ML093200611

2009-10 - Final Written Exam

ML093200611
Person / Time
Site:	San Onofre
Issue date:	11/16/2009
From:	Operations Branch IV
To:	Southern California Edison Co
References
50-361/09-302, 50-362/09-302, ES-401, ES-401-5, SO-09-10/05-206, SO-09-10/05-361
Download: ML093200611 (478)

Text

SONGS October 2009 NRC Written Examination Senior Reactor Operator Answer Key

1. A 26. C 51. A 76. C

2. B 27. A 52. D 77. B

3. B 28. B 53. D 78. C

4. A 29. B 54. A 79. A

5. D 30. C 55. C 80. C

6. A 31. D 56. D 81. D

7. A 32. D 57. A 82. A

8. D 33. B 58. C 83. C

9. B 34. C 59. D 84. D

10. B 35. D 60. C 85. D

11. D 36. A 61. A 86. A

12. C 37. D 62. B 87. B

13. A 38. D 63. B 88. A

14. D 39. B 64. D 89. D

15. C 40. C 65. D 90. A

16. A 41. B 66. A 91. B

17. B 42. D 67. D 92. A

18. C 43. A 68. B 93. B

19. A 44. D 69. C 94. A

20. C 45. C 70. D 95. C

21. B 46. D 71. B 96. C

22. C 47. B 72. A 97. B

23. B 48. C 73. A 98. C

24. B 49. C 74. B 99. A

25. C 50. D 75. C 100. A Answer Key Breakdown:

A = 26 B = 24 C = 25 D = 25 SONGS Oct 2009 SRO Written Exam Answer Key Rev 2d.doc

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 G 2.4.11 Importance Rating 4.0 Reactor Coolant Pump System: Emergency Procedures/Plan: Knowledge of abnormal condition procedures Proposed Question: Common 1 Which ONE (1) of the following is an entry condition listed in SO23-13-6, Reactor Coolant Pump Seal Failure?

A. Controlled Bleed-Off temperature is ABOVE normal.

B. Individual seal cavity temperature is RISING during heatup.

C. Controlled Bleed-Off header pressure is LOWERING.

D. Individual seal cavity pressure is RISING during heatup.

Proposed Answer: A Explanation:

A. Correct. As identified in SO23-13-6, Reactor Coolant Pump Seal Failure Entry Conditions.

B. Incorrect. Plausible because increasing seal cavity temperatures could be an indication of a failure, however, this is not an Entry Condition for SO23-13-6.

C. Incorrect. Plausible because Controlled Bleed-Off header pressure increasing is an Entry Condition for a Reactor Coolant Pump Seal Failure.

D. Incorrect. Plausible because rising seal cavity pressures could be considered an Entry Condition, however, not during a heatup as this would be an expected condition.

Technical Reference(s) SO23-13-6, Entry Conditions Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 1 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE normal and abnormal operations of the Reactor Coolant System.

94469 / 94468 INTERPRET instrumentation and controls utilized in the Reactor Coolant System.

Question Source: Bank # 75538 (See Comments)

Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2000 (replaced Distractor B)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-6 Entry Conditions Revision # 5 Comments /

Reference:

SONGS Exam Bank #75538 Revision # N/A Modified Distractor B from the following:

(1) Controlled Bleed-Off relief valve temperature constant.

Page 3 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 K1.10 Importance Rating 3.0 Reactor Coolant Pump System: Knowledge of the physical connections and/or cause-effect relationships between the RCPs and the following systems: RCS Proposed Question: Common 2 Given the following conditions with the Unit in MODE 5 with loops filled:

• Reactor Coolant System (RCS) temperature is 150°F.

• Steam Generator (SG) temperature is 260°F.

• No Reactor Coolant Pumps are running.

• The Pressurizer is solid.

Which ONE (1) of the following will result if the FIRST Reactor Coolant Pump is started with the conditions listed?

A. Excessive core lift.

B. An RCS pressure transient.

C. Excessive RCP stator temperatures.

D. Exceed RCS heatup limits.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because core lift is a concern when starting the 4th Reactor Coolant Pump, however, in this condition the 1st RCP is being started.

B. Correct. With RCS temperature less then the temperature listed in the Pressure Temperature Limits Report (PTLR) the Steam Generator to RCS T must be less than 100°F. This prevents an overpressure transient on the RCS when the RCP is started and the RCS heats up.

C. Incorrect. Plausible because RCP motor current would be high, however, starting current would only be lowered if the RCP were started at a higher temperature.

D. Incorrect. Plausible because RCS temperature would rise, however, there is insufficient Steam Generator mass to exceed a heatup limit.

Technical Reference(s) SO23-3-1.7, L&S 2.1 Attached w/ Revision # See SO23-5-1.03, Step 6.18.7 Comments / Reference Tech Spec LCO 3.4.7.4 SO23-5-1.3, L&S 4.1 and 4.2 Page 4 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: ANALYZE normal and abnormal operations of the Reactor Coolant System.

94469 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, 14 55.43 Comments /

Reference:

From SO23-3-1.7, L&S 2.1 Revision # 16 Page 5 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.3, Step 6.18.7 Revision # 32 Page 6 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Tech Spec LCO 3.4.7.4 Amendment # 203 Page 7 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.3, L&S 4.1 and 4.2 Revision # 32 Page 8 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 004 A2.25 Importance Rating 3.8 Chemical and Volume Control System: Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Uncontrolled boration or dilution Proposed Question: Common 3 Given the following conditions:

• Unit 2 is operating in MODE 1 with all systems aligned for normal automatic control when the following alarms are received:

• 58A04 - VCT LEVEL HI/LO.

• 58A14 - BORIC ACID PUMPS AUTO START FAILURE.

• 58A06 - BORIC ACID TO VCT FLOW HI/LO.

• All Reactor Coolant System parameters are stable at normal values.

Which ONE (1) of the following:

1.) Identifies the impact on the Chemical and Volume Control System?

2.) What action must be taken to mitigate the situation?

A. 1.) LT-0226, VCT Level Transmitter has failed high and the Boric Acid Pumps have stopped to prevent over boration of the RCS.

2.) Place FIC-0210Y, Boron Makeup Flow Controller in MANUAL to ensure boration remains secured.

B. 1.) LT-0226, VCT Level Transmitter has failed low and the selected Boric Acid Pump failed to start.

2.) Place HS-0210, Makeup Mode Selector in MANUAL to stop the uncontrolled dilution.

C. 1.) LT-0227, VCT Level Transmitter has failed high and the Boric Acid Pumps have stopped to prevent over boration of the RCS.

2.) Place FIC-0210Y, Boron Makeup Flow Controller in MANUAL to ensure boration remains secured.

D. 1.) LT-0227, VCT Level Transmitter has failed low and the selected Boric Acid Pump failed to start.

2.) Place HS-0210, Makeup Mode Selector in MANUAL to stop the uncontrolled dilution.

Page 9 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed Answer: B Explanation:

A. Incorrect. Plausible because the VCT HI / LO alarm would come in on a high failure of LT-0226 and it could be thought that a boration evolution would need to be stopped if in progress and placing FIC-0210Y in MANUAL would prevent normal boration.

B. Correct. VCT Level transmitter LT-0226 failing low causes Auto Makeup to initiate to the VCT and the failure of the selected Boric Acid Pump to start results in the pump failure and low flow alarms and is an indication that the only makeup flow is a dilution.

C. Incorrect. Plausible because the VCT HI / LO alarm would come in on a high failure of LT-0227 and placing FIC-0210Y in MANUAL could prevent an advertent boration.

D. Incorrect. Plausible because the Makeup Mode Selector should be placed in MANUAL, however, the failure of transmitter LT-0227 causes the Charging Pump suction to shift from the VCT to the RWST.

Technical Reference(s) SO23-15-58.A, 58A04 Attached w/ Revision # See SO23-15-58.A, 58A06 Comments / Reference SO23-15-58.A, 58A14 SD-SO23-390, Sect 2.2.21 & Figure I-1 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Chemical and 102549 Volume Control 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 10 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-58.A, 58A04 Revision # 10 Page 11 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-58.A, 58A06 Revision # 10 Page 12 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-58.A, 58A14 Revision # 10 Page 13 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Page 53 Revision # 17 Page 14 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Figure I-1 Revision # 17 Page 15 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 K5.03 Importance Rating 2.9 Residual Heat Removal System: Knowledge of the operational implications of the following concepts as they apply to the RHRS: Reactivity effects of RHR fill water Proposed Question: Common 4 Given the following conditions during Refueling:

• Unit 3 is in MODE 6 and core re-load has been completed.

• While filling and venting a portion of the out-of-service Shutdown Cooling Train, an inadvertent dilution occurred.

• This lowered Refueling Cavity and RCS boron concentration from 2672 ppm to 2587 ppm.

Which ONE (1) of the following describes the indications observed as a result of this dilution?

A. Slight rise in cavity level and a small rise in source range count rate.

B. Slight rise in Core Exit Thermocouple temperature and a doubling in source range count rate.

C. Small rise in dose rates around Shutdown Cooling Equipment and a small rise in source range count rate.

D. Small drop in dose rates around Shutdown Cooling Equipment and a doubling in source range count rate.

Proposed Answer: A Explanation:

A. Correct. The only level change will be associated with the amount of water added and the count rate changes would be small given that the previously existing shutdown margin was > 5% (Keff

.95) and the IBW would be about 105 ppm/% at BOL. There also would be no significant increase in N-16 gamma production to cause coolant dose rates to rise.

B. Incorrect. Plausible because it could be thought that the boron change was large enough to cause a doubling and cause an increase in nuclear heat, however, there would be no CET change until the Reactor was at the POAH.

C. Incorrect. Plausible because it could be thought that the change in core count rate would also be reflected in the coolant dose rate. There also would be no significant increase in N-16 gamma production to cause coolant dose rates to rise.

D. Incorrect. Plausible because dilution of the RCS could slightly reduce RCS specific activity and it could be thought that the boron change was large enough to cause a doubling.

Page 16 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) Operation Physics Summary, Fig 3.2-4 Attached w/ Revision # See LP 2AO711, Pages 13 & 14 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN how and why each of the following will change with successive equal 52680 positive reactivity insertions into a subcritical reactor: Factor by which count rate increases.

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 1, 5 55.43 Page 17 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Operation Physics Summary, Fig 3.2-4 Revision # 54 Page 18 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LP 2AO711, Page 13 Revision # 5-4 Page 19 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LP 2AO711, Page 14 Revision # 5-4 Page 20 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 K2.01 Importance Rating 3.0 Residual Heat Removal System: Knowledge of bus power supplies to the following: RHR pumps Proposed Question: Common 5 Given the following conditions:

• Unit 2 is at 100% power.

• Unit 3 is cooling down in MODE 4.

• 230 kV Switchyard is in a normal alignment.

• All 4160 VAC 1E Bus voltages have lowered to 3950 V.

After 30 seconds has elapsed, which ONE (1) of the following is the power supply to Unit 3 Shutdown Cooling Pump 3P016?

A. Reserve Auxiliary Transformer 2XR2 via Bus 2A06.

B. Emergency Diesel Generator 2G003 via Bus 2A06.

C. Emergency Diesel Generator 3G003 via Bus 3A06.

D. Reserve Auxiliary Transformer 3XR2 via Bus 3A06.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because the Reserve Auxiliary Transformer on the opposite Unit (2XR2) is the Preferred Power Source, however, when a degraded voltage exists on both Units (Switchyard in a normal alignment) this transfer would not take place.

B. Incorrect. Plausible because this power source would be available, however, it requires manual actions by the operator including operation of 50.54.X switches in the associated Switchgear Room. Additionally, Bus 3A06 EDG (3G003) would need to be INOPERABLE to take this action.

C. Incorrect. Plausible because had this condition lasted for longer than 110 seconds the Emergency Diesel Generator would be the source of power, however, power to Shutdown Cooling Pump 3P016 remains on the Reserve Auxiliary Transformer.

D. Correct. This is the power supply to Shutdown Cooling Pump 3P016 until the degraded voltage condition lasts for longer than 110 seconds.

Page 21 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-120, Page 109 Attached w/ Revision # See SD-SO23-120, Figure III-1 Comments / Reference SD-SO23-120, Page 154 SO23-15-63.C, 63C05 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the operation of the Pumps, Tanks, and remotely operated Valves of 79744 the CIS, CSS, and SIS. Include the controls, function, location, and specific features such as type, capacity, and power supplies where applicable.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 8 55.43 Page 22 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-120, Page 109 Revision # 19 Page 23 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-120, Figure III-1 Revision # 19 Page 24 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-120, Figure III-1 Revision # 19 Page 25 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-120, Page 154 Revision # 19 Page 26 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-63.C, 63C05 Revision # 8 Page 27 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006 K5.07 Importance Rating 2.7 Emergency Core Cooling System: Knowledge of the operational implications of the following concepts as they apply to ECCS: Expected temperature levels in various locations of the RCS due to various plant conditions Proposed Question: Common 6 Given the following conditions:

• A Large Break Loss of Coolant Accident (LOCA) has occurred.

• The break location is a Reactor Coolant System Hot Leg.

Which ONE (1) of the following would be the result if the steps of SO23-12-11, EOI Supporting Attachments, Attachment 11, Simultaneous Hot/Cold Leg Injection were performed immediately following the LOCA diagnosis?

A. Inadequate core cooling due to the loss of Safety Injection flow out the break.

B. Safety Injection flow through the core would be stopped.

C. Boration flow would be inadequate to maintain core SHUTDOWN MARGIN.

D. High Pressure Safety Injection Pumps would reach run out conditions.

Proposed Answer: A Explanation:

A. Correct. Failure to wait two hours prior to initiating Simultaneous Hot/Cold Leg Injection would result in an Inadequate Core Cooling situation. This is due to the fluid injected at the Hot Leg getting entrained in the steam leaving the break in the early period of the LOCA.

B. Incorrect. Plausible because Safety Injection flow from the Hot Leg would be impeded due to steam leaving the core area, however, Cold Leg flow would still be ensured.

C. Incorrect. Plausible because performing Attachment 11 would result in effectively reducing the boration rate, however, boration flow would still exceed the minimum required to maintain SDM.

D. Incorrect. Plausible because under certain core conditions the HPSI Pumps can exceed runout.

Attachment 11, Simultaneous Hot/Cold Leg Injection controls the flow rate through the Cold and Hot Leg Injection Valves to prevent this condition from occurring. This issue is addressed in SO23-12-11, Attachment 13.

Technical Reference(s) SO23-14-11, Attachment 11, Step 1a Bases Attached w/ Revision # See SO23-12-11, Attachment 11, Step 3 Caution Comments / Reference SO23-14-11, Attachment 13, Bases Page 28 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: Per the LOCA procedure SO23-12-3 DESCRIBE: The basis for each step, 54933 caution or note.

Question Source: Bank # 75372 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Page 29 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-11, Attachment 11, Step 1a Bases Revision # 2 Page 30 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 11, Step 3 Caution Revision # 6 Page 31 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-11, Attachment 13, Bases Revision # 2 Page 32 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007 K4.01 Importance Rating 3.3 Pressurizer Relief / Quench Tank System: Knowledge of the PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling Proposed Question: Common 7 Given the following condition:

• Annunciator 50A21 - QUENCH TANK TEMP HI has just alarmed.

Which ONE (1) of the following alignments is used to cool the Quench Tank?

The Quench Tank is...

A. drained to the Reactor Coolant Drain Tank and refilled with Primary Makeup Water.

B. vented to the Waste Gas System while the contents cool to ambient temperature.

C. drained to the Containment Sump and refilled with Primary Makeup Water.

D. vented and drained to the Radwaste Primary Tank using the Reactor Coolant Drain Tank Pumps.

Proposed Answer: A Explanation:

A. Correct. This is the guidance provided in Annunciator Response Procedure 50A21. There is no internal method used to cool the Quench Tank.

B. Incorrect. Plausible because this is the required action to address a high Quench Tank pressure, however, a high temperature requires drain and refill of the Quench Tank.

C. Incorrect. Plausible because the Primary Makeup Water Pump is used, however, the effluent is directed to the Reactor Coolant Drain Tank vice Containment Sump.

D. Incorrect. Plausible because this is where the coolant is pumped from the Reactor Coolant Drain Tank, however, this does not address the high temperature and cooling of the Quench Tank.

Technical Reference(s) SO23-15-50.A1, 50A21 Attached w/ Revision # See SD-SO23-360, Figure I-6 Comments / Reference SD-SO23-650, Figure 1 Proposed references to be provided during examination: None Page 33 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the configuration and operational characteristics of the Reactor 94467 / 94465 Coolant System components.

IDENTIFY Reactor Coolant System flowpaths, components and locations including being able to draw and label system diagrams.

Question Source: Bank # 127252 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 Comments /

Reference:

From SO23-15-50.A1, 50A21 Revision # 8 Page 34 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-360, Figure I-6 Revision # 17 Page 35 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-650, Figure 1 Revision # 12 Page 36 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 008 A2.04 Importance Rating 3.3 Component Cooling Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm Proposed Question: Common 8 Given the following conditions on Unit 2:

• All systems on both Units are aligned for normal MODE 1 conditions.

• Annunciator 57C50 - PROCESS/EFFLUENT/AREA RADIATION HI has alarmed from high radiation on 2RE-7819, CCW Non-Critical Loop Radiation Monitor.

Which ONE (1) of the following:

1.) Identifies a possible cause for the alarm?

2.) What action will be taken to mitigate the situation?

A. 1.) Waste Gas Compressor leakage into the Component Cooling Water System.

2.) Swap Waste Gas Compressors and isolate the CCW supply and return valves to the Waste Gas Compressors.

B. 1.) Radwaste Condensate Return Sample Cooler leakage into the Component Cooling Water System.

2.) Have Chemistry secure any sampling through the Radwaste Condensate Return Sample Cooler.

C. 1.) Control Element Drive Mechanism Cooler E404 leakage into the Component Cooling Water System.

2.) Shift Control Element Drive Mechanism Cooling Fans and isolate the CCW supply and return to E404.

D. 1.) Letdown Heat Exchanger leakage into the Component Cooling Water System.

2.) Secure Letdown and Charging and isolate the CCW supply and return to the Letdown Heat Exchanger.

Proposed Answer: D Page 37 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because a Waste Gas Compressor can leak into CCW and the isolation actions are correct, however, the compressors are normally aligned to Unit 3 Non-Critical Loop.

B. Incorrect. Plausible because the Radwaste Condensate Return Sample Cooler can leak into CCW and the isolation actions are correct, however, the Radwaste Condensate Return Sample Cooler is normally aligned to Unit 3 Non-Critical Loop.

C. Incorrect. Plausible because E404 is supplied by the Unit 2 Non-Critical Loop and the isolation actions are correct, however, the cooler is a CCW to low pressure air heat exchanger and could not leak into the CCW System.

D. Correct. The Letdown Heat Exchanger is a viable source based on pressure and activity potential and the actions are correct per SO23-13-7.

Technical Reference(s) SO23-13-7, Step 9 Attached w/ Revision # See SD-SO23-400, Figures 3 & 4 Comments / Reference SD-SO23-400, Page 10 Proposed references to be provided during examination: None Learning Objective: EXPLAIN the interfaces between the CCW System and other plant systems.

81027 / 81030 ANALYZE normal and abnormal operations of the CCW System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 38 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-7, Step 9 Revision # 13 Page 39 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-400, Figure 3 Revision # 18 Page 40 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-400, Figure 4 Revision # 18 Page 41 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-400, Page 10 Revision # 18 Page 42 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 008 G 2.4.46 Importance Rating 4.2 Component Cooling Water System: Emergency Procedures/Plan: Ability to verify that the alarms are consistent with plant conditions Proposed Question: Common 9 Given the following conditions with both Units operating at 100% power:

• Annunciator 64A26 - CCW SURGE TANK TRAIN A LEVEL HI/LO is in alarm on both Units.

• The following Component Cooling Water (CCW) parameters are reported:

• Unit 2 Train A Loop CCW Pump discharge pressure is 118 psig and CCW Surge Tank level is lowering.

• Unit 3 Train A Loop CCW Pump discharge pressure is 113 psig and CCW Surge Tank level is rising.

Which ONE (1) of the following would cause these alarms and indications?

A. Unit 2 and Unit 3 Train A CCW loops are cross-connected via Post Accident Cleanup Unit E370.

B. Unit 2 and Unit 3 Train A CCW loops are cross-connected via Emergency Chiller E336.

C. Unit 2 CCW Surge Tank fill valve is closed with a tube leak in the Unit 3 Letdown Heat Exchanger.

D. Unit 3 CCW Surge Tank fill valve is closed with a tube leak in the Unit 2 Letdown Heat Exchanger.

Proposed Answer: B Page 43 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it may be thought that the Spent Fuel Building CCW loads are common and may be swapped between Units similar to the Emergency Chiller, however, E370 is a Unit specific Train A load.

B. Correct. Emergency Chiller E336 can be supplied from either Unit 2 or Unit 3 Train A CCW.

There are no check valves and inter-unit leakage is a real potential.

C. Incorrect. Plausible because the pressure difference across the Unit 3 Letdown Heat Exchanger would cause a leak into CCW and Unit 3 level would rise, however, the fill valve being closed does not by itself explain Unit 2 level lowering.

D. Incorrect. Plausible because with or without a leak in the Letdown Heat Exchanger, the pressures listed would drive flow to the Unit 3 side causing the level transients described, however no cross-tie path is provided to explain this.

Technical Reference(s) SO23-13-7, Step 11a Attached w/ Revision # See SO23-2-17.1, Attachment 1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of CCW System 81028 / 81030 components.

ANALYZE normal and abnormal operations of the CCW System.

Question Source: Bank # 135049 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 Page 44 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-7, Step 11a Revision # 13 Page 45 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-17.1, Attachment 1 Revision # 15 Page 46 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010 K3.02 Importance Rating 4.0 Pressurizer Pressure Control System: Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RPS Proposed Question: Common 10 Given the following conditions at 100% power:

• HS-0100A, Pressurizer Pressure Channel Select Switch is selected to Channel X.

• PT-0100X, Pressurizer Pressure Control System pressure transmitter has failed low.

Assuming no operator actions, which ONE (1) of the following identifies the FIRST Reactor Protection System trip that will be actuated?

A. Low Departure from Nuclear Boiling Ratio.

B. High Pressurizer Pressure.

C. High Local Power Density.

D. Low Pressurizer Pressure.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because a low Pressurizer pressure is associated with a low DNBR, however, when this pressure transmitter fails low it turns all Heaters on and Pressurizer pressure will rise.

B. Correct. Failing this transmitter low energizes all Pressurizer Heaters, raising pressure until the high pressure trip setpoint is reached.

C. Incorrect. Plausible because low DNBR and high Local Power Density (LPD) trips are generated by Core Protection Calculators which have inputs including pressurizer pressure, however, pressure only affects DNBR trip setpoint, not LPD.

D. Incorrect. Plausible if thought that the pressure transmitter failing low would cause a low Pressurizer pressure trip.

Technical Reference(s) SD-SO23-360, Figure III-5 Attached w/ Revision # See SO23-SO23-710, Figures 1 & 8 Comments / Reference Proposed references to be provided during examination: None Page 47 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the response of the Plant Protection System to failures and alarms, 56622 including possible causes, effects on the system or overall plant, and operator actions to mitigate the effects.

Question Source: Bank # 128108 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 48 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-360, Figure III-5 Revision # 17 Page 49 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-710, Figure 8 Revision # 7 Page 50 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments / R eference: From SD-SO23-710, Figure 1 Revision # 7 Page 51 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012 K2.01 Importance Rating 3.3 Reactor Protection System: Knowledge of bus power supplies to the following: RPS channels, components, and interconnections Proposed Question: Common 11 Given the following conditions:

• Unit 2 is at 100% power.

• Pressurizer Level Control is selected to Channel X.

• Pressurizer Pressure Control is selected to Channel X.

If Vital 120 VAC Instrument Bus 2Y02 is deenergized, which ONE (1) of the following occurs?

A. All Pressurizer Proportional and Backup Heaters energize.

B. A Reactor trip will occur.

C. All three (3) Charging Pumps automatically start.

D. Control Element Assembly Calculator #1 fails.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because all Pressurizer Heaters will energize upon a loss of Vital 120 VAC Instrument Bus 2Y01 with Channel X in service.

B. Incorrect. Plausible because a Core Protection Calculator Auxiliary Trip will generate a Reactor trip, however, two channels are required. Only Channel B trips on the loss of Instrument Bus 2Y02.

C. Incorrect. Plausible because all Charging Pumps will start upon a loss of Vital 120 VAC Instrument Bus 2Y01 with Channel X in service.

D. Correct. Loss of Vital 120 VAC Instrument Bus 2Y02 will cause Control Element Assembly Calculator #1 failure.

Technical Reference(s) SO23-13-18, Attachment 2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 52 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the operation of Pressurizer Level Control System components, 56418 instrumentation, controls and alarms including function, location, interlocks, capacity and power supplies where applicable.

Question Source: Bank # 127140 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2006 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 53 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-18, Attachment 2 Revision # 8 Page 54 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-18, Attachment 2 Revision # 8 Page 55 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 K6.01 Importance Rating 2.7 Engineered Safety Features Actuation System: Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors Proposed Question: Common 12 Given the following conditions:

• Unit 2 is in MODE 1.

• PT-351A, Containment Narrow Range Pressure Transmitter has failed HIGH.

Which ONE (1) of the following describes the effects on the Plant Protective System if a second Containment Narrow Range Pressure Transmitter failed HIGH?

A. CIAS only actuates.

B. CIAS, SIAS and CSAS actuate.

C. CIAS, SIAS and CCAS actuate.

D. CIAS, SIAS, CSAS and CCAS actuate.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because it could be thought that only low Pressurizer Pressure actuated SIAS and that CCAS and CSAS actuation require SIAS actuation.

B. Incorrect. Plausible because it could be thought that with high Containment pressure and SIAS that CSAS would actuate and that the CCAS required a 2/4 signal from the wide range Containment pressure transmitters.

C. Correct. SIAS and CIAS will actuate on 2/4 narrow range Containment pressures at the high setpoint and when SIAS actuates then CCAS will actuate.

D. Incorrect. Plausible because it could be thought that with a failed high Containment pressure and SIAS, that CSAS and CCAS also would actuate however CSAS requires 2/4 from the wide range Containment pressure transmitters.

Technical Reference(s) SD-SO23-720, Figure 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 56 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the operation of the Plant Protection System components and 56627 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 7 55.43 Page 57 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Figure 1 Revision # 8 Page 58 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Figure 1 Revision # 8 Page 59 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 022 A1.04 Importance Rating 3.2 Containment Cooling System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Cooling water flow Proposed Question: Common 13 Given the following conditions:

• Unit 2 is in MODE 1.

• Train A Component Cooling Water System is in service with Train B Component Cooling Water System in standby.

Which ONE (1) of the following describes the normal flowpath alignment of Component Cooling Water (CCW) to the Containment Emergency Cooling Units (ECU)?

A. Train A ECU CCW Supply and Return Valves are open.

Train B ECU CCW Supply and Return Valves are open.

B. Train A ECU CCW Supply and Return Valves are open.

Train B ECU CCW Supply and Return Valves are closed.

C. Train A ECU CCW Supply Valves are closed and Return Valves are open.

Train B ECU CCW Supply Valves are open and Return Valves are closed.

D. Train A ECU CCW Supply Valves are open and Return Valves are closed.

Train B ECU CCW Supply Valves are closed and Return Valves are open.

Proposed Answer: A Explanation:

A. Correct. This is the correct lineup for ECU cooling water flow when in MODE 1 with one Train of Component Cooling Water in operation. Supply and Return Valves on both Trains are open with CCW flow through the two (2) Train A ECUs.

B. Incorrect. Plausible because Train B CCW is in standby, however, at a minimum the Train B Inlet Valves would be open per L&S 5.7.

C. Incorrect. Plausible because the Train B alignment would be considered correct, however, with the Unit in MODE 1 the Train A ECU Supply Valves would also be open.

D. Incorrect. Plausible because the Train A Supply Valves are open and that is required, however, Train A Supply Valves must also be open.

Page 60 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-2-17, Section 6.1 Attached w/ Revision # See SO23-2-17, L&S 2.18 and 5.7 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of CCW System 81028 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 61 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-17, Section 6.1 Revision # 27 Page 62 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-17, L&S 2.18 Revision # 27 Comments /

Reference:

From SO23-2-17, L&S 5.7 Revision # 27 Page 63 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026 A4.01 Importance Rating 4.5 Containment Spray System: Ability to manually operate and/or monitor in the control room: CSS controls Proposed Question: Common 14 Given the following conditions:

• Unit 3 is operating at 100% power in MODE 1.

• A spurious Containment Spray Actuation Signal has just initiated.

Which ONE (1) of the following occurs as a result of the Containment Spray Actuation Signal?

The Containment Spray Pumps...

A. receive an Auto Start signal; SI Pumps and Containment Spray Pumps Mini-Flow Valves open.

B. do NOT receive an Auto Start signal; RWST Outlet Valves open.

C. receive an Auto Start signal; Containment Spray Header Isolation Valves open.

D. do NOT receive an Auto Start signal; Containment Spray Header Isolation Valves open.

Proposed Answer: D Explanation:

A. Incorrect. Plausible if thought that CSAS started the Containment Spray Pumps. The Safety Injection and Containment Spray Mini-Flow Valves open on an SIAS.

B. Incorrect. Plausible because the Containment Spray Pumps will not start, however, it is the Containment Spray Header Isolation Valves that open not the RWST Outlet Valves.

C. Incorrect. Plausible because the Containment Spray Header Isolation Valves will open, however, and SIAS is required to start the Containment Spray Pumps.

D. Correct. Without any SIAS present the Containment Spray Pumps will not start. The Containment Spray Header Isolation Valves will open with a CSAS signal.

Technical Reference(s) SD-SO23-740, Section 2.3.2 Attached w/ Revision # See SD-SO23-720, Section 2.1.2 Comments / Reference SD-SO23-720, Appendix D SD-SO23-720, Figure 2C Page 64 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the instrumentation used to monitor the operation of the CSS and 79745 / 79749 SIS. Include the name, function, sensing points, normal values for the parameters being measured, and location of each instrument.

DESCRIBE the integrated operation of the CSS, and SIS.

Question Source: Bank # 75141 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 SD-SO23-740, Section 2.3.2 Revision # 17 Page 65 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Section 2.1.2 Revision # 8

\

Comments /

Reference:

From SD-SO23-720, Section 2.1.2 Revision # 8

\

Page 66 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Appendix D Revision # 8 Page 67 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Figure 2C Revision # 8

\

Page 68 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026 A2.01 Importance Rating 2.7 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: Reflux boiling pressure spike when first going on recirculation Proposed Question: Common 15 Given the following conditions:

• Unit 3 has experienced a Loss of Coolant Accident.

• All safety systems actuated as designed.

• The Recirculation Actuation Signal (RAS) setpoint has been reached.

• The crew is preparing to perform SO23-12-11, EOI Supporting Attachments, Attachment 14, RAS Operation.

Which ONE (1) of the following describes the affect that RAS operation has on plant parameters and the actions taken to ensure Critical Safety Functions are maintained?

A. The suction pressure to the High Pressure Safety Injection Pumps will be greater and result in flow approaching runout.

Throttle High Pressure Safety Injection Cold Leg Injection Valves to prevent runout.

B. The suction pressure to the Containment Spray Pumps will be greater and result in flow approaching runout.

Throttle the Containment Spray Flow Control Valves to prevent runout.

C. The water being used is hotter and could result in rising Containment pressure.

Verify Containment pressure is less than 14 psig or ensure proper Containment Spray actuation.

D. The water being used is hotter and could result in rising core temperatures.

Raise Safety Injection flow rate by restarting Low Pressure Safety Injection Pumps as required to restore subcooling.

Proposed Answer: C Page 69 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because suction pressure from the Containment Sump will be higher and result in higher flow. The action to throttle flow in this situation would be inappropriate.

B. Incorrect. Plausible because suction pressure from the Containment Sump will be higher and result in higher flow. The action to throttle flow in this situation would be inappropriate.

C. Correct. The higher temperature of the SI cooling flow will result in RCS temperatures and Containment pressure rising. Attachment 14 attempts to reduce this affect by maximizing Containment Cooling but Floating Step 12 instructs the operator to verify Containment pressure less than 14 psig or ensure CSAS actuation.

D. Incorrect. Plausible because core temperatures will rise initially but after RAS the actions to restart LPSI would be inappropriate and jeopardize the available NPSH to the HPSI and Containment Spray Pumps.

Technical Reference(s) SO23-12-11, Attachment 14 Attached w/ Revision # See SO23-12-11, Floating Step 12d Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the operation of the Pumps, Tanks, and remotely operated valves of 79744 / 79749 the CIS, CSS, and SIS. Include the controls, function, location, and specific features such as type, capacity, and power supplies where applicable.

DESCRIBE the integrated operation of the CSS, and SIS.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 70 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 14 Revision # 6 Page 71 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Page 72 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Floating Step 12d Revision # 6 Page 73 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 039 A4.01 Importance Rating 2.9 Main and Reheat Steam System: Ability to manually operate and / or monitor in the control room: Main steam supply valves Proposed Question: Common 16 Given the following conditions:

• Unit is in MODE 3 following a Reactor trip from 100% power.

• Containment pressure is 1.3 psig.

• Steam Generator E088 pressure is 720 psia.

• Steam Generator E089 pressure is 770 psia.

• RCS Tcold is 535°F.

• No operator actions have been taken post-trip.

Which ONE (1) of the following is the correct position for the listed valves?

1. HV-8204, Steam Generator E089 Main Steam Isolation Valve

2. HV-8205, Steam Generator E088 Main Steam Isolation Valve

3. HV-8421, Steam Generator E089 Atmospheric Dump Valve

4. HV-8423, Steam Bypass Control System Valve A. 1. Closed

2. Closed

3. Closed

4. Closed B. 1. Closed

2. Closed

3. Closed

4. Open C. 1. Open

2. Closed

3. Closed

4. Open D. 1. Closed

2. Open

3. Open

4. Open Page 74 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed Answer: A Explanation:

A. Correct. This is the correct configuration given current SG pressure.

B. Incorrect. Plausible because valves would be aligned as such if an MSIS had not occurred.

C. Incorrect. Plausible because given system pressure, it could be thought that the MSIV on E089 is still open along with the SBCS Valve.

D. Incorrect. Plausible because the SBCS Valve should be open and it could be thought that the Atmospheric Dump Valve could also be open given system temperature. Position of HV-8205 is incorrect.

Technical Reference(s) SD-SO23-720, Page 21 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: IDENTIFY Main Steam System flowpaths, components, and locations including 102427 / 102465 being able to draw and label system diagrams.

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

Question Source: Bank # 128014 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 75 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-720, Page 21 Revision # 8 Page 76 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059 G 2.1.27 Importance Rating 3.9 Main Feedwater System: Conduct of Operations: Knowledge of system purpose and/or function Proposed Question: Common 17 Given the following conditions:

• Unit 2 has tripped.

• Reactor Trip Override (RTO) actuated.

With NO operator action, which ONE (1) of the following identifies how the Main Feedwater Control System responds?

A. Each Main Feedwater Regulating Valve positions to 5% open.

B. Main Feedwater Pump speed lowers to 3600 rpm for 10 seconds.

C. All Feedwater Regulating Bypass Valves close.

D. Each Feedwater Regulating Bypass Valve positions to 25% open.

Proposed Answer: B Explanation:

A. Incorrect. Plausible if thought that Main Feedwater Regulating Valves did not fully close on an RTO. The 5% value refers to total Feedwater flow supply to the Steam Generators post-trip.

B. Correct. This is the response of the Main Feedwater Pump following a Reactor Trip Override.

C. Incorrect. Plausible because the Feedwater Regulating Valves close, however, the Feedwater Regulating Bypass Valves position to 50% open.

D. Incorrect. Plausible because the Feedwater Regulating Bypass Valves will reposition, however, they go to 50% open.

Technical Reference(s) LP 2XIR06, Section 6.3.3.2 Attached w/ Revision # See SO23-9-6, Section 6.6 and 6.7 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the operation of Feedwater Control System controls, including the 55260 / 52424 name, function, interlocks, and location of each.

STATE the names of the systems interfacing with the Feedwater Control System and DESCRIBE the flowpath and purpose of each interconnection.

Page 77 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4, 7 55.43 Comments /

Reference:

From LP 2XIR06, Section 6.3.3.2 Revision # 2 Page 78 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-9-6, Section 6.6 Revision # 21 Page 79 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061 A1.02 Importance Rating 3.3 Auxiliary/Emergency Feedwater System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: Steam generator pressure Proposed Question: Common 18 Given the following conditions:

• Emergency Feedwater Actuation Signals 1 and 2 (EFAS-1 & EFAS-2) have actuated following a trip from full power.

• A manual Main Steam Isolation Signal was actuated following reports of steam in the Turbine Building.

• Steam Generator E088 is at 750 psia and 15% narrow range level.

• Steam Generator E089 is at 795 psia and 18% narrow range level.

Under these conditions, which of the following Steam Generator(s) are being automatically fed by Emergency Feedwater Actuation Signals/Auxiliary Feedwater System?

A. Only Steam Generator E088.

B. Only Steam Generator E089.

C. Both Steam Generators E088 and E089.

D. Neither Steam Generator E088 nor E089.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because E088 has the lower level, and is below the setpoint for Diverse Emergency Feed Actuation Signal, however, DEFAS is not applicable (needs ATWS, and no MSIS present) and both SG levels are below the 21% EFAS actuation setpoint.

B. Incorrect. Plausible because it may be thought that with MSIS present, only the SG with the higher pressure will be fed, however, SG pressures must be below 741 psia and the difference must be at least 125 psi.

C. Correct. With EFAS-1 and 2 present, both SG pressures above 741 psia, and both SG levels below 21%, both SGs will be fed.

D. Incorrect. Plausible because if both SG pressures were below 741 psia (setpoint for MSIS), and pressures within 125 psia as listed, neither SG would be fed. However, the MSIS was manual and SG pressures are above 741 psi.

Page 80 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-780, Pages 77 & 83 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the instrumentation used to monitor the operation of the Auxiliary 52728 / 55262 Feedwater System, including the name, function, sensing points, normal values for the parameters being measured and location of each instrument.

DESCRIBE the cause/effect relationships associated with the following Auxiliary Feedwater System conditions/operations: The effect on EFAS components of an MSIS actuation.

Question Source: Bank # 129830 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 81 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-780, Page 77 Revision # 10 Page 82 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-780, Page 83 Revision # 10 Page 83 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061 K1.07 Importance Rating 3.6 Auxiliary/Emergency Feedwater System: Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: Emergency water source Proposed Question: Common 19 Given the following conditions:

• A seismic event has occurred and T-120, Condensate Storage Tank has ruptured.

• Unit 2 has tripped and a Loss of Offsite Power has occurred.

• Annunciator 53B58 - CONDENSATE TANK T-121 LEVEL HI / LO is in alarm.

• SO23-12-9, Functional Recovery Heat Removal Success Paths to provide makeup water to T-121, Condensate Storage Tank are being implemented.

With a REQUIRED cooldown rate of 110°F per hour to Shutdown Cooling System operation, which ONE (1) of the following is the preferred method for makeup to T-121, Condensate Storage Tank?

A. Makeup from the Demineralized Water Storage Tanks using the bypass around the Level Control Valve.

B. Directly from the hard-piped Fire Water Supply system.

C. Semi-automatic makeup from the T-120 vault using the Condensate Transfer Pump.

D. Cross-tie from Unit 3 Condensate Storage Tanks.

Proposed Answer: A Explanation:

A. Correct. Normal automatic makeup valves fail closed and require actions to manually align the bypass valves.

B. Incorrect. Plausible because it is an available method, however, it would be the least preferred method of refill.

C. Incorrect. Plausible because under certain conditions the T-120 vault could be aligned to the Condensate Transfer Pump, however, it is not the preferred method in this condition.

D. Incorrect. Plausible because a cross-tie is available from the Unit 3 Condensate Storage Tanks, however, this piping will divert water to the Unit 2 Hotwell not to T-121.

Page 84 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-12-9, Success Path HR-1, Step 10 Attached w/ Revision # See SO23-15-53.B, 53B58 Comments / Reference SD-SO23-320, Page 4 Proposed references to be provided during examination: None Learning Objective: Per the Functional Recovery procedure SO23-12-9 DESCRIBE: The basis for 55217 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 Page 85 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, HR-1, Step 10 Revision # 25 Page 86 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-53.B, 53B58 Revision # 16 Page 87 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-53.B, 53B58 Revision # 16 Page 88 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Page 89 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-320, Page 4 Revision # 13 Page 90 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 K3.02 Importance Rating 4.1 AC Electrical Distribution System: Knowledge of the effect that a loss or malfunction of the AC distribution system will have on the following: Emergency diesel generator Proposed Question: Common 20 Given the following conditions on Units 2 and 3:

• Low voltage alarms on Buses 2A04, 2A06, 3A04 and 3A06 are annunciating.

• All 1E Bus voltages are approximately 3750 VAC.

• No SIAS actuation is present on either Unit.

• All other equipment is OPERABLE.

Which ONE (1) of the following identifies how the Voltage Protection Circuits respond on Unit 2?

Unit 2 Emergency Diesel Generators...

A. will start; Unit 3 energizes Buses 2A04 and 2A06 via Bus Tie Breakers.

B. remain off; Unit 3 energizes Buses 2A04 and 2A06 via Bus Tie Breakers.

C. will start; 2G002 energizes Bus 2A04 and 2G003 energizes Bus 2A06.

D. remain off; Unit 2 continues to supply Buses 2A04 and 2A06.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because plausible because the EDGs will start, however, with a LOVS signal present the Preferred Source of power to the Unit 2 Buses is the Emergency Diesel.

B. Incorrect. Plausible because under normal conditions the preferred source of power to the Unit 2 Buses is unit 3, however, a Loss of Voltage Signal (LOVS) will start the Emergency Diesel.

C. Correct. Given the conditions listed, the EDGs will start and power their respective 1E Buses.

D. Incorrect. Plausible because if voltage had remained above 3796 VAC and < two minutes had expired (SDVS) the EDGs would not start and 1E Buses would remained energized from Unit 2.

Technical Reference(s) SO23-15-63.B, 63B05 Attached w/ Revision # See SD-SO23-120, Page 109 Comments / Reference Proposed references to be provided during examination: None Page 91 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE normal and abnormal operations of the Emergency Diesel Generators 53492 / 52795 (EDGs) System.

EXPLAIN the interfaces between the Emergency Diesel Generators (EDGs)

System and other plant systems.

Question Source: Bank # 112931 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 92 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-63.B, 63B04 Revision # 13 Page 93 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-63.B, 63B04 Revision # 13 Page 94 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-120, Page 109 Revision # 19 Page 95 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063 K4.02 Importance Rating 3.9 DC Electrical Distribution System: Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties Proposed Question: Common 21 With Unit 2 in MODE 1, which ONE (1) of the following describes the allowable lineup of B022, Swing Battery Charger?

A. Supply 1E DC Bus D1.

B. Supply Non-1E DC Bus D5.

C. Cross-tie 1E DC Buses D2 and D4.

D. Cross-tie 1E DC Buses D2 and Non-1E DC Bus D5.

Proposed Answer: B Explanation:

A. Incorrect. Plausible if thought that that the odd numbered DC buses were the ones supplied by Swing Charger B022, however, Swing Charger B022 supplies the even-numbered buses and DC Bus D5.

B. Correct. Swing Charger B022 supplies the even-numbered Buses and Non-1E DC Bus D5.

C. Incorrect. Plausible because these Buses can be cross-tied, however, there is a KIRK Key interlock between these two breakers preventing the Swing Battery Charger from supplying both Buses.

D. Incorrect. Plausible because both Buses are supplied from the Swing Battery Charger, however, there is a KIRK Key interlock between these breakers preventing the Swing Battery Charger from supplying both Buses.

Technical Reference(s) SD-SO23-140, Figure I-1 Attached w/ Revision # See SO23-6-15, Attachment 17 Comments / Reference Proposed references to be provided during examination: None Learning Objective: IDENTIFY Non-IE 120 VAC and 125 VDC Power Supply System flowpaths, 80702 / 80707 components, and locations including being able to draw and label system diagrams.

EXPLAIN the interfaces between the Non-IE 120 VAC and 125 VDC Power Supply System and other plant systems.

Page 96 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments /

Reference:

From SD-SO23-140, Figure I-1 Revision # 15 Page 97 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-140, Figure I-1 Revision # 15 Page 98 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-6-15, Attachment 17 Revision # 29 Page 99 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064 K2.02 Importance Rating 2.8 Emergency Diesel Generator System: Knowledge of bus power supplies to the following: Fuel oil pumps Proposed Question: Common 22 Which ONE (1) of the following is the power supply to Emergency Diesel Generator 2G003 Fuel Oil Priming Pumps?

A. 125 VDC to Panel 2D1-P1 B. MCC 2BJ C. 125 VDC to Panel 2L-161 D. MCC 2BQ Proposed Answer: C Explanation:

A. Incorrect. Plausible because DC Panel 2D1P1 is an ESF panel, however, it is powered from the Train A side.

B. Incorrect. Plausible because MCC 2BJ is powered from Bus 2B06 which can be supplied from EDG G003.

C. Correct. The Fuel Oil Priming Pumps power supply for EDG 2G003 is DC Panel L-161. The Main Fuel Oil Pumps are engine driven.

D. Incorrect. Plausible because MCC 2BQ is powered from Bus 2B04 which can be supplied from EDG 2G002.

Technical Reference(s) SD-SO23-750, Page 88 Attached w/ Revision # See SD-SO23-750, Figure III-1 Comments / Reference SD-SO23-140, Figure I-2A Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Emergency 73305 Diesel Generator Electrical Systems components.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Page 100 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /

Reference:

From SD-SO23-750, Page 88 Revision # 16 Page 101 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-750, Figure III-1 Revision # 16 Page 102 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-140, Figure I-2A Revision # 15 Page 103 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064 A2.08 Importance Rating 2.7 Emergency Diesel Generator System: Ability to (a) predict the impacts of the following malfunctions or operations on the EDG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of opening / closing breaker between buses (VARS, out of phase, voltage)

Proposed Question: Common 23 Given the following conditions:

• Emergency Diesel Generator (EDG) 3G002 is being paralleled to 1E Bus 3A04 which is aligned to the Reserve Auxiliary Transformer.

• 3G002 Output Breaker is closed with EDG voltage greater than 1E Bus 3A04 voltage.

Which ONE (1) of the following:

1.) Identifies the impact on the Emergency Diesel Generator?

2.) What action must be taken?

A. 1.) EDG VAR meter will move in the negative (-) VAR (BUCK) direction.

2.) ADJUST Voltage Regulator to establish a positive VAR load (+0.1 to +0.5 MVARS).

B. 1.) EDG VAR meter will move in the positive (+) VAR (BOOST) direction.

2.) ADJUST Voltage Regulator to establish a positive VAR load (+0.1 to +0.5 MVARS).

C. 1.) EDG VAR meter will move in the negative (-) VAR (BUCK) direction.

2.) ADJUST Voltage Regulator to establish a negative VAR load (-0.1 to -0.5 MVARS).

D. 1.) EDG VAR meter will move in the positive (+) VAR (BOOST) direction.

2.) ADJUST Voltage Regulator to establish a negative VAR load (-0.1 to -0.5 MVARS).

Proposed Answer: B Page 104 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because this would be the correct action if generator voltage were lower than Bus 3A04 voltage when the breaker was closed and it was desired to establish a positive VAR load.

B. Correct. With EDG voltage greater than bus voltage when the breaker is closed, a positive VAR load will be supplied out the Emergency Diesel Generator (known at SONGS as BOOST).

Because Diesel voltage is significant kindling greater than bus voltage, the Voltage Control Switch is adjusted to decrease generator terminal voltage and establish the VAR load specified.

C. Incorrect. Plausible if thought that this would be the correct action if generator voltage were lower than Bus 3A04 voltage when the breaker was closed and that it was desirable to establish a negative VAR load.

D. Incorrect. Plausible because the VAR meter will move in the positive direction, however, adjusting the Voltage Control Switch in this fashion will cause more VARs to be absorbed into the Generator.

Technical Reference(s) SO23-2-13, Attachment 2, Step 2.6 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: MONITOR the operation of the Diesel Generators per SO23-2-13.

56392 / 56520 SYNCHRONIZE a Diesel Generator to the 4 kV Bus per SO23-2-13 or SO23-3-3.23.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 105 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-13, Attachment 2, Step 2.6 Revision # 37 Page 106 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 073 A1.01 Importance Rating 3.2 Process Radiation Monitoring System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels Proposed Question: Common 24 Given the following conditions:

• Unit 3 is in MODE 6.

• Irradiated fuel movement is in progress.

• A spent fuel assembly is damaged while being transported to the spent fuel racks.

• RE-7822 and RE-7823, Fuel Handling Building (FHB) Air Exhaust Process Radiation Monitors high alarms have actuated.

Which ONE (1) of the following describes the resulting ventilation alignment and effect on radiation levels?

Fuel Handling Building normal...

A. supply fan trips, normal exhaust fan remains running, and PACUs align to lower radiation levels.

B. supply and exhaust fans trip and PACUs align to lower radiation levels.

C. supply fan remains on, normal exhaust fan trips and radiation levels lower.

D. supply and exhaust fans trip, and radiation levels remain the same.

Proposed Answer: B Page 107 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because this condition would create a negative pressure inside the FHB and radiation levels do lower because the PACUs are aligned, however, this alignment would allow a radioactive release.

B. Correct. With a Process Radiation Monitor high alarm the normal supply and exhaust fans will trip and PACUs will take suction from the FHB atmosphere and discharge back into the FHB to lower radiation level.

C. Incorrect. Plausible because this flowpath would suspend the release to atmosphere and adding air to the Fuel Handling Building could dilute the atmosphere, however, both of these fans trip.

D. Incorrect. Plausible because the normal supply and exhaust fans will trip, however, the PACUs are aligned to reduce radiation level.

Technical Reference(s) SD-SO23-435, Page 22 Attached w/ Revision # See SD-SO23-435, Figure 1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Fuel Handling 81409 / 81410 Building HVAC System components.

INTERPRET instrumentation and controls utilized in the Fuel Handling Building HVAC System.

Question Source: Bank # 127549 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2006 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 8 55.43 Page 108 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-435, Page 22 Revision # 3 Page 109 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-435, Figure 1 Revision # 3 Page 110 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 A4.02 Importance Rating 2.6 Service Water System: Ability to manually operate and/or monitor in the control room: SWS valves Proposed Question: Common 25 Which ONE (1) of the following describes the operation of the Train A Saltwater Cooling Heat Exchanger Outlet Valve (HV-6497)?

The Train A Saltwater Cooling Heat Exchanger Outlet Valve (HV-6497) _______________

when Saltwater Cooling Pump P-307 is auto started and _______________ when SWC Pump P-307 is stopped.

A. must be manually opened will automatically close B. will automatically open will automatically close C. will automatically open must be manually closed D. must be manually opened must be manually closed Proposed Answer: C Explanation:

A. Incorrect. Plausible because the valve could be manually opened upon SWC Pump auto start, however, there is no automatic closure associated with this valve.

B. Incorrect. Plausible because the valve will automatically open upon SWC Pump auto start, however, there is no automatic closure associated with this valve.

C. Correct. The CCW/SWC Heat Exchanger Outlet Valve will automatically open when the SWC Pump is started but must be manually closed to avoid an unacceptable failure mode.

D. Incorrect. Plausible because the valve must be manually closed upon SWC Pump start, however, there is no requirement for the valve to be manually opened.

Technical Reference(s) SO23-2-8, L&S 4.8 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 111 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: INTERPRET instrumentation and controls utilized in the Salt Water Cooling 60306 / 60307 System.

ANALYZE normal and abnormal operations of the Salt Water Cooling System.

Question Source: Bank # 127289 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 Page 112 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, L&S 4.8 Revision # 30 Page 113 of 113 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 G 2.1.25 Importance Rating 3.9 Service Water System: Conduct of Operations: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Proposed Question: Common 26 Given the following conditions:

• Unit 2 has been in MODE 1 for 7 days following a 40 day Refueling Outage.

• Spent Fuel Pool temperature is 92°F.

• Spent Fuel Pool level is 26 feet 4 inches.

• Component Cooling Water/Salt Water Cooling (CCW/SWC) Heat Exchanger E001 differential pressure is 10 psid.

• Salt Water Cooling injection temperature is 70°F.

Referring to SO23-2-8, Salt Water Cooling System Operation, Attachment 4, which ONE (1) of the following is the minimum required flow of CCW/SWC Heat Exchanger E001?

Minimum required flow is approximately...

A. 15,900 gpm.

B. 16,800 gpm.

C. 17,200 gpm.

D. 17,900 gpm.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because with the Normal Curve and 9 psid is referenced, the required resultant flow would be 16,600 gpm.

B. Incorrect. Plausible because if the wrong (reverse flow) Normal Curve is used instead of the proper Normal Curve, the required resultant flow would be 16,800 gpm.

C. Correct. Due to the time after the beginning of the Refueling Outage being greater than 45 days, the proper curve to use is the Normal Curve for normal system alignment (not reverse flowing).

With 10 psid, the curve arrives at 17,200 gpm.

D. Incorrect. Plausible because if the Alternate Curve is used the required resultant flow would be 17,900 gpm.

Page 1 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-2-8, Attachment 4 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: SO23-2-8, Attachment 4 Learning Objective: DESCRIBE the configuration and operational characteristics of Salt Water 60305 / 60307 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 10 55.43 Page 2 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, Attachment 4 Revision # 30 Page 3 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, Attachment 4 Revision # 30 Page 4 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, Attachment 4 Revision # 30 Page 5 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, Attachment 4 Revision # 30 Page 6 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-8, Attachment 4 Revision # 30 Page 7 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 K1.02 Importance Rating 2.7 Instrument Air System: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Service air Proposed Question: Common 27 Given the following conditions:

• Unit 2 is operating at 100% power with the Instrument Air system aligned for normal operations.

• Subsequently, an air leak upstream of the Instrument Air Dryers occurs.

• Instrument Air header pressure lowered to 85 psig and is currently 87 psig and steady.

Which ONE (1) of the following describes the current status of the Instrument Air System?

A. Three (3) Instrument Air Compressors are running fully loaded.

Service Air is maintaining Instrument Air via a pressure control valve.

B. Two (2) Instrument Air Compressors are running fully loaded.

Nitrogen Backup is maintaining Instrument Air via a pressure control valve.

C. One (1) Instrument Air Compressor is running fully loaded.

Two (2) Instrument Air Compressors are running half loaded.

Nitrogen Backup and Service Air is maintaining Instrument Air via pressure control valves.

D. Two (2) Instrument Air Compressors are running fully loaded.

One (1) Instrument Air Compressor is running half loaded.

Nitrogen Backup and Service Air is maintaining Instrument Air via pressure control valves and Instrument Air to Containment has closed.

Proposed Answer: A Page 8 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Lowering of Instrument Air header pressure to 85 psig caused all three Instrument Air Compressors to run fully loaded. The Service Air Pressure Control Valve opens at 88 psig.

B. Incorrect. Plausible because at least two Instrument Air Compressors are running fully loaded, however, the Instrument Air header would have to drop to 83 psig for Nitrogen Backup to actuate.

C. Incorrect. Plausible because three Instrument Air Compressors are running, however, they would all be at full load. Nitrogen Backup would not be in service because Instrument Air Header pressure did not drop low enough.

D. Incorrect. Plausible because three Instrument Air Compressors are running, however, they would all be at full load. Nitrogen Backup would not be in service because Instrument Air Header pressure did not drop low enough. Instrument Air to Containment is isolated for a different reason.

Technical Reference(s) SO23-13-5, Attachment 6, L&S 1.2 Attached w/ Revision # See SO23-1-1, Attachment 22, L&S 2.1 Comments / Reference SO2-15-61.C, 61C19 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Instrument 72865 / 72866 and Respiratory & Service Air Systems components.

INTERPRET instrumentation and controls utilized in the Instrument and Respiratory & Service Air Systems.

Question Source: Bank #

Modified Bank # 127082 (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 7, 10 55.43 Page 9 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-5, Attachment 6, L&S 2.1 Revision # 7 Page 10 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-1-1, Attachment 22, L&S 2.1 Revision # 19 Page 11 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO2-15-61.C, 61C19 Revision # 6 Page 12 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SONGS Exam Bank #127082 Revision 10/20/06 Given the following conditions:

• Unit 2 is operating at 100% power with the Instrument Air system aligned for normal operations.

• Subsequently, a valid Instrument Air Header Pressure Low alarm is received, due to an air leak.

• Instrument Air header pressure is currently 87 psig and steady.

Which ONE (1) of the following correctly describes the current status of the Instrument Air System?

A. Three Instrument Air Compressors are running fully loaded.

Nitrogen backup is maintaining Instrument Air via a pressure control valve.

B. Three Instrument Air Compressors are running fully loaded.

Service Air is maintaining Instrument Air via a pressure control valve.

C. Two Instrument Air Compressors are running fully loaded.

One Instrument Air Compressor is running half loaded.

Nitrogen backup is maintaining Instrument Air via a pressure control valve.

D. Two Instrument Air Compressors are running fully loaded.

One Instrument Air Compressor is running half loaded.

Service Air is maintaining Instrument Air via a pressure control valve.

Page 13 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103 A3.01 Importance Rating 3.9 Containment System: Ability to monitor automatic operation of the containment system, including: Containment isolation Proposed Question: Common 28 Which ONE (1) of the following valves receives a CLOSE signal on a Containment Isolation Actuation Signal?

A. Steam Generator Blowdown Isolation Valves.

B. Containment Sump Pump Discharge Isolation Valves.

C. Main Steam Valves to P140, Auxiliary Feedwater Pump.

D. Blended Makeup to Volume Control Tank Isolation Valves.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because these valves could allow contamination to escape Containment during a tube rupture, however, these valves are closed on an MSIS.

B. Correct. These valves are isolated on a CIAS.

C. Incorrect. Plausible because the Main Steam Isolation Valves are closed on a CIAS, however, these valves are not closed until an MSIS is received.

D. Incorrect. Plausible because this interfaces with Letdown, however, it is closed on an SIAS.

Technical Reference(s) SO23-3-2.22, Attachments 4, 11, and 17 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the flowpaths and major components of the CIS, CSS, and SIS 79743 utilized for normal and emergency operations.

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 Page 14 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 7, 9 55.43 Comments /

Reference:

From SO23-3-2.22, Attachment 17 Revision # 16 Page 15 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.22, Attachment 11 Revision # 16 Page 16 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.22, Attachment 4 Revision # 16 Page 17 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 002 K5.01 Importance Rating 3.2 Reactor Coolant System: Knowledge of the operational implications of the following concepts as they apply to the RCS:

Basic heat transfer concepts Proposed Question: Common 29 Given the following condition:

• During an outage, chemical cleaning is performed on Steam Generator tubes, and no tubes in either Steam Generator are plugged.

Given the same 100% Reactor power level before and after the outage, which ONE (1) of the following will be observed?

A. Turbine Governor Valves will be more OPEN than before the outage.

B. Turbine Governor Valves will be more CLOSED than before the outage.

C. Steam Generator T will be LARGER than before the outage.

D. Steam Generator T will be the SAME AS before the outage.

Proposed Answer: B Explanation:

A. Incorrect. Plausible if thought that cleaning of the Steam Generator tubes caused the U in Q =

UAT to increase. In this case, the T will be smaller and the Turbine Governor Valves would have to be opened further for the same power level.

B. Correct. Given the conditions listed, the Turbine Governor Valves will be more closed than before the outage at 100% power.

C. Incorrect. Plausible given the equation Q = UAT. If U decreases then T will be larger, however, cleaning the tubes causes U to increase and the T will decrease.

D. Incorrect. Plausible given the equation Q = UAT. If U increases then A would have to decrease to maintain T constant. Since cleaning the tubes causes U to increase without any associated change in A the T needs to decrease.

Technical Reference(s) LP 0HT122, Page 33 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 18 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: Given formulas applicable to heat transfer, and selected heat exchanger 53321 parameters, CALCULATE and/or PREDICT changes in heat transfer rate and/or heat exchanger inlet/outlet temperatures.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 19 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LP 0HT122, Page 33 Revision # 1-2 The value of U decreases as heat exchanger tube surfaces become fouled. This occurs because the effective thermal conductivity of the tubes is decreased and because the effective thickness of the tubes increases due to the foreign material which attaches itself to the tubes. An accepted method to monitor heat exchanger operation is to monitor changes in UA:

UA = Q / T When the value of UA has decreased below its minimum acceptable (design) value, the heat exchanger is removed from service and cleaned.

Page 20 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 015 A2.05 Importance Rating 3.3 Nuclear Instrumentation System: Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core void formation Proposed Question: Common 30 Given the following conditions:

• A Loss of Coolant Accident is in progress.

• Core Exit Saturation Margin is 10°F superheat.

Which ONE (1) of the following:

1.) Explains the reason for the indicated response(s) of the Source Range Nuclear Instruments if excessive voids are formed in the core due to inadequate core cooling?

2.) What action must be taken to mitigate the situation?

A. 1.) Count rates would LOWER due to more moderation within the core causing LESS fast leakage.

2.) Raise Steam Generator feeding rate.

B. 1.) Count rates would LOWER due to less moderation within the core causing MORE fast leakage.

2.) Open Pressurizer Vent Valves to restore Pressurizer level so that heaters can be energized.

C. 1.) Count rates would RISE due to less moderation within the core causing MORE fast leakage.

2.) Raise Steam Generator steaming rate.

D. 1.) Count rates would RISE due to more moderation within the core inserting positive reactivity to increase the shutdown power level.

2.) Lower Reactor Coolant System pressure to inject the Safety Injection Tanks.

Proposed Answer: C Page 21 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the action to take is correct, however, voiding causes a reduction in moderation and an increase in fast neutron leakage.

B. Incorrect. Plausible because most of the reason for voiding is correct, however, this action would only be taken if an excessive Core Exit Saturation Margin existed.

C. Correct. This is the correct reason for voiding and the correct action to perform per Attachment 5.

D. Incorrect. Plausible because this action is performed during an extended Station Blackout and count rate does rise, however, it is due to less moderation and more fast neutron leakage.

Technical Reference(s) SO23-12-11, FS-10 Attached w/ Revision # See SO23-12-11, Attachment 5 Comments / Reference LP 2LC750, Page 44 Proposed references to be provided during examination: None Learning Objective: ASSESS the response of the following instrumentation to changes in 53354 reactor vessel water level during degraded core conditions: Excore Nuclear Instrumentation.

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 Page 22 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, FS-10 Revision # 6 Page 23 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 5 Revision # 6 Page 24 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LP 2LC750, Page 44 Revision # 3-3 Page 25 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 016 A4.01 Importance Rating 2.9 Non-Nuclear Instrumentation System: Ability to manually operate and/or monitor in the control room: NNI channel select controls Proposed Question: Common 31 Given the following conditions:

• Unit 2 is operating at normal pressure, temperature and level with the Pressurizer Level Controller, LIC-0110 in LOCAL (Operator) Setpoint Control.

• All other Pressurizer level and pressure controls are in Automatic.

• A power descension is in progress.

While in LOCAL (Operator) Setpoint Control, which ONE (1) of the following describes how Pressurizer level is controlled?

Pressurizer level setpoint is...

A. automatically maintained as TAVE changes.

B. automatically maintained as Letdown flow changes.

C. adjusted based on level deviation from setpoint.

D. manually controlled by the Operator.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because TAVE changes will generate a deviation from setpoint, however, only when the controller is in REMOTE.

B. Incorrect. Plausible because as letdown flow changes pressurizer level will change, however, not in the reverse order.

C. Incorrect. Plausible because it could be thought that the deviation signal will prompt the operator to make level setpoint changes, however, SO23-3-10 directs the operator to follow Attachment 5 when in LOCAL (Operator) Setpoint Control.

D. Correct. The operator adjusts the LOCAL setpoint based on SO23-3-10, Attachment 5.

Technical Reference(s) SO23-3-1.10, Attachment 1, Step 1.2.1 Attached w/ Revision # See SO23-3-1.10, Attachments 5 and 8 Comments / Reference Page 26 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the process for performing Pressurizer Pressure and Level 56421 Control evolutions, including the consequences of misalignment or misoperations.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments /

Reference:

From SO23-3-1.10, Attachment 1, Step 1.2.1 Revision # 21 Page 27 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-1.10, Attachment 5 Revision # 21 Page 28 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-1.10, Attachment 8 Revision # 21 Page 29 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 029 K3.01 Importance Rating 2.9 Containment Purge System: Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on the following: Containment parameters Proposed Question: Common 32 Given the following conditions:

• The Unit is in MODE 4 with a cooldown to MODE 5 in progress.

• A Containment Mini-Purge is in progress.

• A Containment Mini-Purge Exhaust Isolation Valve fails closed.

• NO other Containment Mini-Purge components have repositioned.

• Current weather conditions are 75°F.

Which ONE (1) of the following Containment parameter changes can be observed within five (5) minutes if no operator action is taken?

A. Humidity level rises.

B. Temperature rises.

C. Radiation level rises.

D. Pressure rises.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because with exhaust isolated, humid air is still being added to Containment, but at a continuously reducing rate as pressure in Containment builds. Normal Containment Cooling would be reducing humidity.

B. Incorrect. Plausible because the flow of air being added to Containment via the Mini-Purge Supply is reduced, however, there is no forced cooling of this air and Containment Normal Cooling is still in service. Also, there is an RCS cooldown in progress.

C. Incorrect. Plausible because Mini-Purge Exhaust flow is reducing airborne radionuclide concentration and that flow has just been reduced. Over time normal RCS leakage would add radioactivity to the Containment atmosphere but this would not be observable in such a short time span.

D. Correct. With Mini-Purge Exhaust isolated and Mini-Purge Supply still in service, air volume is being added to Containment and Containment pressure would slowly but steadily rise.

Page 30 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-770, Figure 1 and 5 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: STATE the names of the systems interfacing with the CIS, CSS, and SIS 79747 and DESCRIBE the flowpath and purpose of each interconnection.

Question Source: Bank # 127145 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 9 55.43 Comments /

Reference:

From SD-SO23-770, Figure 1 Revision # 8 Page 31 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-770, Figure 5 Revision # 8 Page 32 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 035 K6.03 Importance Rating 2.6 Steam Generator System: Knowledge of the effect of a loss or malfunction on the following will have on the SGs: Steam generator level detector Proposed Question: Common 33 Given the following condition:

• Unit 2 is at 100% power with Main Feedwater controls in Automatic.

Which ONE (1) of the following describes the impact on Steam Generator E088 level control if Narrow Range Level Transmitter LT-1123-1 fails off-scale high?

Steam Generator E088 level control...

A. raises mean level signal value to the Feedwater Control System causing level to lower until operator manual actions are taken.

B. automatically excludes the failed channel from the mean average on poor quality and controls on the remaining good channels average.

C. automatically transfers to MANUAL control if deviation is greater than 7% narrow range.

D. generates a High Level Override signal to close the Feedwater Control Valves to E088.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because it could be thought that the FWCS would continue to average the signals and only provide alarms to alert the operator.

B. Correct. Three channels are compared and a poor quality signal would be discarded automatically from the average.

C. Incorrect. Plausible because it could be thought that a single channel failure would shift the FWCS to MANUAL, however, for this to occur there must be more than one failed channel.

D. Incorrect. Plausible because it could be thought that a single channel failure would result in generation of a HLO signal, however, it must be actual level to generate the HLO signal.

Page 33 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-250, Pages 59 & 73 Attached w/ Revision # See SO23-9-6, L&S 4.5 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the instrumentation used to monitor the operation of the 52830 Feedwater Control System, including the name, function, sensing points, normal values for the parameters being measured, and the location of each instrument.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 34 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-250, Page 59 Revision # 14 Page 35 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-250, Page 65 Revision # 14 Page 36 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-9-6, L&S 4.5 Revision # 12 Page 37 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 041 A2.03 Importance Rating 2.8 Steam Dump/Turbine Bypass Control System: Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of IAS Proposed Question: Common 34 Given the following conditions:

• Unit 3 experienced a complete Loss of Instrument Air and tripped from 100% power.

Which ONE (1) of the following:

1.) Describes the post-trip plant response?

2.) What action must be taken to mitigate the situation?

A. 1.) Steam Bypass Control Valves fail open and will NOT modulate closed as Steam Generator pressure lowers.

2.) Place the Master Controller in MANUAL to close valves.

B. 1.) Steam Bypass Control Valves fail closed until manually opened.

2.) Place the Master Controller in MANUAL and open as necessary to control Steam Generator pressure.

C. 1.) Steam Bypass Control Valves fail closed.

2.) Open the Atmospheric Dump Valves to restore Steam Generator pressure to normal.

D. 1.) Steam Bypass Control Valves fail as is.

2.) Place the Master Controller in MANUAL and close as necessary to control Steam Generator pressure.

Proposed Answer: C Page 38 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because placing the Master Controller in MANUAL would close the valves for most conditions, however, during a loss of Instrument Air the SBCS Valves fail closed.

B. Incorrect. Plausible because it could be thought that a backup nitrogen supply was available to operate the valves, however, only the Atmospheric Dump Valves have this feature.

C. Correct. All air is lost to the SBCS Valves and they fail closed. The Atmospheric Dump Valves are in MANUAL and CLOSED until the operator takes control per SO23-12-1, SPTAs.

D. Incorrect. Plausible because it could be thought that SBCS Valves would fail as is (which under normal conditions would be closed) to prevent a power excursion. If this were the case the action described would be correct if backup air were available.

Technical Reference(s) SO23-13-5, Attachment 2 Attached w/ Revision # See SO23-12-1, Step 8b RNO Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the cause/effect relationships associated with the following 54348 Steam Bypass Control System conditions/operations:

EFFECT on plant operation of a failure of the Steam Bypass Control 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, 10 55.43 Page 39 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-5, Attachment 2 Revision # 7 Page 40 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-1, Step 8b RNO Revision # 21 Page 41 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 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 35 Given the following conditions: C is a typo

• Unit 2 is operating at 100%.

• Annunciator C60A46 - SECONDARY RADIATION HI is in alarm.

• RE-7818, Low Range Air Ejector Radiation Monitor has alarmed and RE-7870, Wide Range Air Ejector Radiation Monitor has a rising trend but is not in alarm.

• A Steam Generator Blowdown Radiation Monitor is in alarm.

Which ONE (1) of the following correctly describes the current condition of A361, Steam Air Ejector Exhaust Unit and the proper operator response?

A. Flow has been automatically 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 A361, Steam Air Ejector Exhaust Unit. Place the Exhaust Unit Heater to ON.

C. Flow has been automatically 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 because it could be thought that this automatic feature exists, however, this action must be performed by the operator.

B. Incorrect. Plausible because it could be thought that this could be the normal alignment, however, this is not the normal alignment in order to preserve A361.

C. Incorrect. Plausible because it could be 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.

Page 42 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-15-60.A2, 60A46 Attached w/ Revision # See SD-SO23-190, Page16 Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given plant conditions, PREDICT and EXPLAIN the response of major 52660 plant systems, equipment and parameters to a steam generator tube rupture.

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, 10, 13 55.43 Page 43 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-60.A2, 60A46 Revision # 14 Page 44 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-190, Page 16 Revision # 11 Page 45 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 056 K1.03 Importance Rating 2.6 Condensate System: Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW Proposed Question: Common 36 Given the following conditions:

• Unit 2 is operating at 100% power.

• All Condensate Pumps are running.

• Condensate Pump P053 trips on overcurrent.

• Main Feedwater Pumps are in their normal alignment.

Which ONE (1) of the following describes the effect on the Main Feedwater Pumps?

A. Reheat Steam Supply Valves open and Main Feedwater Pump speed rises.

B. Reheat Steam Supply Valves close and Main Feedwater Pump speed lowers.

C. Main Steam Supply Valves open and Main Feedwater Pump speed rises.

D. Main Steam Supply Valves close and Main Feedwater Pump speed lowers.

Proposed Answer: A Page 46 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. With all four Condensate Pumps running at 100% power the trip of one Condensate Pump will lower suction pressure to the MFW Pump which will lower discharge pressure. With the lower discharge pressure less Feedwater will enter the Steam Generator, Steam Generator level will lower, and the Feedwater Control Valve will open to raise Steam Generator level. As the control valve opens valve differential pressure will lower and the Master Controller will send a signal to the MFW Pump to increase its speed. Given the conditions listed, the Reheat Steam Supply Valves control steam flow to the MFW Pump and open to raise MFW Pump speed.

B. Incorrect. Plausible because at this power level the Reheat Steam Supply Valves are in control, however, the valves would open and speed would rise.

C. Incorrect. Plausible because Main Feedwater Pump rises, however, at this power level the Reheat Steam Supply Valves are in control.

D. Incorrect. Plausible if thought that Main Feedwater Pump speed lower, however, at this power level the Reheat Steam Supply Valves are in control.

Technical Reference(s) SO23-9-6, Section 6.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Main 64706 Feedwater Pump and Turbine 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 47 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-9-6, Section 6.2 Revision # 21 Page 48 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 072 A1.01 Importance Rating 3.4 Area Radiation Monitoring System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls including: Radiation levels Proposed Question: Common 37 Which ONE (1) of the following Area Radiation Monitors (ARM) initiates an automatic actuation of equipment on increasing radiation levels?

A. RE-7851, Control Room General Area Radiation Monitor.

B. RE-7820, Containment High Range Radiation Monitor.

C. RE-7874, Main Steam Line Radiation Monitor.

D. RE-7839, PASS Lab Radiation Monitor.

Proposed Answer: D Page 49 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that this monitor what automatically realigned Control Room ventilation, however, it is a different monitor located inside the air plenum.

B. Incorrect. Plausible because it could be thought that this monitor would initiate a Containment Purge Isolation Signal, however, it is the Containment Airborne Radiation Monitors that perform this function.

C. Incorrect. Plausible because it could be thought that this monitor would close the Main Steam Isolation Valves, however, this monitor is used for indication only.

D. Correct. This monitor will isolate sampling to the Chemistry Lab and bypass the Sample Coolers on high radiation.

Technical Reference(s) SD-SO23-690, Page 60 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Radiation 103329 Monitoring System components.

Question Source: Bank # 75147 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 11 55.43 Page 50 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Page 60 Revision # 16 Page 51 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, FS-28, Step b1 Caution Revision # 6 Page 52 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 086 K6.04 Importance Rating 2.6 Fire Protection System: Knowledge of the effect of a loss or malfunction of the following will have on the Fire Protection System: Fire, smoke, and heat detectors Proposed Question: Common 38 Which ONE (1) of the following conditions will result following an inadvertent actuation due to a Fire Detection System failure?

A. Emergency Diesel Generator Building Pre-Action Sprinkler System pressurized dry pipe will depressurize and cause the deluge valve to open initiating flow.

B. Hydrogen Seal Oil System Water Spray System will actuate to pressurize the header and when a fusible link melts spray flow is initiated.

C. Main Turbine Bearing Boat HALON will actuate and flow is immediately initiated through open nozzles.

D. Computer Room Fire Dampers close and HALON is discharged.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because this type of pre-action system exists but not in the Emergency Diesel Generator Building.

B. Incorrect. Plausible because it could be thought that to preclude an inadvertent spray down of the Seal Oil Unit a second, confirmatory actuation should occur. This would be a pre-action type of system instead of the water spray system installed at SONGS.

C. Incorrect. Plausible because the statement is correct with the exception that the Main Turbine system uses carbon dioxide.

D. Correct. This is the correct sequence for an inadvertent actuation due to detector failure.

Technical Reference(s) SD-SO23-590, Pages 12, 14, 20, 69 & 70 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of Fire 107169 / 107170 Protection System components.

INTERPRET instrumentation and controls utilized in the Fire Protection System.

Question Source: Bank #

Page 53 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Page 54 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 12 Revision # 14 Page 55 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 14 Revision # 14 Page 56 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 20 Revision # 14 Page 57 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 69 Revision # 14 Page 58 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 70 Revision # 14 Page 59 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-590, Page 71 Revision # 14 Page 60 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 007 EK2.03 Importance Rating 3.5 Reactor Trip - Stabilization - Recovery: Knowledge of the interrelations between a reactor trip and the following: Reactor trip status panel Proposed Question: Common 39 Given the following conditions:

• An Anticipated Transient Without Scram (ATWS) has occurred on Unit 2.

• The Reactor Operator has opened the supply breakers to 2B15 and 2B16.

Which ONE (1) of the following describes the Reactor trip indication available on the Reactor Trip Status Panel?

1. MG Set Output Contactor RED lights _____.

2. UV WHITE lights _____.

3. Reactor Trip Circuit Breaker RED lights _____.

A. 1.) ON 2.) ON 3.) OFF B. 1.) OFF 2.) OFF 3.) ON C. 1.) ON 2.) OFF 3.) OFF D. 1.) OFF 2.) ON 3.) ON Proposed Answer: B Page 61 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because this is the indication available following a Reactor trip.

B. Correct. The MG set breakers open (green lights are illuminated), the UV lights extinguish, however, the RTCBs remain closed.

C. Incorrect. Plausible because the UV lights are extinguished, however, MG set red lights are off and the Reactor Trip Circuit Breakers are still closed with their lights illuminated.

D. Incorrect. Plausible because the MG set lights are extinguished and the RTCBs remain closed, however, when power is lost to the UV coils their respective lights extinguish.

Technical Reference(s) SD-SO23-710, Figure 2 Attached w/ Revision # See SD-SO23-520, Page 4 & Figure 2 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the inputs to the Plant Protection System, the purpose of each, 56628 / 56622 their trip setpoints and actuation logic.

DESCRIBE the response of the Plant Protection System to failures and alarms, including possible causes, effects on the system or overall plant, and operator actions to mitigate the effects.

Question Source: Bank # 128139 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 55.43 Page 62 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-710, Figure 2 Revision # 7 Page 63 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-520, Page 4 Revision # 6 Page 64 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-520, Figure 2 Revision # 6 Page 65 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 008 AK1.02 Importance Rating 3.1 Pressurizer Vapor Space Accident: Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure Proposed Question: Common 40 Given the following initial conditions:

• A Reactor Coolant System leak has occurred.

• Reactor Coolant System pressure is 2200 psia.

• Pressurizer level is 20% and lowering.

• The leak size is estimated at 500 gpm.

Current conditions:

• The Reactor Coolant System leak is determined to be a Pressurizer vapor space break.

• Reactor Coolant System pressure is 1600 psia.

• Pressurizer level is 50% and rising.

With the change in Reactor Coolant System pressure noted above, which ONE (1) of the following is the resultant Reactor Coolant System leak rate?

A. ~300 gpm.

B. ~375 gpm.

C. ~425 gpm.

D. ~500 gpm.

Proposed Answer: C Page 66 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 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 leakrate was based on a simple ratio/proportion calculation. In this instance 3/4ths the pressure would yield 1/4th the leak rate.

C. Correct. This question meets the KA because it tests the operator's understanding of the change in leakrate based on a change in pressure. Leak rate is proportional to the square root of the P.

1/4th the original pressure will correspond to a leak rate approximately 85% of the original leak rate. The operational implications of this are important when evaluating ability to keep the core covered.

D. Incorrect. Plausible if thought that the leak rate would not change because it is a vapor space leak and Pressurizer level is rising.

Technical Reference(s) NRC Exam Formula Sheet Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: NRC Exam Formula Sheet Learning Objective: Per the Reactor Coolant Leak procedure, SO23-13-14, DESCRIBE : The 54932 expected plant response for each step.

Question Source: Bank #

Modified Bank # 127170 (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 14 55.43 Comments /

Reference:

Square Root of Differential Pressure Calculation Revision # N/A Square root of 2200 psia = 46.9 psid Square root of 1600 psia = 40 psid therefore:

40 / 46.9 = .852 x 500 gpm = ~426 gpm Comments /

Reference:

Ratio & Proportion Calculation Revision # N/A 2200 psia / 1600 psia = 500 gpm / x gpm 800000 = 2200 x x = ~363 gpm Page 67 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Exam Bank #127170 Revision #10/23/06 Given the following initial conditions:

• A Reactor Coolant System leak has occurred.

• Reactor Coolant System pressure is 2200 psia.

• Pressurizer level is 20% and lowering.

• The leak size is estimated at 1000 gpm.

Current conditions:

• The Reactor Coolant System leak is determined to be a Pressurizer vapor space break.

• Reactor Coolant System pressure is 1100 psia and stable.

• Pressurizer level is 70% and rising.

Which ONE (1) of the following is the current approximate Reactor Coolant System leak rate?

A. ~300 gpm.

B. ~500 gpm.

C. ~700 gpm.

D. ~1000 gpm.

Page 68 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 009 EK2.03 Importance Rating 3.0 Small Break LOCA: Knowledge of the interrelations between the small break LOCA and the following: SGs Proposed Question: Common 41 Given the following conditions:

• A Small Break Loss of Coolant Accident is in progress.

• The Safety Injection Actuation Signal has actuated.

• All systems are operating as expected.

Per the stated conditions, which ONE (1) of the following is the basis for maintaining a secondary heat sink?

A. To minimize boron stratification of the RCS.

B. Cooling from the injection flow alone 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, Section 2.0 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 69 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: PREDICT and EXPLAIN the response of major plant systems, equipment 53006 and parameters to a loss of forced circulation Question Source: Bank # 75386 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2008 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Page 70 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-3, Section 2.0 Revision # 8 Page 71 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 011 EA1.05 Importance Rating 4.3 Large Break LOCA: Ability to operate and/or monitor the following as they apply to a large break LOCA: Manual and/or automatic transfer of suction of charging pump to borated source Proposed Question: Common 42 Given the following conditions:

• Unit 3 has experienced a large break Loss of Coolant Accident with initiation of SIAS and CIAS.

• Train A 4160 V Bus 3A04 was lost following a plant trip.

• 3LV-0227B, Volume Control Tank Outlet Valve failed to operate on SIAS.

• NO operator action has been taken.

Which ONE (1) of the following describes the status of boration flow to the Charging Pump suction?

A. Boric Acid Makeup Pumps are supplying adequate suction flow through 3HV-9247, Emergency Boration Block Valve.

B. Refueling Water Storage Tank is supplying adequate suction flow through 3LV-0227C, RWST to Charging Pump Suction Isolation.

C. Boric Acid Makeup Tanks are supplying adequate suction flow through 3HV-9240 and 3HV-9235, Gravity Feed Valves.

D. There is NO boric acid flow to the Charging Pump suction; the VCT continues to supply adequate suction head.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because it could be thought that the power loss did not affect the BAMU Pumps and Emergency Boration Valve. With this path aligned the failure of LV-0227B would have no affect.

B. Incorrect. Plausible because it could be thought that LV-0227C still had power and the RWST height of water would overcome the VCT.

C. Incorrect. Plausible because it could be thought that the BAMU Tank height of water would overcome the VCT or that there were two trains of isolation from the VCT outlet.

D. Correct. The Gravity Feed path is aligned but can not overcome the VCT NPSH.

Page 72 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-390, Appendix F, Various Pages Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the operation of the following Chemical and Volume Control 52868 / 53388 System controls, including the name, function, interlocks, and location of each: Boric Acid Makeup Pumps (P-174 & P-175) control.

DESCRIBE the cause/effect relationships associated with the following Chemical and Volume Control System conditions and/or operations: The effect on overall plant operation of transferring charging pump suction from the VCT to the RWST.

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 Page 73 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Appendix F, Page 184 Revision # 17 Page 74 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Appendix F, Page 185 Revision # 17 Page 75 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Appendix F, Page 186 Revision # 17 Page 76 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Appendix F, Page 192 Revision # 17 Page 77 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-390, Appendix F, Page 193 Revision # 17 Page 78 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 015/17 AA2.01 Importance Rating 3.0 RCP Malfunctions: Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause of RCP failure Proposed Question: Common 43 The following annunciators are received in the Control Room:

• 56C24 - RCP P001 SEAL PRESS HI/LO.

• 56B57 - RCP BLEEDOFF FLOW HI/LO.

The Reactor Operator reports the following for Reactor Coolant Pump P-001:

• Vapor seal cavity pressure = 75 psia.

• Upper seal cavity pressure = 1162.5 psia.

• Middle seal cavity pressure = 2250 psia.

Which ONE (1) of the following describes the event in progress?

A. Lower Seal only has failed.

B. Middle Seal only has failed.

C. Both Lower and Middle Seals have failed.

D. Both Lower and Upper Seals have failed.

Proposed Answer: A Explanation:

A. Correct. This is the correct seal failure diagnosis per SO23-13-6, Attachment 1.

B. Incorrect. Plausible because the Middle Seal is at RCS pressure, however, this is because the Lower Seal has failed. If this were true the Middle and Upper Seals would both be indicating 1162.5 psia.

C. Incorrect. Plausible because the Middle Seal is at RCS pressure it could be thought that both the Lower and Middle Seals have failed, however, if this were true the Upper Seal would be indicating 2250 psia.

D. Incorrect. Plausible because it could be thought that with the Middle Seal indicating RCS pressure it is the only seal currently working, however, if this were true the Upper Seal would be indicating 75 psia.

Page 79 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-6, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: Using SO23-13-6, Reactor Coolant Pump Seal Failure, DESCRIBE: The 55452 expected plant response for each Step.

Question Source: Bank # 126991 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, 5 55.43 Page 80 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-6, Attachment 1 Revision # 5 Page 81 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 025 AA2.05 Importance Rating 3.1 Loss of RHR System: Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Limitations on LPI flow and temperature rates of change Proposed Question: Common 44 Given the following conditions:

• Unit 2 entered MODE 5 two (2) days ago for a Refueling Outage.

• Train A Shutdown Cooling Pump tripped on overcurrent.

• Train B Shutdown Cooling Pump is being placed in service.

• The Shutdown Cooling System has been secured for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Which ONE (1) of the following identifies the:

• MINIMUM Shutdown Cooling System flow rate and

• MAXIMUM expected Shutdown Cooling System heatup rate when restoring the system to operation?

MINIMUM Shutdown Cooling System flow rate is __________ and MAXIMUM expected Shutdown Cooling System heatup rate is __________.

A. 2000 gpm 5°F per hour B. 2000 gpm 50°F per hour C. 2500 gpm 5°F per hour D. 2500 gpm 50°F per hour Proposed Answer: D Page 82 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that a 5°F/hr heatup rate is appropriate with the Unit in MODE 5, however, it has been demonstrated that a heatup rate can reach 50°F/hr.

B. Incorrect. Plausible because the expected heatup rate is correct, however, 2000 gpm is less than the Technical Specification minimum of 2200 gpm.

C. Incorrect. Plausible because the flow rate is correct, however, when securing Shutdown Cooling in this condition one would expect to see a heatup rate of up to 50°F/nr.

D. Correct. This is the minimum administrative limit for flow and maximum expected heatup rate when restoring the Shutdown Cooling System to service after temporary termination.

Technical Reference(s) SO23-3-2.6, Step 6.2.2 Caution Attached w/ Revision # See SO23-3-2.6, L&S 2.1 & 2.2 Comments / Reference SO23-5-1.3, L&S 4.4 Proposed references to be provided during examination: None Learning Objective: Given an operational condition addressed by a procedural precaution, 52628 limitation, of administrative requirement, STATE the limiting condition and the basis for that limiting condition for the Shutdown Cooling System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 83 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.6, Step 6.2.2 Caution Revision # 26 Page 84 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.6, L&S 2.1 & 2.2 Revision # 26 Page 85 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.3, L&S 4.4 Revision # 32 Page 86 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 026 AK3.02 Importance Rating 3.6 Loss of Component Cooling Water: Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of ESFAS Proposed Question: Common 45 Which ONE (1) of the following is the reason that the Containment Emergency Cooling Unit (ECU) Component Cooling Water (CCW) Inlet Valves are required to remain OPEN in MODES 1 through 4 even though they receive an open signal when a Containment Cooling Actuation Signal is initiated?

A. Assist Normal Containment Cooling during an accident.

B. Ensure sufficient Containment Cooling in the event Containment Spray fails to actuate.

C. Prevent thermally locking the ECU CCW Outlet Valves if Containment temperature rises during an accident.

D. Prevent Component Cooling Water Pumps from operating in a reduced flow condition.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because it could be thought that this system remains in operation until a Containment Isolation Actuation Signal is received, however, Normal Chill Water isolates on an SIAS.

B. Incorrect. The Containment Emergency Cooling Units provide the necessary protection in the event Containment Spray fails to actuate, however, that is not the reason why the CCW Inlet Valves are left open.

C. Correct. Per L&S 5.7 in SO23-2-17, there is a concern that the ECU Outlet Valves are susceptible to hydraulic locking if the CCW Inlet Valves are left closed in MODES 1 through 4.

D. Incorrect. Plausible because Component Cooling Water system alignment requires adequate flow to the pump, however, in an accident condition there is sufficient flow.

Technical Reference(s) SO23-3-2.22, Attachment 4 Attached w/ Revision # See SO23-2-17, L&S 2.16 and 5.7 Comments / Reference Proposed references to be provided during examination: None Page 87 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: Given an operational condition of the CSS, and SIS conditions addressed 79748 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Page 88 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.22, Attachment 4 Revision # 16 Comments /

Reference:

From SO23-3-2.22, Attachment 4 Revision # 16 Page 89 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-17, L&S 2.16 Revision # 27 Page 90 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-17, L&S 5.7 Revision # 27 Page 91 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 027 AK1.02 Importance Rating 2.8 Pressurizer Pressure Control System Malfunction: Knowledge of the operational implications of the following concepts as they apply to the Pressurizer Pressure Control Malfunctions: Expansion of liquids as temperature increases Proposed Question: Common 46 Given the following conditions:

• Unit 2 is at 100% power with Reactor Coolant System TCOLD on program.

• Pressurizer pressure control setpoint is 2250 psia.

• Pressurizer pressure is 2250 psia.

• Both Pressurizer Proportional Heaters are in service.

• All Pressurizer Backup Heaters are secured.

• Both Pressurizer Spray Valves are closed.

• One (1) Charging Pump is in service.

• A step change in Turbine Control Valve position results in the following:

• Reactor Coolant System TAVE rises 5°F.

• Pressurizer level rises 5%.

• Pressurizer pressure rises 75 psia.

Which ONE (1) of the following would be indicative of initial plant response to the above conditions?

A. Letdown flow will rise to MAXIMUM.

B. The running Charging Pump will STOP.

C. Letdown flow will isolate.

D. Both Pressurizer Spray Valves will go full OPEN.

Proposed Answer: D Page 92 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because Letdown flow will increase, however, it would take a +10.6% deviation for Letdown to be at MAXIMUM flow.

B. Incorrect. Plausible because the Backup Charging Pumps will STOP with a + 4% deviation, however, the Charging Pump in AUTO will continue to run.

C. Incorrect. Plausible if thought that this condition would isolate flow.

D. Correct. With a 50 psia rise in Pressurizer pressure, both Pressurizer Spray Valves go full OPEN.

Technical Reference(s) SD-SO23-360, Figures 3-9 & 3-16 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the cause/effect relationships associated with the Pressurizer 56419 Pressure and Level Control System and an increasing or decreasing Pressurizer pressure and/or level.

Question Source: Bank # 127315 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, 7 55.43 Page 93 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-360, Figure 3-9 Revision # 17 Page 94 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-360, Figure 3-16 Revision # 17 Page 95 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 029 EA2.07 Importance Rating 4.2 ATWS: Ability to determine or interpret the following as they apply to a ATWS: Reactor trip breaker indicating lights Proposed Question: Common 47 Given the following conditions on Unit 2 at 100% power:

• Several Reactor Protection System annunciators are received.

• Several Reactor Trip Circuit Breakers have opened.

• The Control Element Assemblies (CEAs) have NOT inserted.

If the plant is still at power with all CEAs fully withdrawn, which of the following OPEN trip breakers would indicate an Anticipated Transient without Scram (ATWS) condition exists?

Reactor Trip Circuit Breakers __________ indicate open.

A. 1, 2, 5, and 6 B. 1, 3, 5, and 7 C. 3, 4, 7, and 8 D. 1, 2, 3, and 4 Proposed Answer: B Explanation:

A. Incorrect. Plausible because it could be thought that this combination of trip breakers open should result in all rods being deenergized.

B. Correct. This combination of breakers being open should result in all rods being deenergized and the Reactor should trip.

C. Incorrect. Plausible because it could be thought that this combination of trip breakers open should result in all rods being deenergized.

D. Incorrect. Plausible because it could be thought that this combination of trip breakers open should result in all rods being deenergized.

Technical Reference(s) SD-SO23-710, Figure 2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 96 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Learning Objective: IDENTIFY the plant parameter, including trip value, used to actuate the 55846 / 56627 ATWS/DSS.

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 # 127053 (Changed Distractor C)

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 6 55.43 Page 97 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-710, Figure 2 Revision # 7 Page 98 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Exam Bank #127053 Revision # 10/20/06 Distractor C: Replaced RTCB #9 with RTCB #8 for better plausibility.

Page 99 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038 EK1.01 Importance Rating 3.1 Steam Generator Tube Rupture: Knowledge of the operational implications of the following concepts as they apply to the SGTR: Use of steam tables Proposed Question: Common 48 Given the following conditions:

• A Steam Generator Tube Rupture has occurred and both Steam Generators are being used to lower Reactor Coolant System temperature and pressure.

• Reactor Coolant System THOT was initially lowered to less than 530°F.

• The ruptured Steam Generator has been isolated.

• Step 12 of SO23-12-4, Steam Generator Tube Rupture for lowering Pressurizer pressure is being implemented.

• Ruptured Steam Generator pressure is currently 800 psia.

Which ONE (1) of the following is the HIGHEST acceptable temperature for RCS THOT when lowering Pressurizer pressure to within 50 psia of ruptured Steam Generator pressure while maintaining at least 20°F subcooling?

A. 460°F B. 480°F C. 500°F D. 520°F Proposed Answer: C Explanation:

A. Incorrect. Plausible because it could be thought that it was desirable to lower temperature to the point where subcooled margin was increased.

B. Incorrect. Plausible because it could be thought that it was desirable to lower temperature to the point where subcooled margin was increased.

C. Correct. With saturation pressure for 850 psia at 525°F, a target temperature of 500°F would still allow for sufficient subcooled margin.

D. Incorrect. Plausible because this temperature corresponds to a value close to 850 psia, however, it does not allow for any subcooled margin.

Page 100 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-12-4, Step 12 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: Given plant conditions, PREDICT and EXPLAIN the response of major 52660 plant systems, equipment and parameters to a steam generator tube rupture.

Question Source: Bank #

Modified Bank # 127066 (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 10, 14 55.43 Page 101 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-4, Step 12 Revision # 21 Page 102 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Exam Bank #127066 Revision # 10/20/06 A steam generator (SG) tube rupture has occurred and both SGs are being used to lower RCS temperature and pressure.

All the RCPs have been stopped due to a saturation margin of 20°F.

Step 12 (Lowering Pzr Pressure) of SO23-12-4, Steam Generator Tube Rupture, is being implemented.

If ruptured SG pressure is currently 600 psia, then an acceptable initial target temperature for RCS Thot would be:

A.525°F B.475°F C.425°F D.375°F Page 103 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055 G 2.2.44 Importance Rating 4.2 Station Blackout: 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: Common 49 Given the following conditions exist on Unit 3 two (2) hours after initiation of a Station Blackout:

• Reactor Coolant System pressure is 1850 psia.

• Core Exit Saturation Margin is 19°F.

• Reactor Coolant System THOT is 555°F and stable.

• Reactor Coolant System TCOLD is 535°F and stable.

• Representative Core Exit Thermocouple is 605°F.

• Reactor Vessel Level indicates 100%.

• Atmospheric Dump Valves are in service.

• P140, Turbine Driven Auxiliary Feedwater Pump is in service.

Which ONE (1) of the following describes the status of Core Heat Removal and required actions?

A. Natural Circulation Criteria are met.

MAINTAIN Atmospheric Dump Valve steaming rate to ensure subcooling between 10°F and 20°F.

B. Natural Circulation Criteria are NOT met.

REDUCE the steaming rate to MINIMIZE Reactor Coolant System inventory shrinkage and allow the Pressurizer pressure rise to recover subcooling.

C. Natural Circulation Criteria are NOT met.

INCREASE Atmospheric Dump Valve steaming rate to raise subcooling to greater than 20°F and lower REPCET - THOT T.

D. Two Phase Heat Removal Criteria are met.

RAISE Steam Generator narrow range levels to greater than 80% to MAXIMIZE heat removal capability.

Proposed Answer: C Page 104 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that Natural Circulation is met, however, the correct minimum Core Exit Saturation Margin is 20°F.

B. Incorrect. Plausible because Natural Circulation is not met and it could be thought that the RCS shrinkage aspect could be the overriding factor for recovering subcooling.

C. Correct. Given the conditions listed, these are the correct actions per SO23-12-8.

D. Incorrect. Plausible because given the conditions listed, two phase heat removal is in progress per the RNO column of Step 10 (REP CET minus Thot is > 16°F). Heat removal is maximized by raising Steam Generator level up to, but not greater than, 80% narrow range.

Technical Reference(s) SO23-12-8, Step 10 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the observable conditions used to verify the establishment and 53297 / 53125 maintenance of single phase natural circulation.

Explain the operational impact of post trip Reactor Coolant System natural circulation relative to: RCS cooldown rate.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 105 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-8, Step 10 Revision # 20 Page 106 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-8, Step 10 Revision # 20 Page 107 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056 AA2.20 Importance Rating 3.9 Loss of Offsite Power: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: AFW flow indicator Proposed Question: Common 50 Given the following conditions on a trip from 100% power EOC:

• A Loss of Offsite Power has occurred.

• Train A Emergency Diesel Generator has failed to start.

• Emergency Feedwater Actuation Signals (EFAS) 1 and 2 have both actuated.

• HV-8200, Main Steam Supply from Steam Generator E089 to P140, Turbine Driven Auxiliary Feedwater Pump failed CLOSED.

Which ONE (1) of the following is the expected Auxiliary Feedwater flow indication to each Steam Generator as read on the CR-52 lumigraph?

Auxiliary Feedwater flow indication for Steam Generator E088 is indicating _____ gpm; Auxiliary Feedwater flow indication for Steam Generator E089 is indicating _____ gpm.

A. 500 200 B. 500 500 C. 800 200 D. 800 500 Proposed Answer: D Page 108 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible if thought that Steam Generator E089 is receiving reduced low from P140 because its associated Main Steam Supply Valve is not open and Steam Generator E088 is receiving flow from P504 and reduced flow from P140.

B. Incorrect. Plausible because the flow value for Steam Generator E089 is correct, however, Steam Generator E088 is receiving flow from P504 and P140.

C. Incorrect. Plausible because Steam Generator E088 is receiving flow from P504 and P140, however, Steam Generator E089 is receiving full flow from P140.

D. Correct. Steam Generator E088 is receiving flow from P504 and P140. Steam Generator E089 is receiving flow from P140 only. Flow values were validated on the Simulator.

Technical Reference(s) SD-SO23-780, Figure 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the instrumentation used to monitor the operation of the 52728 Auxiliary Feedwater System, including the name, function, sensing points, normal values for the parameters being measured and location of each instrument.

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 Page 109 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 10 Page 110 of 111 Rev 2d

ES-401 SONGS Oct 2009 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 10 Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 10 Page 111 of 111 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 057 AK3.01 Importance Rating 4.1 Loss of Vital AC Instrument Bus: Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus Proposed Question: Common 51 Given the following conditions:

• SO23-13-18, Reactor Protection System Failure/Loss of a Vital Bus is in progress.

• Vital AC Instrument Bus Y01 has been lost due to Inverter failure with the Unit operating at power.

• SO23-6-17, Class 1E 120 VAC Vital Bus Power Supplies System Operation is in progress to energize the Alternate Source.

Which ONE (1) of the following actions is required?

A. OPERATE Charging Pumps as necessary to control Pressurizer level.

B. ACTUATE Train B FHIS, TGIS, CRIS and CPIS due to Train A FHIS, TGIS, CRIS and CPIS actuation.

C. VERIFY SG wide/narrow range levels and pressures for Channel D auto transfer into service and Channel A auto bypass out of service on Feedwater DCS.

D. TRANSFER Pressurizer Level to Channel X to allow restoring the Pressurizer Level Controller to AUTO.

Proposed Answer: A Explanation:

A. Correct. This action is required per SO23-13-18, Attachment 1.

B. Incorrect. Plausible because Train A FHIS, TGIS, CRIS and CPIS will actuate on a loss of Vital Bus Y01, however, the only action required is verification of proper alignment. Train B is not actuated.

C. Incorrect. Plausible because the Channel A Steam Generator levels and pressures must be bypassed on both Steam Generators, however, this action is performed manually by the operator.

D. Incorrect. Plausible because Pressurizer level must be transferred, however, Channel Y must be placed in service as it is powered from Vital Bus Y02.

Technical Reference(s) SO23-13-18, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 1 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: Per the Reactor Protection System Failure procedure, SO23-13-18, 55180 DESCRIBE: The expected plant response for each major step.

Question Source: Bank #

Modified Bank # 128051 (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 7, 10 55.43 Page 2 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-18, Attachment 1 Revision # 8 Page 3 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-18, Attachment 1 Revision # 8 Page 4 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SONGS 2008 NRC Exam Revision # N/A Given the following conditions:

• Vital Bus Y-02 has been lost due to Inverter failure with the Unit operating at power.

• Vital Bus Y-02 has not been energized from the Alternate Source.

Which ONE (1) of the following actions is required and the reason for that action?

A. TRANSFER Pressurizer Level Setpoint to Setpoint LS1 to allow restoring the Pressurizer Level Controller to AUTO.

B. Manually ACTUATE Train A FHIS, TGIS, CRIS and CPIS due to Train B FHIS, TGIS, CRIS and CPIS actuation.

C. VERIFY Auxiliary Feedwater flow to Steam Generator E088 due to EFAS Trip Paths 2 and 4 actuation.

D. CLOSE the failed open Atmospheric Dump Valve (HV-8421) due to loss of the pressure input from the Main Steam pressure transmitter.

Page 5 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 058 AK1.01 Importance Rating 2.8 Loss of DC Power: Knowledge of the operational implications of the following concepts as they apply to Loss of DC power:

Battery charger equipment and instrumentation Proposed Question: Common 52 Given the following conditions:

• Unit 2 is operating at 100% power with all systems aligned for normal operations.

• DC Buses are aligned to the Dedicated Battery Chargers.

• A loss of 480 VAC Bus B06 occurs.

Which ONE (1) of the following describes the current status of DC Buses 2D2 and 2D4?

A. 2D2 and 2D4 DC Buses each continue to be supplied by their respective Dedicated Chargers and 1E Batteries. Should be Charger here and below B. D2 is being supplied only by the 1E Battery and D4 is still supplied by its Dedicated Chargers and 1E Battery.

C. D4 is being supplied only by the 1E Battery and D2 is still supplied by its Dedicated Chargers and 1E Battery.

D. 2D2 and 2D4 are being supplied only by their respective 1E Batteries.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because it could be thought that the Dedicated Chargers were from an uninterruptible power source.

B. Incorrect. Plausible because it could be thought that only the Dedicated Charger to D2 was lost.

C. Incorrect. Plausible because could be thought that only the Dedicated Charger to D4 was lost.

D. Correct. Both Train B Dedicated Chargers are lost.

Technical Reference(s) SO23-13-26, Attachment 6 Attached w/ Revision # See SD-SO23-140, Figure I-2B Comments / Reference Proposed references to be provided during examination: None Page 6 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the configuration and operational characteristics of Non-IE 120 80703 / 80682 VAC and 125 VDC Power Supply System components.

STATE the functions and design bases of the Non-IE 120 VAC and 125 VDC Power Supply System and its components.

Question Source: Bank # 128052 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 7, 10 55.43 Page 7 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-26, Attachment 6 Revision # 8 Page 8 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-140, Figure I-2B Revision # 15 Page 9 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 062 G 2.4.35 Importance Rating 3.8 Loss of Nuclear Service Water: Emergency Procedures/Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects Proposed Question: Common 53 Given the following conditions:

• SO23-13-2, Shutdown from Outside of the Control Room is in progress due to a fire in the Unit 2 Control Room.

• The Radwaste Operator ensures that the Saltwater Cooling / Component Cooling Water (SWC/CCW) Heat Exchanger Outlet Valve is open.

Which ONE (1) of the following describes the reason this action is required?

A. A hot short due to fire could have caused Heat Exchanger Outlet Valve automatic closure and the associated SWC Pump is running at shutoff head.

B. A hot short due to fire could have caused Heat Exchanger Outlet Valve closure and SWC Pump trip. Opening Heat Exchanger Outlet Valve restarts the SWC Pump.

C. The CRS will be unable to start the SWC Pump from the Second Point of Control due to the interlock with the Heat Exchanger Outlet Valve being closed.

D. The CRS will be starting the SWC Pump from the Second Point of Control and the automatic opening feature is defeated with the Fire Isolation Switch in LOCAL.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because hot shorts can result in spurious equipment operation and it could be thought that there were no operator actions to secure the SWC Pump.

B. Incorrect. Plausible because hot shorts can result in spurious equipment operation and an interlock does exist between these components but no interlocks exist with the Fire Isolation Switch in LOCAL.

C. Incorrect. Plausible because an interlock does exist between these components but no interlocks exist with the Fire Isolation Switch in LOCAL.

D. Correct. As part of the local operator actions the Fire Isolation Switch is placed in LOCAL in order to start the SWC Pump. The automatic opening feature is defeated with the FIS in LOCAL.

Page 10 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-410, Page 9 Attached w/ Revision # See SO23-13-2, Attachment 2, Section 4.0 Comments / Reference SO23-13-2, Attachment 6, Step 17.3 SO23-13-2, Attachment 10, Section 7.0 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the purpose and operation of the Fire Isolation Switch for a 56671 given component.

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, 10 55.43 Comments /

Reference:

From SD-SO23-410, Page 9 Revision # 7 Page 11 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-2, Attachment 2, Section 4.0 Revision # 11 Comments /

Reference:

From SO23-13-2, Attachment 6, Step 17.3 Revision # 11 Page 12 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-2, Attachment 10, Section 7.0 Revision # 11 Page 13 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 065 AA2.03 Importance Rating 2.6 Loss of Instrument Air: Ability to determine and interpret the following as they apply to the Loss of the Instrument Air:

Location and isolation of leaks Proposed Question: Common 54 Given the following conditions:

• Unit 2 and 3 are experiencing a major air leak.

• The following Annunciators are in alarm:

• 61C19 - INST AIR HEADER PRESS LO.

• 61B38 - N2 SUPPLY TO INST AIR HEADER ON.

• 61C18 - SERVICE AIR HEADER PRESS LO.

• 61B39 - INST AIR DRYER TEMP/LEVEL/DP HI.

• 61B40 - INST AIR DRYER TROUBLE.

• The following indications are available:

• 2PI-5344A, Instrument Air Header Pressure on CR-61 indicates 65 psig and is slowly lowering.

• Two (2) Instrument Air Compressors are running loaded.

• One (1) Instrument Air Compressor is in standby.

• 2PI-5344B, Nitrogen Supply Header Pressure on CR-61 is steady.

• 2HV-5343 and 3HV-5343, Instrument Air Supply to Containment Excess Flow Check Valves are OPEN.

• Annunciator 57C58 - INSTRUMENT AIR TO CONTAINMENT is NOT in alarm on either unit.

• Flow indication to Unit 2 and Unit 3 are approximately the same.

Which ONE (1) of the following describes the condition that exists?

There is a major leak...

A. at the outlet of the Instrument Air Dryers.

B. at the inlet of the Instrument Air Dryers.

C. on one of the Instrument Air Receivers.

D. on the Instrument Air header going into the Fuel Handling Building.

Page 14 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Proposed Answer: A Explanation:

A. Correct. The leak location would cause all SA and IA compressors to run and cause the Hi D/P alarm on the dryer. The downstream pressure being constant indicates the N2 system is supplying.

B. Incorrect. Plausible because the leak before the IA Dryer would cause the dryer trouble alarm and other low pressure indications, however, it would not cause the IA Dryer Temp/Level/P alarms.

C. Incorrect. Plausible because it could be thought there was not a check valve at each receiver outlet and all compressors would feed the leak.

D. Incorrect. Plausible because it could be thought that the leak on the Fuel Bldg supply would also create the high P condition on the Dryer, however, the N2 Supply pressure would not be stable while IA header pressure was dropping; should indicate the same pressure for this leak.

Technical Reference(s) SD-SO23-570, Figure I-1 Attached w/ Revision # See SD-SO23-570, Pages 6 to 9 Comments / Reference SO23-13-5, Entry Conditions Proposed references to be provided during examination: None Learning Objective: ANALYZE normal and abnormal operations of the Instrument and 72867 Respiratory & Service Air Systems.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 15 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Figure I-1 Revision # 16 Page 16 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Figure I-1 Revision # 16 Page 17 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Page 6 Revision # 16 Page 18 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Page 7 Revision # 16 Page 19 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Page 8 Revision # 16 Page 20 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-570, Page 9 Revision # 16 Page 21 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-5, Entry Conditions Revision # 7 Page 22 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 007 AA1.05 Importance Rating 3.9 Generator Voltage and Electric Grid Disturbances: Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Engineered safety features Proposed Question: Common 55 Given the following conditions:

• Unit 2 is in MODE 1 at 100% power.

• Entry into SO23-13-26, Loss of Power to an AC Bus is required due to a loss of 4160 V Bus 2A08.

Which ONE (1) of the following identifies the action required per SO23-13-26, Loss of Power to an AC Bus?

A. ENERGIZE 1E Pressurizer Heaters as required due to loss of ALL Non-1E and Proportional Heaters.

B. ENSURE the standby Condensate Pump has started due to low Main Feedwater Pump suction pressure.

C. INITIATE a Containment Cooling Actuation Signal due to loss of the Containment Chillers.

D. REDUCE power to 65% due to loss of two (2) Circulating Water Pumps.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because the 1E Pressurizer Heaters must be operated, however, not all Pressurizer Backup Heaters are lost.

B. Incorrect. Plausible because the standby Condensate Pump would start on low discharge pressure or trip of a running Condensate Pump, however, this loss is associated with Bus A03.

C. Correct. A Containment Cooling Actuation Signal (CCAS) must be initiated in the Control Room because Normal Containment Cooling is lost.

D. Incorrect. Plausible because this is the required action per SO23-5-1.7, Power Operations, however, the Circulating Water Pumps are lost on a loss of 4160 V Bus 2A03 or 2A07.

Technical Reference(s) SO23-13-26, Attachments 8 & 12 Attached w/ Revision # See SO23-5-1.7, Attachment 5 Comments / Reference Proposed references to be provided during examination: None Page 23 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE plant and initial operator response to a loss of a Non-1E 4.16 54513 KV bus while at power in accordance with SO23-13-26.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 24 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-26, Attachment 12 Revision # 8 Page 25 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-26, Attachment 12 Revision # 8 Page 26 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-26, Attachment 8 Revision # 8 Page 27 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-26, Attachment 8 Revision # 8 Page 28 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.7, Attachment 5 Revision # 41 Page 29 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E05 EK2.2 Importance Rating 3.7 Steam Line Rupture - Excessive Heat Transfer: Knowledge of the interrelations between the Excess Steam Demand and the following: Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Proposed Question: Common 56 Given the following conditions while at 100% power:

• An Excess Steam Demand Event has occurred inside Containment.

• SO23-12-5, Excess Steam Demand Event directs stabilizing Reactor Coolant temperatures using the Atmospheric Dump Valve on the intact Steam Generator once dry out has occurred on the affected Steam Generator.

Which ONE (1) of the following is the reason for stabilizing Reactor Coolant System temperature?

A. Ensure minimum Reactor Coolant System Core Exit Saturation Margin is maintained.

B. Ensure consistent Reactor Coolant System loop temperatures to prevent loss of Auxiliary Feedwater flow due to high Steam Generator differential pressure.

C. Prevent the post-accident Reactor Coolant System cooldown rate from exceeding the limits in Technical Specifications.

D. Limit Reactor Coolant System heatup which may result in rapid re-pressurization and the onset of Pressurized Thermal Shock conditions.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because this is a desired condition during an ESDE, however, it is the heating of the Reactor Coolant System that is the major concern.

B. Incorrect. Plausible because an asymmetric cooldown is taking place, however, this situation is unavoidable and Auxiliary Feedwater flow can be overridden.

C. Incorrect. Plausible because the cooldown rate can be excessive dependent on ESDE severity, however, under most circumstances the Technical Specification cooldown limit is exceeded.

D. Correct. Limiting Reactor Coolant System heat up is paramount in avoiding Pressurized Thermal Shock conditions.

Page 30 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-12-5, Step 7 Caution Attached w/ Revision # See SO23-14-5, Step 7 Caution Bases Comments / Reference Proposed references to be provided during examination: None Learning Objective: Per the ESDE procedure SO23-12-5 DESCRIBE: The basis for each step, 54790 caution or note.

Question Source: Bank # 75360 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From SO23-12-5, Step 7 Caution Revision # 21 Page 31 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-5, Step 7 Caution Bases Revision # 8 Page 32 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 060 AA1.02 Importance Rating 2.9 Accidental Gaseous Radwaste Release: Ability to operate and/or monitor the following as they apply to the Accidental Gaseous Radwaste: Ventilation system Proposed Question: Common 57 Given the following conditions:

• A planned release of T086, Waste Gas Decay Tank is in progress.

• A high spike occurs on 2RE-7865, Wide Range Gas Monitor.

• 2/3HV-7202, Waste Gas Discharge Isolation Valve failed to close.

Which ONE (1) of the following would result in the closing of 2/3HV-7202, Waste Gas Discharge Isolation Valve?

A. LOSS of all Continuous Exhaust Fans (A310, A311 and A312).

B. INITIATE a Containment Purge Isolation Signal.

C. RAISE 2/3RE-7808, Plant Vent Stack Wide Range Monitor setpoint at the Data Acquisition System.

D. LOSS of both Radwaste Area Exhaust Fans (A192 and A193).

Proposed Answer: A Explanation:

A. Correct. Loss of the Continuous Exhaust Fans will close 2/3 HV-7202, Waste Gas Discharge Isolation Valve.

B. Incorrect. Plausible because 2RE-7865, Wide Range Gas Monitor can be aligned to initiate a CPIS, however, this action will not secure 2/3 HV-7202.

C. Incorrect. Plausible because 2/3RE-7808 is interlocked to close 2/3 HV-7202, Waste Gas Discharge Isolation Valve, however, raising the setpoint will not close the valve.

D. 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.

Technical Reference(s) SD-SO23-660, Figure 1 Attached w/ Revision # See SD-SO23-660, Page 17 Comments / Reference SD-SO23-622, Figure I-1 SD-SO23-690, Page 62 Page 33 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: ANALYZE normal and abnormal operations of the Gaseous Radwaste 56619 / 56617 System.

DESCRIBE the configuration and operational characteristics of Gaseous Radwaste 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 7 55.43 Page 34 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-660, Figure 1 Revision # 7 Page 35 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-660, Page 17 Revision # 7 Comments /

Reference:

From SD-SO23-622, Figure I-1 Revision # 2 Page 36 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Page 62 Revision # 16 Page 37 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 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 58 Which ONE (1) of the following states the reason the Steam Bypass Control System Valves close on Condenser low vacuum?

A. Prevent overfilling the Condenser Hotwells.

B. Protect the Main Turbine.

C. Prevent damage to the Condenser due to overheating.

D. Avoid damage due to differential pressure between Water Boxes.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because this situation can occur if water box differential pressure is high, however, the reason is to avoid Condenser overheating.

B. Incorrect. Plausible if thought that Main Turbine protection were the concern, however, the reason is to avoid Condenser overheating.

C. Correct. This is the reason for blocking SBCS on low Condenser vacuum.

D. Incorrect. Plausible because differential pressure between Water Boxes does impact plant operation, however, this is not the correct reason.

Technical Reference(s) SO23-15-52A, 52A19 Attached w/ Revision # See SD-SO23-175, Pages 27 & 32 Comments / Reference Proposed references to be provided during examination: None Learning Objective: INTERPRET instrumentation and controls utilized in the Main Steam 59226 System.

Question Source: Bank # 127199 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2005B Page 38 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /

Reference:

From SO23-15-52A, 52A19 Revision # 12 Page 39 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-175, Page 27 Revision # 6 Page 40 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-175, Page 32 Revision # 6 Page 41 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 032 G 2.1.27 Importance Rating 3.9 Loss of Source Range Nuclear Instrumentation: Conduct of Operations: Knowledge of system purpose and/or function Proposed Question: Common 59 Given the following conditions:

• Unit 2 is in MODE 6 with core re-load in progress.

• JI-0005, Startup Channel B has failed low.

• JI-0006, Startup Channel A remains OPERABLE.

Which ONE (1) of the following describes operating functions that are affected?

A. Potential loss of audible count rate and loss of input to Core Vibration Monitor.

B. Loss of one channel of Plant Protection System High Log Power Bypass and input to the Main Control Board SUR indication.

C. Loss of one channel of Boron Dilution Monitoring and loss of input to Core Vibration Monitor.

D. Loss of one channel of Boron Dilution Monitoring and loss of Remote Shutdown Panel indication.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because loss of audible count rate is correct, however, the non-safety channels do not input into the Main Control Board SUR indication.

B. Incorrect. Plausible if thought that these inputs were provided by the Startup Channels, however, these indications are provided by the Safety Channels.

C. Incorrect. Plausible because loss of Boron Dilution Monitoring is correct, however, the non-safety channels do not input into the Core Vibration and Loose Parts Monitors D. Correct. These functions are affected by failure of Startup Channel B.

Technical Reference(s) SD-SO23-470, Figures 1A and 1B Attached w/ Revision # See SO23-3-2.15, L&S 4.2.1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the Excore Nuclear Startup Channel System instrumentation Page 42 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 56475 and controls, including the name, function, location, interlock 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6 55.43 Page 43 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-470, Figure 1A (Safety Channel) Revision # 7 Page 44 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-470, Figure 1B (Non-Safety Channel) Revision # 7 Page 45 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.15, L&S 4.2.1 Revision # 13 Page 46 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # AK3.06 Importance Rating 3.6 Steam Generator Tube Leak: Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Normal operating precautions to preclude or minimize SGTR Proposed Question: Common 60 Both Unit 2 and Unit 3 operate with reduced TCOLD bands at power and Turbine Governor Valves full open.

Which ONE (1) of the following describes the reason for operating at reduced TCOLD?

Reduced RCS temperatures...

A. result in lower energy release on a Main Steam Line Break at EOL which reduces the challenge to peak Containment pressure limits.

B. minimize the fouling of the Steam Generator U-tubes which optimizes secondary side heat transfer.

C. lower U-tube degradation caused by Stress Corrosion Cracking extending Steam Generator life.

D. maintain the Condenser T limits associated with National Pollution Discharge Elimination Standards.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because there would be a reduction in the energy release on a MSLB but any change to prevent exceeding a design limit would be addressed by Technical Specifications not an administrative guideline.

B. Incorrect. Plausible because it could be thought that the corrosive film layer would be affected by the reduced temperature.

C. Correct. Due to Steam Generator metallurgy, operating with a reduced temperature minimizes Stress Corrosion Cracking.

D. Incorrect. Plausible because there is a limit on condenser differential temperature, however, reduced TCOLD is associated with stress corrosion cracking.

Technical Reference(s) SO23-5-1.7, LS-1.8 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 47 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the conditions that affect the severity of the steam generator tube rupture accident.

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 SO23-5-1.7, LS-1.8 (p77) Revision # 41 Page 48 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Page 49 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 059 AK2.01 Importance Rating 2.7 Accidental Liquid Radwaste Release: Knowledge of the interrelations between the accidental liquid Radwaste release and the following: Radioactive liquid monitors Proposed Question: Common 61 Given the following condition:

• The Preheater for 2/3E-354, Gas Stripper has developed a leak.

Which ONE (1) of the following Radiation Monitors would be the first to detect this leakage?

A. RE-7812, Radwaste Condensate Return Radiation Monitor.

B. RE-7819, Component Cooling Water Non-Critical Loop Radiation Monitor.

C. RE-7813, Liquid Waste Discharge Radiation Monitor.

D. RE-7870, Condenser Air Ejector Wide Range Radiation Monitor.

Proposed Answer: A Explanation:

A. Correct. Although RE-7870 & RE-7813 could eventually detect the leakage (and RE-7819 if a leak were to occur in this location) this is the first monitor to sense the outflow.

B. Incorrect. Plausible because the Sample Cooler for the Radwaste Condensate Return Radiation Monitor is cooled by CCW via the Non-Critical Loop, however, a leak would need to develop in that Sample Cooler in order for this detector to sense the leak.

C. Incorrect. Plausible because Condensate Return from the Gas Strippers can be directed to the Miscellaneous Test Tank which would then be released past Radiation Monitor RE-7813, however, it is not the first detector in the flowpath.

D. Incorrect. Plausible because Condensate Return from the Gas Strippers can be directed to the Main Condenser which would then be released past Radiation Monitor RE-7870, however, it is not the first detector in the flowpath.

Technical Reference(s) SD-SO23-650, Figures 1 & 2 Attached w/ Revision # See SD-SO23-690, Figures 8, 11, 12, & 13 Comments / Reference Proposed references to be provided during examination: None Page 50 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE normal and abnormal operations of the Radiation Monitoring 103331 / 103328 System.

EXPLAIN the interfaces between the Radiation Monitoring System and other plant systems.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 11 55.43 Page 51 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-650, Figure 1 Revision # 12 Page 52 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Figure 13 Revision # 11 Page 53 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-650, Figure 2 Revision # 12 Page 54 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Figure 11 Revision # 16 Page 55 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Figure 12 Revision # 16 Page 56 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-690, Figure 8 Revision # 16 Page 57 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 067 AA2.05 Importance Rating 3.2 Plant Fire on Site: Ability to determine and interpret the following as they apply to the Plant Fire on Site: Ventilation alignment necessary to secure affected area Proposed Question: Common 62 Given the following condition with Unit 2 in MODE 1:

• Annunciator 60A44 - COMPUTER ROOM SMOKE DETECTED is in alarm.

Which ONE (1) of the following describes the response to this alarm?

At Control Room Panel 2L-154, ensure the Smoke Exhaust Dampers between the Computer Room and the Control Room align to...

A. exhaust smoke from the Computer Room and that the Smoke Exhaust Fan is running.

B. isolate the Computer Room.

C. exhaust smoke from the Control Room and that the Smoke Exhaust Fan is running.

D. isolate the Control Room.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because it could be thought that the Smoke Exhaust Dampers would align to either the Control Room or Computer Room.

B. Correct. This is the correct response given the condition listed.

C. Incorrect. Plausible because it could be thought that the Smoke Exhaust Dampers would align to exhaust any smoke in the Control Room that might have escaped the Computer Room. This action would occur if the Control Room Smoke Detector alarmed.

D. Incorrect. Plausible because it could be thought that the Smoke Exhaust Dampers would align to isolate the Control Room from the source of smoke.

Technical Reference(s) SD-SO23-624, Page 10 Attached w/ Revision # See SO23-15-60.A2, 60A44 Comments / Reference SO23-15-60.B, 60B18 Proposed references to be provided during examination: None Page 58 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: EXPLAIN the interfaces between the Fire Protection System and other 73024 / 73027 plant systems.

ANALYZE normal and abnormal operations of the Fire Protection System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Page 59 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-624, Page 10 Revision # 1 Page 60 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-60.A2, 60A44 Revision # 14 Page 61 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-60.B, 60B18 Revision # 16-1 Page 62 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # A13 AK3.4 Importance Rating 3.1 Natural Circulation: Knowledge of the reasons for the following responses as they apply to the Natural Circulation Operations: RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facility license and amendments are not violated Proposed Question: Common 63 Given the following conditions:

• Unit 2 has experienced a Steam Generator Tube Rupture on E088.

• All Reactor Coolant Pumps are secured due to a Loss of Offsite Power.

• Steam Generator E088 has been isolated per SO23-12-11, EOI Supporting Attachments, Attachment 27, SGTR Actions.

• Cooldown to Shutdown Cooling is required and the following parameters exist:

• Pressurizer level is 5% and rising.

• Reactor Coolant System pressure is 1200 psia.

• Core Exit Saturation Margin is 21°F and rising.

• Steam Generator E088 narrow range level is 45% and stable.

• All ESFAS actuations occurred as designed.

Which ONE (1) of the following is required and the reason for this action?

A. Establish and maintain Pressurizer level at greater than or equal to 40% during cooldown to ensure adequate SHUTDOWN MARGIN.

B. Limit initial cooldown rates to 35-40°F per hour to optimize Natural Circulation flow in both loops.

C. Immediately reduce pressure using manual Auxiliary Spray to less than 1100 psia to prevent lifting Main Steam Safety Valves when E088 fills solid.

D. Throttle Safety Injection flow to prevent a Pressurized Thermal Shock condition with the ruptured Steam Generator isolated.

Proposed Answer: B Page 63 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that this strategy is required for Natural Circulation cooldown, however, this is the strategy for a Natural Circulation cooldown during a Control Room Evacuation.

B. Correct. This strategy is required for Natural Circulation cooldown as identified in SO23-12-11, Attachment 3, Step 1g Note.

C. Incorrect. Plausible because for an uncontrolled increase in the isolated SG level this action would be directed, however, this pressure is not low enough to keep a Main Steam Safety Valve from lifting. The first MSSV lifts at 1105 psig.

D. Incorrect. Plausible because with the SG isolated RCS conditions are recovering and it could be thought that throttle conditions had been established and actions to prevent PTS conditions are warranted.

Technical Reference(s) SO23-12-11, Attachment 27, Step 7 Caution Attached w/ Revision # See SO23-13-2, Attachment 16, Step 1 Note Comments / Reference SO23-12-11, Attachment 3, Step 1d Caution SO23-12-11, Attachment 3, Step 1g Note Proposed references to be provided during examination: None Learning Objective: EXPLAIN how each of the following can affect single-phase natural 53298 circulation: Primary-to-secondary heat transfer rate.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 64 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 27, Step 7 Caution Revision # 6 Page 65 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-2, Attachment 16, Step 1 Note Revision # 11 Page 66 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 3, Step 1d Caution Revision # 6 Page 67 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 3, Step 1g Note Revision # 6 Page 68 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # A16 AA1.1 Importance Rating 3.4 Excess RCS Leakage: Ability to operate and monitor the following as they apply to the Excess RCS Leakage: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Proposed Question: Common 64 Added MISALIGNED to correct title of Given the following conditions on Unit 2:

alarm window

• The following Annunciators are in alarm:

• 57C43 - RCS LEAKAGE ABNORMAL/RECIRC SYS VLV.

• 56A56 - CONTAINMENT SUMP LEVEL HI.

Which ONE (1) of the following statements identifies the operation of the Containment Sump Pumps in this condition?

A. A Pump is running and will AUTO Stop on low level or SIAS/CIAS actuation.

B. A Pump will AUTO start when level reaches the HI-HI alarm and will AUTO Stop on low level or SIAS/CIAS actuation.

C. They will AUTO start when both Discharge Line Isolation Valves are opened and will AUTO Stop on low level.

D. They must be started manually after opening both discharge valves and will AUTO Stop on low level.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because the pumps automatically stop on low level and it could be thought that the pumps would start on a high level alarm.

B. Incorrect. Plausible because the pumps automatically stop on low level and it could be thought that the pumps would start on hi-hi level alarm.

C. Incorrect. Plausible because the pumps automatically stop on low level, however, the pumps must be manually started.

D. Correct. There are no auto start features and the valves must be open to start the pumps. The pumps automatically stop on low level.

Page 69 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SD-SO23-670, Page 8 Attached w/ Revision # See SO23-2-16, Step 6.19.3 Comments / Reference SO23-15-57.C, 57C43 SO23-15-56.A, 56A56 and 56A55 Proposed references to be provided during examination: None Learning Objective: DESCRIBE the configuration and operational characteristics of 81446 / 81448 Containment System components.

ANALYZE normal and abnormal operations of 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 7, 9 55.43 Page 70 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-670, Page 8 Revision # 10 Page 71 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-16, Step 6.19.3 Revision # 23 Page 72 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-57.C, 57C43 Revision # 18 Page 73 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-56.A, 56A56 Revision # 7 Page 74 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-56.A, 56A55 Revision # 7 Page 75 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 068 AA1.28 Importance Rating 3.8 Control Room Evacuation: Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:

PZR level control and pressure control Proposed Question: Common 65 Given the following condition:

• The Control Room has been evacuated due to a seismic event.

Which ONE (1) of the following represents the location and reason for the monitoring of Pressurizer level?

A. Evacuation Shutdown Panel (L-042) because the instrument range is adequate to maintain the plant in a HOT STANDBY condition.

B. Essential Plant Parameters Monitoring Panel (L-411) because the instrument range is adequate to place the plant in a COLD SHUTDOWN condition.

C. Essential Plant Parameters Monitoring Panel (L-411) because the panel is located in the seismically qualified Penetration Building.

D. Evacuation Shutdown Panel (L-042) because the Pressurizer level instrument retains its seismic qualification at this location.

Proposed Answer: D Page 76 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the Evacuation Shutdown Panel is the correct location, however, the reason is because its seismic qualification is maintained.

B. Incorrect. Plausible because achieving Cold Shutdown is a desired condition during a seismic event, however, this panel is used when a fire is the reason the Control Room was evacuated.

C. Incorrect. Plausible because the EPPM is located in the Penetration Building which has seismic qualifications, however, the EPPM itself is not seismically qualified.

D. Correct. Pressurizer level is monitored from the Evacuation Shutdown Panel during a seismic event given the design criteria associated with this indication. The Essential Plant Parameters Monitoring Panel would be used if a fire had occurred.

Technical Reference(s) SO23-13-2, Step 4.10.5 Note Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: As the RO, DESCRIBE: The basis for each step, note and caution, per the 56667 applicable sections and attachments of the Shutdown from Outside the Control Room procedure, SO23-13-2.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 77 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-2, Step 4.10.5 Revision # 11 Page 78 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G 2.1.21 Importance Rating 3.5 Conduct of Operations: Ability to verify the controlled procedure copy Proposed Question: Common 66 Which ONE (1) of the following activities does NOT require verification that the procedure is the most current revision?

Performing...

A. an evolution in the Main Control Room with a goldenrod controlled copy of the procedure.

B. an evolution at the FFCPD Control Room with a field controlled copy of the procedure.

C. a frequently performed evolution in the Main Control Room with a laminated copy of the procedure.

D. an evolution at the FFCPD Control Room with a multiple use procedure in a plastic jacket.

Proposed Answer: A Explanation:

A. Correct. This type of procedure is considered a controlled document.

B. Incorrect. Plausible because it could be thought that these types of procedure copies were controlled documents.

C. Incorrect. Plausible because it could be thought that these types of procedure copies were controlled documents.

D. Incorrect. Plausible because it could be thought that these types of procedure copies were controlled documents.

Technical Reference(s) SO123-0-A3, Section 6.3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 79 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: STATE the guidelines for procedure use during normal operations 55120 including: "Procedure-In-Use" file per Operation's Administrative Procedures.

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 SO123-0-A3, Section 6.3 Revision # 8 Page 80 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Page 81 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G 2.1.15 Importance Rating 2.7 Conduct of Operations: Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.

Proposed Question: Common 67 Given the following conditions:

• SO23-3-3.19, 4 kV Emergency Bus Transfer Test, Attachment 5, SSD Second Point of Control Tests - 2G002 Output Breaker 2A0413 is in progress.

• 2G002 Breaker 2A0413 fails to close when operated at the Train A Second Point of Control.

In accordance with SO23-3-3, Operations Surveillance Program Requirements, which ONE (1) of the following is the first person that needs to be notified about the breaker failure?

A. Shift Manager.

B. Operations Manager.

C. Cognizant System Engineer.

D. SRO Operations Supervisor.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because the Shift Manager is concerned especially if it affected component OPERABILITY, however, it is the SRO Operations Supervisor that is responsible per SO23-3-3.

B. Incorrect. Plausible because at some point the Operations Manager would be informed, however, it is the SRO Operations Supervisor that is responsible per SO23-3-3.

C. Incorrect. Plausible because at some point this individual would be informed, however, it is the SRO Operations Supervisor that is responsible per SO23-3-3.

D. Correct. As defined in SO23-3-3, Operations Surveillance Program Requirements.

Technical Reference(s) SO23-3-3, Steps 6.1.5 and 6.5.1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 82 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: Given a plant situation involving the performance of a surveillance test, 55161 DETERMINE if administrative requirements for surveillances have been met and what corrective action, if any, is required.

Question Source: Bank # 127272 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 Page 83 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-3, Step 6.1.5 and 6.5.1 Revision # 12 Page 84 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-3, Step 6.5.1 Revision # 12 Page 85 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G 2.1.31 Importance Rating 4.6 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 68 Which ONE (1) of the following will generate the Steam Bypass Control System Annunciator 50A07 - SBCS DEMAND PRESENT?

The Steam Bypass Control System...

A. AUTO Permissive Channel Circuitry is generating an output.

B. AUTO Permissive Channel Circuitry and the Master Controller (PIC-8431) are both generating an output.

C. Master Controller (PIC-8431) is generating an output.

D. AUTO Permissive Channel Circuitry and Rate of Change Circuitry are both generating an output.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because this is 1 of 2 conditions required.

B. Correct. Both conditions must be present for the annunciator to be active.

C. Incorrect. Plausible because this is 1 of 2 conditions required.

D. Incorrect. Plausible because Auto Permissive Channel Circuitry is required, however, the Rate of Change Circuitry is not required.

Technical Reference(s) SO23-3-2.18, L&S 2.1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: INTERPRET instrumentation and controls utilized in the Main Steam 102466 / 102485 System.

ANALYZE normal and abnormal operations of the Main Steam System.

Question Source: Bank # 128167 Modified Bank # (Note changes or attach parent)

New Page 86 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 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 SO23-3-2.18, L&S 2.1 Revision # 20 Page 87 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 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 69 Which ONE (1) of the following conditions requires entry into a Technical Specification ACTION STATEMENT while in MODE 3?

A. Pressurizer level is 30%.

B. Charging Pump P191 is cleared.

C. Train A Fuel Oil Storage Tank level is 39,000 gallons.

D. Reactor Coolant System TCOLD is 535°F.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because 38% Pressurizer level is the minimum per the Pressurizer Level Control Program, however, there is no Technical Specification minimum value for level.

B. Incorrect. Plausible because two RCS boron injection flow paths must be OPERABLE, however, Charging Pump P191 is the Swing Pump and can be cleared without impact to boration systems.

C. Correct. This level meets the minimum requirements for MODE 5 or 6, however, level must be greater than 41,800 gallons in MODES 1, 2, 3 or 4.

D. Incorrect. Plausible because this temperature is less than the average temperature required at Hot Zero Power, however, the Technical Specification Minimum Temperature for Criticality is 522°F.

Technical Reference(s) Technical Specification LCO 3.8.3 Attached w/ Revision # See Technical Specification LCO 3.4.2 Comments / Reference SO23-3-1.10, Attachment 5 Technical Specification LCO 3.1.9 Proposed references to be provided during examination: None Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system or equipment OPERABILITY and LCO(s) impacted along with all required actions and surveillances using SONGS procedures, Technical Specifications and Licensee Controlled Specifications (LCS).

Page 88 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # 73789 (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2007 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 89 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.8.3 Amendment # 211 Page 90 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.2 Amendment # 127 Comments /

Reference:

From SO23-3-1.10, Attachment 5 Revision # 21 Page 91 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.1.9 Amendment #127 Comments /

Reference:

From Exam Bank #73789 Revision # 05/22/01 Which ONE (1) of the following conditions requires entry into a Technical Specification ACTION STATEMENT while at 80% power?

A. Diesel Generator 2G002 Fuel Oil Day Tank level is 29 inches.

B. Fuel Oil Storage Tank 2T-035 level is 45,850 gallons.

C. Reactor Coolant System Tcold is 541ºF.

D. Charging Pump 2P-191 is tagged out for repairs.

Page 92 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G 2.2.39 Importance Rating 3.9 Equipment Control: Knowledge of less than or equal to one hour Technical Specification action statements for systems Proposed Question: Common 70 Given the following conditions:

• Unit 2 is in a Refueling Outage.

• Spent fuel is being moved inside Containment.

• Refueling Cavity level is greater than 23 feet above the fuel.

Which ONE (1) of the following is the required condition for the Personnel Air Lock (PAL) doors, Emergency Air Lock (EAL) doors, and Equipment Hatch?

A. The Equipment Hatch must be closed and held in place by 2 bolts; both doors of the PAL and EAL must be closed.

B. The Equipment Hatch must be closed with all bolts installed; both doors in the PAL and EAL must be closed.

C. The Equipment Hatch must be closed and held in place by 4 bolts; both doors in the EAL and PAL must be closed.

D. The Equipment Hatch must be closed and held in place by 4 bolts; one door in the EAL must be closed, and one door in the PAL must be closed or OPERABLE.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because if the Equipment Hatch were OPERABLE (requires 4 bolts) this condition would be correct, however, only one door in the PAL and EAL must be closed.

B. Incorrect. Plausible because the Equipment Hatch would be OPERABLE with all bolts installed, however, only one door in the PAL and EAL must be closed.

C. Incorrect. Plausible because the Equipment Hatch requirements are correct, however, only one door in the PAL and EAL need be closed.

D. Correct. Per Technical Specification LCO 3.9.3.

Technical Reference(s) Technical Specification LCO 3.9.3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 93 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system 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 # 127083 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 10 55.43 Comments /

Reference:

From Technical Specification LCO 3.9.3 Amendment # 193 Page 94 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G 2.2.41 Importance Rating 3.5 Equipment Control: Ability to obtain and interpret station electrical and mechanical drawings Proposed Question: Common 71 Given the following condition:

• An overload condition has occurred on Reserve Auxiliary Transformer 2XR1 Per Drawing 30103, which ONE (1) of the following are automatic functions initiated by operation of Overcurrent Relay, 451-1?

Along with initiating an Annunciator,...

A. trips 230 kV CBs, trips 6.9 kV CBs, and initiates DDSMS.

B. trips 230 kV CBs, trips 6.9 kV CBs, and initiates DFR1 Channel 23.

C. trips 6.9 kV CBs, trips 4.16 kV CBs, and initiates DFR1 Channel 22.

D. trips 230 kV CBs, trips 480 V CBs, and initiates 230 kV Breaker Failure Backup.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because tripping of the breakers is correct, however, this device does not initiate DDSMS.

B. Correct. Per the Function Table on Drawing 30103 and overcurrent relay 451-1.

C. Incorrect. Plausible because tripping of the breakers is correct, however, this device actuates DFR1 Channel 23.

D. Incorrect. Plausible because the 230 kV Breakers and Breaker Failure Backup are actuated by the overcurrent device, however, there are no 480 V circuit breakers that are tripped.

Technical Reference(s) Drawing 30103, 451-1 Overcurrent Relay Attached w/ Revision # See Drawing 30103, Function Table Comments / Reference Proposed references to be provided during examination: Drawing 30103 (Size C)

Learning Objective: Given the appropriate Elementary diagram, DETERMINE starting, 54937 stopping, overriding, indicating, protecting, and interlock criteria, as applicable, for any component.

Page 95 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # 73728 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 Drawing 30103, 451-1 Overcurrent Relay Revision # 11 Page 96 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Drawing 30103, Function Table Revision # 11 Page 97 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 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 72 Given the following conditions on Unit 3:

• Unit 3 is in a Refueling shutdown with a Reduced Inventory Condition.

Which ONE (1) of the following conditions requires that the Unit 3 Containment be evacuated?

A. Notification from Security that a Direct Armed Attack (Code RED) is in progress.

B. Annunciator CONTAINMENT SUMP HI LEVEL alarms in the Control Room.

C. An inadvertent Reactor Coolant System dilution of 100 gallons.

D. Receipt of a seismic alarm at less than Operating Basis Earthquake.

Proposed Answer: A Page 98 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. This is the required action per SO23-13-25, Operator Actions During Security Events.

B. Incorrect. Plausible because it could be thought that receipt of this alarm would require a Containment evacuation, however, it is not required for this condition.

C. Incorrect. Plausible because it could be thought that a dilution, especially in Reduced Inventory Condition would result in increasing count rate, however, AOI SO23-13-11 Emergency Boration of the RCS/Inadvertent Dilution or Boration does not require Containment Evacuation. An increase in radiation levels could require evacuation but this condition is not specified.

D. Incorrect. Plausible because it could be thought that evacuating Containment would be prudent for a seismic event but is not an action specified in SO23-13-3, Earthquake.

Technical Reference(s) SO23-13-25, Step 12a RNO, p6 Attached w/ Revision # See SO23-13-11, Step 5a Comments / Reference SO23-13-3, Attachment 1 Proposed references to be provided during examination: None Learning Objective: Given a SONGS Security Event, DESCRIBE basis for each step, caution or 54470 note in the Abnormal Operating Instruction and the expected plant or operator response in accordance with SO23-13-25.

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 12 55.43 Page 99 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-25, Step 12a RNO Revision # 12-1 Page 100 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-11, Step 5a Revision # 14 Page 101 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-3, Attachment 1 Revision # 11-1 Page 102 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # G 2.3.4 Importance Rating 3.2 Radiation Control: Knowledge of radiation exposure limits under normal or emergency conditions Proposed Question: Common 73 Given the following conditions:

• A room, accessible to individuals, has general area radiation levels of 50 mrem/hour.

• A valve on the far wall of the room has a contact radiation level of 2000 mrem/hour.

• The radiation level 30 centimeters from the valve is 80 mrem/hour.

Which ONE (1) of the following is the correct posting for the room?

A. "CAUTION, RADIATION AREA" with the valve identified as a "HOT SPOT."

B. "CAUTION, RADIATION AREA" with no "HOT SPOT" identified.

C. "CAUTION, HIGH RADIATION AREA" with the valve identified as a "HOT SPOT."

D. "CAUTION, HIGH RADIATION AREA" with no "HOT SPOT" identified.

Proposed Answer: A Explanation:

A. Correct. Given the conditions listed, the posting is correct.

B. Incorrect. Plausible because the posting is a Radiation Area is correct, however, this area also has a hot spot.

C. Incorrect. Plausible because it could be thought that the hot spot radiation area level qualified as a High Radiation Area.

D. Incorrect. Plausible because it could be thought that the general area radiation levels qualify as a High Radiation Area.

Technical Reference(s) SO123-VII-20, Attachment 1 Attached w/ Revision # See SO123-VII-20, Step 6.11.3.3 Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a type of Radiation Area, DESCRIBE its radiation limits, as well as 52585 the access controls required by 10CFR20 and site procedures to enter this area. Include in this description any signs and barriers that define this area.

Page 103 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 12 55.43 Page 104 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VII-20, Attachment 1 Revision # 13 Page 105 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VII-20, Attachment 1 Revision # 13 Page 106 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VII-20, Step 6.11.3.3 Revision # 13 Page 107 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G 2.4.2 Importance Rating 4.5 Emergency Procedures/Plan: Knowledge of system setpoints, interlocks and automatic actions associated with EOP entry conditions Proposed Question: Common 74 Given the following conditions:

• Unit 2 is operating at 100% power.

Which ONE (1) of the following conditions would require the operators to trip the Unit?

A. Stator Hot Gas temperature of 150°F.

B. Steam Generator E089 narrow range level of 90%.

C. Instrument Air header pressure of 65 psig.

D. Main Condenser T is 27°F.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because it could be thought that this temperature would require a plant trip, however, the Turbine would trip automatically at 181°F.

B. Correct. The Turbine should automatically trip at 89% narrow range level.

C. Incorrect. Plausible because it could be thought that this pressure would require a plant trip, however, a Unit trip must be initiated at 50 psig.

D. Incorrect. Plausible because a 25°F T is an NPDES violation, however, it does not require a Unit trip.

Technical Reference(s) SO23-15-52.A, 52A11 Attached w/ Revision # See SO23-15-99.C, 99C01 Comments / Reference SO23-13-5, Step 2b SO23-2-5, L&S 2.4 Proposed references to be provided during examination: None Learning Objective: As the RO, RECOGNIZE and RESPOND to a reactor trip event and 53972 manipulate plant systems and equipment to perform the Standard Post Trip Actions per SO23-12-1.

Page 108 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 109 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-52.A, 52A11 Revision # 12 Page 110 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-5, Step 2b Revision # 7 Page 111 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-99.C, 99C01 Revision # 14 Page 112 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-2-5, L&S 2.4 Revision #

Page 113 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G 2.4.39 Importance Rating 3.9 Emergency Procedures/Plan: Knowledge of RO responsibilities in emergency plan implementation Proposed Question: Common 75 Given the following conditions:

• An emergency event has been declared as an ALERT at 1030.

• You have assumed the duties of Operations Leader.

Which ONE (1) of the following is the LATEST time that you should activate the Emergency Response Data System (ERDS)?

A. 1045.

B. 1100.

C. 1130.

D. 1145.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because the Siren and PA Coordination must be performed within 15 minutes by the Operations Leader.

B. Incorrect. Plausible because personnel must be briefed by the operations leader every 30 minutes as to the status of the plant, Emergency Response Priorities, and any Protective Actions Recommendations initiated by the Emergency Coordinator C. Correct. The Emergency Response Data System must be activated within one hour of declaration of an ALERT or higher classification.

D. Incorrect. Plausible because it could be thought that 15 minutes was allocated to Siren and PA Coordination and then one hour later the ERDS would be activated.

Technical Reference(s) SO23-VIII-30, Step 6.1.1.11.12 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the responsibilities of the Operations Leader during an 56184 emergency event per SO23-VIII-30, including: Providing plant status information.

Page 114 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # 130572 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 Page 115 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-VIII-30, Step 6.1.1.11.12 Revision # 15 Page 116 of 117 Rev 2d

ES-401 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-VIII-30, Step 6.1.1.11.12 Revision # 15 Page 117 of 117 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 040 AA2.05 Importance Rating 4.5 Steam Line Rupture - Excessive Heat Transfer: Ability to determine or interpret the following as they apply to the Steam Line Rupture: When ESFAS systems may be secured Proposed Question: SRO 76 Given the following conditions during an Excess Steam Demand Event outside Containment and upstream of the Main Steam Isolation Valves on Steam Generator E089:

• Steam Generator E089 has been isolated.

• THOT is 480°F and stable. Should be Valve

• Lowest TCOLD is 469°F and stable.

• Representative Core Exit Thermocouple is 495°F and stable.

• Pressurizer level is 39% and rising.

• Pressurizer Pressure is 1690 psia and rising.

• Auxiliary Feedwater is in service supplying E088.

• Reactor Vessel level indicates 100%.

• All CEAs inserted on the trip and power is less than 1X10-4 and lowering.

Which ONE (1) of the following describes the NEXT action of SO23-12-5, Excess Steam Demand Event for these conditions?

A. Refer to SO23-3-2.2, Makeup Operations and ensure a boration of greater than or equal to 40 gpm is maintained.

B. Refer to SO23-12-11, EOI Supporting Attachments, FS-31, Establish CVCS Letdown Flow and override and open Letdown Isolation Valves and restore Letdown to control Pressurizer level.

C. Refer to SO23-12-11, EOI Supporting Attachments, FS-7, Verify SI Throttle / Stop Criteria and stop Charging Pumps one at a time to establish Pressurizer level control.

D. Refer to SO23-12-11, EOI Supporting Attachments, FS-1, Verify Pressurizer Pressure and initiate Pressurizer Spray flow to reduce RCS and Pressurizer differential temperature.

Proposed Answer: C Page 1 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that Shutdown Margin is in jeopardy due to the Excess Steam Demand Event.

B. Incorrect. Plausible because for Pressurizer level greater than 80% the EOI directs action to place Letdown in service, however, implementing FS-7 is a more direct way to address this concern.

C. Correct. Throttle conditions are met and with RCS pressure above SI Pump shutoff head the next throttling steps require securing Charging Pumps.

D. Incorrect. Plausible because at 160°F the EOI does direct actions to initiate spray flow for PTS mitigation, however, this action is not performed by this Floating Step.

Technical Reference(s) SO23-12-5, Steps 7 & 13 Attached w/ Revision # See SO23-12-11, Attachment 2, FS-7 Comments / Reference SO23-14-5, Step 7 Bases SO23-12-10, Attachment SF-5 Proposed references to be provided during examination: None Learning Objective: STATE the major recovery actions in response to an ESDE event.

54789 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 2 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-5, Step 7 Revision # 21 Page 3 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-5, Step 13 Revision # 21 Page 4 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 2, FS-7 Revision # 6 Page 5 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-5, Step 7 Bases Revision # 8 Page 6 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-5 Revision # 3 Page 7 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E02 EA2.2 Importance Rating 4.0 Reactor Trip - Stabilization - Recovery: Ability to determine and interpret the following as they apply to the Reactor Trip Recovery: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Proposed Question: SRO 77 Given the following conditions:

• A Reactor trip has occurred on Unit 3.

• A transition to SO23-12-2, Reactor Trip Recovery has been completed.

• All four Reactor Coolant Pumps are running.

Subsequently:

• Pressurizer Pressure is 1870 psia and slowly lowering with all heaters energized.

• Pressurizer level is 30% and slowly lowering with all Charging Pumps operating.

• Containment sump level is rising.

• Steam Generator E088 Blowdown Radiation monitor shows a rising trend.

• Reactor Coolant System TCOLD is 520°F and stable.

• Reactor Coolant System THOT is 522°F and stable.

Which ONE (1) of the following identifies the action that should be taken in this situation?

A. Enter SO23-12-04, Steam Generator Tube Rupture and isolate Steam Generator E088.

B. Re-diagnose the event per SO23-12-10 Safety Function Status Checks, Attachment SF-1, Recovery Diagnostics and enter the identified EOI.

C. Enter SO23-12-03, Loss of Coolant Accident and initiate SIAS and CIAS.

D. Enter SO23-12-09, Functional Recovery and isolate Steam Generator E088.

Proposed Answer: B Page 8 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because an indication of secondary activity is present, however, there is also leakage into Containment indicated and re-diagnosis is required.

B. Correct. The SFSCs of Reactor Trip Recovery for Pressurizer level and pressure and secondary activity are not met and re-diagnosis is specified.

C. Incorrect. Plausible because of RCS pressure and temperature and Containment sump level rise, however, there is also secondary activity indicated and re-diagnosis is required.

D. Incorrect. Plausible because there are indications of more than one event, however, confirmation via the re-diagnosis process is required.

Technical Reference(s) SO23-12-10, Steps 2, 4, and 7 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: As the SRO, ANALYZE plant conditions to select the appropriate Emergency 54780 Operating Instruction and direct and coordinate the activities of shift personnel to recover from a Reactor Trip Event per SO23-12-2.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 9 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Step 2 Revision # 3 Page 10 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Step 4 Revision # 3 Comments /

Reference:

From SO23-12-10, Step 7 Revision # 3 Page 11 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Page 12 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 015/17 G 2.1.20 Importance Rating 4.6 RCP Malfunctions: Conduct of Operations: Ability to interpret and execute procedure steps Proposed Question: SRO 78 Given the following conditions while in MODE 1:

• Annunciator 50A51 - VIBRATION AND LOOSE PARTS MONITORING SYSTEM TROUBLE is in alarm due to Reactor Coolant Pump P-004 vibration.

• Containment Sump inlet flow indicates 1.1 gpm.

• Charging and Letdown flow mismatch has risen by about 1 gpm.

• Reactor Coolant Pump P-004 Seal Cavity pressures are all normal.

• Reactor Coolant Pump P-004 Controlled Bleedoff flow is 1.5 gpm.

• All other seal parameters are normal.

• Reactor Coolant System Inventory Balance identified the leakage as 1.2 gpm.

• A Containment entry has identified leakage via a crack in the RCP casing.

Which ONE (1) of the following identifies the type of leakage and the action(s) required?

A. This is UNIDENTIFIED LEAKAGE greater than 1 gpm and must be corrected or the plant taken to COLD SHUTDOWN.

B. This is IDENTIFIED LEAKAGE less than 10 gpm and continued operation is allowed with no restrictions.

C. This is PRESSURE BOUNDARY LEAKAGE and the Unit must be placed in MODE 5.

D. This is leakage from a known source that has been specifically located and does not interfere with leakage detection systems. Establish controls to monitor for changes in the leakage rate.

Proposed Answer: C Page 13 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that due to the location this would not be PRESSURE BOUNDARY LEAKAGE (PBL), however, pump casing leaks are unisolable from the RCS and meet the requirement for PBL.

B. Incorrect. Plausible because it could be thought that this was considered UNIDENTIFIED LEAKAGE based on being visually identified and not interfering with the leakage detection systems; however, this is PRESSURE BOUNDARY LEAKAGE which is not allowed in any quantity.

C. Correct. This is PRESSURE BOUNDARY LEAKAGE and the Unit must be placed in MODE 5.

D. Incorrect. Plausible because this particular criterion is used in the Tech Specs to differentiate IDENTIFIED and UNIDENTIFIED LEAKAGE, however, no PRESSURE BOUNDARY LEAKAGE is allowed.

Technical Reference(s) Technical Specification LCO 3.4.13 Attached w/ Revision # See SO23-13-6, Step 3 Comments / Reference SD-SO23-360, Figures I-13 & I-17A Technical Specification Definitions Proposed references to be provided during examination: None Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Page 14 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.13 Amendment # 204 Page 15 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-6, Step 3 Revision # 5 Page 16 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-360, Figure I-17A Revision # 17 Comments /

Reference:

From SD-SO23-360, Figure I-13 Revision # 17 Page 17 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification Definitions Amendment # 204 Page 18 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 009 G 2.2.37 Importance Rating 4.6 Small Break LOCA: Equipment Control: Ability to determine operability and/or availability of safety related equipment Proposed Question: SRO 79 Given the following conditions:

• A Small Break Loss of Coolant Accident is in progress on Unit 2.

• A total loss of Component Cooling Water has occurred on Unit 2.

• The Recirculation Actuation Signal will actuate in 5 minutes.

• Bus 2A04 has tripped and locked out due to a bus fault.

• High Pressure Safety Injection Pump P-018 is running on Train B.

• Actions of SO23-12-3, Loss of Coolant Accident are in progress.

• Steam Generator levels are being maintained by Auxiliary Feedwater.

Which ONE (1) of the following actions must be taken to mitigate the situation?

A. Remain in SO23-12-3, Loss of Coolant Accident and cross-connect Unit 2 Component Cooling Water with Unit 3 per SO23-13-7, Loss of Component Cooling Water and invoke 10CFR50.54.X.

B. Start Train B P-019, HPSI Pump 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 perform SO23-12-11, EOI Supporting Attachments, Attachment 23, Cross-Connecting Class 1E 480V Buses Between Units.

D. Perform actions of SO23-12-11, EOI Supporting Attachments, Attachment 14, RAS Operations to raise RWST level in order to flood Containment above the 23 (foot) level to improve Net Positive Suction Head to the operating HPSI Pump.

Proposed Answer: A Page 19 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Given the conditions listed, remaining in SO23-12-3 is appropriate and cross connecting CCW places the Unit in a 50.54.X notification.

B. Incorrect. Plausible because the pump is available (P-018, the 3rd of a kind Pump will start on an SIAS, therefore, P-019 is available) 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.

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 225 level will impact the Emergency Cooling Unit ductwork and could complicate the loss of CCW that already exists.

Technical Reference(s) SO23-12-3, Step 5 Attached w/ Revision # See SO23-14-3, Step 5 Bases Comments / Reference SO23-12-11, FS-22 SO23-13-7, Attachment 4 SO23-12-11, Attachment 14 Proposed references to be provided during examination: None Learning Objective: STATE the major recovery actions in response to a LOCA event.

52757 / 53682 EVAULATE Component Cooling Water System conditions against Administrative and Technical Specification requirements and determine what action, if any, is required.

Question Source: Bank # 129077 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 2, 5 Page 20 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-3, Step 5 Revision # 20 Page 21 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-3, Step 5 Bases Revision # 8 Page 22 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-7, Attachment 4 Revision # 13 Page 23 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, FS-22 Revision # 6 Page 24 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 14 Revision # 6 Page 25 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 025 AA2.07 Importance Rating 3.7 Loss of RHR System: Ability to determine the following as they apply to the Loss of Residual Heat Removal System: Pump cavitation Proposed Question: SRO 80 Given the following conditions:

• The Reactor Coolant System is in a Midloop Condition with RCS level lowering.

• Train A Shutdown Cooling Pump is oscillating +/- 12 amps.

Which ONE (1) of the following identifies the desired action(s) for the conditions listed?

A. Vent the Train B Shutdown Cooling Heat Exchanger and start the Train B Shutdown Cooling Pump per SO23-3-2.6, Shutdown Cooling System Operation.

B. Vent the Train A Shutdown Cooling Heat Exchanger and throttle flow through Train B Shutdown Cooling Pump per SO23-3-2.6, Shutdown Cooling System Operation.

C. Commence emergency refill of the RCS by starting any HPSI Pump and open two Cold Leg Injection Valves per SO23-13-15, Loss of Shutdown Cooling.

D. Start any available Containment Spray Pump aligned as a Shutdown Cooling Pump per SO23-13-15, Loss of Shutdown Cooling.

Proposed Answer: C Page 26 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the Train A Shutdown Cooling Pump is cavitating and this action would be desired if the RCS were not in a Reduced Inventory Condition, however, venting the Train B SDC Heat Exchanger with the Train A SDC Pump running could worsen the condition.

B. Incorrect. Plausible because vortexing probably is occurring which is causing the Shutdown Cooling Pump to cavitate, however, in this condition emergency refill of the RCS is required.

C. Correct. Shutdown Cooling Pump cavitation is identified by an amperage fluctuation of +/- 10 amps.

With the Reactor Coolant System in a Reduced Inventory Condition emergency refill of the RCS must be performed and the desired flowpath is via a HPSI Pump and Hot or Cold Leg Injection Valves.

D. Incorrect. Plausible because the RNO action for emergency refill of the RCS requests that a Containment Spray Pump be started, however, the CS Pump must be aligned to the RWST in order to refill the RCS.

Technical Reference(s) SO23-13-15, Steps 4h & 4j Attached w/ Revision # See SO23-3-2.6, L&S 7.4 and 7.6 Comments / Reference SO23-13-15, Attachment 10 Proposed references to be provided during examination: None Learning Objective: As the SRO, DIRECT operator response to a loss of shutdown cooling per 53933 / 55323 SO23-13-15.

Per the Loss of Shutdown Cooling procedure, SO23-13-15, 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 Page 27 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-15, Step 4h Revision # 18 Page 28 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-15, Step 4j Revision # 18 Page 29 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-2.6, L&S 7.4 and 7.6 Revision # 26 Page 30 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-15, Attachment 10 Revision # 18 Page 31 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 011 G 2.2.42 Importance Rating 4.6 Large Break LOCA: Equipment Control: Ability to recognize system parameters that are entry-level conditions for Technical Specifications Proposed Question: SRO 81 Given the following conditions on Unit 2 three (3) hours after a Large Break LOCA:

• Chemistry reports the following sampling results just prior to a Large Break Loss of Coolant Accident:

• Safety Injection Tank T-007 boron concentration 2360 ppm.

• Safety Injection Tank T-008 boron concentration 2540 ppm.

• Safety Injection Tank T-009 boron concentration 2740 ppm.

• Safety Injection Tank T-010 boron concentration 2380 ppm.

• Refueling Water Storage Tank boron concentration 2875 ppm.

• Reactor Coolant System pH is 7.2.

Based on the sample results, which ONE (1) of the following describes the impact of the Chemistry results and actions post-accident to remedy this condition?

A. Safety Injection Tank T-009 boron concentration is out of specification high.

Containment Sump pH will result in accelerated corrosion of metals and production of hydrogen gas. Make preparations to purge hydrogen per SO23-1-4.2, Containment Purge and Recirculation Filtration System.

B. Combined Sump water boron concentration will be out of specification low causing an increased chance of return to criticality.

Monitor the Reactivity Critical Safety Function and initiate SO23-12-9, Functional Recovery, FR-1, Recovery - Reactivity Control actions.

C. Safety Injection Tanks T-007 and T-010 boron concentrations are out of specification low causing an increased chance of return to criticality.

Monitor the Reactivity Critical Safety Function and initiate SO23-12-9, Functional Recovery, FR-1, Recovery - Reactivity Control actions.

D. Refueling Water Storage Tank boron concentration is out of specification high.

The amount of boron in the sump post-LOCA will cause early precipitation of boron on the core surfaces. Consider performing SO23-12-11, EOI Supporting Attachments, Attachment 11, Simultaneous Hot / Cold Leg Injection.

Proposed Answer: D Page 32 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that this SIT boron was too high. High boron concentration will affect the sump pH. This is the required procedure if a Containment Purge is necessary.

B. Incorrect. Plausible because it could be thought that this SIT boron was too low if confused with the low limit for RWST boron of 2350 ppm. If boron was low the effects would be correct and the actions appropriate.

C. Incorrect. Plausible because it could be thought that these SITs boron were too low if confused with the low limit for RWST boron of 2350 ppm. If boron was low the effects would be correct and the actions appropriate.

D. Correct. The boron limit is 2800 ppm and could result in boron precipitation on the core earlier than expected on a large break LOCA. Early initiation of Simultaneous Hot / Cold Leg Injection would be a consideration.

Technical Reference(s) Technical Specification LCO 3.5.4 Bases Attached w/ Revision # See Technical Specification SR 3.5.4.3 Comments / Reference Technical Specification SR 3.5.1.4 Proposed references to be provided during examination: None Learning Objective: EXPLAIN the different methods of recovery that are unique to the Functional 55280 Recovery Emergency Operating Instruction (EOI).

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, 5 Page 33 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.5.4 Bases Amendment # 127 Comments /

Reference:

From Technical Specification LCO 3.5.4 Bases Amendment # 127 Page 34 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification SR 3.5.4.3 Amendment # 127 Page 35 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification SR 3.5.1.4 Amendment # 135 Page 36 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 032 AA2.07 Importance Rating 3.4 Loss of Source Range NI: Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Maximum allowable channel disagreement Proposed Question: SRO 82 Given the following conditions:

• The Unit is in MODE 2 with a Reactor startup in progress.

• JI-001-2, Log Power Safety Channel has failed low and was placed in BYPASS.

• The remaining three Log Power Safety Channels indicate the following:

• JI-001-1 reads 5 x 10-4%.

• JI-001-3 reads 4 x 10-5%.

• JI-001-4 reads 7 x 10-4%.

• JI-001-4, Log Power Safety Channel has failed low and is INOPERABLE.

Which ONE (1) of the following identifies the required actions?

Place JI-001-4, Log Power Safety Channel in...

A. TRIP within one (1) hour. The Reactor Startup CANNOT continue until the channel is repaired.

B. BYPASS within one (1) hour. The Reactor Startup CANNOT continue until the cause of the greater than one-half (1/2) decade channel deviation between the remaining two channels is corrected.

C. TRIP or BYPASS within one (1) hour. The Reactor Startup CAN continue as long as the deviation between the two OPERABLE channels is less than one-half (1/2) decade when criticality is achieved.

D. TRIP or BYPASS within one (1) hour. The Reactor Startup CAN continue and criticality achieved with the remaining two channels deviation as is.

Proposed Answer: A Page 37 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Because one channel is already failed and in BYPASS the second channel must be placed in TRIP per Technical Specifications. There are insufficient Log Safety Channels available to continue the startup.

B. Incorrect. Plausible because the failed channel action must occur within one hour, however, the 2nd failed channel must be placed in TRIP. A channel deviation of greater than 1/2 decade is allowed until the Reactor is critical; however, there are insufficient Log Safety Channels available to continue the startup.

C. Incorrect. Plausible because the guidance contained in SO23-3-3.2, Excore NI Calibration allows a one decade disagreement applies until criticality is achieved, however, the 2nd failed channel must be placed in TRIP.

D. Incorrect. Plausible if thought that only two channels were required during the startup and that the 2nd failed channel could be placed in TRIP or BYPASS.

Technical Reference(s) Technical Specification LCO 3.3.1.B Attached w/ Revision # See SO23-3-3.2, Attachment 4 Comments / Reference SO23-3-1.1, Attachment 8 Proposed references to be provided during examination: None Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system 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, 5 Page 38 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.3.1 Amendment # 127 Page 39 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-3.2, Attachment 4 Revision # 14 Page 40 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-1.1, Attachment 8 Revision # 323 Page 41 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 068 G 2.4.41 Importance Rating 4.6 Control Room Evacuation: Emergency Procedures / Plan: Knowledge of the emergency action level thresholds and classifications Proposed Question: SRO 83 Given the following conditions from full power :

• At 1317 both Units 2 and 3 entered SO23-13-2, Shutdown from Outside the Control Room due to a fire with dense smoke inside the Control Room.

• At 1327 Unit 3 reported that Local Control was established.

• At 1329 the Fire Team Leader reported that the fire was out.

• At 1331 Unit 2 reported that Local Control was established.

Which ONE (1) of the following describes the required action associated with these conditions?

A. Notify the NRC within one hour that 10CFR50.54.X was invoked on both Units to establish Local Controls for Train A equipment.

B. Declare an UNUSUAL EVENT based on a fire threatening vital equipment lasting longer than 10 minutes.

C. Declare an ALERT based on Control Room evacuation and successfully establishing Local Control for both Units within 15 minutes.

D. Declare a SITE AREA EMERGENCY based on a fire that required Control Room evacuation.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because it could be thought that 50.54.X is invoked for disabling automatic features of safeguards equipment. 50.54.X would be invoked if Train B components were required to be used with Train A.

B. Incorrect. Plausible because the fire lasting longer than 15 minutes would result in an UNUSUAL EVENT.

C. Correct. Control Room evacuation and successfully establishing local control within 15 minutes is an ALERT.

D. Incorrect. Plausible if thought that two separate events required declaration of a SITE AREA EMERGENCY if it was determined that HOT SHUTDOWN capability was lost.

Page 42 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO123-VIII-1, Attachment 2, Tab D2-4 Attached w/ Revision # See SO123-VIII-1, Attachment 2, Tab D3-4 Comments / Reference SO123-VIII-1, Attachment 2, Tab E1-1 SO23-13-2, Step 2 Caution (p198)

Proposed references to be provided during examination: SO123-VIII-1, Attachment 2 Learning Objective: As the SRO, CLASSIFY emergency events requiring Emergency Plan 56274 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 Page 43 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VIII-1, Attachment 2, Tab D2-4 Revision # 27 Page 44 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VIII-1, Attachment 2, Tab D3-4 Revision # 27 Comments /

Reference:

From SO123-VIII-1, Attachment 2, Tab E1-1 Revision # 27 Page 45 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-2, Step 2 Caution Revision # 11 Page 46 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 067 AA2.03 Importance Rating 3.5 Plant Fire on Site: Ability to determine and interpret the following as they apply to the Plant Fire on Site: Fire alarm Proposed Question: SRO 84 Given the following conditions:

• Annunciator 61A15 - FIRE DETECTED has alarmed.

• The fire was in the Train C Y03 1E Inverter Room and has been extinguished.

• Efforts to maintain Y03 1E Inverter Room temperatures less than 90°F have not been successful.

Which ONE (1) of the following is required per SO23-1-5, Auxiliary Building Normal HVAC System Operation?

A. Open all 1E Inverter Room doors and initiate a Fire Impairment for the Technical Specification Fire Doors.

B. Align the Swing Battery Charger to the Y03 inverter and initiate a Fire Impairment for door blockage.

C. Align forced ventilation when Inverter Room temperatures exceed 120°F.

D. Open the Y03 1E Inverter Room door, align forced ventilation and initiate a Fire Impairment.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because these actions are correct, however, the only time all doors are opened is if temperatures exceed 100°F.

B. Incorrect. Plausible because a Fire Impairment would be issued anytime a door is blocked, however, aligning the Swing Battery Charger is not required.

C. Incorrect. Plausible because forced ventilation must be aligned, however, this action must be performed when room temperatures exceed 90°F.

D. Correct. With the affected room temperature greater than 90°F but less than 100°F, open the affected room door, align forced ventilation, and initiate a Fire Impairment.

Technical Reference(s) SO23-1-5, Attachment 9 Attached w/ Revision # See Comments / Reference Page 47 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: Per the Fire procedure, SO23-13-21, DESCRIBE: The basis for each step, 53413 caution, or note and 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 48 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-1-5, Attachment 9 Revision # 20 Page 49 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # E09 G 2.2.42 Importance Rating 4.6 Functional Recovery: Equipment Control: Ability to recognize system parameters that are entry level conditions for Technical Specifications Proposed Question: SRO 85 Given the following conditions on Unit 2:

• A Station Blackout occurred two (2) hours ago.

• Efforts to recover power or cross-tie to Unit 3 have been unsuccessful.

• Entry into SO23-12-9, Functional Recovery, Attachment FR-2, Recovery - Vital Auxiliaries was made to perform power restoration.

• Auxiliary Feedwater Pump P140 tripped on startup and the overspeed trip linkage is broken and will NOT reset.

• Both Steam Generators are empty and entry to SO23-12-9, Functional Recovery, Attachment FR-5, Recovery - Heat Removal has been made due to NO OPERABLE Steam Generator and Reactor Coolant System temperatures RISING.

• Subcooling has been lost and Core Exit Thermocouples are approaching 700°F.

Which ONE (1) of the following describes the actions to take to establish heat removal?

Align Fire Water to the discharge of...

A. P504, Auxiliary Feedwater Pump and feed Steam Generator E089 using Fire Water at low flow for at least 30 minutes and then recover levels to at least 40% narrow range.

B. P504, Auxiliary Feedwater Pump and feed both Steam Generators using Fire Water. Invoke 10CFR50.54.X due to using Firewater to feed the Steam Generators and notify the NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. P141, Auxiliary Feedwater Pump and feed Steam Generator E088 using Fire Water. Enter the Severe Accident Management Guidelines (SAMG) due to Steam Generator dryout.

D. P141, Auxiliary Feedwater Pump and feed both Steam Generators by cross-tying Auxiliary Feedwater trains using Fire Water. Invoke 10CFR50.54.X due to isolating Auxiliary Feedwater Pumps and notify the NRC within one hour.

Proposed Answer: D Page 50 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that the connection was on P504. The Steam Generator recovery level listed is consistent with guidance in the Functional Recovery Procedure; however, the time is 15 minutes.

B. Incorrect. Plausible because invoking 50.54.X is required due to isolating the Auxiliary Feedwater Pumps, however, not for the reasons stated. Additionally, the Fire System connection is on P141 and NRC notification would be required within one hour.

C. Incorrect. Plausible because feeding both Steam generators is desired and the correct AFW Pump is being used, however, entry into the SAMG is not required.

D. Correct. With the Heat Removal Safety Function NOT met and all other design paths unavailable, the Functional Recovery Procedure directs aligning the Fire System which has a Diesel Driven Pump and feeding both Steam Generators. 10CFR50.54.X (Step 8a, Caution) is declared due to isolating the AFW Pumps because of overpressure concerns with the fire water connection (Step 8c, Caution).

Technical Reference(s) SO23-12-9, Step 8 Attached w/ Revision # See Technical Specification LCO 3.7.5 Bases Comments / Reference SD-SO23-780, Figure 1 Proposed references to be provided during examination: None Learning Objective: Per the Functional Recovery procedure SO23-12-9 DESCRIBE: The basis for 55217 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 1, 2, 5 Page 51 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, Step 8 Revision # 25 Page 52 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, Step 8 Revision # 25 Page 53 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, Step 8 Revision # 25 Page 54 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.7.5 Bases Amendment # 127 Page 55 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-780, Figure 1 Revision # 10 Page 56 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010 A2.01 Importance Rating 3.6 Pressurizer Pressure Control System: Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures Proposed Question: SRO 86 Given the following conditions with the Unit in MODE 1 at 80% power:

• A Steam Bypass Control Valve failed open 2 minutes ago and is now closed.

• Pressurizer pressure is 2020 psia and slowly increasing.

• PIC-100, Pressurizer Pressure Indicating Controller output is 0%.

• Annunciator 50A14 - PZR PRESS HI/LO is in alarm.

• Annunciator 50A04 - PZR PRESS DEVIATION HI/LO is NOT in alarm.

• All systems are in Automatic.

Which ONE (1) of the following:

1.) Identifies the impact of Pressurizer Pressure Control on Technical Specifications?

2.) What procedural action must be taken to address this situation?

A. 1.) Technical Specification LCO 3.4.1, DNB Pressure, Temperature, and Flow Limits must be entered and corrected.

2.) Refer to SO23-13-27, Pressurizer Pressure and Level Malfunctions, Step 3, Pressure Out of Band and ensure all Heaters are energized and both Corrected font Pressurizer Spray Valves are closed.

B. 1.) Technical Specification LCO 3.4.3, RCS Pressure and Temperature (P/T) Limits must be entered and Pressurizer Heaters restored.

2.) Refer to SO23-3-1.10, Pressurizer Pressure and Level, Section 6.1, Normal Pressurizer Pressure Control and control Pressurizer Heaters and Spray in manual.

C. 1.) Technical Specification LCO 3.4.3, RCS Pressure and Temperature (P/T) Limits must be entered and pressure restored.

2.) Trip the Reactor and enter SO23-12-1, Standard Post Trip Actions due to loss of Pressurizer Pressure control.

D. 1.) Technical Specification LCO 3.4.1, DNB Pressure, Temperature, and Flow Limits must be entered and corrected.

2.) Refer to SO23-3-1.10, Pressurizer Pressure and Level, Section 6.7, Manual Pressurizer Pressure Control and operate PIC-100, Pressurizer Pressure Controller in manual to control pressure.

Page 57 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: A Explanation:

A. Correct. Given that the reason for the pressure transient is known, entry into SO23-13-27 is appropriate given the response of the primary system. Swapping to the other Pressurizer Pressure Channel is not required because the deviation alarm is not annunciating. Technical Specification LCO 3.4.1 contains the correct information.

B. Incorrect. Plausible if thought that Pressurizer Heaters were out of service because pressure was responding slowly.

C. Incorrect. Plausible if thought that this Technical Specification LCO is not being met. Given the conditions listed, a Reactor trip is not warranted.

D. Incorrect. Plausible because the Technical Specification entry is correct, however, the wrong procedure and Section of SO23-3-1.10 is used.

Technical Reference(s) SO23-13-27, Step 3b RNO & 3a Attached w/ Revision # See Technical Specification LCO 3.4.1 Comments / Reference SO23-3-1.10, Section 6.1 & 6.7 Technical Specification LCO 3.4.3 Technical Specification LCO 3.4.9 SO23-15-50.A1, 50A04 & 50A14 Proposed references to be provided during examination: None Learning Objective: As the Control Room Supervisor and given plant conditions, DETERMINE 55213 / 56649 appropriate steps to be taken for a Pressurizer Pressure or Level Malfunction in accordance with SO23-13-27.

Given plant and equipment conditions, or Technical Specification/LCS surveillance results, DETERMINE system 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, 5 Page 58 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-27, Step 3b RNO Revision # 4 Page 59 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From 50A14SO23-13-27, Step 3a Revision # 4 Page 60 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.1 Amendment #149 Page 61 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-1.10, Section 6.1 Revision # 21 Page 62 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-3-1.10, Section 6.7 Revision # 21 Page 63 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.3 Amendment #203 Page 64 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.9 Amendment #161 Page 65 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-50.A1, 50A04 Revision # 8 Comments /

Reference:

From SO23-15-50.A1, 50A14 Revision # 8 Page 66 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059 G 2.2.44 Importance Rating 4.4 Main Feedwater: Equipment Control: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions affect plant and system conditions Proposed Question: SRO 87 Given the following conditions on both Steam Generators at full power:

• Feedwater flow is GREATER THAN steam flow.

• Steam Generator narrow range levels are RISING.

• Feedwater Control System Master Controller outputs are LOWERING.

• Feedwater Control Valves are CLOSING.

• K006, Main Feedwater Pump speed is RISING.

• K005, Main Feedwater Pump speed is LOWERING.

Which ONE (1) of the following actions is required?

A. Ensure both Steam Generator Feedwater Control Systems are operating in AUTO per SO23-9-6, Feedwater Control System Operations.

B. Place K006 EAP/MSC in MANUAL and attempt to lower output per SO23-13-24, Feedwater Control System Malfunctions.

C. Place both Steam Generator Feedwater Control Valves in MANUAL and lower output per SO23-9-6, Feedwater Control System Operations.

D. Place both Steam Generator Master Controllers in Preferred Manual and attempt to lower level per SO23-13-24, Feedwater Control System Malfunctions.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because as long as the system was in AUTO one would expect level to be controlled, however, a Feedwater malfunction exists and entry into the AOI is required.

B. Correct. Given the conditions listed, placing K006, Main Feedwater Pump in MANUAL and lowering output to lower speed is the desired action. Refer to hard copy of SO23-13-24, Attachment 1; Flowchart in PDF version is not legible.

C. Incorrect. Plausible because this would help to regain level control, however, the guidance would come from the Abnormal Operating Instruction.

D. Incorrect. Plausible because this is a desired action to lower level, however, the Master Controller is already performing this function.

Page 67 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO23-13-24, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: As an SRO, given specific indications of a Feedwater Control System 56415 malfunction, DESCRIBE the process in determining the required actions in accordance with SO23-13-24.

Question Source: Bank # 128188 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 68 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-24, Attachment 1 (best available) Revision # 3 Page 69 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007 G 2.2.40 Importance Rating 4.7 Pressurizer Relief/Quench Tank System: Equipment Control: Ability to apply Technical Specifications for a system Proposed Question: SRO 88 Given the following conditions:

• Unit 2 is operating at 100% power.

• The lift setpoint for PSV-0200, Pressurizer Safety Valve is determined to be out of tolerance (low) due to an error in the test calculation.

• PSV-0201, Pressurizer Safety Valve is OPERABLE.

Which ONE (1) of the following states the Technical Specification REQUIRED ACTION for this condition?

Restore within...

A. 15 minutes or be in MODE 3 in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. one (1) hour or gag the safety valve and be in MODE 5 in the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

C. two (2) hours or be in MODE 4 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. four (4) hours or be in MODE 5 in the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Proposed Answer: A Explanation:

A. Correct. Per Technical Specification LCO 3.4.10, this is the REQUIRED ACTION and COMPLETION TIME. The valve must be restored within 15 minutes; however, MODE 3 entry is required in the next six hours.

B. Incorrect. Plausible because it could be thought that the ACTION time was 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and that on a low setting, gagging the safety would be prudent and entry into MODE 5 would remove the heat energy for valve lift, however, the initial ACTION time is 15 minutes and MODE 3 entry is required in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per Tech Specs.

C. Incorrect. Plausible because it could be thought that two hours applies, however, MODE 3 entry is required in the next six hours per Tech Specs and the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to MODE 4 is the ACTION for two safeties INOPERABLE.

D. Incorrect. Plausible if thought that MODE 5 needed to be entered.

Page 70 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) Technical Specification LCO 3.4.10 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Page 71 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.10 Amendment # 156 Page 72 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.06 Importance Rating 4.0 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: Inadvertent ESFAS actuation Proposed Question: SRO 89 Given the following conditions:

• The Unit is operating in MODE 1 when a Safety Injection Actuation Signal (SIAS) occurs.

• Pressurizer Pressure is 2245 psia.

• Containment Pressure is 0.3 psig.

• The cause of the SIAS was due to failure of a Matrix Channel.

• The Matrix Channel was declared INOPERABLE.

1.) Which ONE (1) of the following identifies the impact of the channel failure on Technical Specifications?

2.) What action must be taken to mitigate the situation?

A. 1.) Technical Specification LCO 3.3.5, ESFAS Instrumentation is applicable.

2.) Enter SO23-12-1, Standard Post Trip Actions and trip the Reactor and Turbine.

B. 1.) Technical Specification LCO 3.3.5, ESFAS Instrumentation is applicable.

2.) Enter SO23-3-2.7.2, Safety Injection System Removal/Return to Service Operation to reset the SIAS to restore Normal Containment Cooling.

C. 1.) Technical Specification LCO 3.3.6, ESFAS Logic and Manual Trip is applicable.

2.) Enter SO23-13-28, Rapid Power Reduction and place the Unit in MODE 3 within one hour.

D. 1.) Technical Specification LCO 3.3.6, ESFAS Logic and Manual Trip is applicable.

2.) Enter SO23-13-17, Recovery from Inadvertent Safety Injection/Containment Isolation or Containment Spray and override and stop all Charging Pumps.

Proposed Answer: D Page 73 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. The Tech Spec entry is incorrect. A Reactor trip and entry into SO23-12-1 per SO23-13-7, RCP Seal Failure would be considered because Controlled Bleed Off flow to the VCT is lost, however, the CBO relief would lift and the RCPs would be protected.

B. Incorrect. Plausible because the condition to reset SIAS to restore normal Containment Cooling is correct, however, the Technical Specification and procedure entry are both incorrect.

C. Incorrect. Plausible because the Tech Spec entry is correct, however, this would be the wrong procedure to enter because a Rapid Power Reduction is not required.

D. Correct. The SIAS must be recovered from in less than one hour to avoid Technical Specification LCO 3.0.3 entry. This is the correct Tech Spec and procedure entry. Letdown is isolated on an SIAS and the Charging Pumps must be overridden and stopped.

Technical Reference(s) Technical Specification LCO 3.3.6 Attached w/ Revision # See SO23-13-17, Steps 3 & 5 Comments / Reference SO23-13-6, Step 2 SO23-13-17, Steps 6k, 6l, & 6m Proposed references to be provided during examination: None Learning Objective: As the SRO, DIRECT operator actions during recovery from an inadvertent 53939 / 56649 safety injection / containment isolation per SO23-13-17.

Given plant and equipment conditions, or Technical Specification/LCS surveillance results, DETERMINE system 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 5 Page 74 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.3.6 Amendment # 127 Page 75 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-17, Step 3 Revision # 5 Page 76 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-6, Step 2 Revision # 5 Page 77 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-17, Steps 6k, 6l, & 6m Revision # 5 Page 78 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-13-17, Step 5 Revision # 5 Page 79 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 G 2.4.21 Importance Rating 4.6 Service Water System: Emergency Procedures/Plan: Knowledge of the parameters and logic used to assess safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Proposed Question: SRO 90 Given the following conditions on Unit 2:

• SO23-12-9, Functional Recovery was entered due to a Small Break Loss of Coolant Accident and Excess Steam Demand Event.

• Offsite power is unavailable and Train B Emergency Diesel Generator failed to start.

• Containment pressure is 17 psig.

• Reactor Coolant System pressure is 1600 psia and the Pressurizer is empty.

• Subcooled Margin is 2°F.

• All Train A Engineered Safety Feature actuations occurred as required.

• Reactor Vessel Level is 21% in the Plenum.

While performing Safety Function Status Checks you learn that the only available Salt Water Cooling Pump has just tripped.

1.) Which ONE (1) of the following identifies the highest Safety Functions that are NOT met?

2.) Which Functional Recovery Procedure will be entered FIRST?

A. 1.) RCS Inventory Control and RCS Pressure Control.

2.) Implement FR-3, Recovery - RCS Inventory Control.

B. 1.) RCS Pressure Control and Core Heat Removal.

2.) Implement FR-4, Recovery - RCS Pressure Control.

C. 1.) Core Heat Removal and RCS Heat Removal.

2.) Implement FR-5, Recovery - Heat Removal.

D. 1.) Containment Isolation and Containment Temperature and Pressure Control.

2.) Implement FR-6, Recovery - Containment Isolation.

Proposed Answer: A Page 80 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. These are highest Safety Functions affected and the highest priority Safety Function in jeopardy is RCS Inventory Control.

B. Incorrect. Plausible because it could be thought that the Core Heat Removal Safety Function was the highest priority Safety Function jeopardized due to the loss of the SI Pumps but the challenge doesnt exist if SG cooling is working and CETs are less than 700°F.

C. Incorrect. Plausible because it could be thought that both Heat Removal Safety Functions were jeopardized which would require entry into FR-5.

D. Incorrect. Plausible because Containment pressure is 17 psig with no indication that it is lowering, however, FR-6 would be implemented later if conditions did not improve.

Technical Reference(s) SO23-12-10, Attachment SF-3, Steps 3 to 8 Attached w/ Revision # See SO23-12-9, Attachment FR-3, Step 4 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the different methods of recovery that are unique to the Functional 55280 / 55217 Recovery Emergency Operating Instruction (EOI).

Per the Functional Recovery procedure SO23-12-9 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 Page 81 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 3 Revision # 3 Page 82 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 3 Revision # 3 Page 83 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 4 Revision # 3 Page 84 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 5 Revision # 3 Page 85 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 6 Revision # 3 Page 86 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 7 Revision # 3 Page 87 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-10, Attachment SF-3, Step 8 Revision # 3 Page 88 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, Attachment FR-3, Step 4 Revision # 25 Page 89 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 045 G 2.1.20 Importance Rating 4.6 Main Turbine Generator System: Conduct of Operations: Ability to interpret and execute procedure steps Proposed Question: SRO 91 Given the following conditions:

• Unit 3 is at 75% power and performing a shutdown from 100% power for Refueling.

• Unit 2 has been at 100% power for 95 days and is performing monthly In Service Testing on a standby Charging Pump.

• Annunciator 50A02 - COLSS ALARM actuates on Unit 2 and a steady slow power ramp to 100.06% is observed with a slight drop in TCOLD.

Which ONE (1) of the following describes the cause of this alarm and the actions required to mitigate the event?

A. Auxiliary Steam is aligned to Unit 2 and is starting to supply the Unit 3 Turbine Gland Sealing Steam.

Enter SO23-13-11, Emergency Boration of the RCS / Inadvertent Dilution or Boration and immediately borate to restore Shutdown Margin.

B. Auxiliary Steam is aligned to Unit 2 and is starting to supply the Unit 3 Turbine Gland Sealing Steam.

Enter SO23-5-1.7, Power Operations and immediately reduce power to less than or equal to 100%.

C. The standby Charging Pump had reduced boron concentration in its lines when it was started.

Enter SO23-13-11, Emergency Boration of the RCS / Inadvertent Dilution or Boration and immediately borate to restore Shutdown Margin.

D. The standby Charging Pump had elevated boron concentration in its lines when it was started.

Enter SO23-5-1.7, Power Operations and immediately reduce power to less than or equal to 100%.

Proposed Answer: B Page 90 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible if thought that there would be inadequate SHUTDOWN MARGIN with power at this level. If SHUTDOWN MARGIN were inadequate this would be the correct procedure to enter.

B. Correct. The Turbine Gland System is self-sealing above 80% power. Once power drops below 80%, Gland Sealing Steam will be supplied by Auxiliary Steam which will raise power on the supplying Unit. The action required is to reduce power to within 100% per SO23-5-1.7.

C. Incorrect. Plausible because it could be thought that there could be reduced boron in the Charging Pumps causing power to rise, however, an idle Charging Pump during an extended run is not likely to have reduced boron in the lines and a dilution would result in rising TCOLD.

D. Incorrect. Plausible because the procedural action is correct, however, an idle Charging Pump during an extended run is not likely to have elevated boron in the lines and a boration would result in a lowering TCOLD.

Technical Reference(s) SO23-5-1.7, L&S 5.21 Attached w/ Revision # See SO23-5-1.7, Step 6.1.2 Comments / Reference SO23-5-1.7, L&S 2.1 SO23-15-50.A1, 50A02 Proposed references to be provided during examination: None Learning Objective: During Power Operations, EXPLAIN the precaution, limitation or administrative 55143 requirement applicable to plant condition per SO23-5-1.7.

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 Page 91 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.7, L&S 5.21 Revision # 41 Page 92 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-5-1.7, Step 6.1.2 Revision # 41 Comments /

Reference:

From SO23-5-1.7, L&S 2.1 Revision # 41 Page 93 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-50.A1, 50A02 Revision # 8 Page 94 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 071 G 2.1.32 Importance Rating 4.0 Waste Gas Disposal System: Conduct of Operations: Ability to explain and apply system limits and precautions Proposed Question: SRO 92 Given the following conditions:

• Unit 3 is performing a Waste Gas Decay Tank release using 2/3 RT-7808, Plant Vent Stack and Containment Purge Radiation Monitor.

• During the release, 3RT-7865, Containment Purge Radiation Monitor is declared INOPERABLE.

Per the Offsite Dose Calculation Manual (ODCM), which ONE (1) of the following is required?

A. Verify 2/3RT-7808 is OPERABLE.

B. Analyze two independent samples prior to continuing.

C. Estimate the process flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Verify valve alignment, sample and release rate calculations.

Proposed Answer: A Explanation:

A. Correct. Per ODCM, Table 4-3, a minimum of one Channel must be OPERABLE.

B. Incorrect. Plausible because ACTION 35a states that when the number of OPERABLE Channels is less than required, at least two independent samples of the tank contents should be analyzed.

C. Incorrect. Plausible because ACTION 36a states that when the number of OPERABLE Channels is less than required, the process flow rate should be estimated at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Incorrect. Plausible because ACTION 35b states that when the number of OPERABLE Channels is less than required, the valve alignment and release rate calculations must be re-verified.

Technical Reference(s) SO123-ODCM, Table 4-3 Attached w/ Revision #

SO123-ODCM, Table 4-3, ACTIONs 35a & 35b See Comments /

Reference SO123-ODCM, Table 4-3, ACTION 36a Proposed references to be provided during examination: None Learning Objective: Given plant conditions concerning an effluent release, DETERMINE the 53393 applicable technical specification/administrative requirements or limitations.

Page 95 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Question Source: Bank # 71065 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 1, 4 Comments /

Reference:

From SO123-ODCM, Table 4-3 Revision # 0 Page 96 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-ODCM, Table 4-3, ACTIONs 35a & 35b Revision #

Page 97 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-ODCM, Table 4-3, ACTIONs 36a Revision # 0 Page 98 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 034 A3.02 Importance Rating 3.1 Fuel Handling Equipment System: Ability to monitor automatic operation of the Fuel Handling System, including: Load limits Proposed Question: SRO 93 Given the following conditions during Refueling:

• A Spent Fuel Assembly was placed in the Fuel Transfer Carriage inside Containment.

• While transferring the Assembly between the Containment and Fuel Handling Building, the Fuel Transfer Carriage became lodged in the Transfer Canal.

• Transfer stopped when the 800 pound overload limit was reached.

Which ONE (1) of the following actions is required?

A. Evacuate Containment only.

B. Notify Health Physics to monitor radiation levels in the Fuel Transfer Tube Area.

C. Evacuate the Fuel Handling Building only.

D. Notify Health Physics to monitor radiation levels in the Radwaste Building.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because it could be thought that Containment must be evacuated because of the location of the Transfer Canal, however, this area is inaccessible to personnel during refueling.

B. Correct. Given the conditions listed, this the action to be taken for a stuck Fuel Assembly.

C. Incorrect. Plausible because there are individuals inside the Fuel Handling Building, however, it is the Fuel Transfer Tube Area (Penetration Room 111) that must be monitored.

D. Incorrect. Plausible if thought that the Radwaste Building was the location of the Transfer Canal.

Technical Reference(s) SO23-X-7, Precautions 4.43 and 4.51 Attached w/ Revision # See SD-SO23-430, Pages 75 & 76 Comments / Reference Proposed references to be provided during examination: None Learning Objective: As the SRO, DIRECT the response to Fuel Handling Accidents/Loss of Cavity 54861 or SFP Level Control per SO23-13-20.

Page 99 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 7 Page 100 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-X-7, Precaution 4.43 Revision # 16 Comments /

Reference:

From SO23-X-7, Precaution 4.51 Revision # 16 Page 101 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SD-SO23-430, Pages 75 & 76 Revision # 12 Page 102 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 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, over time 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 leave the site for emergency medical treatment.

Which ONE (1) of the following describes the requirements regarding the shift composition and required action in this situation?

A. The 21 Watch may leave the site immediately after turnover of responsibilities to another qualified person on shift. A replacement must arrive within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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 CRS may assume the responsibilities of the 21 Watch. The Shift Manager may perform concurrent SM/CRS duties until shift relief with a qualified STA on site.

Proposed Answer: A Explanation:

A. 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.

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. 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.

Page 103 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SO123-0-A1, Attachment 2 Attached w/ Revision # See Technical Specifications Section 5.2.2 Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given plant conditions, DETERMINE if license conditions have been violated 55164 per 10CFR50.54.

Question Source: Bank # 151972 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam SONGS 2006 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2, 5 Page 104 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-0-A1, Attachment 2 Revision # 18 Page 105 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-0-A1, Attachment 2 Revision # 18 Page 106 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specifications Section 5.2.2 Amendment # 207 Page 107 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G 2.1.23 Importance Rating 4.4 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation Proposed Question: SRO 95 Given the following conditions:

• SO23-12-8, Station Blackout is currently in use.

• Subsequently, a Loss of Coolant Accident occurs.

• Qualified Safety Parameter Display System is OPERABLE.

• Pressurizer level has been below the indicating range for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• Core Exit Thermocouple temperature is 713°F.

• Turbine Driven Auxiliary Feedwater Pump is in operation.

Based on the conditions listed, which ONE (1) of the following is the Control Room Supervisors top priority?

A. Remain in SO23-12-8, Station Blackout, and attempt to restore power to at least one 1E 4160 Volt Bus.

A. Determine that core damage is in progress. Remain in SO23-12-8, Station Blackout and implement the Severe Accident Management Guidelines.

B. Reactor Vessel water level is below the top of the core. Transition to SO23-12-9, Functional Recovery and implement FR-3, Recovery - RCS Inventory Control.

B. The core has just reached saturation conditions and SO23-12-11, EOI Supporting Attachments, Attachment 5, Core Exit Saturation Margin Control should be implemented.

Proposed Answer: C Page 108 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because restoration of power to a Safeguards Bus is a priority, however, Inadequate Core Cooling conditions exist and entry into SO23-12-9 is required.

B. Incorrect. Plausible because the Severe Accident Management Guidelines are available for use, however, conditions have not degraded to the point where the SAMGs would be implemented.

C. Correct. Given the conditions listed, entry into the Functional Recovery Procedure is required.

D. Incorrect. Plausible because feedwater is available, however, superheat conditions exist regardless of RCS pressure and entry into the Functional Recovery Procedure is required.

Technical Reference(s) SO23-12-9, SO23-12-9, Entry Conditions Attached w/ Revision # See SO23-14-9, FR-3 Bases Comments / Reference Proposed references to be provided during examination: None Learning Objective: Per the Functional Recovery procedure SO23-12-9 DESCRIBE: The basis for 55217 each step, caution or note.

Question Source: Bank # 127126 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 55.43 5 Page 109 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-9, Entry Conditions Revision # 25 Page 110 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-9, FR-3 Bases Revision # 25 Page 111 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G 2.2.6 Importance Rating 3.6 Equipment Control: Knowledge of the process for making changes to procedures Proposed Question: SRO 96 A Procedure Modification Permit which could potentially change the intent of an Operating Instruction is being prepared.

Which ONE (1) of the following activities is required for the Procedure Modification Permit?

A. Approval by the Shift Manager is required within 14 days of completion.

B. A 50.59 Safety Evaluation must be performed within 14 days of completion.

C. Approval by the Manager, Operations is required prior to implementation.

D. Approval by the Operations Procedure Group Supervisor must be performed prior to implementation.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because their approval may be required prior to implementation depending on the availability of the Ops Manager.

B. Incorrect. Plausible because a 50.59 is required, however, it is required based on the time the PMP will be used. See Step 3 of OP(123)28.

C. Correct. Per Step 4 of OP(123)28.

D. Incorrect. Plausible because they would review but only to determine if a REV or TCN is required.

Technical Reference(s) SO123-0-A3, Step 6.16 Attached w/ Revision # See Form OP(123)28, Step 4 & Keypoint 13 Comments / Reference Proposed references to be provided during examination: None Learning Objective: As an SRO, given a plant situation, DESCRIBE the administrative or technical 55169 specification requirements applicable to a situation not covered by Normal, Abnormal or Emergency Operating instructions and determine the required action.

Question Source: Bank # 128199 Modified Bank # (Note changes or attach parent)

New Page 112 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Page 113 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-0-A3, Step 6.16 Revision # 8 Page 114 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From OP(123)28, Step 4 Revision # 0 Comments /

Reference:

From OP(123)28, Keypoint 13 Revision # 0 Page 115 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G 2.2.25 Importance Rating 4.2 Equipment Control: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits Proposed Question: SRO 97 Given the following BOC conditions:

• Unit 2 is operating at 100% power with a leaking Main Steam Safety valve on Steam Generator E088.

• There is one (1) Main Steam Safety Valve already gagged on Steam Generator E088.

• Preparations are being made to gag second leaking Main Steam Safety Valve on E088.

Which ONE (1) of the following describes the Technical Specification requirements that apply to gagging a second Main Steam Safety Valve on E088 and what is the basis for this requirement?

Reduce...

A. power which will allow the Safety Valves to remove the required amount of decay heat to prevent exceeding the Safety Limit of 1.03 for DNBR on a loss of the normal secondary heat removal path.

B. allowed power and High Power trip setpoints which ensures that the RCS Pressure Safety Limit of 2750 psia is NOT exceeded on a loss of the normal secondary heat removal path.

C. High Pressure trip setpoints which ensures that the peak centerline temperature of

< 4960°F is NOT exceeded on a loss of the normal secondary heat removal path.

D. High Power trip setpoints which ensures that the Safety Limit of 1.03 for DNBR is NOT exceeded on a loss of the normal secondary heat removal path.

Proposed Answer: B Page 116 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be thought that limiting power would limit decay heat and subsequent RCS temperature post-event and protect against exceeding DNBR, however, the DNBR value is incorrect.

B. Correct. Limiting power and high power trip setpoints is required and in conjunction with the PZR Safety Valves protects against exceeding the RCS Pressure Safety Limit of 2750 psia.

C. Incorrect. Plausible because it could be thought that limiting power and High Pressure setpoints would limit decay heat and subsequent RCS temperature post-event and protect against exceeding Peak Centerline Temperature Safety Limit. The Peak Centerline Temperature listed reflects an EOC condition as PCT is reduced 58°F for every 10,000 MWD/MTU.

D. Incorrect. Plausible because it could be thought that limiting power would limit decay heat and subsequent RCS temperature post-event and protect against exceeding the DNBR safety limit, however, the DNBR value is incorrect.

Technical Reference(s) Technical Specification LCO 3.7.1 Attached w/ Revision # See Technical Specification LCO 3.7.1, Table Comments / Reference Technical Specification LCO 3.7.1, Bases Tech Spec Safety Limit 2.1.1 & 2.1.2, Bases Proposed references to be provided during examination: None Learning Objective: Given plant and equipment conditions, or Technical Specification/LCS 56649 surveillance results, DETERMINE system 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 Page 117 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.7.1 Amendment # 212 Comments /

Reference:

From Technical Specification LCO 3.7.1, Table 3.7.1.1 Amendment # 212 Page 118 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.7.1 Bases Amendment # 127 Page 119 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.7.1 Bases Amendment # 127 Page 120 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Tech Spec Safety Limit 2.1.2 Bases Amendment # 127 Page 121 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Tech Spec Safety Limit 2.1.1 Bases Amendment # 207 Page 122 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 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 98 Given the following conditions:

• An emergency event is in progress on Unit 2, and a SITE AREA EMERGENCY has been declared.

• The Emergency Coordinator duties have been turned over from the Station Emergency Director (SED) to the Corporate Emergency Director (CED).

In this situation, which ONE (1) of the following must authorize EMERGENCY RADIATION EXPOSURE exceeding 10CFR20 limits?

A. Operations Leader B. Health Physics Leader C. Station Emergency Director D. Corporate Emergency Director Proposed Answer: C Explanation:

A. Incorrect. Plausible because the Operations Leader has responsibilities associated with selecting a volunteer for emergency radiation exposure, however, this can only be authorized by the Station Emergency Director.

B. Incorrect. Plausible because an emergency radiation exposure is involved, however, this can only be approved by the Station Emergency Director.

C. Correct. Even though the Station Emergency Director has been relieved, they are still the individual responsible for this authorization.

D. Incorrect. Plausible because it could be thought that with turnover complete that responsibility now resides with the Corporate Emergency Director, however, that person would not be as familiar with plant conditions as the Station Emergency Director.

Technical Reference(s) SO123-VIII-10, Step 4.2.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 123 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Learning Objective: As an SRO, DETERMINE Emergency Coordinator actions required for 55369 notification, evacuation, and exposure control of onsite personnel, and for making notifications and Protective Action Recommendations to offsite agencies in accordance with SO123-VIII-10, Emergency Coordinator Duties.

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 4, 5 Page 124 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO123-VIII-10, Step 4.2.2 Revision # 26-1 Page 125 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G 2.4.6 Importance Rating 4.7 Emergency Procedures/Plan: Knowledge of EOP mitigation strategies Proposed Question: SRO 99 Given the following conditions:

• Unit 2 has tripped from 100% power due to a Loss of Offsite Power.

• A Pressurizer Safety Valve is partially stuck OPEN.

• Both Trains of SIAS have actuated and Safety Injection flow meets the Minimum Required SI Flowrates during Cold Leg Injection per SO23-12-11, EOI Supporting Attachments, Attachment 12.

Current conditions are as follows:

• Pressurizer pressure is 1025 psia.

• Core Exit Thermocouple temperature is 539°F.

• Pressurizer level is 80% and slowly rising.

• Containment temperature is 165°F.

• Reactor Coolant System subcooling is 10°F and lowering.

Which ONE (1) of the following describes the mitigation strategy in accordance with SO23-12-03, Loss of Coolant Accident?

A. Allow Pressurizer level to increase and cooldown the RCS per SO23-12-11 EOI Supporting Attachments, Attachment 5, Core Exit Saturation Margin Control.

B. Maintain RCS temperature constant and stabilize Pressurizer level per SO23-12-11 EOI Supporting Attachments, Floating Step 33, Monitor RCS Solid Operation.

C. Throttle HPSI flow to prevent a solid Pressurizer and cooldown the RCS per SO23-12-11 EOI Supporting Attachments, Floating Step 7, Verify SI Throttle/Stop Criteria.

D. Maintain RCS temperature constant while reducing Pressurizer level to less than 60% per SO23-12-11 EOI Supporting Attachments, Attachment 5, Core Exit Saturation Margin Control.

Page 126 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: A Explanation:

A. Correct. Given the conditions listed with subcooling < 20°F, allowing Pressurizer level to increase while cooling down is the desired action per Attachment 5, Core Exit Saturation Margin Control.

B. Incorrect. Plausible because solid Pressurizer conditions are imminent, however, cooldown must be performed due to lack of subcooling.

C. Incorrect. Plausible if thought that a solid Pressurizer was an undesirable condition, however, a lack of subcooling precludes SI Throttle/Stop.

D. Incorrect. Plausible because maintaining Pressurizer level less than 60% is guidance contained in Attachment 5 when Core Exit Saturation Margin is less than 20°F, however, a cooldown must be performed even if it results in a solid Pressurizer.

Technical Reference(s) SO23-12-3, Step 10 Attached w/ Revision # See SO23-12-11, Attachment 5 Comments / Reference SO23-12-11, Floating Steps 7 & 33 Proposed references to be provided during examination: None Learning Objective: Per the EOI Attachments procedure, SO23-12-11, DESCRIBE: The basis for 55279 / 54723 each step, caution or note.

As the SRO, DIRECT response to and recovery from a loss of coolant accident per SO23-12-3.

Question Source: Bank # 127481 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 127 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-3, Step 10 Revision # 20 Page 128 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Attachment 5 Revision # 6 Page 129 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Floating Step 33 Revision # 6 Page 130 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-11, Floating Step 7 Revision # 6 Page 131 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-12-3, Floating Step 7 Revision # 6 Page 132 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G 2.4.9 Importance Rating 4.2 Emergency Procedures/Plan: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies Proposed Question: SRO 100 Given the following conditions:

• Unit 2 has tripped from 100% power.

• Reactor Trip Override is reset and Steam Generator levels are normal.

• Pressurizer level is 30% and slowly lowering.

• Pressurizer pressure is 2240 psia.

• Letdown is secured.

• Steam Bypass Control System (SBCS) is operating to maintain Steam Generator pressures at 1000 psia.

• Annunciator 50A01 - QUENCH TANK PRESS HI has come in and cleared.

• Annunciator 50A11 - QUENCH TANK LEVEL HI/LO is in alarm.

• Annunciator 50A21 - QUENCH TANK TEMP HI is in alarm.

• Annunciator 50A31 - PZR SAFETY VALVE OUTLET TEMP HI is in alarm.

• Containment pressure is 1.8 psia and rising.

• Containment temperature and humidity are rising.

Which ONE (1) of the following describes the mitigation strategy for the event in progress?

A. Commence controlled cooldown using the Steam Generators and Steam Bypass Control System per SO23-12-11, EOI Supporting Attachments, Attachment 3, Cooldown / Depressurization.

B. Initiate a manual Safety Injection to provide makeup water to the Reactor Coolant System and transition to SO23-12-9, Functional Recovery.

C. Commence cooldown at maximum achievable rate using Atmospheric Dump Valves per SO23-12-11, EOI Supporting Attachments, Attachment 5, Core Exit Saturation Margin Control.

D. Open Pressurizer Normal and Auxiliary Spray Valves to rapidly reduce pressure to less than 1400 psia per SO23-12-1, Standard Post Trip Actions.

Proposed Answer: A Explanation:

A. Correct. Using information gleaned from Annunciator Responses, it can be determined that the Page 133 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 rupture disc on the Quench Tank has blown. This allowed the high pressure condition on the Quench Tank [50A51 - See Note (1)] to clear while continuing a Small Break LOCA out the Pressurizer Safety Valves. In this condition a controlled cooldown is desired to maintain Pressurizer level and minimize voiding of the Reactor Coolant System.

B. Incorrect. Plausible if thought that a manual Safety Injection at this time was going to provide makeup and the starting of all Charging Pumps would do this via the SI, however, in this condition a control cooldown is required via the Steam Generators and SBCS. If a high radiation condition existed inside Containment then this would be an appropriate response, however, it is only addressed in the Functional Response Procedure.

C. Incorrect. Plausible because it could be thought that the faster the RCS was cooled down the quicker HPSI flow would be introduced, however, RCS voiding should be minimized and Pressurizer level control should be maintained.

D. Incorrect. Plausible because using the Pressurizer Normal and Auxiliary Spray Valves to reduce pressure is an approved method, however, voiding could occur and there is no guarantee that HPSI flow would be adequate for the break size.

Technical Reference(s) SO23-14-3, Section 3.0 Attached w/ Revision # See SO23-15-50-A.1, 50A01 Comments / Reference Proposed references to be provided during examination: None Learning Objective: As the SRO, DIRECT response to and recovery from a loss of coolant accident 54723 per SO23-12-3.

Question Source: Bank # 126631 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 55.43 5 Page 134 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-14-3, Section 3.0 Revision # 8 Page 135 of 136 Rev 2d

ES-401 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SO23-15-50-A.1, 50A01 Revision # 8 Page 136 of 136 Rev 2d