ML103210243

SONGS NRC 2010 RO Written Exam Worksheet

ML103210243
Person / Time
Site:	San Onofre
Issue date:	10/15/2010
From:	Clyde Osterholtz Operations Branch IV
To:	Southern California Edison Co
References
Download: ML103210243 (440)

Text

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 1 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 003 K1.03 Importance Rating 3.3 Reactor Coolant Pump System: Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems: RCP seal system Proposed Question: Common 1 Given the following conditions wi th Unit 3 at full power:

Reactor Coolant Pump P-004 seal cavity pr essures are approximately equal to Reactor Coolant System (RCS) pressure. A calculation of RCS leak rate has just been completed and is the same as the previously calculated rate. Plant Computer System is Out Of Service. All radiation levels are normal.

Which of the following describes the cause of these indications?

Reactor Coolant Pump P-004 has a(an)...

A. middle and upper seal failure.

B. excessive Controlled Bleed Off (CBO) flow.

C. vapor seal failure.

D. CBO Excess Flow Check Valve closure.

Proposed Answer: D

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 2 of 108 Rev g Explanation: A. Incorrect. Plausible because this could be an indication of a middle and upper seal failure, however, the lower, middle, and upper seals would all have to fail with the vapor seal intact to create similar circumstances. B. Incorrect. Plausible if thought that excessive CBO flow was the cause, however, staging within the seal package would cause a differential pressure to exist. C. Incorrect. Plausible if thought that failure of the vapor seal would yield normal radiation levels. D. Correct. When CBO flow exceeds 10 GPM, the CBO Excess Flow Check Valve will close creating the conditions listed.

Technical Reference(s) SO23-3-1.7, Attachment 16, L&S 1.22 Attached w/ Revision # See Comments / Reference SO23-15-56.B, 56B57 SD-SO23-360, Figure I-13 SD-SO23-390, Page 38 Proposed references to be provided during examination:None Learning Objective:

06022817 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 # 126661 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 3, 14 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 3 of 108 Rev g Comments /

Reference:

From SO23-3-1.7, Attachment 16, L&S 1.22 Revision # 37

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 4 of 108 Rev g Comments /

Reference:

From SO23-15-56.B, 56B57 Revision # 7

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 5 of 108 Rev g Comments /

Reference:

From SD-SO23-360, Figure I-13 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 6 of 108 Rev g Comments /

Reference:

From SD-SO23-390, Page 38 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 7 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 K4.03 Importance Rating 2.8 Chemical and Volume Control System

Knowledge of the CVCS design feature(s) and/or interlock(s) which provide for the following: Protection of the ion exchangers (high letdown temperature will isolate ion exchangers)

Proposed Question: Common 2 Which of the following is the LOWEST temperature that bypasses flow from TV-0224B, Ion Exchanger Bypass Valve?

A. 120ºF.

B. 130ºF.

C. 140ºF.

D. 150ºF.

Proposed Answer: C Explanation: A. Incorrect. Plausible because the nominal temperature out of the Letdown Heat Exchanger is 115ºF, therefore, it could make sense to divert 5ºF above this temperature. B. Incorrect. Plausible because this is the high temperature alarm for the Volume Control Tank, however, the setpoint for TV-0224B is 140ºF. C. Correct. This is the temperature that isolates flow to the Purification Ion Exchangers. D. Incorrect. Plausible if thought that this is the diversion temperature, however, this is the temperature at which the resin starts to melt.

Technical Reference(s) SD-SO23-390, Page 29 Attached w/ Revision # See Comments / Reference SO23-15-58.A, 58A03 SO23-3-2.1, Attachment 11 Proposed references to be provided during examination:None Learning Objective:

06021961 DESCRIBE the instrumentation used to monitor the operation of the Letdown and Charging Subsystem, including the name, function, sensing points, and location of each instrument.

Question Source: Bank #

Modified Bank #

(Note changes or attach parent) New X Question History: Last NRC Exam ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 8 of 108 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /

Reference:

From SD-SO23-390, Page 29 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 9 of 108 Rev g Comments /

Reference:

From SO23-15-58.A, 58A03 Revision # 11 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 10 of 108 Rev g Comments /

Reference:

From SO23-3-2.1, Attachment 11, L&S 1.1 Revision # 33 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 11 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 K5.04 Importance Rating 2.8 Chemical and Volume Control System

Knowledge of the operational implications of the following concepts as they apply to the CVCS: Reason for hydrogen cover gas in VCT (oxygen scavenge)

Proposed Question: Common 3 Which of the following describes the MAIN reason for maintaining a Hydrogen overpressure in the Volume Control Tank (VCT) during plant operation at power?

A. Minimizes amount of radioactive gas diverted to the Waste Gas System during plant power changes.

B. Provides adequate Chargi ng Pump suction pressure to minimize discharge accumulator pulsations.

C. Minimizes oxygen based corrosion of R eactor Coolant System components.

D. Provides an inert gas to minimize the formation of a hard bubble in the Pressurizer steam space.

Proposed Answer: C Explanation: A. Incorrect. Plausible because hydrogen does help to scavenge oxygen created by radiolysis, however, the amount of diverted gas is a function of the Primary Sampling System piping size. B. Incorrect. Plausible because the hydrogen overpressure does increase Charging Pump suction pressure, however, accumulator pulsations are minimized by the Nitrogen pressure inside the accumulator itself. C. Correct. Hydrogen overpressure scavenges oxygen which minimizes corrosion of RCS components. D. Incorrect. Plausible because the formation of a hard bubble in the Pressurizer steam space is undesirable, however, hydrogen is not an inert hard bubble gas.

Technical Reference(s) SD-SO23-390, Pages 36 & 45 Attached w/ Revision # See Comments / Reference SD-SO23-420, Page 3 Proposed references to be provided during examination:None Learning Objective:

06022872 PREDICT the consequences of the following Chemical and Volume Control System conditions: Inadequate hydrogen overpressure on the VCT.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 12 of 108 Rev g Question Source: Bank # 126539 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, 5 55.43 Comments /

Reference:

From SD-SO23-390, Page 36 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 13 of 108 Rev g Comments /

Reference:

From SD-SO23-390, Page 45 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 14 of 108 Rev g Comments /

Reference:

From SD-SO23-420, Page 3 Revision # 9

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 15 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 A4.02 Importance Rating 3.4 Residual Heat Removal System

Ability to manually operate and/or monitor in the control room: Heat exchanger bypass flow control Proposed Question: Common 4 Given the following condition:

Train A Shutdown Cooling (S DC) System is in service with Train B in standby.

Which of the following identifies how Shutdown Cooling System flow w ould be controlled if power was lost to HV-8160, SDC Heat Exchanger (HX) Bypass Flow Control Valve?

A. CLOSE HV-8161, SDC HX Bypass Normal Block Valve, energize then THROTTLE OPEN HV-0396, SDC HX Bypass Standby Fl ow Valve, to required flowrate.

B. THROTTLE HV-8150 and HV-81 51, SDC HX Outlet Valves.

C. POSITION HV-8150 and HV-8151, SDC HX Outlet Valves to desired flowrate then THROTTLE Component Cooling Wate r flow for desired cooldown.

D. THROTTLE all four (4) Low Pressure Safety Injection Header Loop Isolation Valves.

Proposed Answer: A Explanation: A. Correct. HV-8160 fails "AS-IS" on a loss of power, therefore, HV-8161 must be closed first and then HV-0396 opened to control flow. B. Incorrect. Plausible because these valves are used to control temperature but not flow.

C. Incorrect. Plausible if thought this was an acceptable method to control temperature and flow, however, HV-0396 is used when power is lost to HV-8160. D. Incorrect. Plausible because throttling with LPSI is allowed, however, only two LPSI Isolation Valves are in service to maintain Train separation.

Technical Reference(s) SO23-3-2.6, Attachment 6, Section 2.1 Attached w/ Revision # See Comments / Reference SO23-3-2.6, Attachment 16, L&S 2.4 SO23-3-2.6, Steps 6.1.7 & 6.2.1 SD-SO23-740, Pages 55, 56, & 57 SD-SO23-740, Figure 4 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 16 of 108 Rev g Learning Objective: 81087 / 06022972 DESCRIBE the configuration and operational characteristics of Shutdown Cooling System components. DESCRIBE the flowpaths and major components of the Shutdown Cooling System used for normal, abnormal, and emergency system operations.

Question Source: Bank # 77871 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, 8 55.43 Comments /

Reference:

From SO23-3-2.6, Attachment 6, Section 2.1 Revision # 27 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 17 of 108 Rev g Comments /

Reference:

From SO23-3-2.6, Attachment 16, L&S 2.4 Revision # 27 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 18 of 108 Rev g Comments /

Reference:

From SO23-3-2.6, Steps 6.1.7 & 6.2.1 Revision # 27 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 19 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 56 Revision # 17 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 20 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 57 Revision # 17 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 21 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 55 Revision # 17 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 22 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Figure 4 Revision # 17

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 23 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 A4.02 Importance Rating 4.0 Emergency Core Cooling System

Ability to manually operate and/or monitor in the control room: Valves Proposed Question: Common 5 Given the following conditions:

Unit 3 is in MODE 4 during a plant shutdown. Reactor Coolant System pressure is 500 psia. HV-9350, HV-9340, HV-9360, a nd HV-9370, Safety Injecti on Tank Outlet Valves, are OPEN with power aligned.

What is(are) the MINIMUM required action(s) to CLOSE the valves?

A. Place valve key switches in BYPASS and then in CLOSE.

B. Reduce RCS pressure < 460 psig, and then place valve key switches in BYPASS.

C. Place valve key switches from OPEN to CLOSE position.

D. Depress OVERRIDE pushbuttons and pl ace valve key switches in CLOSE.

Proposed Answer: A Explanation: A. Correct. This is the required action given the conditions listed.

B. Incorrect. Plausible because reducing RCS pressure less than 460 psig would allow the valve to open, however, in this condition the key switch need NOT be placed in BYPASS. C. Incorrect. Plausible if thought that there were no interlocks present given Reactor Coolant System pressure and temperature. D. Incorrect. Plausible because this is the required action if it were desired to close the valve following a Safety Injection Actuation Signal.

Technical Reference(s) SD-SO23-740, Page 34 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

06021971 DESCRIBE the operation of the following Safety Injection and Containment Spray Systems component, including function, location, and specific features including type, capacity, and power supplies as applicable. Safety Injection Tanks and SIT Outlet Valves.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 24 of 108 Rev g Question Source: Bank # 126973 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, 8 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 25 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 34 Revision # 17

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 26 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 K6.03 Importance Rating 3.6 Emergency Core Cooling System

Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Safety Injection Pumps Proposed Question: Common 6 Given the following conditions:

A Small Break Loss of Coolant accident has occurred. All required Safety System Actuations have occurred. Pressurizer pressure is 1000 psia. P-019, Train B High Pressure Safety In jection Pump (HPSI) tripped on overcurrent. HPSI Pump (P-018) is aligned to Train A and operating, but is only currently meeting 50% of the required loop flow per SO23-12-11, EOI Supporting Attachments, Attachment 12, Minimum Required Safety Injection Flowrates During Cold Leg Injection. HPSI Pump (P-017) is aligned to Train A and in standby.

Which of the following describes the usage of P-017, HPSI Pump in these circumstances?

A. Can NOT be used because the High Pressure Safety Injection Valves are set-up to limit the maximum flow in the event of a downstream break in the injection header.

B. Can be used and will result in meet ing the other 50% flow requirement.

C. Can NOT be used due to Emergen cy Diesel sequenced loading concerns.

D. Can be used but may not result in meet ing total Minimum Required Safety Injection Flowrates to each Loop due to parallel operation of HPSI Pumps.

Proposed Answer: D

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 27 of 108 Rev g Explanation: A. Incorrect. Plausible if thought that this was a concern in this circumstance, however, operation of the Standby HPSI Pump (P-017) in the same Train is allowed by the Emergency Operating Instructions. B. Incorrect. Plausible because it can be used, however, the increase in flow may not satisfy the Minimum Required Safety Injection Flowrate requirements. C. Incorrect. Plausible if thought that two pump operations was not allowed due to this concern, however, the concern is based on simultaneous auto start of both pumps and the auto start of the normal Train A HPSI Pump is blocked by the Kirk Interlock switch on the 3 rd of a kind pump. D. Correct. Operation is allowed but the expected flow may be less than two full trains based on pumps operating in parallel.

Technical Reference(s) SO23-14-3, Attachment 1, Step 5 Basis Attached w/ Revision # See Comments / Reference SO23-12-3, Step 5.a.4)

Proposed references to be provided during examination:None Learning Objective:

06021979 Given an operational condition of the Safety Injection and Containment Spray System addressed by a procedural precaut ion, limitation, or administrative requirement, STATE the limiting condition, the limit or the basis for that limiting condition as 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 5, 8, 14 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 28 of 108 Rev g Comments /

Reference:

From SO23-14-3, Attachment 1, Step 5 Basis Revision # 8 Comments /

Reference:

From SO23-14-3, Attachment 1, Step 5 Basis Revision # 8 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 29 of 108 Rev g Comments /

Reference:

From SO23-12-3, Step 5.a.4)

Revision # 21

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 30 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 007 K3.01 Importance Rating 3.3 Pressurizer Relief/Quench Tank System

Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment Proposed Question: Common 7 Assuming no in-leakage, each of the following Containment par ameters would RISE, if the Quench Tank drain piping were to prematurely fail EXCEPT:

A. Pressure.

B. Nitrogen concentration.

C. Containment Sump.

D. Hydrogen concentration.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that an overpressure did not exist in the Quench Tank.

B. Incorrect. Plausible if thought that the tank is inerted with hydrogen. C. Incorrect. Plausible if thought that the only gas and no liquid were contained in the Quench Tank. D. Correct. Hydrogen concentration will not rise because the tank is inerted with nitrogen.

Technical Reference(s) SD-SO23-360, Pages 61 & 74 Attached w/ Revision # See Comments / Reference SD-SO23-360, Figure III-3 Proposed references to be provided during examination:None Learning Objective: 70385 / 94467 EXPLAIN the interfaces between the Reactor Coolant System and other plant systems. DESCRIBE the configuration and operational characteristics of the Reactor Coolant 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

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 31 of 108 Rev g Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 32 of 108 Rev g Comments /

Reference:

From SD-SO23-360, Page 74 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 33 of 108 Rev g Comments /

Reference:

From SD-SO23-360, Page 61 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 34 of 108 Rev g Comments /

Reference:

From SD-SO23-360, Figure III-3 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 35 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 008 K4.07 Importance Rating 2.6 Component Cooling Water System

Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: Operation of the CCW swing bus power supply and its associated breakers and controls Proposed Question: Common 8 Given the following condition:

P-025, Component Cooling Water (CCW) Pump , is being realigned from Train A to Train B.

Which of the following actions realigns the P-024, Component Cooling Water Pump start circuit for a Train A SIAS start signal?

A. Rack out P-025 Breaker A0406 to DISC ONNECT and turn the Kirk Key.

B. Position P-025 Motor Power Transfer Switch D005 to Bus A06.

C. Rack in P-025 Train B Breaker to the CONNECTED position.

D. Remove P-025 Train A Breaker DC Control Power.

Proposed Answer: A Explanation: A. Correct. Component Cooling Water Pump P-024 Breaker A0405 automatic close circuitry is reconnected through an auxiliary switch on the A0406 Kirk Key. B. Incorrect. Plausible if thought that this interlock switch positioning to power the spare pump motor from Train B would enable the Train A Pump, however, the Train A Pump is enabled with the A0406 Kirk Key. C. Incorrect. Plausible because it could be thought that racking in the Train B supply to the spare pump would then enable the normal Train A Breaker, however, the Train A Pump is enabled with the A0406 Kirk Key. D. Incorrect. Plausible because it could be thought that removing control power to the Swing Train A Breaker would realign to the normal Train A breaker, however, the Train A Pump is enabled with the A0406 Kirk Key.

Technical Reference(s) SD-SO23-400, Figure 9 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 36 of 108 Rev g Learning Objective:

06022005 DESCRIBE the operation of the following Component Cooling Water System controls, including the name, function, interlocks, and location of each: CCW Pump P025 Kirk Key interlock.

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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 37 of 108 Rev g Comments /

Reference:

From SD-SO23-400, Figure 9 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 38 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 010 A1.07 Importance Rating 3.7 Pressurizer Pressure Control System

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS pressure Proposed Question: Common 9 Given the following conditions with Unit 3 at 100% power:

3PIC-0100, Pressurizer Pressure Controller is in AUTO with a setpoint at 2225 psia. One (1) bank of Backup Heaters is ON in MANUAL. All other Backup Heater s are in AUTO / OFF. Both sets of Proportional Heaters are in AUTO.

Both Pressurizer Spray Valve Controllers are in AUTO.

Based on the above conditions, what is the LOWEST Reactor Coolant System pressure at which the Pressurizer Spray Valves would be 100% open?

A. 2250 psia B. 2275 psia C. 2300 psia D. 2325 psia Proposed Answer: B Explanation: A. Incorrect. Plausible if thought that a 25 psia deviation caused the valves to be full open, however, this is the setpoint when the Spray Valves start to open. B. Correct. The Pressurizer Spray Valves will be 100% open when the deviation from setpoint is 50 psia. With a setpoint of 2225 psia the valves will be full open at 2275 psia. C. Incorrect. Plausible because the normal setpoint on the Pressurizer Pressure Controller is 2250 psia, therefore, when the deviation from setpoint reaches 50 psia and Reactor Coolant System pressure is 2300 psia, the Spray Valves will be full open. D. Incorrect. Plausible if thought that a 100 psia deviation caused the valves to be full open.

Technical Reference(s) SO23-3-1.10, Attachment 9, L&S 1.1 Attached w/ Revision # See Comments / Reference SO23-13-27, Attachment 4 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 39 of 108 Rev g Learning Objective:

06022841 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 # 127009 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 Comments /

Reference:

From SO23-3-1.10, Attachment 9, L&S 1.1 Revision # 22 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 40 of 108 Rev g Comments /

Reference:

From SO23-13-27, Attachment 4 Revision # 4

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 41 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 012 K6.06 Importance Rating 2.7 Reactor Protection System

Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Sensors and detectors Proposed Question: Common 10

Given the following conditions:

Unit 2 is at 100% power. One (1) Core Protection Calculator (CPC) speed sensor on Reactor Coolant Pump P003 fails low.

Which of the following describes the plant response to this condition?

A. A failed sensor will be indicated on the associated CPC.

The associated CPC will NOT trip. B. A failed sensor will be indicated on the associated CPC.

The associated CPC will trip on DNBR and LPD.

C. All four CPCs will indicate failed sensors.

The associated CPCs will NOT trip. D. All four CPCs will indicate failed sensors. All four CPCs will trip on DNBR and LPD.

Proposed Answer: B

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 42 of 108 Rev g Explanation: A. Incorrect. Plausible because a failed sensor will indicate on the associated CPC, however, had the sensor failed high the associated CPC would not trip. B. Correct. Per SO23-3-2.13, the failed sensor is indicated and the individual CPC will trip.

C. Incorrect. Plausible if thought that one sensor inputs to all four channels. D. Incorrect. Plausible if thought that one sensor inputs to all four channels.

Technical Reference(s) SO23-3-2.13, Section 6.4 Attached w/ Revision # See Comments / Reference SO23-3-2.13, Attachment 1, Section 2.0 Proposed references to be provided during examination:None Learning Objective:

06023685 /

06025697 DESCRIBE the inputs to the CPCs and CEACs, the purpose of each input, and the outputs available from the system. LIST the instruments which input to the CPCs and CEACs and the calculational function which each provides. Given an abnormal condition or malfunction of the Core Protection Calculators: PREDICT the effect of the given conditions on the Core Protection Calculators and plant operations.

Question Source: Bank # 209010 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 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 43 of 108 Rev g Comments /

Reference:

From SO23-3-2.13, Section 6.4 Revision # 15 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 44 of 108 Rev g Comments /

Reference:

From SO23-3-2.13, Attachment 1, Section 2.0 Revision # 15 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 45 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 012 A3.03 Importance Rating 3.4 Reactor Protection System

Ability to monitor automatic operation of the RPS, including: Power supply Proposed Question: Common 11 Which of the following would be the expected indications on the Reactor Trip Breaker Mimic Panel when a Loss of Vital AC Bus Y01 occurs?

A. K-1 & K-2 Relay white lights are OFF. Only two (2) Reactor Trip Breaker green lights are ON.

B. K-1 & K-2 Relay white lights are ON. Only two (2) Reactor Trip Breaker green lights are ON.

C. K-1 & K-2 Relay white lights are OFF. Only four (4) Reactor Trip Breaker green lights are ON.

D. K-1 & K-2 Relay white lights are ON. Only four (4) Reactor Trip Breaker green lights are ON.

Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 46 of 108 Rev g Explanation: A. Incorrect. Plausible because both K-1 & K-2 are deenergized, however, loss of a vital bus will deenergize two matrix relays in each affected matrix (6 total) which will open paths to two K relays and open four breakers. B. Incorrect. Plausible because both K-1 & K-2 are affected, however, the UV lights are normally illuminated. Loss of a vital bus will deenergize two matrix relays in each affected matrix (6 total) which will open paths to two K relays and open four breakers. C. Correct. Loss of a vital bus will deenergize two matrix relays in each affected matrix which will open paths to two K relays and open four breakers. D. Incorrect. Plausible because 4 RTCBs are open, however, the UV lights are normally illuminated, not extinguished.

Technical Reference(s) SD-SO23-510, Figure 13 Attached w/ Revision # See Comments / Reference Lesson Plan 2XCR09, Pages 45 & 61 Proposed references to be provided during examination:None Learning Objective:

06023698 /

06023697 DESCRIBE the inputs to the Plant Protection System, the purpose of each, their trip setpoints and actuation logic. DESCRIBE the operation of the Plant Protection System components and instrumentation, including function, location, design basis, interlocks, setpoints, special features 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 6 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 47 of 108 Rev g Comments /

Reference:

From SD-SO23-510, Figure 13 Revision # 10 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 48 of 108 Rev g Comments /

Reference:

From Lesson Plan 2XCR09, Page 61 Revision # 1 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 49 of 108 Rev g Comments /

Reference:

From Lesson Plan 2XCR09, Page 45 Revision # 1

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 50 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.03 Importance Rating 4.4 Engineered Safety Features Actuation System

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: Rapid depressurization Proposed Question: Common 12

Given the following conditions:

An Excess Steam Demand Event has o ccurred on Steam Generator E-088 inside Containment. The cooldown caused a rapid depressurization of the Reactor C oolant System (RCS) to 1100 psia. MSIS, CIAS, SIAS, CCAS and CSAS have fully actuated. NO operator actions have been taken.

Which of the following:

1.) Identifies the impact on the RCS w hen Steam Generator E-088 reaches dryout?

2.) Actions should be taken to mitigate the situation?

A. 1.) Heat Removal will stop and due to the cooldown and excessive differential temperature will exist between the Pressurizer and RCS.

2.) When dryout occurs, initiate depressurization of the RCS to reduce subcooling to 20ºF to 50ºF.

B. 1.) An excessive differential temperature will exist between the two loops and could cause thermal shock at the Reactor Vessel inlet nozzles.

2.) When dryout occurs, reduce the ho tter loops temperature using Steam Generator E-089 to within 20ºF of the affected loop.

C. 1.) Heat Removal will stop with the RCS at a higher mass and if allowed to heatup could cause a Pressurized Thermal Shock condition. 2.) Prior to reaching dryout, dump steam from E-089 to maintain < 200 psi above E-088 and stabilize E-089 pressure at P SAT for the lowest T COLD after dryout.

D. 1.) Heat Removal will stop with the RCS at a higher mass and if allowed to heatup could cause the Pressurizer to go solid. 2.) Dump steam from E-089 to maintain the highest T COLD stable without cooling down further and then immediatel y throttle Safety Injection.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 51 of 108 Rev g Proposed Answer: C Explanation: A. Incorrect. Plausible if thought that the issue was the T between the Pressurizer and RCS Loops and reducing the pressure would reduce this T, however, the increased mass of the Reactor Coolant and subsequent heatup could cause a Pressurized Thermal Shock (PTS) condition if actions aren't taken to stabilize at the lowest T COLD. B. Incorrect. Plausible if thought that the issue was the T between the RCS Loops and reducing the temperature in the least affected Loop would narrow this differential, however, if temperature isn't stabilized at the lowest T COLD then a subsequent heatup could cause a Pressurized Thermal Shock condition due to the increased mass from Safety Injection. C. Correct. The increased mass of the Reactor Coolant System and subsequent heatup could cause a Pressurized Thermal Shock condition if actions aren't taken to stabilize at the lowest T COLD. D. Incorrect. Plausible if thought that reducing pressure in the least affected Steam Generator would add to the total excessive cooldown, however, if temperature isn't stabilized at the lowest T COLD then a subsequent heatup would occur and cause PTS.

Technical Reference(s) SO23-14-5, Attachment 1, Section 3.0 Attached w/ Revision # See Comments / Reference SO23-12-11, Attachment 2, FS-30 Proposed references to be provided during examination:None Learning Objective:

06022998 /

06023111 PREDICT and EXPLAIN the response of major plant systems, equipment and parameters to an excess steam demand event. STATE the major recovery actions in response to an ESDE 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 52 of 108 Rev g Comments /

Reference:

From SO23-14-5, Attachment 1, Section 3.0 Revision # 8 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 53 of 108 Rev g Comments /

Reference:

From SO23-12-11, Attachment 2, FS-30 Revision # 7 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 54 of 108 Rev g Comments /

Reference:

From SO23-12-11, Attachment 2, FS-30 Revision # 7

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 55 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 022 A3.01 Importance Rating 4.1 Containment Cooling System

Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation Proposed Question: Common 13

Given the following condition with Unit 3 at 100% power:

Surveillance testing results in an inadvertent Safety Injection Act uation Signal (SIAS).

Which of the following describes the condition of the Containment Normal Cooling Unit Fans

? Containment Normal Cooling Unit Fans

... A. must be manually restarted after the SIAS is reset.

B. remain running during the inadvertent SIAS.

C. are overridden and restarted without resetting the SIAS.

D. automatically restar t when the SIAS is reset.

Proposed Answer: B Explanation: A. Incorrect. Plausible because conceptually it would make sense for the Fans to trip since they have no cooling water, however, they continue to run. B. Correct. Normal Chilled Water to Containment is closed by either SIAS or CIAS signal. Despite the fact that cooling water is secured, the Normal Containment Cooling Fans continue to run. C. Incorrect. Plausible if thought that the Fans trip, however, they continue to run.

D. Incorrect. Plausible if thought that the Fans trip, however, they continue to run.

Technical Reference(s) Lesson Plan 2XAL09, Page 17 Attached w/ Revision # See Comments /

Reference SO23-3-2.22, Attachment 4, Steps 2.5.13 & 14 SO23-3-2.22, Attachment 7, Steps 2.2.16 Proposed references to be provided during examination:None Learning Objective: 81446 / 81447 DESCRIBE the configuration and operational characteristics of Containment System components. INTERPRET instrumentation and controls utilized in the Containment System.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 56 of 108 Rev g ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 57 of 108 Rev g Question Source: Bank # 75596 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2000 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 9 55.43 Comments /

Reference:

From Lesson Plan 2XAL09, Page 17 Revision # 6-4 Comments /

Reference:

From SO23-3-2.22, Attachment 4, Steps 2.5.13 & 14 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 58 of 108 Rev g Comments /

Reference:

From SO23-3-2.22, Attachment 7, Step 2.2.16 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 59 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 022 G 2.1.7 Importance Rating 4.4 Containment Cooling System

Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Proposed Question: Common 14 Given the following conditions:

A loss of Normal Containment Cooling is in progress. Containment temperature and pr essure are slowly rising.

How does an increase in Contai nment pressure affect indicated Pressurizer pressure?

As Containment pressure rises, Pr essurizer pressure will indicate...

A. less than actual due to a Containment differential pressure detector with an open reference port.

B. greater than actual due to a Containm ent differential pressure detector with an open reference port.

C. less than actual due to a Containment differential pressure detector with a closed reference port.

D. greater than actual due to a Containm ent differential pressure detector with an closed reference port.

Proposed Answer: A Explanation: A. Correct. With an open reference port, as Containment pressure rises indicated Pressurizer pressure will lower. B. Incorrect. Plausible because the Containment differential pressure detector has an open reference port, however, indicated pressure will read less than actual. C. Incorrect. Plausible because indicated pressure will read less than actual, however, it is due to an open reference port. D. Incorrect. Plausible if thought that a closed reference port existed for this instrument.

Technical Reference(s) SO23-14-9, Attachment 1, Step 13 Attached w/ Revision # See Comments / Reference

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 60 of 108 Rev g Proposed references to be provided during examination:None Learning Objective: 115787 / 81445 DESCRIBE the effect of the following changes on pressure and differential pressure detectors: Pressure EXPLAIN the interfaces between the Containment 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 5, 9 55.43 Comments /

Reference:

From SO23-14-9, Attachment 1, Step 13 Revision # 10

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 61 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 A2.02 Importance Rating 4.2 Containment Spray System: Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic recirculation transfer Proposed Question: Common 15 Given the following c onditions on Unit 2:

A Large Break Loss of Coolant Accident and Loss of Offsite Power have occurred. Train B 4160 Volt Bus 2A06 tripped on overcurrent. Recirculation Actuation Signal (RAS) has actuated. 2HV-9306 and 2HV-9307, Train A Safety Injection Miniflow Valves have NOT closed. Refueling Water Storage Tank (RWST) level is less than 19%.

Which of the following identifies the impact on the Containment Spray System and what action(s) are necessary to mitigate the event?

A. Train A Containment Spray Pump will begin to cavitate with Miniflow Valves open. Stop the Train A Containment Spray Pump when flow starts to oscillate.

B. Water is transferred from the C ontainment Emergency Sump to the RWST. Verify Emergency Sump level is > 18' 4" and ensure Miniflow Valves closed.

C. Train B Containment Spray Pump Minifl ow Valves are interlocked with Train A. Close all Miniflow Valves and verify Emergency Sump level is > 20'.

D. Train A Containment Spray Pump will trip due to the RAS actuation.

Close Miniflow Valves and then restart the Train A Containment Spray Pump.

Proposed Answer: B

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 62 of 108 Rev g Explanation: A. Incorrect. Plausible because the RAS actuation may have occurred before adequate level was reached in the Containment Emergency Sump, how ever, flow through the Miniflow Valves is designed to keep the Containment Spray Pump cool and would not result in cavitation. B. Correct. Water continues to transfer from the Containment Emergency Sump to the RWST if the Miniflow valves fail to automatically close. The Miniflow Valves are closed and sump level is verified above 18'4". C. Incorrect. Plausible if thought that the Miniflow Valves are interlocked with each other, however, this action is done automatically upon a RAS actuation and adequate Containment Emergency

Sump level. D. Incorrect. Plausible because the Miniflow Valves should be closed, however, it is the Containment Spray Pumps that trip on a RAS actuation.

Technical Reference(s) SO23-12-11, Attachment 14, Steps 1 & 2 Attached w/ Revision # See Comments / Reference SD-SO23-740, Figure 1 Proposed references to be provided during examination:None Learning Objective:

81670 / 06028370 INTERPRET instrumentation and controls utilized in the Safety Injection and Containment Spray System. DISCUSS the major event mitigation strategies for various Emergency Operating Instruction accidents.

Question Source: Bank # 127471 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, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 63 of 108 Rev g Comments /

Reference:

From SO23-12-11, Attachment 14, Steps 1 & 2 Revision # 7 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 64 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Figure 1 Revision # 17

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 65 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 K4.07 Importance Rating 3.8 Containment Spray System

Knowledge of the CSS design feature(s) and/or interlock(s) which provide for the following: Adequate level in the containment sump for suction (interlock)

Proposed Question: Common 16 Given the following conditions:

A Large Break Loss of Coolant Accident has occurred. Recirculation Actuation Syst em (RAS) has just actuated. All required automatic Safeguards actuations have properly initiated. Emergency Sump level is 15' 9" plant elevation. Containment pressure is 42 psig and slowly rising.

Which of the following describes the status of High Pressure Safety Injection (HPSI) Pumps, Containment Spray (CS) Pumps, Refueling Water Storage Tank (RWST), and associated pump suction paths?

HPSI and CS Pumps are operating with the Emergency Sump Suction Valves open and RWST Suction Valves __________.

RWST level is __________.

A. open lowering B. closed rising C. open rising D. closed lowering Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 66 of 108 Rev g Explanation: A. Incorrect. Plausible because the valve response is correct and it could be thought that with the RWST Suction Valves still open that there would be flow from the RWST, however, with 42 psig in Containment the only source of suction flow will be from the Emergency Sump. B. Incorrect. Plausible if thought that the RWST Suction Valves closed on RAS, however, both suctions will be aligned until sump level is verified and then the RWST Suction Valves are

manually closed. C. Correct. Upon RAS, the LPSI Pumps trip and the Emergency Sump Valves open but the RWST Suction Valves must be manually closed after verifying sump level. With less than 18'4" in the sump the HPSI Pump Mini-Flow Recirc Valves will still be open discharging to the RWST. With 42 psig in Containment the only source of suction flow will be from the Emergency Sump. D. Incorrect. Plausible because it could be thought that the RWST Suction Valves closed on RAS, however, both suctions will be aligned until sump level is verified and then the RWST Suction Valves are manually closed.

Technical Reference(s) SD-SO23-740, Pages 9 & 38 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective: 81669 / 81671 DESCRIBE the configuration and operational characteristics of Safety Injection and Containment Spray System components. ANALYZE normal and abnormal operations of the Safety Injection and Containment Spray 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 67 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 9 Revision # 17 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 68 of 108 Rev g Comments /

Reference:

From SD-SO23-740, Page 38 Revision # 17

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 69 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 039 A4.03 Importance Rating 2.8 Main and Reheat Steam System

Ability to manually operate and/or monitor in the control room: MFW pump turbines Proposed Question: Common 17 As Reactor power is raised from 5% to 100%, how do the Main Feed Pump Turbine Governor Valves respond?

Main Steam Governor Valve Reheat Steam Governor Valves A. Throttles closed Throttle closed B. Throttles open Throttle closed C. Throttles closed Throttle open D. Throttles open Throttle open Proposed Answer: A Explanation: A. Correct. During an initial startup, the Reheat Steam Governor Valves (multiple poppets on LP side) open first, followed by the Main Steam Governor Valve poppet (only one poppet on HP side). As Turbine load is increased, Reheat Steam pressure rises. The Main Governor Valve closes first followed by the Reheat Steam Governor Valve as power is increased. B. Incorrect. Plausible because the Reheat Steam Governor Valve closes, however, the Main Steam Governor Valve is also closed. C. Incorrect. Plausible because the Main Steam Governor Valve closes, however, the Reheat Steam Governor Valve is full open and throttles closed. D. Incorrect. Plausible if thought that these valves worked in the reverse order, however, this description coincides with a Turbine load decrease.

Technical Reference(s) SD-SO23-260, Figure 10 Attached w/ Revision # See Comments / Reference SO23-2-1, Attachment 18, L&S 4.6 Proposed references to be provided during examination:None Learning Objective:

64702 / 64706 IDENTIFY Main Feedwater Pump and Turbine System flowpaths, components, and locations including being able to draw and label system diagrams. DESCRIBE the configuration and operational characteristics of Main Feedwater Pump and Turbine system components.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 70 of 108 Rev g 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, 14 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 71 of 108 Rev g Comments /

Reference:

From SD-S)23-260, Figure 10 Revision # 14 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 72 of 108 Rev g Comments /

Reference:

From SO23-2-1, Attachment 18, L&S 4.6 Revision # 25

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 73 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 059 A1.07 Importance Rating 2.5 Main Feedwater System

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls, including: Feed Pump speed, including normal control speed for ICS Proposed Question: Common 18

Which of the following describes the response of the Unit 3 Feedwater Co ntrol System to the Reactor Trip Override (RTO) signal?

Main Feedwater (MFW) Regulating Valves close,...

A. MFW Bypass valves go to 5% open.

MFW Pumps speed lowers to 3000 rpm and remains there.

B. MFW Bypass valves go to 5% open.

MFW Pumps speed lowers towards 3600 rpm, then modulates to control valve P. C. MFW Bypass valves go to 50% open.

MFW Pumps speed lowers to 3000 rpm and remains there.

D. MFW Bypass valves go to 50% open.

MFW Pumps speed lowers towards 3600 rpm, then modulates to control valve P. Proposed Answer: D Explanation: A. Incorrect. Plausible because Main Feedwater Pump speed used to lower to 3000 rpm (prior to Digital FWCS installation), however, it will modulate to control P and the Bypass Valves open to 50%. The 5% value is a misconception as this is the design power level for adequate feed flow using the Bypass Valves. B. Incorrect. Plausible because the action of the Main Feedwater Pump is correct, however, the 5% value is a misconception as this is the design power level for adequate feed flow using the Bypass

Valves. C. Incorrect. Plausible because the Bypass Valve positioning and initial lowering of Main Feedwater Pump speed was correct before the Digital FWCS installation, however, speed will modulate to control valve P. D. Correct. This is the correct action of the Feedwater Control System post trip.

Technical Reference(s) SO23-9-6, Step 6.8 Attached w/ Revision # See Comments / Reference SO23-9-6, Attachment 6, Steps 2.4 7 2.5 SO23-9-6, Attachment 12, L&S 4.2 & 4.4

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 74 of 108 Rev g Proposed references to be provided during examination:None Learning Objective:

06018325 Given Feedwater Control System indications in response to the following events, DETERMINE if the correct actions where taken (automatic and/or manual) and what additional actions are required to achieve the desired results: Reactor Trip Override Question Source: Bank # 209018 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, 7 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 75 of 108 Rev g Comments /

Reference:

From SO23-9-6, Step 6.8 Revision # 25 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 76 of 108 Rev g Comments /

Reference:

From SO23-9-6, Attachment 12, L&S 4.2 & 4.4 Revision # 25 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 77 of 108 Rev g Comments /

Reference:

From SO23-9-6, Attachment 6, Step 2.4 Revision # 25 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 78 of 108 Rev g Comments /

Reference:

From SO23-9-6, Attachment 6, Step 2.5 Revision # 25

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 79 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 K2.01 Importance Rating 3.2 Auxiliary/Emergency Feedwater System

Knowledge of the bus power supplies to the following: AFW system MOVs Proposed Question: Common 19 Which of the following Auxiliary Feedwater Valv es is electrically controlled using DC power?

Auxiliary Feedwater Pump...

A. P-140 Discharge Valve, 2HV-4705.

B. P-141 Discharge Valve, 2HV-4713.

C. P-504 Discharge Valve, 2HV-4712.

D. P-504 Discharge Bypass Valve, 2HV-4762.

Proposed Answer: A Explanation: A. Correct. Both P-140 Discharge Valves are powered from DC Buses D1 and D2.

B. Incorrect. Plausible because P-141, Control Valve HV-4715 is powered from a DC Bus D2, however, the Pump Discharge Valves are powered from an MCC and a Vital Instrument Bus. C. Incorrect. Plausible because P-504, Control Valve HV-4730 is powered from DC Bus D1, however, the Pump Discharge Valves are powered from an MCC and a Vital Instrument Bus. D. Incorrect. Plausible because this valve is powered from a Vital Instrument Bus, however, it is AC as opposed to DC.

Technical Reference(s) SD-SO23-780, Page 57 Attached w/ Revision # See Comments / Reference SD-SO23-780, Figure 1 Proposed references to be provided during examination:None Learning Objective:

06018523 Given an operational condition of the Auxiliary Feedwater System addressed by a procedural precaution, limitation, or administrative requirement, STATE the limiting condition and the basis for that limiting condition.

Question Source: Bank # 73812 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 80 of 108 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 81 of 108 Rev g Comments /

Reference:

From SD-SO23-780, Page 57 Revision # 11 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 82 of 108 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 83 of 108 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 84 of 108 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 85 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 062 G 2.1.28 Importance Rating 4.1 AC Electrical Distribution System

Conduct of Operations: Knowledge of the purpose and function of major system components and controls Proposed Question: Common 20 Which of the following describes the func tion and purpose of the 480 VAC Containment Penetration Backup Breaker Panels?

Provide...

A. an alternate supply of power to Safety Related 480 VAC loads in Containment.

B. an alternate supply of power for Non-Safety Related 480 VAC loads to protect the Containment penetration.

C. backup overload protection for Safety Rela ted loads to prevent loss of Safety Buses during harsh Containment conditions.

D. backup overload protection for any 480 VAC loads capable of causing damage to Containment penetrations.

Proposed Answer: D Explanation: A. Incorrect. Plausible because it could be thought that backup infers an alternate source, however, they provide backup overload protection for 480 VAC loads capable of causing damage to Containment penetrations. B. Incorrect. Plausible because it could be thought that the panels only existed for Non-Safety Buses, however, the Backup Penetration Panels provide backup overload protection for all 480 VAC loads capable of causing damage to Containment penetrations. C. Incorrect. Plausible because it could be thought that the panels provided backup protection to protect the Safety Related Buses, however, they provide backup overload protection for all 480 VAC loads capable of causing damage to Containment penetrations. D. Correct. The Containment Penetration Backup Breaker Panels provide backup overload protection for all 480 VAC loads capable of causing damage to Containment penetrations.

Technical Reference(s) SD-SO23-120, Page 70 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 86 of 108 Rev g Learning Objective: 81442 / 81447 STATE the functions and design bases of the Containment System and its

components. INTERPRET instrumentation and controls utilized in the Containment 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 9 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 87 of 108 Rev g Comments /

Reference:

From SD-SO23-120, Page 70 Revision # 19

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 88 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 062 K1.04 Importance Rating 3.7 AC Electrical Distribution System

Knowledge of the physical connections and/or cause-effect relationships between the AC Electrical Distribution System and the following systems: Offsite power sources Proposed Question: Common 21

Given the following conditions with Unit 2 in a normal 100% power alignment:

Unit 3 has just been taken off line due to a Reactor Coolant System leak. Unit 2 trips, causing a disturbanc e on the Edison Grid and voltage on all 1E 4160 V Buses on both SONGS Units degrade to 4000 Volts. Unit 3 Safety Injection Actuation Signal (SIAS) occurs 45 seconds after Unit 2 trips.

Which of the following will be the source of power to the Unit 3 1E 4160 V Buses five (5) minutes after the SIAS actuation if the degraded Offsite Power condition continues to exist?

A. Unit 2 Diesel Generators.

B. Unit 2 Reserve Auxiliary Transformers.

C. Unit 3 Diesel Generators.

D. Unit 3 Reserve Auxiliary Transformers.

Proposed Answer: C Explanation: A. Incorrect. Plausible because the Unit 2 EDGs can be aligned to the Unit 3 Safeguard Buses, however, this action can only be performed when the load from both Buses will NOT exceed the rating for one (1) EDG and this is not possible with an SIAS on the other Unit. B. Incorrect. Plausible because this is the Alternate Preferred Source, however, not with a Sustained Degraded Voltage Signal (SDVS). C. Correct. With a SDVS and SIAS, the Unit 3 EDGs will be powering the Safeguard Buses.

D. Incorrect. Plausible because this is the Normal Preferred Source, however, not with a Sustained Degraded Voltage Signal and a Safety Injection Actuation Signal.

Technical Reference(s) SO2-15-63.B, 63B04 Attached w/ Revision # See Comments / Reference SD-SO23-120, Pages 147 & 155 SD-SO23-120, Pages 109 & 110 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 89 of 108 Rev g Learning Objective:

06028412 /

06028413 DESCRIBE the operation of the following 1E 4.16 KV Electrical System controls, and interlocks associated with the degraded voltage system: 4.16 KV Bus Automatic Transfer controls. DESCRIBE the integrated operation of SDVS (Sustained Degraded Voltage Signal) and DGVSS (Degraded Grid Voltage with SIAS Signal) including sensor inputs, actuation logic, and actuated devices.

Question Source: Bank # 141832 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 90 of 108 Rev g Comments /

Reference:

From SO2-15-63.B, 63B04 Revision # 13 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 91 of 108 Rev g Comments /

Reference:

From SD-SO23-120, Page 147 Revision # 19 Comments /

Reference:

From SD-SO23-120, Page 155 Revision # 19 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 92 of 108 Rev g Comments /

Reference:

From SD-SO23-120, Page 110 Revision # 19 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 93 of 108 Rev g Comments /

Reference:

From SD-SO23-120, Page 109 Revision # 19

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 94 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 063 K1.02 Importance Rating 2.7 DC Electrical Distribution System

Knowledge of the physical connections and/or cause-effect relationships between the DC Electrical Distribution System and the following systems: AC electrical system Proposed Question: Common 22 Given the following c onditions on Unit 3:

3Q069, 120 VAC Uninterruptible Power Supply (UPS) is being supplied by its normal power source.

Which of the following conditions will cause an immediate transfer of Inverter 3Y012 Static Transfer Switch?

A. Inverter 3Y012 Output Overvoltage of 110%.

B. Inverter 3Y012 Input Circuit Breaker opens.

C. Battery Charger 3B015 loss of power from 480 VAC Transformer 3T016.

D. Inverter 3Y012 high tem perature relay and alarm.

Proposed Answer: B Explanation: A. Incorrect. Plausible because an overcurrent condition of 120% would cause this transfer, however, not an overvoltage. B. Correct. Opening of the Input Breaker results in an undervoltage condition that causes Static Switch transfer. C. Incorrect. Plausible because the Battery Charger supplies power to the DC Bus which powers the Inverter; however, in this condition the Battery itself would continue supplying the Inverter. D. Incorrect. Plausible because there is a high temperature relay and alarm associated with the Inverter, however, it is an alarm indication only.

Technical Reference(s) SD-SO23-130, Pages 16 & 17 Attached w/ Revision # See Comments / Reference SD-SO23-130, Figure 4 Proposed references to be provided during examination:None Learning Objective:

0701364 DISCUSS the operation of the 1E 125 VDC/120 VAC System including controls, instrumentation, interlocks, capacity, power supplies and system response to component failures.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 95 of 108 Rev g 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:

From SD-SO23-130, Page 17 Revision # 12 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 96 of 108 Rev g Comments /

Reference:

From SD-SO23-130, Page 15 Revision # 12 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 97 of 108 Rev g Comments /

Reference:

From SD-SO23-130, Figure 4 Revision # 12

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 98 of 108 Rev g ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 99 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 K2.01 Importance Rating 2.7 Emergency Diesel Generator System

Knowledge of the bus power supplies to the following: Air compressor Proposed Question: Common 23 Which of the following is the power supply to Emergency Diesel Generat or 2G002 Starting Air Compressors?

Motor Control Center...

A. 2BD B. 2BH C. 2BDX D. 2BHX Proposed Answer: C Explanation: A. Incorrect. Plausible because MCC 2BD is supplied from 2B04 and is located in the Emergency Diesel Generator Room, however, this is not the power supply to the Starting Air Compressors. B. Incorrect. Plausible because MCC 2BH is supplied from 2B06, however, it is located in the 2G003 Emergency Diesel Generator room. C. Correct. MCC 2BDX is supplied from Bus 2B14 via Bus 2A07.

D. Incorrect. Plausible because MCC 2BHX supplies the Starting Air Compressors, however, it is for the 2G003 Emergency Diesel Generator.

Technical Reference(s) SO23-2-13.1, Attachment 1, Steps 2.2.3 & 5Attached w/ Revision # See Comments / Reference SO23-2-13.1, Attachment 2, Steps 2.2.3 & 5 Proposed references to be provided during examination:None Learning Objective: 73243 / 73245 IDENTIFY Emergency Diesel Generat or Mechanical Systems flowpaths, components, and locations including being able to draw and label system

diagrams. DESCRIBE the configuration and operational characteristics of Emergency Diesel Generator Mechanical Systems components.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 100 of 108 Rev g Question Source: Bank # 208022 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 55.43 Comments /

Reference:

From SO23-2-13.1, Attachment 1, Step 2.2.5 Revision # 5 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 101 of 108 Rev g Comments /

Reference:

From SO23-2-13.1, Attachment 1, Step 2.2.3 Revision # 5 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 102 of 108 Rev g Comments /

Reference:

From SO23-2-13.1, Attachment 2, Step 2.2.3 Revision # 5 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 103 of 108 Rev g Comments /

Reference:

From SO23-2-13.1, Attachment 2, Step 2.2.5 Revision # 5

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 104 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 K3.03 Importance Rating 3.6 Emergency Diesel Generator System

Knowledge of the effect that a loss or malfunction of the EDG system will have on the following: EDG (manual loads)

Proposed Question: Common 24 Given the following condition:

Emergency Diesel Generator (EDG) 2G002 is being operated in parallel with Offsite Power when all the EDG Output Br eaker control power fuses blow.

Which of the following is the effect on the EDG Output Breaker to this failure?

The EDG Output Breaker...

A. will immediately trip OPEN.

B. can only be opened from the Control Room.

C. will trip OPEN on a loss of Generator excitation.

D. can only be opened manually at t he breaker cubicle.

Proposed Answer: D

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 105 of 108 Rev g Explanation: A. Incorrect. Plausible if thought that the loss of control power fuses would trip the breaker.

B. Incorrect. Plausible if thought that the breaker will still trip from the Control Room, however, loss of control power disables remote operation. C. Incorrect. Plausible if thought that control power also fed Generator excitation, however, it is supplied from a different source. D. Correct. Given the conditions listed, the breaker can only be opened locally.

Technical Reference(s) Drawing 30328 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

73307 ANALYZE normal and abnormal operations of the Emergency Diesel Generator

Electrical Systems.

Question Source: Bank # 127077 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2005A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments /

Reference:

From Drawing 30328 (Refer to Print)

Revision # 30

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 106 of 108 Rev g ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 107 of 108 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 073 K5.03 Importance Rating 2.9 Process Radiation Monitoring System

Knowledge of the operational implications of the following concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits Proposed Question: Common 25 Given the following conditions:

An operator must hang a clearance on a valve located 5 feet away from a Containment Purge Line elbow r eading the equivalent of 100 mrem per hour. Health Physics reports that the radiation level 10 feet from the purge line is 10 mrem per hour. The purge line elbow is considered a point source.

Which of the following is the dose rate in the area the operator will be hanging the clearance?

A. 20 mrem/hr B. 40 mrem/hr C. 50 mrem/hr D. 80 mrem/hr Proposed Answer: B Explanation: A. Incorrect. Plausible if thought I 1 x (D 1) = I 2 x (D 2) then 10 x 10

= I 2 x 5 = 20 mrem/hr. B. Correct. I 1 x (D 1)2 = I 2 x (D 2)2 then 10 x 10 2 = I 2 x 5 2 = 40 mrem/hr. C. Incorrect. Plausible if thought that the dose at 5 feet was 1/2 the dose at 10 feet. D. Incorrect. Plausible if thought that the dose at 5 feet was 8 times the dose at 10 feet.

Technical Reference(s) Lesson Plan 2LC898, Page 54 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 108 of 108 Rev g Learning Objective:

06022759 Given a situation requiring the performance of Minor Maintenance by Operators in a Radiological Controlled Area (RCA), DESCRIBE the radiological precautions and safe work practices that apply to the situation, to include: APPLY the Operator REP special instruction to vent and drain activities and the movement of Contaminated Material including instruments allowable to determine dose rates.

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 12 55.43 Comments /

Reference:

From Lesson Plan 2LC898, Page 54 Revision # 1-1

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 1 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 076 K4.03 Importance Rating 2.9 Service Water System: Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Automatic opening features associated with SWS isolation valves to CCW heat exchangers Proposed Question: Common 26 Given the following c onditions on Unit 2:

Train A Salt Water Cooling (SWC) is aligned to the Emergency Discharge Line due to Circulating Water System Heat Treatment. It is necessary to swap the Train A Salt Water Cooling Pumps.

Which of the following describes why it is pref erred to start the on-co ming Salt Water Cooling Pump from the Second Point of Control cabinet?

A. It defeats the CCW Heat Exchanger Salt Water Normal Outlet Valve OPEN interlock required for SWC Pump start.

B. CCW Heat Exchanger Salt Water Normal Outlet Valve can NOT be open at the same time as the Emergency Outlet (Beach) Valve.

C. It blocks the automatic OPEN signal to the Salt Water Cooling Pump Discharge Valve to allow throttling flow slowly to the Emergency Header.

D. It defeats the annunciator for Salt Wate r Pump Incomplete Sequence due to the CCW Heat Exchanger Salt Water Normal Outlet Valve being closed.

Proposed Answer: A Explanation: A. Correct. It allows starting the pump with the Normal Outlet Valve to the Outfall closed. B. Incorrect. Plausible if thought that the start from the Second Point of Control is to prevent automatic opening of the Normal Outlet Valve to the Outfall, however, the automatic opening is defeated by a step to open the breaker to the Normal Outlet Valve prior to pump start. C. Incorrect. Plausible if thought that defeating the automatic opening would be required, however, the pump discharge is manually opened prior to pump start and the start from the Second Point of Control allows starting the pump with the Normal Outlet Valve to the Outfall closed. D. Incorrect. Plausible because it could be thought that this alarm would lock in after a normal pump start, however, the alarm is not the concern and the action to start from the Second Point of Control is to allow starting the pump with the Normal Outlet Valve to the Outfall closed.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 2 of 111 Rev g Technical Reference(s) SO23-2-8.1, Attachment 9, Step 2.2 Attached w/ Revision # See Comments / Reference SO23-2-8.1, Attachment 20, L&S 1.3 Proposed references to be provided during examination:None Learning Objective: 60305 / 60307 DESCRIBE the configuration and operational characteristics of Salt Water Cooling System components. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments /

Reference:

From SO23-2-8.1, Attachment 9, Step 2.2 Revision # 9 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 3 of 111 Rev g ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 4 of 111 Rev g Comments /

Reference:

From SO23-2-8.1, Attachment 20, L&S 1.3 Revision # 9

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 5 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 078 G 2.2.37 Importance Rating 3.6 Instrument Air System: Equipment Control: Ability to determine operability and/or availability of safety related equipment Proposed Question: Common 27 Given the following conditions:

HV-8419, Atmospheric Dump Valve (ADV) air supply check valve has failed OPEN. Annunciator 52A35 - ADV HV-8419 AIR

/ N2 PRESS LO is in alarm. Instrument Air header pressure at the ADV is 10 psig and lowering.

Assuming Instrument Air is completely lost, wh ich of the following describes the impact on the operation of the Atmospheric Dump Valve?

A. Valve fails open because there is no pressure to keep the valve closed.

B. Supply pressure for valve operation is below allowed values but spring pressure will assist with valve opening.

C. Manual operation only is available because the Nitrogen Backup Supply is lost through the same check valve.

D. Normal operation is lost but valve cl osure on a Main Steam Isolation Signal is maintained by the Nitrogen Backup Supply.

Proposed Answer: C Explanation: A. Incorrect. Plausible if thought that the valve fails open, however, the valve fails closed.

B. Incorrect. Plausible because supply pressure is below allowed values and there is spring pressure applied to the valve, however, the spring pressure is designed to fail the valve closed. C. Correct. The low pressure alarm is indicative of low air and low nitrogen supply. The low pressure alarm is 73 psig and the Backup Nitrogen Supply Regulator supplies at 80 psig. The supply pressure to the valve is lost and manual valve operation is required. D. Incorrect. Plausible because it could be thought that the Nitrogen Backup was for closure of the Atmospheric Dump Valves on MSIS, however, they fail closed and the backup nitrogen is for plant cooldown during a Small Break LOCA and will be at reduced pressure.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 6 of 111 Rev g Technical Reference(s) SD-SO23-160, Pages 20 & 24 Attached w/ Revision # See Comments / Reference SD-SO23-160, Figures 4b & 4c SO23-15-52.A, 52A35 Proposed references to be provided during examination:None Learning Objective: 59223 / 59227 IDENTIFY Main Steam System flowpaths, components, and locations including being able to draw and label system diagrams. ANALYZE normal and abnormal operations of the Main Steam 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, 8 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 7 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Page 24 Revision # 20

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 8 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Page 20 Revision # 20 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 9 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Figure 4c Revision # 20

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 10 of 111 Rev g Comments /

Reference:

From SO23-15-52.A, 52A35 Revision # 14

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 11 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Figure 4b Revision # 20

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 12 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 103 A1.01 Importance Rating 3.7 Containment System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment controls including: Containment pressure, temperature, and humidity Proposed Question: Common 28 Given the following conditions on Unit 2 while in MODE 1:

Annunciator 60A03 - CONTAINMENT / FHB TEMP HI is in alarm. All available Containment Norma l Cooling Units are operating. No symptoms of a Reactor Coolant, Main Steam or Feedwater leak exist. Average Containment temperatur e is 105ºF and slowly rising.

Which of the following describes the appropria te actions to take in this condition?

A. Initiate a plant shutdown due to maximum design average Containment temperature being exceeded.

B. Place the Containment Emergency Cooling Units in service.

C. Start any available Reactor Cavity Fans and Control Element Drive Mechanism Cooling Units.

D. Initiate a Containment Mini-Purge at the maximum allowed flowrate.

Proposed Answer: B Explanation: A. Incorrect. Plausible if thought that the maximum temperature had been exceeded, however, the maximum temperature per Technical Specifications is 120ºF and the Alarm Response Procedure specifies starting the Containment Emergency Cooling Units at 105ºF. B. Correct. The Alarm Response Procedure specifies starting the Containment Emergency Cooling Units at 105ºF. C. Incorrect. Plausible if thought that starting this equipment would be preferred over starting the Containment Emergency Cooling Units, however, the Alarm Response Procedure specifies starting the Containment Emergency Cooling Unit at 105ºF. D. Incorrect. Plausible if thought that starting this equipment would reduce Containment temperature, however, the Alarm Response Procedure specifies starting the ECUs.

Technical Reference(s) Technical Specification LCO 3.6.5 Attached w/ Revision # See Comments / Reference SO23-15-60.A1, 60A03 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 13 of 111 Rev g Proposed references to be provided during examination:None Learning Objective: 81640 / 81638 ANALYZE normal and abnormal operations of the Containment Air Handling System. DESCRIBE the configuration and operational characteristics of Containment Air Handling 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:

From Technical Specification LCO 3.6.5 Amendment # 127 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 14 of 111 Rev g Comments /

Reference:

From SO23-15-60.A1, 60A03 Revision # 11

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 15 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 027 K2.01 Importance Rating 3.1 Containment Iodine Removal System: Knowledge of bus power supplies to the following: Fans Proposed Question: Common 29 Which of the following is the power supply to 2A-353, Containment Recirculation Filtration Unit? 480 VAC...

A. Bus 2B09 in the 63' Penetration Building.

B. Motor Control Center BO in the 50' Control Building.

C. Bus 2B18 in the 56' Turbine Building.

D. Motor Control Center BU in the 50' Radwaste Building.

Proposed Answer: A Explanation: A. Correct. This is the new power supply to 2A-353.

B. Incorrect. Plausible because Motor Control Center BO once was the power supply to this fan, however, the MCC is located in the 70' Control Building closet. See Modified Bank Question in Comments / Reference. C. Incorrect. Plausible because Bus 2B18 is located in the 56' Turbine Building and is powered from 480 V Bus 2A07 which is located in the 30' Turbine Building. D. Incorrect. Plausible because Motor Control Center BU is powered from 480 V Bus 2A09 (via 2B15) which is located in the 85' Control Building and MCC BU is located in the 50' Radwaste Building which would be a logical source of power for the Containment Recirculation Filtration Unit.

Technical Reference(s) SD-SO23-770, Pages 49 & 69 Attached w/ Revision # See Comments / Reference SO23-1-4.2, Attachment 2, Step 2.1.17 Proposed references to be provided during examination:None Learning Objective:

81639 INTERPRET instrumentation and controls utilized in the Containment Air

Handling System.

Question Source: Bank # Modified Bank # 127296 (Note changes or attach parent) New ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 16 of 111 Rev g 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:

From SD-SO23-770, Page 49 Revision # 9 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 17 of 111 Rev g Comments /

Reference:

From SD-SO23-770, Page 69 Revision # 9 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 18 of 111 Rev g Comments /

Reference:

From SO23-1-4.2, Attachment 2, Step 2.1.17 Revision # 30 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 19 of 111 Rev g Comments /

Reference:

From Exam Bank #127296 Revision # 10/24/06 Which of the following is the power supply to A-353, Containment Recirculation Filtration Unit?

480 VAC Motor Control Center...

A. BO B. BMX C. BZ D. BU ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 20 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 055 A3.03 Importance Rating 2.5 Condenser Air Removal System: Ability to monitor automatic operation of the CARS, including: Automatic diversion of CARS exhaust Proposed Question: Common 30 Given the following conditions with Unit 2 operating at 100% power:

Annunciator 60A46 - SECONDARY RADIATION HI is in alarm. RE-7818, Low Range Air Ejector Radiation Monitor has alarmed. RE-7870, Wide Range Air Ejector Radiation Monitor has a rising trend but is NOT in alarm. A Steam Generator Blowdown R adiation Monitor is in alarm.

Which of the following describes the current c ondition of A361, Steam Air Ejector Exhaust Unit and the proper operator response?

A. Flow has been automatica lly aligned through A361, Steam Air Ejector Exhaust Unit.

Place A361 Control Switch in DIRECT to ensure flow through the unit.

B. Flow is normally aligned through A 361, Steam Air Ejector Exhaust Unit.

Place the Exhaust Unit Heater to ON.

C. Flow has been automatic ally aligned through A361 due to RE-7818 ALERT alarm. Place A361 Control Switch to ON and ensure heater is in AUTO.

D. Flow is bypassing A361, Steam Air Ejector Exhaust Unit.

Place A361 Control Switch in DIRECT to manually align flow through the unit.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that this automatic feature exists, however, this action must be performed by the operator. B. Incorrect. Plausible if thought that this could be the normal alignment, however, this is not the normal alignment in order to preserve the filters in A361. C. Incorrect. Plausible if thought that this feature exists and is from the wide range monitor versus the narrow range, however, alignment must be performed by an operator. D. Correct. The unit has no AUTO alignment features and is not normally aligned. The operator places the control switch in DIRECT based on Annunciator Response Procedure guidance.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 21 of 111 Rev g Technical Reference(s) SO23-15-60.A2, 60A46 Attached w/ Revision # See Comments / Reference SD-SO23-190, Page 14 SO23-13-14, Attachment 3, Step 2.1.1 Proposed references to be provided during examination:None Learning Objective: 60605 / 06022695 DESCRIBE the configuration and operational characteristics of Condenser Air Removal System components. Per the Reactor Coolant Leak procedure, SO23-13-14, DESCRIBE : The expected plant response for each step.

Question Source: Bank # 209135 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2009 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10, 11 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 22 of 111 Rev g Comments /

Reference:

From SO23-15-60.A2, 60A46 Revision # 14 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 23 of 111 Rev g Comments /

Reference:

From SD-SO23-190, Page 14 Revision # 12 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 24 of 111 Rev g Comments /

Reference:

From SO23-13-14, Attachment 3, Step 2.1.1 Revision # 14

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 25 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 086 K5.04 Importance Rating 2.9 Fire Protection System: Knowledge of the operational implication of the following concepts as they apply to the Fire Protection System: Hazards to personnel as a result of fire type and methods of protection Proposed Question: Common 31 Which of the following identifie s the personnel hazard that a ccompanies a HALON actuation during a fire?

HALON... A. exposure to combustion produces an acidic residue that can cause chemical burns.

B. exposure to combustion produces additional toxic gases in the affected area.

C. in concentrations greater than 0.5%

causes damage to the lungs due to its corrosive qualities.

D. at the proper concentration chemically r eacts with air increasing the nitrogen in the atmosphere.

Proposed Answer: B Explanation: A. Incorrect. Plausible if thought that this was a possible HALON interaction, however, HALON is non-reactive with material outside the combustion process and extinguishes the combustion by interfering with the chemical reaction thereby smothering the fire. B. Correct. HALON, when exposed to combustion, can produce toxic gases. C. Incorrect. Plausible if thought that this was a possible HALON biological interaction, however, HALON itself is not toxic. D. Incorrect. Plausible if thought that nitrogen concentration would increase and lower oxygen in the area, however, HALON extinguishes the combustion process by interfering with the chemical reaction and smothering the fire and does not increase the nitrogen in the atmosphere.

Technical Reference(s) SD-SO23-590, Pages 17 & 99 Attached w/ Revision # See Comments / Reference SO23-7-4, Step 8.1 Proposed references to be provided during examination:None Learning Objective:

06019292 DESCRIBE the operation of the following Halon 1301 Fire Suppression System components, including function, location, and specific features including type, capacity, and power supplies where applicable.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 26 of 111 Rev g 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 Comments /

Reference:

From SO23-7-4, Step 8.1 Revision # 4 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 27 of 111 Rev g Comments /

Reference:

From SD-SO23-590, Page 17 Revision # 15 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 28 of 111 Rev g Comments /

Reference:

From SD-SO23-590, Page 99 Revision # 15

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 29 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 041 A4.06 Importance Rating 2.9 Steam Dump/Turbine Bypass Control System: Ability to manually operate and/or monitor in the control room: Atmospheric relief valve controllers Proposed Question: Common 32 Given the following conditions:

Unit 2 is in MODE 3 at normal operating pressure and temperature. Main Steam Isolation Valves are closed. Reactor Coolant System temperature is being controlled by operation of the Atmospheric Dump Valves in AUTO.

Which of the following describes the response of the Atmospheric Dump Valve Controller when one of the Steam Generator Pressure Channel inputs fail?

High failure of a single channel will...

A. have no effect and low failure will maintain last good value.

B. open the valve and low failu re will close the valve.

C. have no effect and low failure will close the valve.

D. open the valve and low fa ilure will have no effect.

Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 30 of 111 Rev g Explanation: A. Incorrect. Plausible because it could be thought that the control and failure scheme could be similar to Feedwater Control (DCS). B. Incorrect. Plausible if thought that the controller responded to either channel failing, however, a high channel failure will prevent the valve from opening. C. Correct. With this design, a low or high channel failure will prevent the valve from opening. Stem is worded as such because the ADVs are normally closed and in MANUAL at power. D. Incorrect. Plausible if thought that a high failure was to ensure continued heat removal.

Technical Reference(s) SD-SO23-160, Pages 21 & 22 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

102465 DESCRIBE the configuration and operational characteristics of Main Steam System components.

Question Source: Bank # 209031 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 31 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Page 21 Revision # 20 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 32 of 111 Rev g Comments /

Reference:

From SD-SO23-160, Page 22 Revision # 20

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 33 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 014 K4.03 Importance Rating 3.2 Rod Position Indication System: Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Rod bottom lights Proposed Question: Common 33 Which of the following results in illuminati ng the amber Control Element Assembly Rod Bottom Light?

A. All CEDM coils deenergized and pulse counter resets to zero (0) inches.

B. All CEDM coils deenergized and pulse counter reaching the Lower Electrical Limit.

C. One (1) out of two (2) Reed Switches reaching the Lower Group Limit.

D. Two (2) out of two (2) Reed Swit ches actuated at zero (0) inches.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that the signal was from the Pulse Counting Position Indication resetting to zero on a trip, however, the rod bottom light will only light if two out of two Reed Switches are actuated at zero (0) inches. B. Incorrect. Plausible if thought that the signal was from the Lower Electrical Limit Reed Switches combined with the pulse counter. It is a misconception that the LEL Reed Switches actuate the Rod Bottom Lights. The LEL is at one (1) step. C. Incorrect. Plausible if thought that the signal was from either Reed Switch actuated at the Lower Group Limit (LGL), however, the LGL is a Plant Computer System derived function. D. Correct. The Rod Bottom Light will only light if two out of two Reed Switches are actuated at zero (0) inches.

Technical Reference(s) SD-SO23-510, Pages 25 & 29 Attached w/ Revision # See Comments / Reference SO23-3-2.19, Attachment 8, L&S 4.5 Proposed references to be provided during examination:None Learning Objective:

81788 / 81785 INTERPRET instrumentation and controls utilized in the Control Element Drive Mechanism Control System (CEDMCS). EXPLAIN the interfaces between the Control Element Drive Mechanism Control System (CEDMCS) and other plant systems

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 34 of 111 Rev g 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 6 55.43 Comments /

Reference:

From SD-SO23-510, Page 25 Revision # 10 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 35 of 111 Rev g Comments /

Reference:

From SD-SO23-510, Page 29 Revision # 10 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 36 of 111 Rev g Comments /

Reference:

From SO23-3-2.19, Attachment 8, L&S 4.5 Revision # 23

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 37 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 072 G 2.1.27 Importance Rating 3.9 Area Radiation Monitoring System: Conduct of Operations: Knowledge of system purpose and/or function Proposed Question: Common 34 Which of the following Area Radiat ion Monitors provides a direct input into the Qualified Safety Parameter Display System (QSPDS)?

A. RE-7848, Containment Buildi ng 30' Area Radiat ion Monitor.

B. RE-7850, Fuel Handling Bu ilding Area Radiation Monitor.

C. RE-7851, Control Room Area Radiation Monitor.

D. RE-7820-1, Containment High Range Area Radiat ion Monitor.

Proposed Answer: D Explanation: A. Incorrect. Plausible because Containment Building radiation is monitored by QSPDS, however, only the high range monitor performs this function. B. Incorrect. Plausible because the Fuel Handling Building has ESFAS initiated protection; however, this function is not monitored by QSPDS. C. Incorrect. Plausible if thought that the QSPDS would alert the Control Room Operator to high radiation, however, this function is provided by a different alarm. D. Correct. RE-7820-1 & RE-7820-2 are both inputs into QSPDS.

Technical Reference(s) SD-SO23-690, Page 72 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

06023555 APPLY Technical Specification operability requirements and action statements to the Accident Monitoring System.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 38 of 111 Rev g 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 39 of 111 Rev g Comments /

Reference:

From SD-SO23-690, Page 72 Revision # 16

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 40 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 035 K6.01 Importance Rating 3.2 Steam Generator System: Knowledge of the effect of a loss or malfunction of the following will have on the SGS: MSIVs Proposed Question: Common 35 Given the following conditions:

Unit 3 is operating at 50% power. 3HV-8204, Steam Generator E-089 Main Steam Isolation Valve (MSIV) fails CLOSED.

Which of the following describes the plant response to these conditions?

Steam Generator E-088 level...

A. swells until the Feedwater Level Control System adjusts to the rising steam demand. B. swells, then shrinks due to a Reactor Trip generated by a Core Protection Calculator (CPC) Auxiliary Trip.

C. shrinks due to decreasing Steam Generat or pressure then swells as Turbine load stabilizes at a lower output.

D. shrinks due to a Turbine trip caused by an auxiliary contact in the MSIV control circuit.

Proposed Answer: B Explanation: A. Incorrect. Plausible because the Main Steam Header is cross connected downstream of the Main Steam Isolation Valves, however, an Asymmetric Steam Generator Trip will be generated. B. Correct. The Core Protection Calculator generates an Auxiliary Trip to protect against MSIV closure. C. Incorrect. Plausible because increasing the steam demand from one Steam Generator will cause steam pressure to lower, however, the Core Protection Calculator inserts an Auxiliary Trip. D. Incorrect. Plausible because the Turbine does trip, however, not for the reason listed.

Technical Reference(s) Lesson Plan 2XCR02, Page 102 Attached w/ Revision # See Comments / Reference SO23-3-2.13, Attachment 2, Step 9 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 41 of 111 Rev g Learning Objective:

06023685 DESCRIBE the inputs to the CPCs and CEACs, the purpose of each input, and the outputs available from the system. LIST all CPC Auxiliary Trips and their setpoints.

Question Source: Bank # 75570 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2000 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 42 of 111 Rev g Comments /

Reference:

From SO23-3-2.13, Attachment 2, Step 9 Revision # 15 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 43 of 111 Rev g Comments /

Reference:

From Lesson Plan 2XCR02, Page 102 Revision # 2-1

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 44 of 111 Rev g 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 36 Given the following condition:

A Core Exit Thermocouple (CET) feeding the Critical Function Monitoring System (CFMS) Subcooled Margin Monitor has an open circuit.

1.) Which of the follo wing identifies the impact on the CET indication?

2.) What action would ensure that the LOWEST CFMS Subcooled Margin was being displayed in the Control Room at CR-56?

A. 1.) The CET indication fails low.

2.) Select WORST-CASE SCM from the QSPDS temperature instruments.

B. 1.) The CET indication fails low. 2.) Select CET SCM from the Q SPDS temperature instruments.

C. 1.) The CET indication fails high. 2.) Select WORST-CASE SCM from t he QSPDS temperature instruments.

D. 1.) The CET indication fails high. 2.) Select CET SCM from the Q SPDS temperature instruments.

Proposed Answer: A Explanation: A. Correct. This is the correct indication and action to display the lowest Subcooled Margin. B. Incorrect. Plausible because this CET indication does fail low and an open circuit on a CET will remove it from scan on the SMM, however, selecting Worst-Case SCM from the QSPDS temperature instrument display will always yield the lowest Subcooled Margin on CR-56. C. Incorrect. Plausible because selecting Worst-Case SCM from the QSPDS temperature instrument displays the lowest Subcooled Margin on CR-56, however, this CET indication fails low on an open circuit. D. Incorrect. Plausible because an open circuit on a CET will remove it from scan on the SMM, however, selecting Worst-Case SCM from the QSPDS temperature instrument display will always yield the lowest Subcooled Margin on CR-56.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 45 of 111 Rev g Technical Reference(s) SO23-3-2.32, Attachment 1, Step 2.16 Attached w/ Revision # See Comments / Reference SD-SO23-820, Pages 63 & 65 NRC Generic Fundamentals Exam Bank Proposed references to be provided during examination:None Learning Objective: 115728 / 06023553 STATE the basic theory of operation of the following temperature measurement devices: Thermocouple ANALYZE normal and abnormal operation of the Accident Monitoring System, including alarms, limiting conditions and actions required.

Question Source: Bank # 209032 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, 8 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 46 of 111 Rev g Comments /

Reference:

From SO23-3-2.32, Attachment 1, Step 2.16 Revision # 11 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 47 of 111 Rev g Comments /

Reference:

From SD-SO23-820, Page 63 Revision # 8 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 48 of 111 Rev g Comments /

Reference:

From SD-SO23-820, Page 65 Revision # 8 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 49 of 111 Rev g Comments /

Reference:

From NRC Generic Fundamentals Exam Bank Revision # 07/07 TOPIC: 191002 KNOWLEDGE: K1.14 [2.8/2.9]

QID: P213 An open circuit in a thermocouple detector causes the affected temperatur e indication to fail...

A. high. B. low.

C. to reference junction temperature.

D. as is. ANSWER: B.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 50 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 015 K1.08 Importance Rating 2.6 Nuclear Instrumentation System: Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: RCS (pump start)

Proposed Question: Common 37 Given the following conditions on Unit 2 while in MODE 3 post-trip:

Natural Circulation has not been established. A Reactor Coolant Pump start is bei ng planned per SO23-12-11, EOI Supporting Attachments, Floating Step 5, Start RCPs.

What is the concern of starting the FIRST Reactor Coolant Pump without having Natural Circulation established?

A. A rapidly rising Core Exit Temperature due to loop stagnation.

B. Indications of cavitation due to hotter suction temperatures.

C. An increase in Excore NI power indica tions due to positive reactivity addition.

D. A loss of Core Saturation Margin due to Reactor Coolant pressure transient.

Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 51 of 111 Rev g Explanation: A. Incorrect. Plausible because it could be thought that the concern was hot water being circulated when the pump was started, however, the concern is circulating diluted water through the core and this would be indicated by an increase in Excore Nuclear Instrument countrate. B. Incorrect. Plausible because it could be thought that the issue is that the water would be hotter in the pump suction and cause cavitation issues, however, the concern is circulating diluted water through the core. C. Correct. The issue of concern is positive reactivity due to diluted water. When this diluted water is swept into the core it would be detected by an increase in Excore Nuclear Instrument countrate. D. Incorrect. Plausible if thought that the issue was loss of subcooling based on the pressure transient, however, the concern is circulating diluted water through the core.

Technical Reference(s) SO23-12-11, FS-5, Step j & Note Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

55279 Per the EOI Attachments procedure, SO23-12-11, 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 5, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 52 of 111 Rev g Comments /

Reference:

From SO23-12-11, FS-5, Step j & Note Revision # 7 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 53 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 045 K3.01 Importance Rating 2.9 Main Turbine Generator System: Knowledge of the effect that a loss or malfunction of the MTG system will have on the following: Remainder of the plant Proposed Question: Common 38 Given the following conditions with Unit 3 at 100% power:

All control systems are in AUTO. The Turbine Generator trips on a Voltage Regulator card failure.

Assuming NO operator action, which of the following describes the secondary plant response immediately following the occurrence?

A. Main Steam Safety Valves OPEN; St eam Generators are fe d to the High Level Override setpoint.

B. Steam Bypass Control System Valves modulate OPEN; Main Feedwater Isolation Valves are controlled by Reactor Trip Override.

C. Main Steam Safety Valves modulate OPEN; Main Feedwater Isolation Valves CLOSE.

D. Steam Bypass Control System Valv es modulate OPEN; Main Feedwater Regulating Valves CLOSE.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that the High Level Override (HLO) signal was upstream of a Reactor Trip Override (RTO). B. Incorrect. Plausible because the SBCS Valves will modulate OPEN, however, it is the Main Feedwater and Main Feedwater Bypass Valves that are controlled by RTO. C. Incorrect. Plausible if thought that accumulation on the Main Steam Safety Valves caused them to modulate OPEN. The Main Feedwater Isolation Valves are unaffected by the conditions listed. D. Correct. The SBCS valves will modulate OPEN and the Main Feedwater Regulating Valves will CLOSE. Technical Reference(s) SO23-5-1.4, Step 6.2.13 Attached w/ Revision # See Comments / Reference SO23-3-2.18, Attachment 9, L&S 1.3 SO23-9-6, Step 6.8 SD-SO23-250, Page 77

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 54 of 111 Rev g Proposed references to be provided during examination:None Learning Objective:

06022629 PREDICT and EXPLAIN the response of major plant systems, equipment and

parameters to a Reactor Trip.

Question Source: Bank # 126732 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 55 of 111 Rev g Comments /

Reference:

From SO23-5-1.4, Step 6.2.13 Revision # 17 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 56 of 111 Rev g Comments /

Reference:

From SO23-3-2.18, Attachment 9, L&S 1.3 Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 57 of 111 Rev g Comments /

Reference:

From SO23-9-6, Step 6.8 Revision # 25 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 58 of 111 Rev g Comments /

Reference:

From SD-SO23-250, Page 77 Revision # 14

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 59 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # E02 G 2.1.31 Importance Rating 4.6 Reactor Trip - Stabilization - Recovery System: Conduct of Operations: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup Proposed Question: Common 39

A Reactor trip has occurred from 100% power and the following conditions are observed:

Pressurizer level is 28% and rising. Reactor Coolant System pressure is 2225 and rising. Reactor Coolant System T AVE is 545ºF and stable. Both Steam Generator levels are 35% and rising.

Both Steam Generator pressures are 1000 psia and stable. Assume NO operator actions and all systems respond as expected.

Given these conditions, which of the following statements de scribes the Feedwater System configuration to t he Steam Generators?

Feedwater to the Steam Generators is being supplied by...

A. Auxiliary Feedwater only.

B. Main and Auxiliary Feedwater.

C. neither system. Auxiliary Feedw ater must be manually actuated.

D. Main Feedwater only.

Proposed Answer: D Explanation: A. Incorrect. Plausible because Steam Generator levels should have fallen below the EFAS actuation setpoint, however, current level would have the AFW Valves closed. B. Incorrect. Plausible because Steam Generator levels should have fallen below the EFAS actuation setpoint, however, current level would have the AFW Valves closed and MFW Valves open. C. Incorrect. Plausible if thought that Main Feedwater was lost. Auxiliary Feedwater is actuated given pre-trip conditions; however, the AFW Valves are closed. D. Correct. Given the conditions listed, feedwater is being supplied from the Main Feedwater System.

Technical Reference(s) SO23-12-2, Steps 7 & 8 Attached w/ Revision # See Comments / Reference

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 60 of 111 Rev g Proposed references to be provided during examination:None Learning Objective:

06022629 PREDICT and EXPLAIN the response of major plant systems, equipment and

parameters to a Reactor Trip.

Question Source: Bank # 209039 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 61 of 111 Rev g Comments /

Reference:

From SO23-12-2, Steps 7 & 8 Revision # 19

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 62 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 008 AA1.08 Importance Rating 3.8 Pressurizer Vapor Space Accident: Ability to operate and/or monitor the following as they apply to the Pressurizer Vapor Space Accident: PRT level, pressure, and temperature Proposed Question: Common 40 Given the following conditions followin g a Unit trip and SIAS actuation:

Pressurizer pressure is 1720 psia and slowly LOWERING. Quench Tank pressure is 20 psig and STABLE. Pressurizer level is 28% and RISING.

Reactor Coolant System T cold is 545ºF and STABLE. Steam Generator narrow range leve ls are 21% and slowly RISING. Steam Generator pressures are 1000 psia and STABLE. Containment temperature is 125ºF and slowly RISING.

Containment pressure is 3 psig and slowly RISING.

Containment humidity is RISING.

Which of the following could be t he cause of the above conditions?

A. Reactor Coolant System Cold Leg is leaking.

B. Pressurizer steam space is leaking.

C. Pressurizer Safety Valve is leaking.

D. Steam Generator level condensing pot is leaking.

Proposed Answer: B

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 63 of 111 Rev g Explanation: A. Incorrect. Plausible because Pressurizer pressure is lowering and Containment humidity level is rising, however, Pressurizer level is also rising which would be indicative of a Pressurizer steam space leak. B. Correct. Given the conditions listed, a Pressurizer steam space leak is occurring. C. Incorrect. Plausible because Pressurizer pressure is lowering, however, Quench Tank pressure is not changing. D. Incorrect. Plausible because Containment humidity level is rising and Steam Generator levels are rising, however, if the condensing pot were leaking one would expect indicated narrow range level to be much higher and Steam Generator pressures would not be stable.

Technical Reference(s) SO23-14-10, Attachment 1, Step 3 Bases Attached w/ Revision # See Comments / Reference SO23-3-1.11, Attachment 7, L&S 1.2 SO23-3-1.11, Attachment 7, L&S 1.5 & 1.6 Proposed references to be provided during examination:None Learning Objective:

55326 Given plant conditions, PREDICT and EXPLAIN the response of containment instrumentation to adverse containment conditions during a Loss of Coolant Accident.

Question Source: Bank # 208139 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2008 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 64 of 111 Rev g Comments /

Reference:

From SO23-14-10, Attachment 1, Step 3 Bases Revision # 2 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 65 of 111 Rev g Comments /

Reference:

From SO23-3-1.11, Attachment 7, L&S 1.2, 1.5, & 1.6 Revision # 10

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 66 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 009 EK3.22 Importance Rating 4.4 Small Break LOCA: Knowledge of the reasons for the following responses as they apply to the Small Break LOCA: Maintenance of heat sink Proposed Question: Common 41 Given the following conditions:

A Small Break Loss of Coolant Accident is in progress. Safety Injection Actuat ion Signal has actuated. All systems are operat ing as expected.

Which of the following is the basis fo r maintaining a secondary heat sink?

A. To minimize boron stratificati on of the Reactor Coolant System.

B. Cooling from the injection flow al one is inadequate to remove decay heat.

C. Reflux boiling is the primary means of heat removal prior to voiding in the hot legs.

D. Minimize potential for PTS during cooldown and depressurization phase.

Proposed Answer: B Explanation: A. Incorrect. Plausible because boron stratification is a concern, however, more so during a Large Break LOCA. B. Correct. Any Reactor Coolant System pressure that remains above the shutoff head of the High Pressure Safety Injection Pumps will result in a lowering of inventory without the attendant makeup. The Steam Generators provide decay heat removal until the system is cooled down and

depressurized. C. Incorrect. Plausible because this statement is true if talking about a Large Break LOCA. D. Incorrect. Plausible because it could be thought that PTS was a concern during a Small Break LOCA, however, the concern is the ability to remove decay heat.

Technical Reference(s) SO23-14-3, Attachment 1, Section 2.0 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

91482 Per the LOCA procedure SO23-12-3, DESCRIBE the basis for each step, caution or note.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 67 of 111 Rev g Question Source: Bank # 209141 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2009 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From SO23-14-3, Attachment 1, Section 2.0 Revision # 8

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 68 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 011 EA2.11 Importance Rating 3.9 Large Break LOCA: Ability to determine and interpret the following as they apply to a Large Break LOCA: Conditions for throttling or stopping HPI Proposed Question: Common 42

Given the following conditions:

Unit 2 tripped from 100% power due to a Loss of Coolant Accident. Verification of Safety Injection Th rottle/Stop criteria is in progress. The following conditions are noted: Steam Generator E-088 level is 63% na rrow range with Auxiliary Feedwater flow available and the Atmospheric Dump Valve THROTTLED OPEN. Steam Generator E-089 level is 12% narrow range with no Auxiliary Feedwater flow available and the Atmospheric Dump Valve CLOSED. Core Exit Thermocouple temperature is 460ºF. Pressurizer pressure is 550 psia. Pressurizer level is 98% and stable. Qualified Safety Parameter Display System indicates Reactor Head level at 20%.

Which of the following criteria does NOT meet HPSI Throttle / Stop Criteria?

A. Reactor Coolant System subcooling.

B. Pressurizer level.

C. Steam Generator availability.

D. Reactor Head level.

Proposed Answer: A Explanation: A. Correct. RCS subcooling does not meet the minimum required 20ºF.

B. Incorrect. Plausible if thought that Pressurizer level is too high, however, as long as level is greater than 30% and not lowering SI Throttle / Stop Criteria is met. C. Incorrect. Plausible because one of two Steam Generators does not have feedwater available, however, only one Steam Generator is required per FS-7. D. Incorrect. Plausible if thought that Reactor Head level had to be 100%, however, it is Reactor Vessel Plenum level that must exceed that value.

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 69 of 111 Rev g Technical Reference(s) SO23-12-11, FS-7, Steps a thru e Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:Steam Tables Learning Objective: 55279 / 55339 Per the EOI Attachments procedure, SO23-12-11, DESCRIBE: The CEN-152 basis or reason for these steps. DESCRIBE the operational principles and strategies of the various attachments and floating steps of the EOIs.

Question Source: Bank # 75403 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, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 70 of 111 Rev g Comments /

Reference:

From SO23-12-11, FS-7, Steps a thru e Revision # 7 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 71 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 015/017 AK1.02 Importance Rating 3.7 RCP Malfunctions: Knowledge of the operational implications of the following concepts as they apply to RCP Malfunctions (Loss of RC Flow): Consequences of an RCP failure Proposed Question: Common 43

Given the following conditions during a Lo ss of Coolant Accident on Unit 2:

The Reactor is tripped and S023-12-1, Stan dard Post Trip Actions, is in progress Pressurizer pressure is 1425 psia and lowering. Trip Two-Leave Two Reactor Coolant Pump (RCP) Strategy is being implemented. RCP 2P001 trips but 2P004 continues to run when the STOP pushbutton is depressed.

Which of the following is the des ired method for securing the RCP?

A. Deenergize Bus 2A01 by opening the Reserve Auxiliary Transformer Supply Breaker.

B. Dispatch an operator to verify DC power is aligned to RCP 2P004 Breaker.

C. Deenergize Bus 2A01 by opening the Unit Auxiliary Transformer Supply Breaker.

D. Dispatch an operator to locally OPEN the Feeder Breakers to Buses 2A01 and 2A02. Proposed Answer: A Explanation: A. Correct. Deenergizing 2A01 will stop the RCP. This is the desired method because it stops RCS inventory loss in a timely manner. B. Incorrect. Plausible if thought that opening DC control power would trip the RCP because it is normally supplied from the other Unit (i.e., Unit 3 DC power supplies the Unit 2 RCPs). C. Incorrect. Plausible because RCPs can be operated in MODES 4 or 5 (via back feeding), however, because the Reactor is tripped, the Reserve Au xiliary Transformer is supplying RCP power. D. Incorrect. Plausible because this would stop the RCP, however, it would also trip all other RCPs.

Technical Reference(s) SO23-14-1, Attachment 1, Step 6 Attached w/ Revision # See Comments / Reference SO23-12-3, Foldout Page, Step 2 SO23-3-1.7, Attachment 16, L&S 1.11 Proposed references to be provided during examination:None ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 72 of 111 Rev g Learning Objective: 53204 / 94468 DISCUSS the major procedural actions for the following EOI concepts: Trip 2 / Leave 2 strategy INTERPRET instrumentation and controls utilized in the Reactor Coolant System. Question Source: Bank # 73912 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, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 73 of 111 Rev g Comments /

Reference:

From SO23-14-1, Attachment 1, Step 6 Revision # 8

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 74 of 111 Rev g Comments /

Reference:

From SO23-12-3, Foldout Page, Step 2 Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 75 of 111 Rev g Comments /

Reference:

From SO23-3-1.7, Attachment 16, L&S 1.11 Revision # 37

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 76 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 025 AK3.01 Importance Rating 3.1 Loss of RHR System: Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath Proposed Question: Common 44

Given the following conditions:

The Unit is in MODE 4 with the Shut down Cooling (SDC) System in service. The operating SDC Pump has become air bound.

Which of the following is the reason for venting the Shutdown Cooling Syst em prior to shifting to the standby SDC Pump when the running SDC Pump becomes air bound per SO23-13-15, Loss of Shutdown Cooling System?

A. Avoid depletion of Reactor Coolant System hydrazine.

B. The in-service SDC Heat Exchanger could become air bound.

C. The Standby SDC Pump could become air bound.

D. Prevent Steam Generator U-tube air entrapment when the standby pump is started.

Proposed Answer: C Explanation: A. Incorrect. Plausible because hydrazine may be present in the Shutdown Cooling System since it could be added as early as 220ºF per SO23-5-1.5, however, the reason is to avoid air binding of the standby pump. B. Incorrect. Plausible if thought that the SDC Heat Exchangers were configured horizontally, however, these heat exchangers are vertical. C. Correct. Per the CAUTION in SO23-13-15, Loss of Shutdown Cooling System. D. Incorrect. Plausible because given the MODE 4 condition the Steam Generator may be required as a Heat Removal Loop per Technical Specifications.

Technical Reference(s) SO23-13-15, Step 5.b RNO & Caution Attached w/ Revision # See Comments / Reference SO23-5-1.5, Step 6.9.5.2 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 77 of 111 Rev g Learning Objective:

06022703 Per the Loss of Shutdown Cooling procedure, SO23-13-15, DESCRIBE: The basis for each step, caution, or note. The expected plant response for each step.

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 5, 10 55.43 Comments /

Reference:

From SO23-13-15, Step 5.b RNO & Caution Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 78 of 111 Rev g ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 79 of 111 Rev g Comments /

Reference:

From SO23-5-1.5, Step 6.9.5.2 Revision # 31

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 80 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 022 G 2.1.19 Importance Rating 3.9 Loss of Reactor Coolant Makeup: Conduct of Operations: Ability to use plant computers to evaluate system or component status Proposed Question: Common 45

Given the following c ondition on Unit 2:

2LT-0226, Volume Control Tank Level Transmitter has failed low.

Which of the following describes the effect on the Chemical and Volume Control System (CVCS) for this failure?

A. The Refueling Water Storage Tank is a ligned to the Charging Pump suction with no override capability.

B. The Refueling Water Storage Tank is ali gned to the Charging Pump suction but can be manually realigned to t he Volume Control Tank.

C. The signal from 2LT-0226 is rejected and 2LT-0227 becomes the selected signal to prevent any spurious CVCS actuations.

D. A continuous makeup to the Volume Control Tank is in progress and will divert Letdown to Radwaste on high level.

Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 81 of 111 Rev g Explanation: A. Incorrect. Plausible if thought that the transmitter that provided indication and low level alarm, LT-0226, also provided the automatic swap to the Refueling Water Storage Tank with no override capability, however, this feature is from LT-0227 which has not failed and the swapover valving can be overridden to align to the Volume Control Tank. This condition is no longer true on Unit 2. B. Incorrect. Plausible because it could be thought that transmitter LT-0226 provided the automatic swap to the Refueling Water Storage Tank, however, this feature is from LT-0227 which has not failed. This condition is no longer true on Unit 2. C. Correct. When the Boration Distributed Control System was installed during the Cycle 16 Refueling Outage it specifically prevented failure of either VCT Level Transmitters (LT-0226 and LT-0227) from causing either VCT diversion to the RWST (LT-0227) or initiation of auto makeup (LT-0226). This signal is now averaged from both instruments and a replacement value is sent to the DCS should a transmitter fail high or low. D. Incorrect. Plausible because this is the effect of the failure on Unit 3 which is not yet equipped with the Distributed Control System. If no actions were taken to stop the makeup, the high level diversion of Letdown to Radwaste feature is from LT-0227 which did not fail.

Technical Reference(s) Lesson Plan 2RPS539, Pages 10 & 33 Attached w/ Revision # See Comments / Reference SD-SO23-390, Figure I-13 & Page 36 Proposed references to be provided during examination:None Learning Objective:

06022865 DESCRIBE the operation of the following Chemical and Volume Control System controls, including the name, function, interlocks, and location of each: VCT Level Controller.

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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 82 of 111 Rev g Comments /

Reference:

From Lesson Plan 2RPS539, Page 10 Revision # 0

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 83 of 111 Rev g Comments /

Reference:

From Lesson Plan 2RPS539, Page 33 Revision # 0

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 84 of 111 Rev g Comments /

Reference:

From Lesson Plan 2RPS539, Page 33 Revision # 0

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 85 of 111 Rev g Comments /

Reference:

From SD-SO23-390, Figure I-13 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 86 of 111 Rev g Comments /

Reference:

From SD-SO23-390, Page 36 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 87 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 027 AK2.03 Importance Rating 2.6 Pressurizer Pressure Control System Malfunction: Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners Proposed Question: Common 46 Given the following conditi on while at 100% power:

The Pressurizer Pressure Transmitter for the controlling channel fails high.

With NO operator action, which of the following is the first AUTOMATIC plant response as a result of this malfunction?

A. Both Pressurizer Spray Valves close.

B. Reactor trip due to low pressure.

C. All Pressurizer Backup Heaters energize.

D. Reactor trip due to high pressure.

Proposed Answer: B Explanation: A. Incorrect. Plausible if thought that once pressure drops below 2275 psig the Spray Valves will fully close, however, given the condition of the controlling channel, the Spray Valves remain open. B. Correct. When the Pressurizer Pressure Transmitter fails high, both Spray Valves open. This causes pressure to lower until a low pressure Reactor trip is generated. See Figure III-4 from SD-SO23-360 (attached), the Pressurizer Pressure Control Channels are separate from the Pressurizer Pressure Plant Protection System Channels. C. Incorrect. Plausible because the Pressurizer Backup Heaters would energize once pressure drops below 2200 psig, however, the Heaters are locked out when the Pressurizer Pressure Transmitter fails high at 2340 psig. D. Incorrect. Plausible if thought that when the controlling channel fails high the Reactor will trip on high pressure.

Technical Reference(s) SO23-3-1.10, Attachment 9, L&S 1.4 & 1.5 Attached w/ Revision # See Comments / Reference SD-SO23-360, Pages 82 &152; Figure III-4 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 88 of 111 Rev g Learning Objective: 06022848 / 54830 DESCRIBE the cause/effect relationships associated with the Pressurizer Pressure and Level Control System and an increasing or decreasing Pressurizer pressure and/or level. DESCRIBE the effect of a stuck open Pressurizer Spray Valve including operator actions to stop the pressure reduction.

Question Source: Bank # 75209 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2005A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /

Reference:

From SO23-3-1.10, Attachment 9, L&S 1.4 & 1.5 Revision # 22 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 89 of 111 Rev g Comments /

Reference:

From SD-SO23-360, Page 82 Revision # 18 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 90 of 111 Rev g Comments /

Reference:

From SD-SO23-360, Page 152 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 91 of 111 Rev g Comments /

Reference:

From SD-SO23-360, Figure III-4 Revision # 18

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 92 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # E05 EA2.1 Importance Rating 2.7 Excess Steam Demand: Ability to determine and interpret the following as they apply to the Excess Steam Demand: Facility conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Question: Common 47 Given the following conditions:

The plant tripped due to a Feedwat er Line Break inside Containment. Subsequently, an open Pressurizer Safety Valve is also diagnosed.

Which procedure would provide the guidance to MITIGATE the events?

A. SO23-12-1, Standard Po st Trip Actions.

B. SO23-12-3, Loss of Coolant Accident.

C. SO23-12-5, Excess Steam Demand Event.

D. SO23-12-9, Functional Recovery.

Proposed Answer: D Explanation: A. Incorrect. Plausible because SO23-12-1 contains the diagnostic flow chart to determine the correct procedure to be entered, however, it does not contain the necessary actions to mitigate both events. B. Incorrect. Plausible because during performance of Step 2, Verify LOCA Diagnosis it would be determined that two events were in progress and SO23-12-9, Functional Recovery should be entered, however, SO23-12-3 does NOT provide the guidance to mitigate both events. C. Incorrect. Plausible because if SO23-12-5 were entered, Step 2, Verify ESDE Diagnosis would determine that two events were in progress and SO23-12-9, Functional Recovery should be entered; however, SO23-12-5 does NOT provide the guidance to mitigate both events. D. Correct. Per the Entry Conditions and guidance provided in SO23-12-1, SO23-12-3, and S023-12-5, the correct procedure to enter is SO23-12-9, Functional Recovery.

Technical Reference(s) SO23-12-1, Attachment 1 Attached w/ Revision # See Comments / Reference SO23-12-3, Step 2.c SO23-12-5, Step 2.c SO23-12-9, Entry Conditions Proposed references to be provided during examination:None ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 93 of 111 Rev g Learning Objective:

06004844 DISCUSS the techniques for implementing an emergency operating instruction, including assignment of personnel, use of response not obtained column, reviewing the procedure and verifying completion of subsequent action steps.

Question Source: Bank # 127713 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 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 94 of 111 Rev g Comments /

Reference:

From SO23-12-1, Attachment 1 Revision # 22 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 95 of 111 Rev g Comments /

Reference:

From SO23-12-3, Step 2.c Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 96 of 111 Rev g Comments /

Reference:

From SO23-12-5, Step 2.c Revision # 22 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 97 of 111 Rev g Comments /

Reference:

From SO23-12-9, Entry Conditions Revision # 26

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 98 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 038 EK1.02 Importance Rating 3.2 Steam Generator Tube Rupture: Knowledge of the operational implications of the following concepts as they apply to the Steam Generator Tube Rupture: Leak rate versus pressure drop Proposed Question: Common 48 Given the following conditions:

A Steam Generator Tube Ruptur e is estimated at 250 gpm. Reactor Coolant System pressure is 2200 psia and lowering. Steam Generator pressures are 800 psia.

Pressurizer level is 37% and lowering.

The Unit is tripped and plant parameters are as follows:

Reactor Coolant System pressure is 1700 psia and lowering. Steam Generator pressures are 1000 psia. Pressurizer level is 13% and lowering.

Based on the two sets of data, which of the following describes the effect on primary-to-secondary leakage?

Leakage following the trip is approximately _____ of the initial l eak rate or about _____ gpm.

A. 10%; 25 B. 50%; 125 C. 70%; 175 D. 110%; 275 Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 99 of 111 Rev g Explanation: A. Incorrect. Plausible because this answer could be arrived at if an error is made calculating the square root of the differential pressure to determine flow rate. B. Incorrect. Plausible if thought that 1/2 of the differential pressure present would result in 1/2 of the original leak rate if a Ratio & Proportion calculation was used. C. Correct. Leak rate is proportional to the square root of the differential pressure. 1/2 of the original P will correspond to approximately 70% of the original leak rate. The operational implications of this are important when evaluating the ability to remove adequate decay heat post-trip. D. Incorrect. Plausible if thought that the leak rate would increase because Steam Generator pressure is higher.

Technical Reference(s) NRC Exam Formula Sheet Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective: 116406 / 116407 WRITE and EXPLAIN the continuity of fluid flow equation. SOLVE problems using the continuity of fluid flow equation.

Question Source: Bank # 126529 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 14 55.43 Comments /

Reference:

NRC Exam Formula Sheet Revision # N/A Square Root of Differential Pressure Calculation

Square root of 1400 psia = 37.4 psid Square root of 700 psia = 26.5 psid 26.5 / 37.4 = .708 x 250 gpm = ~175 gpm Comments /

Reference:

NRC Exam Formula Sheet Revision # N/A Ratio & Proportion Calculation

1400 psia / 700 psia = 250 gpm / x gpm 175,000 = 1400 x x = ~125 gpm

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 100 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # E06 EK2.1 Importance Rating 3.3 Loss of Feedwater: Knowledge of the interrelations between the Loss of Feedwater and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure mode s, and automatic and manual features Proposed Question: Common 49 Given the following conditions at 10% power on Unit 3:

HV-4713, Auxiliary Feedwater Pump (P-141) Discharge Isolation Valve is taken out of service for motor repairs. Subsequently, Unit 3 trips due to a Loss of Offsite Power. EFAS-1 and EFAS-2 were m anually actuated during perf ormance of Standard Post Trip Actions. Five (5) minutes post-EFAS, P-140, Turbin e Driven Auxiliary Feedwater Pump trips on overspeed.

Given the conditions above with NO operator action, which of the following describes the status of feedwater flow to the Steam Generators?

A. Main Feedwater is supplying both Steam Generators through the Main Feedwater Control Bypass Valves. Both Motor Driven Auxiliary Feedwater Pumps are running.

B. P-504 is supplying SG E-088 through HV-4712, Normal Discharge Valve and P-141 is supplying SG E-089 through HV-4763, Discharge Bypass Valve at 300 gpm.

C. P-504 is supplying SG E-088 through HV-4712, Normal Discharge Valve and P-141 is running on minimum recirc with no flow to Steam Generator E-089.

D. P-504 is supplying E-088 through HV-4712, Normal Discharge Valve and supplying Steam Generator E-089 through the cross-tie line.

Proposed Answer: C

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 101 of 111 Rev g Explanation: A. Incorrect. Plausible because it could be thought that Main Feedwater would still be available, however, a loss of vacuum has tripped the Main Feedwater Pumps. B. Incorrect. Plausible because it could be thought that HV-4763, Discharge Bypass Valve for P-141 would receive an EFAS signal to OPEN or that it was procedurally aligned when removing HV-4713, Normal Discharge Valve from service. C. Correct. HV-4763, Discharge Bypass Valve gets a CLOSE signal on EFAS and is not aligned by procedure when HV-4713, Normal Discharge Valve is removed from service. D. Incorrect. Plausible because it could be thought that with the Train A AFW out of service the procedure to remove HV-4713, Normal Discharge Valve from service would align the cross-tie line, however, this is not allowed in MODES 1 or 2.

Technical Reference(s) SD-SO23-780, Figure 1 Attached w/ Revision # See Comments / Reference SO23-2-4, Steps 6.25.1 & 6.25.2 SO23-2-4, Attachment 8, Steps 1.2 & 2.1 Proposed references to be provided during examination:None Learning Objective:

06018520 DESCRIBE the cause/effect relationships associated with the following Auxiliary Feedwater System conditions/operations: The effect on overall plant operation of a malfunction of an operating Auxiliary Feedwater Pump. The effect on overall plant operations of a failure of an AFW System electro-hydraulic valve.

Question Source: Bank # 209049 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, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 102 of 111 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 103 of 111 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 104 of 111 Rev g Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 11

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 105 of 111 Rev g Comments /

Reference:

From SO23-2-4, Section 6.25 Revision # 27 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 106 of 111 Rev g Comments /

Reference:

From SO23-2-4, Attachment 8, Steps 1.2 & 2.1 Revision # 27

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 107 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 056 AK3.02 Importance Rating 4.4 Loss of Offsite Power: Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power Proposed Question: Common 50 132389 Given the following conditions:

Unit 3 was at 100% power. A complete Loss of Offsite Power occurred 15 minutes ago. 1E Buses have been reenergized from the Emergency Diesel Generators. There are no Reactor Coolant Pumps running.

Letdown flow has been restored. Pressurizer level is 68% and slowly lowering. Pressurizer pressure is 2320 psia and slowly lowering.

Main Steam Isolation Valves are closed.

In accordance with SO23-12-7, Lo ss of Forced Circulation / Loss of Offsite Power, which of the following actions is required?

Operate the-

A. Auxiliary Feedwater Syst em to establish at least one intact Steam Generator narrow range level between 40% and 80%.

B. Auxiliary Feedwater System to est ablish 130 to 150 gpm flow to each Steam Generator for at least 5 minutes.

C. Main Feedwater System to establish at least one intact St eam Generator narrow range level between 40% and 80%.

D. Main Feedwater System and use Main St eam Safety Valves to establish Natural Circulation for decay heat removal.

Proposed Answer: A

ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 108 of 111 Rev g Explanation: A. Correct. Per SO23-13-7, Step 9.b RNO.

B. Incorrect. Plausible because AFW flow must be established, however, this requirement is only met if a Loss of Feedwater event had occurred and AFW flow was being restored. C. Incorrect. Plausible because the level range is correct, however, the MSIVs are closed and the Main Feedwater Pumps are not available. D. Incorrect. Plausible because Natural Circulation must be established on a Loss of Forced Circulation, however, with the MSIVs closed the Atmospheric Dump Valves would be placed in service per Step 9.a RNO.

Technical Reference(s) SO23-12-7, Step 9.b RNO Attached w/ Revision # See Comments / Reference SO23-12-7, Foldout Page SO23-12-6, Step 7.g RNO and 7.h Proposed references to be provided during examination:None Learning Objective:

06023125 STATE the major recovery actions in response to a LOFC/LOOP event.

Question Source: Bank # 126657 Modified Bank # (Note changes or attach parent) New Question History: Last NRC Exam SONGS 2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 109 of 111 Rev g Comments /

Reference:

From SO23-12-7, Step 9.b RNO Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 110 of 111 Rev g Comments /

Reference:

From SO23-12-7, Foldout Page Revision # 21 ES-401 SONGS NRC 2010 RO Written Exam Worksheet Form ES-401-5 Page 111 of 111 Rev g Comments /

Reference:

From SO23-12-6, Step 7.g RNO and 7.h Revision # 22

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 1 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 057 AA1.05 Importance Rating 3.2 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: Backup instrument indicationsProposed Question: Common 51 Which of the following sets of indications could be used as verification that a Loss of a Vital Bus Y01 has occurred?

A. Position indication for MCC powered ESF Channel A Valves failed on CR-57.

EFAS Trip Path 1 & 3 Auxiliary Feedwater Valves OPEN.

B. Lumigraphs for Reactor Protection System Channel A failed on CR-56.

Loss of status indicating lamps for both Reactor Protection System Status Panels.

C. Lumigraphs for Reactor Protection System Channel A failed on CR-56.

EFAS Trip Path 1 & 3 Auxiliary Feedwater Valves OPEN.

D. Position indication for MCC powered Channel A Valves failed on CR-57.

Loss of status indicating lamps for both Reactor Protection System Status Panels.

Proposed Answer: C Explanation: A. Incorrect. Plausible because EFAS Trip Path 1 and 3 Auxiliary Feedwater Valves will open, however, valve positions are provided from the Motor Control Center (MCC) 480 VAC to 120 VAC Control Transformers NOT from the Vital AC Bus. B. Incorrect. Plausible because the lumigraph information is correct, however, the status panels are associated with a loss of Y02. C. Correct. Per the conditions listed in SO23-13-18, Reactor Protection System Failure/Loss of a Vital Bus, Steps 2a & 2b. D. Incorrect. Plausible because status indicating lamps on the RPS Panels are lost but these are associated with Bus Y02 and valve positions are provided from the MCC 480 VAC to 120 VAC Control Transformers.

Technical Reference(s) SO23-13-18, Attachment 1, Step 2.2.9 Attached w/ Revision # See Comments / Reference SO23-13-18, Step 2.a SO23-13-18, Attachment 2, Step 2.2.10 Proposed references to be provided during examination:None Learning Objective: 80605 / 115111 DESCRIBE the configuration and operational characteristics of 1E 125 VDC and 120 VAC Electrical System components. As a reactor operator, RESPOND to a Loss of Vital Bus per SO23-13-18.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 2 of 111 Rev g 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 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 3 of 111 Rev g Comments /

Reference:

From SO23-13-18, Step 2.a Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 4 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 1, Step 2.2.9 Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 5 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 2, Step 2.2.10 Revision # 10

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 6 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 058 AA1.03 Importance Rating 3.1 Loss of DC Power: Ability to operate and/or monitor the following as they apply to the Loss of DC power: Vital and battery bus components Proposed Question: Common 52 Given the following condition:

Unit 2 is in MODE 1, when a Loss of DC Bus D1 occurs.

Which of the following components are a ffected and what action is required?

A. Control Power is lost to Buses 2B04 and 2B24.

If Component Cooling Water Pump P-026 needs to be started, locally operate the P-026 breaker.

B. Train A Emergency Diesel G enerator automatically starts.

Place 2G-002 EDG in MAINT LOCKOUT du e to loss of radiator cooling.

C. PV-0201A, Letdown Backpressure Control Valve fails OPEN.

Locally start Train A Charging Pumps to match Charging and Letdown flow.

D. Control Power is lost to Buses 2A04 and 2B04.

If Charging Pump P-190 needs to be started, locally operate the P-190 breaker.

Proposed Answer: D Explanation: A. Incorrect. Plausible because control power is lost to both of these 480 V buses, however, this is a Train B 4160 V load. B. Incorrect. Plausible because DC Bus D1 does provide control power to the Train A Emergency Diesel Generator and placing the EDG in MAINTENANCE LOCKOUT would be appropriate if there were a loss of radiator cooling, however, the EDG will not start. C. Incorrect. Plausible because any Train A C harging Pumps would have to be started locally, however, two of four Letdown Isolation Valves fail closed due to a loss of Instrument Air to Containment. D. Correct. A loss of DC Bus D1 results in a loss of control power to the Train A Buses. Any associated breakers that must be operated must be done so locally.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 7 of 111 Rev g Technical Reference(s) SO23-13-18, Attachment 5, Step 2.1.2.1 Attached w/ Revision # See Comments / Reference SO23-13-18, Attachment 5, Step 2.1.2.17 SO23-13-18, Attachment 6, Step 2.1.2.1 SD-SO23-120, Page 146 Proposed references to be provided during examination:None Learning Objective: 80607 / 80604 ANALYZE normal and abnormal operations of the 1E 125 VDC and 120 VAC

Electrical System. EXPLAIN the interfaces between the 1E 125 VDC and 120 VAC Electrical 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, 10 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 8 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 5, Step 2.1.2.1 Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 9 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 5, Step 2.1.2.17 Revision # 10

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 10 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 6, Step 2.1.2.1 Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 11 of 111 Rev g Comments /

Reference:

From SD-SO23-120, Page 146 Revision # 19

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 12 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 062 G 2.2.4 Importance Rating 4.5 Loss of Nuclear Service Water: Emergency Procedures/Plan: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures Proposed Question: Common 53 Given the following c onditions on Unit 2:

The following Salt Water Cooling (SWC) System Annunciators are in alarm: 64A15 - SWC TRAIN A FLOW HI/LO. 64A20 - SWC TRAIN B FLOW HI/LO.

64A34 - SWC RETURN HEADER PRESSURE HI.

Which of the following describes the conditi on that exists and the actions required?

A. A low flow condition exists due to Heat Exchanger fouling.

Initiate Reverse Flow Operations.

B. A high flow exists causing a high return pressure.

Throttle the SWC Pump Discharge Valves to reduce flow.

C. A low flow condition exis ts due to Outfall blockage. Align the discharge flowpath to the Seawall.

D. A high flow condition exists due to Outfall rupture. Align the discharge flowpath to the Seawall.

Proposed Answer: C Explanation: A. Incorrect. Plausible because it is a low flow condition and it could be thought that these were indications of fouling and reverse flow operations would be a correct action, however, the high return pressure is indicative of a blockage of flow downstream of the Heat Exchangers (HXs) and the correct action is to align the discharge to the Seawall. B. Incorrect. Plausible if thought that these were indications of high flow and throttling could reduce flow, however, the high return pressure is indicative of a blockage of flow downstream of the HXs and the correct action is to align the discharge to the Seawall. C. Correct. High return pressure is indicative of a blockage of flow downstream of the HXs and the correct action is to align the discharge to the Seawall. D. Incorrect. Plausible because the correct action is to align discharge flow to the Seawall, however, the high return pressure is indicative of a blockage of flow downstream of the HXs.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 13 of 111 Rev g Technical Reference(s) SO23-13-7, Step 16.a RNO Attached w/ Revision # See Comments / Reference SO23-15-64.A, 64A15, 64A20, 64A34 Proposed references to be provided during examination:None Learning Objective:

06022659 Using SO23-13-7, Loss of Component Cooling Water or Saltwater Cooling, 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 8, 10 55.43 Comments /

Reference:

From SO23-13-7, Step 16.a RNO Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 14 of 111 Rev g Comments /

Reference:

From SO23-15-64.A, 64A15 Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 15 of 111 Rev g Comments /

Reference:

From SO23-15-64.A, 64A20 Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 16 of 111 Rev g Comments /

Reference:

From SO23-15-64.A, 64A34 Revision # 14

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 17 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 055 EA2.02 Importance Rating 4.4 Station Blackout: Ability to determine and interpret the following as they apply to the Station Blackout: RCS core cooling through natural circulation cooling to SG cooling Proposed Question: Common 54 Which of the following statement s describes a valid criterion for Heat Removal during a Station Blackout?

Verify...

A. two-phase heat removal by monitoring REP CET temperatures maintained less than 700ºF.

B. Natural Circulation by monitoring R EP CET temperatures greater than 20ºF difference from T HOT. C. two-phase heat removal by maintaining RCS Loop T less than 68ºF.

D. Natural Circulation by maintaining Subcooled Margin less than 20ºF.

Proposed Answer: A Explanation: A. Correct. Two-phase heat removal is achiev ed by monitoring Representative Core Exit Thermocouples as long as they are less than 700ºF, otherwise, a transition to SO23-12-9, Functional Recovery would need to be made. This is an RNO action of SO23-12-8, Station Blackout. B. Incorrect. Plausible because the monitoring of Natural Circulation can be achieved using REP CET and T HOT, however, the temperature difference must be less than 16ºF. C. Incorrect. Plausible because RCS Loop T is a monitored parameter, however, it is used to assess Natural Circulation and the T must be less than 58ºF. D. Incorrect. Plausible because Subcooled Margin is a monitored parameter and it is used to assess Natural Circulation, however, it must be maintained greater than or equal to 20ºF. Technical Reference(s) SO23-12-8, Step 10 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 18 of 111 Rev g Learning Objective:

54103 EXPLAIN the purpose/bases of the following major steps (A/ERs and RNOs) of the SBO EOI, including: Two Phase Cooling.

Question Source: Bank # 73780 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 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 19 of 111 Rev g Comments /

Reference:

From SO23-12-8, Step 10 Revision # 21

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 20 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 077 AK2.02 Importance Rating 3.1 Generator Voltage and Electric Grid Disturbances: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Breakers, relays Proposed Question: Common 55

Which of the following is the r eason for maintaining a MINIMUM voltage on the 1E 480 VAC Motor Control Centers during a degraded grid condition?

A. Limit the decrease in motor speed due to slip.

B. Allow LOCAL/REMOTE indicati ng lights to be easily observed.

C. Prevent an undervoltage trip of valve operator motor feeder breakers.

D. Ensure sufficient voltage available to operate motor contactor (42) relay coils.

Proposed Answer: D Explanation: A. Incorrect. Plausible because motor speed could be impacted, however, this is usually a result of a lower frequency. B. Incorrect. Plausible if thought that this was a valid reason for minimum voltage. C. Incorrect. Plausible if thought that an undervoltage trip existed, however, this would be associated with a Bus vice an MCC breaker. D. Correct. Insufficient 480 Motor Control Center (MCC) voltage will result in a lower output voltage from the 480/120 VAC Control Power Transformer. This lower voltage may be insufficient to operate motor contactor relays.

Technical Reference(s) DBD-SO23-120, Page 217 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

115956 / 115958 DEFINE the following terms as they relate to circuit breakers: Control power DESCRIBE the controls and indications on typical 4160V and 480V circuit breakers.

Question Source: Bank # 209056 Modified Bank #

(Note changes or attach parent) New ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 21 of 111 Rev g Question History: Last NRC Exam

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 22 of 111 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments /

Reference:

From DBD-SO23-120, Page 217 Revision # 7

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 23 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 029 G 2.1.7 Importance Rating 4.4 ATWS: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Proposed Question: Common 56 Given the following c onditions on Unit 2:

The following Annunciators are in alarm: 50A05 - T AVG HI. 50A07 - SBCS DEMAND PRESENT. 50A10 - CEDMCS CEA WITHDRAWAL PROHIBIT.

50A14 - PZR PRESS HI/LO.

50A15 - HOT LEG LOOP 1 TEMP HI. 50A16 - HOT LEG LOOP 2 TEMP HI. 50A17 - COLD LEG LOOP 1 TEMP HI.

50A18 - COLD LEG LOOP 2 TEMP HI.

56A14 - DNBR LO RPS PRETRIP. 56A15 - PZR PRESS HI PRETRIP. Pressurizer pressure is 2390 psia. All Reactor Trip Breakers are closed.

Steam Generator levels ar e 65% narrow range and rising.

Which of the following describes the event in progress and the action required?

A. A partial loss of load has occurred. R apidly reduce power per SO23-13-28, Rapid Power Reduction.

B. A Dilution event is ongoing. Commence an Emergency Boration per SO23-13-11, Emergency Boration.

C. An Anticipated Transient Without Scram has occurred. Manually trip the Reactor and enter SO23-12-1, Standard Post Trip Actions.

D. An Excessive Feed Event is occurring.

Take manual control of Feedwater Control Valves and stabilize Steam Generator levels.

Proposed Answer: C

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 24 of 111 Rev g Explanation: A. Incorrect. Plausible because a loss of load has occurred, however, the Reactor trip should have occurred and the correct action is to trip the Reactor and enter SO23-12-1, SPTAs. B. Incorrect. Plausible because most of the indications could point to a dilution event except for Steam Generator level, however, the Reactor trip should have occurred and the correct action is to trip the Reactor and enter SO23-12-1, SPTAs. C. Correct. A high Pressurizer Pressure trip condition exists at 2375 psia. D. Incorrect. Plausible because it could be thought that the rising Steam Generator level was creating a positive reactivity condition that caused these indications, however, an over feed event would result in lower Reactor Coolant temperatures and pressures.

Technical Reference(s) SO23-15-56A, 56A05 Attached w/ Revision # See Comments / Reference SO123-0-A1, Step 6.1.3.7 SO123-0-A2, Step 6.9.1.1 Proposed references to be provided during examination:None Learning Objective:

06023787 Given an operational condition of the ATWS/DSS System addressed by a procedural precaution, limitation, or administrative requirement, STATE the limiting condition and the basis for that limiting 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 5, 6, 10 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 25 of 111 Rev g Comments /

Reference:

From SO23-15-56A, 56A05 Revision # 8 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 26 of 111 Rev g Comments /

Reference:

From SO123-0-A1, Step 6.1.3.7 Revision # 26 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 27 of 111 Rev g Comments /

Reference:

From SO123-0-A2, Step 6.9.1.1 Revision # 20

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 28 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 074 EA2.07 Importance Rating 4.1 Inadequate Core Cooling: Ability to determine and interpret the following as they apply to an Inadequate Core Cooling: The difference between a LOCA and inadequate core cooling, from trends and indicators Proposed Question: Common 57

Which of the following is an indication of Inadequate Core Cooling as defined in the Emergency Operating Instructions?

A. Loss of RCS subcooling. Reactor Vessel Level Monitoring System indicating the lowest detector in the Plenum is uncovered.

B. RCS Loop temperatures rising. Pressurizer level lowering when High Pressure Safety Injection is throttled.

C. Pressurizer level lowering when High Pr essure Safety Injection is throttled and Core Exit Temperatures rising.

D. Pressurizer pressure stabilizing as level reaches 100%. Reactor Vessel Level Monitoring System is indicating level rising in the upper Head.

Proposed Answer: A Explanation: A. Correct. A loss of Reactor Coolant System subcooling coupled with an empty Plenum would be indicative of an Inadequate Core Cooling condition independent of the situation that caused it. B. Incorrect. Plausible because Reactor Coolant System Loop temperatures are rising, however, if Pressurizer level lowers when HPSI flow is throttled this is an indication of a Loss of Coolant Accident as opposed to Inadequate Core Cooling. C. Incorrect. Plausible because Pressurizer level is lowering when HPSI flow is throttled and Core Exit Temperatures are rising, however, if Pressurizer level decreases when HPSI flow is throttled this is an indication of a Loss of Coolant Accident as opposed to Inadequate Core Cooling. D. Incorrect. Plausible because the Pressurizer bubble may have shifted to the Head, however, this would not be an indication of Inadequate Core Cooling.

Technical Reference(s) SO23-14-7, Attachment 1, Step 11 Attached w/ Revision # See Comments / Reference SO23-14-7, Attachment 1, 4.4.11.e SO23-14-10, Attachment 1, Step 4.14 Proposed references to be provided during examination:None Learning Objective:

06023013 PREDICT and EXPLAIN the response of major plant systems, equipment and parameters to a loss of forced circulation.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 29 of 111 Rev g Question Source: Bank # 75561 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2000 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 30 of 111 Rev g Comments /

Reference:

From SO23-14-7, Attachment 1, Step 11 Revision # 7

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 31 of 111 Rev g Comments /

Reference:

From SO23-14-7, Attachment 1, Step 4.4.11.e Revision # 7 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 32 of 111 Rev g Comments /

Reference:

From SO23-14-10, Attachment 1, Step 4.14 Revision # 2

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 33 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 028 AK3.05 Importance Rating 3.7 Pressurizer Level Malfunction: Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunction: Actions contained in EOP for PZR level malfunction Proposed Question: Common 58 Given the following conditions during a power ascension:

Pressurizer Level is on program at 45%. SO23-3-1.10, Pressurizer Pressure and Level Control, Forcing Pressurizer Sprays is in progress using all Non-1E Pressurizer Heaters. Pressurizer Level Control Channel Y is selected. Pressurizer Level Control Channel Y failed to 20%.

LIC-0110, Pressurizer Level Controller was placed in MANUAL.

All other switches are in their normal configuration.

Which of the following is the reason for controlling Pressurizer Heaters per SO23-13-27, Pressurizer Pressure and Level Malfunction?

When Channel X is selected, No n-1E Pressurizer Heaters...

A. will automatically reenergize because they were in AUTO.

B. must be manually reenergized because they tripped on low Pressurizer level.

C. will automatically reenergize because Pressurizer Spray flow is being forced.

D. must be manually reenergized because devia tion from setpoint is greater than 6%.

Proposed Answer: B Explanation: A. Incorrect. Plausible because this would occur if the PZR Heaters had not tripped given that forcing Sprays is in progress. B. Correct. The low level heater cutout has tripped all PZR Heaters at 23%, they must be manually controlled. C. Incorrect. Plausible because forcing PZR Sprays is in progress, however, the PZR Heaters deenergized when level dropped below 23% and must be manually reset. D. Incorrect. Plausible because certain Pressurizer level control actions are generated on level deviation, however, a 6% deviation would start all Backup Charging Pumps.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 34 of 111 Rev g Technical Reference(s) SO23-13-27, Steps 2.c & Step 2.h.6) Attached w/ Revision # See Comments / Reference SO23-13-27, Attachment 2 SO23-3-1.10, Step 6.3 Proposed references to be provided during examination:None Learning Objective:

55219 DESCRIBE the Pressurizer Level Control System expected response to Pressurizer level transient and the required operator action if the expected plant response is not obtained in accordance with SO23-13-27.

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 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 35 of 111 Rev g Comments /

Reference:

From SO23-13-27, Step 2.c Revision # 4 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 36 of 111 Rev g Comments /

Reference:

From SO23-13-27, Step 2.h.6)

Revision # 4 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 37 of 111 Rev g Comments /

Reference:

From SO23-13-27, Attachment 2 Revision # 4

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 38 of 111 Rev g Comments /

Reference:

From SO23-3-1.10, Step 6.3 Revision # 22

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 39 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 005 AK2.03 Importance Rating 3.1 Inoperable/Stuck Control Rod: Knowledge of the interrelations between the Inoperable/Stuck Control Rod and the following:

Metroscope Proposed Question: Common 59 Given the following condition:

Regulating Group 6 CEAs wi ll be inserted 6 steps from the All Rods Out (ARO) position.

Which of the following indications would be used to determine if a CEA becomes immovable?

A. Reed Switch indication from the Rod Position CRT Display.

B. Pulse Counter information fr om the Plant Co mputer System.

C. Core Mimic Display from the Main Control Board.

D. Pulse Counter information fr om the CEA Operator Module.

Proposed Answer: A Explanation: A. Correct. Only the Reed switch indication will provide information regarding a stuck CEA. B. Incorrect. Plausible because Pulse Counter is available from the Plant Computer System (PCS), however, Pulse Counter does not indicate actual steps moved, only pulses sent to the CEAs. C. Incorrect. Plausible because the Core Mimic Display is Reed Switch driven, however, the only information provided is dropped CEA position. D. Incorrect. Plausible because Pulse Counter information originates from the CEA Operator Module, however, the Pulse Counter would indicate that demand to move the CEA was sent but does not relay actual CEA position.

Technical Reference(s) SD-SO23-510, Figures 11 & 12A Attached w/ Revision # See Comments / Reference Technical Specification LCO 3.1.5 Bases SD-SO23-510, Pages 7 & 58 Proposed references to be provided during examination:None Learning Objective:

81788 INTERPRET instrumentation and controls utilized in the Control Element Drive Mechanism Control System (CEDMCS).

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 40 of 111 Rev g 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 6 55.43 Comments /

Reference:

From SD-SO23-510, Page 7 Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 41 of 111 Rev g Comments /

Reference:

From SD-SO23-510, Page 58 Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 42 of 111 Rev g Comments /

Reference:

From Technical Specification LCO 3.1.5 Bases Amendment # 127 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 43 of 111 Rev g Comments /

Reference:

From SD-SO23-510, CEA Operator Module Revision # 10 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 44 of 111 Rev g Comments /

Reference:

From SD-SO23-510, Secondary Rod Position CRT Display Revision # 10

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 45 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 036 AA1.02 Importance Rating 3.1 Fuel Handling Accident: Ability to operate and/or monitor the following as they apply to the Fuel Handling Incidents: ARM system Proposed Question: Common 60

Given the following conditions with Unit 2 in MODE 6:

During fuel inspection activities, the fuel inspection device was raised out of the Spent Fuel Pool. 2RE-7850, Fuel Handling Building Area Radiation Monitor has exceeded the alarm setpoint. 2RE-7822 and 2RE-7823, Fuel Handling Bu ilding Ventilation Airborne Monitors have NOT exceeded their alarm setpoints.

Which of the following statements describes the system response?

A. Fuel Handling Isolation Signal (FHIS) is generated.

B. Data Acquisition System (DAS) alarm is received in the Control Room.

C. Upward motion of the New Fuel Elevator is automatically stopped.

D. Emergency Response Data System (ERDS) signal is activated to Sacramento.

Proposed Answer: B Explanation: A. Incorrect. Plausible because it could be thought that an FHIS would be generated, however, the Process Radiation Monitors must detect high radiation. B. Correct. A DAS alarm is received in the Control Room. C. Incorrect. Plausible because the New Fuel Elevator does have an interlock that prevents upward motion, however, only when a fuel assembly is placed inside of it. D. Incorrect. Plausible because a signal is sent to the ERDS from the DAS, however, this system must be activated manually in the Control Room. Additionally ERDS is sent to the NRC whereas SOES is sent to Sacramento.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 46 of 111 Rev g Technical Reference(s) SD-SO23-690, Figure 15 Attached w/ Revision # See Comments / Reference SO23-3-2.32, Attachment 1, Step 2.14 SD-SO23-690, Page 7 SD-SO23-430, Page 34 SO23-13-18, Attachment 1, Step 2.2.16 Proposed references to be provided during examination:None Learning Objective:

06024294 Given indications of a refueling accident, DETERMINE the action required per SO23-13-20 and EXPLAIN the basis for the actions taken.

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 11 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 47 of 111 Rev g Comments /

Reference:

From SD-SO23-690, Figure 15 Revision # 16

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 48 of 111 Rev g Comments /

Reference:

From SO23-3-2.32, Attachment 1, Step 2.14 Revision # 11 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 49 of 111 Rev g Comments /

Reference:

From SD-SO23-690, Page 7 Revision # 16 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 50 of 111 Rev g Comments /

Reference:

From SD-SO23-430, Page 34 Revision # 13 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 51 of 111 Rev g Comments /

Reference:

From SO23-13-18, Attachment 1, Step 2.2.16 Revision # 10

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 52 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 060 AK3.02 Importance Rating 3.3 Accidental Gaseous Radwaste Release: Knowledge of the reasons for the following responses as they apply to the Accidental Gaseous Radwaste Release: Isolation of the auxiliary building ventilation.

Proposed Question: Common 61 Given the following conditions:

A planned release of T-086, Waste Gas Decay Tank is in progress. A high spike occurs on 2RE-7865, Wide Range Gas Monitor. 2/3HV-7202, Waste Gas Discharge Is olation Valve failed to close.

Which of the following would result in the closing of 2/3HV-7202, Waste Gas Discharge Isolation Valve?

A. LOSS of both Radwaste Area Exhaust Fans (A192 and A193).

B. RAISE 2/3RE-7808, Plant Vent Stack Wide Range Monitor setpoint at the Data Acquisition System.

C. LOSS of all Continuous Exhaus t Fans (A310, A311 and A312).

D. INITIATING a Containment Purge Isolation Signal.

Proposed Answer: C Explanation: A. Incorrect. Plausible because the Radwaste Area Exhaust Fans discharge to the Continuous Exhaust Plenum and it could be thought that low flow would trip the Continuous Exhaust Fans. B. Incorrect. Plausible because 2/3RE-7808 is interlocked to close 2/3HV-7202, Waste Gas Discharge Isolation Valve, however, raising the setpoint will NOT close the valve. C. Correct. Loss of the Continuous Exhaust Fans will close 2/3HV-7202, Waste Gas Discharge Isolation Valve. D. Incorrect. Plausible because 2RE-7865, Wide Range Gas Monitor can be aligned to initiate a CPIS, however, this action will not secure 2/3HV-7202.

Technical Reference(s) SD-SO23-660, Figure 1A Attached w/ Revision # See Comments / Reference SD-SO23-622, Figure I-1 Proposed references to be provided during examination:None

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 53 of 111 Rev g Learning Objective:

81529 ANALYZE normal and abnormal operations of the Radwaste, Penetration, and Safety Equipment Building HVAC System.

Question Source: Bank # 209064 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2009 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 13 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 54 of 111 Rev g Comments /

Reference:

From SD-SO23-660, Figure 1A Revision # 8

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 55 of 111 Rev g Comments /

Reference:

From SD-SO23-622, Figure I-1 Revision # 3

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 56 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 003 AK1.04 Importance Rating 3.1 Dropped Control Rod: Knowledge of the operational implications of the following concepts as they apply to the Dropped Control Rod: Effects of power level and control position on flux Proposed Question: Common 62 With Unit 3 at 100%, which of the following is the reason for lowering power level within 15 minutes following a dropped Control Element Assembly?

A. Prevent Azimuthal Power Tilt from ex ceeding the CPC Auxiliary Trip setpoint.

B. Increase the margin to Departure from Nucleate Boiling.

C. Minimize Axial Shape Index induced flux redistribution.

D. Offset the burnout of xenon and its detrimental effe cts on power distribution.

Proposed Answer: B Explanation: A. Incorrect. Plausible because Azimuthal Power Tilt is in an addressable constant in the Core Protection Calculator, however, there is no CPC trip setpoint associated with Azimuthal Power Tilt. B. Correct. Lowering power level will increase the margin to Departure from Nucleate Boiling.

C. Incorrect. Plausible because ASI is affected by the downpower, however, the reason is to increase the margin to Departure from Nucleate Boiling. D. Incorrect. Plausible because Xenon is a consideration, however, it is the build in of Xenon that is the concern.

Technical Reference(s) Lesson Plan 2A0713, Page 3 Attached w/ Revision # See Comments / Reference Lesson Plan 2XCR02, Pages 85 & 102 Proposed references to be provided during examination:None Learning Objective: 116112 / 116118 DESCRIBE the effects of control rods on power peaking or hot-channel factors. EXPLAIN the effects of full and/or partial length rods on flux distribution (I). Question Source: Bank #

Modified Bank #

(Note changes or attach parent) New X Question History: Last NRC Exam

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 57 of 111 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 1 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 58 of 111 Rev g Comments /

Reference:

From Lesson Plan 2A0713, Page 3 Revision # 6-5

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 59 of 111 Rev g Comments /

Reference:

From Lesson Plan 2XCR02, Page 85 Revision # 2-1 Comments /

Reference:

From Lesson Plan 2XCR02, Page 102 Revision # 2-1 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 60 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 051 AK3.01 Importance Rating 2.8 Loss of Condenser Vacuum: Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum Proposed Question: Common 63 Given the following conditions while per forming a Heat Treat ment on Unit 3:

The following Annunciators have alarmed in the order listed: Annunciator 99B37 - VACUUM LO. Annunciator 99B17 - VACUUM LO PRETRIP. SO23-13-10, Loss of Condenser Vacuum has been entered. Main Condenser backpressure degrades to 10.5" Hg backpressure.

What is the effect on Steam Bypass Control System (SBCS) operation?

A. SBCS is disabled due to low Condenser vacuum.

B. SBCS "QUICK OPEN" act uation is blocked but "MODULATE" operation is still enabled. C. Vacuum is not degraded enough to have an effect or require any actions.

D. SBCS "EMERGENCY OFF" is disabl ed until vacuum lowers to 3.5" Hg backpressure.

Proposed Answer: A Explanation: A. Correct. When Condenser pressure lowers below 10" Hg backpressure, the interlock for system operation on low vacuum is actuated. B. Incorrect. Plausible if thought that a lowered vacuum would allow the valves to MODULATE but not let them QUICK OPEN given conditions within the Condenser, however, the entire system is disabled. C. Incorrect. Plausible because an error could be made in the calculation and one could think that there was > 20" Hg vacuum which would allow system operation. D. Incorrect. Plausible because depressing the EMERGENCY OFF pushbutton will close the SBCS Valves should they open spuriously, however, in this case the RESET pushbutton is disabled until vacuum improves.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 61 of 111 Rev g Technical Reference(s) SO23-3-2.18, Steps 6.3.2 & 6.3.5 Attached w/ Revision # See Comments / Reference SD-SO23-175, Pages 21 & 25 Proposed references to be provided during examination:None Learning Objective: 102485 / 06022559 ANALYZE normal and abnormal operations of the Main Steam System. DESCRIBE the operation of the Steam Bypass Control System controls.

Question Source: Bank #

Modified Bank #73325 (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 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 62 of 111 Rev g Comments /

Reference:

From SO23-3-2.18, Step 6.3 Revision # 21 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 63 of 111 Rev g Comments /

Reference:

From SD-SO23-175, Page 21 Revision # 7 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 64 of 111 Rev g Comments /

Reference:

From SD-SO23-175, Page 25 Revision # 7 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 65 of 111 Rev g Comments /

Reference:

From Exam Bank #73325 Revision # 06/23/03 While performing a heat treat on Unit 3, the condenser low vacuum alarm is received. You note that main condenser backpressure is 5.8" Hg abs. What effect should this condition have on Steam Bypass Control System (SBCS) operation? A. SBCS is disabled due to low Condenser vacuum.

B. SBCS "quick-open" actuation is blocked but "modulate" operation is still enabled. C. Vacuum is not degraded enough to have an effect or require any actions.

D. SBCS "Emergency Off" should be depressed to prevent system operation.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 66 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 037 G 2.1.7 Importance Rating 4.4 Steam Generator Tube Leak: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretations Proposed Question: Common 64 Given the following conditions on Unit 3 at 100% power:

A Steam Generator Tube Leak has been id entified on Steam Generator E-088. SO23-13-14, RCS Leak, Attachment 1, RT-7870 Steam Generator Leakage in Radiation Readings, is being performed to determine the size of the leak. Condenser Vacuum Pump, P-054, was just started per Attach ment 3, Minimizing Contamination during a St eam Generator Tube Leak.

With respect to RE-7870, Condenser Air Ejector Wide Range Gas Monitor, what is the effect of starting P-054?

A. Operation of RT-7870 will be unaffected by the Condenser Vacuum Pump because A-361, Air Ejector Exhaust Unit, automatically shifts to DIRECT.

B. RE-7870 readings are not valid until the Condenser Vacu um Pump has run for at least 15 minutes.

C. Actual leak rate cannot be determined until the grid is re-scaled on the Data Acquisition System Leak Rate Page.

D. RE-7870 setpoint on the Data Acquisition System is raised to the maximum allowable value established in the Offsite Dose Calculation Manual.

Proposed Answer: B Explanation: A. Incorrect. Plausible because a substitute value is installed, however, this is done to RT-7818, Condenser Air Ejector Low Range Radiation Monitor. B. Correct. Per the note in Attachment 1.

C. Incorrect. Plausible because the Data Acquisition System Leak Rate Page created does re-scale, however, this process is done automatically. D. Incorrect. Plausible because this action is performed in Attachment 3, however, it is done to RE-7821, Turbine Plant Sump Radiation Monitor in preparation for discharging.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 67 of 111 Rev g Technical Reference(s) SO23-13-14, Attachments 1, Step 2.1 Note Attached w/ Revision # See Comments / Reference SO23-13-14, Attachments 2, Step 2.1 Note SO23-13-14, Attachment 3, Step 2.1.1 SO23-13-14, Attachment 3, Step 2.1.13 Proposed references to be provided during examination:None Learning Objective:

06022695 Per the Reactor Coolant Leak procedure, SO23-13-14, 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, 11, 13 55.43 Comments /

Reference:

From SO23-13-14, Attachment 1, Step 2.1 Note Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 68 of 111 Rev g Comments /

Reference:

From SO23-13-14, Attachment 2, Step 2.1 Note Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 69 of 111 Rev g Comments /

Reference:

From SO23-13-14, Attachment 3, Step 2.1.1 Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 70 of 111 Rev g Comments /

Reference:

From SO23-13-14, Attachment 3, Step 2.1.13 Revision # 14

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 71 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 067 AK1.02 Importance Rating 3.1 Plant Fire on Site: Knowledge of the operational implications of the following concepts as they apply to the Plant Fire on Site:

Fire fighting Proposed Question: Common 65 During active fire fighting efforts inside the Pr otected Area, which of the following is the earliest a fire could be considered "EXTINGUIS HED" by the Fire Incident Commander as defined in plant procedures?

A. The fire has been completely contained.

Heat and visible flame are present, but the affected area is being continually reduced by the applic ation of extinguishing agents. B. Combustion appears to have stopped completely. No heat is being produced and no light is being emitted from the fire's source, but some smoke is still present.

C. The fire is contained and controlled. Heat, smoke and glowing embers are present but there is no longer any visible flame.

D. Combustion appears to have stopped comp letely. There is heat and smoke being produced; however, the smoke in the area is being evacuated.

Proposed Answer: B Explanation: A. Incorrect. Plausible because the fire should be contained, however, heat and visible flame are indications that the fire has not been extinguished. B. Correct. As defined in SO23-13-21, Fire.

C. Incorrect. Plausible because the fire should be contained and controlled, however, heat and glowing embers would be an indication that the fire has not been extinguished. D. Incorrect. Plausible because some indications listed are correct, however, smoke need not be evacuated from the area to consider the fire extinguished.

Technical Reference(s) SO23-13-21, Step 4.11, Note Attached w/ Revision # See Comments / Reference SO23-13-21, Step 4.1, Note Proposed references to be provided during examination:None Learning Objective:

54227 Given a Fire Scenario in the protected area, DESCRIBE the duties and responsibilities of the Fire Technical Advisor and the Fire Department Incident Commander per SO23-13-21 and SO123-0-A2.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 72 of 111 Rev g Question Source: Bank # 209063 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 55.43 Comments /

Reference:

From SO23-13-21, Step 4.11, Note Revision # 17 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 73 of 111 Rev g Comments /

Reference:

From SO23-13-21, Step 4.1, Note Revision #17

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 74 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 1 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 66 On the Critical Functions Monitoring System (CFMS) display screen, which of the following is indicated by a numerical value replaced by a magenta colored "BD"?

A. A parameter which is out of range.

B. More information is available.

C. Total CFMS failure has occurred.

D. A request for input from the operator.

Proposed Answer: A Explanation: A. Correct. As described in SO23-3-2.32, Critical Functions Monitoring System Operation. B. Incorrect. Plausible because this is available from CFMS, however, it is represented by the colors blue & light blue. C. Incorrect. Plausible because this condition could exist, however, it is preceded by Annunciator alarm 63B12 - CFMS/QSPDS INPUT OR HARDWARE TROUBLE. D. Incorrect. Plausible because CFMS data can be inputted, however, there is not a color associated with it. Technical Reference(s) SO23-3-2.32, Attachment 1, Section 2.6 Attached w/ Revision # See Comments / Reference SO23-3-2.32, Attachment 1, Section 2.8 SO23-15-63.B, 63B12 Proposed references to be provided during examination:None Learning Objective:

06023553 ANALYZE normal and abnormal operation of the Accident Monitoring System, including alarms, limiting conditions and actions required.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 75 of 111 Rev g 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 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 76 of 111 Rev g Comments /

Reference:

From SO23-3-2.32, Attachment 1, Section 2.6 Revision # 11 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 77 of 111 Rev g Comments /

Reference:

From SO23-3-2.32, Attachment 1, Section 2.8 Revision # 11 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 78 of 111 Rev g Comments /

Reference:

From SO23-15-63.B, 63B12 Revision # 13

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 79 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.30 Importance Rating 4.4 Conduct of Operations: Ability to locate and operate components, including local controls Proposed Question: Common 67 Given the following conditions:

Unit 2 is recovering from a dropped CEA. Prior to withdrawing the CEA, Annunciator 50A40 - CEDMCS TIMER FAILURE needs to be reset by actuating the ACTM Manual Transfer Switch for the dropped CEA.

Which of the following describes the location of the controls and the system response when the ACTM Manual Transfer Switch for the dropped CEA is actuated?

Dispatch an operator to...

A. 37' Radwaste Building, Control Element Drive Mechanism Control System Room. The CEA is transferred to the Upper Gripper and all flags are reset.

B. 30' Control Building, 2L-91, Contro l Element Assembly Calculators. The CEA is transferred to the Lower Gripper and all flags are reset.

C. 37' Radwaste Building, Control Element Drive Mechanism Control System Room.

The CEA and it associated Subgroup is transferred to the Hold Bus.

D. 30' Control Building, 2L-91, Contro l Element Assembly Calculators.

The CEA and it associated Subgroup is transferred to the Hold Bus.

Proposed Answer: A

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 80 of 111 Rev g Explanation: A. Correct. This is the correct location and response that is performed.

B. Incorrect. Plausible because the CEA is transferred, however, it is transferred to the Upper Gripper and the location is incorrect. C. Incorrect. Plausible because the location is correct and the individual CEA is placed on the Hold Bus, however, operating the ACTM Manual Transfer Switch only places the associated CEA on the Hold Bus. D. Incorrect. Plausible because the individual CEA is placed on the Hold Bus, however, operating the ACTM Manual Transfer Switch only places the associated CEA on the Hold Bus and the location is incorrect.

Technical Reference(s) SO23-3-2.19, Attachment 8, Steps 2.7 & 2.8Attached w/ Revision # See Comments / Reference SO23-15-50.A2, 50A40 Proposed references to be provided during examination:None Learning Objective:

06022688 Per the misaligned CEA procedure, SO23-13-13, DESCRIBE: The basis for each step, caution, or note. The expected plant response for each step.

Question Source: Bank # 209057 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 6, 7 55.43 Comments /

Reference:

From SO23-3-2.19, Attachment 8, Steps 2.7 & 2.8 Revision # 23 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 81 of 111 Rev g ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 82 of 111 Rev g Comments /

Reference:

From SO23-15-50.A2, 50A40 Revision # 13

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 83 of 111 Rev g Comments /

Reference:

From SO23-15-50.A2, 50A40 Revision # 13

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 84 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.22 Importance Rating 4.0 Equipment Control: Knowledge of limiting conditions for operations and safety limits Proposed Question: Common 68 Which of the following states the required action(s) for Pressurizer Pr essure exceeding 2750 psia in MODES 1 or 2?

A. Restore Compliance within five (5) minutes.

B. Restore Compliance and be in MODE 3 within one (1) hour.

C. Request Compliance Division to notify the NRC within four (4) hours.

D. Restore Compliance and be in MODE 3 within seven (7) hours.

Proposed Answer: B Explanation: A. Incorrect. Plausible because this is the required ACTION for MODES 3, 4, or 5.

B. Correct. Per Technical Specification Safety Limit 2.1.2.

C. Incorrect. Plausible because the NRC must be notified, however, it is within one (1) hour.

D. Incorrect. Plausible because this is the required ACTION for LCO 3.0.3.

Technical Reference(s) Technical Specification Safety Limit 2.1.2 Attached w/ Revision # See Comments / Reference Technical Specification LCO 3.0.3 Proposed references to be provided during examination:None Learning Objective: 55688 / 56437 DESCRIBE the general arrangement, format, and use of the Technical Specifications. DESCRIBE or SUMMARIZE the basic format and terminology used in the Technical Specifications and Licensee Controlled Specifications, including: Safety Limits Question Source: Bank # 208047 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 85 of 111 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From Technical Specification Safety Limit 2.1.2 Amendment # 207 Comments /

Reference:

From Technical Specification Safety Limit 2.1.2 Amendment # 207 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 86 of 111 Rev g Comments /

Reference:

From Technical Specification LCO 3.0.3 Amendment # 207

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 87 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.13 Importance Rating 4.1 Equipment Control: Knowledge of tagging and clearance procedures Proposed Question: Common 69 Which of the following tags is hung on a tem porary power supply during a Motor Control Center outage?

A. Clearance.

B. In-Test.

C. Caution.

D. Permission.

Proposed Answer: C Explanation: A. Incorrect. Plausible because a Clearance can be used for electrical work, however, only if equipment is deenergized. B. Incorrect. Plausible because In-Test Tags would be used for electrical equipment, however, not for this application. C. Correct. As outlined in the CAUTION of SO123-XX-5.1, Attachment 5, Manual Work Authorization Record Modification Permit. The Caution Tag would include the Work Authorization Number and breaker position. D. Incorrect. Plausible because Permission Tags do exist, however, not for this application.

Technical Reference(s) SO123-XX-5.1, Attachment 5, Step 6.c Attached w/ Revision # See Comments / Reference SO123-XX-5, Sections 6.5, 6.6, & 6.9 Proposed references to be provided during examination:None Learning Objective:

06024285 Given conditions, DETERMINE the action required in response to the stated conditions involving the preparation, issuance, release or restoration from a work authorization per SO123-XX-5.

Question Source: Bank # 142989 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 88 of 111 Rev g Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From SO123-XX-5.1, Attachment 5, Step 6.c Revision # 18 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 89 of 111 Rev g Comments /

Reference:

From SO123-XX-5, Section 6.6 Revision # 28 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 90 of 111 Rev g Comments /

Reference:

From SO123-XX-5, Section 6.9 Revision # 28 Comments /

Reference:

From SO123-XX-5, Section 6.9 Revision # 28 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 91 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.2 Importance Rating 4.6 Equipment Control: Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels Proposed Question: Common 70 Given the following conditions:

CEA Group 5 is being withdrawn from 108 inches to 123 inches. At 112 inches on Group 5, the CEDM CS Control Switch is released. CEA #14 and #15 motion STOPS. CEA #16 and #17 CONTINUE to withdraw. All CEA motion is terminated by placing CEDMCS in OFF. CEA #16 and #17 indicate 123 inches.

Which of the following is required and what is the reason for that action?

A. Reduce thermal power to limits specified in the COLR within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to preclude operation outside of DNBR limits.

B. Restore Group 5 alignment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by withdrawing CEAs 14 and 15 in MANUAL INDIVIDUAL to prevent exceeding AZTILT limits.

C. Restore Group 5 alignment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by inserting CEA 16 and 17 using MANUAL INDIVIDUAL to preclude excessive power peaking.

D. Immediately trip the Reactor to pr eclude operation outside of a design basis condition.

Proposed Answer: D Explanation: A. Incorrect. Plausible because DNBR limits could be exceeded, however, a Reactor Trip is required. B. Incorrect. Plausible because Azimuthal Tilt limits could be exceeded, however, a Reactor Trip is required. C. Incorrect. Plausible because power peaking limits could be exceeded, however, a Reactor Trip is required. D. Correct. With two CEAs misaligned greater than 7 inches, a Reactor trip is required.

Technical Reference(s) SO23-13-13, Step 1.b RNO Attached w/ Revision # See Comments / Reference SO23-15-50.A1, 50A28 Technical Specification LCO 3.1.5 Bases ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 92 of 111 Rev g Proposed references to be provided during examination:None Learning Objective:

06022688 Per the misaligned CEA procedure, SO23-13-13, DESCRIBE: The basis for each step, caution, or note.

Question Source: Bank # 126620 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From SO23-13-13, Step 1.b RNO Revision # 12 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 93 of 111 Rev g Comments /

Reference:

From SO23-15-50.A1, 50A28 Revision # 8 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 94 of 111 Rev g Comments /

Reference:

From Technical Specification LCO 3.1.5 Bases Amendment # 127 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 95 of 111 Rev g Comments /

Reference:

From Technical Specification LCO 3.1.5 Bases Amendment # 127

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 96 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.7 Importance Rating 3.5 Radiation Control: Ability to comply with radiation work permit requirements during normal or abnormal conditions Proposed Question: Common 71 Given the following conditions:

A "full body" entry into a Radiation Area is required to hang a clearance on a Liquid Waste Pump. The Survey Map shows loose surface c ontamination levels of 25,000 dpm/100 cm 2 around the pump in the area that will be accessed.

Which of the following describes the protective clothing requirements that should be specified on the Radiation Exposure Permit for this task?

A. Lab coat, face shield, gloves, and booties.

B. A single full set of protective clothing.

C. Two full sets of protective clothing and a face shield.

D. A full set of protective clothing with an outer set of plastic cl othing and respirator.

Proposed Answer: B Explanation:

A. Incorrect. Plausible if thought that this contamination level would allow use of this level of clothing, however, a face shield is only required in areas of high contamination. B. Correct. As defined in SO123-VII-20.10, Radiological Work Planning and Controls. C. Incorrect. Plausible because it could be thought that this contamination level would require use of this level of clothing, however, a face shield is only required in areas of high contamination. D. Incorrect. Plausible if thought that this contamination level would require use of this level of clothing, however, plastic clothing (i.e., rain suit) is only required in areas where cloth clothing could become wet.

Technical Reference(s) SO123-VII-20.10, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 97 of 111 Rev g Learning Objective:

06025688 Given a situation requiring the performance of minor valve maintenance in a Red Badge Zone, DESCRIBE the radiological precautions and safe work practices that apply to the situation, to include: REP Requirements.

Question Source: Bank # 209071 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 12 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 98 of 111 Rev g Comments /

Reference:

From SO123-VII-20.10, Attachment 1 Revision # 12

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 99 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.15 Importance Rating 2.9 Radiation Control: Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: Common 72 Which of the following detectors is used primarily for alpha contamination surveys?

A. An ion chamber.

B. A Geiger-Mueller detector.

C. A BF3 propor tional counter.

D. A scintillation detector.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because it will detect radiation, however, not alpha particles. B. Incorrect. Plausible because it is the most sensitive of detectors but not for alpha particles. C. Incorrect. Plausible because it will detect radiation, however, primarily neutrons. D. Correct. This detector is most sensitive to alpha particles.

Technical Reference(s) Lesson Plan 2LC898, Page 31 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

06016384 DESCRIBE the detector characteristic required for detecting beta and alpha radiation.

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 11 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 100 of 111 Rev g 55.43 Comments /

Reference:

From Lesson Plan 2LC898, Page 31 Revision # 1-1 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 101 of 111 Rev g Comments /

Reference:

From Lesson Plan 2LC898, Page 31 Revision # 1-1

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 102 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.12 Importance Rating 3.2 Radiation Control:: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Proposed Question: Common 73 Which of the following describes a Very High Radiation Area and associ ated access controls?

An accessible area where personnel coul d receive a dose of greater than...

A. 5 REM in one hour at 30 cent imeters from the source.

Access is locked with the keys controlled by the Health Physics Checkpoint.

B. 500 RAD in one hour at one meter from the source.

Access is locked with the keys controlled by the Health Physics Manager and Shift Manager. C. 2 REM in one hour at 30 cent imeters from the source.

Access is locked with the keys controlled by the Health Physics Supervisor and

Control Room Supervisor.

D. 5000 RAD in one hour at one meter from the source.

Access is locked with the keys controlled by the Health Physics Checkpoint.

Proposed Answer: B Explanation: A. Incorrect. Plausible because it could be thought that 5 REM was the limit with keys controlled by the HP Checkpoint. B. Correct. As defined in SO123-VII-20 and SO123-VII-20.11.

C. Incorrect. Plausible because it could be thought that 2000 mrem was the limit with keys controlled by the HP Supervisor and CRS. D. Incorrect. Plausible because it could be thought that 5000 RAD was the limit with keys controlled by the HP Checkpoint.

Technical Reference(s) SO123-VII-20, Attachment 1 Attached w/ Revision # See Comments / Reference SO123-VII-20.11, Step 6.6.8 Proposed references to be provided during examination:None

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 103 of 111 Rev g Learning Objective:

53334 DESCRIBE the following areas with respect to radiation levels, posting limits, and access controls as required by 10CFR20. Very High Radiation Area Question Source: Bank # 209072 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 12 55.43 Comments /

Reference:

From SO123-VII-20, Attachment 1 Revision # 14 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 104 of 111 Rev g Comments /

Reference:

From SO123-VII-20.11, Step 6.6.8 Revision # 12

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 105 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.3 Importance Rating 3.7 Emergency Procedures/Plan: Ability to identify post accident instrumentation Proposed Question: Common 74 Which of the following describes the primary purpose of the Core Exit Thermocouples?

The Core Exit Thermocouples monitor...

A. the Reactor Vessel Head to help diagnose voiding in the Head area.

B. core conditions to help maintain an a cceptable Departure fr om Nucleate Boiling Ratio during power operations.

C. for Inadequate Core Cooling during accident conditions.

D. core conditions to help maintain an acceptable Linear Heat Rate during power operations.

Proposed Answer: C Explanation: A. Incorrect. Plausible because it could be thought that this was the purpose, however, this is a function of the Heated Junction Thermocouple System. B. Incorrect. Plausible because it could be thought that this was used by Reactor Protection System, however, it is not an input. C. Correct. Per Technical Specification LCO 3.3.11 Bases. Core Exit Thermocouples are not specifically identified in the Control Room with a PAMI (Post Accident Monitoring Instrumentation) label but are part of the Qualified Safety Parameter Display System (QSPDS) and Critical Function Monitoring System (CFMS). D. Incorrect. Plausible because it could be thought that this was used by Reactor Protection System, however, it is not an input.

Technical Reference(s) Technical Specification LCO 3.3.11 Bases Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

06023553 ANALYZE normal and abnormal operation of the Accident Monitoring System, including alarms, limiting conditions and actions required.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 106 of 111 Rev g Question Source: Bank # 209041 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, 10 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 107 of 111 Rev g Comments /

Reference:

From Tech Spec LCO 3.3.11 Bases Amendment # 127

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 108 of 111 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.11 Importance Rating 4.0 Emergency Procedures/Plan: Knowledge of abnormal condition procedures Proposed Question: Common 75 Given the following End-of-Core (EOC) condition:

A Group 6 Control Element Asse mbly has dropped into the core.

Which of the following is the basis for commencing a boration to meet the Power Reduction Requirement rather than us ing CEAs when at EOC?

A. To minimize the Axial Shape I ndex effects of rod insertion.

B. To prevent radial peaking factors from impacting COLSS Linear Heat Rate.

C. Minimizes reactivity insertion due to the high value of Inverse Boron Worth.

D. A Group 6 insertion can NOT be performed due to the Lower Electrical Limit interlock.

Proposed Answer: D Explanation: A. Incorrect. Plausible because Axial Shape Index is a concern at EOC conditions, however, the electrical limit associated with a Group 6 CEA is the reason. B. Incorrect. Plausible because insertion beyond 142" can adversely impact COLSS LHR and DNBR POLs, however, this is not the reason for the conditions given. C. Incorrect. Plausible because the reason is correct, however, the value of inverse boron worth is low at end-of-life conditions and the subsequent dilution of this boron is a concern. D. Correct. Per the guideline listed in SO23-13-13, a Group 6 CEA is inhibited by a Lower Electrical Limit (LEL) interlock.

Technical Reference(s) SO23-13-13, Step 2.a.2)

Attached w/ Revision # See Comments / Reference SO23-3-2.19, Attachment 8, Step 6.11 Proposed references to be provided during examination:None Learning Objective:

06022688 Per the misaligned CEA procedure, SO23-13-13, DESCRIBE: The basis for each step, caution, or note.

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 109 of 111 Rev g Question Source: Bank # 208029 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 6 55.43 ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 110 of 111 Rev g Comments /

Reference:

From SO23-13-13, Step 2.a.2)

Revision # 12

ES-401 2010 NRC RO Written Exam Worksheet Form ES-401-5 Page 111 of 111 Rev g Comments /

Reference:

From SO23-3-2.19, Attachment 8, Step 6.11 Revision # 23

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 1 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 015/017 G 2.2.44 Importance Rating 4.4 RCP Malfunctions: Equipment Control: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Proposed Question: SRO 76 Given the following conditions on Reactor C oolant Pump (RCP) 2P-002 at 100% power:

Controlled Bleed Off flow indicates zero (0) gpm. Vapor Seal Cavity indicates 10 psi.

Upper Seal Cavity indicates 810 psi. Middle Seal Cavity indicates 1525 psi. Leakage into the Containment Sump is 12 gpm and has been confirmed by performing a Reactor Coolant System Inventory Balance.

Which of the following describes the required actions for these conditions?

A. Reduce the leakage to less than one (1) gpm within four (4) hours or initiate SO23-13-28, Rapid Power Reduction, to be in HOT STANDBY in six (6) hours.

B. A single Seal Stage has failed. Pump the Containment Sump to maintain an indicated level and enter Containm ent to re-seat the Vapor Seal.

C. Initiate a controlled power reduction per SO23-5-1.7, Power Operations, then immediately trip the Reactor and Reactor Coolant Pump.

D. Trip the Reactor, trip RCP 2P-002 fi ve (5) seconds after the CEAs have been inserted then perform SO23-12-1, Standard Post Trip Actions.

Proposed Answer: D

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 2 of 110 Rev g Explanation: A. Incorrect. Plausible because these would be the actions for an unidentified leak of this magnitude per SO23-13-14, Reactor Coolant Leak, however, SO23-13-6, Reactor Coolant Pump Seal Malfunction requires tripping the Reactor and affected pump if the Vapor Seal has failed and leakage into Containment is > 10 gpm. B. Incorrect. Plausible because continued operation with a single failed seal is allowed in SO23-13-6, Reactor Coolant Pump Seal Malfunction, however, in this case SO23-13-6 requires tripping the

Reactor and affected RCP. C. Incorrect. Plausible because this would be the action for Controlled Bleed Off leak into Containment of less than or equal to 4 gpm per SO23-13-6, Step 3.c, however, the leakage is not at that threshold and the tripping criteria is not correct. D. Correct. SO23-13-6, Reactor Coolant Pump Seal Malfunction, requires tripping the Reactor and affected RCP if the Vapor Seal has failed and leakage into Containment is > 10 gpm.

Technical Reference(s) SO23-13-6, Step 3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

55458 As the SRO, DIRECT operator response to a Reactor Coolant Pump Seal Failure per SO23-13-6.

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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 3 of 110 Rev g Comments /

Reference:

From SO23-13-6, Step 3 Revision # 5

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 4 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 065 AA2.03 Importance Rating 2.9 Loss of Instrument Air: Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Location and isolation of leaks Proposed Question: SRO 77 Given the following conditions with Unit 2 at 100% power:

Instrument Air header pressure has lowered to 55 psig due to a leak. Instrument Air header pressure as r ead on 2/3-PI-5344A on CR-61 is stable. The leak has been located in the Unit 2 Ring Header. P-053, Condensate Pump has AUTO started. P-062, Main Feedwater Pump has tripped.

Steam Generator leve ls are uncontrolled.

Which of the following actions is required for the conditions listed?

A. Initiate a rapid power reduction per SO23-13-28, Rapid Power Reduction, to 70%

power. B. Trip the Reactor and initiate SO23-12-1, Standard Post Trip Actions.

C. Initiate a controlled power reduction per SO23-5-1.7, Power Operations, until Steam Generator levels have stabilized.

D. Refer to SO23-13-5, Loss of Instrument Ai r, and trip the Reacto r if Instrument Air pressure stabilizes below 50 psig.

Proposed Answer: B

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 5 of 110 Rev g Explanation: A. Incorrect. Plausible because entry into SO23-13-28 would be required if a Main Feedwater Pump had tripped with the Unit at 100% power; however, because the Main Feedwater Pump trip is accompanied by an Instrument Air header leak, the Reactor must be tripped. B. Correct. This is the required action because plant systems have become unstable (i.e., tripping of Main Feedwater Pump, fluctuating Steam Generator levels, etc.) even with Instrument Air header pressure greater than 50 psig. C. Incorrect. Plausible because Instrument Air pressure has stabilized, however, plant systems have become unstable and a Reactor Trip is required. D. Incorrect. Plausible because action is required per SO23-13-5 if Instrument Air header pressure is less than 50 psig, however, SO23-13-5 requires an earlier trip of the Reactor if plant systems become unstable.

Technical Reference(s) SO23-13-5, Step 1.j Attached w/ Revision # See Comments / Reference SO23-13-5, Steps 1.m, n, & p SO23-13-5, Steps 2.a, & b SO23-13-5, Attachment 6, L&S 1.8 SO23-13-28, Entry Conditions Proposed references to be provided during examination:None 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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 6 of 110 Rev g Comments /

Reference:

From SO23-13-5, Step 1.j Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 7 of 110 Rev g Comments /

Reference:

From SO23-13-5, SO23-13-5, Step 1.m, n, & p Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 8 of 110 Rev g Comments /

Reference:

From SO23-13-5, SO23-13-5, Step 2.a Revision # 8 Comments /

Reference:

From SO23-13-5, SO23-13-5, Step 2.b Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 9 of 110 Rev g Comments /

Reference:

From SO23-13-28, Entry Conditions Revision # 2 Comments /

Reference:

From SO23-13-5, Attachment 6, L&S 1.8 Revision # 8

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 10 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 029 G 2.4.6 Importance Rating 4.7 ATWS: Emergency Procedures/Plan: Knowledge of EOP mitigation strategies Proposed Question: SRO 78 Given the following conditions:

An Anticipated Transient Without Scram (ATW S) is in progress due to failure of all efforts to insert Control Rods. Charging Pumps are NOT available.

Which of the following is the pr eferred order for im plementing boration using Emergency Core Cooling per SO23-12-9, Functional Recovery, Attachment FR-1, Reco very - Reactivity Control?

High Pressure Safety Injection,...

A. Containment Spray Pumps via LPSI lines, then Safety Injection Tanks.

B. Containment Spray Pumps via LPSI lines, then Low Pressure Safety Injection Pumps. C. Low Pressure Safety Injection Pumps, then Safety Injection Tanks.

D. Low Pressure Safety Injection Pumps, then Containment Spray Pumps via LPSI lines.

Proposed Answer: B Explanation: A. Incorrect. Plausible if thought that the boron volume in the SITs would be an option, however, this method is not specified and a continuous flowrate of 40 gpm is not guaranteed. B. Correct. This is the correct order of implementation specified in SO23-12-9, Functional Recovery.

C. Incorrect. Plausible if thought that the boron volume in the SITs would be an option and that a normal LPSI lineup would be preferred to an alternate lineup for Spray, however, the SIT method is not specified. Additionally, Containment Spray Pumps have a higher head than LPSI Pumps. D. Incorrect. Plausible if thought that a normal LPSI lineup would be preferred to an alternate lineup for Containment Spray, however, Containment Spray Pumps have a higher head than Low Pressure Safety Injection Pumps and thus requires a smaller pressure reduction for flow.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 11 of 110 Rev g Technical Reference(s) SO23-14-9, Attachment FR-1, Step 4.5 Attached w/ Revision # See Comments / Reference SO23-12-9, Attachment FR-1, RAC-RC3 Proposed references to be provided during examination:None Learning Objective:

53929 As the SRO, DIRECT accident mitigation by use of the Functional Recovery

EOI per SO23-12-9.

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 Comments /

Reference:

From SO23-14-9, Attachment FR-1, Step 4.5 Revision # 10 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 12 of 110 Rev g Comments /

Reference:

From SO23-12-9, Attachment FR-1, RAC-RC3 Revision # 26 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 13 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # E06 EA2.1 Importance Rating 3.9 Loss of Feedwater: Ability to determine and interpret the following as they apply to the Loss of Feedwater: Facility conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Question: SRO 79 Given the following conditions:

Unit 2 has tripped following a Bus 2A07 overcurrent trip and loss of Condenser vacuum. Auxiliary Feedwater (AFW) Pump P-141 br eaker will not close and AFW Pump P-504 was cleared for Boundary of the Week. AFW Pump P-140 is running but cannot develop sufficient discharge head. SO23-12-1, Standard Post Tr ip Actions, is complete.

SO23-12-6, Loss of Feedwat er, is in progress. The cause of the loss of vacuum was identified and Condenser vacuum is restored.

Main Feedwater Pump P-062 was RESET and available for use. Shortly after entry into SO 23-12-6, the following occurs: Annunciator 57C57 - TURBINE BLDG FLOODING has just alarmed. A Main Feedwater pipe rupture was veri fied between the Turbine Building and the Safety Equipment Building.

Which of the following actions is required?

A. Implement SO23-12-9, F unctional Recovery, and initiate Attachment FR-5, Recovery - Heat Removal, Success Path HR-1, Step 7 immediately.

B. Remain in SO23-12-6, Loss of Feedwat er, and transition to Step 10, Establish Condensate Pump Flow to Availabl e SGs and depressurize to 500 psig.

C. Remain in SO23-12-6, Loss of Feedwat er, and continue to align Main Feedwater Pump P-062 to feed the Steam Generators.

D. Rediagnose per Safety Function Status Checks SF-1, Recovery Diagnostics and transition to SO23-12-5, Ex cess Steam Demand Event.

Proposed Answer: A

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 14 of 110 Rev g Explanation: A. Correct. As outlined in SO23-12-6, Step 8.b, a transition to the Functional Recovery Procedure must be performed. B. Incorrect. Plausible because a Condensate Pump would be available from Bus 2A03 since there is not a Loss of Offsite Power and it did not incur an overcurrent trip, however, there are two events in progress and entry into SO23-12-9 is required. Otherwise, without Condensate Pumps available SO23-12-6 would direct entry into SO23-12-9 at Step 10. C. Incorrect. Plausible if thought that the Steam Generators could continue to be fed, however, a transition to SO23-12-9 is warranted. D. Incorrect. Plausible because rediagnosis would be appropriate to ensure correct procedure is being entered and it would be performed as part of the Safety Function Status Checks (since SO23-12-1 is complete), however, there are two events in progress and this would require entry into SO23-12-9, Functional Recovery.

Technical Reference(s) SO23-12-6, Steps 8.b, 10.a, & 10.k Attached w/ Revision # See Comments / Reference SO23-12-10, Attachment 4 Proposed references to be provided during examination:None Learning Objective:

53927 As the SRO, DIRECT response to and recovery from a Loss of Feedwater accident per SO23-12-6.

Question Source: Bank # 127441 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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 15 of 110 Rev g Comments /

Reference:

From SO23-12-6, Step 8.b Revision # 22 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 16 of 110 Rev g Comments /

Reference:

From SO23-12-6, Step 10.a Revision # 22 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 17 of 110 Rev g Comments /

Reference:

From SO23-12-6, Step 10.k Revision # 22 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 18 of 110 Rev g Comments /

Reference:

From SO23-12-10, Attachment 4 Revision # 4

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 19 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 009 G 2.4.41 Importance Rating 4.6 Small Break LOCA: Emergency Procedures/Plan: Knowledge of emergency action level thresholds and classifications Proposed Question: SRO 80 Given the following conditions:

The Reactor tripped from 100% power. There was a fire in Vital AC Bus Y01 that was extinguished in 10 minutes but the bus was lost. A Reactor Coolant System leak into the Quench Tank exists due to Safety Valve leakage. Pressurizer Level is stable.

Letdown flow is at minimum.

Two (2) Charging Pumps are operating.

Reactor Coolant Pump Controlled Bleed Off flow is 5 gpm total.

Which of the following would be the Emergency Plan Event Code for these conditions?

A. No Classification required.

B. B1-1, UNUSUAL EVENT.

C. E1-1, UNUSUAL EVENT.

D. B2-1, ALERT.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that there were no Emergency Plan Action levels exceeded. B. Incorrect. Plausible because it could be thought that this fell within the UNUSUAL EVENT Criteria for identified leakage, however, two Charging pumps provide 88 gpm and the combined Letdown and Controlled Bleed Off flow is 33 gpm resulting in a 55 gpm inventory loss which exceeds the threshold for an ALERT classification. C. Incorrect. Plausible because it this involved a fire affecting Safety Related Equipment, however, the fire has to be active for 15 minutes or longer for this classification. D. Correct. Two Charging Pumps provide 88 gpm and the combined Letdown and Controlled Bleed Off flow is 33 gpm resulting in a 55 gpm inventory loss which exceeds the threshold for an ALERT classification.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 20 of 110 Rev g Technical Reference(s) SO123-VIII-1, Attachment 2, Tab B-2 & P-1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:SO123-VIII-1, Attachment 2.

Learning Objective: 122527 / 56274 CLASSIFY events related to the Cold Shutdown, Fission Product Barrier and System Malfunction Categories. As the SRO, CLASSIFY emergency events requiring Emergency Plan implementation per SO123-VIII-1.

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:

From SO123-VIII-1, Attachment 2, Tab B-2 Revision # 29

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 21 of 110 Rev g Comments /

Reference:

From SO123-VIII-1, Attachment 2, Tab P-1 Revision # 29

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 22 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 1 K/A # 011 EA2.03 Importance Rating 4.2 Large Break LOCA: Ability to determine or interpret the following as they apply to a Large Break LOCA: Consequences of managing LOCA with loss of CCW Proposed Question: SRO 81

Given the following conditions:

A Large Break Loss of Coolant Acci dent is in progress on Unit 2. A total loss of Component Coolin g Water has occurred on Unit 2. The Recirculation Actuation Si gnal will actuate in 5 minutes. Bus 2A04 has tripped and locked out due to a bus fault. High Pressure Safety Injection (HPSI) Pu mp P-018 is currently aligned to Train B. Actions of SO23-12-3, Loss of C oolant Accident, are in progress.

Which of the following actions should be taken to mitigate the situation?

A. Remain in SO23-12-3, Loss of C oolant Accident, and cross-connect Unit 2 Component Cooling Water with Unit 3 and invoke 10CFR50.54.X on Unit 2.

B. Start P-019, HPSI Pump to Train B following the Recirculation Actuation Signal in order to provide additional flow and transition to SO23-12-9, Functional Recovery, Attachment FR-5, Recovery - Heat Removal, if HPSI Pump performance becomes unstable.

C. Transition to SO23-12-9, Functional Recovery, Attachment FR-5 , Recovery - Heat Removal, and cross-connect Unit 2 Component Cooling Water with Unit 3 and

invoke 10CFR50.54.X on Unit 3.

D. Perform actions of SO23-12-11, EOI S upporting Attachments, Attachment 14, RAS Operations to raise RWST level in order to flood Containmen t above the 23' (foot) level to improve Net Positive Sucti on Head to the operating HPSI Pump.

Proposed Answer: A

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 23 of 110 Rev g Explanation: A. Correct. Given the conditions listed, remaining in SO23-12-3 is appropriate and cross connecting CCW places Unit 2 in a 50.54.X notification. B. Incorrect. Plausible because HPSI Pump P-019 is available (P-018, the 3 rd of a kind Pump will start on an SIAS, therefore, P-019 is available to run) and might be considered, however, according to Step 5 EOI Bases, it will only increase flow marginally, if at all, and one operating train is sufficient at his time. Transitioning to the FR is plausible as this is the RNO action in Floating Step 22 if HPSI Pump flow becomes unstable. C. Incorrect. Plausible because it could be thought that the FR is the procedure required for this condition, however, one Train is all that is required given the conditions listed and cross connecting with Unit 3 CCW places Unit 2 in a 50.54.X notification. D. Incorrect. Plausible because refilling the RWST would be a desired action given the loss of CCW and raising level does improve HPSI Pump NPSH, however, flooding above the 22'5" level will impact the Emergency Cooling Unit ductwork and could complicate the loss of CCW that already exists. Technical Reference(s) SO23-13-7, Attachment 4, Guidelines Attached w/ Revision # See Comments / Reference SO23-14-3, Attachment 1, Step 4.4.5 SO23-12-11, FS-22 SO23-12-11, Attachment 14, Step 4 Proposed references to be provided during examination:None Learning Objective: 52757 / 53682 STATE the major recovery actions in response to a LOCA event. EVALUATE Component Cooling Water System conditions against Administrative and Technical Specification requirements and determine what action, if any, is required.

Question Source: Bank # 208077 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2008 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 24 of 110 Rev g Comments /

Reference:

From SO23-13-7, Attachment 4, Guidelines Revision # 14 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 25 of 110 Rev g Comments /

Reference:

From SO23-14-3, Attachment 1, Step 4.4.5 Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 26 of 110 Rev g Comments /

Reference:

From SO23-14-3, Attachment 1, Step 4.4.5 Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 27 of 110 Rev g Comments /

Reference:

From SO23-12-11, FS-22 Revision # 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 28 of 110 Rev g Comments /

Reference:

From SO23-12-11, Attachment 14, Step 4 Revision # 7

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 29 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 036 AA2.02 Importance Rating 4.1 Fuel Handling Accident: Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: Occurrence of a fuel handling incident Proposed Question: SRO 82

Given the following conditions during REFUELING Operations:

Steam Generator Nozzle Dams are installed. An irradiated fuel assembly has just been removed from the Upender in the Fuel Transfer Pool and is in transit to the Spent Fuel Pool racks. The Refueling Operations Supervisor reports Refueling Water Level is slowly lowering about 0.25" (1/4") per minute. Health Physics reports that a small amount of water is seeping into Steam Generator E-088 bowl.

Which of the following actions should be performed FIRST?

A. Lower the fuel assembly into a deep area of the Cask Pool, and close the Cask Pool Gate.

B. Immediately suspend fuel movement and initiate CRIS.

C. Seat the fuel assembly in the Spent Fuel Pool racks.

D. Return the fuel assembly to the Upender.

Proposed Answer: C Explanation: A. Incorrect. Plausible because this would cover the assembly, however, there is sufficient time to place the assembly in the SFP racks. B. Incorrect. Plausible because the first action is required, however, the 2 nd is for a Fuel Handling Accident. C. Correct. With the small amount of leakage through a failed nozzle dam, the assembly can be seated in the SFP racks. D. Incorrect. Plausible because it could be thought that this would be quicker, however, there is sufficient time to place the assembly in the SFP racks.

Technical Reference(s) SO23-13-20, Steps 2 & 5.a Attached w/ Revision # See Comments / Reference

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 30 of 110 Rev g Proposed references to be provided during examination:None Learning Objective:

54861 As the SRO, DIRECT the response to Fuel Handling Accidents/Loss of Cavity or SFP Level Control per SO23-13-20.

Question Source: Bank # 209083 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 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 31 of 110 Rev g Comments /

Reference:

From SO23-13-20, Step 5.a Revision # 10 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 32 of 110 Rev g Comments /

Reference:

From SO23-13-20, Step 2 Revision # 10 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 33 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # A11 AA2.2 Importance Rating 3.4 RCS Overcooling-PTS: Ability to determine and interpret the following as they apply to the RCS Overcooling: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. Proposed Question: SRO 83

Given the following conditions a fter a trip from 100% power:

A Steam Line Break has occurred inside Containment. SO23-12-5, Excess Steam Demand Event, Step 13, Limit RCS Re-pressurization is in progress. Reactor Coolant System subcooling is 160ºF and rising. Containment pressure is 6 psig.

Which of the following actions is required to reduce Reactor Coolant System subcooling?

A. Initiate FS-32, Establish Manual Auxiliary Spray then refer to SO23-12-11, Attachment 5, Core Exit Saturation Ma rgin Control using the value of PTS subcooling in place of Core Exit Saturation Margin.

B. Establish Normal Auxiliary Spray flow t hen transition to SO23-12-11, Attachment 5, Core Exit Saturation Margin Control using the value of Core Exit Saturation Margin in place of PTS subcooling.

C. Initiate FS-32, Establish Manual Auxiliary Spray then refer to SO23-12-11, Attachment 5, Core Exit Saturation Margin Control using the value of Core Exit Saturation Margin in place of PTS subcooling.

D. Establish Normal Auxiliary Spray flow t hen transition to SO23-12-11, Attachment 5, Core Exit Saturation Margin Control using the value of PTS subcooling in place of Core Exit Saturation Margin.

Proposed Answer: A

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 34 of 110 Rev g Explanation: A. Correct. Use FS-32 due to a harsh Containment and Core Exit Saturation Margin Control using the value of PTS subcooling in place of Core Exit Saturation Margin. B. Incorrect. Plausible because Attachment 5 use is correct, however, the Normal Auxiliary Spray Valve should not be used in a harsh Containment. C. Incorrect. Plausible because using FS-32 is correct, however, the value of PTS subcooling is used in place of Core Exit Saturation Margin. D. Incorrect. Plausible because spray flow is required and the transition step is correct, however, the Normal Auxiliary Spray Valve should not be used in a harsh Containment.

Technical Reference(s) SO23-12-5, Step 13 Attached w/ Revision # See Comments / Reference SO23-14-5, Attachment 1, Step 13 SO23-12-11, Attachment 5, CESM Control Proposed references to be provided during examination:None Learning Objective: 53926 / 55279 As the SRO, DIRECT response to and recovery from an Excess Steam Demand Event per SO23-12-5. Per the EOI Attachments procedure, SO23-12-11, 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 55.43 5 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 35 of 110 Rev g Comments /

Reference:

From SO23-12-5, Step 13 Revision # 22 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 36 of 110 Rev g Comments /

Reference:

From SO23-14-5, Attachment 1, Step 13 Revision # 8 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 37 of 110 Rev g Comments /

Reference:

From SO23-14-5, Attachment 1, Step 13 Revision # 8 Comments /

Reference:

From SO23-12-11, Attachment 5, CESM Control Revision # 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 38 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 032 AA2.01 Importance Rating 2.9 Loss of Source Range NI: Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Normal/abnormal power supply operation Proposed Question: SRO 84 Given the following conditions:

Unit 3 has just entered MODE 5 on Shutdown Cooling. Reactor Coolant System T COLD is 195ºF. Annunciator 50A57 - START-UP CHANNEL 2 TROUBLE has just alarmed due to a loss of power.

Which of the following outlines the required actions for the failed Startup Channel?

A. Stop the cooldown and transfer Channel 2 to its alternate power per SO23-3-2.20, Computer Operation.

B. Continue the cooldown to ~150ºF and verify the Bor onometer low alarm is set within 50 ppm of current boron concentration per SO23-5-1.5, Pl ant Shutdown from Hot Standby to Cold Shutdown.

C. Stop the cooldown and transfer Channe l 2 to an alternate power source per SO23-3-2.15, Excore Inst rumentation Operations.

D. Continue the cooldown to ~120ºF and align the audi ble count rate monitor on Start-up Channel 1 per SO23-5-1.5, Plant Shutdown from Hot Standby to Cold Shutdown.

Proposed Answer: C Explanation: A. Incorrect. Plausible because the cooldown must be stopped, however, the procedure entry is incorrect. B. Incorrect. Plausible because the Boronometer alarm must be reset, however, RCS temperature must be held within +/- 20ºF. C. Correct. This is the correct action for one Source Range Channel INOPERABLE per SO23-3-2.15.

D. Incorrect. Plausible because the audible count rate monitor should be placed on the OPERABLE Channel, however, RCS temperature must be held within +/- 20ºF.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 39 of 110 Rev g Technical Reference(s) SO23-3-2.15, Attachment 4, Step 4.4 Attached w/ Revision # See Comments / Reference SO23-3-2.15, Step 6.4 Proposed references to be provided during examination:None Learning Objective:

53666 ALIGN the Train 'B' source range nuclear instrumentation channel to its alternate power supply per SO23-3-2.15.

Question Source: Bank # 127442 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 2, 5 Comments /

Reference:

From SO23-3-2.15, Attachment 4, Step 4.4 Revision # 13 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 40 of 110 Rev g Comments /

Reference:

From SO23-3-2.15, Step 6.4 Revision # 13

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 41 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 1 Group # 2 K/A # 069 AA2.01 Importance Rating 4.3 Loss of Containment Integrity: Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: Loss of containment integrity Proposed Question: SRO 85 Which of the following conditions represents a vi olation of Containmen t Systems as described in Technical Specifications?

While at 100% power,...

A. HV-5434, Nitrogen Supply Isolation Valve to Safety Injection Tanks, fails to stroke full open.

B. the outer Containment airlock door fails its leak rate test and has to be opened to facilitate repairs that will take two (2) hours.

C. OPERABILITY tests on redundant Cont ainment Loop 1 Hot Leg Sample Valves (HV-0508 and HV-0509); one of the two valves (HV-0508) fails closed.

D. a mechanic blocks open t he outer Containment airlo ck door for two (2) hours to perform maintenance activities on the INOPERABLE inner Containment door.

Proposed Answer: D Explanation: A. Incorrect. Plausible because a valve has failed to stroke full open, however, with two other downstream check valves OPERABLE, Containment Systems are intact. B. Incorrect. Plausible because the leak rate test was failed, however, the inner door remains OPERABLE and Technical Specifications are not violated. C. Incorrect. Plausible because Post Accident Sa mpling Systems would be affected with the valve failed closed, however, Containment Systems are not impacted. D. Correct. With the inner Containment door already INOPERABLE, Containment Systems are violated when the outer OPERABLE door is blocked for two hours.

Technical Reference(s) Technical Specification LCO 3.6.2 Attached w/ Revision # See Comments / Reference Technical Specification LCO 3.6.3 SD-SO23-740, Figure 2 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 42 of 110 Rev g Learning Objective:

56649 Given plant and equipment conditions, or Technical Specification/LCS surveillance results, DETERMINE syst em or equipment OPERABILITY and LCO(s) impacted along with all required actions and surveillances using SONGS procedures, Technical Specifications and Licensee Controlled Specifications (LCS).

Question Source: Bank # 73339 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 2 Comments /

Reference:

From Technical Specification LCO 3.6.2 Amendment # 127 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 43 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.6.2 Amendment # 127 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 44 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.6.2 Amendment # 127 Comments /

Reference:

From Technical Specification LCO 3.6.3 Amendment # 127 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 45 of 110 Rev g Comments /

Reference:

From SD-SO23-740, Figure 2 Revision # 17

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 46 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 022 G 2.4.1 Importance Rating 4.8 Containment Cooling System: Emergency Procedures/Plan: Knowledge of EOP entry conditions and immediate action steps Proposed Question: SRO 86 Given the following conditions:

All Control Element Drive Mechanism Cooling has been lost for one (1) hour. A Containment entry to investigate the cause has been delayed.

Which of the following actions should be di rected by the Control Room Supervisor?

A. Trip the Reactor and then perform SO23 1.5, Plant Shutdown from Hot Standby to Cold Shutdown, to initiate a plant cooldown to less than 350ºF.

B. Enter SO23-3-2.22, Engineered Safety F eatures Actuation System Operation, and initiate a Containment Cooling Ac tuation Signal on one (1) train.

C. Enter SO23-1-4, Containment Normal H eat Removal, Operation of the Reactor Cavity Cooling Units, and start a second f an in each set to cool the area around the Reactor. D. Refer to SO23-15-60.A1 - CEDM COOL ING SHROUD TEMP HI, and verify Control Element Drive Mechanism Cooling Unit Dampers OPEN to promote Natural Circulation cooling.

Proposed Answer: A Explanation: A. Correct. These are the required actions per Operating Instruction SO23-1-4 and Annunciator SO23-15-60A1, 60A13. Entry into SO23-5-1.5 will facilitate the cooldown. B. Incorrect. Plausible if thought that the additional cooling using Containment Emergency Cooling Units would be the appropriate strategy to keep t he CEDM temperatures within design, however, this is a strategy for a high temperature condition on the shroud or coils but the Reactor is required to be tripped prior to exceeding one hour with a total loss of cooling and a plant cooldown to

< 350ºF is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. C. Incorrect. Plausible because it could be thought that the additional area cooling using the Reactor Cavity Cooling Units would be the appropriate strategy to lower CEDM temperatures, however, the Reactor is required to be tripped prior to exceeding one hour with a total loss of cooling. D. Incorrect. Plausible because this action is performed upon receipt of the alarm at 160ºF, however, a loss of CEDM cooling for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> requires a Reactor trip.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 47 of 110 Rev g Technical Reference(s) SO23-1-4, Reference 2.2.1 Attached w/ Revision # See Comments / Reference SO23-1-4, Attachment 20, L&S 5.1 SO23-1-4, Section 6.8 SO23-15-60.A1, 60A13 Proposed references to be provided during examination:None Learning Objective:

81789 ANALYZE normal and abnormal operations of the Control Element Drive Mechanism Control System (CEDMCS).

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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 48 of 110 Rev g Comments /

Reference:

From SO23-1-4, References 2.2.1 Revision # 18 Comments /

Reference:

From SO23-1-4, Attachment 20, L&S 5.1 Revision # 18 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 49 of 110 Rev g Comments /

Reference:

From SO23-1-4, Section 6.8 Revision # 18 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 50 of 110 Rev g Comments /

Reference:

From SO23-15-60.A1, 60A13 Revision # 11 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 51 of 110 Rev g Comments /

Reference:

From SO23-15-60A1, 60A13 Revision # 11

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 52 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 A2.07 Importance Rating 3.9 Containment Spray System: Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding, or sump level below cutoff (interlock) limit Proposed Question: SRO 87 Given the following conditions:

A Large Break Loss of Coolant Accident has occurred in Containment. Containment pressure is 35 psia and slowly lowering. Both Trains of SIAS, CCAS, CSAS and CIAS have actuated.

Recirculation Actuation Si gnal just actuated and all aut omatic components operated properly. Refueling Water Storage Tank Outlet Valves are CLOSED. Subsequently, the Containment Emergency Sump becomes blocked.

Which of the following:

1.) Identifies the impact of the clogged su mp on the Emergency Co re Cooling System Pumps?

2.) Actions that should be tak en to mitigate the situation?

A. 1.) Oscillations in flow, dischar ge pressure, and amperage are occurring. 2.) STOP one (1) Train of High Pressure Safety Injection and Containment Spray.

B. 1.) Discharge pressure is normal but fl ow and amperage are both lower than normal. 2.) STOP both Trains of Containment Spray and CLOSE the Spray Header Control Valves.

C. 1.) Discharge pressure is normal but flow and amperage are both lower than normal.

2.) STOP one (1) Train of High Pressure Sa fety Injection and Containment Spray.

D. 1.) Oscillations in flow, dischar ge pressure, and amperage are occurring. 2.) STOP both Trains of Containment Spray and CLOSE the Spray Header Control Valves.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 53 of 110 Rev g Proposed Answer: D Explanation: A. Incorrect. Plausible because the indications are correct. The action to stop the HPSI Pump is only performed after the Containment Spray Pumps are stopped and HPSI Pump performance continues to be unstable. B. Incorrect. Plausible because the action is correct, however, with the Containment Emergency Sump blocked, oscillations in flow, pressure and amperage will occur. C. Incorrect. Plausible if thought that pump cavitation did not affect discharge pressure, however, the required actions under these circumstances would be to secure both Containment Spray Pumps and close their discharge path. D. Correct. With the Containment Emergency Sump blocked, oscillations in flow, pressure and amperage will occur. This is the correct action per SO23-12-11, EOI Supporting Attachments, FS-22, Monitor ECCS Pumps Suction After RAS, Step b.

Technical Reference(s) SO23-12-11, FS-22 Attached w/ Revision # See Comments / Reference SO23-12-11, Attachment 14, Step 6 Proposed references to be provided during examination:None Learning Objective:

55279 Per the EOI Attachments procedure, SO23-12-11, 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 55.43 5 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 54 of 110 Rev g Comments /

Reference:

From SO23-12-11, FS-22 Revision # 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 55 of 110 Rev g Comments /

Reference:

From SO23-12-11, Attachment 14, Step 6 Revision # 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 56 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 G 2.1.7 Importance Rating 4.7 Auxiliary/Emergency Feedwater System: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Proposed Question: SRO 88 Given the following conditions followin g a Steam Generator Tube Rupture:

SO23-12-4, Steam Generator Tube Rupture is in progress Step 24, Reset EFAS, is being performed.

Which of the following is the procedural direct ion and reason that will be given for Auxiliary Feedwater control?

Establish Auxiliary Feedwater flow using the...

A. AC powered valves (HV-4714 or HV-4731) to provide better response as a result of a longer stroke time from fully closed to fully open.

B. DC powered valves (HV-4730 or HV-4715) to minimize the load on the Vital AC Bus and to prevent feeding a ruptured SG if a Vital AC Bus is lost.

C. AC powered valves (HV-4714 or HV-4731) to minimize the load on the 1E Batteries and to prevent feeding a ruptur ed SG if a DC bus is lost.

D. DC powered valves (HV-4730 or HV-4715) to allow for better fl ow characteristics and allow finer control of Auxiliary Feedwater flow.

Proposed Answer: C Explanation: A. Incorrect. Plausible because these valves are correct, however, the reason is not. B. Incorrect. Plausible because this reason could be correct, however, these are the wrong valves.

C. Correct. Use these valves for the reason listed. D. Incorrect. Plausible if thought that this is the reason for using the DC powered valves.

Technical Reference(s) SO23-12-4, Step 24 Attached w/ Revision # See Comments / Reference SO23-14-4, Attachment 1, Step 24 SO23-2-4, Attachment 12, L&S 2.9 Proposed references to be provided during examination:None ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 57 of 110 Rev g Learning Objective:

53000 Per the SGTR procedure SO23-12-4 DESCRIBE: The basis for each step, caution or note.

Question Source: Bank # 208089 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 1, 5

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 58 of 110 Rev g Comments /

Reference:

From SO23-12-4, Step 24 Revision # 22 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 59 of 110 Rev g Comments /

Reference:

From SO23-14-4, Attachment 1, Step 24 Revision # 7 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 60 of 110 Rev g Comments /

Reference:

From SO23-2-4, Attachment 12, L&S 2.9 Revision # 27

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 61 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 G 2.2.22 Importance Rating 4.7 Residual Heat Removal System: Equipment Control: Knowledge of limiting conditions for operations and safety limits Proposed Question: SRO 89 Given the following conditions on Unit 2 during plant cooldown:

Reactor has been shutdown for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Train A Shutdown Cooling Train had just been placed in service when Offsite Power was lost. Recovery is expected to take several hours. Train A Low Pressure Safety Inject ion Pump motor failed on the transient. Reactor Coolant System temperature is 320ºF. Reactor Coolant System pressure is 100 psia.

Steam Generator levels are at 45% wide range. All other Safety Related Pumps are OPERABLE.

Which of the following actions should be ta ken to meet Technical Specifications?

A. Ensure Natural Circulation is establish ed and immediately ali gn Train A Shutdown Cooling using the Containment Spray Pump.

B. Raise pressure and allow temperat ure to rise above 350ºF and operate Atmospheric Dump Valves to restore R eactor Coolant System Loops to service.

C. Flow stoppage is allowed for one (1) hour to permit realignment. Start Train B Shutdown Cooling System and rest ore Train A within the hour.

D. Place Train B Shutdown C ooling System in service i mmediately and enter MODE 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Proposed Answer: D

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 62 of 110 Rev g Explanation: A. Incorrect. Plausible because Natural Circulation would be established for this condition and it could be thought that the Containment Spray Pump could be utilized, however, only MODE 5 allows use of the Containment Spray Pump per Technical Specification LCO 3.4.7. B. Incorrect. Plausible pressure and temperature are being raised; however, there is inadequate level in the Steam Generators to support OPERABILITY. C. Incorrect. Plausible because it could be thought that invoking this one hour allowance in the specification is allowed and that it could be construed as a defacto ACTION statement, however, this allowance is for intentional securing of heat removal for plant operational needs and is not an ACTION statement for restoring OPERABILITY. Additionally, the core is NOT subcooled by greater than 10ºF, therefore, this action is not allowed. D. Correct. This is the REQUIRED ACTION for this condition per Technical Specification LCO 3.4.6, RCS Loops - MODE 4.

Technical Reference(s) Technical Specification LCO 3.4.6 & Bases Attached w/ Revision # See Comments / Reference Technical Specification LCO 3.4.7 Proposed references to be provided during examination:None Learning Objective:

56649 Given plant and equipment conditions, or Technical Specification/LCS surveillance results, DETERMINE syst em or equipment OPERABILITY and LCO(s) impacted along with all required actions and surveillances using SONGS procedures, Technical Specifications and Licensee Controlled Specifications (LCS).

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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 63 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.6 Amendment # 203 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 64 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.6 Amendment # 203 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 65 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.6 Bases Amendment # 203

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 66 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.7 Amendment # 203 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 67 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 A2.10 Importance Rating 3.9 Emergency Core Cooling System: Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low boron concentration in SIS Proposed Question: SRO 90 Given the following conditions on Unit 2 in MODE 1 at EOC:

Annunciator 57A59 - LOOP 1B SAFETY INJECTION CHECK VALVE LEAKAGE PRESSURE HI is in alarm at 1000 psig. Reactor Coolant System leakage has risen from 0.2 gpm to 0.7 gpm. Prior Inservice Testing Program l eakage surveillance was within limits.

Which of the following:

1.) Identifies the impact on the Emergency Core Cooling System?

2.) Actions should be taken to mitigate the situation?

A. 1.) Continued leak age could result in low boron concentrations in the Safety Injection header.

2.) Be in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to exceeding Technical Specification LCO 3.4.13, RCS Operati onal Leakage criteria.

B. 1.) A pressure lock could occur that prevents proper operation of T-007, Safety Injection Tank Isolation Valve.

2.) Isolate the high pressure portion of the system from the low pressure portion with one closed manual, deac tivated automatic, or check valve per LCO 3.4.14, RCS Pressure Isolation Valve Leakage criteria.

C. 1.) Continued leak age could result in low boron concentrations in the Safety Injection header.

2.) Isolate the high pressure portion of the system from the low pressure portion with one closed manual, deac tivated automatic, or check valve per LCO 3.4.14, RCS Pressure Isolation Valve Leakage criteria.

D. 1.) A pressure lock could occur that prevents proper operation of T-007, Safety Injection Tank Isolation Valve.

2.) Be in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to exceeding Technical Specification LCO 3.4.13, RCS Operat ional Leakage criteria.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 68 of 110 Rev g Proposed Answer: C Explanation: A. Incorrect. Plausible because continued leakage could result in low boron concentrations in the Safety Injection header, however, the REQUIRED ACTION listed is for Technical Specification LCO 3.4.13, RCS Operational Leakage, which has NOT been exceeded. B. Incorrect. Plausible because the action is correct, however, this valve is already open. C. Correct. This is the REQUIRED ACTION as outlined in Technical Specification LCO 3.4.14, RCS Pressure Isolation Valve Leakage. D. Incorrect. Plausible if thought that Technical Specification LCO 3.4.13, RCS Operational Leakage, has been exceeded.

Technical Reference(s) Technical Specification LCO 3.4.14 Attached w/ Revision # See Comments / Reference Technical Specification LCO 3.4.13 Proposed references to be provided during examination:None Learning Objective:

52829 EVALUATE plant conditions using Technical Specifications and determine the

required actions.

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 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 69 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.14 Amendment # 127 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 70 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.4.13 Amendment # 204 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 71 of 110 Rev g Comments /

Reference:

From SO23-15-57.A - 57A59 Revision # 7

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 72 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 068 A2.02 Importance Rating 2.8 Liquid Radwaste System: Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release Proposed Question: SRO 91 Given the following conditions on Unit 2 at 100% power:

A batch release was started the previous shift per SO23-8-7, Liquid Radioactive Release Operations, Attachment 2, Simplified Release of Radwaste Secondary Tank T-057. While reviewing the Release Permit you disco ver that the tank recirculation did not meet the volume requirement.

Which of the following:

1.) Describes the impact on the Liquid Effluent Release Limits?

2.) Actions are required to mitigate the situation?

A. 1.) Radiation Monitor alarm settings prevent exceeding limits. 2.) Stop the release and obtain a new release permit after a proper tank recirculation.

B. 1.) Radiation Monitor detector s ensitivity prevents exceeding limits. 2.) The release may be continued as long as the Liquid Effluent Radiation Monitoring instrumentation remains OPERABLE.

C. 1.) Offsite Dose Calculation Manual limits have been exceeded. 2.) Stop the release and evaluate Emer gency Plan entry based on the release rates. D. 1.) 10CFR20, Standards for Protection Against Radiation, have been exceeded. 2.) Stop the release and initiate an i mmediate notificati on to the NRC per SO123-0-A7, Notification and Reporting of Significant Events.

Proposed Answer: A

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 73 of 110 Rev g Explanation: A. Correct. Proper tank recirc is an ODCM mandated requirement prior to release and requires stopping the release and reevaluating conditions with a new permit and complete recirculation. B. Incorrect. Plausible if thought that Radiation Monitor detector sensitivity prevents exceeding the limits, however, proper tank recirculation is an ODCM mandated requirement prior to release and requires stopping the release. C. Incorrect. Plausible if thought that ODCM limits may have been exceeded and that E-Plan entry criteria were met, however, the Radiation Monitor setpoints do prevent exceeding the ODCM limits which are more conservative then E-Plan entry criteria. D. Incorrect. Plausible because it could be thought that 10CFR20 limits may have been exceeded and a report to the NRC was warranted, however, the radiation monitor setpoints do prevent exceeding the 10CFR20 limits which must be exceeded to warrant an NRC report.

Technical Reference(s) SO23-8-7, Attachment 2, Step 1.3 Attached w/ Revision # See Comments / Reference SO23-3-2.36, Attachment 4, L&S 1.14 ODCM, Table 1-1 Proposed references to be provided during examination:None Learning Objective:

56430 As the Control Room Supervisor, COORDINATE Radwaste processing and release activities per SO23-8-7 and SO23-8-15.

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, 5

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 74 of 110 Rev g Comments /

Reference:

From SO23-8-7, Attachment 2, Step 1.3 Revision # 17

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 75 of 110 Rev g Comments /

Reference:

From SO23-3-2.36, Attachment 4, L&S 1.14 Revision # 6 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 76 of 110 Rev g Comments /

Reference:

From ODCM, Table 1-1 Revision # 0

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 77 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 072 G 2.2.12 Importance Rating 4.1 Area Radiation Monitoring System: Equipment Control: Knowledge of surveillance procedures Proposed Question: SRO 92 Given the following conditions on Unit 2 at 100% power:

RI-7820-1, Containment High Range Area Monitor, is out of service. While performing Shiftly Surveillance, the OPERATE light for RI-7820-2, Containment High Range Area Monitor, is extinguished with the Mode Select Switch in OPERATE. RI-7820-2 OPERATE light bulb wa s verified to be working.

Which of the following REQUIRED ACTIONS should be implemented?

A. Submit a Special Report to the NRC withi n 14 days of the plan to restore one (1) channel to OPERABLE status.

B. Immediately start actions to restore a channel, initiate monitoring of radiation levels on the surface of Containment Building, and restore one (1) channel within 7 days.

C. Initiate a Unit Shutdown per the requirements of Technical Specification 3.0.3 and perform an NRC Notification within one (1) hour of initiation of the shutdown.

D. Initiate monitoring of Area Radiation Monitors outside Containment and restore an OPERABLE channel within 30 days.

Proposed Answer: B

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 78 of 110 Rev g Explanation: A. Incorrect. Plausible if thought that a 14 day report was required, however, LCS 3.3.102, Radiation Monitoring Instrumentation, requires initiating the pre-planned alternate which SO23-3-3.21, Common Shiftly Surveillances, defines as monitoring the outside Containment walls for radiation.

TS 3.3.11, Post Accident Monitoring Instrumentation, specifies that one channel be restored within

7 days. B. Correct. LCS 3.3.102, Radiation Monitoring Instrumentation, requires initiating actions immediately to restore one channel and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate the pre-planned alternate which SO23-3-3.21, Common Shiftly Surveillances, defines as monitoring the outside Containment walls for radiation. TS LCO 3.3.11, Post Accident Monitoring Instrumentation, also specifies that one channel be

restored within 7 days. C. Incorrect. Plausible if thought that not having any OPERABLE Containment High Range Radiation Monitors would require a plant shutdown which then would require the one hour notification, however, TS 3.3.11, Post Accident Monitoring Instrumentation specifies that one channel be

restored within 7 days and LCS 3.3.102, Radiation Monitoring Instrumentation, requires initiating actions immediately to restore one channel and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate the pre-planned alternate. D. Incorrect. Plausible if thought that the actions specified would be the appropriate pre-planned alternate described by LCS 3.3.102, Radiation Monitoring Instrumentation and that a 30 day ACTION would apply, however, LCS 3.3.102 requires initiating the pre-planned alternate which SO23-3-3.21, Common Shiftly Surveillances, defines as monitoring the outside Containment walls for radiation.

Technical Reference(s) SO23-3-3.21, Step 6.6.3 Attached w/ Revision # See Comments / Reference Licensee Controlled Specification 3.3.102.E Technical Specification Table 3.3.11-1 Technical Specification LCO 3.3.11 Proposed references to be provided during examination:None Learning Objective:

54872 APPLY all Administrative Requirements, Technical Specifications, and Action Statements for the Radiation Monitoring 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 4, 5

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 79 of 110 Rev g Comments /

Reference:

From SO23-3-3.21, Step 6.6.3 Revision # 33 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 80 of 110 Rev g Comments /

Reference:

From Licensee Controlled Specification 3.3.102.E Revision # 0 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 81 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.3.11 Amendment # 194 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 82 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.3.11, Table 3.3.11-1 Amendment # 194

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 83 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 2 Group # 2 K/A # 086 G 2.4.31 Importance Rating 4.1 Fire Protection System: Emergency Procedures/Plan: Knowledge of annunciator alarms, indications, or response procedures Proposed Question: SRO 93

Given the following conditions:

A fire has reportedly engulf ed Motor Control Center BQ. 10 minutes after arriving at the scene the Fire Department Incident Commander reports that the fire has not been contained.

Which of the following describes the r equired actions for these circumstances?

A. Trip Unit 2, enter SO 23-12-1, Standard Post Tr ip Actions, and declare an UNUSUAL EVENT due to the fire conditions.

B. Trip Units 2 and 3, enter SO23-12-1, Standard Post Trip Actions, and perform the Appendix R actions with one (1) hour time limit s of SO23-13-21, Fire.

C. Initiate SO23-13-2, Shutdown from Ou tside the Control Room, if spurious equipment operations occur and perform Time Critical actions of SO23-13-21, Fire.

D. Evaluate the need to reduce power on Unit 2 based on spurious equipment operation and perform Appendi x R Compensatory actions of SO23-13-21, Fire.

Proposed Answer: B

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 84 of 110 Rev g Explanation: A. Incorrect. Plausible if thought that this fire only affected Unit 2 and that 10 minutes was the E-Plan criteria for an UNUSUAL EVENT, however, the UE Classification requires that the fire is active for 15 minutes. SO23-13-21, Fire, directs that if the fire has not been contained within 10 minutes then both Units are tripped. B. Correct. This MCC contains equipment that can affect both Units and SO23-13-21, Fire, directs that if the fire has not been contained within 10 minutes then both Units are tripped and SO23-12-1, Standard Post Trip Actions, are performed. Additionally, SO23-13-21 actions with less than or equal to one hour time limits are performed. C. Incorrect. Plausible because it could be thought that for a fire in this area then SO23-13-2, Shutdown from Outside the Control Room would be invoked and the other actions stated would be correct, however, this is not one of the zones that direct SO23-13-2 actions. D. Incorrect. Plausible because for fires in other zones this would be a consideration and the compensatory actions are required, however, this area contains equipment affecting both Units.

Technical Reference(s) SO23-13-21, Step 4.4.4 & 4.4.7 Attached w/ Revision # See Comments / Reference SO23-13-21, Attachment 1, Page 53 SO23-13-21, Attachment 2, Page 153 SO123-VIII-1, Attachment 2, Tab E-1 Proposed references to be provided during examination:None Learning Objective:

53944 As the SRO, direct the operator response to a fire in the plant per SO23-13-21.

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 1, 5

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 85 of 110 Rev g Comments /

Reference:

From SO23-13-21, Step 4.4.4 Revision # 17 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 86 of 110 Rev g Comments /

Reference:

From SO23-13-21, Attachment 1, Page 53 Revision # 17 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 87 of 110 Rev g Comments /

Reference:

From SO23-13-21, Attachment 2, Page 153 Revision # 17

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 88 of 110 Rev g Comments /

Reference:

From SO23-13-21, Step 4.4.7 Revision # 17 Comments /

Reference:

From SO123-VIII-1, Attachment 2, Tab E-1 Revision # 29

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 89 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.5 Importance Rating 3.9 Conduct of Operations: Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Proposed Question: SRO 94

Given the following:

Unit 2 is in MODE 1. The shift is manned to the minimum composition per Appendix R. The shift has 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> remaining.

The 21 Watch has become ill and must l eave the site for emergency medical treatment.

Which of the following describes the require ments regarding the shift composition and required action in this situation?

A. The CRS may assume the responsibilitie s of the 21 Watch. The Shift Manager may perform concurrent SM/CRS duties until shift relief with a qualified STA on site.

B. The 21 Watch may NOT leave the site until minimum manning has been maintained by calling in a qualified relief.

C. Responsibilities of the 21 Watch may be turned over to the 22 Watch for the remainder of the shift.

D. The 21 Watch may leave the site immediately after turnover of responsibilities to another qualified person on shift. A repl acement must arrive within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Proposed Answer: D Explanation: A. Incorrect. Plausible because the crew may choose to assume responsibilities as they need to, however, a maximum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> below minimum manning is allowed. B. Incorrect. Plausible because if there is an emergency they may leave, however, the position must be filled within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. C. Incorrect. Plausible because the crew may choose to assume responsibilities as they need to, however, there is too much time left on shift (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) to not have a replacement. D. Correct. A medical emergency meets the requirements of an "unexpected absence" and the individual is allowed to leave. Immediate action must be taken to restore the shift complement to the minimum requirements.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 90 of 110 Rev g Technical Reference(s) SO123-0-A1, Attachment 2 Attached w/ Revision # See Comments / Reference Technical Specifications Section 5.2.2 Proposed references to be provided during examination:None Learning Objective:

55164 Given plant conditions, DETERMINE if license conditions have been violated per 10CFR50.54.

Question Source: Bank # 209194 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2009 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 91 of 110 Rev g Comments /

Reference:

From SO123-0-A1, Attachment 2 Revision # 26 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 92 of 110 Rev g Comments /

Reference:

From SO123-0-A1, Attachment 2 Revision # 26 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 93 of 110 Rev g Comments /

Reference:

From Technical Specifications Section 5.2.2 Amendment # 207

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 94 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.23 Importance Rating 4.6 Equipment Control: Ability to track Technical Specification limiting conditions for operations Proposed Question: SRO 95 Given the following conditions:

Unit 3 is at 4% power. Technical Specification Limiting Condition for Operations 3.0.3 is entered on October 19 at 0100. At 0130, a shutdown is commenced on Unit 3.

If MODE 3 is achieved at 0230 on Oct ober 19, when must MODE 5 be entered?

A. October 19 @ 1400 B. October 19 @ 1530 C. October 20 @ 1400 D. October 20 @ 1730 Proposed Answer: C Explanation: A. Incorrect. Plausible because this is 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> after LCO 3.0.3 was entered, however, this is the required entry time for MODE 4. B. Incorrect. Plausible because this is 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> after MODE 3 was achieved, however, the COMPLETION TIME starts when LCO 3.0.3 is entered. C. Correct. MODE 5 must be entered 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> after LCO 3.0.3 is declared, therefore, this is the correct COMPLETION TIME. D. Incorrect. Plausible if thought that the 37 hour4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> COMPLETION TIME started after MODE 3 was entered. Technical Reference(s) Technical Specification LCO 3.0.3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

55335 DESCRIBE the action to be taken if LCO 3.0.3 is entered.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 95 of 110 Rev g Question Source: Bank #

Modified Bank #74100 (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 2 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 96 of 110 Rev g Comments /

Reference:

From Technical Specification LCO 3.0.3 Amendment # 127 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 97 of 110 Rev g Comments /

Reference:

From SONGS Exam Bank #74100 Revision # 07/14/03 Given the following conditions: Unit 3 is in MODE 1. Technical Specification Limiting Condition for Operations 3.0.3 is entered on July 1 at 1200. At 1300 a Unit shutdown is commenced. If MODE 3 is achieved at 1600 on July 1, by what time on July 3 must MODE 5 be entered?

A. 0000 B. 0100 C. 2100 D. 2200 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 98 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.7 Importance Rating 3.6 Equipment Control: Knowledge of the process for conducting special or infrequent tests Proposed Question: SRO 96 Given the following conditions:

During the performance of troubleshooting via an Infrequently Performed Test Evolution (IPTE), it is noted t hat one of the Initia l Conditions is not appropriate for the existing plant conditions and the evolution is stopped. The Management Designee has determined that this represents a CHANGE OF INTENT from the stated Initial Conditions.

Which of the following should be done pr ior to proceeding with the test?

A. The Test Specialist makes Pen and Ink changes to the procedure.

B. A Procedure Modification Permit (PMP) to the procedure must be approved.

C. The Control Room Supervisor notes t he discrepancy on the official copy as a clarification.

D. The procedure is changed and receives t he same level of review and approval as the original.

Proposed Answer: D Explanation: A. Incorrect. Plausible because the Test Specialist is the person with the necessary technical expertise for conducting the test or evolution, however, a Change of Intent requires procedure rewrite. B. Incorrect. Plausible because a Procedure Modification Permit would be one of the documents required when dealing with a Change of Intent to a procedure, however, infrequently performed tests or evolutions require an additional margin of safety. C. Incorrect. Plausible because the control room supervisor exercises direct responsibility for plant safety, however, a Change of Intent is outside the bounds of their authority. D. Correct. As required by SO123-IT-1, Infrequently Performed Tests or Evolutions Controls Program.

Technical Reference(s) SO123-IT-1, Steps III.G, H, & I Attached w/ Revision # See Comments / Reference SO123-IT-1, Step IV.H Proposed references to be provided during examination:None ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 99 of 110 Rev g Learning Objective:

54798 Given an IPTE, DETERMINE the level of review required when the "intent" of the IPTE is changed per SO123-IT-1.

Question Source: Bank # 74626 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 55.43 3 Comments /

Reference:

From SO123-IT-1, Steps III.G, H, & I Revision # 12 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 100 of 110 Rev g Comments /

Reference:

From SO123-IT-1, Step IV.H Revision # 12

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 101 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.4 Importance Rating 3.7 Radiation Control: Knowledge of radiation exposure limits under normal or emergency conditions Proposed Question: SRO 97 Given the following conditions:

A GENERAL EMERGENCY has been declared due to a Loss of Coolant Accident with extremely high offsite radi oactive release rates. A worker attempting to isolate an uncontrolled release has sustained life-threatening injuries in a high dose area. The Emergency Response Organization is planning a rescue operation. The estimated exposure for the rescue is 35 REM.

In accordance with SO123-VIII-10, Emergency Coor dinator Duties, which of the following describes the restriction, if any, on attempting the rescue?

A. The rescue can NOT be attempted because the estimated exposure exceeds the federal limit for life saving operations.

B. A volunteer is desired, but not required, prior to proceeding wit h the rescue. If a volunteer cannot be located, an empl oyee may be chosen by the Emergency Coordinator.

C. The rescue may proceed without restricti on since the estimated exposure is less than the limit for life saving operations.

D. Due to the amount of expected exposure, the rescue may only proceed if a volunteer is available.

Proposed Answer: D Explanation: A. Incorrect. Plausible if thought that this restriction was still in place, however, the TEDE received may exceed 25.001 REM as long as someone has volunteered. B. Incorrect. Plausible because this condition is defined, however, only if the life-saving activity is greater than 10 but less than 25 REM. C. Incorrect. Plausible because the limit is greater than 25.001 REM, however, for this condition a volunteer is required. D. Correct. As required by SO123-VIII-10, Emergency Coordinator Duties, Step 6.7.7.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 102 of 110 Rev g Technical Reference(s) SO123-VIII-10, Step 6.7.7 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

54896 As the Emergency Coordinator, COORDINATE emergency response activities during implementation of the emergency plan per SO123-VIII-10.

Question Source: Bank # 127238 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2005B Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 4, 5 Comments /

Reference:

From SO123-VIII-10, Step 6.7.7 Revision # 26

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 103 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.6 Importance Rating 3.8 Radiation Control: Ability to approve release permits Proposed Question: SRO 98 Given the following conditions:

A Gaseous Waste release is planned for Unit 2. Wind direction is from the ocean.

Which of the following actions describes the status of the planned release in accordance with SO23-8-15, Gaseous Effluent Release?

The Gaseous Effluent Release...

A. should ONLY be initiat ed if wind speed is below the minimum required by a /Q calculation.

B. shall NOT be initiated until wind direction changes.

C. should ONLY be initiat ed if wind speed is above the minimum required by a /Q calculation.

D. is DESIRABLE and may commence without restriction.

Proposed Answer: C Explanation: A. Incorrect. Plausible because a /Q calculation must be performed, however, wind speed must be above the minimum required. B. Incorrect. Plausible because this is the most favorable, however, not necessarily the most practical. C. Correct. Per the Objective of Attachment 4 in SO23-8-15.

D. Incorrect. Plausible if thought that dosing the public was desirable.

Technical Reference(s) SO23-8-15, Attachment 4, Objective Attached w/ Revision # See Comments / Reference SO23-8-15, Attachment 7, Step 3.1 Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 104 of 110 Rev g Learning Objective:

56430 As the Control Room Supervisor, COORDINATE Radwaste processing and release activities per SO23-8-7 and SO23-8-15.

Question Source: Bank # 209098 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 55.43 4 Comments /

Reference:

From SO23-8-15, Attachment 4, Objective Revision # 17 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 105 of 110 Rev g Comments /

Reference:

From SO23-8-15, Attachment 7, Step 3.1 Revision # 17

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 106 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.40 Importance Rating 4.5 Emergency Procedures/Plan: Knowledge of SRO responsibilities in emergency plan implementation Proposed Question: SRO 99 Given the following conditions duri ng Emergency Plan implementation:

An ALERT has been declared. The Shift Manager has assumed responsibility as the Emergency Coordinator. The Emergency Offsite Facility and Te chnical Support Center are NOT yet activated.

Which of the following may the Emergency Coordinator delegate to another individual?

A. Reclassifying the event in progress.

B. Making Protective Action Recommendations.

C. Notifying Offsite Agencies.

D. Terminating the event when conditions are no longer met.

Proposed Answer: C Explanation: A. Incorrect. Plausible because once the event is classified it could be thought that another qualified individual would be allowed to perform this function, however, this is not allowed by SO123-VIII-10. B. Incorrect. Plausible if thought that on shift Health Physics personnel were available to perform this function, however, this is not allowed by SO123-VIII-10. C. Correct. The Emergency Coordinator may direct an operator to notify Offsite Agencies such as NRC Headquarters via the Red Phone. D. Incorrect. Plausible if thought that another qualified individual were allowed to perform this function, however, this is not allowed by SO123-VIII-10.

Technical Reference(s) SO123-VIII-10, Steps 4.2.2 & 5.1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None Learning Objective:

54888 DIRECT notifications of state and local agencies concerning emergency classification per SO123-VIII-10.

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 107 of 110 Rev g Question Source: Bank # 127039 Modified Bank #

(Note changes or attach parent) New Question History: Last NRC Exam SONGS 2005B Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments /

Reference:

From SO123-VIII-10, Step 4.2.2 Revision # 26 ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 108 of 110 Rev g Comments /

Reference:

From SO123-VIII-10, Step 5.1 Revision # 26

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 109 of 110 Rev g Examination Outline Cross-reference:

Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.44 Importance Rating 4.4 Emergency Procedures/Plan: Knowledge of emergency plan protective action recommendations Proposed Question: SRO 100 Given the following conditions:

During a declared emergency, the Emergency Coordinator determines there is a need to change the previous Protective Action Recommendation (PAR) for offsite personnel from "None" to "Evacuate the State Beach". The event classification remains unchanged.

What effect will this change in the PAR have on NOTIFICATIONS made to Offsite Agencies?

A. Changing the PAR requires a new set of verbal and hard copy notifications.

B. Notification of the c hange in PAR is required only if the event classification is also changed. C. A PAR change requires event reclassification and a new set of verbal but NOT hard copy notifications.

D. Changing the PAR requires only additional comments on the next hard copy notification form.

Proposed Answer: A Explanation: A. Correct. Reclassification, upgrade in PAR, or starting/stopping a radiological release requires a new set of verbal and printed notifications. B. Incorrect. Plausible if thought that this is the requirement, however, any change in Protective Action Recommendations requires a new set of verbal and printed notifications. C. Incorrect. Plausible because a new set of verbal notifications is required, however, a change in PAR does not necessarily require event reclassification. D. Incorrect. Plausible because a hard copy is required, however, it must be performed immediately.

Technical Reference(s) SO123-VIII-10, Step 6.8 Note & 6.8.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:None

ES-401 SONGS NRC 2010 SRO Written Exam Worksheet Form ES-401-5 Page 110 of 110 Rev g Learning Objective: 54890 / 54895 DETERMINE if plant conditions allow reclassification of an emergency event

per SO123-VIII-10. DETERMINE additional protective actions recommendation during implementation of the emergency plan per SO123-VIII-10.

Question Source: Bank # 73637 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 55.43 5 Comments /

Reference:

From SO123-VIII-10, Step 6.8 Note & 6.8.2 Revision # 26