ML17179A011

2017-06-FINAL Written Exam

ML17179A011
Person / Time
Site:	Comanche Peak
Issue date:	06/19/2017
From:	Vincent Gaddy Operations Branch IV
To:	Vistra Energy
References
50-445/OL-17, 50-446/OL-17
Download: ML17179A011 (229)

Text

ANSWER KEY CPNPP 2017 NRC SRO Exam 1 D 26 A 51 B 76 A 2 B 27 e 52 A 77 D

I 3 c 28 c 53 B I 78 c 4 A I 29 c 54 A 79 B 5 D 30 c 65 B 80 c 6 c 31 A 56 A 81 c I

7 A I

i 32 D 57 A ---- --

8 D 33 c 58 c 83 c 9 D 34 c 59 B 84 D 10 A 35 D 60 A 85 c 11 c 36 c 61 B 86 A 12 c 37 c 62 B I 87 B 13 A 38 D 63 c 88 c 14 A 39 c 64 c 89 A 15 D 40 B 66 B 90 B 16 B 41 B 66 c 91 D 17 B 42 D 67 c 92 D 18 A 43 B 58 D 93 A 19 A 44 c 69 A I 94 B 20 D 45 8 70 A II 95 D I

21 c 46 c 71 A I 96 A 22 B 47 D I 72 c I 97 c 23 A 48 D 73 D 98 D I 24 i A 49 A 74 c --

25 i D 50 D 76 A 100 c Total SRO A-26 A-5 B-20 B- 4 C - 30 C- 8 D-24 D-8 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 003 K4.03 Level of Difficulty: 2 Importance Rating 2.5 Reactor Coolant Pump: Knowledge of RCPS design feature(s) and/or interlock(s) which provide for the following: Adequate lubrication of the RCP.

Question # 1 Unit 2 plant conditions:

Plant heatup is in progress RCPs are to be started in accordance with SOP-108B, Reactor Coolant Pump Based on the above plant conditions, complete the following statements.

1. In accordance with SOP-108B, you are directed to start the oil lift pump ___(1)___

minute(s) before starting the RCP.

2. If oil lift pressure = 610 psig, the RCP Oil Pressure permissive interlock ___(2)___ been met.

A. 1) one

2) has B. 1) one

2) has NOT C. 1) two

2) has NOT D. 1) two

2) has Answer: D Page 1 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of RCP starting interlocks that ensure proper lubrication.

Explanation:

A. Incorrect. 1st part is incorrect because SOP-108B directs you to start the oil lift pump 2 minutes prior to starting the RCP. It is plausible because the oil lift pump is secured one minute after the pump has started. 2nd part is correct. Oil lift pressure has to be 600 psig to satisfy the RCP start permissive.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part incorrect because the RCP oil lift pressure starting interlock has been met (600 psig).

C. Incorrect. 1st part is correct. SOP-108B directs you to start the oil lift pump 2 minutes prior to starting the RCP. 2nd part is incorrect but plausible (see B).

D. Correct. 1st part is correct (see C). 2nd part is correct (see A).

Technical Reference(s) Reactor Coolant Study Guide Attached w/ Revision # See SOP-108B Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Reactor Coolant system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.RC1.OB03)

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 41.7 55.43 Page 2 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 004 K4.11 Level of Difficulty: 2 Importance Rating 3.1 Chemical and Volume Control: Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following:

Temperature/pressure control in letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst.

Question # 2 Unit 1 plant conditions:

100% power The crew has just alternated from PDP operation to CCP 1-01 in service Letdown flow is being raised to 120 gpm 1-PK-131, LTDN HX OUT PRESS CTRL M/A station is in AUTO Based on the above plant conditions, complete the following statement.

When the Reactor Operator opens the second Orifice Isolation valve, pressure sensed by 1-PT-131, LTDN HX 1-01 OUTLET PRESSURE TRANSMITTER will ___(1)___ and 1-PCV-131, LTDN HX OUT PRESS CTRL valve will ___(2)___ to maintain Letdown pressure on setpoint.

A. (1) increase (2) close B. (1) increase (2) open C. (1) decrease (2) close D. (1) decrease (2) open Answer: B Page 6 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of CVCS design features which prevent pressure in the letdown line from causing flashing and thus piping damage.

Explanation:

A. Incorrect. 1st part correct (see B below). 2nd part incorrect but plausible as most valves control pressure on the downstream side, thus as pressure sensed increases the valve closes to lower pressure. This is a common misconception at CPNPP.

B. Correct. 1st part correct, as the second orifice is placed in service the pressure sensed by the pressure transmitter will increase. This is because the pressure is sensed upstream of PCV-131 and downstream of the Letdown Heat Exchanger, therefore as another orifice is placed in service this pressure will always increase. 2nd part is correct, the controller, PK-131 is set to maintain upstream pressure at 310 psig and therefore if the pressure sensed increases the valve must open to lower pressure back to setpoint.

C. Incorrect. 1st part incorrect but plausible as the pressure is sensed downstream of the orifices.

Orifices are used to lower pressure; therefore it is plausible to think that placing another orifice in service would cause the pressure downstream of the orifice to lower. 2nd part is incorrect but plausible (see A above).

D. Incorrect. 1st part is incorrect but plausible (see C above). 2nd part is correct (see B above).

Technical Reference(s) CVCS Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Chemical and Volume Control system including interrelations with other systems to include interlocks and control loops.

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 41.7 55.43 Page 7 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 005 K1.01 Level of Difficulty: 3 Importance Rating 3.2 Residual Heat Removal: Knowledge of the physical connections and/or cause/effect relationships between the RHRS and the following systems: CCWS.

Question # 3 Unit 2 plant conditions:

Design Basis Large Break LOCA in progress Which of the following correctly describes how the Train B CCW to RHR Heat Exchanger isolation valves will be positioned in order to prevent exceeding the CCW system design temperature? (Assume all automatic valve movements are complete).

CCW HX Inlet Isolation valve 2CC-0157 is ___(1)___ and CCW HX Outlet Isolation valve 2-HV-4573 is ___(2)___.

A. (1) closed (2) full open B. (1) throttled to allow 40% flow (2) throttled to allow 40% flow C. (1) closed (2) throttled to allow 40% flow D. (1) throttled to allow 40% flow (2) full open Answer: C Page 10 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the relationship between RHR and CCWS during a LOCA.

Explanation:

A. Incorrect. Inlet Isolation valve position is correct. Outlet Isolation valve position is incorrect but plausible because the outlet isolation valves do travel to the full open position, but then throttle down to allow 40% flow automatically. The question states after automatic valve movement is complete.

B. Incorrect. Inlet isolation valve position is incorrect but plausible because the final Outlet Isolation valve position is open to allow 40% flow. Outlet Isolation valve position is correct.

C. Correct. The inlet isolation valves are normally sealed closed and stay closed during an SI. They have orifices drilled in them which allow sufficient flow during a DB LOCA when coupled with the outlet isolation valve being open to allow 40% flow.

D. Incorrect. Inlet isolation valve position is incorrect but plausible because the final Outlet Isolation valve position is open to allow 40% flow. Outlet Isolation valve position is incorrect but plausible because the outlet isolation valves do travel to the full open position, but then throttle down to 40% open automatically. The question states after automatic valve movement is complete.

Technical Reference(s) LO21.SYS.CC1 Attached w/ Revision # See Component Cooling Water Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Component Cooling Water system. (LO21.SYS.CC1.OB05)

Question Source: Bank # 2014 NRC RO Retake Exam Q4 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014/2015 RO Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.8 55.43 Page 11 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 006 K2.04 Level of Difficulty: 2 Importance Rating 3.6 Emergency Core Cooling: Knowledge of bus power supplies to the following: ESFAS-operated valves.

Question # 4 Complete the following statement regarding 2-8801A, CCP Safety Injection Isolation Valve.

2-8801A is powered from ___(1)___ and ___(2)___ be operated from the Remote Shutdown Panel.

A. (1) 2EB1-1 (2) can B. (1) 2EB1-1 (2) CANNOT C. (1) 2EB2-1 (2) can D. (1) 2EB2-1 (2) CANNOT Answer: A Page 16 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge power supplies to ESFAS operated valves in the Emergency Core Cooling System.

Explanation:

A. Correct. 2-8801A is powered from 2EB1-1 and it can be operated from the RSP.

B. Incorrect. 2-8801A is powered from 2EB1-1 and it can be operated from the RSP. It is plausible because if it were the other isolation valve (2-8801B), it would be correct.

C. Incorrect. The power supply is incorrect. It is plausible because if it were 2-8801B it would be correct. 2-8801A can be operated from the RSP.

D. Incorrect. The power supply is incorrect. It is plausible because if it were 2-8801B it would be correct. 2-8801A can be operated from the RSP. It is plausible because If it were the other isolation valve (2-8801B), it would be correct.

Technical Reference(s) ECCS Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Emergency Core Cooling system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.SI1.OB03)

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 41.7 55.43 Page 17 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 007 K3.01 Level of Difficulty: 2 Importance Rating 3.3 Pressurizer Relief/Quench Tank: Knowledge of the effect that a loss or malfunction of the PRTS will have on the following:

Containment.

Question # 5 Given the following plant conditions:

A Pressurizer (PRZR) Power Operated Relief Valve (PORV) opened at 2335 psig and will NOT close The associated PRZR PORV Block Valve failed to close manually and the Pressurizer Relief Tank rupture disk has blown Pressure has equalized between the PRT and containment PRZR PORV Outlet (Tailpipe) temperature is indicating 250°F Which of the following is the expected Containment pressure for the conditions listed?

A. 2 psig B. 5 psig C. 10 psig D. 15 psig Answer: D Page 19 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how a failed PRT (rupture disk) affects containment (raising pressure).

Explanation:

A. Incorrect. Plausible if Mollier Diagram is improperly read.

B. Incorrect. Plausible if Mollier Diagram is improperly read.

C. Incorrect. Plausible if Mollier Diagram is improperly read.

D. Correct. With a nominal opening pressure of 2335 psig, the isenthalpic expansion occurs at approximately 1110 BTU/lbm. Starting at 1110 BTU/lbm on the Mollier Diagram and going to the right you can see that the discharge will be a wet vapor. If the temperature of the steam is 250oF, the pressure has to be Psat for 250oF which is 30 psia or ~ 15 psig.

Technical Reference(s) Mollier Diagram Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables (Mollier Diagram)

Learning Objective: DISCUSS the operator actions, including all cautions, notes, RNOs and bases associated with EOP-1.0, Loss of Reactor or Secondary Coolant.

Question Source: Bank #

Modified Bank # 2013 NRC Exam Q7 (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.14 55.43 Page 20 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 008 A1.04 Level of Difficulty: 2 Importance Rating 3.1 Component Cooling Water: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: Surge Tank Level.

Question # 6 Unit 2 plant conditions:

Component Cooling Water Pumps 2-01 and 2-02 are in service Component Cooling Water Surge Tank Level is lowering with the following Annunciators in alarm:

2-ALB-3B, Window 2.4 - CCW SRG TK TRN A LVL HI-HI/LO 2-ALB-3B, Window 1.3 - CCW SRG TK TRN A/B LVL LO-LO Component Cooling Water Surge Tank levels are slowly lowering on each compartment Per ABN-502, Component Cooling Water System Malfunctions, complete the following statement regarding operator actions that would identify the leak source.

CLOSE the ___(1)___ and monitor Surge Tank compartment levels. The leak is on the side that continues to fall below ___(2)___ with the other side stable.

A. (1) Non-Safeguards Loop Isolation Valves (2) 37%

B. (1) Non-Safeguards Loop Isolation Valves (2) 58%

C. (1) Safeguards Loop Supply and Return Isolation Valves one Train at a time (2) 37%

D. (1) Safeguards Loop Supply and Return Isolation Valves one Train at a time (2) 58%

Answer: C Page 24 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor CCW surge tank level and determine leak location by what tank level does.

Explanation:

A. Incorrect. Plausible if thought that with both compartments lowering, the source must be the common piping and the methodology would identify a leak on the Non-Safeguards header, however, the isolation of Reactor Coolant Pump cooling should not be performed if other procedurally specified lineups are available.

B. Incorrect. Plausible because it could be thought that with both compartments lowering, the source must be the common piping and the methodology would identify a leak on the Non-Safeguards header, however, the tanks are common until 37% level on Unit 2 which is where the partition plate starts.

C. Correct. The tank is common above 37% on Unit 2 and the leak cannot be identified using this methodology until level reaches 37%. This is the procedurally specified method.

D. Incorrect. Plausible because the tank is common above 58% on Unit 1 and the leak cannot be identified using this methodology until level reaches 58%. This is the procedurally specified method but the wrong Unit.

Technical Reference(s) Component Cooling Water Study Guide Attached w/ Revision # See ABN-502 Comments / Reference 2-ALB-3B Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Component Cooling Water system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.CC1.OB03)

Question Source: Bank # 2011 NRC Exam Q44 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.5 55.43 Page 25 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO R Written E Exam Workssheet Form m ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Datte: Rev. 1 Tier 2 Group 1 K/A 010 A A4.01 Level of Difficulty: 2 Importance Rating 3.7 Pressurizer Pressure Con ntrol: Ability to manually opera ate and/or mon nitor in the control room: Pzr spray valve.

Question n#7 Unit 1 pllant conditio ons:

RCSR Pressuure is rising Based on o the indica ations prov vided, comp plete the sta atements below.

1. With 1-PK-455A A in AUTO, the Spray valves will start to ope en at a nom minal MINIMUM press sure of ___ _(1)___ psig g.

2. MAN NUAL Spray y initiation can c be achieved by takking manua al contrrol of 1-PK--455A and ___(2)___ _ demand.

A. (1 1) 2260 (2

2) increasinng B. (1 1) 2260 (2

2) decreasing C. (1 1) 2310 (2

2) increasinng D. (1 1) 2310 (2

2) decreasing Answer: A Page 35 of 54 PNPP NRC 2017 CP 2 RO Wrritten Exam W Worksheet 1 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by testing knowledge of MANUAL operation of the Przr Spray Valves and understanding of how demand on the controller affects RCS pressure.

Explanation:

A. Correct. 1st part is correct, with 1-PK-455A in AUTO Pressurizer Spray valves will start to open at 2260 psig increasing. 2nd part is correct, based on the indications provided, demand on the controller must be increased to open the spray valves. The spray valves will start to open at a demand output of 57.8%. The picture shows current demand at approximately 47%.

B. Incorrect. 1st part is correct (see A above). 2nd part is incorrect but plausible because with RCS pressure rising it is plausible to think that demand on the controller must be lowered to cause spray valves to open and thus lower RCS pressure. This is how flow controllers work, if flow is rising then manual control is taken and the demand lowered to lower flow (i.e. 1-FK-121, charging flow controller)

C. Incorrect. 1st part is incorrect but plausible as 2310 psig is when the spray valves are fully open.

However, in this case the question is asking when the spray valves will start to open. 2nd part is correct (see A above).

D. Incorrect. 1st part is incorrect but plausible (see C above). 2nd part is incorrect but plausible (see B above).

Technical Reference(s) Pressurizer Pressure and Level Control Attached w/ Revision # See Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: LIST and EXPLAIN the Pressurizer Pressure and Level Control System design features which provide for the trips, permissives and interlocks.

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 41.7 55.43 Page 36 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 012 A3.02 Level of Difficulty: 3 Importance Rating 3.6 Reactor Protection: Ability to monitor automatic operation of the RPS, including: Bistables.

Question # 8 Unit 2 plant conditions:

Unit 2 is operating at 100% power 2-LT-554, SG 4 LVL (NR) CHAN I fails to 100% coincident with the following annunciators:

2-ALB-8A, Window 4.8 - SG 4 STM & FW FLO MISMATCH 2-ALB-8A, Window 4.12 - SG 4 LVL DEV Assuming NO operator action, which of the following identifies the Unit 2 actuation setpoint and expected plant response?

A. The Turbine will trip at 84% level in SG 2-04.

B. The Turbine will trip at 81.5% level in SG 2-04.

C. The Reactor will trip at 38% level in SG 2-04.

D. The Reactor will trip at 35.4% level in SG 2-04.

Answer: D Page 38 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the automatic operation of the RPS system including bistable setpoints.

Explanation:

A. Incorrect. Plausible because if the channel failed low the SG level would rise and the turbine would trip at 84% SG level on Unit 1 causing a reactor trip.

B. Incorrect. Plausible because if the channel failed low on Unit 2 the SG level would rise and the turbine would trip at 81.5% SG level causing a reactor trip.

C. Incorrect. Plausible because channel 554 is the controlling channel which when it fails high causes the feedwater control valve to close and at 38% level in Unit 1 SG 1-04 a reactor trip would be generated which would then cause a turbine trip.

D. Correct. Channel 554 is the controlling channel which when it fails high causes the feedwater control valve to close and at 35.4% level on a Unit 2 SG a reactor trip would be generated which would then cause a turbine trip.

Technical Reference(s) Reactor Protection and ESFAS Study Attached w/ Revision # See Guide Comments / Reference ABN-710 Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Steam Generator Level Instrument Malfunction in accordance with ABN-710 Steam Generator Level Instrument Malfunction Question Source: Bank # 2014 NRC Exam Q62 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 39 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 013 K3.02 Level of Difficulty: 3 Importance Rating 4.3 Engineered Safety Features Actuation: Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following: RCS.

Question # 9 Unit 1 plant conditions:

A 1 inch Small Break LOCA occurs A Loss of Offsite Power occurs Bus 1EA1 has experienced an 86-1 lockout SSW pump 1-02 has tripped RCS subcooling is currently 15°F and trending toward 0°F Given the current plant conditions, if the operators are unable to depressurize the RCS to less than 650 psig, what are the expected consequences?

A. SI Accumulators injecting maintains adequate core cooling and will not result in fuel damage.

B. Natural Circulation maintains adequate core cooling and will not result in fuel damage.

C. TDAFWP loss leads to inadequate core cooling resulting in fuel damage.

D. RCS inventory loss leads to inadequate core cooling resulting in fuel damage.

Answer: D Page 45 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the consequences of ESFAS failure on the RCS/Core.

Explanation:

A. Incorrect. Plausible because if the RCS is depressurized to the point where the accumulators inject adequate inventory would exist until break flow removes enough inventory to uncover the core. The stem states that the RCS cannot be depressurized by the operators to less than 650 psig which is above the accumulator injection pressure. If the RCS is not depressurized to the accumulator injection pressure additional inventory will not be provided by the accumulators.

B. Incorrect. Plausible because if Natural Circulation is maintained, adequate heat removal will also occur as long as the loop remains filled to transport the heat from the core to the steam generators, however, without makeup the loops will eventually drain and heat removal via the steam generators will be ineffective no matter what level remains in the steam generators.

C. Incorrect. Plausible because heat removal via the SGs does provide cooling until RCS inventory is depleted to the point that coupling with the SGs no longer exists.

D. Correct. Given the degraded RCS and the inability to depressurize the RCS by the operators fuel damage is expected due to loss of RCS inventory.

Technical Reference(s) Core Cooling Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EVALUATE plant conditions to DETECT conditions which could lead to core damage from a lack of adequate core cooling and DETERMINE the appropriate mitigation strategies consistent with the Functional Restoration Guidelines.

Question Source: Bank # 2014 NRC Exam Q36 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 46 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 022 G2.2.12 Level of Difficulty: 4 Importance Rating 3.7 Containment Cooling: Knowledge of surveillance procedures.

Question # 10 Unit 1 plant conditions:

Reactor power = 100%

Dayshift has the unit OPT-102A, Operations Shiftly Routine Tests, Form 1 - Mode 1 and 2 Shiftly Surveillances, is being performed 1-TI-5400A, CNTMT AVE TEMP is reading 108°F In accordance with OPT-102A and based on the above plant conditions, complete the following statements.

1. The LATEST time that containment temperature can be recorded is ___(1)___.

2. The surveillance acceptance criteria for containment temperature ___(2)___ been met.

A. (1) 0930 (2) has B. (1) 0930 (2) has NOT C. (1) 1200 (2) has D. (1) 1200 (2) has NOT Answer: A Page 51 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of surveillance procedures that check for (among other things) adequate containment cooling.

Explanation:

A. Correct. 1st part is correct (see B). 2nd part is correct. The acceptance criterion for containment temperature is 110oF and the actual value is less than the acceptance criteria.

B. Correct. 1st part is correct because per OPT-102A, TS surveillance parameters shall be recorded between the hours of 0630 and 0930 during day shift. 2nd part is incorrect but plausible because the surveillance acceptance criterion is 110°F and the current temperature is only 2°F below that value.

C. Incorrect. 1st part is incorrect because per OPT-102A, TS surveillance parameters shall be recorded between the hours of 0630 and 0930 during day shift. It is plausible because if it were not a TS parameter, there is no requirement to record prior to 0930 and 1200 seems reasonable in that it would always be in the first half of the shift. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) OPT-102A Attached w/ Revision # See OPT-102A-1 Comments / Reference Proposed references to be provided during examination:

Learning Objective: APPLY the administrative requirements of the Containment Ventilation system including Technical Specifications, TRM and ODCM. (LO21.SYS.CL1.OB04)

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 41.10 55.43 Page 52 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 1-10 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 026 G2.4.20 Level of Difficulty: 2 Importance Rating 3.8 Containment Spray: Knowledge of the operational implications of EOP warnings, cautions, and notes.

Question # 11 Complete the following statements regarding a CAUTION in EOS-1.3A, Transfer to Cold Leg Recirculation.

1. Any Containment Spray pump taking suction from the RWST should be stopped when RWST level reaches a MINIMUM value of ___(1)___ to prevent potential pump damage.

2. 1-ALB-2B, Window 4.6 - RWST EMPTY alarm ___(2)___ require the operator to secure the Containment Spray pumps based on RWST level.

A. (1) 0%

(2) will B. (1) 9%

(2) will C. (1) 0%

(2) will NOT D. (1) 9%

(2) will NOT Answer: C Page 1 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the implication of EOP cautions (in this case implication of securing Containment Spray pumps on low RWST level and whether or not they can be restarted upon swapping suction sources).

Explanation:

A. Incorrect. 1st part correct, per EOS-1.3A the Containment Spray pumps should be secured when RWST level reaches 0%. 2nd part incorrect but plausible as the name of the alarm is RWST EMPTY which implies that RWST will be empty (0%), however at CPNPP the RWST EMPTY alarm indicates that RWST level has just reached 9%.

B. Incorrect. 1st part is incorrect but plausible as this is the value when ECCS pumps are secured.

2nd part is incorrect but plausible (see A above).

C. Correct. 1st part is correct (see A above). 2nd part is correct, per 1-ALB-2B the RWST EMPTY alarm is received when RWST level is at or below 9%. The CAUTION in EOS-1.3A states to secure containment spray pumps when RWST level is at 0%. Therefore this alarm cannot alert the operator to secure the containments spray pumps.

D. Incorrect. 1st part is incorrect but plausible (see B above). 2nd part is correct (see C above).

Technical Reference(s) EOS-1.3A Attached w/ Revision # See 1-ALB-2B, Window 4.6 - RWST EMPTY Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for all Steps, Notes and Cautions of EOS-1.3A, Transfer to Cold Leg Recirculation.

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 41.10 55.43 Page 2 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 039 K5.08 Level of Difficulty: 2 Importance Rating 3.6 Main and Reheat Steam: Knowledge of the operational implications of the following concepts as the apply to the MRSS:

Effect of steam removal on reactivity.

Question # 12 Unit 1 plant conditions:

Reactor power = 100%

A steam generator Atmospheric Relief Valve (ARV) fails OPEN Based on the above plant conditions, complete the following statements.

1. The ARV opening adds ___(1)___ reactivity to the core.

2. The net reactivity effect is greater at ___(2)___ of Core Life.

A. (1) negative (2) End B. (1) negative (2) Beginning C. (1) positive (2) End D. (1) positive (2) Beginning Answer: C Page 5 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the impact of steam demand on core reactivity.

Explanation:

A. Incorrect. Plausible if thought that steam demand adds negative reactivity to the core. Reactivity effects at EOL are greater due to a larger MTC.

B. Incorrect. Plausible if thought that steam demand adds negative reactivity to the core. Also plausible if thought that reactivity effects at BOL are greater.

C. Correct. Steam demand adds positive reactivity to the core and reactivity effects at EOL are greater due to larger MTC.

D. Incorrect. Plausible because steam demand adds positive reactivity to the core. Also plausible if thought that reactivity effects at BOL are greater.

Technical Reference(s) Increased Heat Removal Accidents Study Attached w/ Revision # See Guide Comments / Reference LO21GFRCOF Proposed references to be provided during examination:

Learning Objective: DISCUSS the excessive increase in secondary steam flow transient.

(LO21MCOTA8OB102)

Question Source: Bank # 2016 NRC Exam Q16 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2016 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.1 55.43 Page 6 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 059 A2.12 Level of Difficulty: 3 Importance Rating 3.1 Main Feedwater: Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of feedwater regulating valves.

Question # 13 Unit 1 plant conditions:

100% power 1-PI-507, MSL HDR PRESS fails low ABN-709, Steam Line, Steam Header & Turbine 1st Stage Pressure & Feed Header Pressure Instrument Malfunction is entered Based on the above plant conditions, complete the following statements.

1. 1-PI-507 failing low will result in the Steam Generator Feedwater Flow Control valves throttling ___(1)___.

2. ABN-709 directs the operator to manually control 1-SK-509A, FWPT MASTER SPD CTRL to maintain Feedwater Header pressure ___(2)___ greater than Steam Header pressure.

A. (1) open (2) 80 - 181 psid B. (1) open (2) 80 - 193 psid C. (1) closed (2) 80 - 181 psid D. (1) closed (2) 80 - 193 psid Answer: A Page 11 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to predict the impact of a feedwater regulating system malfunction and use of procedures to mitigate the failure.

Explanation:

A. Correct. 1st part is correct Steam Header pressure failing low will cause the feedwater pumps to decrease in speed, therefore the Feedwater Regulating valves will throttle open to attempt to maintain Steam Generator water levels on program. 2nd part is correct ABN-709 directs the operator to maintain 80 - 181psid between feed and steam header pressures from 20 - 100%

power.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because on Unit 2 ABN-709 directs the operator to maintain 80 - 193 psid between feed and steam header pressures from 20 - 100% power.

C. Incorrect. 1st part is incorrect because MFP speeds would lower. It is plausible because it is a common misconception to think that a lower pressure input will cause feedwater flow to increase.

2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) ABN-302 Attached w/ Revision # See Main Feedwater Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Main Feedwater system. (LO21.SYS.MF1.OB05)

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 41.5 55.43 Page 12 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 061 K6.01 Level of Difficulty: 3 Importance Rating 2.5 Auxiliary/Emergency Feedwater: Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners.

Question # 14 A Reactor Trip has just occurred on Unit 1:

The TDAFWP is Out-of-Service MDAFWP 1-02 tripped on Overcurrent MDAFWP 1-01 is cross-connected supplying ALL SGs MDAFWP 1-01 total flow to ALL SGs is 600 gpm stable 1-FV-2456, MD AFW PMP 1-01 TO CST RECIRC ISOL VLV loses air pressure Based on the above conditions, complete the statements below.

1. With one MDAFW pump operating supplying all four SGs, flow must be limited to a MAXIMUM of ___(1)___ in order to preclude pump runout.

2. As a result of the failure, flow from MDAFWP 1-01 to all SGs has ___(2)___.

A. (1) 800 gpm (2) lowered B. (1) 700 gpm (2) lowered C. (1) 800 gpm (2) remained the same D. (1) 700 gpm (2) remained the same Answer: A Page 14 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the effect that a loss of air to a valve controller/positioner will have on the system/plant.

Explanation:

A. Correct. 1st part is correct; with one MDAFW pump operating to supply all four SGs, pump flow must be limited to 800 gpm in order to preclude pump runout. 2nd part is correct as the valve will fail open resulting in approximately 200 gpm of flow being diverted away from the Steam Generators to the CST.

B. Incorrect. 1st part is incorrect but plausible because a flow restricting orifice is provided downstream of each feed regulator valve. The orifice is designed to limit the maximum flow to a faulted SG to 700 gpm and prevent a pump runout condition. 2nd part is correct (see A).

C. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible if the misconception exists that the valve failed closed. At the current flow to all SGs the valve would already be closed, therefore, flow to the SGs would remain the same.

D. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is incorrect but plausible (see C).

Technical Reference(s) Auxiliary Feedwater Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Auxiliary Feedwater system and PREDICT the system response. ( LO21SYSAF1OB104 )

Question Source: Bank #

Modified Bank # 2015 NRC Exam Q25 (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 15 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 062 A2.12 Level of Difficulty: 2 Importance Rating 3.2 AC Electrical Distribution: Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Restoration of power to a system with a fault on it.

Question # 15 Unit 1 plant conditions:

A 86-2 LOR fault has occurred on 6.9 KV Safeguards Bus 1EA1 Diesel Generator 1-01 failed to automatically start The crew has entered ABN-602, Response to a 6900/480V System Malfunction Safeguards Bus 1EA1 is needed immediately Based on the conditions above, complete the statements below.

1. Per ABN-602, the Diesel Generator will be started by FIRST attempting a remote

___(1)___ start.

2. When Diesel Generator 1-01 has reached rated voltage and speed the supply breaker CS-1EG1, DG 1 BKR 1EG1 ___(2)___.

A. (1) normal (2) MUST be manually closed B. (1) emergency (2) MUST be manually closed C. (1) normal (2) SHOULD automatically close D. (1) emergency (2) SHOULD automatically close Answer: D Page 19 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to use procedures to correctly energize a bus that had a fault on it.

Explanation:

A. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible even when combined with a normal start of part 1 because this is how the system normally works when a normal start is provided (the breaker must be manually closed).

B. Incorrect. 1st part is correct (see D). 2nd part is incorrect but plausible because if a normal start was performed with no emergency start signal present then the DG output breaker must be manually closed.

C. Incorrect. 1st part is incorrect but plausible because the next step in the procedure is to perform a remote normal start. 2nd part is correct even when combined with a normal start of part 1 because an emergency start signal from the loss of power to the bus will be present, therefore the breaker should automatically close even when a normal start is performed in this case.

D. Correct. 1st part is correct. An emergency start will be attempted FIRST to restore power to the safeguards bus. 2nd part is correct. When the DG has reached rated voltage and speed with an emergency start signal present then the DG output breaker should automatically close.

Technical Reference(s) ABN-602 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Diesel Generator system. (LO21.SYS.ED1.OB123)

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 41.7 55.43 Page 20 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 063 A4.02 Level of Difficulty: 3 Importance Rating 2.8 DC Electrical Distribution: Ability to manually operate and/or monitor in the control room: Battery voltage indicator.

Question # 16 Given the following indications of Unit 1 DC Safeguards Bus voltage in the Control Room:

V-1ED1, 125 VDC SWITCH PNL 1ED1 VOLT, is at 134 volts and 2 amps CHARGE V-1ED2, 125 VDC SWITCH PNL 1ED2 VOLT, is at 135 volts and 1 amp CHARGE V-1ED3, 125 VDC SWITCH PNL 1ED3 VOLT, is at 135 volts and 1 amp CHARGE V-1ED4, 125 VDC SWITCH PNL 1ED4 VOLT, is at 134 volts and 2 amps CHARGE After a plant transient the following is observed:

V-1ED1, 125 VDC SWITCH PNL 1ED1 VOLT, is at 123 volts and 190 amps DISCHARGE V-1ED2, 125 VDC SWITCH PNL 1ED2 VOLT, is at 134 volts and 2 amps CHARGE V-1ED3, 125 VDC SWITCH PNL 1ED3 VOLT, is at 124 volts and 70 amps DISCHARGE V-1ED4, 125 VDC SWITCH PNL 1ED4 VOLT, is at 135 volts and 1 amp CHARGE Which of the following events has caused the change in DC Safeguards Bus voltage?

A loss of...

A. Motor Control Center XEB1-1.

B. Safeguards Bus 1EA1.

C. Motor Control Center XEB2-1.

D. Safeguards Bus 1EA2.

Answer: B Page 24 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor battery voltage in the control room and determine cause of adverse system response.

Explanation:

A. Incorrect. Plausible because this is a Train A Motor Control Center, however, it powers common loads as opposed to the Battery Chargers.

B. Correct. A loss of Safeguards Bus 1EA1 will de-energize 480 V Motor Control Centers 1EB1-1 and 1EB3-1 which power their respective Battery Chargers. As a result, the Battery will become the only source of power and begin to discharge as shown.

C. Incorrect. Plausible because this is a Train B Motor Control Center, however, it powers common loads as opposed to the Battery Chargers.

D. Incorrect. Plausible because two Motor Control Centers have become deenergized, however, it is the Train A Safeguards Bus that is affected as opposed to Train B.

Technical Reference(s) SOP-604A Attached w/ Revision # See CB-11 Snapshot Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the general power supply for the DC Electrical System (Safeguards and non-Safeguards) for the following:

125 Volt DC Train A Safeguards (Busses uED1 and uED3)

(LO21.SYS.DC1.OB08)

Question Source: Bank # 2010 NRC Exam Q21 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 25 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 064 A3.07 Level of Difficulty: 3 Importance Rating 3.6*

Emergency Diesel Generator: Ability to monitor automatic operation of the ED/G system, including: Load Sequencing.

Question # 17 Complete the following statements regarding the Emergency Diesel Generators and the Solid State Safeguards Sequencer.

1. Following receipt of a Blackout Signal the Emergency Diesel Generators are designed to start, attain rated speed and voltage, and be ready-to-load within a MAXIMUM time of

___(1)___.

2. Upon restoration of power to a 6.9 KV Safeguards Bus the piece of equipment that will be automatically sequenced onto the bus FIRST will be the ___(2)___.

A. (1) 10 seconds (2) SSW pump B. (1) 10 seconds (2) CCP C. (1) 5 seconds (2) SSW pump D. (1) 5 seconds (2) CCP Answer: B Page 35 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor automatic operation of the DG and Load Sequencing following a Blackout.

Explanation:

A. Incorrect. 1st part is correct (see B below). 2nd part is incorrect but plausible as this is a common misconception at CPNPP that the SSW pumps are sequenced on first to provide cooling to the EDG.

B. Correct. 1st part is correct. The Diesel Generators are designed such that they will start from an auto or manual start, reach rated voltage and speed, and be ready-to-load within 10 seconds of the start signal. 2nd part is correct. The CCP is sequenced onto the bus before the SSW pump.

C. Incorrect. 1st part is incorrect but plausible as the EDG Starting Air admission valves will close 5 seconds after a normal start signal, this could be easily confused with the 10 second value of when the EDG is ready-to-load. 2nd part is incorrect but plausible (see A above).

D. Incorrect. 1st part is incorrect but plausible (see C above). 2nd part is correct (see B above).

Technical Reference(s) EDG Lesson Plan Attached w/ Revision # See Sequencer Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Blackout Sequencers including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.ES3.OB103)

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 41.7 55.43 Page 36 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 073 K4.01 Level of Difficulty: 3 Importance Rating 4.0 Process Radiation Monitoring: Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint.

Question # 18 Which of the following choices of radiation monitors BOTH input to X-HCV-014, Waste Gas Discharge Control Valve and automatically close the valve?

1) X-RE-5701 (ABV089), Aux Building Vent Exhaust Monitor

2) X-RE-5570A/B (PVG684/685), Plant Vent Stack Wide Range Gas Monitor

3) X-RE-5567A/B (PVG384/385), Plant Vent Stack Noble Gas Monitor

4) X-RE-5700 (FBV088), Fuel Building Vent Exhaust Monitor A. 1 and 2 B. 1 and 3 C. 2 and 4 D. 3 and 4 Answer: A Page 40 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of DRM interlocks that terminate a radiological release.

Explanation:

A. Correct. A high radiation alarm on either the Plant Vent Stack Wide Range Noble Gas Radiation Monitor (PVG684/685) or the Aux Building Vent Duct Radiation Monitor (ABV089) will automatically close HCV-0014.

B. Incorrect. Plausible because the Aux Building Vent Duct Radiation Monitor (ABV089) will automatically close HCV-0014, but the Plant Vent Stack Noble Gas Monitor will not perform this action.

C. Incorrect. Plausible because the Plant Vent Stack Wide Range Noble Gas Monitor (PVG684/685) will automatically close HCV-0014, but the Fuel Building Vent Exhaust Monitor (FBV088) will not perform this action.

D. Incorrect. Plausible because the Fuel Building Vent Exhaust Monitor (FBV088) monitors downstream of HCV-0014, but neither of these monitors will perform this action.

Technical Reference(s) Gaseous Waste Processing Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: COMPREHEND the normal, abnormal and emergency operations of the Gaseous Waste system.

Question Source: Bank # 2012 NRC Exam Q37 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 41 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 076 K4.02 Level of Difficulty: 2 Importance Rating 2.9 Service Water: Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Automatic start features associated with SWS pump controls.

Question # 19 Unit 1 plant conditions:

Unit 1 SSW was in an abnormal lineup with SSW Pump 1-01 RUNNING and SSW Pump 1-02 in STANDBY CCW Pump 1-02 is out of service for preventative maintenance Subsequently SSW Pump 1-01 trips and SSW Pump 1-02 fails to automatically start ABN-501, Station Service Water System Malfunction is entered Based on the above plant conditions, complete the following statements.

1. SSW Pump 1-02 should have started when ___(1)___ in Train A SSW dropped to the required setpoint.

2. The FIRST action directed by ABN-501, is to ___(2)___.

A. (1) header pressure (2) place DG 1-01 in PULL OUT B. (1) header pressure (2) manually start SSW Pump 1-02 C. (1) return header flow (2) place DG 1-01 in PULL OUT D. (1) return header flow (2) manually start SSW Pump 1-02 Answer: A Page 45 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of Service Water Pump automatic starting interlocks.

Explanation:

A. Correct. 1st part is correct. Service Water Pump starts on low header pressure of 10 psig. 2nd part is correct. The first step in ABN-501 is to place the affected train diesel generator handswitch, CS-1DG1E in PULLOUT. This is an Initial Operator Action.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because the first step is to place the EDG in PULLOUT. It is plausible because the second step is to verify that the standby pump started and if not, manually start it.

C. Incorrect. 1st part is incorrect because the starting interlock is based on header pressure, not flow. It is plausible because it would seem likely that an auto start feature on low flow would be desirable. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) ABN-501 Attached w/ Revision # See SSW Study Guide Comments / Reference ALM-0011A Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Station Service Water Header Pressure Low in accordance with ABN-501, Station Service Water System.

Question Source: Bank #

Modified Bank # 2012 NRC Exam Q24 (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 46 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 078 K1.02 Level of Difficulty: 2 Importance Rating 2.7 Instrument Air: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Service air.

Question # 20 Unit 1 plant conditions:

Unit 1 is in MODE 6 during a Refueling Outage Work is in progress inside the Steam Generators Core offload is in progress The Wet Cask Pit is at reduced level for fuel inspection equipment repair A loss of Instrument Air has occurred on Unit 1 Based on the given conditions, which of the following is the impact on the Unit 1 Service Air System?

Service Air...

A. is unavailable for use inside the Control Room Envelope Boundary.

B. must be aligned to the Wet Cask Pit and Spent Fuel Pool X-01 gates.

C. quality must be evaluated prior to aligning to Unit 1 Instrument Air.

D. is unavailable for use inside the Unit 1 Containment Building.

Answer: D Page 54 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge how the Instrument Air and Service Air systems interact.

Explanation:

A. Incorrect. Plausible because it could be thought that loss of instrument air would cause a loss of ability to supply service air inside the CRE boundary, however the controls for service air use inside the CRE boundary are administrative.

B. Incorrect. Plausible because instrument air supplies the gate seals but compressed air bottles are provided for the gate seals.

C. Incorrect. Plausible because the misconception could exist that the service air compressor could be used as a temporary supply to the instrument air per SOP-301A .

D. Correct. 1-HS-3486, CNTMT SERV AIR ISOL VLV will fail close isolating service air to Containment.

Technical Reference(s) ABN-301 Attached w/ Revision # See Service Air Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Instrument Air System.

Question Source: Bank # 2014 NRC Exam Q47 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.9 55.43 Page 55 of 60 CPNPP NRC 2017 RO Written Exam Worksheet 11-20 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 103 A1.01 Level of Difficulty: 3 Importance Rating 3.7 Containment: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity.

Question # 21 Unit 1 plant conditions:

Large Break LOCA has just occurred Containment pressure = 44 psig increasing Phase B Containment Isolation has not occurred Based on the above conditions, complete the following statements.

1. ___(1)___ PHASE B MAN ACT hand switch(es) must be taken to the ACT position at either MCB location to initiate BOTH trains of Phase B equipment.

2. If ONE train of Containment Spray fails to actuate, containment pressure and temperature ___(2)___ remain below its designed limits.

A. (1) ONLY one (2) should B. (1) ONLY one (2) should NOT C. (1) BOTH (2) should D. (1) BOTH (2) should NOT Answer: C Page 1 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how containment systems are operated to prevent exceeding design pressure.

Explanation:

A. Incorrect. 1st part is incorrect because it requires both switches taken to ACT to manually initiate Phase B / Containment Spray. It is plausible because each switch will activate components in both trains. 2nd part is correct because by design, Containment Spray is designed to accomplish its function with only One train.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect because only one train is required to maintain containment pressure below its design pressure. It is plausible because it is a Large Break LOCA and you only have 1 CS train available.

C. Correct. 1st part is correct. 2nd part is correct.

D. Incorrect. 1st part is correct. 2nd part is incorrect but plausible (see B).

Technical Reference(s) Containment Study Guide Attached w/ Revision # See LO21.SYS.CS1 Comments / Reference TS Bases 3.6.4 Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Containment system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.CY1.OB02)

Question Source: Bank # 2014/15 Retake NRC Exam Q28 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014/15 Retake NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.5 55.43 Page 2 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 006 K6.05 Level of Difficulty: 3 Importance Rating 3.0 Emergency Core Cooling System: Knowledge of the effect of a loss or malfunction of the following will have on the ECCS:

HPI/LPI cooling water.

Question # 22 Unit 1 plant conditions:

100% power CCP 1-01 running Complete the following statement regarding cooling water to CCP 1-01.

Assuming NO operator action, a loss of ___(1)___ flow to CCP 1-01 Oil Cooler will cause bearing damage after a MINIMUM of approximately ___(2)___ minutes.

A. (1) SSW (2) 4 B. (1) SSW (2) 13 C. (1) CCW (2) 4 D. (1) CCW (2) 13 Answer: B Page 7 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how a loss of cooling water effects the CCPs which are a pump in the ECCS system Explanation:

A. Incorrect. 1st part is correct. SSW cools the CCP bearing oil coolers. 2nd part is incorrect but plausible because per ABN-101, 4 minutes is the time in which RCP seal damage would occur upon a loss of seal injection and thermal barrier flow. The four minutes for RCP seal damage and the 13 minutes for CCP bearing damage are both relatively new numbers placed in our procedures after operating experience revealed when damage would occur and are numbers that could be confused for each other.

B. Correct. 1st part is correct (see A). 2nd part is correct. Per ABN-501, with a loss of SSW flow to the CCP oil cooler, CCP bearing damage will occur after approximately 13 minutes.

C. Incorrect. 1st part is incorrect but plausible because CCW cools the Seal Water HX which in turn cools the CCP recirculation prior to its return to the VCT. Operating experience at CPNPP has shown that without CCW flow to cool the Seal Water HX the operating CCP will overheat. Also, the Positive Displacement Charging Pump Speed Changer Oil Cooler is cooled by CCW. These two reasons make CCW a plausible distractor. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) ABN-501 Attached w/ Revision # See ABN-101 Comments / Reference SSW Study Guide & Big Book CCW Study Guide & Big Book Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Station Service Water System including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.SW1.OB03)

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 41.4 55.43 Page 8 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 007 G2.1.28 Level of Difficulty: 3 Importance Rating 4.1 Pressurizer Relief/Quench Tank: Knowledge of the purpose and function of major system components and controls.

Question # 23 Unit 1 plant conditions:

Reactor power = 100%

A PRZR Safety valve has been leaking by its seat PRT pressure = 35 psig rising The RCDT system is lined up to cool the PRT Based on the above conditions, complete the following statements:

1. The PRT is cooled by water from the RCDT system being ___(1)___.

2. If cooling is not aligned to the PRT, the PRT rupture disks are designed to fail at a MINIMUM pressure of ___(2)___.

A. (1) sprayed directly into the PRT vapor space (2) 91 psig B. (1) sprayed directly into the PRT vapor space (2) 100 psig C. (1) sparged directly into the PRT water space (2) 91 psig D. (1) sparged directly into the PRT water space (2) 100 psig Answer: A Page 17 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the design function of removing heat from the PRT.

Explanation:

A. 1st part is correct. Water from the RCDT system is sprayed into the PRT vapor space to remove heat which will also reduce pressure. 2nd part is correct. The PRT rupture disks are designed to fail at 91 psig.

B. 1st part is correct (see A). 2nd part is incorrect because the PRT rupture disks are designed to fail at 91 psig. It is plausible because the PRT design pressure is 100 psig.

C. 1st part is incorrect because the PRT is cooled by water being sprayed directly into its vapor space. It is plausible the PRZR Safety valves and PORVs discharge into the PRT water space to remove energy. 2nd part is correct (see A).

D. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) LO21.SYS.RC4 Attached w/ Revision # See LO21.SYS.RC1 Comments / Reference Reactor Coolant System Study Guide Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Reactor Coolant system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.RC1.OB03)

Question Source: Bank #

Modified Bank # 2014/15 Retake NRC (Note changes or attach parent)

Exam Q6 New Question History: Last NRC Exam 2014/15 NRC Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 18 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 012 K2.01 Level of Difficulty: 2 Importance Rating 3.3 Reactor Protection: Knowledge of bus power supplies to the following: RPS channels, components, and interconnections.

Question # 24 Which of the following completes the statements below?

1. RPS Channel II is powered from inverter ___(1)___.

2. This inverter receives normal input power from bus ___(2)___.

A. (1) IV1PC2 A. 1ED2 B. (1) IV1EC2 (2) 1ED2 C. (1) IV1PC2 (2) 1ED4 D. (1) IV1EC2 (2) 1ED4 Answer: A Page 24 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the power supplies to RPS components.

Explanation:

A. Correct. DC bus 1ED2 is the normal power supply to Inverter 1PC2 which powers RPS Channel 2.

B. Incorrect. Incorrect because 1EC2 does not power RPS Channel 2. It is plausible because1EC2 is powered by 1ED2 and does power safeguards equipment.

C. Incorrect. Incorrect because 1ED4 does not power inverter 1PC2. It is plausible because the bypass source for inverter 1PC2 is 1EC4.

D. Incorrect. Incorrect because 1ED4 does not power inverter 1PC2. It is plausible because the bypass source for inverter 1PC2 is 1EC4.

Technical Reference(s) 208, 120 & 118 VAC Dist Study Guide Attached w/ Revision # See Reactor Protection and ESFAS Study Comments / Reference Guide Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Reactor Protection and Engineered Safeguard Actuation Systems including interrelations with other systems to include interlocks and control loops. (LO21.SYS.ES1.OB03)

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 41.7 55.43 Page 25 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 039 K1.08 Level of Difficulty: 2 Importance Rating 2.7 Main and Reheat Steam: Knowledge of the physical connections and/or cause/effect relationships between the MRSS and the following systems: MFW.

Question # 25 Unit 2 plant conditions:

Reactor power = 10%

Based on the above plant condition, the steam supply to the MFW Pump Turbine Low Pressure Control Valves (poppets) will be ___(1)___ and steam from the ___(2)___ will be used to drive the MFP Turbine.

A. (1) open (2) MSRs B. (1) closed (2) Main Steam system C. (1) closed (2) MSRs D. (1) open (2) Main Steam system Answer: D Page 28 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the relationship between the Main & Reheat steam system and the MFW system.

Explanation:

A. Incorrect. 1st part is correct. Speed control will start opening the LP control valves (five poppet valves) to admit steam. Since very little steam will be available at this point from the low-pressure source, the speed control system will continue to open the LP control valves until they are full open and the HP control valve will start to open since both are operated from the same control arm. 2nd part is incorrect. At low power (at 10%, the turbine is not loaded yet), there is not sufficient steam from the MSRs to drive the MFP turbine. It is plausible because at full power, it would be correct.

B. Incorrect. 1st part is incorrect but plausible since the MFP will be driven by HP steam from the Main Steam System and the question is asking about the Low Pressure poppets. It is reasonable to think that when high pressure steam is driving the MFP the low pressure poppets would be closed. 2nd part is correct. At low power (at 10%, the turbine is not loaded yet), there is not sufficient steam from the MSRs to drive the MFP turbine, therefore, the LP Control Valves will open in sequence to raise MFP speed, with no significant steam flow available it will continue to open until all of the LP Control Valve are open and the HP Control valve opens to supply steam from the main steam system.

C. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see A). 2nd part is correct (see B).

Technical Reference(s) Main Steam Study Guide Attached w/ Revision # See Main Feedwater Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the basic design and flowpath of the Main Feedwater system.

(LO21.SYS.MF1.OB102)

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 41.4 55.43 Page 29 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 062 A3.04 Level of Difficulty: 3 Importance Rating 2.7 AC Electrical Distribution: Ability to monitor automatic operation of the ac distribution system, including: Operation of inverter (e.g., precharging synchronizing light, static transfer).

Question # 26 Unit 1 plant conditions:

Reactor power = 100%

Inverter IV1EC1 is powered from its normal source Based on the above plant conditions, complete the following statement.

Inverter IV1EC1 static transfer switch will automatically transfer panel 1EC1 to ___(1)___ if inverter ___(2)___ voltage lowers to < 105 volts.

A. (1) 1EC3 (2) DC Input B. (1) 1EC3 (2) AC Output C. (1) 1EC4 (2) DC Input D. (1) 1EC4 (2) AC Output Answer: A Page 32 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the automatic operation of inverters .

Explanation:

A. Correct. 1st part is correct. The bypass power source for 1EC1 is 1EC3. 2nd part is correct. The static transfer switch for inverter IV1EC1 will transfer to its bypass source if DC input voltage drops to below 105 VDC.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because AC output voltage would have to lower to ~ 59 VAC for the static transfer switch to actuate. It is plausible because the there is a transfer based on low AC output voltage and 105 Volts IS the DC input setpoint.

C. Incorrect. 1st part is incorrect because the bypass source is 1EC3. It is plausible because if it were a Train B inverter, it would be correct. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) 208, 120 & 118 VAC Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the 208/120 VAC, 118 VAC Distribution, Inverters and Lighting system. (LO21.SYS.AC3.OB06)

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 41.7 55.43 Page 33 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 063 K2.01 Level of Difficulty: 2 Importance Rating 2.9 DC Electrical Distribution: Knowledge of bus power supplies to the following: Major DC loads.

Question # 27 A loss of DC Bus _________ would cause all steam dump valves to fail closed.

A. 1D1 B. 1ED1 C. 1D3 D. 1ED3 Answer: B Page 37 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of DC electrical loads.

Explanation:

A. Incorrect. This is not supplied by 1D1. It is plausible because this is a 125 VDC power supply and does supply power to some turbine control systems.

B. Correct. Upon a loss of 1ED1 or 1ED2, all steam dump valves would fail closed due to the loss of Train arming solenoid valve power.

C. Incorrect. This is not supplied by 1D3. It is plausible because this is a 125 VDC power supply and does supply some turbine control circuits.

D. Incorrect. This is not supplied by 1ED3. It is plausible because this is a 1E 125 VDC power supply.

Technical Reference(s) 208, 120 & 118 VAC Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DEMONSTRATE an understanding of the components of the DC Electrical Distribution system including interrelations with other systems to include interlocks and control loops. (LO21.SYS.DC1.OB02)

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 41.7 55.43 Page 38 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 076 A4.01 Level of Difficulty: 3 Importance Rating 2.9 Service Water: Ability to manually operate and/or monitor in the control room: SWS pumps.

Question # 28 Unit 2 plant conditions:

Reactor power = 100%

Loss of Offsite Power occurs Both Station Service Water (SSW) Pumps were in operation prior to the Reactor Trip Safeguards Bus 2EA2 has an 86-1 Lockout Relay actuated Both Emergency Diesel Generators have responded per design Which of the following is the status of the SSW Pumps 1 minute later?

A. NO SSW Pump is running.

B. BOTH SSW Pumps are running.

C. SSW Pump 2-01 is running and SSW Pump 2-02 is NOT running.

D. SSW Pump 2-01 is NOT running and SSW Pump 2-02 is running.

Answer: C Page 41 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring ability to monitor SWS pump operation with a safeguard bus lockout and determine proper operation of the SWS system.

Explanation:

A. Incorrect. Plausible because misconceptions on when the SSW Pumps are started could exist. If it were 40 seconds earlier, it would be correct.

B. Incorrect. Plausible because SSW Pump 2-02 would be running if the lockout was an 86-2.

C. Correct. With an 86-1 bus 2EA2 will not be powered from the EDG, the other bus, 2EA1 will be powered from the EDG and SSW Pump 2-01 will have started on the Blackout Sequencer at 25 seconds.

D. Incorrect. Plausible if confused which bus had the LOR when answering the question.

Technical Reference(s) ABN-602 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: RELATE operating experience with the Station Service Water and Component Cooling Water systems operation. (LO21.SST.SW1.OB06)

Question Source: Bank #

Modified Bank # 2012 NRC Exam Q23 (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 42 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 001 A1.02 Level of Difficulty: 3 Importance Rating 3.1 Control Rod Drive: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including: T-ref.

Question # 29 Unit 1 plant conditions:

Reactor power = 80%

Control rods are in MANUAL When the operator attempts to correct Tave, control rods are inadvertently placed in AUTO Based on the conditions provided, determine the following:

1. The MAXIMUM initial rate of control rod movement in steps per minute (spm).

2. The proper direction of control rod movement.

A. (1) 36 spm (2) OUT B. (1) 36 spm (2) IN C. (1) 40 spm (2) OUT D. (1) 40 spm (2) IN Answer: C Page 46 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor control rods movement based on deviation from Tref.

Explanation:

A. Incorrect. 1st part is incorrect with 4.0oF deviation the initial rod withdrawal rate will be 40 steps per minute. From 3-5oF error, the rod speed is ramped form 8 steps to 72 steps per minute. At 4oF error, the speed will be half way between 8 and 72 steps per minute (64/2 = 32 steps per minute + 8 steps = 40 steps per minute). It is plausible because if the error is taken half way between 3 and 5oF as half way between 0 and 72 steps per minute, the answer would be 36 steps per minute. 2nd part is correct with Tave lower than Tref control rods will withdraw or move OUT to restore Tave to Tref.

B. Incorrect. 1st part is incorrect but plausible (see A above). 2nd part is incorrect but plausible as when temperature lowers it adds positive reactivity to the core, therefore a common misconception is that rods must then be inserted or driven IN to add negative reactivity to the core to zero the net reactivity of the core.

C. Correct. 1st part is correct with 4.0oF deviation the initial rod withdrawal rate will be 40 steps per minute. From 3-5oF error, the rod speed is ramped form 8 steps to 72 steps per minute. At 4oF error, the speed will be half way between 8 and 72 steps per minute (64/2 = 32 steps per minute

+ 8 steps = 40 steps per minute). 2nd part is correct (see A above).

D. Incorrect. 1st part is correct (see C above). 2nd part is incorrect but plausible (see B above).

Technical Reference(s) Rod Control Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Rod Control System and PREDICT the system response. (LO21.SYS.CR1.OB04)

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 41.5 55.43 Page 47 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 002 K1.12 Level of Difficulty: 3 Importance Rating 3.5*

Reactor Coolant: Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: NIS.

Question # 30 Unit 1 plant conditions:

Power ramp is in progress Based on condition above, complete the following statements.

1. When Reactor Power is at 45%, the RCS Loop Low Flow Reactor Trip will occur if flow in a MINIMUM of ___(1)___ decrease(s) below 90% rated flow.

2. 1-PCIP, Window 4.5 - RX 48% PWR 3-LOOP FLO PERM P-8 will be EXTINGUISHED when ___(2)___ PR NIs increase to above 48% reactor power.

A. (1) 1 RCS loop (2) 2 out of 4 B. (1) 1 RCS loop (2) 3 out of 4 C. (1) 2 RCS loops (2) 2 out of 4 D. (1) 2 RCS loops (2) 3 out of 4 Answer: C Page 50 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the relationship between the RCS (RCS Loop Low Flow Reactor Trip) and PR NIs.

Explanation:

A. Incorrect. 1st part is incorrect but plausible because if Reactor power were above 48% then the RX 48% PWR 3-LOOP FLO PERM P-8 Window on the PCIP would be EXTINGUISHED and then only 1 RCS loop 90% rated flow would cause the RCS Loop Low Flow Reactor Trip to occur. 2nd part is correct as Rx power INCREASES above 48% power the RX 48% PWR 3-LOOP FLO PERM P-8 Window will EXTINGUISH when 2 out of 4 Power Range Nuclear Instruments RISE above 48% power.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect but plausible because if Reactor power were LOWERING below 48% power then the RX 48% PWR 3-LOOP FLO PERM P-8 Window would LIGHT when 3 out of 4 Power Range Nuclear Instruments FELL below 48% power.

C. Correct. 1st part is correct with Rx power < 48% (at 45%) then the RX 48% PWR 3-LOOP FLO PERM P-8 Window on the PCIP is LIT and 2 RCS loops 90% rated flow will cause the RCS Loop Low Flow Reactor Trip to occur. 2nd part is correct, in order to EXTINGUISH the RX 48%

PWR 3-LOOP FLO PERM P-8 window on the PCIP then 2 out of 4 PR NIs must be 48% power.

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) 1-PCIP Attached w/ Revision # See Excore Instrument Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Excore Instrumentation system. (LO21.SYS.EC1.OB05)

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 41.6 55.43 Page 51 of 55 CPNPP NRC 2017 RO Written Exam Worksheet 21-30 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 015 K2.01 Level of Difficulty: 2 Importance Rating 3.3 Nuclear Instrumentation: Knowledge of bus power supplies to the following: NI channels, components, and interconnections.

Question # 31 The normal power supply to Power Range Nuclear Instrument 1-NI-41 is _________.

A. 1PC1 B. 1PC2 C. 1PC3 D. 1PC4 Answer: A Page 1 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the power supplies to the Power Range Nuclear Instruments.

Explanation:

A. Correct. Power to the PR Nuclear Instrument 1-NI-41 is 1PC1.

B. Incorrect. Plausible as 1PC2 is the power supply to PR Nuclear Instrument 1-NI-42.

C. Incorrect. Plausible as 1PC3 is the power supply to PR Nuclear Instrument 1-NI-43.

D. Incorrect. Plausible as 1PC4 is the power supply to PR Nuclear Instrument 1-NI-44.

Technical Reference(s) ABN-603, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Excore Instrumentation system. (LO21.SYS.EC1.OB05)

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 41.7 55.43 Page 2 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 017 K3.01 Level of Difficulty: 2 Importance Rating 3.5 In-Core Temperature Monitor: Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: Natural circulation indications.

Question # 32 Unit 1 plant conditions:

Reactor Trip due to a Loss of Offsite Power and SBLOCA EOS-1.2A, Post LOCA Cooldown and Depressurization in progress PRZR level = 33% stable Core Exit Thermocouples (CETs) are NOT available Natural circulation is being verified:

Pressurizer pressure = 2000 psig stable Intact SG pressures = 855 psig stable RCS Hot Leg temperatures = 540°F stable RCS Cold Leg temperatures = 528°F stable Based on the above plant conditions, complete the following statements.

1. The parameters stated ___(1)___ indicate natural circulation exists.

2. IF Natural Circulation is unable to be verified, EOS-1.2A directs ___(2)___ in an attempt to establish Natural Circulation.

A. (1) do NOT (2) raising AFW flow B. (1) do (2) raising AFW flow C. (1) do NOT (2) opening ARVs D. (1) do (2) opening ARVs Answer: D Page 4 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge how to verify natural circulation when the Core Exit TCs have been lost.

Explanation:

A. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

B. Incorrect. 1st part is correct (see D). 2nd part is incorrect because EOS-1.2A directs dumping more steam in an effort to establish natural circulation cooling. It is plausible because increasing AFW flow would raise SG level and could lower the heat sink temperature (raising the T) but EOS-1.2A specifically directs dumping more steam if NC cannot be verified.

C. Incorrect. 1st part is incorrect because the indications provided do support natural circulation. It is plausible because temperatures being stable do not seem to support that cooling is taking place. It is common to erroneously think that SG pressure would be lowering as decay heat lowers. It is also a common error to think that since Thot is not lowering, cooling is not taking place. 2nd part is correct (see D).

D. Correct. 1st part is correct. Tcold is at the Saturation pressure for SGs and the core is currently Subcooled based on PRZR pressure. 2nd part is correct. Per EOS-1.2A, if natural circulation cannot be verified, you are to dump more steam, thus opening ARVs would dump more steam.

Technical Reference(s) EOS-1.2A & Attachment 3 Attached w/ Revision # See CCM-RVLIS Study Guide Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: EXPLAIN the instrumentation and controls of the Core Cooling Monitor system and PREDICT the system response. (LO21.SYS.RC3.OB104)

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 41.7 55.43 Page 5 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 029 K4.03 Level of Difficulty: 2 Importance Rating 3.2*

Containment Purge: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Automatic Purge Isolation.

Question # 33 Unit 1 plant conditions:

100% power Inadvertent Safety Injection occurs Which of the following describes how isolation of the Containment Purge Supply and Exhaust System is verified?

Verification of the position of these dampers is performed by checking _________

windows LIT on the Monitor Light Box Panels.

A. red B. white C. green D. orange Answer: C Page 11 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how to verify the Containment Purge system is automatically isolated after a Safety Injection which is a design feature of CVI.

Explanation:

A. Incorrect. Plausible since red windows are for Phase A and vent dampers are closed by CVI.

B. Incorrect. Plausible since white windows are for proper SI alignment and vent dampers are closed by CVI.

C. Correct. In Modes 1-4 these dampers have the fuses removed so no position indication is available on the hand switches. Position is determined by checking the green CVI lights LIT on MLBs.

D. Incorrect. Plausible since orange windows are for proper phase B alignment and vent dampers are closed by CVI.

Technical Reference(s) EOP-0.0A Attached w/ Revision # See MLB Color Key Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the location (if applicable) of the following indications and controls, and DESCRIBE how each is interpreted or used to predict, monitor, or control changes in the Containment Ventilation System: 7) Fan and damper hand switches. (LO21.SYS.CL1.OB04)

Question Source: Bank #

Modified Bank # 2005 NRC Exam Retake (Note changes or attach parent)

Q61 New Question History: Last NRC Exam 2005 NRC Exam Retake Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 12 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 2 K/A 034 K1.04 Level of Difficulty: 3 Importance Rating 2.6 Fuel Handling Equipment: Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems: NIS Question # 34 During manipulation of fuel assemblies in the reactor vessel, Source Range channel N-31 fails low while Gamma-Metrics SR instrument N-0050B is INOPERABLE.

Which of the following actions are required per Technical Specification 3.9.3, Nuclear Instrumentation?

Suspend all CORE ALTERATIONS immediately A. WHILE initiating actions to restore SR channel N-31 AND Gamma-Metrics SR N-0050B to OPERABLE status immediately.

B. WHILE initiating actions to restore SR channel N-31 AND Gamma-Metrics SR N-0050B to OPERABLE status within 1hour.

C. AND suspend operations that would cause introduction of coolant into the RCS with boron concentration the COLR limit immediately.

D. AND suspend operations that would cause introduction of coolant into the RCS with boron concentration the COLR limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Answer: C Page 19 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the cause-effect relationship between Fuel Handling operations in the Reactor Vessel and the operability of Source Range Nuclear Instruments.

Explanation:

A. Incorrect. Plausible since this would restore BOTH inoperable monitors and action would have to be taken immediately to restore ONE of these monitors if two of the required monitors were INOPERABLE per TS 3.9.3, however, the action time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is incorrect.

B. Incorrect. Plausible since this would restore BOTH inoperable monitors and action would have to be taken immediately to restore ONE of these monitors if two of the required monitors were INOPERABLE per TS 3.9.3.

C. Correct. With conditions met to ONLY enter Condition A of TS 3.9.3 and NOT Condition B (two required source monitors are NOT inoperable), Condition A requires suspension of operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1 immediately. TS LCO 3.9.1 requires boron concentrations less than the COLR limit.

D. Incorrect. Plausible because the action is correct, however, the time for the action to be completed is immediately, NOT 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Technical Reference(s) RFO-102 Attached w/ Revision # See TS 3.9.3 Comments / Reference TSB 3.9.3 Proposed references to be provided during examination:

Learning Objective: DESCRIBE the Fuel Handling structures including design features to preclude an inadvertent criticality. (LO21.RFO.FH1.OB01)

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 41.7 55.43 Page 20 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 035 A2.03 Level of Difficulty: 2 Importance Rating 3.4 Steam Generator: Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Pressure/level transmitter failure.

Question # 35 Unit 1 plant conditions:

Time = 0800:

Reactor power = 100%

A leak develops in the reference leg of the controlling NR level detector for SG 1-01 ABN-710, Steam Generator Level Instrumentation Malfunction is entered SG 1-01 level is being controlled manually Time = 0815:

An alternate SG level channel has been selected It is desired to place SG level control in AUTOMATIC Based on the above plant conditions, complete the following statements.

1. The leak in the reference leg will cause indicated level in SG 1-01 to ___(1)___.

2. In accordance with ABN-710, when SG 1-01 level is stable at ___(2)___, you are to place the Feedwater Flow Control Valve in AUTOMATIC.

A. (1) lower (2) 64%

B. (1) lower (2) 67%

C. (1) rise (2) 64%

D. (1) rise (2) 67%

Answer: D Page 25 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to predict the impact of a failure and use the appropriate procedure to mitigate/correct the issue.

Explanation:

A. Incorrect. 1st part is incorrect because indicated level will rise. It is plausible because actual level would lower (if the control system was not in manual) when the control system reduces FW to the SG and it is a common error to think that a leak in a reference leg will cause indicated level to lower. 2nd part is incorrect because program level for Unit 1 SGs is 67%. It is plausible because if it were Unit 2, it would be correct.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. ABN-710 directs you to place in automatic when level is stable at program level. For Unit 1, this is 67%.

C. Incorrect. 1st part is correct (see D). 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct. A leak in the reference leg will cause indicated level to rise. 2nd part is correct (see B).

Technical Reference(s) ABN-710 Attached w/ Revision # See SGWLC Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: DIFFERENTIATE between the Unit 1 and Unit 2 Steam Generator Water Level Control systems. (LO21.SYS.SN1.OB07)

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 41.5 55.43 Page 26 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 045 K5.18 Level of Difficulty: 3 Importance Rating 2.7 Main Turbine Generator: Knowledge of the operational implications of the following concepts as they apply to the MT/B System: Purpose of low-power reactor trips (limited to 25% power).

Question # 36 Unit 1 plant conditions:

Unit startup is in progress in accordance with IPO-003A, Power Operations Reactor Power = 9% stable The main turbine is being synchronized to the grid A turbine control malfunction results in a reactor power excursion Based on the above plant conditions, complete the following statements.

1. The design basis of the Intermediate Range Neutron Flux trip is to protect against

___(1)___ from a subcritical condition.

2. If Intermediate Range power exceeds the IR High Flux Trip Setpoint due to the power excursion, the reactor ___(2)___.

A. (1) steam line break (2) will trip because this trip is still active B. (1) steam line break (2) will NOT trip because this trip has been blocked C. (1) uncontrolled control rod withdrawal (2) will trip because this trip is still active D. (1) uncontrolled control rod withdrawal (2) will NOT trip because this trip has been blocked Answer: C Page 31 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the reason for the high flux trip (25%) and how turbine operations can interact with this trip.

Explanation:

A. Incorrect. 1st part is incorrect because per TSB 3.3.1, the purpose of this trip is to protect against a rod withdrawal while in the source range. It is plausible because a steam line break in the source range at EOL could also cause that trip setpoint to be reached. 2nd part is correct. IAW IPO-003A, the turbine is paralleled and loaded prior to blocking the IR and PR 25% reactor trip so this trip would still be active.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect because the trip is still in effect at this point in IPO-003A. It is plausible because if you think (in error) that the turbine is loaded after going above 10% power, it would seem logical that the 25% reactor trips would be blocked at this point.

C. Correct. 1st part is correct. This reactor trip is designed to protect against a rod withdrawal accident while subcritical. 2nd part is correct (see A).

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) IPO-003A Attached w/ Revision # See TSB 3.3.1 Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Reactor Protection and Engineered Safeguard Actuation Systems.

(LO21.SYS.ES1.OB05)

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 41.5 55.43 Page 32 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 075 G2.1.27 Level of Difficulty: 2 Importance Rating 3.9 Circulating Water: Knowledge of system purpose and/or function.

Question # 37 Unit 1 Circulating Water system normally supplies cooling water to Ventilation Chiller _________.

A. X-02 B. X-04 C. X-06 D. X-08 Answer: C Page 38 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of purpose of the Circulating Water System which includes the loads that it cools.

Explanation:

A. Incorrect. Chiller X-02 is cooled by CCW. It is plausible because Unit 1 Circulating Water does cool Chiller X-05 and X-06.

B. Incorrect. Chiller X-04 is cooled by CCW. It is plausible because Unit 1 Circulating Water does cool Chiller X-05 and X-06.

C. Correct. Unit 1 Circulating Water cools chiller X-05 and X-06.

D. Incorrect. Chiller X-08 is cooled by Unit 2 Circulating Water. It is plausible because if it were Unit 2 Circulating Water, it would be correct.

Technical Reference(s) Circulating Water Study Guide Attached w/ Revision # See Ventilation Chill Water Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Circulating Water system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.CW1.OB03)

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 41.7 55.43 Page 39 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 068 A4.04 Level of Difficulty: 2 Importance Rating 3.8 Liquid Radwaste: Ability to manually operate and/or monitor in the control room: Automatic isolation.

Question # 38 Which of the following will cause an AUTO closure of X-RV-5253, Liquid Waste Processing System Discharge Isolation Valve while a release is in progress?

A. PC-11 channel not responding to POLL (MAGENTA).

B. Only 2 of 4 Circulating Water Pumps running on associated Unit.

C. PC-11 channel in ALERT alarm (YELLOW).

D. Loss of counts on X-RE-5253, Liquid Effluent Radiation Monitor.

Answer: D Page 43 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor automatic actions of the Liquid Radwaste system.

Explanation:

A. Incorrect. Plausible because it could be thought that a monitor not responding to POLL would be INOPERABLE.

B. Incorrect. Plausible because Circulating Water Pumps must be running for the valve to remain open, however, a 2 of 4 coincidence allows release to Unit aligned for discharge.

C. Incorrect. Plausible because radiation level has increased, however, it requires a high radiation level alarm to close X-RV-5253.

D. Correct. A loss of counts on the Liquid Effluent Radiation Monitor will trip X-RV-5253 (OPERATE FAILURE).

Technical Reference(s) ALM-3200 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Gaseous Waste system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.RWS.OB03)

Question Source: Bank # 2013 NRC Exam Q38 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 44 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 009 EA2.22 Level of Difficulty: 2 Importance Rating 3.0 Small Break LOCA: Ability to determine or interpret the following as they apply to a small break LOCA: Charging flow trend recorder.

Question # 39 Unit 1 plant conditions:

Time = 0800:

Reactor power = 100%

Time = 0803:

RCS pressure = 1700 psig lowering Pressurizer level = 20% lowering Based on plant conditions at Time = 0803, the Charging Flow Recorder on CB-06 will indicate _________.

(Assume that 1-FK-0121, CCP Charging Flow Controller remains in AUTO).

A. no flow B. minimum flow in auto C. flow equal to seal injection flow D. flow equal to seal injection plus safety injection flow Answer: C Page 49 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine/interpret what the charging flow recorder should indicate during a small break LOCA.

Explanation:

A. Incorrect. The recorder will display normal charging flow (isolated) plus seal injection flow. As Przr level lowers, FCV-0121 will open. As this occurs, seal injection flow will increase which will be reflected on the charging flow recorder. It is plausible because normal charging flow isolates on an SI signal.

B. Incorrect. The recorder will display normal charging flow (isolated) plus seal injection flow.

As Przr level lowers, FCV-0121 will open more but the only flow path downstream of FCV-0121 is through seal injection valves. It is plausible because 55 gpm is the minimum setting on FCV-0121 controller to maintain sufficient flow through the RHX.

C. Correct. The flow recorder indicates normal charging flow which includes seal injection flow. During an SI, normal charging isolation valves isolate but the seal injection valves do not so the charging flow recorder will only display the flow that is going to seal injection.

D. Incorrect. The charging flow recorder measures flow downstream of the SI isolation valves. It is plausible because it is for measuring CCP flow.

Technical Reference(s) CVCS Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Chemical and Volume Control system. (LO21.SYS.CS1.OB04)

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 41.7 55.43 Page 50 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 015/17 AK1.04 Level of Difficulty: 3 Importance Rating 2.9 RCP Malfunctions: Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow.

Question # 40 Unit 2 plant conditions:

Reactor power = 35%

RCP 2-02 trips

1. In the 30 seconds following the trip of RCP 2-02, and assuming NO operator action, SG 2-02 water level will initially ___(1)___.

2. Upon plant stabilization RCS Loop 2 differential temperature will be ___(2)___ than prior to RCP 2-02 trip.

A. (1) shrink (2) larger B. (1) shrink (2) smaller C. (1) swell (2) larger D. (1) swell (2) smaller Answer: B Page 55 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine/interpret what the charging flow recorder should indicate during a small break LOCA.

Explanation:

A. Incorrect. 1st part is correct; when RCP trips the SG will stop steam causing SG pressure to rise. A rise in SG pressure will cause the Steam bubbles in the downcomer region, where SG level is measured, to collapse level resulting a lowering SG level, initially. 2nd part is incorrect but plausible, natural circulation conditions usually established during a loss of forced flow will result in a larger delta temperature.

B. Correct. 1st part is correct; when RCP trips the SG will stop steam causing SG pressure to rise. A rise in SG pressure will cause the Steam bubbles in the downcomer region, where SG level is measured, to collapse level resulting a lowering SG level, initially. 2nd part correct, upon a loss of forced flow with other RCPs running the flow through the loop will reverse and stabilize at Thot. Delta Temperature will stabilize at 0.

C. Incorrect. 1st part is incorrect but plausible because SG will stop steaming and FCV are over feeding which will result in SG levels rising after the initial shrink. 2nd part is incorrect but plausible, natural circulation conditions usually established during a loss of forced flow will result in a larger delta temperature.

D. Incorrect. 1st part is incorrect but plausible because SG will stop steaming and FCV are over feeding which will result in SG levels rising after the initial shrink. 2nd part is correct (see B)

Technical Reference(s) ABN-101 Attached w/ Revision # See SGWLC Study Guide Comments / Reference EOS-0.2A Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to an RCP Trip per ABN-101, Reactor Coolant Pump Trip/Malfunction.

Question Source: Bank #

Modified Bank # 2013 NRC Exam Q42 (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.8 55.43 Page 56 of 61 CPNPP NRC 2017 RO Written Exam Worksheet 31-40 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 022 G2.1.25 Level of Difficulty: 3 Importance Rating 3.9 Loss of Rx Coolant Makeup: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Question # 41 Unit 2 plant conditions:

The crew is responding to a leak in the RCS per ABN-103, Excessive Reactor Coolant Leakage The crew is also responding to a loss of automatic and manual makeup to the VCT per ABN-105, CVCS System Malfunction The following parameters are observed:

Letdown flow = 140 gpm stable Seal Water Return flow = 12 gpm stable Charging flow = 172 gpm stable Seal Water Injection flow = 8 gpm per RCP stable VCT level = 52% lowering Pressurizer level = 60% stable Assuming makeup to the VCT CANNOT be restored what is the MAXIMUM amount of time that can elapse prior to the Charging Pump suction automatically transferring to the RWST?

REFERENCE PROVIDED A. 55 minutes B. 47 minutes C. 29 minutes D. 18 minutes Answer: B Page 1 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine/interpret information from a table (TDM-804B) to calculate gallons in the VCT and then determine how long until the charging pump suction swaps due to charging system leakage with no Rx Coolant System Makeup capability.

Explanation:

A. Incorrect. Plausible because if 60% is used for VCT level, vice 52% by misreading the stem, then 60% - 2% = 1094.4 gallons. Leak Rate = Charging - (Letdown + Seal Water Return flow) =

172 gpm - (140 + 12) gpm = 20 gpm. 1094.4 / 20 gpm = 54.72 minutes.

B. Correct. Using TDM-804B, 52% - 2% = 1506.2 gallons - 562.6 gallons = 943.6 gallons.

Leak Rate = Charging - (Letdown + Seal Water Return flow) = 172 gpm - (140 + 12) gpm = 20 gpm. 943.6 gallons / 20 gpm = 47.18 minutes.

C. Incorrect. Plausible because using TDM-804B, 52% - 2% = 1506.2 gallons - 562.6 gallons =

943.6 gallons. If thought that Leak Rate = Charging - Letdown = 172 gpm - 140 gpm = 32 gpm.

943.6 / 32 gpm = 29.49 minutes D. Incorrect. Plausible because using TDM-804B, 52% - 2% = 1506.2 gallons - 562.6 gallons =

943.6 gallons. If thought that Leak Rate = (Charging + Seal Water Injection) - (Letdown + Seal Water Return) = (172 + 32) - (140 + 12) = 52 gpm. 943.6 gpm / 52 gpm = 18.15 minutes.

Technical Reference(s) CVCS Study Guide Attached w/ Revision # See TDM-804B Comments / Reference Proposed references to be provided during examination: TDM-804B, VCT 2-01 Learning Objective: ANALYZE the response to a Reactor Coolant System Malfunction in accordance with ABN-105, CVCS System Malfunction Question Source: Bank #

Modified Bank # ILOT0910 (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 41.10 55.43 Page 2 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 025 AK2.01 Level of Difficulty: 3 Importance Rating 2.9 Loss of RHR System: Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: RHR heat exchangers.

Question # 42 Unit 1 plant conditions:

Unit 1 is in MODE 4 entering a Refueling outage Residual Heat Removal (RHR) Train A is in Shutdown Cooling Mode Which of the following would result in the loss of Train A RHR heat removal capability?

A. A loss of power to 1-HV-606, U1 RHR HX 1-01 FLO CTRL VLV.

B. Closing 1CC-0109, RHR HX 1-01 CCW SPLY ISO VLV.

C. A loss of power to 1-FCV-618, RHR HX 1-01 BYP FLO CTRL VLV.

D. Closing 1-HV-4572, RHR HX 1-01 CCW RET VLV.

Answer: D Page 5 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the relationship between the RHR heat exchangers and the rest of the RHR system.

Explanation:

A. Incorrect. Plausible if thought that the RHR Heat Exchanger Flow Control Valve will close on a loss of power. However, this valve fails open on a loss of power allowing maximum flow through the RHR Heat Exchanger and thus increases the RHR heat removal capability.

B. Incorrect. Plausible because a typical isolation valve would terminate flow when closed and result in a complete loss of heat removal capability. However, the CCW Inlet Isolation valve for the RHR Heat Exchangers are of special design with an orifice in the disc that allows sufficient flow for the RHR system to meet design basis accident criteria when closed. Thus closing of this valve would reduce the flow of CCW through the RHR Heat Exchanger but would not result in a loss of RHR heat removal capability.

C. Incorrect. Plausible if thought that the RHR Heat Exchanger Bypass Flow Control Valve will open on a loss of power. However, this valve fails closed on a loss of power which forces all RHR flow through the RHR Heat Exchanger and thus increases the RHR heat removal capability.

D. Correct. As the plant is in Shutdown Cooling Mode, Component Cooling Water flow has been adjusted to RHR Heat Exchanger 01. Closing the CCW return valve would remove RHR heat removal capability.

Technical Reference(s) Residual Heat Removal Study Guide Attached w/ Revision # See SOP-102A Comments / Reference Proposed references to be provided during examination:

Learning Objective: DEMONSTRATE an understanding of the components of the Residual Heat Removal system including interrelations with other systems to include interlocks and control loops.

Question Source: Bank # 2014 NRC Exam Q6 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 6 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 026 AA2.04 Level of Difficulty: 2 Importance Rating 2.5 Loss of Component Cooling Water: Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The normal values and upper limits for the temperatures of the components cooled by CCW.

Question # 43 Unit 1 plant conditions:

Reactor power = 100%

CCW to the Non-Safeguards loop isolates Based on the above plant conditions, complete the following statement regarding the temperature of letdown flow on the exit of the Letdown Heat Exchanger.

When CCW to the Letdown Heat Exchanger is lost, letdown temperature will rise from a normal temperature of ___(1)___, and 1-TCV-0129, High Temperature Diversion Valve will direct water to the VCT (bypassing the Letdown Demineralizer) when temperature rises to a setpoint of ___(2)___, to avoid damaging the resin in the demineralizers.

A. (1) 95oF (2) 125oF B. (1) 95oF (2) 135oF C. (1) 115oF (2) 125oF D. (1) 115oF (2) 135oF Answer: B Page 13 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine the normal values and limits for the temperatures (letdown temperature) of the components cooled by CCW (letdown HX).

Explanation:

A. Incorrect. 1st part is correct. Normal downstream temperature of the letdown HX is 95oF. 2nd part is incorrect because the Letdown High Temp Divert Valve setpoint is 135oF. It is plausible because 125oF is the high temperature alarm setpoint.

B. Correct. 1st part is correct (see A). 2nd part is correct. The divert valve setpoint is 135oF.

C. Incorrect. 1st part is incorrect because the normal temperature at the outlet of the LD HX is 95oF.

It is plausible because 115oF is the assumed temperature of the VCT when calculating NPSH requirements for the CCPs. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) CVCS Study Guide Attached w/ Revision # See CCW Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Component Cooling Water System and PREDICT the system response. (LO21.SYS.CC1.OB04)

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 41.7 55.43 Page 14 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 027 AK3.03 Level of Difficulty: 2 Importance Rating 3.7 Pressurizer Pressure Control System Malfunction: Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction.

Question # 44 Unit 1 plant conditions:

1/1-PS-455F, PRZR PRESS CTRL CHAN SELECT is in the 455/456 position PRZR pressure controlling channel fails LOW Based on the above conditions, complete the statement below.

In accordance with ABN-705, Pressurizer Pressure Malfunction, the reason 1-PK-455A, PRZR MASTER PRESS CTRL is placed in MANUAL prior to selecting an alternate controlling channel on 1/1-PS-455F, PRZR PRESS CTRL CHAN SELECT is to prevent A. a PRZR PRESS LO Reactor Trip from occurring B. a PRZR PRESS HI Reactor Trip from occurring C. 1-PCV-455A, PRZR PORV from opening D. 1-PCV-456, PRZR PORV from opening Answer: C Page 18 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the reason for placing 1-PK-455A in manual prior to selecting an alternate control channel following a channel failure.

Explanation:

A. Incorrect. Plausible because it is a misconception that the improper sequence could momentarily cause a second low pressure signal and result in an inadvertent reactor trip.

B. Incorrect. Plausible because it could be thought that the high pressure trip could be initiated but the coincidence is 2 of 4 and only one channel is failed.

C. Correct. ABN-705 requires placing the master pressure controller in manual prior to selecting an alternate controlling channel due to the possibility of inadvertently opening the associated PORV due to the proportional/integral controller response.

D. Incorrect. The explanation is correct but the associated PORV is 1-PCV-455A not 1-PCV-456.

Technical Reference(s) ABN-705 Attached w/ Revision # See Pressurizer Pressure and Level Control Comments / Reference Study Guide Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Pressurizer Pressure and Level Control System. (LO21.SYS.PP1.OB07).

Question Source: Bank # 2014/15 RO NRC Retake Exam Q45 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014/15 RO NRC Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.5 55.43 Page 19 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 029 EK2.06 Level of Difficulty: 3 Importance Rating 2.9 ATWS: Knowledge of the interrelations between the and the following an ATWS: Breakers, relays, and disconnects.

Question # 45 Unit 1 plant conditions:

Reactor Trip Breaker testing is in progress on Train A Train A Reactor Trip Breaker (RTA) is OPEN Train A Reactor Trip Bypass Breaker (BYA) is CLOSED Train B Reactor Trip Breaker (RTB) is CLOSED Reactor failed to trip from an automatic signal Which failure prevented an automatic Reactor Trip?

A. RTB Undervoltage Trip coil failed to energize.

B. BYA Undervoltage Trip coil failed to de-energize.

C. BYA Shunt Trip coil failed to energize.

D. RTB Shunt Trip coil failed to de-energize.

Answer: B Page 24 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires the applicant to demonstrate knowledge of Reactor Trip and Bypass Breakers and how failures associated with components of these breakers can cause an ATWT.

Explanation:

A. Incorrect. Plausible because RTB is equipped with an undervoltage trip coil, however, trip coils are normally energized and de-energize on a trip signal.

B. Correct. Given the conditions listed, the BYA Undervoltage Trip coil failed to de-energize.

C. Incorrect. Plausible because the Shunt Trip coil is designed to energize and trip open the breaker, however, BYA is not equipped with a Shunt Trip.

D. Incorrect. Plausible because RTB is equipped with a Shunt Trip coil, however, it energizes to trip.

Technical Reference(s) Reactor Protection and ESFAS Study Attached w/ Revision # See Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Solid State Protection System including interrelations with other systems to include interlocks and control loops.

(LO21SYSES2OB103)

Question Source: Bank # 2016 NRC Exam Q45 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2016 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.6 55.43 Page 25 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 038 EK1.03 Level of Difficulty: 3 Importance Rating 3.9 Steam Generator Tube Rupture: Knowledge of the operational implications of the following concepts as they apply to the SGTR: Natural circulation.

Question # 46 Unit 2 plant conditions:

A Steam Generator Tube Rupture has occurred EOP-3.0B, Steam Generator Tube Rupture is in progress All RCPs have been tripped The step to depressurize the Reactor Coolant System is being performed Which of the following is a possible result of performing this step?

A. A rapid drop in core differential temperature as Natural Circulation degrades.

B. A rapid drop in ruptured SG temperature due to loop stagnation during the pressure reduction.

C. A rapid rise in PRZR level due to voiding in the Reactor Head during Natural Circulation.

D. A rapid rise in Containment pressure due to overpressurization of the Pressurizer Relief Tank.

Answer: C Page 29 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of the implications that natural circulation has on a SGTR.

Explanation:

A. Incorrect. Plausible because any voiding that may occur during the depressurization would tend to hinder Natural Circulation, however, core differential temperature would not degrade rapidly.

B. Incorrect. Plausible because a rapid drop in ruptured SG temperature may occur, but this is a result of Safety Injection flow into the loop and not due to any depressurization.

C. Correct. The upper head region may void during RCS depressurization if the RCPs are not running. This will result in a rapidly increasing Pressurizer level.

D. Incorrect. Plausible because the PRT may rupture, however, this is not likely to occur. Even if the PRT were to rupture, Containment conditions would only change slightly and a rapid rise in pressure would not occur.

Technical Reference(s) EOP-3.0B Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from EOP-3.0, STATE the purpose/bases for the step(s). (LO21.ERG.E3A.OB103)

Question Source: Bank # 2010 NRC Exam Q45 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 30 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 040 AA1.04 Level of Difficulty: 3 Importance Rating 4.3 Steam Line Rupture - Excessive Heat Transfer: Ability to operate and / or monitor the following as they apply to the Steam Line Rupture: Isolation of all steam lines from header.

Question # 47 Unit 1 plant conditions:

LOCA has occurred EOS-1.2A, Post LOCA Cooldown and Depressurization in progress RCS Depressurization is in progress with PRZR pressure at 1900 psig A steam line break on SG 1-01 results in steam line pressure lowering Based on the above plant conditions, which of the following will cause a MSL Isolation?

A. SG 1-01 pressure decreases to a set point of 618 psig.

B. SG 1-01 pressure decreases to a set point of 605 psig.

C. SG 1-01 rate of pressure decrease exceeds a set point of 17 psi/sec.

D. SG 1-01 rate of pressure decrease exceeds a set point of 100 psi/sec.

Answer: D Page 36 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires the ability to monitor plant conditions and determine when MSIVs will isolate during a steam line break based on the status of the P-11 signal.

Explanation:

A. Incorrect. Plausible because 618 psig in the SG is the value at which the low steam line pressure SI signal and Main Steamline Isolation due to low pressure is reinstated at 605 psig when PRZR pressure increases above 1960 psig (P-11) during plant heatup.

B. Incorrect. Plausible as this would be a correct answer if PRZR pressure were above 1960 psig and P-11 was not blocked.

C. Incorrect. Plausible as this would be a correct answer if PRZR pressure were above 1960 psig and P-11 was not blocked.

D. Correct. Since PRZR pressure is 1900 psig and RCS Depressurization is in progress, P-11 must be blocked per EOS-1.2A. When P-11 is blocked the MSL Isolation on low SG pressure of 605 psig is no longer in effect. Also, when P-11 is blocked the MSL Isolation due to rate of decrease changes to 100 psi/sec and the 17 psi/sec will no longer cause isolation.

Technical Reference(s) EOS-1.2A Attached w/ Revision # See IPO-001A Comments / Reference Main Steam Study Guide IPO-007A Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Main Steam system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.MR1.OB03)

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 41.7 55.43 Page 37 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 054 AK1.02 Level of Difficulty: 4 Importance Rating 3.6 Loss of Main Feedwater: Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): Effects of feedwater introduction on dry S/G.

Question # 48 Unit 1 initial plant conditions:

A loss of all feedwater has occurred FRH-0.1A, Response to Loss of Secondary Heat Sink is in progress RCS Bleed and Feed is in progress The TDAFW Pump has been reset and is now available Current plant conditions:

AFW flow is to be established to SG 1-01 All SG WR indications are < 14%

RCS temp = 562°F rising Based on the above plant conditions, complete the following statements.

1. When establishing feedwater flow to a dry SG, the primary concern is ___(1)___ of the SG shell.

2. In accordance with FRH-0.1A, feedwater flow to SG 1-01 will be established ___(2)___.

A. (1) brittle fracture (2) at a rate not to exceed 100 gpm B. (1) brittle fracture (2) at the maximum available rate C. (1) thermal shock (2) at a rate not to exceed 100 gpm D. (1) thermal shock (2) at the maximum available rate Answer: D Page 44 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires knowledge of the effects of feedwater into a dry SG.

Explanation:

A. Incorrect. 1st part is incorrect because the susceptibility to the SG is thermal shock of the thick shell due to the thermal gradient that can be established. It is plausible because it is common to think that brittle fracture is a concern due to the impact of introducing cold water to a hot, dry SG.

2nd part is incorrect but plausible because with RCS temperature increasing, FRH-0.1A directs feedwater flow to SG 1-01 be established at the MAXIMUM available rate. It is plausible because if temperature were stable or lowering the initial feedwater flow to SG 1-01 would be limited to 100 gpm.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct with the parameters given, feedwater flow to SG 1-01 will be established at the MAXIMUM available rate (i.e. RCS temperature rising).

C. Incorrect. 1st part is correct. The susceptibility to the SG is thermal shock of the thick shell due to the thermal gradient that can be established. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) FRH-0.1A Attached w/ Revision # See WOG Eval Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1. (LO21.ERG.FH1.OB04)

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 41.10 55.43 Page 45 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 055 EK3.02 Level of Difficulty: 3 Importance Rating 4.3 Station Blackout: Knowledge of the reasons for the following responses as they apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power.

Question # 49 Which of the following describes the reasons for depressurizing the Steam Generators to 310 psig in accordance with ECA-0.0A, Loss of All AC Power?

A. Minimizes RCP seal leakage and initiates Safety Injection System Accumulator discharge.

B. Establishes Natural Circulation conditions and initiates Safety Injection System Accumulator discharge.

C. Establishes Natural Circulation conditions and minimizes secondary heat sink requirements if Auxiliary Feedwater inventory is limited.

D. Minimizes RCP seal leakage and minimizes secondary heat sink requirements if Auxiliary Feedwater inventory is limited.

Answer: A Page 49 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A by requiring knowledge of the reasons for EOP actions.

Explanation:

A. Correct. Lowering RCS pressure and restoring lost inventory is the reason for depressurizing.

B. Incorrect. Plausible because RCS depressurization will assist Natural Circulation, but is not the reason for depressurization to 310 psig.

C. Incorrect. Plausible because Natural Circulation will be established as a byproduct of rapid depressurization. Rapid cooldown and depressurization due to limited AFW is an action that could be taken in E-3 series procedures.

D. Incorrect. Plausible because in E-3 series procedures, rapid secondary depressurizations may be performed when there is limited makeup availability.

Technical Reference(s) ECA-0.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions from ECA-0.0, Loss of All AC Power.

Question Source: Bank # 2014 NRC Exam Q11 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 50 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 057 AA2.16 Level of Difficulty: 3 Importance Rating 3.0 Loss of Vital AC Inst. Bus: Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: Normal and abnormal Pzr level for various modes of plant operation.

Question # 50 Unit 2 plant conditions:

Reactor power = 80%

1/2-LS-459D PRZR LVL CTRL SELECT switch is selected to 459/460 2PC2 de-energizes Based on the above conditions, complete the following statements with regard to the effect of the loss of power?

1. ___(1)___ will close, isolating letdown.

2. Pressurizer program level will ___(2)___.

A. (1) Level Control Valve LCV-459 (2) increase B. (1) Level Control Valve LCV-459 (2) decrease C. (1) Level Control Valve LCV-460 (2) increase D. (1) Level Control Valve LCV-460 (2) decrease Answer: D Page 56 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the KA by requiring knowledge of how a loss of a vital instrumentation bus affects equipment associated with pressurizer level.

Explanation:

A. Incorrect. 1st part is incorrect because LCV-459 does not close due to a loss of power to 2PC2.

It is plausible because LCV-460 does close. 2nd part is incorrect because program level fails low.

It is plausible because actual level will rise due to the isolation of letdown and charging to seals.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. Level reference to the pressurizer level control scheme has also dropped due to the change to an Average Tave control signal. The failure of one Tave signal will lower the average Tave signal and therefore lower the Pressurizer level reference signal and thus program level will lower.

C. Incorrect. 1st part is correct. LCV-460 does close as it is a Train B powered valve. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct. 2nd part is correct.

Technical Reference(s) 208, 120 & 118 VAC Distribution Study Attached w/ Revision # See Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: RELATE operating experience with the 208/120 VAC, 118 VAC Distribution, Inverters and Lighting system operation. (LO21.SYS.AC3.OB09)

Question Source: Bank # 2014/15 NRC RO Retake Exam Q50 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014/15 NRC RO Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.5 55.43 Page 57 of 62 CPNPP NRC 2017 RO Written Exam Worksheet 41-50 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 062 AK3.04 Level of Difficulty: 3 Importance Rating 3.5 Loss of Nuclear Svc Water: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: Effect on the nuclear service water discharge flow header on a loss of CCW.

Question # 51 Unit 1 plant conditions:

Reactor power = 100%

SSW Pump 1-01 is operating CCW Pump 1-01 is operating Train B CCW heat exchanger was removed from service due to a tube leak In order to return the Train B CCW heat exchanger to service, complete the following statements.

1. The ___(1)___ side of the Train B CCW heat exchanger should be filled, vented and pressurized prior to starting the Train B SSW pump.

2. The above recovery action prevents ___(2)___.

A. (1) shell (2) release of hydrazine to the safe shutdown impoundment B. (1) shell (2) chloride infusion if a tube leak exists C. (1) tube (2) release of hydrazine to the safe shutdown impoundment D. (1) tube (2) chloride infusion if a tube leak exists Answer: B Page 1 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the effect on SSW system when recovering from a loss of the CCW heat exchanger.

Explanation:

A. Incorrect. 1st part is correct. The shell side of the CCW heat exchanger is the side in which CCW flows. 2nd part is incorrect because CCW is at a higher pressure than SSW which could lead to a release of hydrazine to the SSI.

B. Correct. 1st part is correct (See A). 2nd part is correct. Filling, venting and pressurizing the CCW side of the heat exchanger prior to starting the Train B SSWP will prevent chloride infusion into the CCW side of the CCW heat exchanger due to CCW pressure being greater than SSW pressure.

C. Incorrect. 1st part is incorrect because the tube side of the CCW heat exchanger is the side SSW flows through. 2nd part is incorrect but plausible (See A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (See B).

Technical Reference(s) Station Service Water Study Guide Attached w/ Revision # See SOP-502A Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Station Service Water system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.SW1.OB03)

Question Source: Bank # 2016 NRC Exam Q52 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2016 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.4 55.43 Page 2 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 065 G2.4.21 Level of Difficulty: 3 Importance Rating 4.0 Loss of Instrument Air: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Question # 52 Unit 1 plant conditions:

Time = 0800:

Reactor was manually tripped due to lowering Instrument Air pressure The TDAFW Pump is out of service Time = 0810:

The crew is transitioning from EOP-0.0A, Reactor Trip or Safety Injection The Critical safety functions are being reviewed Based on the above plant conditions, complete the following statement.

Due to the failure of _________ may be applicable without prompt operator action.

A. 1-FCV-0121, CCP Charging Flow Control Valve, FRI-0.1A, Response to High Pressurizer Level B. 1-FCV-0121, CCP Charging Flow Control Valve, FRI-0.2A, Response to Low Pressurizer Level C. PV-2453 A&B / PV-2454 A&B, MD AFW Flow Control Valves, FRH-0.1A, Response to Loss of Secondary Heat Sink D. PV-2453 A&B / PV-2454 A&B, MD AFW Flow Control Valves, FRH-0.3A, Response to Steam Generator High Level Answer: A Page 7 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how components using instrument air fail and how that impacts the evaluation of critical safety function status trees.

Explanation:

A. Correct. FCV-0121 fails open. This, coupled with letdown valves failing closed, would result in high pressurizer level if not promptly corrected B. Incorrect. FCV-0121 fails open. It is plausible because if it were to fail closed, the potential would exist to have Przr level < 17%.

C. Incorrect. 1) The AFW flow control valves have accumulators that can operate the valves for 30 minutes after the loss of IA and 2) The valves fail open upon a loss of IA. It is plausible because if the valves failed closed, you would have no AFW flow to the SGs.

D. Incorrect. The AFW flow control valves have accumulators that can operate the valves for 30 minutes after the loss of IA. It is plausible because if/when the accumulators were depleted, it could be correct.

Technical Reference(s) IA Study Guide Attached w/ Revision # See ABN-301 Comments / Reference FRI-0.1A FRH-0.1A Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Instrument Air Compressor Trip or Header Pressure Low in accordance with ABN-301 Instrument Air System Malfunction.

(LO21.ABN.301.OB03)

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 41.7 55.43 Page 8 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A W/E04 EK2.2 Level of Difficulty: 3 Importance Rating 3.8 LOCA Outside Containment: Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

Facilitys 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.

Question # 53 Unit 1 plant conditions:

Unit 1 is responding to a Loss of Coolant Accident (LOCA) per ECA-1.2A, LOCA Outside Containment.

The crew believes that the leak outside of Containment has been isolated but Reactor Coolant System pressure is not rising.

Which of the following alternate indications may be used to determine if the break has been isolated per ECA-1.2A, LOCA Outside Containment?

A. Refueling Water Storage Tank level stable.

B. Reactor Vessel Level Indicating System indication rising.

C. Emergency Core Cooling System flows rising.

D. Emergency Core Cooling System alignment verification.

Answer: B Page 19 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the interrelations between the LOCA outside containment and heat removal system valves that are cycled in an attempt to locate the leak.

Explanation:

A. Incorrect. Plausible because RWST inventory could be lost to the Safeguards Building from an interfacing system break outside Containment and RWST level stable could indicate that break flow has ceased, however, RWST level may still be lowering with the break isolated as ECCS flow refills the RCS. Therefore, RWST level change is not a good indicator of break isolation.

B. Correct. As stated in Attachment 2, Step 3 Bases, RCS pressure may not initially rise once the break is isolated, due to plant cooldown or when the RCS is saturated. RVLIS indication rising shows that ECCS flow is not leaving the RCS via the break, but rather it is refilling the RCS. This indicates that the break is isolated from the RCS.

C. Incorrect. Plausible because ECCS flows could indicate that the break is isolated if it were lowering. Rising ECCS flow is indicative of the RCS break becoming worse.

D. Incorrect. Plausible because an ECCS valve alignment is performed in Step 1 of ECA-1.2A, and this may isolate the break, however, verifying ECCS alignment alone does not ensure that the break is isolated. RCS parameters, such as pressure and RVLIS trend must be evaluated to verify break isolation.

Technical Reference(s) ECA-1.2A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions from ECA-1.2, LOCA Outside Containment.

Question Source: Bank # 2013 NRC Exam Q54 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 20 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Level RO SRO Examination Outline Cross-reference:

Rev. Date: Rev. 2 Tier 1 Group 1 K/A W/E11 G2.4.8 Level of Difficulty: 2 Importance Rating 3.8 Loss of Emergency Coolant Recirc: Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Question # 54 Unit 1 plant conditions:

ECA-1.1A, Loss of Emergency Coolant Recirculation is in progress CST level is lowering Based on the above plant conditions, complete the following statement.

1. The INITIAL level at which ECA-1.1A directs makeup to the CST is ___(1)___.

2. ECA-1.1A directs makeup to the CST by performing ___(2)___ in parallel with ECA-1.1A.

A. (1) 10%

(2) ABN-305, Auxiliary Feedwater System Malfunction B. (1) 10%

(2) SOP-304A, Auxiliary Feedwater System C. (1) 6%

(2) ABN-305, Auxiliary Feedwater System Malfunction D. (1) 6%

(2) SOP-304A, Auxiliary Feedwater System Answer: A Page 25 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of how abnormal procedures are used in conjunction with the EOPs during a loss of reactor coolant recirculation.

Explanation:

A. Correct. 1st part is correct. ECA-1.1A verifies that CST level is > 10%. The RNO will apply which directs you to makeup to the CST. 2nd part is correct. ECA-1.1A directs you to makeup to the CST using ABN-305 AFW System Malfunction.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because you are directed to makeup using ABN-305. It is plausible because if you were not in ECA-1.1A, it could be correct.

C. Incorrect. 1st part is incorrect because the initial level at which you are directed to makeup to the CST is 10%. It is plausible because 6% is a value used for the RWST level at which you swap to containment recirculation. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) ECA-1.1A Attached w/ Revision # See SOP-304A Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from ECA-1.1, STATE the purpose/basis for the step(s). (LO21.ERG.C11.OB04)

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 41.10 55.43 Page 26 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A W/E05 EA1.2 Level of Difficulty: 2 Importance Rating 3.7 Inadequate Heat Transfer - Loss of Secondary Heat Sink: Ability to operate and / or monitor the following as they apply to the (Loss of Secondary Heat Sink). Operating behavior characteristics of the facility.

Question # 55 Unit 1 plant conditions:

Time = 0800:

FRH-0.1A, Response to Loss of Secondary Heat Sink is in progress FRH-0.1A directs you to establish Feed Flow from the Condensate System Time = 0810:

SG pressure is being reduced on the selected SG(s) to allow condensate flow SG pressure on the selected SG(s) = 575 psig Based on the above plant conditions, complete the following statements.

In accordance with FRH-0.1A,

1. the MINIMUM number of SGs that must be depressurized to allow condensate flow is

___(1)___.

2. SG pressure(s) at Time = 0810 ___(2)___ low enough to allow adequate condensate flow to the SG(s).

A. (1) one (2) is(are)

B. (1) one (2) is(are) NOT C. (1) two (2) is(are)

D. (1) two (2) is(are) NOT Answer: B Page 29 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the operational characteristics of the facility (shutoff head of the condensate pumps) during a loss of secondary heat sink event.

Explanation:

A. Incorrect. 1st part is correct. When using condensate pumps to supply FDW to the SG, at least one SG must be depressurized to ~ 500 psig IAW FRH-0.1A. 2nd part is incorrect because FRH-0.1A directs you to reduce SG pressure to < 500 psig. It is plausible because the green band on condensate pump discharge pressure, 1-PI-2240, CNDS PMP DISCH HDR PRESS goes to 575 psig.

B. Correct. 1st part is correct (see A). 2nd part is correct. SG must be depressurized to ~ 500 psig IAW FRH-0.1A.

C. Incorrect. 1st part is incorrect because when using the condensate pumps to supply feed, at least ONE SG must be depressurized so one SG would be the minimum. It is plausible because if using a Low Pressure Feedwater Source, at least two SGs must be depressurized. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) FRH-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1. (LO21.ERG.FH1.OB04 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 41.7 55.43 Page 30 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 077 AA1.03 Level of Difficulty: 2 Importance Rating 3.8 Generator Voltage and Electric Grid Disturbances: Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage regulator controls.

Question # 56 Unit 1 plant conditions:

ABN-402, Main Generator Malfunction has been entered due to erratic MVARs Main Generator voltage regulator is placed in MANUAL Main Generator output:

550 MWe Power Factor = 0.6 Leading Based on the above plant conditions, complete the following statements.

1. In order to return Main Generator output to within the capability curve, excitation must be

___(1)___.

2. If Main Generator output cannot be returned to within the limits of the capability curve, ABN-402 directs you to trip the ___(2)___.

REFERENCE PROVIDED A. (1) raised (2) turbine B. (1) raised (2) reactor C. (1) lowered (2) turbine D. (1) lowered (2) reactor Answer: A Page 35 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to monitor/operate the Main Generator voltage regulator controls during Generator/Grid Voltage disturbances.

Explanation:

A. Correct. 1st part is correct. With a leading power factor at 550 MWe, excitation is low so it must be raised to return to within limits. 2nd part is correct because at 550 MWe, reactor power is

< 50% power so ABN-402 directs tripping the turbine.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because at 550 MWe, reactor power is < 50% so a turbine trip is directed. It is plausible because if power were > 50%

(600 MWe), it would be correct.

C. Incorrect. 1st part is incorrect because with a leading power factor at 550 MWe, excitation is low so it must be raised to return to within limits. It is plausible because if it were a lagging power factor, it could be correct. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) ABN-402 Attached w/ Revision # See TDM-401A Comments / Reference IPO-003A Proposed references to be provided during examination: TDM-401A, Reactive Capability Curve Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Main Generator. (LO21SYSMG1OB126)

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 41.10 55.43 Page 36 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 024 AK1.02 Level of Difficulty: 2 Importance Rating 3.6 Emergency Boration: Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: Relationship between boron addition and reactor power.

Question # 57 Unit 1 plant conditions:

Reactor power = 6%

Rod Control is in MANUAL 1/1-FLRM, CONTROL ROD MOTION CTRL, is CAUTION tagged for repair of a broken wire Xenon concentration is stable Fifteen minutes later the following indications are observed:

Volume Control Tank (VCT) level is 70% and rising Annunciator 1-ALB-6A, Window 2.6 - VCT LVL HI, is in alarm TAVE - TREF is plus (+) 4°F Reactor power 6.2% rising Based on above plant conditions, which of the following is required per ABN-105, Chemical and Volume Control System Malfunctions?

A. Commence an Emergency Boration because an inadvertent dilution is occurring.

B. Remove CAUTION tag and manually insert Control Rods to restore TAVE - TREF.

C. Place Rod Control in AUTO to allow automatic Control Rod insertion.

D. Place 1/1-TCV-129, LTDN DIVERT VLV, in VCT position to remove the demineralizers from Letdown.

Answer: A Page 43 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the relationship between boron concentration and reactor power.

Explanation:

A. Correct. A dilution anomaly is in progress and this is the action per ABN-105.

B. Incorrect. Plausible because ABN-105 would direct manual rod insertion first, however, with a CAUTION tag in place the control switch will not be operated. For personnel and equipment safety the power to the switch would be DANGER tagged at the source.

C. Incorrect. Plausible because the temperature difference would result in automatic rod insertion, however, the Control Rods are not to be placed in AUTO below 15% power.

D. Incorrect. Plausible as this is a proper action per ABN-105 if a new demineralizer has been placed in service, but VCT level indicates the dilution is from water intrusion into the CVCS and this action would have no benefit.

Technical Reference(s) ABN-105 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Dilution Anomaly in accordance with ABN-105, Chemical and Volume Control System Malfunctions.

Question Source: Bank # 2012 NRC Exam Q65 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 44 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 032 G2.2.36 Level of Difficulty: 2 Importance Rating 3.1 Loss of Source Range NI: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Question # 58 Given the following conditions:

Unit 2 is in MODE 6 N-31 and N-32 are the OPERABLE Source Range Nuclear Instruments STA-617, High Voltage Switching and Clearance, is about to be performed in the Switchyard Which of the following must be performed prior to implementing STA-617, High Voltage Switching and Clearance?

A. Place the High Flux at Shutdown Switch in BLOCK on both N-31 and N-32 to prevent loss of the Source Range Nuclear Instrumentation.

B. Place the High Flux at Shutdown Switch in BLOCK on both N-31 and N-32 to prevent an automatic shift of CCP suction to the RWST.

C. Suspend CORE ALTERATIONS and positive reactivity additions due to the potential for spiking of the Source Range Nuclear Instrumentation.

D. Suspend CORE ALTERATIONS and positive reactivity additions due to the potential for loss of power to Refueling equipment.

Answer: C Page 50 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine the maintenance effects (power switching) on the status of the SR NIs. Spiking is the concern when switching power. This constitutes a momentary loss of operability (loss of SR) due to spiking but the NIs and suspending CORE ALTERATIONS is an action of LCO 3.9.3, Nuclear Instrumentation.

Explanation:

A. Incorrect. Plausible because spiking of the Source Range Nuclear Instrumentation will occur, however, placing the High Flux at Shutdown Switch in BLOCK will not prevent a loss of the SR NIs.

B. Incorrect. Plausible because this is a common misconception as the plant used to have a flux doubling circuit that would automatically shift CCP suction to the RWST.

C. Correct. Per the Precaution outlined in SOP-703.

D. Incorrect. . Plausible because CORE ALTERATIONS would be suspended, however, not due to the potential loss of power to Refueling Equipment.

Technical Reference(s) SOP-703 Attached w/ Revision # See TS-3.9.3 Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Excore Instrumentation system. (LO21.SYS.EC1.OB05).

Question Source: Bank # 2013 NRC Exam Q67 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.6 55.43 Page 51 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 037 AA1.07 Level of Difficulty: 3 Importance Rating 3.1 Steam Generator Tube Leak: Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: CVCS letdown flow indicator.

Question # 59 Unit 2 plant conditions:

Reactor power = 100%

The crew is in ABN-106, High Secondary Activity, due to a steam generator tube leak Main Steam Line radiation monitor 2-RE-2327 (MSL-280) MAIN STEAM LINE 2-03 is in RED (HIGH) alarm and rising Main Steam Line N-16 monitor 2-RE-2327A (N16-276) MAIN STEAM LINE 2-03 LEAK RATE is in RED (HIGH) alarm reading 150 gpd and stable 2-FI-121A, CHRG FLO is indicating 175 gpm and stable 2-FCV-121A, CCP CHRG FLO CTRL is at 100% demand Total RCP Seal Leakoff Flow 15 gpm and stable CCP 2-01 and CCP 2-02 are both running PRZR LVL has lowered from 50% to 45% in the last four minutes and continues to lower The RO performed a Leak Rate using the Job Aid and determined the leak rate to be approximately 203 gpm Based on the above plant conditions, complete the following statements.

1. 1-FI-132, LTDN FLO indicator is reading approximately ___(1)___ gpm.

2. In accordance with ABN-106, the required action is to ___(2)___.

A. (1) 45 (2) Reduce power in accordance with IPO-003A, Power Operations to < 50% in one hour and be in MODE 3 in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. (1) 45 (2) trip the reactor and actuate Safety Injection C. (1) 75 (2) Reduce power in accordance with IPO-003A, Power Operations to < 50% in one hour and be in MODE 3 in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. (1) 75 (2) trip the reactor and actuate Safety Injection Answer: B Page 57 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires the operator to monitor the CVCS letdown flow indicator during a steam generator tube leak and calculate letdown flow rate using the leak rate calculation.

Explanation:

A. Incorrect. 1st part is correct. This is the correct leak rate calculation using 1) the difference in charging, letdown and seal return and 2) the change in Przr level:

1) the difference in charging, letdown and seal return: [175 gpm - (45 gpm + 15 gpm) = 115 gpm].

2) Change in Przr level: [50%-45% over 4 minutes = 70 gal/% x 5% divided by 4 minutes ~ 88 gpm].

Total Leak rate: [115 + 88 = 203 gpm total leakage].

2nd part is incorrect because with PRZR lowering in an uncontrolled manner, ABN-106 directs tripping the reactor. It is plausible because if Przr level stable (which would require a smaller leak rate), it would be correct.

B. Correct. 1st part is correct (see A). 2nd part is correct. IAW ABN-106, you are directed to trip the reactor and initiate safety injection if Przr level is lowering uncontrollably.

C. Incorrect. 1st part is incorrect because the correct value is 45 gpm. It is plausible because if you add the seal return flow term to Charging flow when determining the leak rate and use the 75 gpm orifice value the total is 115 gpm (same as the 45 gpm orifice value). This is the incorrect leak rate calculation using 1) charging, subtracting letdown (75 gpm) and adding seal return and 2) the change in Przr level

1) charging, subtracting letdown (75 gpm) and adding seal return: [175 gpm - (75 gpm - 15 gpm) =

115 gpm].

2) Change in Przr level: [50%-45% over 4 minutes = 70 gal/% x 5% divided by 4 minutes ~ 88 gpm].

Total Leak rate: [115 + 88 = 203 gpm total leakage].

2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) ABN-106 Attached w/ Revision # See ABN-103 Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Steam Generator Tube Leakage greater than or equal to 75 gpd in accordance with ABN-106, High Secondary Activity.

Question Source: Bank #

Modified Bank # 2015 NRC Exam Q61 (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X Page 58 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 59 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 051 AA2.02 Level of Difficulty: 3 Importance Rating 3.9 Loss of Condenser Vacuum: Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.

Question # 60 Unit 1 plant conditions:

Main Condenser vacuum has been degrading ABN-304, Main Condenser and Circulating Water System Malfunction is in progress Condenser vacuum indicates 23.5 inches Hg and is degrading by 0.25 inches Hg per minute The crew is reducing load at approximately 2% per minute Power is currently at 40%

Assuming the current trends continue, which of the following describes the action that must be taken, and the LATEST time the action must be taken, in accordance with ABN-304, Main Condenser and Circulating Water System Malfunction?

Trip the...

A. Reactor within 10 minutes.

B. Turbine within 10 minutes.

C. Reactor within 15 minutes.

D. Turbine within 15 minutes.

Answer: A Page 67 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires the ability to determine reactor/turbine trip criteria based on condenser vacuum.

This question does not overlap with Q56 in that the criteria used to determine whether to trip the turbine or reactor is based on if you are above/below 10%, not 50%.

Explanation:

A. Correct. In 10 minutes vacuum would not be greater than 21 inches Hg, and power is

> 10%, therefore, trip the Reactor.

B. Incorrect. Plausible because tripping the Turbine is the correct action if power level is less than 10%, however, in 10 minutes power would still exceed 10%.

C. Incorrect. Plausible because power would be at 10% in 15 minutes but vacuum will be 21 in 10 minutes, requiring a Reactor Trip in 10 minutes.

D. Incorrect. Plausible because power would be at 10% in 15 minutes but vacuum will be 21 in 10 minutes, requiring a Reactor Trip in 10 minutes.

Technical Reference(s) ABN-304 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EVALUATE all system limitations and precautions associated with responding to a Main Condenser, Circ Water, and TPCW malfunction. (LO21.ABN.304.OB12)

Question Source: Bank # 2011 NRC Exam Q57 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 68 of 71 CPNPP NRC 2017 RO Written Exam Worksheet 51-60 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A W/E06 EA2.1 Level of Difficulty: 3 Importance Rating 3.4 Degraded Core Cooling: Ability to determine and interpret the following as they apply to the (Degraded Core Cooling):

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Question # 61 Unit 1 plant conditions:

Small break LOCA has occurred inside containment Core exit thermocouples = 760°F increasing NO RVLIS lights are lit Based on the above plant conditions, complete the following statements.

1. Current conditions ___(1)___ indicate that at least a portion of the fuel is uncovered.

2. Review of Critical Safety Function status trees will determine that ___(2)___ is required to be entered.

A. (1) do (2) FRC-0.1A, Response to Inadequate Core Cooling B. (1) do (2) FRC-0.2A, Response to Degraded Core Cooling C. (1) do NOT (2) FRC-0.1A, Response to Inadequate Core Cooling D. (1) do NOT (2) FRC-0.2A, Response to Degraded Core Cooling Answer: B Page 1 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires the ability to access plant condition and select the appropriate procedure.

Explanation:

A. Incorrect. 1st part is correct. With CETs > 750 degrees and no RVLIS indication, core uncovery will have occurred at some point of the active fuel. 2nd part is incorrect because entry into FRC-0.2A (Degraded Core Cooling) is required. It is plausible because if CETs were > 1200 degrees, it would be correct.

B. Correct. 1st part is correct. 2nd part correct.

C. Incorrect. 1st part is incorrect because with CETs > 750 degrees and no RVLIS indication, core uncovery will have occurred at some point of the active fuel. It is plausible because if < 750 degrees, it may be correct. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct.

Technical Reference(s) Core Cooling Study Guide Attached w/ Revision # See FRC-0.1A Status Tree Comments / Reference Proposed references to be provided during examination:

Learning Objective: DEFINE the following situations: 1) Adequate core cooling. 2) Degraded core cooling. 3) Inadequate core cooling. (LO21.MCO.MI2.OB01)

Question Source: Bank # 2014/15 NRC RO Retake Exam Q33 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014/15 NRC RO Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.5 55.43 Page 2 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A W/E13 EA1.3 Level of Difficulty: 2 Importance Rating 3.1 Steam Generator Over-pressure: Ability to operate and / or monitor the following as they apply to the (Steam Generator Overpressure): Desired operating results during abnormal and emergency situations.

Question # 62 Unit 1 plant conditions:

SG 1-01 overpressure condition exists SG 1-01 pressure is 1220 psig stable Based on the conditions above complete the following statements.

1. A MAXIMUM of ___(1)___ MSSVs are open. (Disregard any Accumulation)

2. The operator may determine the number of MSSVs open by monitoring the ___(2)___.

A. (1) 4 (2) Main Control Board AND Plant Computer B. (1) 4 (2) Plant Computer ONLY C. (1) 5 (2) Main Control Board AND Plant Computer D. (1) 5 (2) Plant Computer ONLY Answer: B Page 7 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires tests the ability to observe the desired operating results of a SG overpressure condition and monitor the results.

Explanation:

A. Incorrect. 1st part is correct at 1220 psig 4 MSSVs would be open. 2nd part is incorrect but plausible because the ARVs are monitored on the Main Control Board.

B. Correct. 1st part is correct (see A). 2nd part is correct the MSSV positions are monitored on the Plant Computer on either the EP screen or the MS screen.

C. Incorrect. 1st part is incorrect but plausible because if SG pressure were 15 psig higher then 5 MSSVs would be open. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) Main Steam Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Main Steam System and PREDICT the system response. (LO21.SYS.MR1.OB04)

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 41.7 55.43 Page 8 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A W/E15 EK3.3 Level of Difficulty: 2 Importance Rating 2.9 Containment Flooding: Knowledge of the reasons for the following responses as they apply to the (Containment Flooding):

Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

Question # 63 Unit 1 plant conditions:

A LOCA has occurred Containment pressure is 8 psig and rising While responding in EOP-1.0A, Loss of Reactor or Secondary Coolant, the Control Room observed Containment Sump level greater than 816' and entered FRZ-0.2A, Response to Containment Flooding The Control Room is attempting to identify water volumes other than the Refueling Water Storage Tank or Safety Injection Accumulators that may be the source of the additional water in Containment Based on the above plant conditions, complete the following statements.

1. FRZ-0.2A directs Chemistry to sample the containment sump water for activity in order to

___(1)___.

2. The ___(2)___ water system could still be contributing to the Containment Flooding and should be isolated in accordance with FRZ-0.2A.

A. (1) determine the possibility and extent of fuel damage (2) Component Cooling B. (1) determine the possibility and extent of fuel damage (2) Ventilation Chilled Water C. (1) determine possible storage locations for the water outside containment (2) Component Cooling D. (1) determine possible storage locations for the water outside containment (2) Ventilation Chilled Water Answer: C Page 10 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires knowledge of the reasons for actions taken during containment flooding (chemistry sampling the sump) in order to determine actions/manipulation of controls (where to put the water).

Explanation:

A. Incorrect. 1st part is incorrect because determining the activity of the water helps determine where the water can be pumped to. It is plausible because the level of activity in the sump water could be due to possible fuel damage, however, this is not the reason the ECCS sump water is sampled per FRZ-0.2A. 2nd part is correct. Containment pressure has not reached 18 psig yet so Component Cooling water is not completely isolated to containment and could be the source.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect because Ventilation Chilled water isolates on Phase A Containment Isolation. It is plausible because it does come into containment and if the Phase A had not actuated, it could be correct.

C. Correct. 1st part is correct. Determining the activity of the water helps determine where the water can be pumped, thereby, attempting to prevent the flooding from damaging critical pieces of equipment in containment. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect (see B).

Technical Reference(s) FRZ-0.2A Attached w/ Revision # See RPS & ESFAS Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, NOTE or CAUTION, DISCUSS the reason or basis for the step, NOTE or CAUTION. in FRZ-0.2 A/B. (LO21.ERG.FZ2.OB04)

Question Source: Bank #

Modified Bank # 2013 NRC Exam Q65 (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 11 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A W/E03 EK2.1 Level of Difficulty: 2 Importance Rating 3.6 LOCA Cooldown - Depress: Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Question # 64 Unit 1 plant conditions:

EOS-1.2A, Post LOCA Cooldown and Depressurization in progress due to a SBLOCA All RCPs have been stopped RHR Pumps are in STANDBY SIPs are in STANDBY Normal charging flow has been established Containment pressure is 6 psig and stable The following indications are observed:

RCS Hot Leg temperatures are all 460°F and rising RCS pressure is 835 psig and lowering Subcooling is 65°F and degrading Pressurizer level is 38% and slowly lowering Which of the following actions should be taken in response to the given conditions per EOS-1.2A, Post LOCA Cooldown and Depressurization?

A. Immediately manually start and align Emergency Core Cooling System pumps.

B. Immediately re-actuate Safety Injection to align Emergency Core Cooling System.

C. When subcooling or pressurizer level meets foldout page criteria then manually start and align Emergency Core Cooling System pumps.

D. When subcooling or pressurizer level meets foldout page criteria then re-actuate Safety Injection to align Emergency Core Cooling System.

Answer: C Page 19 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires knowledge of the interrelations between the LOCA cooldown process and equipment used during the event.

Explanation:

A. Incorrect. Plausible because manually starting and aligning ECCS pumps is required per EOS-1.2 foldout page, however, subcooling is NOT less than 55°F or PRZR level is NOT less than 34% for adverse containment.

B. Incorrect. Plausible because it may be thought that re-actuating SI is the proper action because EOS-1.2A, foldout page title for step is SI REINITIATION CRITERIA, however, subcooling is NOT less than 55°F or PRZR level is NOT less than 34% for adverse containment.

C. Correct. Manually starting and aligning ECCS pumps is correct action when subcooling is less than 55°F or PRZR level is less than 34%.

D. Incorrect. Plausible because it may be thought that re-actuating SI is the proper action because EOS-1.2A, foldout page title for step is SI REINITIATION CRITERIA when subcooling is less than 55°F or PRZR level is less than 34%.

Technical Reference(s) EOS-1.2A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a set of plant conditions, IDENTIFY the proper transitions through/out of EOS-1.2. (LO21.ERG.E12.OB06)

Question Source: Bank # 2013 NRC Exam Q5 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.7 55.43 Page 20 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A W/E09&E10 G2.4.2 Level of Difficulty: 2 Importance Rating 4.5 Natural Circ - Depress: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Question # 65 Unit 1 plant conditions:

Time = 0800:

Reactor shut down in progress after a long run at full power Reactor power = 8%

Non-Safeguards 6.9 KV busses de-energize Based on the above plant conditions, complete the following statements.

1. The RCP Undervoltage condition will ___(1)___.

2. When natural circulation is established, the temperature difference between RCS THOT and TCOLD will be ___(2)___ than it was when the RCPs were operating.

A. (1) require a manual reactor trip (2) smaller B. (1) require a manual reactor trip (2) larger C. (1) result in an automatic reactor trip (2) smaller D. (1) result in an automatic reactor trip (2) larger Answer: B Page 25 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of the system setpoints/interlocks that will result in EOP entry criteria (loss of RCPs) which also result in a natural circulation condition.

Explanation:

A. Incorrect. 1st part is correct. Below P-7 (10%), the RPS (RCP) undervoltage trip is automatically bypassed, however, all RCPs will have lost power and the crew will have to trip the reactor and enter the ERG network per ABN-101. 2nd part is incorrect because shutting down from a long run at power (since your refueling); decay heat will be significant which will create a large T for driving head (~30-40oF). With RCPs operating, at 8% power, the T will be minimal (~ 2oF). It is plausible because one could think that the RCP heat will create a significant temperature difference. The T however, is measured across the SG.

B. Correct. 1st part is correct (see A). 2nd part is correct. With the significant decay heat load, the T will be much larger than the T when RCPs are operating.

C. Incorrect. 1st part is incorrect. Below P-7 (10%), the RPS (RCP) undervoltage trip is automatically bypassed, however, all RCPs will have lost power and the crew will have to trip the reactor and enter the ERG network per ABN-101. It is plausible because if power were > 10%, it could be correct. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) RPS & ESFAS Study Guide Attached w/ Revision # See Rod Control Study Guide Comments / Reference ABN-101 Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Reactor Protection and Engineered Safeguard Actuation Systems including interrelations with other systems to include interlocks and control loops. (LO21.SYS.ES1.OB03 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 41.7 55.43 Page 26 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.1.3 Level of Difficulty: 3 Importance Rating 3.7 Knowledge of shift or short-term relief turnover practices.

Question # 66 Unit 2 plant conditions:

Time = 1315:

The Unit 2 Reactor Operator must leave the Control Room for a short period of time to get an annual audiometric test.

In order for the short term relief to be in compliance with OWI-107, Operations Department Turnover and Briefing Instructions, the Reactor Operator should return to the AT THE CONTROLS AREA no later than ___(1)___ and at a MINIMUM permission should be granted by the ___(2)___.

A. (1) 1345 (2) Unit 2 Unit Supervisor B. (1) 1345 (2) Shift Manager C. (1) 1415 (2) Unit 2 Unit Supervisor D. (1) 1415 (2) Shift Manger Answer: C Page 29 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires knowledge shift turnover practices.

Explanation:

A. Incorrect. Plausible because it could be thought 30 minutes is the short term relief time limit; however OWI-107 defines short term relief as < 60 minutes. In accordance with OWI-107, the respective Unit Supervisor is the permission authority for operators on the unit.

B. Incorrect. Plausible because it could be thought 30 minutes is the short term relief time limit; however OWI-107 defines short term relief as < 60 minutes. In accordance with OWI-107, the Shift Manager is the permission authority for the Unit Supervisors.

C. Correct. Short term relief is no longer than 60 minutes in accordance with OWI-107. In accordance with OWI-107, the respective Unit Supervisor is the permission authority for operators on the unit.

D. Incorrect. Short term relief is no longer than 60 minutes in accordance with OWI-107. In accordance with OWI-107, the Shift Manager is the permission authority for the Unit Supervisors.

Technical Reference(s) OWI-107 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: CONDUCT shift relief and turnover in accordance with station procedures; VERIFYING that an adequate number of qualified personnel are available for turnover and ENSURING that all personnel are properly relieved.

Question Source: Bank # 2014 NRC Exam Q67 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 30 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.1.21 Level of Difficulty: 2 Importance Rating 3.5*

Ability to verify the controlled procedure copy.

Question # 67 Complete the following statements regarding procedure verification activities in accordance with ODA-407, Operations Department Procedure Use and Adherence.

1. A Working Copy procedure printed from the Approved Directory ___(1)___ the requirement for an alternative method of status verification of that procedure.

2. IF a revision is made to a procedure currently in progress, the Working Copy of the procedure ___(2)___ required to be updated once the revision is effective.

A. (1) does NOT meet (2) is B. (1) does NOT meet (2) is NOT C. (1) meets (2) is D. (1) meets (2) is NOT Answer: C Page 34 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of verifying working copies of procedures against approved methods of ODA-407.

Explanation:

A. Incorrect. 1st part is incorrect but plausible as one would think the primary method would be to verify against the controlled copy of the procedure in the control room or other designated location and the alternative method would be check it against the SPARCS database. However, ODA-407 and STA-306 work together to state that the Approved drive is an electronic location against which working copies of procedures can be verified as an alternative to the above listed methods. 2nd part is correct per ODA-407 working copies of procedures used in the field to perform plant operations are to be updated, if still in progress, with revisions or PCNs as applicable.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect but plausible as it is reasonable to think that a working copy of a procedure in progress would not be updated as these procedures are pre-marked to N/A steps that are not applicable and subsequently get approved by the Unit Supervisor. In order to update this procedure the entire process would need to be re-performed and re-approved by the Unit Supervisor and this would be a time intensive process.

C. Correct. 1st part is correct per ODA-407 an ELECTRONIC CONTROLLED COPY maintained by Operations Department or DCC, and available on an approved drive (controlled by the Operations, Maintenance, or DCC) includes all changes and revisions. When printed from this source, this meets the STA-306 requirement for an alternative method of status verification for a WORKING COPY for the initial use of the procedure. Per ODA-306 electronic document files of procedures shall be maintained on the approved directory. 2nd part is correct (see A).

C. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) ODA-407 Attached w/ Revision # See STA-306 Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE requirements for Conduct of Operations in accordance with ODA-102, ODA-407 and Operations Guideline 3. (LO21.ADM.XA3.OB01)

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 41.10 Page 35 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 55.43 Page 36 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.1.42 Level of Difficulty: 2 Importance Rating 2.5 Knowledge of new and spent fuel movement procedures.

Question # 68 In accordance with RFO-102, Refueling Operation, complete the following statements.

When CORE ALTERATIONS are in progress

1. the equipment Hatch____(1)____.

2. both doors in the ____(2)____air lock can be open as long as one door is capable of being closed.

A. (1) must be closed (2) emergency B. (1) must be closed (2) personnel C. (1) can be open (2) emergency D. (1) can be open (2) personnel Answer: D Page 41 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge fuel movement procedures.

Explanation:

A. Incorrect. 1st part is incorrect because IAW RFO-102, the equipment hatch must be closed and held in place by four bolts or capable of being closed and held in place by four bolts. 2nd part is incorrect because per RFO-102, at least one door in the emergency airlock must be closed. It is plausible because if were the personnel airlock, it would be correct.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. The personnel airlock must have one door that is capable of being closed.

C. Incorrect. 1st part is correct. The equipment hatch is not required to be closed as long as it is capable of being closed. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) RFO-403 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal operations of the Fuel Handling system.

(LO21.RFO.FH1.OB05)

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 41.10 55.43 Page 42 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.2.3 Level of Difficulty: 3 Importance Rating 3.8 (multi-unit license) Knowledge of the design, procedural, and operational differences between units.

Question # 69 Initial Unit 1/2 plant conditions:

Unit 1 100% power 14 days from Refueling Outage Shutdown Unit 2 100% power and stable for 100 days Subsequently:

Both Units are responding to events in the ERGs Complete the statements below regarding procedure response in accordance with ODA-407, Operations Department Procedure Use and Adherence.

1. ___(1)___ has the lead for monitoring common equipment status and operating common equipment in the ERGs.

2. Based on the severity of the event to the unit responsible for monitoring and operating common equipment, this responsibility may be transferred to the other unit by the

___(2)___.

A. (1) Unit 1 (2) Shift Manager B. (1) Unit 1 (2) Shift Ops Manager C. (1) Unit 2 (2) Shift Manager D. (1) Unit 2 (2) Shift Ops Manager Answer: A Page 44 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of operational differences between units while both units are operating in the ERGs.

Explanation:

A. Correct. 1st part is correct, with both units responding to events in the ERGs, Unit 1 will monitor and operate common equipment. 2nd part is correct, with both units responding to events in the ERGs the Shift Manager may request responsibility of monitoring and operating common equipment transferred to Unit 2 based on the severity of the event on Unit 1.

B. Incorrect. 1st part is correct (see A above). 2nd part is incorrect but plausible as the Shift Ops Manager is responsible for directing station operations for both Unit 1 and Unit 2 per ODA-102, Conduct of Operations.

C. Incorrect. 1st part is incorrect but plausible as with Unit 1 14 days from shutting down for a refueling outage IPO-003A will have directed transferring common equipment to Unit 2.

However, this is specifically referring to which unit will provide power to the common equipment and not the unit that will be responsible for monitoring and operation of the equipment if both units are operating in the ERGs. 2nd part is correct (see A above).

D. Incorrect. 1st part is incorrect but plausible (see C above). 2nd part is incorrect but plausible (see B above).

Technical Reference(s) ODA-407 Attached w/ Revision # See ODA-102 Comments / Reference IPO-003A/B Proposed references to be provided during examination:

Learning Objective: DISCUSS the operator role in plant operation including the interface with procedures. (LO21.ERG.XG1.OB101)

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 41.10 55.43 Page 45 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.2.12 Level of Difficulty: 2 Importance Rating 3.7 Knowledge of surveillance procedures.

Question # 70 Which of the following describes the use of the Master Surveillance Test List (MSTL)?

A. A reference used to cross-tie Technical Specification surveillance requirements to the appropriate surveillance procedure.

B. A log used to track and document Technical Specification limiting condition for operations entries that result from the performance of surveillances.

C. A reference used to determine which Technical Specification surveillances are scheduled to be performed in the upcoming 30 days.

D. A log used to track and document Technical Specification special condition surveillance test results.

Answer: A Page 50 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A because it requires knowledge of surveillance procedures.

Explanation:

A. Correct: The MSTL cross-ties Technical Specification and the surveillance procedure number, the frequency of performance, the plant operational applicability, and any special considerations that are associated with the surveillance.

B. Incorrect: Plausible since the MSTL is related to Technical Specification surveillances, but it is a cross-tie of Technical Specifications and the surveillance procedures used to satisfy the Technical Specification surveillance requirements.

C. Incorrect: Plausible since the MSTL is related to Technical Specification surveillances, but it is a cross-tie of Technical Specifications and the surveillance procedures used to satisfy the Technical Specification surveillance requirements.

D. Incorrect: Plausible since the MSTL is related to Technical Specification surveillances, but it is a cross-tie of Technical Specifications and the surveillance procedures used to satisfy the Technical Specification surveillance requirements.

Technical Reference(s) STA-702 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the purpose of the Master Surveillance Test List (MSTL)

(ADM.XA5.OB126)

Question Source: Bank # 2005 NRC RO Retake Q68 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2005 NRC RO Retake Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 51 of 54 CPNPP NRC 2017 RO Written Exam Worksheet 61-70 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 3 Group K/A G2.2.7 Level of Difficulty: 3 Importance Rating 2.9 Knowledge of the process for conducting special or infrequent tests.

Question # 71 In accordance with STA-122, Infrequently Performed Tests or Evolutions (IPTE), the following attributes are true of an IPTE:

1. A major evolution performed at greater than 18 month intervals that is covered by an existing normal procedure ___(1)___ be considered an IPTE.

2. An Outage support function of ___(2)___ or higher risk should be considered for IPTE controls.

A. (1) would (2) orange B. (1) would (2) yellow C. (1) would NOT (2) orange D. (1) would NOT (2) yellow Answer: A Page 1 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of IPTE determination at CPNPP.

Explanation:

A. Correct. 1st part is correct. Per STA-122, regardless of whether a procedure exists if a major evolution is performed at greater than or equal to 18 month intervals it will be considered an IPTE. 2nd part is correct. Per STA-122 an Outage support function of orange or higher should be considered for IPTE.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible as yellow is the next lowest risk category and it is reasonable to believe that yellow risk items require IPTE.

C. Incorrect. 1st part is incorrect but plausible because with a normal procedure available it is reasonable to believe IPTE considerations are not warranted. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) STA-122 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS plant operations in accordance with station procedures.

(OPD1.ADM.XA1.OB04)

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 41.10 55.43 Page 2 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.3.5 Level of Difficulty: 2 Importance Rating 2.9 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Question # 72 Given the following conditions:

A Portable Frisker is being used to perform a whole body frisk Background radiation is at 150 counts per minute Which of the following is the LOWEST count rate at which an individual is considered to be contaminated in accordance with STA-653, Contamination Control Program?

A. 175 counts per minute B. 225 counts per minute C. 275 counts per minute D. 325 counts per minute Answer: C Page 4 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires the ability to use fixed radiation monitors.

Explanation:

A. Incorrect. Plausible if actual level of 100 cpm above background cannot be recalled.

B. Incorrect. Plausible if actual level of 100 cpm above background cannot be recalled.

C. Correct. With a background radiation of 150 cpm + a detected radiation level of 100 cpm above background = 250 cpm. Therefore the minimum choice that would indicate that the worker is contaminated would be 275 cpm.

D. Incorrect. Plausible if actual level of 100 cpm above background cannot be recalled.

Technical Reference(s) STA-653 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN how to monitor personnel and personal items for contamination, including the use of friskers and personnel contamination monitors.

Question Source: Bank #

Modified Bank # 2014 NRC Exam Q71 (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.11 55.43 Page 5 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.3.12 Level of Difficulty: 2 Importance Rating 3.2 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.

Question # 73 Given the following conditions:

An entire room, in the Fuel Building, containing a highly radioactive resin container has been posted under a single posting Dose Rates at 1 foot from the radioactive resin container are 20 R/hr General Area Dose Rates are 1500 mR/hr Which of the following is the type of radiological area and who is the LOWEST approval authority required for entry in accordance with STA-660, Control of High Radiation Areas?

A. Very High Radiation Area (VHRA)

Plant Manager B. Locked High Radiation Area (LHRA)

Plant Manager C. Very High Radiation Area (VHRA)

Radiation Protection Manager D. Locked High Radiation Area (LHRA)

Radiation Protection Manager Answer: D Page 10 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of radiation safety principles.

Explanation:

A. Incorrect. Plausible if thought that greater than 1000mr/hr is VHRA as the lowest approval authority for entry into a VHRA is the Plant Manager in accordance with STA-660.

B. Incorrect. Plausible as the area meets requirements for a LHRA. However, the lowest approval authority for entry into a LHRA with a dose rate of 10 R/hr or greater is the Radiation Protection Manger not the Plant Manager in accordance with STA-660.

C. Incorrect. Plausible if thought that greater than 1000mr/hr is VHRA and the lowest approval authority for the stated conditions is the Radiation Protection Manage in accordance with STA-660.

D. Correct. The area meets requirements for posting as a LHRA and the lowest approval authority for the stated conditions is the Radiation Protection Manage in accordance with STA-660.

Technical Reference(s) STA-660 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Question Source: Bank # 2014 NRC Exam Q73 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 41.12 55.43 Page 11 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.4.12 Level of Difficulty: 2 Importance Rating 4.0 Knowledge of general operating crew responsibilities during emergency operations.

Question # 74 Which of the following actions would be inappropriate to perform prior to direction in an emergency response guideline?

A. Isolating Auxiliary Feedwater flow to a single faulted Steam Generator.

B. Throttling Auxiliary Feedwater flow to control a ruptured Steam Generator level within the required band.

C. Securing a Centrifugal Charging Pump to prevent overfilling the Pressurizer following an inadvertent Safety Injection.

D. Closing the Main Steam Isolation Valves to isolate a steam line break which has not resulted in a Safety Injection.

Answer: C Page 18 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of how ABNs are used in conjunction with EOPs.

Explanation:

A. Incorrect. Plausible because this is a numbered step in EOP-2.0, but the ERG Rules of Usage addresses this as being acceptable.

B. Incorrect. Plausible because this is a numbered step in EOP-3.0, but the ERG Rules of Usage addresses this as being acceptable.

C. Correct. Performing steps out of sequence is allowed, but must be done with caution to prevent masking symptoms or defeating the intent of the EOP being used. Although terminating SI early might be beneficial to prevent filling the Pressurizer if the only event is a spurious SI, this may result in further degradation of the plant if another undiagnosed event is in progress.

D. Incorrect. Plausible because this is a numbered step in EOS-0.1, but the ERG Rules of Usage addresses this as being acceptable.

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the requirements associated with deviating from an ERG.

Question Source: Bank # 2012 NRC Exam Q73 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 41.10 55.43 Page 19 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 3 Group K/A G2.4.14 Level of Difficulty: 3 Importance Rating 3.8 Knowledge of general guidelines for EOP usage.

Question # 75 Unit 1 plant conditions:

Small Break Loss of Coolant Accident Containment pressure peaked at 8 psig and is currently at 4.8 psig and lowering Containment radiation peaked at 1.5 x 105 R/hr and is currently at 1 x 104 R/hr and lowering Containment temperature is 160°F and lowering Which of the following describes:

1. Pressurizer level INDICATED versus ACTUAL?

2. The status of using Adverse Containment values?

A. (1) Indicated PRZR level is higher than actual.

(2) Adverse Containment values must be used.

B. (1) Indicated PRZR level is lower than actual.

(2) Adverse Containment values are NO longer required to be used.

C. (1) Indicated PRZR level is higher than actual.

(2) Adverse Containment values are NO longer required to be used.

D. (1) Indicated PRZR level is lower than actual.

(2) Adverse Containment values must be used.

Answer: A Page 24 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 RO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires knowledge of EOP usage guidelines.

Explanation:

A. Correct. Indicated PRZR level is higher than actual due to reference leg heating given current Containment conditions. Although current Containment radiation levels are less than 105 R/hr, the integrated dose must be verified less than 106 Rads.

B. Incorrect. Plausible if thought that Containment pressure has this effect on indicated PRZR level. Additionally, adverse containment values must continue to be used.

C. Incorrect. Plausible because the PRZR level indication is correct, however, adverse containment values must continue to be used.

D. Incorrect. Plausible because the integrated dose rate is correct, however, indicated PRZR level is higher than actual due to reference leg heating.

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the rules for use of Adverse Containment Parameters, including conditions under which their use may be terminated, once initiated.

(LO21.ERG.XD2.OB13)

Question Source: Bank # ILOT7269 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 41.10 55.43 Page 25 of 26 CPNPP NRC 2017 RO Written Exam Worksheet 71-75 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 011 EA2.01 Level of Difficulty: 3 Importance Rating 4.7 Large Break LOCA: Ability to determine or interpret the following as they apply to a Large Break LOCA: Actions to be taken based on RCS temperature and pressure - saturated and superheated.

Question # 76 Unit 1 plant conditions:

Time = 0800:

A LOCA has occurred EOP-1.0A, Loss of Reactor or Secondary Coolant is in progress The crew is on Step 7, Reset ESF Actuation Signals SI reset push buttons fail to operate from the MCB Time = 0810:

The crew is on Step 12, Check if RCS Cooldown and Depressurization is Required RCS temperature = 484°F RHR flow = 780 gpm RCS is 32°F superheated Containment pressure = 7 psig Based on the above plant conditions, complete the following statements.

1. At Time = 0800, EOP-1.0A, Step 7, SI will be reset using EOP-0.0A, Reactor Trip or Safety Injection, Attachment 9, Post Event System Realignment by ___(1)___.

2. At Time = 0810, EOP-1.0A, Step 12 will direct the Unit Supervisor to ___(2)___.

A. 1) de-energizing SSPS locally

2) remain in EOP-1.0A, Loss of Reactor or Secondary Coolant B. 1) de-energizing SSPS locally

2) GO TO EOS-1.2A, Post LOCA Cooldown and Depressurization C. 1) cycling the RTBs from the MCB

2) remain in EOP-1.0A, Loss of Reactor or Secondary Coolant D. 1) cycling the RTBs from the MCB

2) GO TO EOS-1.2A, Post LOCA Cooldown and Depressurization Answer: A Page 1 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine the actions to be taken during a LBLOCA based on plant parameters of superheated conditions.

SRO Only:

NUREG 1021 ES 401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level of knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Correct. 1st part is correct; Caution prior to step 7 of EOP-1.0A refers to Attachment 9 of EOP-0.0A as well as the basis of step 7 to reset either trains SI signal at SSPS per steps 20 and

21. This is done by de-energizing SSPS locally at the cabinet. 2nd part is correct; given that the RCS is 32°F superheated with an RCS temperature of 484°F, then using steam tables the applicant must determine that RCS pressure is approximately 431 psia. The candidate must subtract 15 psi to determine gauge pressure of approximately 416 psig. Per EOP-1.0A, Step 12 with adverse containment conditions and RCS pressure less than 425 psig the RNO step must be referenced. The RNO states that if RHR flow is greater than 750 gpm (currently at 780 gpm) then remain in EOP-1.0A and go to Step 13. The correct procedure flowpath is to remain in EOP-1.0A.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because if the candidate determined an RCS pressure of 431 psia and did not subtract the 15 psi to obtain gauge pressure the transition criteria to EOS-1.2A would be met based on an RCS pressure greater than 425 psig with adverse containment and the RNO step would not be referenced.

C. Incorrect. 1st part is incorrect but plausible as cycling RTBs per step 11 of EOP-0.0A, Attachment 9 will re-instate automatic SI actuation signal. This is a common misconception that re-instating automatic SI signal will reset the SI signal. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) EOP-1.0A Attached w/ Revision # See EOP-0.0A Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: DISCUSS the operator actions, including all cautions, notes, RNOs and bases associated with EOP-1.0A. (LO21.ERG.E1A.OB04)

Page 2 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 3 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Revision Date: Rev. 1 Tier # 1 Group # 1 K/A # 026 G2.2.38 Level of Difficulty: 3 Importance Rating 4.5 Loss of Component Cooling Water: Knowledge of conditions and limitations in the facility license.

Question # 77 Unit 1 plant conditions:

Reactor power = 100%

LBLOCA occurs CCWP 1-02 appropriately sequences ON and immediately TRIPS Subsequently:

The crew has just completed Step 6, Perform The Following To Complete Recirculation Alignment, of EOS-1.3A, Transfer To Cold Leg Recirculation.

Based on the above plant conditions, complete the following statements.

Per Technical Specification 3.7.7, CCW System Bases

1. the CCW System ___(1)___ capable of meeting its Design Basis Safety Function.

2. if Train A CCW System temperature reaches 120°F, the CCW System ___(2)___ reached its MAXIMUM design temperature.

A. (1) is (2) has B. (1) is NOT (2) has C. (1) is NOT (2) has NOT D. (1) is (2) has NOT Answer: D Page 11 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the conditions and limitations of the facility license (operability) of the CCW system.

SRO Only:

NUREG 1021 ES 401 Attachment 2 B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include:

Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1).

Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4).

Knowledge of TS bases that are required to analyze TS required actions and terminology.

Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Incorrect. 1st part is correct per TS 3.7.7 Bases the Design Bases of the CCW system only requires ONE train to remove post LOCA heat load from the containment sump during the recirculation phase. 2nd part is incorrect but plausible as the maximum allowed RHR temperature without CCW flow available before RHR Pumps must be secured in Cold Leg Recirculation is 120°F.

B. Incorrect. 1st part is incorrect but plausible because with a LBLOCA in progress the CCW safeguards loop will automatically split on HI-3 in Containment (18 psig) and therefore one RHR Pump will not have cooling available in the Recirculation mode. Since one RHR Pump will have no cooling available it must be secured during the lineup of Cold Leg Recirculation and it is plausible to think that both RHR pumps must be running in recirculation mode to maintain core cooling and accomplish the appropriate Safety analysis. 2nd part is incorrect but plausible (see A).

C. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is correct per the bases of TS 3.7.7 the CCW Systems design basis is to remove the post LOCA heat load from the containment sump during the recirculation phase and not exceed 135°F.

D. Correct. 1st part is correct (see A). 2nd part is correct (see C).

Technical Reference(s) TS 3.7.7 Bases Attached w/ Revision # See EOS-1.3A & Bases Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the Technical Specifications and Bases associated with the following specifications: 1) TS 3.7.7, Component Cooling Water System (LO21.SST.SW1.OB05)

Question Source: Bank #

Modified Bank (Note changes or attach parent)

New X Page 12 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 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 43.1 Page 13 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 029 EA2.01 Level of Difficulty: 2 Importance Rating 4.7 ATWS: Ability to determine or interpret the following as they apply to a ATWS: Reactor nuclear instrumentation.

Question # 78 Unit 1 plant conditions:

Time = 0800:

Reactor power = 100%

RCS pressure = 2100 psig lowering The reactor fails to trip manually Time = 0803:

FRS-0.1A, Response to Nuclear Power Generation / ATWT is in progress Power Range NIs = 4%

Neutron Flux Wide Range Instruments = 8%

RCS pressure = 1700 psig lowering Containment pressure = 6 psig rising Time = 0806:

Power Range NIs = 2%

Neutron Flux Wide Range Instruments = 4%

Based on the above plant conditions, completes the statements below.

1. The EARLIEST time that the crew may transition out of FRS-0.1A is ___(1)___.

2. The crew will TRANSITION to ___(2)___.

A. (1) 0803 (2) EOP-0.0A, Reactor Trip or Safety Injection B. (1) 0803 (2) EOP-1.0A, Loss of Reactor or Secondary Coolant C. (1) 0806 (2) EOP-0.0A, Reactor Trip or Safety Injection D. (1) 0806 (2) EOP-1.0A, Loss of Reactor or Secondary Coolant Answer: C Page 17 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine the correct procedure path using Nuclear Instrumentation.

SRO Only:

NUREG 1021 ES 401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. 1st part is incorrect but plausible as the US will not transfer out of FRS-0.1A until reactor power is < 5% on the Neutron Flux Wide Range Instruments as Containment pressure is adverse (> 5 psig) and the PRNIs are not post-accident qualified. 2nd part is incorrect when paired with time 0803 but plausible as FRS-0.1A does direct you to perform steps 1-8 of EOP-0.0A if an SI signal exists.

B. Incorrect. 1st part is incorrect because you will not transfer out of FRS-0.1A until reactor power is

< 5% on the Neutron Flux Wide Range Instruments as Containment pressure is adverse (> 5 psig) and the PRNIs are not post-accident qualified. 2nd part is incorrect but plausible when paired with time 0803 as FRS-0.1A does direct the crew to transition to procedure and step in effect when conditions are met, in this case with a LOCA in progress it is reasonable to think that EOP-1.0A would be the procedure and step in effect, also It is plausible because after transferring to EOP-0.0A, you will then transition to EOP-1.0A due to the LOCA.

C. Correct. 1st part is correct, when power is < 5% on Neutron Flux Wide Range meters, FRS-0.1A directs the US to Step 18 where RCPs are checked just prior to returning to procedure and step in effect. 2nd part is correct when the crew transitions it will be to EOP-0.0A as it is the procedure and step in effect.

D. Incorrect. 1st part is correct, when power is < 5% on Neutron Flux Wide Range meters, FRS-0.1A directs the US to Step 18 where RCPs are checked just prior to returning to procedure and step in effect. 2nd part is incorrect but plausible when paired with time 0806 as after the transition is made to EOP-0.0A, you will then transition to EOP-1.0A due to the LOCA.

Technical Reference(s) FRS-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the operator response to an Anticipated Transient Without Trip.

(LO21.MCO.MI5.OB02)

Page 18 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 19 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 055 G2.4.35 Level of Difficulty: 2 Importance Rating 4.0 Station Blackout: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Question # 79 Unit 1 plant conditions:

A station blackout has occurred Based on the above plant conditions, complete the following statements.

1. During a station blackout, personnel will be dispatched to isolate RCP seals using guidance contained in ___(1)___.

2. RCP seal injection is isolated to ___(2)___.

A. 1) ECA-0.0A, Loss of All AC Power

2) minimize collapse of steam voids in CCW when charging is reestablished B. 1) ECA-0.0A, Loss of All AC Power

2) prevent thermal shocking the RCP seals when charging is reestablished C. 1) SOP-108A, Reactor Coolant Pump

2) minimize collapse of steam voids in CCW when charging is reestablished D. 1) SOP-108A, Reactor Coolant Pump

2) prevent thermal shocking the RCP seals when charging is reestablished Answer: B Page 28 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of auxiliary operator tasks performed during a blackout and the reason (operational effects) of those actions.

SRO Only:

NUREG 1021 ES 401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. 1st part is correct. ECA-0.0A provides guidance to isolate RCP seals. 2nd part is incorrect because the reason for isolating RCP seal injection (per ECA-0.0A step 10 bases) is to prevent thermal shocking the RCP seals when charging is restored. It is plausible because ECA-0.0A step 10 Bases addresses isolating RCP thermal barrier CCW return outside containment locally to protect the CCW system from steam formation due to RCP thermal barrier heating. (per ECA-0.0A step 10 bases).

B. Correct. 1st part is correct (see A). 2nd part correct. The reason for isolating RCP seals is to prevent thermal shocking the seals upon a charging pump start.

C. Incorrect. 1st part is incorrect because the guidance to isolate RCP seals is contained in ECA-0.0A. It is plausible because there is guidance in the RCP SOP for isolating / restoring RCP seals. Also, ECA-0.0A does give some directions by referring to other SOPs (SOP-304A/B for guidance on starting and stopping the TDAFWP in Attachment 8 (see attached)). 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) ECA-0.0A & Bases Attached w/ Revision # See SOP-108A Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions from ECA-0.0.

(LO21.ERG.C00.OB06 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Page 29 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO 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 55.43 43.5 Page 30 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 056 G2.4.45 Level of Difficulty 3 Importance Rating 4.3 Loss of Off-site power: Ability to prioritize and interpret the significance of each annunciator or alarm.

Question # 80 Unit 1 Reactor Trip occurred The plant is stable in EOS-0.1A, Reactor Trip Response Shift Manager has directed a plant cooldown

1. The initiating event for the Reactor Trip is a ___(1)___.

2. The plant cool down will be performed per ___(2)___.

A. (1) Loss of Offsite Power (2) IPO-005A, Plant Cooldown from Hot Standby to Cold Shutdown B. (1) Reactor Coolant Pump trip (2) IPO-005A, Plant Cooldown from Hot Standby to Cold Shutdown C. (1) Loss of Offsite Power (2) EOS-0.2A, Natural Circulation Cooldown D. (1) Reactor Coolant Pump trip (2) EOS-0.2A, Natural Circulation Cooldown Answer: C Page 44 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

The question is a K/A match as it requires the applicant interpret from the first out panel indications the condition that caused the reactor trip (prioritize & interpret) and the required actions.

SRO Only:

NUREG 1021 ES 401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. 1st part is correct (See C below). 2nd part is incorrect but plausible as the applicant may believe that the normal procedure for performing a cooldown which is per IPO-005A is still preferred. This is plausible as the procedure may be performed without RCPs running but this would not be correct for the given plant conditions. Further the applicant may mistake the fact that window 4.2 NOT being lit indicates at least one RCP is running which would prompt performance of IPO-005A. However, this indication is misleading in that the RCP coastdown results in this First Out not indicating.

B. Incorrect. 1st part is incorrect but plausible as there are three first out annunciators that indicate RCPs are tripped, however the RED annunciator RX>50% TURB TRIP is LIT due to the loss of offsite power and is the cause of the reactor trip. 2nd part is incorrect but plausible (See A above).

C. Correct. 1st part is correct because the loss of offsite power caused a turbine trip that led to the RX>50% TURB TRIP annunciator being lit RED. 2nd part is correct because with no reactor coolant pumps available and a plant cooldown directed per EOS-0.1A, the correct transition is to EOS-0.2A.

D. Incorrect. 1st part is incorrect but plausible (See B above). 2nd part is correct (See C above).

Technical Reference(s) ALM-4000A Attached w/ Revision # See EOS-0.1A Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.1, Reactor Trip Response. (LO21.ERG.E01.OB02)

Question Source: Bank # 2016 NRC Exam Q76 Modified Bank # (Note changes or attach parent)

New Page 45 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Question History: Last NRC Exam 2016 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 46 of 50 CPNPP NRC 2017 SRO Written Exam Worksheet 76-80 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 040 G 2.1.7 Level of Difficulty: 4 Importance Rating 4.7 Steam Line Rupture - Excessive Heat Transfer: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Question # 81 A seismic event has occurred at Comanche Peak Unit 1 has experienced a Reactor Trip and Safety Injection A complete Main Steamline Isolation was verified in EOP-0.0A, Reactor Trip or Safety Injection Transition has been made to EOP-2.0A, Faulted Steam Generator Isolation The following parameters are observed:

Containment pressure is 15 psig rising RCS Tave = 475°F lowering RCS pressure = 1620 psig lowering Pressurizer level = 32% lowering SG 1-01 pressure 15 psig SG 1-02, 1-03 & 1-04 pressures 540 psig lowering SG 1-01 has been isolated AFW flow to SGs 1-02, 1-03 and 1-04 = 180 gpm per SG SG 1-01 level = 20% wide range rising SG 1-02, 1-03 & 1-04 levels 55% narrow range stable Which of the following is the first procedure transition required in accordance with EOP-2.0A?

Transition to...

A. ECA-2.1A, Uncontrolled Depressurization of All Steam Generators.

B. EOP-1.0A, Loss of Reactor or Secondary Coolant.

C. EOP-3.0A, Steam Generator Tube Rupture.

D. EOS-1.1A, Safety Injection Termination.

Answer: C Page 1 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring an evaluation of provided instrumentation and operating characteristics of a Steam Line Rupture and making an operational decision on procedure transition from another ERG.

SRO Only:

E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. Plausible because the plant indications show pressure lowering in all intact steam generators, however the pressure is not decreasing in an uncontrolled manner based on the intact steam generators all being at the same pressure and at an expected pressure following blowdown of a single steam generator.

B. Incorrect. Plausible because there would be no radiation monitor feedback for the faulted ruptured steam generator in this condition and the operator would have to diagnose that the faulted steam generator is not attaining dryout condition to avoid bypassing the transition to EOP-3.0A.

C. Correct. The rising level in the faulted steam generator and the lowering pressurizer level, RCS pressure and RCS temperature indicate that the faulted steam generator is also ruptured.

D. Incorrect. Plausible because subcooling is 100°F and a secondary heat sink exists however with RCS pressure lowering and pressurizer level less than 34% SI cannot be terminated.

Technical Reference(s) EOP-2.0A & Bases Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: IDENTIFY the symptoms for the entry conditions of EOP-2.0, Faulted Steam Generator Isolation.

Question Source: Bank # 2014 NRC Exam Q79 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 Page 2 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 55.43 43.5 Page 3 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO S RO

v. Date: Rev. 1 Tier 1 Group 2 KIA 005 AA2.03 Im ortance Ratin 4.4 ions:

• Reactor po r = 90%

• 1-ALB-060, dow 3.5, DRPI ROD DEV is lit

• 1-ALB-060, Win w 3.7, ANY ROD AT BOT is dark

• Control Rod D4 an

• HB (both in Control Bank D) will not respond to demand signals from the Control Roo ...

• Troubleshooting has d ~rmined the Rods are mechanically bound

• ABN-712, Rod Centro! S tern Malfunction has been entered

• SDM has been verified

1. Control Rods 04 and HB _

(1) _ con ed OPERABLE per TS 3.1.4, Rod Group Alignment Limits. **

2. In accordance with ABN-712, Section 3, Drop ~ isaligned Rod in Mode 1 or 2, the crew is required to _(2)_.

".>t A. (1) are ~a-(2) trip the reactor immediately and GO TO EOP-0. , Reactor Trip or Safety Injection B. (1) are (2) shut down to Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> using IP0-003A, Po C. (1) are NOT (2) trip the reactor immediately and GO TO EOP-0.0A, Reactor Tr Injection D. (1) are NOT (2) shut down to Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> using iP0-003A, Power Operation Answer: D Page 11 of88 CPNPP NRG 2017 SRO Written Exam W orksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-40 1-5 TH question matches the KA by requiring the ability to determine the correct actions for two stuck cont I rods.

While not asking the section in ABN-712 to from different sections in the procedure.

Explanation:

A. Incorrect. 16 part is incorrect because IAW T.S. 3.1. operable, the affected rods must be trippable and with the rod mechanically bound it is not 1 ble. It is plausible because one must know that the operability of the rod is specifically tied to * "lity, it is a common misconception that rods may still be operable even though they cannot be "pped as the SOM of the core has remained unchanged as long as power and boron concentrat n has not changed. 2nd part is incorrect because you are not required to trip the reactor. It is p usible because if the two rods had dropped, it would be correct.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. With 2 rods misaligned from the step counter by> 12 steps (as verified by the alarm), the plant 1 required to be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> using IP0-003A.

C. Incorrect. 1st part is correct. IAW ABN-712, if the control rods are not capable f motion (i.e.

mechanically bound), they are not considered trippable; if they are not trippable t y are not operable per TS 3.1.4. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical References ABN-712 1--~~~~~~->._._-+-~~~~~~~~~~~~~~~~

Attached w/ Revision See 1-ALB-60 Comments I Reference TSB 3.1.4 Proposed references to be provided during examination: ~~~~~~~~~~~~~~~~

Page 12 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 ANALYZE the response to a Dropped or Misaligned Rod in MODE 1 or 2 in accordance with ABN-712, Rod Control System Malfunction.

(L021.ABN.712.0802}

Bank#

Modified Bank# - - - -- - - - (Note changes or attach parent)

New x Question History: Last NRC Exam Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content:

43.5 Page 13 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 060 G2.2.25 Level of Difficulty: 3 Importance Rating 4.2 Accidental Gaseous Radwaste Release: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Question # 83 Unit 1 plant conditions:

Reactor power = 100%

A relief valve is lifting on Gas Decay Tank #10 PC-11 HIGH alarm for X-RE-5701 AUX BLDG VENT DUCT (ABV089) alarms The radioactivity contained in Gas Decay Tank # 10 is determined to be 210,000 curies of noble gas Based on the above plant conditions, complete the following statements.

In accordance with TRM 13.10.32, Gas Storage Tanks

1. Gas Decay Tank #10 ___(1)___ within the MAXIMUM allowed quantity of radioactivity.

2. if the activity in Gas Decay Tank #10 were maintained within limits of TRM 13.10.32, the total body dose rate at the site boundary from noble gases would be below the limit stated in TS 5.5.4 of ___(2)___.

A. (1) is (2) 500 mrem/yr B. (1) is (2) 1500 mrem/yr C. (1) is NOT (2) 500 mrem/yr D. (1) is NOT (2) 1500 mrem/yr Answer: C Page 19 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the bases in TS (5.5.4) for limits for Gas Decay Tanks.

SRO Only:

NUREG 1021, ES-401, Attachment 2:

B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Examples of SRO exam items for this topic include: 1) Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1). 2) Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4). 3) Knowledge of TS bases that are required to analyze TS required actions and terminology. 4) Same items above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Incorrect. 1st part is incorrect because the maximum quantity of radioactivity that may be contained in any Gas Decay Tank is 200,000 curies of noble gas per TRM 13.10.32, Gas Storage Tanks. Plausible because if the value of curies in the tank provided in the stem were below 200,000 curies it would be correct. 2nd part is correct the TS 5.5.4 limit for dose at the site boundary for noble gasses is 500 mrem / year per TS 5.5.4, Radioactive Effluent Controls Program and the bases of TRM 13.10.32, Gas Storage Tanks.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect because the TS 5.5.4 and TRM 13.10.32 bases limit for dose at the site boundary for noble gasses is 500 mrem / year. It is plausible because if it were the limit for Iodine 131/133 it would be correct for any particular organ.

C. Correct. 1st part is correct the maximum quantity of radioactivity that may be contained in any Gas Decay Tank is 200,000 curies of noble gas per TRM 13.10.32, Gas Storage Tanks. 2nd part is correct (see A).

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) TRM 13.10.32 & Bases Attached w/ Revision # See TS 5.5.4 Comments / Reference Proposed references to be provided during examination:

Learning Objective: APPLY the administrative requirements of the Gaseous Waste system including Technical Specifications, TRM and ODCM. (LO21.SYS.RWS.OB05)

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 Page 20 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 43.2 Page 21 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 028 AA2.07 Level of Difficulty: 3 Importance Rating 2.9 Pressurizer Level Malfunction: Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Seal water flow indicator for RCP.

Question # 84 Unit 1 plant conditions:

Unit 1 is performing a Reactor startup Reactor Power = 8% stable Seal Injection Flow to each RCP = 8 gpm stable Pressurizer Water Level = 25% stable 1/1-LS-459D, PRZR LVL CTRL CHAN SELECT switch is in the 459/460 position Centrifugal Charging Pump 1-01 is in service Subsequently:

1 -LT-459, PRZR LVL CHAN I fails HIGH ABN-706, Pressurizer Level Instrumentation Malfunction is entered Based on the above conditions, complete the following statements.

1. Reactor Coolant Pump Seal Injection Flow indication will ___(1)___.

2. Technical Specification 3.3.1, RTS Instrumentation, ___(2)___ required to be entered for FUNCTION 9, Pressurizer Water Level - High.

A. (1) remain the same (2) is B. (1) remain the same (2) is NOT C. (1) lower (2) is D. (1) lower (2) is NOT Answer: D Page 26 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the diagnoses of how RCP seals will fail during a Pressurizer Level Instrument failure and how the failure will affect a control room indication for RCP seals SRO Only:

NUREG 1021, ES-401, Attachment 2:

B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Examples of SRO exam items for this topic include: 1) Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1). 2) Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4). 3) Knowledge of TS bases that are required to analyze TS required actions and terminology. 4) Same items above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Incorrect. 1st part is incorrect but plausible because it is reasonable to think that RCP Seal Injection would remain the same if thought that Pressurizer Level Channel 460 was the controlling channel. The Level Control Channel Select switch has both transmitters in the switch position (i.e. 459/460) so it is reasonable to think that Level Channel 460 could be the controlling channel. 2nd part is incorrect but plausible as this TS would be entered with a failure high of Pressurizer Level Channel 459 if Reactor Power were above P-7 (10%)

because the TS requires 3 channels to operable and only 3 channels are available, however, in this case the unit is in Mode 1 less than 10% power and the TS in not required to be entered.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct with Reactor Power less than P-7 (10%) TS 3.3.1 is not required to be entered for Function 9 - Pressurizer Water Level High. This is annotated in TS 3.3.1 Bases and TS Table 3.3.1 RTS Instrumentation.

C. Incorrect. 1st part is correct when Pressurizer Level Channel 459 fails high with Przr Level control and FCV-121, Charging Flow Control in automatic then FCV-121 will throttle closed to attempt to lower Pressurizer level; as it throttles closed it will lower flow to RCP seals and bring in the alarm for RCP seal flow low at less than 6.5 gpm. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (B).

Technical Reference(s) ABN-706 Attached w/ Revision # See ALB-5C & ALB-5A Comments / Reference TS 3.3.1 & Bases Proposed references to be provided during examination:

Learning Objective: EVALUATE plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation while responding to a Chemical and Volume Control System malfunction Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Page 27 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 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 43.2 Page 28 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A W/E16 G 2.2.42 Level of Difficulty: 3 Importance Rating 4.6 High Containment Radiation: Ability to recognize system parameters that are entry level conditions for Technical Specifications.

Question # 85 Unit 1 plant conditions:

Unit 1 is in MODE 3 1-RE-6290A, Containment High Range Radiation Monitor, has failed Which of the following is the Technical Specification impact?

A. Enter a Tracking LCOAR for TS LCO 3.3.3, Post Accident Monitoring (PAM)

Instrumentation.

B. Enter a Tracking LCOAR for TS LCO 3.3.4, Remote Shutdown System.

C. Enter an Active LCOAR for TS LCO 3.3.3, Post Accident Monitoring (PAM)

Instrumentation.

D. Enter an Active LCOAR for TS LCO 3.3.4, Remote Shutdown System.

Answer: C Page 35 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to recognize TS entry conditions.

SRO Only:

NUREG 1021, ES-401, Attachment 2:

B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include:

Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1).

Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4).

Knowledge of TS bases that are required to analyze TS required actions and terminology.

Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Incorrect. Plausible because the Technical Specification is correct, however, an Active LCOAR must be initiated and only one of 2 channels is INOPERABLE.

B. Incorrect. Plausible if thought that Containment High Range Radiation was a Technical Specification LCO 3.3.4 entry.

C. Correct. An Active LCOAR must be initiated and only one of 2 channels is INOPERABLE for Technical Specification LCO 3.3.3.

D. Incorrect. Plausible because an Active LCOAR must be initiated and only one of 2 channels is INOPERABLE, however, the Technical Specification entry is incorrect.

Technical Reference(s) TS 3.3.3 Attached w/ Revision # See ODA-308 Comments / Reference Proposed references to be provided during examination:

Learning Objective: LIST and DESCRIBE the following Technical Specifications (i.e., LCOs, action statements and conditional surveillance requirement of one hour and less, if applicable) for the Reactor Coolant System:

3.3.3, Post Accident Monitoring Instrumentation (SYS.RC1.OB18)

Question Source: Bank # 2011 NRC Exam Q83 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X Page 36 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 55.43 43.2 Page 37 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 003 G2.4.35 Level of Difficulty: 3 Importance Rating 4.0 Reactor Coolant Pump: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Question # 86 Unit 1 initial plant conditions:

Unit 1 is in MODE 4 following a Reactor Trip Crew is performing a Natural Circulation Cooldown Starting an RCP is desired Which of the following is proper procedural direction to give the Nuclear Equipment Operator starting the RCP?

Place the RCP Overcurrent Trip Selector Switch in the A. COLD LOOP position to restore the locked rotor and failure to accelerate automatic trips, in accordance with EOS-0.2A, Natural Circulation Cooldown, Attachment 3, Starting an RCP.

B. COLD LOOP position to restore the locked rotor and failure to accelerate automatic trips, in accordance with SOP-108A, Reactor Coolant Pump.

C. HOT LOOP position to ensure locked rotor protection is properly defeated, in accordance with EOS-0.2A, Natural Circulation Cooldown, Attachment 3, Starting an RCP.

D. HOT LOOP position to ensure locked rotor protection is properly defeated, in accordance with SOP-108A, Reactor Coolant Pump.

Answer: A Page 45 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of local auxiliary operator tasks during and emergency and what effect they have.

SRO Only:

NUREG 1021, ES-401, Attachment 2:

E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Correct. 1st part is correct the Cold Loop position restores the locked rotor and failure to accelerate automatic RCP trips and the RCP Overcurrent Trip Selector Switch should be placed in this position when starting the RCP. 2nd part is correct the RCP should be started per the Attachment of EOS-0.2A.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because guidance is contained in SOP-108A for starting an RCP and positioning the RCP Overcurrent Trip Selector Switch. Also, there are instances when ERGs direct actions to be performed from an SOP. For example, EOS-0.2A directs placing the RHR system in service per SOP-102A on step 25 of the ERG. In this case starting the RCP per the Attachment of EOS-0.2A is the correct procedural flowpath.

C. Incorrect. 1st part is incorrect but plausible because defeating automatic trips would appear to have merit when the desire to start an RCP in the ERGs is preferred, however, the seriousness of the current situation does not warrant the bypass of equipment protection at this point. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B)

Technical Reference(s) EOS-0.2A Attached w/ Revision # See SOP-108A Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.2, Natural Circulation Cooldown.

Question Source: Bank # 2012 NRC Exam Q86 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Page 46 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO 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 55.43 43.5 Page 47 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 004 A2.05 Level of Difficulty: 3 Importance Rating 4.3 CVCS: 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:

RCP Seal Failures.

Question # 87 Unit 1 plant conditions:

Reactor Power = 100%

1-ALB-5A, Window 1.2 - ANY RCP SEAL 1 LKOFF FLO HI alarms 1-ALB-5A, Window 3.2 - ANY SEAL 2 LEAKOFF FLO HI is DARK ABN-101, Reactor Coolant Pump Trip/Malfunction is entered RCP 1-01 #1 Seal Leakoff Flow = 6.5 gpm rising RCP 1-01 Seal Injection Flow = 8.5 gpm rising RCP 1-01 Seal Inlet temperature is rising Based on the above plant conditions, complete the following statements.

1. As RCP 1-01 #1 Seal Leakoff flow continues to rise ___(1)___ will also rise.

2. Per ABN-101, the US should direct the crew to ___(2)___.

A. (1) VCT level (2) PERFORM an orderly shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per IPO-003A, Power Operations B. (1) VCT level (2) Immediately TRIP the reactor and GO TO EOP-0.0A, Reactor Trip or Safety Injection C. (1) PRZR level (2) PERFORM an orderly shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per IPO-003A, Power Operations D. (1) PRZR level (2) Immediately TRIP the reactor and GO TO EOP-0.0A, Reactor Trip or Safety Injection Answer: B Page 55 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine how a failure of RCP 1-01 seal will affect the CVCS system and actions to mitigate RCP #1 Seal Failure.

SRO Only:

NUREG 1021, ES-401, Attachment 2:

E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. 1st part is correct. With the conditions stated, and RCP 1-01 #1 Seal Leakoff flow rising the leakoff from the seal will be directed back to the VCT via the Seal Water HX and VCT level will rise. 2nd part is incorrect but plausible because with Total #1 Seal Flow between 6 and 8 gpm and with stable pump bearing and seal temperatures then an orderly shutdown to Mode 3 would be performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per IPO-003A, however, in this case RCP 1-01 Seal Inlet temperature is rising which requires an immediate Reactor Trip and entry into EOP-0.0A per ABN-101.

B. Correct. 1st part is the correct (see A). 2nd part is correct. Per ABN-101 if Total #1 Seal Flow is greater than 6 gpm (#1 Seal Leakoff flow + #2 Seal Leakoff indications = Total #1 Seal Flow, 6.5 gpm + 1 gpm (assumed since containment entry not practical at power) = 7.5 gpm) and Pump Bearing/Seal Inlet temperature is rising then per ABN-101 an immediate Reactor Trip and entry into EOP-0.0A is required.

C. Incorrect. 1st part is incorrect but plausible since as #1 Seal Leakoff increases Seal Injection flow will also rise and it is reasonable to believe that as Seal Injection Flow rises PRZR level will increase, however, with PRZR level control in automatic it will stay constant and maintain program level by varying charging flow as necessary. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) ABN-101 Attached w/ Revision # See 1-ALB-5A Comments / Reference RCS Study Guide Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the Chemical and Volume Control System. (LO21.SYS.CS1. OB104)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Page 56 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 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 43.5 Page 57 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 022 G2.4.30 Level of Difficulty: 3 Importance Rating 4.1 Containment Cooling: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or transmission system operator.

Question # 88 Unit 1 plant conditions:

Time = 0400:

A containment cooling equipment failure has occurred TS 3.6.5, Containment Air Temperature entry is made Time = 1200:

Unit shutdown is initiated as required by TS 3.6.5 Time = 1400:

Unit is in Mode 3 No Emergency Plan classifications were required Based on the above plant conditions, complete the following statements.

1. Per TS 3.6.5, Containment Average Air Temperature of GREATER THAN ___(1)___ has been exceeded.

2. In accordance with STA-501, Non Routine Reporting, a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report must be made to the NRC NO LATER THAN time ___(2)___.

A. (1) 120°F (2) 1800 B. (1) 110°F (2) 1800 C. (1) 120°F (2) 1600 D. (1) 110°F (2) 1600 Answer: C Page 67 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of plant events that must be reported to the NRC including the time and point of initiation related to TS violation of Containment Average Air Temperature.

SRO Only:

This question is SRO only because a determination of NRC notification requirements must be made which is an SRO responsibility.

Explanation:

A. Incorrect. 1st part is correct. Per TS 3.6.5 a containment average air temperature of greater than 120°F exceeds the LCO limit. 2nd part is incorrect IAW STA-501 (10CFR72), any shutdown required by TS is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification requirement from the initiation of the shutdown. It is plausible because it is a common misconception that the clock to make a report to the NRC for a Unit shutdown does not start until the Unit has been shutdown (i.e. Mode 3).

B. Incorrect. 1st part is incorrect but plausible as per OPT-102A the surveillance limit is 110°F. 2nd part is incorrect but plausible (see A).

C. Correct. 1st part is correct (see A). 2nd part is correct IAW STA-501 (10CFR50.72), any shutdown required by TS is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification requirement from the initiation of the shutdown.

D. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is correct (see C).

Technical Reference(s) TS 3.6.5 Attached w/ Revision # See STA-501 Comments / Reference 10CFR50.72 OPT-102A Proposed references to be provided during examination:

Learning Objective: Given an event related to system operation/status, CLASSIFY which events must be reported to external agencies, with respect to each category: 1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reports 2) 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reports 3) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reports 4) Written reports (LO21.ADM.XA7.OB01)

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 43.1 Page 68 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 039 A2.05 Level of Difficulty: 3 Importance Rating 3.6 Main and Reheat Steam: Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power.

Question # 89 Unit 1 initial plant conditions:

Reactor power = 90%

A safety valve on SG 1-02 starts leaking by its seat Current conditions:

Reactor power = 92%

1-ALB-6D, Window 4.10 - QUADRANT PWR TILT alarms QPTR is determined to be 1.03 TS 3.2.4, Quadrant Power Tilt Ratio is entered Based on the above plant conditions, complete the following statements.

1. When the steam leak has stabilized, MWe will be___(1)___.

2. In accordance with TS 3.2.4, reactor power ___(2)___ have to be lowered.

A. (1) the same (2) does B. (1) the same (2) does NOT C. (1) lower (2) does D. (1) lower (2) does NOT Answer: A Page 73 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to use procedures (TS) to mitigate the consequences of the malfunction.

SRO ONLY:

This is TS knowledge beyond that required by an RO.

NUREG 1021, ES-401, Attachment 2:

B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include:

Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1).

Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4).

Knowledge of TS bases that are required to analyze TS required actions and terminology.

Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Correct. 1st part is correct. The turbine is set to maintain MWe so when the steam leak diverts some steam from the turbine, the turbine control valves will open to maintain MWe (pulling more steam). 2nd part is correct. With QPTR > 1.02, TS 3.2.4 requires power to be reduced by > 3% of RTP for every 1% over a QPTR of 1.00. This will equal 9% so power will have to be reduced to

< 91% at a minimum.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because power will have to be reduced to below 91%. It is plausible because the limit for TS 3.2.4 is 1.02 and the tilt is 1.03. If you thought that you had to reduce only 3% (for being .01 over the limit of 1.02 instead of 9% for being .03 over 1.00), this would put the maximum power of 97% instead of 91%.

C. Incorrect. 1st part is incorrect because MWe would stay approximately the same because the turbine control system is designed to maintain MWe. It is plausible because if it were designed to maintained steam pressure (like the Steam Dumps before the turbine is loaded), MWe would lower while steam pressure were maintained constant. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) TS 3.2.4 Attached w/ Revision # See Main Steam Study Guide Comments / Reference Proposed references to be provided during examination: TS 3.2.4, QPTR Learning Objective: DESCRIBE the components of the Main Steam system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.MR1.OB03)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Page 74 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 75 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 061 G2.2.22 Level of Difficulty: 2 Importance Rating 4.7 Auxiliary / Emergency Feedwater: Knowledge of limiting conditions for operations and safety limits.

Question # 90 Unit 1 plant conditions:

Preparations for a Reactor startup are in progress Unit is in Mode 3 with all control rods inserted 1-PV-2453A, MDAFWP 1 SG 1 FLO CTRL loses electrical power Maintenance states that the repair will take approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Based on the above plant conditions, complete the following statements.

1. 1-PV-2453A will fail ___(1)___.

2. The Unit Supervisor ___(2)___ continue with the startup to criticality.

A. (1) open (2) may B. (1) open (2) may NOT C. (1) closed (2) may D. (1) closed (2) may NOT Answer: B Page 80 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the operability requirements of the AFW system to make an LCO determination and therefore the correct decision about going up a mode.

SRO Only:

NUREG 1021 ES 401 Attachment 2 B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include: 1) Application of Required Actions (Section

3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1). 2) Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4). 3) Knowledge of TS bases that are required to analyze TS required actions and terminology. 4) Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

SRO-only knowledge generally cannot be claimed for questions that can be answered solely based on knowledge of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action statements and the safety limits since Reactor Operators (ROs) are typically required to know these items.

Explanation:

A. Incorrect. 1st part is correct. 1-PV-2453A fails open on a loss of electrical power. 2nd part is incorrect because with the valve inoperable, one train of AFW becomes inoperable. LCO 3.0.4 prevents you from going up a mode (Mode 2 if going critical) unless you are allowed continued operation. It is plausible because the valve fails which will provide flow if needed so it would seem ok for it to remain operable.

B. Correct. 1st part is correct (see A). 2nd part correct. With the valve/train inoperable, you are not allowed to go up a mode (being critical would make you Mode 2).

C. Incorrect. 1st part is incorrect because the valve fails open on a loss of power. It is plausible for it to fail closed in that it could cause an overcooling event when failing open. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) AFW Study Guide Attached w/ Revision # See LCO 3.0.4 Comments / Reference TS 3.7.5 TSB 3.7.5 Proposed references to be provided during examination:

Learning Objective: APPLY the administrative requirements of the Auxiliary Feedwater system including Technical Specifications, TRM and ODCM (LO21.SYS.AF1.OB106)

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 Page 81 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 55.43 43.2 Page 82 of 88 CPNPP NRC 2017 SRO Written Exam Worksheet 81-90 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 001 A2.14 Level of Difficulty: 3 Importance Rating 3.9 Control Rod Drive: Ability to (a) predict the impacts of the following malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms.

Question # 91 Unit 1 plant conditions:

Time = 0800:

Reactor power = 80%

1-ALB-6D, Window 1.6, CONTROL ROD CTRL URGENT FAIL alarms due to a failure in the Logic Cabinet Based on the above plant conditions, complete the following statements.

1. The affected control rods ___(1)___ be moved in MANUAL.

2. If the alarm CANNOT be cleared, TS 3.1.4, Rod Group Alignment Limits ___(2)___

require a plant shutdown.

A. (1) can (2) does B. (1) can (2) does NOT C. (1) can NOT (2) does D. (1) can NOT (2) does NOT Answer: D Page 1 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to predict the impact of an Urgent Failure and have knowledge of procedures (TS) that may be used to address the failure.

SRO Only:

NUREG 1021 ES 401 Attachment 2 B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include:

Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1).

Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4).

Knowledge of TS bases that are required to analyze TS required actions and terminology.

Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

Explanation:

A. Incorrect. 1st part is incorrect because an Urgent Failure in the logic cabinet will prevent manual rod motion. It is plausible because being in the logic cabinet would seem to indicate that individual rod motion would still be possible. 2nd part is incorrect because per the TSB 3.1.4, an Urgent Failure does not result in rod inoperability (the rods can still be tripped). It is plausible because the rods cannot be moved in either direction. If the control rods could not be tripped, it would be correct.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. Because the control rods are still considered operable, TS 3.1.4 does not require a plant shutdown.

C. Incorrect. 1st part is correct. An Urgent Failure prevents both Automatic and Manual rod motion. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) TS 3.1.4 Attached w/ Revision # See TSB 3.1.4 Comments / Reference 1-ALB-6D Proposed references to be provided during examination:

Learning Objective: APPLY the administrative requirements of the Rod Control System including Technical Specifications, TRM and ODCM. (LO21.SYS.CR1.OB06)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Page 2 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO 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 55.43 43.5 Page 3 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 2 K/A 033 A2.03 Level of Difficulty: 2 Importance Rating 3.5 Spent Fuel Cooling: Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.

Question # 92 Unit 1 plant conditions:

Unit 1 is shutdown for refueling Fuel offload is in progress FB-810, Window 4.3 - RFL CAVITY 1 LEVEL LO is in alarm Refueling Cavity Level = 85711 Spent Fuel Pool Level = 8589 ABN-909, Spent Fuel Pool/Refueling Cavity Malfunction is entered Fuel handling has been suspended Based on the above plant conditions, complete the following statements.

In accordance with ABN-909, when equalizing building pressures,

1. the transfer tube gate valve will be ___(1)___.

2. the crew will use SOP-801A, Containment ventilation System, Section ___(2)___.

A. 1) left open

2) 5.6.1, Containment Purge Supply AND Exhaust System Startup B. 1) left open

2) 5.6.5, Containment Pressure Relief System Operation C. 1) closed

2) 5.6.1, Containment Purge Supply AND Exhaust System Startup D. 1) closed

2) 5.6.5, Containment Pressure Relief System Operation Answer: D Page 8 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to predict the impact of a lowering SFP level and select the appropriate procedure to mitigate plant conditions.

SRO Only:

NUREG 1021 ES 401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. 1st part is incorrect because the transfer tube gate will be closed when fuel handling is suspended. It is plausible because leaving them open when equalizing pressure would return the levels to normal as pressure was equalized (quicker). 2nd part is incorrect because you are directed to equalize pressure using Containment Pressure Relief OR Alternating primary plant supply and exhaust fans. It is plausible because operating the Containment Purge fans would lower containment pressure.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part correct. ABN-909 directs you to use Containment Pressure Relief OR Alternating primary plant supply and exhaust fans.

C. Incorrect. 1st part is correct. The transfer tube is closed when suspending fuel movement and not opened again until pressures are approximately equal. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) Spent Fuel Cooling Study Guide Attached w/ Revision # See ABN-909 Comments / Reference SOP-801A Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Spent Fuel Pool Cooling and Cleanup system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.SF1.OB03)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Page 9 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 10 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 068 G2.2.38 Level of Difficulty: 2 Importance Rating 4.5 Liquid Radwaste: Knowledge of conditions and limitations in the facility license.

Question # 93 Plant conditions:

A Batch Liquid Radioactive Effluent Release is planned Based on the above plant conditions, complete the following statements.

1. In accordance with STA-603, Control of Station Radioactive Effluents, review and approval of the batch release ___(1)___ be delegated to the Unit Supervisor.

2. If the quantity of radioactive material in the Liquid Holdup Tank to be released is 11 Curies, it ___(2)___exceed the limit stated in TR 13.10.33, Explosive Gas and Storage Tank Radioactivity Monitoring Program, Liquid Holdup Tanks.

A. (1) can (2) does B. (1) can (2) does NOT C. (1) can NOT (2) does D. (1) can NOT (2) does NOT Answer: A Page 17 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

The question is a match to the K/A as it requires knowledge of conditions in the facility license.

SRO Only:

NUREG 1021, ES-401 Attachment 2 D. Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions. [10 CFR 55.43(b)(4)]

Some examples of SRO exam items for this topic include:

• Process for gaseous/liquid release approvals, i.e., release permits.

• Analysis and interpretation of radiation and activity readings as they pertain to selection of administrative, normal, abnormal, and emergency procedures.

• Analysis and interpretation of coolant activity, including comparison to emergency plan criteria and/or regulatory limits.

Explanation:

A. Correct. 1st part is correct. The responsibility may be delegated by the Shift Manager to the Unit Supervisor. 2nd part is correct per TR 13.10.33, the limit is 10 Curies.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because per TR 13.10.33, the limit is 10 Curies and it were 1 Curie less it would be within the limit.

C. Incorrect. 1st part is incorrect because this responsibility can be designated to a Unit supervisor.

It is plausible because what can and cannot be designated varies on the responsibility of the Shift Manager. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) STA-603 Attached w/ Revision # See TRM Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Spent Fuel Pool Cooling and Cleanup system including interrelations with other systems to include interlocks and control loops.

(LO21.SYS.SF1.OB03)

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 43.1 Page 18 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.1.6 Level of Difficulty: 3 Importance Rating 4.8 Ability to manage the control room crew during plant transients.

Question # 94 Complete the following statements regarding the Shift Technical Advisor (STA) position when entering the ERG network in accordance with ODA-102, Conduct of Operations.

If the designated STA

1. reports to the Control Room 8 minutes after the trip occurred, he/she ___(1)___ within the time requirements of ODA-102.

2. is assigned as a Unit Supervisor when entering the ERG network, the Shift Manager is procedurally required to DIRECT the STA to ___(2)___.

A. (1) is (2) turn over STA duties to another qualified individual B. (1) is (2) be relieved as the Unit Supervisor by another qualified individual C. (1) is NOT (2) turn over STA duties to another qualified individual D. (1) is NOT (2) be relieved as the Unit Supervisor by another qualified individual Answer: B Page 21 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA as it requires demonstration of knowledge of control room watch position requirements during a plant transient by requiring the ability to determine how the STA position shall be manned.

SRO Only:

This question is SRO only as it details an SRO only task of knowledge of the administrative procedures that specify implementation and coordination of the STA position in the control room.

Explanation:

A. Incorrect. 1st part is correct. The STA has up to 10 minutes to report to the control room following an event. 2nd part is incorrect because the designated STA must perform the STA Duties during an event. It is plausible because conducting a turnover of the Unit Supervisor position during an event is not something that is normally performed; however, this situation is specifically delineated in ODA-102.

B. Correct. 1st part is correct (see A). 2nd part is correct. The STA must be relieved as the Unit Supervisor per ODA-102.

C. Incorrect. 1st part is incorrect because the STA has up to 10 minutes to report to the control room following an event. It is plausible because a reasonable amount of time for an STA to get to the control room is 5 minutes which has been exceeded. Also, If he/she were 3 minutes later, it would be correct. 2nd part is incorrect but plausible (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B)

Technical Reference(s) ODA-102 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the operator role in plant operation including the interface with procedures. (LO21.ERG.XG1.OB01)

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 43.5 Page 22 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A G2.1.5 Level of Difficulty: 3 Importance Rating 3.9 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Question # 95 Current plant conditions:

Unit 1 is in Mode 1 Unit 2 is in Mode 4

1. The Operations shift crew is required to have a MINIMUM of ___(1)___ NEOs to satisfy the On-Shift staffing requirements of ODA-102, Conduct of Operations.

2. Per T.S. 5.2.2 Unit Staff, the Operations shift crew composition may be ONE less than the minimum requirements for a period of time NOT TO EXCEED ___(2)___ hours.

A. (1) 8 (2) four B. (1) 4 (2) two C. (1) 4 (2) four D. (1) 8 (2) two Answer: D Page 25 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring the ability to determine plant staffing requirements based on plant conditions.

SRO Only:

NUREG 1021 ES 401 Attachment 2 A. Conditions and limitations in the facility license. [10 CFR 55.43(b)(1)]

Examples of SRO exam items for this topic include:

• Reporting requirements when the maximum licensed thermal power output is exceeded.

• Administration of fire protection program requirements such as compensatory actions associated with inoperable sprinkler systems, fire doors, etc.

• The required actions for not meeting administrative controls listed in Technical Specification (TS)

Section 5 or 6, depending on the facility (e.g., shift staffing requirements).

• National Pollutant Discharge Elimination System (NPDES) requirements, if applicable.

• Processes for TS and FSAR changes.

Explanation:

A. Incorrect. 1st part is correct for the stated conditions, a total of 8 NEOs are required per ODA-102. 2nd part is incorrect but plausible as an operator can work as much as 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in excess of the normal shift without exceeding work hour rules.

B. Incorrect. 1st part is incorrect because for the stated conditions, 8 NEOs are required. It is plausible because ODA-102 states that 4 NEOs are required for Safe shutdown, two for each nd unit when in Modes 1, 2, 3, or 4. 2 part is correct per ODA-102 the operations shift crew composition may be one less than the minimum required in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

C. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct for the stated conditions, a total of 8 NEOs are required per ODA-102. 2nd part is correct (see B).

Technical Reference(s) ODA-102 Attached w/ Revision # See STA-615 Comments / Reference Proposed references to be provided during examination:

Learning Objective: SUMMARIZE the minimum Operations crew required by Tech Specs for any mode of operation. (LO21.RLS.SL1.OB16)

Question Source: Bank #

Modified Bank # ILOT8051 (Note changes or attach parent)

New Question History: Last NRC Exam Page 26 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO 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 55.43 43.5 Page 27 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.2.21 Level of Difficulty: 3 Importance Rating 4.1 Knowledge of pre and post-maintenance operability requirements.

Question # 96 Post maintenance testing is being performed on a safety related pump by performance of a surveillance test. One of the test parameters has exceeded the Alert Limit.

Due to the safety related pump parameter exceeding the Alert Limit, which of the following states ALL of the criteria that are IMMEDIATELY applicable per ODA-308, LCO Tracking Program?

1. Must increase test frequency

2. Must declare the pump INOPERABLE

3. Must perform the surveillance on the other trains pump to determine if a common cause failure exists A. 1 ONLY B. 1, 2 ONLY C. 1, 3 ONLY D. 1, 2, 3 Answer: A Page 34 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

The question matches the K/A as it requires a demonstration of knowledge on post maintenance requirements of equipment including actions which must be taken when the post maintenance testing of that equipment exceeds specified test criteria.

SRO Only:

This question is SRO only as only SROs are required to demonstrate knowledge of how a piece of equipment is dispositioned following testing in which specific test criteria were exceeded in accordance with ODA-308, LCO Tracking Program. This process is collectively application of ODA-308 and the surveillance test program which is part of the facility operating limitations.

Explanation:

A. Correct. When the acceptable range was exceeded, you have automatically exceed the Alert Limit and you are in the Alert Range. The requirements for being in this range are to: Increase test frequency, initiate a condition report and the IST Engineer will determine the cause. The pump may still be operable.

B. Incorrect. Incorrect because you do not have to declare the pump inoperable. It is plausible because if you do not meet the Acceptance Criteria (Action Limit), the pump must be declared inoperable.

C. Incorrect: Incorrect because you are not required to perform the surveillance on the other train pump. It is plausible because it make sense to check the operability of the other train equipment to determine if a common cause failure exists.

D. Incorrect. Incorrect because the only requirement of the ones stated is to increase your test frequency. It is plausible (see A & B).

Technical Reference(s) OPT-201A Attached w/ Revision # See IST-100 Comments / Reference ODA-308-5.5.8 Proposed references to be provided during examination:

Learning Objective: Given the condition of a structure, system or component, INFER the Operability of the structure, system or component. (LO21.ADM.XA5.OB02)

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 Page 35 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 55.43 43.2 Page 36 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.2.20 Level of Difficulty: 3 Importance Rating 3.8 Knowledge of the process for managing troubleshooting activities.

Question # 97 Given the following conditions:

Troubleshooting is in progress under a Work Order for an installed Spare 118 VAC Inverter to replace a capacitor Subsequently:

During Troubleshooting it is determined that several other Inverter internal components must be replaced Complete the statement below describing the process to complete troubleshooting and repair activities on the installed Spare 118 VAC Inverter.

The existing Work Order must undergo a(n) ___(1)___, the Work Order must be re-impacted and the ___(2)___ must authorize continuing work.

A. (1) editorial change (2) Shift Manager B. (1) editorial change (2) RWO Supervisor C. (1) revision (2) Shift Manager D. (1) revision (2) RWO Supervisor Answer: C Page 42 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the troubleshooting process and what actions must be taken via work control process once it is determined that components must be replaced.

SRO Only:

This question is SRO only as only SROs are required to demonstrate knowledge of how the work control process works with regard to impacting work orders and authorizing work.

Explanation:

A. Incorrect. 1st part is incorrect but plausible because the work order is only adding components that need to be replaced within the same piece of equipment; it is plausible to think that if the major piece of equipment under maintenance does not change then a revision is not required.

2nd part is correct and plausible when paired with an editorial change because it is reasonable to think the Shift Manager must be required to authorize the continuation of work after any changes to a work order have been performed, even an editorial change.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect but plausible because The RWO Supervisor is responsible for ensuring appropriate reviews and signatures are completed and initial and date page one of the WO on the discipline line of the appropriate revision column for both technical and safety reviews have been completed.

C. Correct. 1st part is correct, a revision is required as the scope of work has changed and now additional components must be replaced within the inverter. 2nd part is correct; the Shift Manager is responsible for authorizing the continuation of work after a revision to a work order.

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) STI-606.01 Attached w/ Revision # See STA-202 Comments / Reference Proposed references to be provided during examination:

Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies Question Source: Bank #

Modified Bank # 2014 NRC Exam Q96 (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 Page 43 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 55.43 43.5 Page 44 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.3.12 Level of Difficulty: 2 Importance Rating 3.7 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.

Question # 98 Upper Internals Lift preparations are being made.

All non-essential personnel are required to leave Containment elevations of ___(1)___ prior to the lift.

The Upper Internals Lift ___(2)___ required by the FSAR to be observed by a Licensed Fuel Handling SRO.

A. (1) 832 through 860 (2) is NOT B. (1) 860 and above (2) is NOT C. (1) 832 through 860 (2) is D. (1) 860 and above (2) is Answer: D Page 52 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

The question is a K/A match as it requires the applicant to be knowledgeable of radiation worker practices during the Refueling Operation of upper internals lift.

SRO Only:

NUREG 1021, ES-401 Attachment 2 G. Fuel handling facilities and procedures. [10 CFR 55.43(b)(7)]

Some examples of SRO exam items for this topic include: 1) Refuel floor SRO responsibilities. 2)

Assessment of fuel handling equipment surveillance requirement acceptance criteria. 3)

Prerequisites for vessel disassembly and reassembly. 4) Decay heat assessment. 5) Assessment of surveillance requirements for the refueling mode. 6) Reporting requirements. 7) Emergency classifications.

K/A G2.3.12 does NOT have a 10CFR55.43 tie in the K/A catalog. The following is justification for allowing this K/A to be tested on the exam (SRO Initial Training Task List Attached to question):

NUREG 1021, ES-401 Attachment 2 The SRO-only test items are required to be tied to one of the 10 CFR 55.43(b) items. However, if a licensee desires to evaluate a knowledge/ability that is not tied to one of the 10 CFR 55.43(b) items, then the licensee can classify the knowledge/ability as unique to the SRO position provided that there is documented evidence that ties the knowledge/ability to the licensees SRO job position duties in accordance with the systematic approach to training (SAT) (see attached SRO Initial Training Task List).

Explanation:

A. Incorrect. Part 1 is incorrect as described in C below. Part 2 is incorrect as described in B below.

B. Incorrect. Part 1 is correct as described in D below. Part 2 is incorrect in accordance with RFO-102, it is plausible because numerous other activities such as the vessel head lift and Upper Internals replacement are not Core Alterations and thus would not require observation throughout the evolution by the SRO.

C. Incorrect. Part 1 is incorrect but plausible as the Refueling Operating floor elevation is 832. It is plausible to believe that as the upper internals may breach the water that 832 though 860 should be cleared of non-essential personnel. However, this is not the procedural requirement as adequate shielding exists for several work areas below 860 elevation but do not in the elevations at 860 and above. Part 2 is correct as described in D below.

D. Correct. Part 1 is correct in accordance with RFO-102. Part 2 is correct in accordance with RFO-102 and the FSAR.

Technical Reference(s) RFO-101 Attached w/ Revision # See RFO-102 Comments / Reference FSAR Table 13.1-2 Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of conducting fuel Page 53 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 handling. (LO21RFOFH2OB101)

Question Source: Bank #

Modified Bank # 2016 NRC Exam Q98 (Note changes or attach parent)

New Question History: Last NRC Exam 2016 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 43.7 Page 54 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 xamination Outline Cross-reference: Level RO SRO Tier 3 Grou KIA G2.4.11 Im ortance Ratin 4.2 Question # 99

• Unit 1 is respondi to a plant transient in an ABN

• Shift Manager is in t daily POD meeting at the MSC

• The Unit 1 US has bee ssigned Command Function In accordance with ODA-407, Oper complete the following statements.

1.

copy.

2. A deviation from the ABN is required; the Unit The Unit 2 US _(2)_ authoriized to concur wi A. (1) working (2) is NOT B. (1) working (2) is C. (1) controlled (2) is NOT D. (1) controlled (2) is Answer: D Page 63of75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 T

• question matches the KA by requiring knowledge of how to physically utilize abnormal proc dures in the control room and if SM approval is required to deviate from the ABN during use.

NUREG 10 j, ES-401Attachment2 E. Assessme of facility conditions and selection of appropriate procedures during normal, abnormal, and ergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.4 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and the 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed . On rea of SRO level knowledge (with respect to selecting a procedure) is knowledge of the conten of the procedure versus knowledge of the procedure's overall mitigative strategy or purpose.

The applicant's knowledge can e evaluated at the level of 10 CFR 55.43(b)(5) by ensuring that the additional knowledge of the proc ure's content is required to correctly answer the written test item, for example:

• Knowledge of when to implement achments and appendices, including how to coordinate these items with procedure steps.

• Knowledge of diagnostic steps and de-~,-..........-oints in the emergency operating procedures (EOP) that involve transitions to event specific Cedures or emergency contingency procedures.

• Knowledge of administrative procedures th ify hierarchy, implementation, and/or coordination of.plant normal, abnormal, and cy procedures.

Explanation:

8 A. Incorrect. 1 part is incorrect because per ODA-407, 1UJ1llll""ules of Usage: During performance of Abnormal Operating Procedures, it is d to write on the control copy as a log or place keeping tool. It is plausible becaus ot the normal practice.

2nd part is incorrect because when a deviation is required, a must approve the deviation and a second SRO must concur. It is plausible beca e Shift Manager is preferred, but not required. Therefore, if thought the shift mana s required then Unit 2 US would not be authorized to concur.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct.

authorized to concur with the deviation. Shift Manager permission for a preferred, is not a requirement.

C. Incorrect. 1st part is correct. For Abnormal Operating Procedures, it is desirab write on the control copy. 2nd part is incorrect but plausible (see A).

D. Correct. 1st art is correct see C . 2nd art is correct see B .

Technical Reference s ODA-407 1--~~~~~~'--'-_,_-+-~~~~~~~~~~~~~~~

Attached w/ Revision See Comments I Reference Proposed references to be provided during examination: ~~~~~~~~~~~~~~~~

Learning Objective: STATE requirements for Conduct of Operations in accordance with ODA-102, Page 64 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 ODA-407 and Ops Guideline 3 Bank#

Modified Bank# - - - - - - - - (Note changes or attach parent)

New x Last NRC Exam Question Cognitive Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content:

43.5 Page 65of75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A G2.4.29 Level of Difficulty: 4 Importance Rating 4.4 Knowledge of the emergency plan.

Question # 100 Given the following conditions:

The Emergency Response Organization has been activated A Site Area Emergency has been declared and a Site Evacuation is in progress The Emergency Coordinator is in the Emergency Operations Facility (EOF)

Which of the following actions may be delegated by the Emergency Coordinator?

A. Authorizing re-entry into evacuated areas.

B. Making Protective Action Recommendations to off-site authorities.

C. Activating and directing the CPNPP Emergency Response Organization.

D. Approving Notification Message Forms prior to sending.

Answer: C Page 68 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 K/A Match:

This question matches the KA by requiring knowledge of the emergency plan and any specific actions that may be delegated by the Emergency Coordinator.

SRO Only:

NUREG 1021, ES-401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]

This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

The applicants knowledge can be evaluated at the level of 10 CFR 55.43(b)(5) by ensuring that the additional knowledge of the procedures content is required to correctly answer the written test item, for example:

• Knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps.

• Knowledge of diagnostic steps and decision points in the emergency operating procedures (EOP) that involve transitions to event specific sub-procedures or emergency contingency procedures.

• Knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

Explanation:

A. Incorrect. Plausible if thought that the Operations Support Center Manager can authorize re-entry as the position controls ERDC Teams.

B. Incorrect. Plausible because PARS are reviewed by Radiation Protection prior to sending, however, this function cannot be delegated.

C. Correct. As listed in EPP-109, Step 4.1.1 and is a responsibility of the Recovery Manager when the Recovery Organization is formed.

D. Incorrect. Plausible because the EOF Communicator sends the messages, however, the Emergency Coordinator must approve Notification Message Forms.

Technical Reference(s) EPP-109 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Question Source: Bank # 2013 NRC Exam Q99 Modified Bank # (Note changes or attach parent)

Page 69 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

ES-401 CPNPP NRC 2017 SRO Written Exam Worksheet Form ES-401-5 New Question History: Last NRC Exam 2013 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 43.5 Page 70 of 75 CPNPP NRC 2017 SRO Written Exam Worksheet 91-100 Rev. 3

CPNPP NRC 2017 SRO/RO Written Exam Reference List

1. NRC Generic Fundamentals Equation Sheet

2. TDM-804B, Equipment Data, Tank Height vs Volume, VCT 2-01

3. TDM-401A, Turbine/Generator Limit Curves, Reactive Capability Curve

4. Steam Tables CPNPP NRC 2017 SRO & RO Written Exam Reference Package Rev. 3

GENERIC FUNDAMENTALS EXAMINATION EQUATIONS AND CONVERSIONS HANDOUT SHEET EQUATIONS



Q  pT mc P = Po10SUR(t)



Q 

mh P = Poe(t/)

 A = Aoe-t Q UAT CRS/D = S/(1 - Keff)

  m Q

3

 Nat Circ CR1(1 - Keff1) = CR2(1 - Keff2) 2 T  m  Nat Circ 1/M = CR1/CRX Keff = 1/(1 - ) A = r 2

= (Keff - 1)/Keff F = PA SUR = 26.06/ m = Av eff W 

mP Pump eff E = IR 5 eff

 Thermal Efficiency = Net Work Out/Energy In 1  eff g(z2 - z1) + (v22 - v12) + (P2 - P1) + (u2 - u1) + (q - w) = 0 5* = 1 x 10-4 sec gc 2gc eff = 0.1 sec-1 (for small positive ) gc = 32.2 lbm-ft/lbf-sec2 2 2 DRW  tip / avg CONVERSIONS 1 Mw = 3.41 x 106 Btu/hr 1 Curie = 3.7 x 1010 dps 1 hp = 2.54 x 103 Btu/hr 1 kg = 2.21 lbm 1 Btu = 778 ft-lbf 1 galwater = 8.35 lbm (C = (5/9)((F - 32) 1 ft3water = 7.48 gal (F = (9/5)((C) + 32 CPNPP NRC 2017 SRO & RO Written Exam Reference Package Rev. 3

CPNPP PROCEDURE NO.

TECHNICAL DATA MANUAL UNIT 2 TDM-804B REVISION NO. 3 EQUIPMENT DATA PAGE 14 OF 30 TANK HEIGHT VS VOLUME INFORMATION USE INSIDE DIAMETER: 89.500 INCHES TOTAL INSIDE LENGTH OF TANK: 121.740 IN.

HEIGHT OF TANK CYLINDER: 80.00 INCHES DEPTH OF ELLIPTICAL HEADS: 20.870 INCHES LEVEL INDICATION BEGINS AT 26.230 INCHES LEVEL INDICATION ENDS AT 95.520 INCHES LIQUID LEVEL LIQUID LEVEL LIQUID LEVEL HEIGHT VOLUME IND. HEIGHT VOLUME IND. HEIGHT VOLUME IND.

(INCHES) (GALLONS) (%) (INCHES) (GALLONS) (%) (INCHES) (GALLONS) (%)

26.23 524.9 0.00 26.92 543.8 1.00 27.62 562.6 2.00 28.31 581.5 3.00 29.00 600.4 4.00 29.69 619.3 5.00 30.39 638.1 6.00 31.08 657.0 7.00 31.77 675.9 8.00 32.47 694.7 9.00 33.16 713.6 10.00 33.85 732.5 11.00 34.54 751.4 12.00 35.24 770.2 13.00 35.93 789.1 14.00 36.62 808.0 15.00 37.32 826.8 16.00 38.01 845.7 17.00 38.70 864.6 18.00 39.40 883.5 19.00 40.09 902.3 20.00 40.78 921.2 21.00 41.47 940.1 22.00 42.17 958.9 23.00 42.86 977.8 24.00 43.55 996.7 25.00 44.25 1015.6 26.00 44.94 1034.4 27.00 45.63 1053.3 28.00 46.32 1072.2 29.00 47.02 1091.0 30.00 47.71 1109.9 31.00 48.40 1128.8 32.00 49.10 1147.6 33.00 49.79 1166.5 34.00 50.48 1185.4 35.00 51.17 1204.3 36.00 51.87 1223.1 37.00 52.56 1242.0 38.00 53.25 1260.9 39.00 53.95 1279.7 40.00 54.64 1298.6 41.00 55.33 1317.5 42.00 56.02 1336.4 43.00 56.72 1355.2 44.00 57.41 1374.1 45.00 58.10 1393.0 46.00 58.80 1411.8 47.00 59.49 1430.7 48.00 60.18 1449.6 49.00 60.88 1468.5 50.00 61.57 1487.3 51.00 62.26 1506.2 52.00 62.95 1525.1 53.00 63.65 1543.9 54.00 64.34 1562.8 55.00 65.03 1581.7 56.00 65.73 1600.6 57.00 66.42 1619.4 58.00 67.11 1638.3 59.00 67.80 1657.2 60.00 68.50 1676.0 61.00 69.19 1694.9 62.00 69.88 1713.8 63.00 70.58 1732.6 64.00 71.27 1751.5 65.00 71.96 1770.4 66.00 72.65 1789.3 67.00 73.35 1808.1 68.00 74.04 1827.0 69.00 74.73 1845.9 70.00 75.43 1864.7 71.00 76.12 1883.6 72.00 76.81 1902.5 73.00 77.50 1921.4 74.00 78.20 1940.2 75.00 78.89 1959.1 76.00 79.58 1978.0 77.00 80.28 1996.8 78.00 80.97 2015.7 79.00 81.66 2034.6 80.00 82.35 2053.5 81.00 83.05 2072.3 82.00 83.74 2091.2 83.00 84.43 2110.1 84.00 85.13 2128.9 85.00 85.82 2147.8 86.00 86.51 2166.7 87.00 87.21 2185.6 88.00 87.90 2204.4 89.00 88.59 2223.3 90.00 89.28 2242.2 91.00 89.98 2261.0 92.00 90.67 2279.9 93.00 91.36 2298.8 94.00 92.06 2317.6 95.00 92.75 2336.5 96.00 93.44 2355.4 97.00 94.13 2374.3 98.00 94.83 2393.1 99.00 95.52 2412.0 100.00 NOTE: Any changes to this table should be routed for review for impact by Core Performance Engineering.

TITLE: VOLUME CONTROL TANK 2-01 SOURCE: TE 92-1504, TE 92-2225 CPNPP NRC 2017 SRO & RO Written Exam Reference Package Rev. 3

CPNPP PROCEDURE NO.

TECHNICAL DATA MANUAL UNIT 1 TDM-401A TURBINE/GENERATOR INFORMATION USE l LIMIT CURVES PAGE 5 OF 13 l REVISION NO. 6 REACTIVE CAPABILITY CURVE Capability curve Limitations due to rotor vibration

& core heating CP UNIT 1 MW AND MVAR LIMITS FOR NUCLEAR SAFETY AND PLANT RELIABILITY

! Unit 1 gross MWs varies between 1236 MW (summer) and 1263 MW (winter)

! 6900 Volt bus limits are 6480 to 7150 volts

! 345 kV switchyard limits are 340 to 361 kV (Transmission limits have been more restrictive)

! Generator field current is limited to 9450 amps. l

! Generator Hydrogen Pressure maximum/minimum operating range is 65 PSIG to 45 PSIG **.

Generator Capability OM Display 1ZA60H242 may be referenced for limitations associated with the 65 psig to 45 psig operating range.

TITLE: REACTIVE CAPABILITY CURVE SOURCE: EV-CR-2014-011395-8, ODMI CPNPP NRC 2017 SRO & RO Written Exam Reference Package Rev. 3