurizer Pressure and Level Revision # 7 Malfunctions Prior to the trip, level setpoint is 53%. After the trip due to RCS Tave lowers to ~ 545°F, setpoint changes to 38%.
Page 15 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 014 K4.06 Importance Rating 3.4 Rod Position Indication System: Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Individual and group misalignment Proposed Question: Common 31 Which ONE of the following conditions will prevent CEAs from being withdrawn in Manual Sequential?
Selected Group Group 3 Group 4 Group 5 A. 3 125 20 3 B. 3 142 45 3 C. 4 145 60 3 D. 4 145 110 25 Proposed Answer: D Explanation:
A. Plausible if thought that 105 was too great a deviation between groups 3 and 4, however the only interlock is > 91.77 between the groups.
B. Plausible if thought that 142 was above the upper group stop for group 3, in which case group 4 would have to be selected group, however the upper group stop is > 145.
C. Plausible as 85 separation between groups 3 and 4 would prevent rod motion, however this is not applicable since group 3 is above the upper group stop.
D. Correct. The minimum required separation between groups 4 and 5 is 91.77 and in this case only 85 separates the two groups.
Technical Reference(s) SO23-3-2.19, CEDMCS Operations Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 81786 - DESCRIBE the configuration and operational characteristics of Control Element Drive Mechanism Control System (CEDMCS) components.
Page 16 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SO23-3-2.19, CEDMCS Operations Revision # 28 Page 17 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 015 K5.06 Importance Rating 3.4 Nuclear Instrumentation System: Knowledge of the operational implications of the following concepts as they apply to the NIS:
Subcritical multiplications and NIS indications Proposed Question: Common 32 As criticality is approached during a reactor startup, successive equal positive reactivity insertions result in a ____(1)____ change in equilibrium count rate and a ____(2)____ time to reach each new equilibrium condition.
A. 1. larger
- 2. longer B. 1. larger
- 2. shorter C. 1. smaller
- 2. longer D. 1. smaller
- 2. shorter Proposed Answer: A Explanation:
A. Correct.
B. Plausible as positive reactivity insertions will result in a larger reactivity change, and it could be thought that as power rises each successive positive addition will be proportionately smaller and thus require less time to reach equilibrium.
C. Plausible as it will take more time to reach equilibrium, and is could be thought that successive additions will be smaller as the proportion to current power will be less, however each positive addition will result in a larger change in equilibrium count rate.
D. Plausible if thought that successive additions will be smaller as the proportion to current power will be less, however each positive addition will result in a larger change in equilibrium count rate and if thought that as power rises each successive positive addition will be proportionately smaller and thus require less time to reach equilibrium.
Page 18 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) General Physics Reactor Theory Handout Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52680 - EXPLAIN how and why each of the following will change with successive equal positive reactivity insertions into a subcritical reactor: Factor by which count rate increases and the time required for count rate to stabilize Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments /
Reference:
General Physics Reactor Theory Handout Revision # 4 Page 19 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 017 A2.01 Importance Rating 3.1 Incore Temperature Monitoring System: Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
Thermocouple open and short circuits Proposed Question: Common 33 Given the following conditions on Unit 2:
- One of the two Core Exit Thermocouples (CET) providing inputs to the Subcooling Margin calculation has failed.
- Subsequently, the second CET developed an open circuit.
- 1. How does the open circuit failure affect the CET?
- 2. What procedure will the crew use to transfer the Subcooling Margin Monitor display on CR56 to RCS Subcooling Margin?
A. 1. The CET indication fails low.
- 2. SO23-3-2.20 Computer Operation.
B. 1. The CET indication fails high.
- 2. SO23-3-2.20 Computer Operation.
C. 1. The CET indication fails low.
- 2. SO23-3-2.32 Critical Functions Monitoring System.
D. 1. The CET indication fails high.
- 2. SO23-3-2.32 Critical Functions Monitoring System.
Proposed Answer: C Explanation:
A. Plausible as the CET will fail low, however changing the SCM display is done using SO23-3-2.32.
B. Plausible as SO23-3-2.20 is used for a variety of PCS operations, however not for changing SCM display.
C. Correct.
D. Plausible as the correct procedure is referenced, however the CET indication will fail low.
Page 20 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) General Physics Sensors Handout Attached w/ Revision # See SO23-3-2.32 Critical Functions Comments / Reference Monitoring System.
Proposed references to be provided during examination:
Learning Objective: 54386 - EXPLAIN the following theoretical principles as they relate to the Incore Instrumentation System: Temperature measurement with a thermocouple detector Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 21 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
General Physics Sensors Handout Revision # 4 Page 22 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-2.32 Critical Functions Monitoring Revision # 16 System.
Page 23 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 033 K3.02 Importance Rating 2.8 Spent Fuel Pool Cooling System: Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Area and ventilation radiation monitoring systems Proposed Question: Common 34 An operator has manually initiated a Train A Fuel Handling Isolation Signal due to a leak in the Spent Fuel Pool.
Radiation levels in the Fuel Handling Building will be monitored by A. Train B Fuel Handling Building Airborne Radiation Monitor, RE-7823. Activity levels will be monitored by the use of local air samples.
B. Fuel Handling Building Spent Fuel Cask Area Radiation Monitor, RE-7850. Activity levels will be monitored by the use of local air samples.
C. Train B Fuel Handling Building Airborne Radiation Monitor, RE-7823. Activity levels will be monitored by Fuel Handling Building Spent Fuel Cask Area Radiation Monitor, RE-7850.
D. Fuel Handling Building Spent Fuel Cask Area Radiation Monitor, RE-7850. Activity levels will be monitored by Train B Fuel Handling Building Airborne Radiation Monitor, RE-7823.
Proposed Answer: B Explanation:
A. Plausible as RE-7823 would normally monitor rad levels and the applicant may think that since only Train A FHIS was actuated that RE-7823 would still be monitoring, however both RMs isolate on either Train FHIS acuation.
B. Correct.
C. Plausible as RE-7823 would normally monitor rad levels and the applicant may think that since only Train A FHIS was actuated that RE-7823 would still be monitoring, however both RMs isolate on either Train FHIS acuation.
D. Plausible as rad levels will be monitored by RE-7850, however activity levels will be monitored by local air samples.
Technical Reference(s) SD-SO23-435, Fuel Handling Building Attached w/ Revision # See Page 24 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Ventilation System Description Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56644 - DESCRIBE the causes and corrective actions associated with an operating event for the Fuel Handling Building (FHB) Ventilation System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11 55.43 Page 25 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-435, Fuel Handling Building Revision # 4 Ventilation System Description Page 26 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-435, Fuel Handling Building Revision # 4 Ventilation System Description Both RMs isolate on either a Train A or Train B FHIS.
Page 27 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 041 K6.03 Importance Rating 2.7 Steam Dump/Turbine Bypass Control System: Knowledge of the effect of a loss or malfunction on the following will have on the SDS:
Controller and positioners, including ICS, S/G, CRDS Proposed Question: Common 35 Given the following conditions:
- Unit 2 is operating at 100% Reactor power.
- S/G E-088 Steam Pressure Input to Steam Bypass Control System (SBCS) pressure transmitter, PT-8239, fails high.
Which ONE of the following correctly describes the impact to the SBCS system?
A. Permissive signals with be in on ALL four SBCS valves.
B. Permissive signals will be in on ONLY two SCBS valves.
C. An open signal will be received on ALL four SBCS valves.
D. An open signal will be received on ONLY two SBCS valves.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible if thought that each SG pressure transmitter fed two of the four SBCS valves, however the two pressure signals are used for all four valves in either a low or high select manner.
C. Plausible as this would be the case if an SG transmitter failed low, however the transmitter failed high.
D. Plausible if thought that each SG transmitter fed two valves and that the valve open signal was a high select, however all four valves are affected and the valve open signal is a low select.
Page 28 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-3-2.18, SBCS Operation Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52446 - DESCRIBE how the following inputs affect the operation of the Steam Bypass Control System: Steam Pressure Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 29 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-2.18, SBCS Operation Revision # 24 Page 30 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 045 A1.05 Importance Rating 3.8 Main Turbine Generator System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of primary plant parameters (temperature and pressure) following T/G trip Proposed Question: Common 36 Unit 3 was operating at 100% Reactor power when the following events occurred:
- The Main Turbine inadvertently tripped.
- The Loss of Load circuitry failed to actuate.
Which ONE of the following describes the automatic response of RCS temperature and pressure to this transient?
RCS temperature and pressure will initially rise until A. SBCS valves Quick Open and restore RCS temperature and pressure to NOT/NOP.
B. the High Pressurizer Pressure Trip trips the Reactor on high pressure at 2375 psia.
C. the Diverse Scram System trips the Reactor on high Pressurizer pressure at 2428 psia.
D. Pressurizer Code Safety Valves open to lower RCS temperature and pressure at 2500 psia.
Proposed Answer: B Explanation:
A. Plausible as the SBCS valves will receive a quick open signal and will initially lower pressure and temperature slightly, however the full load rejection exceeds the capacity of SBCS to prevent tripping on high pressure.
B. Correct. The initiating device for the high pressure trip is different than the loss of load trip and would therefore be unaffected.
C. Plausible if thought that the failure of the Loss of Load circuit would prevent the High Pressurizer Pressure Trip.
D. Plausible if thought that the failure of the Loss of Load circuit would prevent both high pressure Page 31 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 trips from tripping the Reactor.
Technical Reference(s) SD-SO23-175 Steam Bypass Control Attached w/ Revision # See System (SBCS) Comments / Reference SD-SO23-710 Reactor Protection System SD-SO23-520 Anticipated Transient Without Scram-Diverse Scram System Proposed references to be provided during examination:
Learning Objective: 55254 - DESCRIBE the expected response of the associated components, instruments and controls for a malfunction or misoperation of one or more of the following Plant Protection System components: 120 VAC Power Sources, Input Sensors, Output Devices Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /
Reference:
SD-SO23-175 Steam Bypass Control System Revision # 10 (SBCS)
Page 32 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-710 Reactor Protection System Revision # 7 Page 33 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-710 Reactor Protection System Revision # 7 Comments /
Reference:
SD-SO23-520 Anticipated Transient Without Revision # 8 Scram-Diverse Scram System Page 34 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 068 A4.04 Importance Rating 3.8 Liquid Radwaste System: Ability to manually operate and/or monitor in the control room: Automatic isolation Proposed Question: Common 37 Given the following conditions on Unit 2 at 100% power:
- A Liquid Release to the Unit 2 Circulating Water Outfall was in progress from T-057, Radwaste Secondary Tank, when a loss of offsite power occurred.
Which of the following correctly describes the impact to the Liquid Release following the loss of offsite power?
Liquid Release flowrate will be A. flowing at a higher rate due to the loss of Circulating Water System backpressure.
B. terminated due to isolation on loss of the Circulating Water Pumps running interlock.
C. flowing at a lower rate by gravity drain due to loss of the Radwaste Secondary Tank Pumps.
D. flowing at same flowrate due to the release equipment being unaffected by the loss of power.
Proposed Answer: B Explanation:
A. Plausible since Circ Water Pumps will trip on the Loss of Offsite Power and thus lower the backpressure, however the release will isolate via the closure of HV-7644 with no Circ Water Pumps running.
B. Correct.
C. Plausible if thought that the release path would still be aligned following a LOOP, however the release path will isolate on a LOOP.
D. Plausible if thought that components associated with the release are either 1E powered equipment or passive systems.
Technical Reference(s) SD-SO23-680, Miscellaneous Liquid and Attached w/ Revision # See Page 35 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Solid Radwaste Processing System Comments / Reference SD-SO23-650, Coolant Radwaste System Description Proposed references to be provided during examination:
Learning Objective: 55858 - DESCRIBE the operations of the following Miscellaneous Liquid Radwaste System controls, including the name, function, interlocks and location of each: Radwaste to Circwater Outfall Release Valve, 2(3)HV-7644 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 13 55.43 Comments /
Reference:
SD-SO23-680, Miscellaneous Liquid and Solid Revision # 7 Radwaste Processing System Page 36 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-650, Coolant Radwaste System Revision # 13 Description Page 37 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 075 K2.03 Importance Rating 2.6 Circulating Water System: Knowledge of bus power supplies to the following: Emergency/essential SWS pumps Proposed Question: Common 38 Which of the following correctly states the power supplies for Unit 3 Train A Saltwater Cooling Pumps P-112 and P-307?
P-112 P-307 A. 3A04 3A04 B. 3A04 2A04 C. 3B04 3B04 D. 3B04 2B04 Proposed Answer: A Explanation:
A. Correct.
B. Plausible because 3P-307 is located in the Unit 2 SWC Pump Room, however it are powered from Unit 3.
C. Plausible if thought that SWC pumps are 1E 480V power, however they are 4kV pumps.
D. Plausible if thought that SWC pumps are 1E 480V power, however they are 4kV pumps and even though P-307 is located in the Unit 2 pump room, it is still powered from Unit 3.
Technical Reference(s) SD-SO23-410, Saltwater Cooling System Attached w/ Revision # See Description Comments / Reference Proposed references to be provided during examination:
Learning Objective: 60303 - IDENTIFY Salt Water Cooling System flowpaths, components, and locations including being able to draw and label system diagrams.
Page 38 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SD-SO23-410, Saltwater Cooling System Revision # 10 Description Page 39 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-410, Saltwater Cooling System Revision # 10 Description Page 40 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # CE/E02 EA1.1 Importance Rating 3.7 Reactor Trip/Stabilization/Recovery: Ability to interpret and/or monitor the following as they apply to Reactor Trip Recovery:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features Proposed Question: Common 39 Given the following conditions:
- Unit 2 Reactor tripped 10 minutes ago from 100% power.
- SO23-12-1, Standard Post Trip Actions, steps 1 through 10 have been completed.
- The CRS has just diagnosed SO23-12-2, Reactor Trip Recovery, as the optimal EOI.
- SO23-12-1, steps 12-17 have NOT yet been initiated.
At this time, what are the expected setpoints on:
- 1. Pressurizer Level Controller, LIC-0110?
- 2. FWCS Master Controller, FIC-1121?
A. 1. 38%
- 2. 55%
B. 1. 38%
- 2. 68%
C. 1. 53%
- 2. 55%
D. 1. 53%
- 2. 68%
Proposed Answer: B Explanation:
A. Plausible if thought that both controller setpoints automatically adjust to low power setpoints, however only LIC-0110 automatically adjusts to the low power setpoint. Additionally, during steps 12-17 the 22 will lower the setpoint on FIC-1121 to 55% but those steps have not yet been initiated at this time.
B. Correct.
Page 41 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Plausible because only one of the controllers will automatically adjust to the low power setpoint, however these are backwards.
D. Plausible if thought that both controller setpoints required manual operator action to adjust the setpoints, however LIC-0110 will automatically adjust to the low power setpoint.
Technical Reference(s) SO23-13-27, Pressurizer Pressure and Attached w/ Revision # See Level Malfunctions Comments / Reference SO23-9-6, Feedwater Control System Operation Proposed references to be provided during examination:
Learning Objective: 53040 - Predict and explain the response of major plant systems, equipment and parameters to a Reactor Trip.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 42 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-27, Pressurizer Pressure and Level Revision # 7 Malfunctions Pressurizer level setpoint automatically adjusts based on RCS temperature. Following a Reactor trip, temperature will automatically be maintained at 545°F due to SBCS being set at 1000 psia (=545°F for a saturated system)
Page 43 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-9-6, Feedwater Control System Operation Revision # 30 FW Master Controller FV-1121 will automatically maintain SG level but the setpoint must be manual set.
Page 44 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 008 AK2.02 Importance Rating 2.7 Pressurizer Vapor Space Accident: Knowledge of the interrelation between the Pressurizer Vapor Space Accident and the following:
Sensors and detectors Proposed Question: Common 40 Which type of device actuates annunciator 57B17, PZR RELIEF VALVE OPEN?
A. Thermocouple.
B. Acoustic Monitor.
C. Pressure detector.
D. Resistance Temperature Detector (RTD).
Proposed Answer: B Explanation:
A. Plausible if thought that the alarm was actuated by high temperature steam flowing through the relief valve, however it is an acoustic detector.
B. Correct.
C. Plausible if thought that the alarm was actuated by high pressure in the relief line, however it is an acoustic detector.
D. Plausible if thought that the alarm was actuated by high temperature steam flowing through the relief valve, however it is an acoustic detector.
Technical Reference(s) SD-SO23-360, Reactor Coolant System Attached w/ Revision # See Description Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56417 - DESCRIBE the operation of Pressurizer Pressure Control System components, instrumentation, controls and alarms including function, location, interlocks, capacity and power supplies where applicable Page 45 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3 55.43 Comments /
Reference:
SD-SO23-360, Reactor Coolant System Revision # 26 Description Page 46 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 009 EK3.21 Importance Rating 4.2 Small Break LOCA: Knowledge of the reasons for the following responses as the apply to the small break LOCA: Actions contained in EOP for small break LOCA/leak Proposed Question: Common 41 Given the following conditions:
- A small break LOCA is in progress.
- Safety Injection Actuation Signal has actuated.
Which ONE of the following is the basis for maintaining a secondary heat sink?
A. To minimize boron stratification of the RCS.
B. Cooling from the break flow alone is inadequate to remove decay heat.
C. Minimize potential for PTS during cooldown and depressurization phase.
D. Reflux boiling is the primary means of heat removal prior to voiding in the hot legs.
Proposed Answer: B Explanation:
A. Plausible because boron stratification is a concern, however, more so during a Large Break LOCA.
B. Correct.
C. Plausible as this is a valid concern, however it is applicable to an ESDE.
D. Plausible because this statement is true if talking about a Large Break LOCA.
Technical Reference(s) SO23-14-3, LOCA Bases and Deviation Attached w/ Revision # See Justfication Comments / Reference Proposed references to be provided during examination:
Learning Objective: 91482 - Per the LOCA procedure SO23-12-3, DESCRIBE the basis for each step, caution or note.
Page 47 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2011 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3 55.43 Comments /
Reference:
SO23-14-3, LOCA Bases and Deviation Revision # 9 Justfication Page 48 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 011 EA2.04 Importance Rating 3.7 Large Break LOCA: Ability to determine or interpret the following as they apply to a Large Break LOCA: Significance of PZR readings Proposed Question: Common 42 Given the following conditions on Unit 3:
- The Unit tripped from 70% Reactor power due to a large break LOCA.
- Representative Core Exit Temperature is 350°F and slowly lowering.
- Containment pressure is 20 psig and stable.
What is the maximum Pressurizer pressure at which Shutdown Cooling can be placed in service per SO23-12-3, Loss of Coolant Accident?
A. 375 psig.
B. 360 psig.
C. 340 psig.
D. 320 psig.
Proposed Answer: D Explanation:
A. Plausible if thought that the highest pressure at which SDC could be placed in service was 375 psig, however 375 is the temp limit for placing SDC in service following a LOCA.
B. Plausible if thought that 20 psig must be added to the normal pressure requirement of 340 psig, however it is subtracted.
C. Plausible as 340 psig would be the maximum pressure if Containment pressure was < 3 psig, however Containment pressure is 20 psig.
D. Correct. 340 psig - 20 psig = 320 psig.
Technical Reference(s) SO23-12-3, Loss of Coolant Accident Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Page 49 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 56401 - PLACE the Shutdown Cooling System in service during post accident conditions Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SO23-12-3, Loss of Coolant Accident Revision # 22 Comments /
Reference:
SO23-12-3, Loss of Coolant Accident Revision # 22 Page 50 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 015/017 AK1.04 Importance Rating 2.9 RCP Malfunctions: Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow Proposed Question: Common 43 Given the following conditions on Unit 2 at Beginning of Cycle (BOC):
- The Unit is operating at 100% Reactor power.
- RCP P003 tripped on overcurrent due to a shaft seizure.
Ten minutes following the RCP malfunction, which ONE (1) of the following describes the feedwater requirements to maintain levels in the steam generators?
A. Feedwater flow requirement for SG E089 is lower than SG E088 because there is less heat input to SG E089.
B. Feedwater flow requirement for SG E088 is lower than SG E089 because there is less heat input to SG E088.
C. SG E089 and SG E088 feedwater flow requirements are approximately the same because steam demand from each S/G remains balanced.
D. SG E089 and SG E088 feedwater flow requirements are approximately the same because RCP heat input is a small fraction of core decay heat.
Proposed Answer: A Explanation:
A. Correct. RCP P-003 is a loop 1 RCP which connects to SG E089.
B. Plausible if thought that RCP P-003 was a loop 2 RCP, however it is a loop 1 RCP.
C. Plausible as the steam demand is balanced between the two SGs, however with less heat input into E089, E088 will supply more steam and thus require more feedwater to maintain level than E089.
D. Plausible if thought that heat input from the RCPs would be the major factor, however it is mass flowrate which is the major cause for the differing heat transfer rates.
Technical Reference(s) General Physics Heat Transfer Handout Attached w/ Revision # See Page 51 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 SD-SO23-160 Main and Reheat Steam Comments / Reference System Proposed references to be provided during examination:
Learning Objective: 94469 - ANALYZE normal and abnormal operations of the Reactor Coolant System.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5 55.43 Page 52 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
General Physics Heat Transfer Handout Revision # 4 With an RCP stopped in Loop 1, the heat transfer from the Reactor to S/G E-088 is much greater (approximately double) and thus will produce more steam since the S/Gs are cross connected and maintained at the same pressures.
With more steam leaving S/G E-088, more feedwater will be required.
Page 53 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-160 Main and Reheat Steam System Revision # 24 Page 54 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 022 G 2.2.42 Importance Rating 3.9 Loss of Reactor Coolant Makeup: Ability to recognize system parameters that are entry-level conditions for Technical Specifications Proposed Question: Common 44 Given the following conditions:
- Unit 2 is operating at 100% Reactor power.
- The crew has just isolated the Charging pump discharge header due to a leak upstream of Charging Pump Discharge Header Isolation Valve, 2HV-9200.
- An alternate charging path has NOT yet been aligned.
Which ONE of the following Technical Specification LCOs must be entered?
A. LCO 3.0.3 due to TWO Boric Acid Flowpaths being inoperable.
B. LCO 3.1.9, Boration Systems - Operating, due to ONE Boric Acid Flowpath being inoperable.
C. LCO 3.5.2, ECCS - Operating, due to BOTH Trains of Emergency Core Cooling being inoperable.
D. LCO 3.5.4, Refueling Water Storage Tank, due to the Refueling Water Storage Tank being inoperable.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible if thought that only one train of BA required Charging pumps to inject, however both BAMU pumps and gravity feed boration require Charging pumps to inject boron.
C. Plausible as the Charging pumps do start on a SIAS and do aid the ECCS system by injecting boron during a SIAS, however a charging flowpath is not required for ECCS operability.
D. Plausible as the RWST is a potential source of boric acid for the RCS and boron can be injected to the RCS from the RWST via the Charging pumps, however only BA concentration, volume and temperature requirements are needed for RWST operability.
Page 55 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-14, Reactor Coolant Leak Attached w/ Revision # See Technical Specifications Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56649 - Given plant or system conditions, DETERMINE system or equipment OPERABILITY and LCO(s) impacted along with all required actions and surveillances Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-13-14, Reactor Coolant Leak Revision # 18 Page 56 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Technical Specifications, LCO 3.5.2 Bases Revision #
Comments /
Reference:
Technical Specifications, LCO 3.5.4 Bases Revision #
Page 57 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 026 AK3.03 Importance Rating 4.0 Loss of Component Cooling Water: Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: Guidance actions contained in EOP for Loss of CCW Proposed Question: Common 45 Given the following conditions on Unit 3:
- Saltwater Cooling Pump 3P-112 tripped on overcurrent.
- 3P-307 is being aligned for service.
SO23-13-7, Loss of CCW/SWC, cautions, DO NOT close the DC Control Power for the SWC Pump to be started until the running CCW Pump has been stopped.
What is the basis for this caution?
A. SWC Pump breaker failure could result in severe injury or death.
B. An inadvertent dilution would occur due to changes in letdown temperature.
C. An inadvertent boration would occur due to changes in letdown temperature.
D. Applying DC Control Power with a start signal locked in on the SWC Pump could cause control power fuses to blow.
Proposed Answer: A Explanation (Optional):
A. Correct.
B. Plausible as CCW temp would rise without SWC flow and starting a SWC pump could cause a sudden drop in CCW temperature, however prior to placing the standby SWC pump in service the LDHX would be transferred to the opposite CCW/SWC loop.
C. Plausible as CCW temp would rise and starting a SWC pump could cause a sudden drop in CCW temperature, however prior to placing the standby SWC pump in service the LDHX would be transferred to the opposite CCW/SWC loop. Additionally, lowering letdown temp would cause boron concentration to go down, not up.
D. Plausible if thought that the starting current along with charging springs being charged could cause control power fuses to blow, however the power sources for the SWC pump and control power are different.
Page 58 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-7, Loss of CCW/SWC Attached w/ Revision # See SO23-3-2.1, CVCS Operations Comments / Reference Proposed references to be provided during examination:
Learning Objective: 81028 - DESCRIBE the configuration and operational characteristics of CCW System components.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Page 59 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Comments /
Reference:
SO23-3-2.1, CVCS Operations Revision # 38 Page 60 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 027 G 2.1.28 Importance Rating 4.1 Pressurizer Pressure Control System Malfunction: Knowledge of the purpose and function of major system components and controls.
Proposed Question: Common 46 Given the following conditions:
- Unit 2 is operating at 50% power during a power ascension.
- Forcing Pressurizer Spray with two Spray Valves is in progress.
- PIC-0100, Pressurizer Pressure Controller setpoint is 2225 PSIA.
- Both Spray Valves are in AUTO.
- Both Proportional Heaters and all Non-1E Backup Heaters are ON.
- Both 1E Backup Heaters are OFF and in AUTO.
- Pressurizer Pressure Control System is selected to Channel X.
Subsequently, Pressurizer Pressure Transmitter PT-0100X fails LOW.
With NO operator action, what is the status of the 1E Backup Heaters and Pressurizer Spray Valves one (1) minute later?
A. Both 1E Backup Heaters are OFF, both Pressurizer Spray Valves are OPEN.
B. Both 1E Backup Heaters are ON, both Pressurizer Spray Valves are CLOSED.
C. Train A 1E Backup Heater is ON, Train B 1E Backup Heater is OFF, both Pressurizer Spray Valves are CLOSED.
D. Both 1E Backup Heaters are OFF, Train A Pressurizer Spray Valve is CLOSED, Train B Pressurizer Spray Valve is OPEN.
Proposed Answer: B Page 61 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:
A. Incorrect. Plausible because Pressurizer pressure will be rising with all Backup Heaters on, therefore, it could be determined that one minute later pressure was greater than 2250 PSIA which would deenergize the Proportional Heaters and open the Spray Valves. The control signal however, is coming from the failed pressure transmitter which is failed low (1500 PSIA).
B. Correct. Pressurizer Spray is forced by lowering the setpoint of the Pressurizer Pressure Controller from 2250 PSIA to 2225 PSIA. Non-1E Backup Heaters are then energized and when pressure rises 25 PSIA above setpoint (now 2250 PSIA) the Pressurizer Spray Valves start to open. With Channel X failed low, all Heaters will be energized and the Spray Valves will be closed because the pressure input is failed low (1500 PSIA).
C. Incorrect. Plausible because both Spray Valves are closed, however, there is no train differentiation on the 1E Backup Heaters related to the pressure transmitter.
D. Incorrect. Plausible if thought that the Backup Heaters turned off due to high pressure and that train separation existed with the Spray Valves.
Technical Reference(s) SO23-13-27, Attachments 1 & 4 Attached w/ Revision # See SO23-3-1.10, Section 6.3 Comments / Reference Proposed references to be provided during examination: None Learning Objective: 56417 - DESCRIBE the operation of Pressurizer Pressure Control System components, instrumentation, controls and alarms including function, location, interlocks, capacity and power supplies where applicable.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2011 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Page 62 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-27, Pressurizer Pressure and Level Revision # 7 Malfunctions With the setpoint set to 2225 psia, and a failure of the pressure transmitter to 1500 psia, both spray valves will be closed.
Page 63 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-27, Pressurizer Pressure and Level Revision # 7 Malfunctions The 1E heaters will deenergize if their respective train level transmitter fails low, however it was the press xmitter that failed low in this case.
Page 64 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038 EK1.03 Importance Rating 3.9 Steam Generator Tube Rupture: Knowledge of the operational implications of the following concepts as they apply to the SGTR: Natural circulation Proposed Question: Common 47 Given the following conditions:
- Unit 3 Reactor tripped 30 minutes ago due to a Loss of Offsite Power.
- Upon the Reactor trip, a Steam Generator Tube Rupture occurred on S/G E-089.
- Pressurizer pressure is 1400 psia and stable.
- Steam Generator E-089 has been isolated.
- SO23-12-11, FS-3, Monitor Natural Circulation Established, is in progress.
- SO23-12-11, Attachment 3, Cooldown and Depressurization, has just been initiated.
Which ONE of the following correctly describes the
- 1. initial RCS cooldown rate?
- 2. method of RCS depressurization?
A. 1. 35-40°F / hr.
- 2. Normal Pressurizer Spray.
B. 1. 70-95°F / hr.
- 2. Auxiliary Pressurizer Spray.
C. 1. 35-40°F / hr.
- 2. Auxiliary Pressurizer Spray.
D. 1. 70-95°F / hr.
- 2. Normal Pressurizer Spray.
Proposed Answer: C Explanation:
Page 65 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 A. Plausible as the initial cooldown rate during a natural circ asymmetrical cooldown is35-40F, however with no RCPs running, normal spray is not available.
B. Plausible as aux spray is the correct method of depressurization, however the initial cooldown rate during a natural circ asymmetrical cooldown is35-40F.
C. Correct.
D. Plausible as this would be the correct cooldown rate and depressurization method if both S/Gs and RCPs were available, however that is not the case.
Technical Reference(s) SO23-12-4, Steam Generator Tube Attached w/ Revision # See Rupture Comments / Reference SO23-12-11, EOI Supporting Attachments Proposed references to be provided during examination:
Learning Objective: 53909 - As the RO, respond to a SGTR, per SO23-12-4.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 2, 10 55.43 Page 66 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-4, Steam Geneator Tube Rupture Revision # 23 Page 67 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-11, EOI Supporting Attachments Revision # 14 Page 68 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-11, EOI Supporting Attachments Revision # 14 Page 69 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # CE/E05 EA2.2 Importance Rating 3.4 Steam Line Rupture/Excessive Heat Transfer: Ability to determine and interpret the following as they apply to the (Excess Steam Demand): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments Proposed Question: Common 48 Given the following conditions on Unit 2:
- At 0200, Unit 2 tripped from 100% power.
- At 0215, following the transition into SO23-12-2, Reactor Trip Recovery, an Excess Steam Demand Event occurred on S/G E-089.
- At 0227, RCS Tc was stabilized by setting HV-8419, S/G E-088 Atmospheric Dump Valve, to 351 psia, in automatic control.
Assuming RCS Tc is maintained stable, what is the earliest time that the Technical Specification cooldown rate limit will be restored?
A. 0323 B. 0330 C. 0335 D. 0342 Proposed Answer: A Explanation:
A. Correct. The TS cooldown rate limit is 100°F/hr. This equates to a rate of 1.67°F/min. RCS Tc lowered 113°F in 12 minutes. At a rate of 1.67°F/min, it would take 68 minutes to lower 113°F.
Since the cooldown commenced at 0215, temperature would have remain steady for 56 additional minutes to average a less than 100°F/hr cooldown rate.
B. Plausible if thought that the Technical Specification cooldown rate was 90°F/hr, however that is the site administrative limit.
C. Plausible because 68 minutes is the correct total time at the TS rate of 100°F/hr, however the Page 70 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 cooldown started when the ESDE occurred, not when RCS temperature was stabilized.
D. Plausible because 75 minutes is the correct total time at the administrative rate of 90°F/hr, however the cooldown started when the ESDE occurred, not when RCS temperature was stabilized.
Technical Reference(s) Technical Specifications Attached w/ Revision # See Steam Tables Comments / Reference SO23-05-01.05 Plant Shutdown from Hot Standby to Cold Shutdown Proposed references to be provided during examination: Steam Tables Learning Objective: 94469 - ANALYZE normal and abnormal operations of the Reactor Coolant System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5 55.43 Page 71 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
LCS 3.4.103, RCS Pressure and Temperature Revision # 1 Limits Comments /
Reference:
SO23-05-01.05 Plant Shutdown from Hot Revision # 38 Standby to Cold Shutdown Page 72 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 054 AK3.04 Importance Rating 4.4 Loss of Main Feedwater: Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW):
Actions contained in EOPs for loss of MFW Proposed Question: Common 49 Given the following conditions:
- Unit 3 has experienced a complete loss of Feedwater.
- SO23-12-6, Loss of Feedwater, is in progress.
- Steam Generators are being depressurized to facilitate feedwater restoration.
Per SO23-12-6, Loss of Feedwater, what is the reason for this direction?
To prevent A. isolating steam to AFW Pump P-140.
B. a loss of the Main Feedwater flowpath.
C. a loss of the Auxiliary Feedwater flowpath.
D. inadvertent closure of the Atmospheric Dump Valves.
Proposed Answer: B Explanation:
A. Plausible if thought that P-140 was a potential success path and that MSIS would isolate steam to the pump, however MSIS does not isolate steam to P-140.
B. Correct.
C. Plausible as the correct reason is a loss of feed path, however the concern is the loss of the Main Feedwater flowpath.
D. Plausible since the ADVs do close on an MSIS and may be in use to facilitate the depressurization.
Page 73 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-12-6, Loss of Feedwater Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53001 - Per the LOFW procedure SO23-12-6 describe the basis for each step, caution or note.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-12-6, Loss of Feedwater Revision # 23 Page 74 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055 EA1.05 Importance Rating 3.3 Station Blackout: Ability to operate and monitor the following as they apply to a Station Blackout: Battery, when approaching fully discharged Proposed Question: Common 50 Given the following conditions:
- A Station Blackout has occurred on Unit 2.
- Unit 3 1E AC buses are being supplied by the Unit 3 Emergency Diesel Generators.
- All 1E DC buses indicate 120 VDC and lowering.
- All DC load reductions have been completed.
- AC power restoration is not expected on Unit 2 for several hours.
SO23-12-8, Station Blackout, directs ____(1)____ when ALL 1E DC Buses voltages lower below a maximum of ____(2)____ VDC.
A. 1. cross-tying Unit 2 and Unit 3 1E DC buses
- 2. 108 B. 1. cross-tying Unit 2 and Unit 3 1E DC buses
- 2. 118 C. 1. transferring L411 EPPM Panel power to Portable Generator G005
- 2. 108 D. 1. transferring L411 EPPM Panel power to Portable Generator G005
- 2. 118 Proposed Answer: C Explanation:
A. Plausible as 108 VDC is the voltage where action is required and cross-tying power between units is a potential recovery action for a Station Blackout, however this is only available for AC power.
B. Plausible as 118 VDC is the voltage where 1E Bus Trouble alarm comes in and cross-tying power Page 75 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 between units is a potential recovery action for a Station Blackout, however this is only available for AC power.
C. Correct.
D. Plausible as this is the correct action, however 118 VDC is the voltage where 1E Bus Trouble alarm comes in, not the voltage at which the EPPM is placed on G005.
Technical Reference(s) SO23-12-8, Station Blackout Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52386 - DESCRIBE the conditions that affect the severity of a station blackout.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-12-8, Station Blackout Revision # 23 Page 76 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056 AA1.10 Importance Rating 4.3 Loss of Offsite Power: Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power: Auxiliary/emergency feedwater pump (motor driven)
Proposed Question: Common 51 Given the following conditions on Unit 2:
- The Reactor tripped 5 minutes ago from 100% power.
- Emergency Feed Actuation Signal (EFAS) 1 and 2 automatically actuated four minutes ago.
- One minute ago, a loss of off-site power occurred.
- S/G levels are both 24% NR and slowly lowering.
What is the expected response of Train A AFW Pump P-141?
Pump P-141 will A. start immediately due to the EFAS signal being locked in.
B. remain off until S/G E-089 level lowers to < 21% and then start immediately.
C. start after a 30-second time delay due to the EFAS signal being locked in.
D. remain off until S/G E-089 level lowers to < 21% and then start after a 30-second time delay.
Proposed Answer: C Explanation:
A. Plausible if thought that the pump would restart immediately since it was already running, however if power is lost, the 30 second time delay restarts.
B. Plausible as the AFW cycling valves will not reopen until < 21%, however the pump will restart after the 30 second time delay, regardless of level.
C. Correct.
D. Plausible if thought that the pump would restart immediately since it was already running, however if power is lost, the 30 second time delay restarts. Also, the AFW cycling valves will not reopen until < 21%, however the pump will restart after the 30 second time delay, regardless of level.
Page 1 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-780, AFW System Description Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52844 - DESCRIBE the general sequence of events during a Loss of Offsite Power or Station Blackout event Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 2 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-780, AFW System Description Revision # 15 Comments /
Reference:
SD-SO23-720 Engineered Safety Features Revision # 10 Actuation System Page 3 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 057 AA1.01 Importance Rating 3.7 Loss of Vital AC Instrument Bus: Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus:
Manual Inverter Swapping Proposed Question: Common 52 Given the following conditions:
- Unit 3 has experienced loss of Vital Bus Y01 due to a failed inverter.
- Y01 is currently being manually transferred to its alternate source of power.
Which ONE of the following Control Room indications will return, giving the crew positive indication that Vital Bus Y01 has been transferred to its alternate source of power?
A. CRT Rod Position indication.
B. DC Bus D1 voltage indication.
C. Channel A lumigraphs on CR56.
D. Pressurizer Pressure controller PIC-0100.
Proposed Answer: C Explanation:
A. Plausible if thought that CEAC 1 is powered from Vital Bus Y01, however it is powered from Vital Bus Y02.
B. Plausible if thought a loss of Vital Bus Y01 would cause a loss of D1 indication, however this does not occur since the D1 battery will maintain voltage indication.
C. Correct.
D. Plausible if thought that PIC-0100 gets power from Y01, however PIC-0100 gets power from Instrument Bus #1.
Technical Reference(s) SO23-13-18, Loss of a Vital Bus Attached w/ Revision # See SO23-13-19, Loss of a Non-1E Inst Bus Comments / Reference Proposed references to be provided during examination:
Page 4 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 52762 - DISCUSS the operation of the 1E 125 VDC/120 VAC System including controls, instrumentation, interlocks, capacity, power supplies and system response to component failures.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SO23-13-18, Loss of a Vital Bus (loss of Y01) Revision # 14-2 Comments /
Reference:
SO23-13-18, Loss of a Vital Bus (loss of Y02) Revision # 14-2 Page 5 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-19, Loss of a Non-1E Inst Bus Revision # 15 Page 6 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 058 G 2.4.8 Importance Rating 3.8 Loss of DC Power: Knowledge of how abnormal operating procedures are used in conjunction with EOPs Proposed Question: Common 53 Given the following conditions:
- Unit 3 tripped from 100% Reactor power 5 minutes ago.
- SO23-12-1, Standard Post Trip Actions are in progress.
- All swing equipment is aligned to Train B.
A complete loss of 1E 125 VDC Bus D2 has just occurred.
Which ONE of the following mitigating actions will require LOCAL operator action to complete?
A. Securing Charging Pump P-191 per SO23-13-18, Loss of a 1E DC Bus.
B. Operation of BOTH Atmospheric Dump Valves per SO23-13-18, Loss of a 1E DC Bus.
C. Opening SWC Pump P-114 Discharge Valve, HV-6203, per SO23-13-7, Loss of CCW/SWC.
D. Transferring the non-critical CCW loop from Train B to Train A per SO23-13-7, Loss of CCW/SWC.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible since a loss of D2 will fail one ADV closed and fail the pressure input to the other ADV, however one ADV can still be operated in MANUAL from the Control Room. Additionally, this failure is a result of a loss of Vital Bus Y02, but is directed from SO23-13-18, Attachment 6, Loss of D2.
C. Plausible since HV-6203 fails on a loss of D2, however it fails open.
D. Plausible since the non-critical loop must be transferred to Train A, however it can be done from the Control Room on a loss of D2.
Technical Reference(s) SO23-13-18, Loss of a 1E DC Bus Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Page 7 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 80607 - ANALYZE normal and abnormal operations of the 1E 125 VDC and 120 VAC Electrical System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /
Reference:
SO23-13-18, Loss of a 1E DC Bus Revision # 14-2 Page 8 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 9 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 062 AK3.02 Importance Rating 3.6 Loss of Nuclear Service Water: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS Proposed Question: Common 54 Given the following conditions on Unit 2:
- Unit 2 tripped 5 minutes ago due to a large break LOCA.
- Safety Injection (SIAS) and Containment Cooling Actuation Signals (CCAS) have both actuated.
- All swing pumps are aligned to Train A.
- Train A CCW/SWC was in service prior to the trip.
- Train B CCW/SWC was in standby.
Which ONE of the following describes the automatic plant response to SWC Pump 2P-114 failing to start on the ESFAS actuations, and what is the reason for this response?
A. CCW Pump 2P-026 will start, however Train B Emergency Cooling Units WILL NOT start due to the failure of SWC Pump 2P-114 to start.
B. CCW Pump 2P-026 and Train B Emergency Cooling Units will start due to SWC Pump 2P-114 having no effect on their starting circuitry.
C. CCW Pump 2P-026 will not start due to the failure of SWC Pump 2P-114 to start, Train B Emergency Cooling Units will not start due to the CCW Pump 2P-026 not starting.
D. CCW Pump 2P-026 will not start due to the failure of SWC Pump 2P-114 to start, Train B Emergency Cooling Units will start but Containment cooling will be degraded due to the loss of heat sink.
Proposed Answer: B Explanation:
A. Plausible as the CCW P-026 will start, however the Train B ECUs will start. The ECUs do have a low flow interlock, but that interlock is with CCW, not SWC.
Page 10 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 B. Correct.
C. Plausible as CCW and SWC do have a master-slave starting interlock, however it is SWC that starts on a CCW pump start, not the other way around. Additionally, the Train B ECUs will not start if the CCW pump doesnt start.
D. Plausible as CCW and SWC do have a master-slave starting interlock, however it is SWC that starts on a CCW pump start, not the other way around. Additionally, Train B ECUs will start given the listed conditions and the cooling they would provide would be degraded without Train B SWC flow.
Technical Reference(s) SD-SO23-770, Containment Design, Attached w/ Revision # See Ventilation and Hydrogen Control Systems Comments / Reference SD-SO23-400, Component Cooling Water Proposed references to be provided during examination:
Learning Objective: 60307 - ANALYZE normal and abnormal operations of the Salt Water Cooling System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4, 7 55.43 Comments /
Reference:
SD-SO23-770, Containment Design, Ventilation Revision # 11 and Hydrogen Control Systems Page 11 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-400, Component Cooling Water Revision # 23 Page 12 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 065 AA2.08 Importance Rating 2.9 Loss of Instrument Air: Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Failure modes of air-operated equipment Proposed Question: Common 55 Given the following conditions:
- Unit 3 is in MODE 3 during a MOC startup
- Auxiliary Feedwater Bypass Control Valves 3HV-4762 and 3HV-4763 are 20% open.
Subsequently, a complete loss of Instrument Air occurs.
The AFW Bypass Control Valves will fail ___(1)___ and the Steam Bypass Control Valves will fail ___(2)___.
A. 1. as-is
- 2. as-is B. 1. as-is
- 2. closed C. 1. closed
- 2. as-is D. 1. closed
- 2. closed Proposed Answer: D Explanation:
A. Plausible as Main Feedwater Regulating valves fail as-is on a loss of instrument air and closure of SBCS valves would cause RCS temperature to rise, however all of these valves fail closed.
B. Plausible as Main Feedwater Regulating valves fail as-is on a loss of instrument air, however they fail closed.
C. Plausible as AFW bypass control valves fail closed on a loss of IA, however SBCS valves fail closed.
D. Correct.
Page 13 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-5, Loss of Instrument Air Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53373 - IDENTIFY the local indications, automatic actions, and effect on other plant systems and equipment for a Loss of Instrument Air.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Page 14 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-5, Loss of Instrument Air Revision # 13 Page 15 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 077 AK2.07 Importance Rating 3.6 Generator Voltage and Electric Grid Disturbances: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Turbine / generator control Proposed Question: Common 56 Given the following conditions:
Unit 2 is operating at 100% Reactor power when the Turbine Control System megawatt loop was inadvertently placed in service.
Which ONE of the following grid disturbances would cause Reactor power to exceed 100%?
A. Rising grid voltage.
B. Rising grid frequency.
C. Lowering grid voltage.
D. Lowering grid frequency.
Proposed Answer: B Explanation:
A. Plausible as a reduction in Main Turbine load with the megawatt loop will cause Reactor power to rise, but only for a reduction in real load, not reactive load.
B. Correct.
C. Plausible as the Unit will assume more reactive load if grid voltage lowers, however an increase in reactive load will not cause Reactor power to increase.
D. Plausible as the Unit will assume more real load if grid frequency lowers, however steam demand will not change, thus Reactor power will not change.
Technical Reference(s) SO23-10-2 Turbine Startup and Normal Attached w/ Revision # See Operation Comments / Reference Proposed references to be provided during examination:
Page 16 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: 53690 - Given a malfunction or misoperation, DESCRIBE the expected response of the associated components, instruments and controls of the turbine protection system.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5 55.43 Comments /
Reference:
SO23-10-2, SO23-10-2 Turbine Shutdown Revision # 25 Page 17 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 001 AK1.06 Importance Rating 4.0 Continuous Rod Withdrawal: Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal: Relationship of reactivity and reactor power to rod movement Proposed Question: Common 57 Given the following Middle-of-Cycle (MOC) conditions:
- The Reactor was critical at 2x10-3% power when a CEDMCS malfunction caused a 10 second continuous withdrawal of Group 6 CEAs to occur.
- The Steam Bypass Control System (SBCS) is in AUTO.
Which ONE of the following correctly describes the automatic Reactor response?
Reactor power will...
A. rise and stabilize above the Point of Adding Heat.
B. rise to the point of tripping on High Logarithmic Power.
C. remain constant and Reactor Coolant System temperature will rise.
D. rise until the point of adding heat and then lower to some point below the Point of Adding Heat.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as the Reactor would trip on high log power at .83%, however this trip is bypassed at 1x10-4%.
C. Plausible as RCS temperature will rise when greater than the POAH, however power will not remain the same.
D. Plausible as power will rise above the point of adding heat and stabilize, however it will stabilize above the point of adding heat.
Technical Reference(s) General Physics Kinetics Handout Attached w/ Revision # See Comments / Reference Page 18 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination:
Learning Objective: 53251 - DESCRIBE the response of the following parameters with time during and following a positive reactivity insertion into a critical reactor below the point of adding heat: Reactor power level Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 1 55.43 Page 19 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
General Physics Kinetics Handout Revision # 4 Page 20 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 005 AK3.05 Importance Rating 3.4 Inoperable/Stuck Control Rod: Knowledge of the reasons for the following responses as they apply to the Inoperable / Stuck Control Rod:
Power limits on rod misalignment Proposed Question: Common 58 Given the following conditions:
- Unit 2 was operating at 100% Reactor power when a Shutdown Bank CEA slipped 30 into the core.
- All efforts to withdraw the slipped CEA were unsuccessful.
SO23-13-13, Misaligned or Immovable Control Element Assembly, directs lowering Reactor power in accordance with the Core Operating Limits Report.
Which ONE of the following describes the reason for lowering Reactor power in this condition?
A. To compensate for increased Radial Power Peaking in the core.
B. To determine the amount of negative reactivity added by the dropped CEA.
C. To ensure RCS temperature remains above the Technical Specification limit.
D. To compensate for the reduction in Shutdown Margin from the misaligned CEA.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as turbine load will lowered to restore Tc and determine the amount of negative reactivity inserted by the CEA misalignment, however this is not the reason for the Reactor power reduction.
C. Plausible as lowering turbine load will raise RCS Tc and will assist in remaining above 535°F, however this is not the reason for the Reactor power reduction.
D. Plausible as Shutdown Margin is reduced with a CEA not fully withdrawn, however this is not the reason for reducing Reactor power.
Technical Reference(s) 2AO713, Misaligned CEA Lesson Plan Attached w/ Revision # See Page 21 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 SO23-5-1.7, Power Operations Comments / Reference LCS 3.1.105 Proposed references to be provided during examination:
Learning Objective: 54879 - Per the misaligned CEA procedure, SO23-13-13, DESCRIBE: The basis for each step, caution, or note Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
LCS 3.1.105 Revision #
Page 22 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
2AO713, Misaligned CEA Lesson Plan Revision # 6-9 Page 23 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 051 AA1.04 Importance Rating 2.5 Loss of Condenser Vacuum: Ability to operate and / or monitor the following as they apply to the Loss of Condenser Vacuum: Rod position Proposed Question: Common 59 Given the following conditions on Unit 2 while shutting down for a refueling outage:
- Reactor power is 40% and lowering.
- Main Condenser backpressure is 3.7 Hg and slowly degrading.
Which ONE of the following describes the mitigating actions to be taken in this situation?
A. Condenser vacuum is in the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit area of operation. Attempt to restore Condenser vacuum by performing a rapid power reduction using CEAs ONLY.
B. Condenser vacuum has exceeded the Low Vacuum Turbine Trip setpoint.
Immediately trip the Reactor and enter SO23-12-1, Standard Post Trip Actions.
C. Condenser vacuum is in the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit area of operation. Attempt to restore Condenser vacuum by performing a rapid power reduction using CEAs and boron.
D. Condenser vacuum has exceeded the Low Vacuum Turbine Trip setpoint.
Immediately trip the Turbine ONLY and perform a rapid power reduction using CEAs ONLY.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible if thought that at 40% Reactor power that 3.7 Hg backpressure is exceeding the Turbine trip setpoint, however the trip setpoint at this power level is 4.5 Hg. Additionally, the Reactor would not be required to be tripped as 40% is below the Loss of Load trip setpoint.
C. Plausible as vacuum is in the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit area, however when boron concentration is less than 110 ppm, only CEAs are used to reduce power.
D. Plausible as only the Turbine would have to be tripped if the low vacuum trip setpoint was exceeded, however the trip setpoint is 4.5Hg at this power level. Additionally, downpowering with Page 24 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 only CEAs is the correct action to take.
Technical Reference(s) SO23-5-1.7, Power Operations Attached w/ Revision # See SO23-13-10, Loss of Vacuum Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52775 - DESCRIBE the Unit 2/3 Low Pressure Turbine Back Pressure limits and their effects on operator actions during normal and off-normal conditions Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 25 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.7, Power Operations Revision # 53 Page 26 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-10, Loss of Vacuum Revision # 10 Comments /
Reference:
SO23-13-28, Rapid Power Reduction Revision # 7 Page 27 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-28, Rapid Power Reduction Revision # 7 Page 28 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 059 AA2.03 Importance Rating 3.1 Accidental Liquid Radwaste Release: Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: Failure modes, their symptoms, and the causes of misleading indications on a radioactive-liquid monitor Proposed Question: Common 60 A liquid release of Secondary Radwaste Tank T-057 is in progress.
Per SO23-8-7, Liquid Radioactive Waste Release Operations, why is it necessary to maintain the process flowrate greater than 60 gpm?
A. The liquid radwaste discharge valves, 2/3HV-7641 and -7642, fail closed on low flow.
B. The minimum sensitivity of radiation monitor, RE-7813, requires greater than 60 gpm sample flow.
C. Maintaining a flowrate of > 60 gpm minimizes localized hot spots in Radwaste discharge piping.
D. Less than 60 gpm flowrate will not maintain the Marineli Canister around the radiation detector full of sample fluid.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as RE-7813 does require a minimum sample flow, however the sample flow required is 2 gpm. 60 gpm of process flow satisfies the 2 gpm sample flow.
C. Plausible as higher flowrate will minimize the buildup of crud and assist in minimizing hot spots, however this is not the basis for requiring 60 gpm of process flow.
D. Plausible as low sample flow could potentially fail to fill the sample flow canister, however this is not the reason for maintaining > 60 gpm process flow.
Technical Reference(s) SO23-8-7, Liquid Radioactive Waste Attached w/ Revision # See Release Operations Comments / Reference Proposed references to be provided during examination:
Learning Objective: 55858 - DESCRIBE the operations of Miscellaneous Liquid Radwaste System controls, including the name, function, interlocks and location of each Page 29 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 11 55.43 Comments /
Reference:
SO23-8-7, Liquid Radioactive Waste Release Revision # 23 Operations Page 30 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 068 AK2.01 Importance Rating 3.9 Control Room Evacuation: Knowledge of the interrelations between the Control Room Evacuation and the following: Auxiliary shutdown panel layout Proposed Question: Common 61 Which ONE of the following evolutions can be performed from the Evacuation Shutdown Panel, L-042?
A. Isolate Safety Injection Tanks.
B. Start and stop Charging Pumps.
C. Start an Emergency Diesel Generator.
D. Initiate feed flow to a Steam Generator.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as this action is directed in SO23-13-2, Shutdown From Outside the Control Room, however this done locally.
C. Plausible as this action is directed in SO23-13-2, Shutdown From Outside the Control Room, however this done locally.
D. Plausible as this action is directed in SO23-13-2, Shutdown From Outside the Control Room, however this done locally.
Technical Reference(s) SO23-13-2, Shutdown From Outside the Attached w/ Revision # See Control Room Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56675 - As the RO. perform 21/31 actions during a Shutdown from Outside the Control Room, per SO23-13-2 Page 31 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-13-2, Shutdown From Outside the Control Revision # 19 Room Level RO SRO Page 32 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference:
Tier # 1 Group # 2 K/A # 074 G 2.4.6 Importance Rating 3.7 Inadequate Core Cooling: Knowledge of EOP mitigation strategies.
Proposed Question: Common 62 Given the following conditions:
- Unit 2 tripped 10 seconds ago from 100% Reactor power due to lowering RCS pressure.
- Pressurizer level is 5% and lowering rapidly.
- RCS pressure is 1575 psia and lowering rapidly.
In this condition, SO23-12-3, Loss of Coolant Accident, directs the operator to ensure SIAS has actuated.
Which ONE of the following describes the primary reason for this direction?
A. To provide adequate core Shutdown Margin during the RCS depressurization.
B. To provide adequate RCS subcooling during and after initial RCS depressurization.
C. To restore RCS pressure control by refilling the Pressurizer during depressurization.
D. To restore RCS inventory control when RCS pressure lower below HPSI pump shut off head.
Proposed Answer: D Explanation:
A. Plausible as HPSI pumps are used for Reactivity Control if > 1 full length CEA failed to insert and emergency boration is not available, however this is not the case.
B. Plausible as the injection of SI flow will aid in recovering RCS subcooling, however this is not the primary reason for SI flow.
C. Plausible as SI flow will aid in minimizing the pressure drop, however this is not the primary reason for SI flow.
D. Correct.
Technical Reference(s) SO23-12-3, Loss of Coolant Accident Attached w/ Revision # See SO23-14-3, Loss of Coolant Accident Comments / Reference Page 33 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Bases Proposed references to be provided during examination:
Learning Objective: 54933 - Per the LOCA procedure, SO23-12-3, DESCRIBE the basis for each step, note or caution Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments /
Reference:
SO23-12-3, Loss of Coolant Accident Revision # 22 Page 34 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-14-3, Loss of Coolant Accident Bases Revision # 9 Page 35 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-14-3, Loss of Coolant Accident Bases Revision # 9 Page 36 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 076 AK2.01 Importance Rating 2.6 High Reactor Coolant Activity: Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors Proposed Question: Common 63 Given the following conditions:
- Unit is operating normally at 100% power.
- NO radioactive releases are in progress .
- Secondary Radwaste Tank T-057 has developed a large leak at the tank outlet flange.
Which ONE of the following radiation monitors will be the first to indicate a high activity?
A. Liquid Waste Discharge Monitor RE-7813.
B. Plant Vent Stack Range Monitor RE-7808.
C. BPS Neutralization Sump Monitor RE-7817.
D. Containment Purge Stack Monitor RE-7828.
Proposed Answer: B Explanation:
A. Plausible if thought that T-057 vault drains are discharged through the normal Radwaste discharge line as the normal discharge line is monitored by RE-7813, however the vault drains to the Radwaste sump. The Radwaste sump is vented to atmosphere which exits through the Plant Vent Stack.
B. Correct. Radwaste air discharges exit via the Plant Vent Stack which is monitored by RE-7808.
C. Plausible if thought that the Radwaste area vaults drained to the BPS system which is monitored by RE-7817, however the vault drains to the Radwaste sump. The Radwaste sump is vented to atmosphere which exits through the Plant Vent Stack.
D. Plausible if thought that Radwaste gases are discharged through the Purge Stack which is monitored by RE-7828, however only Containment air exits via the Purge Stack.
Technical Reference(s) SD-SO23-690, Radiation Monitoring Attached w/ Revision # See System Comments / Reference Page 37 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 SD-SO23-622 Radwaste Building Ventilation and Continueous Exhaust Ventilation Systems Proposed references to be provided during examination:
Learning Objective: 56767 - DETERMINE the appropriate radiation monitor(s) to be used under the given conditions and the action to be taken based on the radiation monitor conditions.
Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2006 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 11 55.43 Comments /
Reference:
SD-SO23-690, Radiation Monitoring System Revision # 18 Page 38 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 39 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-622 Radwaste Building Ventilation and Revision # 5 Continueous Exhaust Ventilation Systems Page 40 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # CE/A11 AK3.3 Importance Rating 3.1 RCS Overcooling: Knowledge of the reasons for the following responses as they apply to the (RCS Overcooling): Manipulation of controls required to obtain desired operating results during abnormal and emergency situations Proposed Question: Common 64 Following a steam line rupture inside Containment, SO23-12-5, Excess Steam Demand Event, directs the operator to stabilize RCS temperature using the Atmospheric Dump Valve on the unaffected Steam Generator, once dryout has occurred on the affected Steam Generator.
What is the reason for stabilizing RCS temperature?
A. Ensure minimum RCS Subcooled Margin is maintained.
B. Promote initial development of Natural Circulation flow through the core.
C. Prevent the RCS cooldown rate from exceeding Technical Specification limits.
D. Limit RCS heatup, which may result in Pressurized Thermal Shock conditions.
Proposed Answer: D Explanation:
A. Plausible as an RCS heatup following dryout of a S/G could cause a loss of subcooling margin, however this is not the reason for stabilizing RCS temperature.
B. Plausible as stable or lowering RCS temperatures is a requirement for natural circulation, however this is not the reason for stabilizing RCS temperature.
C. Plausible as RCS TS cooldown limits may be exceeded during an ESDE, however this is not the reason for stabilizing RCS temperature.
D. Correct.
Page 41 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-14-11 EOI Supporting Attachments Attached w/ Revision # See Bases and Deviations Justification Comments / Reference Proposed references to be provided during examination:
Learning Objective: 54790 - Per the ESDE procedure SO23-12-5 DESCRIBE the basis for each step, caution or note Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments /
Reference:
SO23-14-11 EOI Supporting Attachments Bases Revision # 3 and Deviations Justification Page 42 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # CE/E09 EK1.3 Importance Rating 3.2 Functional Recovery: Knowledge of the operational implications of the following concepts as they apply to the (Functional Recovery):
Annunciators and conditions indicating signals, and remedial actions associated with the (Functional Recovery)
Proposed Question: Common 65 Given the following conditions:
- Unit 3 tripped from 100% power 20 minutes ago.
- Standard Post Trip Actions have been completed and SO23-12-6, Loss of Feedwater has been entered.
- RCS temperature is 545°F and stable.
- RCS pressure is 2050 psia and slowly lowering.
- Both S/G pressures are 1000 psia and stable.
- S/G E-089 level is 60% WR and slowly lowering.
- S/G E-088 level is 5% NR and slowly rising.
- Feedwater flow has NOT been established.
- Annunciator window 60A46, Secondary Radiation Hi, has just gone into alarm.
How do the current conditions impact the mitigation strategy of the crew?
The crew will A. exit SO23-12-6, Loss of Feedwater, and enter SO23-12-9, Functional Recovery.
B. initiate SO23-12-4, Steam Generator Tube Rupture, in conjunction with SO23-12-6, Loss of Feedwater.
C. initiate SO23-12-9, Functional Recovery, in conjunction with SO23-12-6, Loss of Feedwater.
D. continue in SO23-12-6, Loss of Feedwater, due to RCS Heat Removal being a higher safety function than Containment Isolation.
Proposed Answer: A Explanation:
Page 43 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 A. Correct. The Containment Isolation safety function will be failed when the secondary rad hi alarm is received and will require a rediagnosis. The rediagnosis will indicate two events and direct transition into the Functional Recovery procedure.
B. Plausible as a SGTR and LOFW are both indicated, however the FR will be entered, not two EOIs simultaneously.
C. Plausible as the FR will be entered, however it will not be performed in conjunction with the LOFW EOI.
D. Plausible as RCS Heat Removal is a higher safety function, however entering the FR is required.
Technical Reference(s) SO23-12-10, Safety Function Status Attached w/ Revision # See Checks Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53956 - As the RO, EVALUATE a safety function status check for optimal recovery EOIs.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 44 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 Page 45 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 Page 46 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.1.3 Importance Rating 3.7 Conduct of Operations: Knowledge of shift or short-term relief turnover practices Proposed Question: Common 66 Given the following conditions:
- Both Units are operating at 100% Reactor power.
- Both Units are manned to minimum Appendix R levels.
- There are 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> remaining on the shift.
- The Unit 2 CRS is Shift Manager qualified.
- The Shift Manager receives a message about a family emergency at home and wants to leave the site immediately.
Which ONE of the following describes the required actions to maintain Minimum Operations Shift Crew Composition requirements, per SO123-0-A1, Conduct of Operations?
A. The Shift Manager may NOT leave the Protected Area until another Shift Manager has been recalled and is within the Protected Area.
B. The Shift Manager may leave the Protected Area, however a replacement Shift Manager must be within the Protected Area within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. The Shift Manager may leave the Protected Area immediately if the Unit 2 CRS assumes Shift Manager duties, however a replacement CRS must be recalled and be within the Protected Area within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. The Unit 2 CRS may assume the Shift Manager duties immediately, however the Shift Manager may NOT leave the Protected Area until a replacement CRS has been recalled and is within the Protected Area.
Proposed Answer: C Explanation:
A. Plausible as the SM position is excluded from the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time window to drop below minimum manning, however the SM could be relieved by the Unit 2 CRS.
Page 47 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 B. Plausible as this is true for all positions except for the SM.
C. Correct.
D. Plausible as the SM position cannot be vacated, however the CRS position may be one less than minimum manning for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Technical Reference(s) SO123-0-A1, Conduct of Operations Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 52816 - DESCRIBE the guidelines and administrative requirements for Operations Shift Relief.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 48 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO123-0-A1, Conduct of Operations Revision # 35 Comments /
Reference:
SO123-0-A1, Conduct of Operations Revision # 35 Page 49 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.1.19 Importance Rating 3.9 Conduct of Operations: Ability to use plant computers to evaluate system or component status Proposed Question: Common 67 Given the following post-LOCA Qualified Safety Parameter Display System (QSPDS) indications on Unit 3:
- The temperature difference between Heated and Unheated Junction Thermocouples 1 through 6 are all approximately 225°F.
- The temperature difference between Heated and Unheated Junction Thermocouples 7 and 8 are both approximately 60°F.
Which ONE of the following correctly describes the inventory conditions in the Unit 3 Reactor Head and Plenum regions?
A. The Head is partially full and the Plenum is completely full.
B. The Head is completely empty and the Plenum is partially full.
C. The Head is completely empty and the Plenum is completely full.
D. The Head is completely empty and the Plenum is completely empty.
Proposed Answer: B Explanation:
A. Plausible if thought that a high temperature difference indicated the presence of coolant and that HJTCs were numbered from bottom to top, however these are the opposite of what is correct.
B. Correct.
C. Plausible if thought that 6 HJTCs are in the head and two are in the plenum.
D. Plausible if thought that the bottom two HJTCs were located below the fuel alignment plate.
Technical Reference(s) SD-SO23-822, QSPDS System Description Attached w/ Revision # See Page 50 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments / Reference Proposed references to be provided during examination:
Learning Objective: 70383 - INTERPRET instrumentation and controls utilized in the Reactor Coolant System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 3 55.43 Page 51 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-822, QSPDS System Description Revision # 0 Page 52 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.1.44 Importance Rating 3.9 Conduct of Operations: Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation Proposed Question: Common 68 Given the following conditions:
- Unit 3 was performing a fuel shuffle in the Spent Fuel Pool when the Spent Fuel Handling Machine Operator noticed Spent Fuel Pool level lowering.
- The crew is performing actions of AOI SO23-13-23, Loss of Spent Fuel Pool Cooling.
- The source of the leak has NOT been determined.
- The Spent Fuel Pool Cooling Discharge Siphon Breaker is uncovered.
Which ONE of the following describes the impact of this condition, and the action(s) that is(are) required in accordance with AOI SO23-13-23, Loss of Spent Fuel Pool Cooling?
A. The SFP Cooling Pumps may become air-bound. Stop any running SFP Cooling Pump, and vent the casing prior to restarting.
B. The SFP Cooling Pumps may become air-bound. Stop the running SFP Cooling Pump, initiate makeup to the Spent Fuel Pool, start the standby SFP Cooling Pump.
C. Fuel Handling Building Airborne Radiation Levels will rise due to agitation of the bottom of the SFP. Initiate 1 Train of Fuel Handling Isolation Signal while making up to the SFP.
D. Fuel Handling Building Airborne Radiation Levels will rise due to the reduced shielding of SFP water. Initiate makeup using NSW and ensure the hose is submerged at least 3 ft below the surface of the water.
Proposed Answer: C Explanation:
A. Plausible as the siphon breaker will draw in some air if uncovered, however the air that is drawn in will be discharged at the bottom of the pool, not routed to the pump suction.
B. Plausible as the siphon breaker will draw in some air if uncovered, however the air that is drawn in Page 53 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 will be discharged at the bottom of the pool, not routed to the pump suction.
C. Correct.
D. Plausible as FHB rad levels will rise, however NSW is a last resort for SFP makeup. Additionally, the NSW hose is NOT to be submerged if used for refill.
Technical Reference(s) SO23-13-23, Loss of SFP Cooling Attached w/ Revision # See SO23-3-2.11.1, SFP Level Change and Comments / Reference Purification Crosstie Operations Proposed references to be provided during examination:
Learning Objective: 55431 - Per the Loss of Spent Fuel Pool Cooling procedure SO23-13-23, DESCRIBE the basis for each step, caution or note Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 54 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-23, Loss of SFP Cooling Revision # 12 Page 55 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-2.11.1, SFP Level Change and Revision # 21 Purification Crosstie Operations Page 56 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.2.42 Importance Rating 3.9 Equipment Control: Ability to recognize system parameters that are entry-level conditions for Technical Specifications Proposed Question: Common 69 A Unit shutdown is in progress, with Reactor power at 20%. In this condition, what is the minimum Tcold allowed by Technical Specifications?
A. 495°F B. 522°F C. 535°F D. 543°F Proposed Answer: B Explanation:
A. Plausible as this is the Tc value at which a CPC aux trip would be generated, however 522 is the minimum allowable Tc per tech specs.
B. Correct.
C. Plausible as 535 is the minimum when > 30% power, however not at 20% power.
D. Plausible as this is the bottom of the Power Operations Tc band, however it is not the tech spec minimum Tc.
Technical Reference(s) Technical Specifications Attached w/ Revision # See SO23-5-1.7, Power Operations Comments / Reference Proposed references to be provided during examination:
Learning Objective: 55265 - DESCRIBE the Technical Specification operability requirements and action statements associated with the Reactor Coolant System Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Page 57 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
Technical Specifications Comments /
Reference:
Technical Specifications Page 58 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.7, Power Operations Revision # 53 Page 59 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.2.14 Importance Rating 3.9 Equipment Control: Knowledge of the process for controlling equipment configuration or status Proposed Question: Common 70 A suction valve has been discovered closed, for no apparent reason, on Unit 2 Charging Pump, 2P-191, by the Radwaste Operator on his rounds.
Which ONE of the following is required to be performed as a result of this misalignment per SO123-0-A4, Configuration Control?
A. Partial alignment verifications on Charging pumps 2P-191 & 3P-191 only.
B. Full alignment verification on the Unit 2 Charging and Letdown system only.
C. Full alignment verifications on the Units 2 and 3 Charging and Letdown system.
D. Partial alignment verifications on Charging pumps 2P-190, 2P-191, 2P-192 and 3P-191.
Proposed Answer: D Explanation:
A. Plausible as a partial alignment is required on 3P-191, however 2P-190 and 2P-192 also require partial alignments.
B. Plausible if thought that a full system alignment would be required, however only the four listed pumps would require a partial alignment.
C. Plausible as redundant component on the opposite unit requires an alignment check, however the entire system is not required to be aligned.
D. Correct.
Page 60 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-0-A4, Configuration Control Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56337 - When discovered, DETERMINE the action required for a system misalignment, per SO23-0-A4 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-0-A4, Configuration Control Revision # 19 Page 61 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.2.41 Importance Rating 3.5 Equipment Control: Ability to obtain and interpret station electrical and mechanical drawings Proposed Question: Common 71 An overload condition has occurred on Reserve Auxiliary Transformer 2XR1.
Per Drawing 30103, which ONE of the following lists an automatic function initiated by operation of Overcurrent Relay, 451-1?
Relay 451-1 will trip Reserve Auxiliary Transformer ___(1)___ circuit breakers and initiate Digital Fault Recorder Channel ___(2)___.
A. 1. 480V
- 2. 22 B. 1. 480V
- 2. 23 C. 1. 4.16kV
- 2. 22 D. 1. 4.16kV
- 2. 23 Proposed Answer: D Explanation:
A. Plausible if the key is misread or the applicant lacks sufficient attention to detail while interpreting the drawing.
B. Plausible if the key is misread or the applicant lacks sufficient attention to detail while interpreting the drawing.
C. Plausible if the key is misread or the applicant lacks sufficient attention to detail while interpreting the drawing.
D. Correct, per Drawing 30103.
Technical Reference(s) Drawing 30103 Attached w/ Revision # See Comments / Reference Page 62 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: Drawing 30103 Learning Objective: DESCRIBE the operation of the following 220kV switchyard protective devices, including name, function, location and action upon actuation: Overcurrent relays Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Page 63 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Drawing 30103 Revision # 12 Page 64 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Drawing 30103 Revision # 12 Page 65 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.3.11 Importance Rating 3.8 Radiation Control: Ability to control radiation releases Proposed Question: Common 72 Given the following conditions:
- Unit 2 was operating at 100% power when a Steam Generator tube rupture occurred on S/G E-089.
- Unit 2 Reactor was tripped and SO23-12-1, Standard Post Trip Actions, has been completed.
- SO23-12-4, Steam Generator Tube Rupture, is in progress.
- S/G E-089 has been isolated.
- S/G E-089 level is 75% NR and slowly rising.
Which ONE of the following describes the preferred method of continuing the cooldown to MODE 5?
A. Dump steam to the condenser from S/G E-088 ONLY in order to minimize radiological releases.
B. Dump steam through S/G E-088 ADV ONLY in order to minimize contamination of the condensate and feedwater systems.
C. Dump steam to the condenser from S/G E-088 and E-089 to minimize radiological releases and prevent overfilling S/G E-089.
D. Dump steam through S/G E-088 and E-089 ADVs to minimize contamination of the condensate and feedwater systems and prevent overfilling S/G E-089.
Proposed Answer: A Explanation:
A. Correct.
B. Plausible as only SG E-088 is the only SG to be used for the cooldown to MODE 5 and contaminating the secondary is undesired, however it is preferable when compared to releasing via the ADV.
Page 66 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Plausible as both SGs are used for the initial cooldown, however once the faulted SG is isolated, the cooldown to MODE 5 is done with only the unaffected SG.
D. Plausible as both SGs are used for the initial cooldown, however once the faulted SG is isolated, the cooldown to MODE 5 is done with only the unaffected SG.
Technical Reference(s) OSM-9 Standard EOI Good Practices and Attached w/ Revision # See Strategies Comments / Reference SO23-12-4, Steam Generator Tube Rupture Proposed references to be provided during examination:
Learning Objective: 52744 - STATE the major recovery actions in response to an SGTR.
Question Source: Bank #
Modified Bank # x (Note changes or attach parent)
New Question History: Last NRC Exam 2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Page 67 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
VISION QUESTION # 126738 126738 Unit 2 was operating at 100% power when a tube rupture occurred on E089.
Which ONE (1) of the following describes the preferred method of cooling down the RCS for SG maintenance?
A. Dump steam to the condenser using the E088 SG to minimize radiological releases B. Dump steam through the E088 SG's ADVs to minimize contamination of the secondary system for ALARA reasons C. Dump steam through the E089 SG's ADVs to reduce the contamination in the condensate D. Dump steam to the condenser using the E089 SG to minimize radiological Releases Answer: A Page 68 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
OSM-9 Standard EOI Good Practices and Revision # 12 Strategies Page 69 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-4, Steam Generator Tube Rupture Revision # 23 Page 70 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.3.13 Importance Rating 3.4 Radiation Control: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Proposed Question: Common 73 An operator is performing a valve lineup which requires entry into an area with a general area radiation level of 1250 mr/hr and a general removable contamination level of 50,000 dpm/100cm2 beta/gamma.
Based on the listed conditions, how will the area be posted?
A. A High Radiation and a Contaminated Area.
B. A High Radiation and a High Contamination Area.
C. A Locked High Radiation Area and a Contaminated Area.
D. A Locked High Radiation Area and a High Contamination Area.
Proposed Answer: C Explanation:
A. Plausible as the area is a contaminated area, however it is a locked high radiation area.
B. Plausible if thought that the listed conditions would be a high rad and high contaminated area, however it is a locked high rad and contaminated area.
C. Correct.
D. Plausible as locked high radiation is correct, however it is not a high contaminated area.
Technical Reference(s) SO123-VII-20.11.1 Radiological Posting Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 54709 - STATE the 10CFR20 and San Onofre administrative controls for exposure to radiation and contamination Page 71 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #
Modified Bank # x (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Comments /
Reference:
SO123-VII-20.11.1 Radiological Posting Revision # 14 Comments /
Reference:
Original Question A Prejob Brief is in progress with a review of HP survey maps for a job area.
An operator notes one accessible area that may be entered has a dose rate of 950 mrem/hour and contamination levels of 31,000 dpm/100 cm2 beta/gamma.
This area should be posted as a:
A. Contamination Area and High Radiation Area B. Contamination Area and Radiation Area C. High Contamination Area and Radiation Area D. High Contamination Area and High Radiation Area Answer: A Page 72 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.4.3 Importance Rating 3.7 Emergency Procedures/Plan: Ability to identify post-accident instrumentation Proposed Question: Common 74 How are lumigraphs in the Control Room marked to indicate that they are Post Accident Monitoring Instrumentation?
The lumigraph label has A. a red stripe.
B. a yellow stripe.
C. PAMI inscribed on it.
D. QSPDS inscribed on it.
Proposed Answer: C Explanation:
A. Plausible as a red stripe on the label means it is a Train A power lumigraph, indicating it is fire hardened, however not all Train A lumigraphs are PAMI and not all PAMI are Train A instruments.
B. Plausible if thought that Train A lumigraphs are fire hardened and therefore Train B lumigraphs are PAMI instruments.
C. Correct.
D. Plausible as QSPDS is a qualified post-accident monitoring system, however Control Room lumigraphs are not labeled as QSPDS.
Technical Reference(s) SO23-V-5, Severe Accident Management Attached w/ Revision # See Guidelines Comments / Reference Proposed references to be provided during examination:
Learning Objective: 55029 - DESCRIBE the configuration and operational characteristics of Accident Monitoring System components.
Question Source: Bank #
Page 73 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /
Reference:
SO23-V-5, Severe Accident Management Revision # 6 Guidelines Page 74 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.4.49 Importance Rating 4.6 Emergency Procedures/Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls Proposed Question: Common 75 Given the following conditions:
- Both Units 2 & 3 reactors have been tripped.
- The Control Room is being evacuated due to dense smoke.
Which ONE of the following correctly identifies the order in which the "IMMEDIATE ACTIONS" are to be completed, per SO23-13-2, Shutdown From Outside the Control Room?
A. 1) Manually initiate MSIS
- 2) Stop all Charging Pumps and remove from AUTO
- 2) Stop all Charging Pumps and ensure in AUTO
- 2) Stop all Charging Pumps and remove from AUTO
- 2) Stop all Charging Pumps and ensure in AUTO
- 3) Manually initiate MSIS Proposed Answer: A Explanation:
A. Correct.
B. Plausible because the order is correct, however Charging Pumps are to be removed from AUTO.
Ensuring Charging Pumps in AUTO is plausible if thought that it would be desired to have pumps start and stop to maintain Pressurizer level near the program band of 38%.
Page 75 of 76 Rev b
ES-401 SONGS NRC 2012 RO Written Exam Worksheet Form ES-401-5 C. Plausible if thought that all Primary Plant actions would be taken before secondary plant actions.
D. Plausible if thought that all Primary Plant actions would be taken before secondary plant actions, also the Charging Pumps should be removed from AUTO.
Technical Reference(s) SO23-13-2, Shutdown From Outside the Attached w/ Revision # See Control Room Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56675 - As the RO, PERFORM 21/31 actions during a Shutdown from Outside the Control Room, per SO23-13-2 Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2003 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /
Reference:
SO23-13-2, Shutdown From Outside the Control Revision # 19 Room Page 76 of 76 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 007 EA2.02 Importance Rating 4.6 Reactor Trip/Stabilization/Recovery: Ability to determine or interpret the following as they apply to a reactor trip: Proper actions to be taken if the automatic safety functions have not taken place Proposed Question: SRO 76 Given the following conditions:
- Unit 2 has tripped from 100% Reactor power.
- SO23-12-2, Reactor Trip Recovery, is in progress.
- SO23-12-1, Standard Post Trip Actions, steps 12-17 have been completed.
- The cycling relays for HV-4713, P-141 Discharge to E-089 Flow Control Valve, and HV-4731, AFW to E-089 Containment Isolation Valve, have failed to re-energize.
- S/G E-088 level is 55% NR and stable.
- S/G E-089 level is 85% NR and rising.
Per the listed conditions, which ONE of the following is the FIRST mitigating action the CRS should direct?
A. Isolate S/G E-089 and reset EFAS per SO23-3-2.22, ESFAS Operation, to restore S/G E-089 level.
B. Stop ALL feedwater to S/G E-089 by overriding and stopping AFW Pump P-141 per SO23-12-2, Reactor Trip Recovery.
C. Stop ALL feedwater to S/G E-089 by overriding and closing HV-4713 and HV-4731 per SO23-3-2.22 ESFAS Operation.
D. Isolate S/G E-089 with the exception of S/G Blowdown Isolation Valve HV-4053 and S/G Water Sample Isolation Valve HV-4057 to restore S/G E-089 level per SO23-12-2, Reactor Trip Recovery.
Proposed Answer: B Explanation:
A. Plausible as this action is directed in SO23-12-2, however isolating the S/G is only performed if level is 100%.
B. Correct.
C. Plausible as closing these valves would stop the over feeding event, however AFW valves cannot be overridden and closed, they can only be overridden open.
Page 1 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 D. Plausible as this action is directed in SO23-12-2, however isolating the S/G is only performed if level is 100%.
Technical Reference(s) SO23-12-2, Reactor Trip Recovery Attached w/ Revision # See SD-SO23-720 Engineered Safety Features Comments / Reference Actuation System Proposed references to be provided during examination:
Learning Objective: 54780 - As the SRO, ANALYZE plant conditions to select the appropriate Emergency Operating Instruction and direct and coordinate the activities of shift personnel to recover from a Reactor Trip Event, per SO23-12-2 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Comments /
Reference:
SO23-12-2, Reactor Trip Recovery Revision # 20 Page 2 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-2, Reactor Trip Recovery Revision # 20 Comments /
Reference:
SD-SO23-720 Engineered Safety Features Revision # 10 Actuation System Page 3 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 008 G 2.4.21 Importance Rating 4.6 Pressurizer Vapor Space Accident: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
Proposed Question: SRO 77 Given the following conditions:
- Unit 2 has tripped from 100% Reactor power.
- RCS temperature is 537°F and slowly lowering.
- Pressurizer pressure is 1050 psia and slowly lowering.
- Pressurizer level is 75% and slowly rising.
- Containment pressure is 1.5 psig and slowly rising.
- Average Containment temperature is 95°F and slowly rising.
- Both S/G levels are 22% NR and slowly rising.
- Both S/G pressures are 900 psia and slowly rising.
- Containment Radiation Monitors are trending to alarm.
- Secondary Radiation Monitors are NOT alarming or trending to alarm.
Based on the listed conditions,
- 1. What is the highest failed safety function criteria per SO23-12-1, Standard Post Trip Actions?
- 2. Which EOI will the crew transition to in order to mitigate the event?
A. 1. RCS Pressure Control
- 2. SO23-12-9, Functional Recovery B. 1. RCS Inventory Control
- 2. SO23-12-9, Functional Recovery C. 1. RCS Pressure Control
- 2. SO23-12-3, Loss of Coolant Accident D. 1. RCS Inventory Control
- 2. SO23-12-3, Loss of Coolant Accident Page 4 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: D Explanation:
A. Plausible because RCS pressure control is failed however it is not the highest failed safety function.
B. Plausible because RCS inventory control is the highest failed safety function, and multiple failed safety functions could indicate Functional Recovery is the optimal EOI, however LOCA is the lone event making LOCA the correct optimal EOI.
C. Plausible because RCS pressure control is failed and LOCA is the correct optimal EOI, however pressure control is not the highest failed safety function.
D. Correct.
Technical Reference(s) SO23-12-1, Standard Post Trip Actions. Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 57480 - ANALYZE plant conditions to select the appropriate Emergency Operating Instruction and direct and coordinate the activities of shift Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 5 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-1, Standard Post Trip Actions Revision # 26 Comments /
Reference:
SO23-12-1, Standard Post Trip Actions Revision # 26 Page 6 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-1, Standard Post Trip Actions Revision # 26 Page 7 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056 G 2.4.13 Importance Rating 4.6 Loss of Offsite Power: Knowledge of crew roles and responsibilities during EOP usage Proposed Question: SRO 78 Given the following conditions:
- Units 2 and 3 have tripped due to a Loss of Offsite power.
- Both Unit 2 Emergency Diesel Generators have failed to start due to a common mode failure and are NOT expected to be available for several hours.
- Both Unit 3 Emergency Diesel Generators have started and loaded onto their respective buses.
- The GOC reports that a line to the switchyard will NOT be available for approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- The Unit 2 CRS has determined SO23-12-11, Attachment 24, Supplying 1E 4kV Bus with Opposite Unit Diesel, to be the proper success path.
Per SO23-12-11, whose authorization is required to perform Attachment 24, Supplying 1E 4kV Bus with Opposite Unit Diesel?
A. Unit 2 CRS.
B. Unit 3 CRS.
C. Shift Manager.
D. Operations Manager.
Proposed Answer: C Explanation:
Page 8 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 A. Plausible that the Unit 2 CRS could direct this action as it is listed in the EOI, however SM approval is required per SO23-12-11.
B. Plausible that the Unit 3 CRS would have to authorized using the Unit 3 EDGs, however a 50.54 declaration is required and 12-11 states that the SM must authorize it.
C. Correct.
D. Plausible if thought that the Operations Manager would have to authorize intentionally deviating from Technical Specifications, however only SM authorization is required.
Technical Reference(s) SO23-12-11, Attachment 24, Supplying 1E Attached w/ Revision # See 4kV Bus with Opposite Unit Diesel Comments / Reference Proposed references to be provided during examination:
Learning Objective: 54902 - DISCUSS the Control Room Supervisor's responsibility and techniques for coordinating shift activities during emergency conditions including:
Consulting/notifying plant management Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1 Page 9 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-11, Attachment 24 Revision # 14 Page 10 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038 EA2.15 Importance Rating 4.4 Steam Generator Tube Rupture: Ability to determine and interpret the following as they aply to a SGTR: Pressure at which to maintain RCS during S/G cooldown.
Proposed Question: SRO 79 Given the following conditions:
- Unit 3 Reactor was tripped due to a Loss of Offsite power.
- Following the Reactor trip, a Steam Generator Tube Rupture occurred on S/G E-089.
- S/G E-089 has been isolated.
- RCS pressure is 1400 psia and stable.
- S/G E-089 pressure is 950 psia and stable.
- Core Exit Temperature is 525°F and stable.
- S/G E-089 level is 85% NR and rising.
How will the CRS prioritize RCS pressure control in this condition and what is the reason for this strategy?
A. Maintaining RCS subcooling > 20°F subcooled is a higher priority than lowering RCS pressure to < 50 psia above S/G E-089 pressure due to the potential for voiding in the head when < 20°F subcooled in the RCS.
B. Lowering RCS pressure to < 50 psia above S/G E-089 pressure is a higher priority than maintaining RCS subcooling > 20° subcooled due to the potential for Main Steam Safety Valves lifting if S/G E-089 level reaches 100% NR.
C. Lowering RCS pressure to < 50 psia above S/G E-089 pressure is a higher priority than maintaining RCS subcooling > 20° subcooled since the boron added from the HPSI and Charging pumps will maintain Shutdown Margin in the event of an inadvertent dilution.
D. Maintaining RCS subcooling > 20°F subcooled is a higher priority than lowering RCS pressure to < 50 psia above S/G E-089 pressure due to the potential for an inadvertent dilution challenging Shutdown Margin when < 50 psia differential pressure between the RCS and S/G E-089.
Page 11 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: B Explanation:
A. Plausible as maintaining subcooling takes priority over lowering RCS pressure when pressure is <
1000 psia, however at this time, RCS pressure is 1400 psia.
B. Correct.
C. Plausible as this is the correct priority, however the basis for this action is incorrect. The correct basis is that at > 1000 psia, the SG safety valves could lift if SG level reaches 100%.
D. Plausible as maintaining subcooling takes priority over lowering RCS pressure when pressure is <
1000 psia, however at this time, RCS pressure is 1400 psia.
Technical Reference(s) SO23-14-4, SGTR Bases and Deviation Attached w/ Revision # See Justification Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53925 - As the SRO, DIRECT response to and recovery from a steam generator tube rupture, per SO23-12-4 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 12 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-14-4, SGTR Basis and Deviations Revision # 8 Justifications Page 13 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 062 AA2.02 Importance Rating 3.6 Loss of Nuclear Service Water: Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The cause of possible SWS loss Proposed Question: SRO 80 Given the following conditions:
- Train A CCW/SWC is in service.
- 64A55 SWC TRAIN A FLOW TROUBLE, is in alarm.
- Train A SWC Pump amps are lower than normal.
Per the listed conditions:
- 1. What is the reason for these alarms?
- 2. In addition to placing Train B CCW/SWC in service, what actions will the crew take to mitigate the event?
A. 1. The Train A CCW HX is fouled.
- 2. Reverse flow through the HX per SO23-2-8, Saltwater Cooling System Operation.
B. 1. The SWC discharge line is blocked.
- 2. Reverse flow through the HX per SO23-2-8, Saltwater Cooling System Operation.
C. 1. The Train A CCW HX is fouled.
- 2. Transfer Train A SWC loop to the Emergency Discharge Line per SO23-2-8.1, Saltwater Cooling System Removal/Return To Service Evolutions (Online Or Outage).
D. 1. The SWC discharge line is blocked.
- 2. Transfer Train A SWC loop to the Emergency Discharge Line per SO23-2-8.1, Saltwater Cooling System Removal/Return To Service Evolutions (Online Or Outage).
Proposed Answer: A Page 14 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:
A. Correct.
B. Plausible as this is the correct action, however if discharge line blockage was the cause of the alarms, CCW HX D/P would be low.
C. Plausible as HX fouling is the event in progress and discharging to the emergency discharge line would mitigate the event if the fouling was downstream of the HX outlet, however a high DP alarm would not be in if the fouling was downstream of the HX outlet.
D. Plausible as this would mitigate the event if discharge line blockage was the event in progress, however HX fouling is the reason for the alarms.
Technical Reference(s) SO23-13-7, Loss of CCW/SWC Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 60307 - ANALYZE normal and abnormal operations of the Salt Water Cooling System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Page 15 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-7, Loss of CCW/SWC Revision # 18 Page 16 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 077 AA2.05 Importance Rating 3.8 Generator Voltage and Electric Grid Disturbances: Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Operational status of offsite circuit Proposed Question: SRO 81 Given the following conditions:
- An electrical grid disturbance has occurred resulting in a partial loss of grid generation.
- Grid Voltage = 220 kV
- Grid Frequency = 59.5 Hz What is the operational status of offsite power sources?
Offsite power sources are A. OPERABLE.
B. INOPERABLE due to low system voltage ONLY.
C. INOPERABLE due to low system frequency ONLY.
D. INOPERABLE due to low system voltage AND low system frequency.
Proposed Answer: C Explanation:
A. Plausible as offsite power sources are operable down to 218kV, however offsite power is inoperable when less than 59.7 Hz.
B. Plausible because when system voltage is < 226 kV, action is taken to attempt to maintain/restore main generator parameters within operating bands, however offsite power is not inoperable until <
218 kV. Additionally, plausible if thought that frequency does not inop offsite power until 57 hZ since at that frequency the Reactor must be tripped.
C. Correct.
D. Plausible because when system voltage is < 226 kV, action is taken to attempt to maintain/restore main generator parameters within operating bands, however offsite power is not inoperable until <
218 kV.
Page 17 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-4, Operation During Major System Attached w/ Revision # See Disturbances Comments / Reference Proposed references to be provided during examination:
Learning Objective 55216 - EVALUATE plant status against Technical Specification requirements
- for a major system disturbance event and determine the required action.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 2 Comments /
Reference:
SO23-13-4, Operation During Major System Revision # 21 Disturbances Page 18 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Page 19 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 003 G 2.4.4 Importance Rating 4.7 Dropped Control Rod: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures Proposed Question: SRO 82 Unit 3 Initial Conditions:
- Time = 0700
- Reactor Power = 99.8%
- RCS Tc = 549°F
- Turbine MWe = 1210 MWe Unit 3 Current Conditions:
- Time = 0705
- Reactor Power = 97.8%
- RCS Tc = 547°F
- Turbine MWe = 1185 MWe Which ONE of the following procedures will be used to mitigate the event?
A. SO23-12-1, Standard Post Trip Actions.
B. SO23-13-10, Loss of Condenser Vacuum.
C. SO23-13-4, Operation During Major System Disturbances.
D. SO23-13-13, Misaligned or Immovable Control Element Assembly.
Proposed Answer: D Explanation:
A. Plausible as Turbine load and Tc would lower if a steam leak was the cause of the indications and a Reactor trip would be required, however Reactor power rise during a steam leak.
Page 20 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 B. Plausible as Reactor power and Turbine load would lower during a loss of vacuum, however Tc would rise.
C. Plausible as Reactor power and Turbine load would lower during a grid frequency rise, and lowering Generator load is an entry condition into 13-4, however Tc would rise if grid frequency was rising.
D. Correct. None of the provided information are listed as entry conditions for AOI 13-13, however the listed conditions are all results of the dropped CEA, thus the applicants should be able to determine the correct event and mitigating procedure.
Technical Reference(s) SO23-13-4, Operation During Major System Attached w/ Revision # See Disturbances Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53937 - DIRECT operator response to a misaligned CEA Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 21 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-4, Operation During Major System Revision # 21 Disturbances Page 22 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-13, Misaligned CEA Revision # 15 Page 23 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 060 AA2.04 Importance Rating 3.4 Accidental Gaseous Radwaste Release: Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste Release: The effects on the power plant of isolating a given radioactive-gas leak Proposed Question: SRO 83 Given the following conditions:
- A Waste Gas Decay Tank release was in progress.
- A leak has occurred on 2/3RT-7808, Plant Vent Stack Radiation Monitor, sample flow inlet line.
- The Waste Gas Decay Tank release was terminated and the PEO has isolated the leak by closing the 2/3RT-7808 sample and discharge line isolation valves.
Per the Offsite Dose Calculation Manual, with 2/3RT-7808 isolated, what is required to maintain the Plant Vent Stack in service?
ENSURE A. either 2RT-7865 or 3RT-7865 is OPERABLE and aligned to the Plant Vent Stack AND at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup.
B. either 2RT-7865 or 3RT-7865 is OPERABLE and aligned to the Plant Vent Stack OR grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. both 2RT-7865 and 3RT-7865 are OPERABLE and aligned to the Plant Vent Stack AND at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup.
D. both 2RT-7865 and 3RT-7865 are OPERABLE and aligned to the Plant Vent Stack OR grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Page 24 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: D Explanation:
A.
Technical Reference(s) Offsite Dose Calculation Manual Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 55432 - DESCRIBE the use of the Offsite Dose Calculation Manual Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 4 Comments /
Reference:
Offsite Dose Calculation Manual Revision # 6 Page 25 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Offsite Dose Calculation Manual Revision # 6 Page 26 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # CE/E09 G 2.4.6 Importance Rating 4.7 Functional Recovery: Knowledge of EOP mitigation strategies Proposed Question: SRO 84 Given the following conditions:
- Unit 3 Reactor has tripped.
- 1E 4kV Bus 3A06 has an overcurrent lockout.
- Pressurizer level indicates 0%.
- RCS pressure is 500 psig and lowering.
- Containment Pressure is 16 psig and rising.
- Containment radiation levels are rising.
- Train A Containment Spray Pump P-012 has tripped on overcurrent.
- The CRS is diagnosing the event in progress.
Which ONE of the following describes the event diagnosis and action required upon transition from SO23 12-1?
Transition from SO23-12-1, Standard Post Trip Actions, to A. SO23-12-9, Functional Recovery, due to the RCS Inventory Control and RCS Pressure Control Safety Functions not being met.
B. SO23-12-9, Functional Recovery, due to the Containment Isolation and Containment Temperature and Pressure Control Safety Functions not being met.
C. SO23-12-3, Loss of Coolant Accident, and transition to SO23-12-9, Functional Recovery, when the STA determines the Containment Isolation SFSC criteria is not being met.
D. SO23-12-3, Loss of Coolant Accident, and transition to SO23-12-9, Functional Recovery, when the STA determines the Containment Temperature and Pressure Control SFSC criteria is not being met.
Proposed Answer: D Explanation:
Page 27 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 A. Plausible if thought that the failure of two safety functions would direct transition into 12-9, Functional Recovery, however this is not necessarily the case. Two different events have to be diagnosed and in this case, LOCA is the only event diagnosed. Additionally, it could be thought that Loss of Forced Circulation would constitute a second event, and all RCPs would be secured based on the loss of sufficient NPSH, however a LOFC is not credited as a second event which would direct transition to the Functional Recovery.
B. Plausible if thought that the failure of two safety functions would direct transition into 12-9, Functional Recovery, however this is not necessarily the case. Two different events have to be diagnosed and in this case, LOCA is the only event diagnosed. Additionally, it could be thought that Loss of Forced Circulation would constitute a second event, and all RCPs would be secured based on the loss of sufficient NPSH, however a LOFC is not credited as a second event which would direct transition to the Functional Recovery.
C. Plausible if thought that Containment conditions would fail the Containment Isolation Safety Function and require entry into the Functional Recovery, however the Containment Isolation Safety Function is satisfied as long as CIAS has actuated, regardless of Containment conditions.
D. Correct.
Technical Reference(s) SO23-12-1, Standard Post Trip Actions Attached w/ Revision # See SO23-12-10, Safety Function Status Comments / Reference Checks Proposed references to be provided during examination:
Learning Objective: 53976 - As the SRO, EVALUATE safety function status check for functional recovery accident mitigation Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 28 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-1, Standard Post Trip Actions Revision # 26 Page 29 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10 Safety Function Status Checks Revision # 5 Since none of the conditions are satisfied, the RNO directs entering the Functional Recovery.
Page 30 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Page 31 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Page 32 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # CE/A16 AA2.1 Importance Rating 3.5 Excess RCS Leakage: Ability to determine and interpret the following as they apply to the (Excess RCS Leakage): Facility conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Question: SRO 85 Given the following conditions:
- Unit 3 is operating at 100% power.
- Three Charging Pumps are operating.
- Letdown flow is indicating 15 gpm.
- VCT level is 41% and lowering at 3% per minute.
- Pressurizer level is 49% and lowering.
- Containment humidity is rising.
- RCS T-cold is 541°F and stable.
Which ONE of the following describes the event in progress and the action required?
A. Charging line leak downstream of the Regenerative Heat Exchanger. Enter SO23 14, Reactor Coolant Leak, and isolate Letdown.
B. Charging line leak downstream of the Regenerative Heat Exchanger. Trip the Reactor and enter SO23-12-1, Standard Post Trip Actions.
C. Letdown line leak between the Regenerative Heat Exchanger and Containment. Enter SO23-13-14, Reactor Coolant Leak, and isolate Letdown.
D. Letdown line leak between the Regenerative Heat Exchanger and Containment. Trip the Reactor and enter SO23-12-1, Standard Post Trip Actions.
Proposed Answer: C Explanation:
A. Plausible because the procedure and action is correct, however Letdown flow would be 28 gpm if the leak was in the Charging header.
B. Plausible because Pressurizer level is lowering and the leak is inside Containment, however Letdown flow would be 28 gpm if the leak was in the Charging header.
Page 33 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 C. Correct.
D. Plausible because the leak location is correct and the leakage exceeds Charging Pump capacity, however Letdown is isolated in an attempt to isolate the leak prior to tripping the Reactor per SO23-13-14.
Technical Reference(s) SO23-13-14, Reactor Coolant Leak Attached w/ Revision # See SD-SO23-390, CVCS System Description Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53932 - DIRECT response to an Reactor Coolant Leak Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 34 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-14, Reactor Coolant Leak Revision # 18 Comments /
Reference:
SO23-13-14, Reactor Coolant Leak Revision # 18 Page 35 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 A2.04 Importance Rating 2.9 Residual Heat Removal: Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction Proposed Question: SRO 86 Given the following conditions:
- Unit 2 is in MODE 4.
- Core Exit Temperature is 240°F and lowering slowly.
- Shutdown Cooling is in service using the Train B Shutdown Cooling HX, Train B LPSI Pump P-016, and SDC HX Bypass Normal Flow Valve HV-8160.
Subsequently:
- Shutdown Cooling Flow lowers to 2350 gpm by CFMS.
- 1. Which ONE of the following describes the impact of the valve closure?
- 2. What mitigating action will be directed by SO23-13-15, Loss of Shutdown Cooling?
A. 1. RCS cooldown rate will rise.
- 2. Transfer to Train A SDC operation per SO23-3-2.6, Shutdown Cooling Operations.
B. 1. RCS cooldown rate will lower.
- 2. Transfer to Train A SDC operation per SO23-3-2.6, Shutdown Cooling Operations.
C. 1. RCS cooldown rate will rise.
- 2. Place HV-0396, SDC HX Bypass Standby Flow Valve, in service per SO23-3-2.6, Shutdown Cooling Operations.
D. 1. RCS cooldown rate will lower.
- 2. Place HV-0396, SDC HX Bypass Standby Flow Valve, in service per SO23-3-2.6, Shutdown Cooling Operations.
Proposed Answer: C Explanation:
Page 36 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 A. Plausible as the cooldown rate will rise since all shutdown cooling flow is going through the HX, however transferring to Train B SDC will not mitigate the event since both trains of SDC use the same HX bypass flowpath.
B. Plausible if thought that the cooldown rate will lower due to a reduction in SDC flow, however most of the flow will continue and all of the flow will be getting cooled via the HX. Also plausible if thought that the two trains of SDC are independent of each other and that the other should be placed in service, however transferring to the alternate bypass valve, HV-0396, is the correct action.
C. Correct.
D. Plausible as placing HV-0396 is the correct action, however the cooldown rate will rise.
Technical Reference(s) SO23-13-15, Loss of Shutdown Cooling Attached w/ Revision # See SD-SO23-740, Shutdown Cooling System Comments / Reference Description SO23-3-2.6, Shutdown Cooling Operations Proposed references to be provided during examination:
Learning Objective: 53933 - DIRECT operator response to a Loss of Shutdown Cooling Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 37 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-15, Loss of Shutdown Cooling Revision # 25 Page 38 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-15, Loss of Shutdown Cooling Revision # 25 Page 39 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-3-2.6, Shutdown Cooling Operations Revision # 34 Page 40 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-740, Shutdown Cooling System Revision # 23 Description Initially, HV-8160 and HV-8161 are open with a portion of the SDC flow going through SDCHX E-003 (normally 10-20%). However when HV-8160 closes, all SDC flow is through the HX causing cooldown rate to rise. Additionally, opening HV-0396 is the quickest and simplest method to restore SDC as the remainder of the equipment is unaffected.
Page 41 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.06 Importance Rating 4.0 Engineering Safety Features Actuation: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent ESFAS actuation Proposed Question: SRO 87 Given the following conditions:
- Unit 3 is operating at 2% Reactor power during an MOC startup.
- SBCS is in service in LOCAL/AUTO with the setpoint set to 1000 psia.
- RCS Tc is 545°F and stable.
An inadvertent MSIS has just occurred.
- 1. Which ONE of the following describes automatic plant response?
- 2. What actions are required to mitigate the event?
A. 1. Main Steam Safety Valves will open to stabilize Reactor power and RCS temperature at approximately 556°F.
- 2. Initiate EFAS to reestablish auxiliary feedwater per SO23-2-4, Auxiliary Feedwater Operation.
B. 1. Main Steam Safety Valves will open to stabilize Reactor power and RCS temperature at approximately 556°F.
- 2. Override AFW valves using the override pushbuttons to reestablish auxiliary feedwater per SO23-2-4, Auxiliary Feedwater Operation.
C. 1. RCS temperature will rise causing Reactor power to lower to below the Point of Adding Heat.
- 2. When Reactor power lowers to below the point of adding heat, manually trip the Reactor and initiate EFAS to reestablish auxiliary feedwater per SO23-12-1, Standard Post Trip Actions.
D. 1. RCS temperature will rise causing Reactor power to lower to below the Point of Adding Heat.
- 2. When Reactor power lowers to below the point of adding heat, manually trip the Reactor and override AFW valves using the override pushbuttons to reestablish Page 42 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 auxiliary feedwater per SO23-12-1, Standard Post Trip Actions.
Proposed Answer: C Explanation:
A. Plausible as the MSSVs would open and maintain RCS temp at 556°F, however power will turn and drop below the POAH prior to temp getting that high, thus requiring a Reactor trip.
B. Plausible as the MSSVs would open and maintain RCS temp at 556°F, however power will turn and drop below the POAH prior to temp getting that high, thus requiring a Reactor trip.
C. Correct.
D. Plausible as power will lower below the POAH and require a Reactor trip, however AFW valves cannot be overridden to open when an MSIS is present unless an EFAS is also present.
Technical Reference(s) SO23-05-01.03.01 Plant Startup From Hot Attached w/ Revision # See Standby to Minimum Load Comments / Reference SD-SO23-720 Engineered Safety Features Actuation System SD-SO23-160 Main and Reheat Steam System Proposed references to be provided during examination:
Learning Objective: 52781 - STATE under what conditions an ESFAS trip function may be operationally bypassed or overriden Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 43 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-05-01.03.01 Plant Startup From Hot Revision # 34 Standby to Minimum Load Comments /
Reference:
SD-SO23-720 Engineered Safety Features Revision # 10 Actuation System The AFW valves cannot be overridden to feed unless they have an EFAS signal actuated, however in this case, no EFAS signal is present.
Page 44 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SD-SO23-160 Main and Reheat Steam System Revision # 24 1100 psia is the setpoint of the 1st MSSV which corresponds to 556°F Page 45 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 G 2.2.25 Importance Rating 4.2 AC Electrical Distribution: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits Proposed Question: SRO 88 Technical Specifications bases states that to maintain an EDG OPERABLE, at least one of the associated EDG Air Start System Air Receiver pressures must be maintained at a minimum of ____(1)____ psia in order to be capable of starting the EDG a minimum of
____(2)____ time(s).
A. 1. 136
- 2. 1 B. 1. 136
- 2. 5 C. 1. 175
- 2. 1 D. 1. 175
- 2. 5 Proposed Answer: A Explanation:
A. Correct.
B. Plausible as 136 psia is the minimum pressure, however the EDG must only be capable of one start.
C. Plausible as 1 start is the correct number of starts, however 175 psia is not the minimum required pressure.
D. Plausible as 175 psia is the minimum pressure to be capable of 5 starts, however this is the pressure below which the action statement for air receivers is entered.
Technical Reference(s) Technical Specification LCO 3.8.3 and LCO Attached w/ Revision # See 3.8.3 Bases Comments / Reference Page 46 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination:
Learning Objective: 55301 - APPLY all Administrative Requirements, Technical Specifications and Action Statements associated with the Emergency Diesel Generators (EDGs)
System.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 2 Comments /
Reference:
Tech Spec Bases 3.8.3 Revision # 127 Page 47 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
Tech Spec LCO 3.8.3 Revision # 127 Page 48 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063 A2.01 Importance Rating 3.2 DC Electrical Distribution: Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Grounds Proposed Question: SRO 89 Given the following conditions:
- 125 VDC Buses D1 and D3 were cross-tied when a subsequent ground caused a loss of both DC Buses.
- 15 seconds later, the Reactor tripped due to a Loss of Offsite Power
- Following the trip, an Excess Steam Demand Event occurred on S/G E-088 inside Containment.
- RCS temperature is 480°F and lowering
- Pressurizer pressure is 1675 psia and lowering.
- Containment pressure is 21 psig.
- S/G E-088 pressure is 670 psia and lowering.
- S/G E-089 pressure is 875 psia and rising.
Which of the following Critical Safety Functions will require local operator action to satisfy the Safety Function Status Check?
A. Vital Auxiliaries.
B. Reactor Coolant System Heat Removal.
C. Reactor Coolant System Pressure Control.
D. Containment Temperature and Pressure Control.
Proposed Answer: B Explanation:
A. Incorrect. Plausible if thought that the loss of two DC Buses and one AC bus (due to the Train A EDG not having control power to close the output breaker remotely) would result in the safety function not being met, however, this safety function is fully met as all Train B equipment would be available.
B. Correct. Steam Generator E-089 is the only available Steam Generator for Heat Removal and the loss of Bus D3 removes power to run P-140 and loss of Bus D1 removes control power for starting Page 49 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 P-141. The only way to provide feedwater to an OPERABLE Steam Generator is by local actions, manually locally closing the Train B AFW Pump P-504 breaker.
C. Incorrect. Plausible if thought that the excessive cooldown would not satisfy subcooling margin requirements, however the RCS is 131°F subcooled.
D. Incorrect. Plausible if thought that the loss of DC power would result in lack of Containment Cooling without local action, however, the Train B Containment Spray Pump and Emergency Cooling Units will be operating and satisfy the safety function.
Technical Reference(s) SO23-12-10, Safety Function Status Attached w/ Revision # See Checks Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53956 - EVALUATE a safety function status check for optimal recovery EOIs Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 50 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 Vital Auxililaries is satisfied due to having Train A EDG and 1E DC available.
Page 51 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 RCS Pressure control is satisfied due to being 131°F subcooled, which is in the safety function band.
Page 52 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 No feedwater is available to an intact S/G without local actions.
Page 53 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-12-10, Safety Function Status Checks Revision # 5 Plausible if thought that > 14 psig, however the safety function is satisfied.
Page 54 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Page 55 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 G 2.1.7 Importance Rating 4.7 Instrument Air: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Proposed Question: SRO 90 Given the following conditions:
- An Instrument Air leak has occurred on Unit 2.
- SO23-13-5, Loss of Instrument Air, has been initiated.
- Instrument Air header pressure is 58 psig and stable.
- Annunciator 52A21, FWRV FV-1121 AIR PRESS LO is alarming intermittently.
- Annunciator 52A02, FWCS SG2 E088 Level Deviation, has just gone into alarm.
Based on the listed conditions, what action should the CRS direct to mitigate the event?
A. Trip the Reactor and initiate SO23-12-1, Standard Post Trip Actions.
B. Initiate SO23-13-24, FWCS Malfunctions, to attempt to regain control of S/G E-088 level.
C. Place the S/G E-088 FWCS Master Controller in MANUAL and attempt control S/G E-088 level using Prompt and Prudent actions per OSM-14, Operations Department Expectations.
D. Take Local-Manual control of Feedwater Regulating Valves to control S/G E-088 level per SO23-9-6, Section for Local-Manual Operation of Main Feedwater Control Valves.
Proposed Answer: A Explanation:
A. Correct, per SO23-13-5, Loss of Instrument Air.
B. Plausible as the S/G Level Deviation alarm is an entry condition for SO23-13-24, however a Reactor Trip is required per SO23-13-5.
C. Plausible as Prompt and Prudent actions would be authorized for a S/G level deviation, however a Reactor Trip is required.
Page 56 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 D. Plausible as the Feed Regulating and Feed Regulating Bypass valves are air operated and could require local-manual operation if Instrument Air pressure was lost.
Technical Reference(s) SO23-13-5, Loss of Instrument Air Attached w/ Revision # See SO23-13-24, FWCS Malfunction Comments / Reference OSM-14, Operations Department Expectations 52A21 FWRV FV-1121 AIR PRESS LO Proposed references to be provided during examination:
Learning Objective: 53938 - As the SRO, DIRECT operator response to a loss of instrument air, per SO23-13-5 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 57 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comment /
Reference:
SO23-13-5, Loss of Instrument Air Revision # 13 Page 58 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-13-24, FWCS Malfunctions Revision # 6 Comments /
Reference:
OSM-14, Operations Department Expectations Revision # 29 Page 59 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
52A21 FWRV FV-1121 AIR PRESS LO Revision # 20 Page 60 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 075 A2.01 Importance Rating 3.2 Circulating Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Loss of Intake Structure Proposed Question: SRO 91 Given the following conditions:
- Unit 2 was operating at 100% Reactor power when a large influx of sea life caused a degraded intake.
- SO23-13-10, Loss of Vacuum, is in progress.
- Reactor power and Turbine load were lowered 5% to stabilize condenser vacuum.
- Main Circulating Water Pump P-116 was secured due to waterbox fouling.
- Maintenance estimates it will take 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> to clean the waterbox and restore P-116 to service.
- Condenser backpressure is now 6.2 Hg and stable.
- Circ water T peaked at 25.7°F and is now 24°F and slowly lowering.
Which ONE of the following describes the actions required for these conditions?
Note: NPDES = National Pollutant Discharge Elimination System A. Immediately trip the Reactor due to Condenser vacuum being in the Area of Restricted Operation. NPDES Circ water T limits have NOT been violated.
B. Continue the downpower to 85% due to Main Circulating Water Pump expected to be out of service for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. NPDES Circ water T limits have NOT been violated.
C. Immediately trip the Reactor due to Condenser vacuum being in the Area of Restricted Operation. NRC Operations Center must be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to exceeding NPDES Circ water T limits.
D. Continue the downpower to 85% due to Main Circulating Water Pump expected to be out of service for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. NRC Operations Center must be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to exceeding NPDES Circ water T limits.
Proposed Answer: D Page 61 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:
A. Plausible as vacuum is in the area of restricted operation, however an immediate Reactor trip is not required at this time. Additionally, Circ water T limits have been violated.
B. Plausible as a power reduction to 85% power is required, however Circ water T limits have been violated.
C. Plausible as the NPDES limit has been violated, however a Reactor trip is not required.
D. Correct.
Technical Reference(s) SO23-5-1.7, Power Operations Attached w/ Revision # See SO23-02-05 Circulating Water System Comments / Reference Operation Proposed references to be provided during examination:
Learning Objective: 73101 - RESPOND to Degraded Intake / Outfall capacity Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Page 62 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.7, Power Operations Revision # 53 Page 63 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.7, Power Operations Revision # 53 Comments /
Reference:
SO23-02-05 Circulating Water System Revision # 31 Operation Reference 2.4.8:
Page 64 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 035 G 2.4.30 Importance Rating 4.1 Steam Generator: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
Proposed Question: SRO 92 Given the following sequence of events on Unit 2:
- At time = 1700, Annunciator 60A46, Secondary Radiation Hi, alarmed.
- At time = 1705, Unit 2 Reactor was tripped.
- At time = 1710, an Alert was declared.
- At time = 1715, SO23-12-4, Steam Generator Tube Rupture was entered.
- At time = 1720, the event was upgraded to Site Area Emergency.
What is the latest time the initial verbal notification must be made to the NRC Headquarters Operations Officer?
A. 1800 B. 1810 C. 1815 D. 1820 Proposed Answer: B Explanation:
A. Plausible as the declaration clock starts when the first indication of the event is received, however the clock to make reports starts upon the first event declaration time.
B. Correct.
C. Plausible if thought that the clock begins upon entry into the optimal EOI, however it begins upon first event declaration.
D. Plausible if thought that the verbal notification clock resets upon event classification upgrade, however initial notification is due one hour from the initial declaration.
Technical Reference(s) SO23-VIII-10, Emergency Coordinator Attached w/ Revision # See Page 65 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Duties Comments / Reference Proposed references to be provided during examination:
Learning Objective: 55369 - As an SRO, DETERMINE Emergency Coordinator actions required for notification, evacuation, and exposure control of onsite personnel, and for making notifications and PARs to offsite agencies.
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 66 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-VIII-10, Emergency Coordinator Duties Revision # 31 Page 67 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 071 G 2.1.23 Importance Rating 4.4 Waste Gas Disposal: Ability to perform specific system and integrated plant procedures during all modes of plant operation Proposed Question: SRO 93 Given the following conditions:
- A Waste Gas release is in progress on T-085, Waste Gas Decay Tank.
- Continuous Exhaust Fans A-311 and A-312 are in service.
- Radiation Monitor 2/3RT-7808G is aligned to the Continuous Exhaust Plenum.
- Radiation Monitor 3RT-7865-1 is aligned to the Unit 3 Containment Purge Stack.
- The purge was completed last shift.
During the release the following occurs:
- Radiation Monitor 2/3RT-7808G has failed high.
- Continuous Exhaust Fan A-311 trips on overcurrent.
Which ONE of the following:
- 2) What action is required to continue the release?
A. 1) Tripping of Continuous Exhaust Fan A-311.
- 2) Align 3RT-7865-1 to the Plant Vent Stack along with 2RT-7865-1 to monitor the release per SO23-8-15, Radwaste Gas Discharge.
B. 1) Radiation Monitor 2/3RT-7808G failing high.
- 2) Install a jumper around the contact of 2/3RT-7808G that terminates the release and align 3RT-7865-1 to the Plant Vent Stack per SO23-8-15, Radwaste Gas Discharge.
C. 1) Tripping of Continuous Exhaust Fan A-311.
- 2) Install a jumper around the contact of 2/3RT-7808G that terminates the release and Page 68 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 align 3RT-7865-1 to the Plant Vent Stack per SO23-8-14, Radwaste Gas Collection System Operation.
D. 1) Radiation Monitor 2/3RT-7808G failing high.
- 2) Align 3RT-7865-1 to the Plant Vent Stack along with 2RT-7865-1 to monitor the release per SO23-8-14, Radwaste Gas Collection System Operation.
Proposed Answer: B Explanation:
A. Plausible as a loss of both Exhaust fans would terminated the release and aligning 3RT-7865-1 to the Vent Stack is required to continue the release, however only one fan was lost and RT-7808 would have to have a jumper installed.
B. Correct.
C. Plausible as the actions to continue the release are correct, however the release was terminated due to RT-7808 failing high.
D. Plausible as RT-7808 failing high terminated the release, however RT-7808 would have to have a jumper installed to recommence the release.
Technical Reference(s) SO23-08-15 Radwaste Gas Discharge Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56619 - ANALYZE normal and abnormal operations of the Gaseous Radwaste System Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2007 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Comments /
Reference:
SO23-08-15 Radwaste Gas Discharge Revision # 20 Page 69 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-08-15 Radwaste Gas Discharge Revision # 20 Page 70 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.1.15 Importance Rating 3.4 Conduct of Operations: Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.
Proposed Question: SRO 94 Per OSM-14, Operations Department Expectations, whose approval is required for Priority One - Special Orders?
A. Operations Director.
B. Manager of Plant Operations.
C. Any Shift Manager qualified licensed operator.
D. Any CRS holding the Control Room command function.
Proposed Answer: B Explanation:
A. Plausible if thought that the Operations Director is the authorizing authority for Priority One -
Special Orders, however it is the Manager of Plant Operations who authorizes them.
B. Correct.
C. Plausible since Priority One - Special Orders are required to be reviewed at the beginning of each shift and Shift Managers may have the authority to approve Special Orders, however the Manager of Plant Operations is the authorizing authority for these orders.
D. Plausible since Priority One - Special Orders are required to be reviewed at the beginning of each shift and it could be thought that any SRO holding the Unit command function may have the authority to approve Special Orders, however the Manager of Plant Operations is the authorizing authority for these orders.
Technical Reference(s) OSM-14, Operations Department Attached w/ Revision # See Expectations Comments / Reference Proposed references to be provided during examination:
Page 71 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Learning Objective: 53806 - Discuss the process and responsibility of the Control Room Supervisor for distribution and acknowledgement of information including:
Selection/approval process for acknowledgement of information reading assignments Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Comments /
Reference:
OSM-14, Operations Department Expectations Revision # 29 Page 72 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.1.42 Importance Rating 3.4 Conduct of Operations: Knowledge of new and spent fuel movement procedures Proposed Question: SRO 95 The Unit is in MODE 6 with the Reactor Vessel Head removed. The following conditions exist:
- Fuel transfer activities have been stopped while a problem with the Fuel Transfer Carriage is being fixed.
- The Refueling SRO is attending an outage planning brief in the Outage Control Center.
- Nuclear Fuels Management asks the Control Room to direct the Refueling Bridge Operator to uncouple a CEA for weighing.
Which ONE of the following is correct concerning this situation?
- 1. Uncoupling a CEA for weighing
- 2. What oversight is required to perform this evolution?
A. 1. IS a CORE ALTERATION.
- 2. The evolution may not commence until the Refueling SRO has returned to the Refueling Bridge.
B. 1. is NOT a CORE ALTERATION.
- 2. The evolution may not commence until the Refueling SRO has returned to the Refueling Bridge.
C. 1. IS a CORE ALTERATION.
- 2. The Refueling SRO is not required to be on the Refueling Bridge since a fuel bundle is not being moved.
D. 1. is NOT a CORE ALTERATION.
- 2. The Refueling SRO is not required to be on the Refueling Bridge since a fuel bundle is not being moved.
Page 73 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: A Explanation:
A. Correct.
B. Plausible if thought that since the fuel bundle is not being relocated that it would not be a core alteration, however weighing CEAs is a core alt.
C. Plausible as this is a core alt, however the refueling SRO is required to be on the bridge.
D. Plausible if thought that since the fuel bundle is not being relocated that it would not be a core alteration, and thus the refueling SRO would not be required.
Technical Reference(s) SO23-5-1.8, Shutdown Operations Attached w/ Revision # See SO23-X-7, Nuclear Fuel Movement for Comments / Reference Refueling Cycles Proposed references to be provided during examination:
Learning Objective: 56258 - Given plant conditions during core alterations, DETERMINE the action required of the Refueling SRO for the stated situation Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 7 Page 74 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.8, Shutdown Operations Revision # 24 Page 75 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-X-7, Nuclear Fuel Movement for Refueling Revision # 26 Cycles Page 76 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.2.5 Importance Rating 3.2 Equipment Control: Knowledge of the process for making design or operating changes to the facility Proposed Question: SRO 96 Given the following conditions:
- Excessive packing leakage from the standby TPCW pump was noted by a PEO.
- The PEO has isolated the leak by closing the suction and discharge valves to the standby TPCW pump and racking out the breaker.
- The Work Authorization Request is expected to be completed in the next week.
Per SO23-0-A4, Configuration Control,
- 1. How would the status of the TPCW pump be tracked?
- 2. Would a 10CRF50.59 screening be required?
A. 1. Status Control Form.
- 2. 50.59 screening IS required.
B. 1. Status Control Form.
- 2. 50.59 screening is NOT required.
C. 1. Plant Status Control Tracking Card.
- 2. 50.59 screening IS required.
D. 1. Plant Status Control Tracking Card.
- 2. 50.59 screening is NOT required.
Proposed Answer: B Explanation:
A. Plausible as a Status Control Form is the correct configuration control method, however a 50.59 screening is not required.
B. Correct.
C. Plausible as a Plant Status Control Tracking Card is used for configuration control, however this is only used if the temporary status is less than one shift. Additionally, a 50.59 screening is not Page 77 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 required.
D. Plausible as a 50.59 screening is not required and a PSCTC is used for configuration control, however only if temporary status is less than one shift.
Technical Reference(s) SO23-0-A4, Configuration Control Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56388 - Given a situation, DESCRIBE the administrative requirements that apply to the performance of an alignment not covered by an operating instruction, per SO23-0-A4 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 3 Page 78 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-0-A4, Configuration Control Revision # 19 Comments /
Reference:
SO23-0-A4, Configuration Control Revision # 19 Level RO SRO Page 79 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference:
Tier # 3 Group #
K/A # G 2.2.18 Importance Rating 3.9 Equipment Control: Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.
Proposed Question: SRO 97 Given the following MODE 5 conditions:
- Unit 2 RCS is 30 in the hot leg.
- Containment Closure Sheets are in effect per SO23-5-1.8.1, Shutdown Nuclear Safety.
- Personnel Hatch is open.
- Containment Mini Purge is in service.
- 1. Who is responsible for approving the Unit 2 Containment Closure Sheets?
- 2. Who is responsible for signing the Containment Closure Tracking Sheet to verify the ability to meet Containment Closure requirements?
A. 1. The Unit 2 CRS.
- 2. Each individual designated to perform closure actions must sign the Containment Closure Tracking Sheet once per shift.
B. 1. The Unit 2 CRS.
- 2. A supervisor from the division requiring Containment openings to be open shall sign the Containment Closure Tracking Sheet once per shift.
C. 1. The Outage Director.
- 2. Each individual designated to perform closure actions must sign the Containment Closure Tracking Sheet once per shift.
D. 1. The Outage Director.
- 2. A supervisor from the division requiring Containment openings to be open shall sign the Containment Closure Tracking Sheet once per shift.
Proposed Answer: B Explanation:
A. Plausible as the Unit 2 CRS is responsible for approving Containment Closure sheets, however Page 80 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 the department supervisors are responsible for signing the Containment Closure Tracking Sheets.
B. Correct.
C. Plausible as the Outage Director is responsible for notifying Operations Department of changes to the Defense in Depth sheets, which address Containment Closure requirements, however the CRS is responsible for approving the Containment Closure Sheets.
Plausible as the Outage Director is responsible for notifying Operations Department of changes to the Defense in Depth sheets, which address Containment Closure requirements, however the CRS is responsible for approving the Containment Closure Sheets.
Technical Reference(s) SO23-5-1.8.1, Shutdown Nuclear Safety Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:
Learning Objective: 56154 - As the SRO, DIRECT evolutions and activities in MODES 5 and 6 to ensure that Shutdown Safety Functions are maintained operable, functional, or available Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Page 81 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.8.1, Shutdown Nuclear Safety Revision # 31 Comments /
Reference:
SO23-5-1.8.1, Shutdown Nuclear Safety Revision # 31 The Outage Director is in charge of the Outage Control Center.
Comments /
Reference:
SO23-5-1.8.1, Shutdown Nuclear Safety Revision # 31 Page 82 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.8.1, Shutdown Nuclear Safety Revision # 31 Page 83 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-5-1.8.1, Shutdown Nuclear Safety Revision # 31 Page 84 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.3.6 Importance Rating 3.8 Radiation Control: Ability to approve release permits Proposed Question: SRO 98 The following meteorological conditions exist prior to performing a gaseous effluent release:
- Wind direction at 10 meters is 110°.
- Temperature difference between 10 and 40 meters is 0.20°C
- Wind speed at 10 meters is 7.7 miles per hour.
Which ONE of the following is the determination for the release per SO23-8-15, Attachment 4, Determination of Current Weather Conditions, Section 2.2?
A. Wind speed is DESIRABLE and the release can be performed.
B. Wind direction is DESIRABLE and the release can be performed.
C. Wind speed is UNDESIRABLE and the release can NOT be performed.
D. Wind direction is UNDESIRABLE and the release can NOT be performed.
Proposed Answer: B Explanation:
A. Incorrect. Plausible because if only Step 2.2.1 is performed, the wind direction would yield an UNDESIRABLE release.
B. Correct. With a T of 0.20°C and a wind speed of 7.7 mph the /Q = 2.9E-5 / 7.7 = 3.77E-6, therefore, the wind speed is DESIRABLE and the release can be performed.
C. Incorrect. Plausible because it could be thought that the wind is blowing in this direction, however, it is the direction the wind is blowing from. The release can be performed but the direction is UNDESIRABLE.
D. Incorrect. Plausible because the Table at 2.2.3 could be misread and this would yield an UNDESIRABLE conclusion.
Page 85 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-8-15, Radwaste Gas Discharge Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: SO23-8-15, Attachment 4 Learning Objective: 56068 - COORDINATE radioactive gas releases Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 4 Page 86 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-8-15, Attachment 4 Revision # 20 Page 87 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-8-15, Attachment 4 Revision # 20 The minimum wind speed to conduct the release is 6.0 mph, therefore the release can be commenced due to wind speed.
Page 88 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #
K/A # G 2.4.18 Importance Rating 4.0 Emergency Procedures/Plan: Knowledge of the specific bases for EOPs Proposed Question: SRO 99 Given the following conditions during a Loss of Coolant Accident:
- The following annunciators are in alarm:
- 57C10 - CONTAINMENT RADIATION HI
- 56A07 - CONTAINMENT PRESS HI ESFAS CHANNEL TRIP
- 57C19 - CONTAINMENT HYDROGEN LEVEL HI
- The following annunciator is NOT in alarm:
- 56A08 - CONTAINMENT PRESS HI - HI ESFAS CHANNEL TRIP
- Containment radiation levels are 65 R/HR.
- Containment temperature is 130°F.
- Reactor Coolant System pressure is 900 psia.
Which ONE of the following strategies should be considered per SO23-12-3, Loss of Coolant Accident, and what is the Technical Specification basis for this action?
A. Perform a hydrogen purge of Containment to reduce the concentration of hydrogen to less than 4%.
B. Secure Dome Air Circulators to allow Containment hydrogen to rise and concentrate away from electrical equipment.
C. Secure Containment Cooling to allow Containment humidity levels to rise and shift away from detonation / flammability area curve.
D. Initiate Containment Spray to strip Iodine from the Containment atmosphere to minimize fission product release in the event of a Containment breach.
Proposed Answer: D Explanation:
A. Plausible because purging hydrogen from Containment used to be directed in the LOCA EOI, however recent SONGS Unit 2/3 analysis has shown that hydrogen levels will not exceed 4% for at least 30 days during a design basis LOCA.
Page 89 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 B. Plausible because this action will concentrate hydrogen at the top of Containment, however, this creates ideal conditions for a hydrogen burn. Additionally, ensuring at least one Containment Dome Air Circulator is directed by 12-3, LOCA.
C. Plausible because raising the moisture content in Containment will shift from a detonation /
flammability area into the non-explosive region.
D. Correct. There is no Containment Spray signal at this time (otherwise, the HI - HI alarm would be in) and radiation level is > 40 R/HR. The LOCA EOI Bases and the EOI RNO recommends initiating Containment Spray to strip the atmosphere of iodine and reduce the potential for exceeding cumulative thyroid dose at the Exclusion Area Boundary.
Technical Reference(s) SO23-14-3, Loss of Coolant Accident Attached w/ Revision # See Bases Comments / Reference Proposed references to be provided during examination:
Learning Objective: 53962 - INITIATE Containment temperature and pressure control recovery Question Source: Bank # x Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam 2008 Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 4 Page 90 of 93 Rev b
ES-401 SONGS NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /
Reference:
SO23-14-3, Loss of Coolant Accident Bases Revision # 9 Comments /
Reference:
SO23-12-3, Loss of Coolant Accident Revision # 22 Comments /
Reference:
SO23-12-3, Loss of Coolant Accident Revision # 22 Page 91 of 93 Rev b