ML12158A566

CP-2012-06 Draft Written Exam

ML12158A566
Person / Time
Site:	Comanche Peak
Issue date:	06/11/2012
From:	NRC Region 4
To:	Luminant Generation Co
References
Download: ML12158A566 (413)

Text

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 K2.01 Importance Rating 3.1 Reactor Coolant Pump System: Knowledge of bus power supplies to the following: RCPs Proposed Question: Common 1 Given the following condition:

Unit 1 experiences a loss of Non-Safeguards Bus 1A3 while operating at 700 MWe load.

Which of the following automatic actions will occur?

A. Turbine Runback due to loss of power to Condensate Pump 1-01.

B. Reactor Trip due to loss of Reactor Coolant Pump 1-03.

C. Turbine Trip due to loss of Turbine Plant Cooling Water Pump 1-01.

D. Reactor Trip due to loss of Rod Drive Motor Generator Set 1-01.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because power is lost to Condensate Pump 1-01 and a Turbine Runback would initiate to 60% power, however, the Unit is already < 60%.

B. Correct. Unit 1 is greater than 48% power and in this condition a Reactor Trip will occur when one RCP is lost.

C. Incorrect. Plausible because power is lost to TPCW Pump 1-01, however, the standby pump will AUTO start and prevent the Turbine from tripping.

D. Incorrect. Plausible because the Rod Drive Motor Generator Set 1-01 is powered from 1B3, however, 1B4 remains energized which powers Rod Drive Motor Generator Set 1-02.

Technical Reference(s) ALM-0064A, 1-ALB-6D, Window 1.9 Attached w/ Revision # See ALM-0063A, 1-ALB-6C, Window 4.2 Comments / Reference Bus 1A3 & 1B3 Loads Proposed references to be provided during examination: None Learning Objective: DEMONSTRATE an understanding of the components of the Reactor Coolant System including interrelations with other systems to include interlocks and control loops.

Page 1 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # SYS.RC1.OB03.009 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3, 5, 7 55.43 Comments /

Reference:

From ALM-0063A, 1-ALB-6C, Window 4.2 Revision # 5 Page 2 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0064A, 1-ALB-6D, Window 1.9 Revision # 6 Page 3 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Bus 1A3 & 1B3 Loads Revision # N/A 1A3 COMPT CUB 2 TBX-RCPCPX-03, REACTOR COOLANT PUMP 1-03, E1-0032 sh 55 CUB 3 CP1-TWAPTP-01, TURBINE BUILDING COOLING WATER PUMP 1-01, E1-0032 sh 37 CUB 4 CP1-CWAPCW-03, CIRCULATING WATER PUMP 1-03, E1-0032 sh 44 CUB 5 Instrumentation CUB 6 CP1-COAPCP-01, CONDENSATE PUMP 1-01, E1-0032 sh 33 CUB 7 Spare CUB 8 CP1-EPTRNT-03, TRANSFORMER T1B3, E1-0032 sh 23 1B3 COMPT 7B Space 7C MCC 1B3-2, E1-0015 7D 1-SC18D001, SHAFT LIFT OIL PUMP, E1-0034 sh 22 8B Space 8C TBX-ESELMG-01, CONTROL ROD MG SET #1, E1-0034 sh 40 8D 1-SC10D013, AUXILIARY OIL PUMP C, E1-0034 sh 18 Page 4 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 004 K3.04 Importance Rating 3.4 Chemical and Volume Control System: Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: RCPs Proposed Question: Common 2 Given the following conditions:

Unit 1 is in MODE 1.

Centrifugal Charging Pump 1-01 is providing Charging flow.

An Instrument Air tubing break has occurred on 1-HCV-0182, RCP SEAL WTR PRESS CTRL valve.

All other components supplied by Instrument Air are functioning properly.

Which of the following are the effects on the Reactor Coolant Pumps?

Seal Injection flow will A. increase and LOW SEAL WTR BRG TEMPs (Pump Bearings) will decrease.

B. increase and LOW SEAL WTR BRG TEMPs (Pump Bearings) will increase.

C. decrease and LOW SEAL WTR BRG TEMPs (Pump Bearings) will decrease.

D. decrease and LOW SEAL WTR BRG TEMPs (Pump Bearings) will increase.

Proposed Answer: D Page 5 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because if HCV-182 failed closed, Seal Injection flow would increase (less Charging flow and more Seal Injection flow) and the bearing temperature would decrease, however, HCV-182 fails open on Loss of Instrument Air.

B. Incorrect. Plausible because the decrease in Seal Injection flow will result in an increase in bearing temperature, however, HCV-182 fails open which lowers back pressure on Seal Injection and results in less flow to the RCP Pump bearings.

C. Incorrect. Plausible because actual Seal Injection flow will decrease, however, the decrease in Seal Injection flow will result in an increase in bearing temperature.

D. Correct. HCV-182 fails open on Loss of Instrument Air and Seal Injection flow decreases.

Additionally, the decrease in Seal Injection flow will result in an increase in bearing temperature.

Technical Reference(s) ABN-101, Steps 7.3.3 & 7.3.4 Attached w/ Revision # See ABN-301, Attachment 1 Comments / Reference LO21.SYS.CS1, Slide #8 Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Reactor Coolant System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3, 10 55.43 Page 6 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-101, Step 7.3.3 Revision # 10 Page 7 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-101, Step 7.3.4 Revision # 10 Comments /

Reference:

From ABN-301, Attachment 1 Revision # 11 Page 8 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LO21.SYS.CS1, Slide #8 Revision # 05/25/11 Page 9 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 K4.05 Importance Rating 2.5 Residual Heat Removal System: Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:

Relation between RHR flowpath and refueling cavity Proposed Question: Common 3 Given the following conditions:

Unit 1 is in MODE 6.

Residual Heat Removal (RHR) Train B is providing Shutdown Cooling.

Charging and Letdown are in their normal MODE 6 alignment maintaining a steady level in the Reactor Vessel.

RHR Train A is being aligned per SOP-102A, Residual Heat Removal System, for filling the Refueling Cavity.

The following actions have been performed:

1/1-APPRH1, RHRP 1 is in PULLOUT.

1/1-8701A, RHRP 1 HL RECIRC ISOL VLV, is CLOSED.

1/1-8812A, RWST TO RHRP 1 SUCT VLV, is OPEN.

1/1-8809A, RHR TO CL 1 & 2 INJ ISOL VLV, is CLOSED.

1/1-8716A, RHRP 1 XTIE VLV, is OPEN.

1/1-8840, RHR TO HL 2 & 3 INJ ISOL VLV, is OPEN.

1/1-8702A, RHRP 1 HL RECIRC ISOL VLV, remains CLOSED.

The Refueling Cavity level is now RISING at a steady rate.

Which of the following is responsible for the level rise?

A. Leakage past 1-8809A, RHR TO CL 1 & 2 INJ ISOL VLV, is occurring.

B. 1-PK-131, LTDN HX OUT PRESS CTRL, has failed to 100% demand.

C. Leakage past 1-HCV-0606, RHR HX 1-01 FLO CTRL VLV, is occurring.

D. 1-FK-121, CCP CHRG FLO CTRL, has failed to 0% demand.

Proposed Answer: C Page 10 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible if thought that this valve leaking would raise level in the Refueling Cavity, however, a flow path already exists for flow from the RWST and requires 1-HCV-0606 still to leak by for Refueling Cavity level to rise B. Incorrect. Plausible since 1-PCV-131 is used to control Letdown pressure and flow from RHR, but having the controller fail to 100% demand would increase Letdown flow and Refueling Cavity level would lower.

C. Correct. As outlined in the CAUTION of SOP-102A, Step 5.7.1 (OE for CPNPP #SMF-05-1381).

D. Incorrect. Plausible since 1-FK-121 controls the position of 1-FCV-121, which controls Charging flow, however, if 1-FK-121 failed at 0% demand, 1-FCV-121 would go closed. This would reduce Charging flow and cause Refueling Cavity level to lower.

Technical Reference(s) SOP-102A, Step 5.7.1 Attached w/ Revision # See OP51.SYS.RH1.FG01 Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Residual Heat Removal System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7, 10 55.43 Page 11 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-102A, Step 5.7.1 Revision # 18 Page 12 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From OP51.SYS.RH1.FG01 Revision #

Page 13 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From OP51.SYS.RH1.FG01 Revision #

T-125 T

TO PRT 8117 TO BTRS 8149A FC FC 8149B 8160 8152 TCV-381B HCV 128 8149C FROM T RHR T-127 REGEN HX LCV LCV 460 459 LD FROM T LOOP 3 INT LEG T-126 M M 8147 8105 8106 ALT CHRG LOOP 1 COLD LEG 8146 NORM CHRG LOOP 4 COLD LEG 8145 AUX SPRAY Page 14 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 G 2.4.49 Importance Rating 4.6 Residual Heat Removal System: Emergency Procedures/Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls Proposed Question: Common 4 Given the following conditions:

A Small Break Loss of Coolant Accident (LOCA) has occurred on Unit 2.

EOS-1.2B, Post LOCA Cooldown and Depressurization, is in progress.

Reactor Coolant System (RCS) pressure is 1100 psig and slowly lowering.

Containment pressure is 4 psig and slowly rising.

All Reactor Coolant Pumps have been stopped.

RCS cooldown to Cold Shutdown is in progress.

RCS subcooling is 70°F and improving.

Safety Injection (SI) and SI sequencers have been RESET.

ECCS status is as follows:

Both Centrifugal Charging Pumps are running.

1-FI-917, CCP SI FLO, is 400 GPM and stable.

1-FI-121A, CHRG FLO, is 32 GPM and stable.

Both Safety Injection Pumps are running.

1-FI-918, SIP 1 DISCH FLO, is 350 GPM and stable.

1-FI-922, SIP 2 DISCH FLO, is 350 GPM and stable.

Both Residual Heat Removal (RHR) Pumps are in Standby.

The crew is preparing to depressurize the RCS when pressure rapidly lowers to 50 psig and Containment pressure rapidly raises to 25 psig.

Which of the following is required?

A. Manually actuate Safety Injection.

B. Manually actuate Containment Spray.

C. Manually restart the RHR Pumps.

D. Perform EOP-0.0B, Reactor Trip or Safety Injection, Attachment 2, Safety Injection Actuation Alignment.

Page 15 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed Answer: C Explanation:

A. Incorrect. Plausible because actuating Safety Injection would normally start all ECCS Pumps, however, once the SI and SI Sequencers have been RESET manual start of the ECCS Pumps is required.

B. Incorrect. Plausible because Containment pressure increasing to greater than 18.2 psig would require entry into FRZ-0.1B, Response to High Containment Pressure, for Containment Spray verification, however, the pumps should have started automatically at 18.2 psig, manual actuation is not required.

C. Correct. This is the prescribed action per EOS-1.2B, Step 9, CAUTION Bases.

D. Incorrect. Plausible because this would appear correct if mistakenly believed that SI actuated again once it was RESET, however, SI will not actuate again and entry into EOP-0.0B is not required.

Technical Reference(s) EOS-1.2B, Step 9, CAUTION Bases Attached w/ Revision # See EOS-1.2B, Step 9 and CAUTION Comments / Reference EOP-0.0B, Attachment 2 Proposed references to be provided during examination: None Learning Objective: Given a set of plant conditions, IDENTIFY the proper transitions through/out of EOS-1.2, Post LOCA Cooldown and Depressurization.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 16 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.2B, Step 9, CAUTION Bases Revision # 8 Page 17 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.2B, Step 9 and CAUTION Revision # 8 Page 18 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0B, Attachment 2 Revision # 8 Page 19 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006 K5.10 Importance Rating 2.5 Emergency Core Cooling System: Knowledge of the operational implications of the following concepts as they apply to ECCS: Theory of thermal stress Proposed Question: Common 5 Given the following conditions:

FRP-0.1B, Response to Imminent Pressurized Thermal Shock Condition, Step 7, (Check If ECCS Can Be Terminated), is in progress.

NO Reactor Coolant Pumps (RCPs) are running.

Adequate Reactor Coolant System (RCS) subcooling to terminate ECCS does NOT exist.

Adequate RCS subcooling to restart an RCP does exist.

Why is a RCP started in this condition?

An RCP restart establishes A. forced flow in order to provide improved temperature control for the RCS Temperature Soak.

B. improved mixing of the RCS with ECCS injection to reduce core T and lessen the thermal stress across the Cold Leg nozzle.

C. forced flow to lower the temperature at the core outlet and increase subcooling in order to terminate ECCS.

D. improved mixing of the RCS with ECCS injection to raise the water temperature in the downcomer and lessen the thermal stress across the Vessel wall.

Proposed Answer: D Page 20 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because temperature control is improved with forced circulation, however, the desired mixing is the reason for the RCP restart.

B. Incorrect. Plausible because improved mixing is the reason for the RCP restart, however the area for concern of flaw propagation is not the Cold Leg nozzle but rather the Reactor Vessel wall.

C. Incorrect. Plausible because forced circulation would reduce core outlet temperature and improve subcooling, however, that is not the reason for the RCP restart.

D. Correct. Improved mixing of the relatively warm RCS fluid with the cold ECCS injection is needed to raise downcomer temperature and lessen the thermal stress across the Reactor Vessel wall.

Technical Reference(s) FRP-0.1A, Step 7 Attached w/ Revision # See FRP-0.1A, Step 7 Bases Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a procedural Step, Note, or Caution, DISCUSS the reason or basis for the Step, Note, or Caution in FRP-0.1A/B, Response to Imminent Pressurized Thermal Shock Condition.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10, 14 55.43 Page 21 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Step 7 Revision # 8 Page 22 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Step 7 Bases Revision # 8 Page 23 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Step 7 Bases Revision # 8 Page 24 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006 A4.04 Importance Rating 3.7 Emergency Core Cooling System: Ability to manually operate and/or monitor in the control room: RHRS Proposed Question: Common 6 Which of the following describes the valves that MUST be CLOSED in order to manually OPEN 1-8811A, CNTMT SUMP TO RHRP 1 SUCT ISOL VLV?

A. 1-8812A, RWST TO RHRP 1 SUCT VLV, and BOTH 1-8701A, RHRP1 HL RECIRC ISOL VLV, AND 1-8702A, RHRP1 HL RECIRC ISOL VLV.

B. 1-8812A, RWST TO RHRP 1 SUCT VLV, and EITHER 1-8701A, RHRP1 HL RECIRC ISOL VLV, OR 1-8702A, RHRP1 HL RECIRC ISOL VLV.

C. 1-8804A, RHRP 1 TO CCP SUCT VLV, and BOTH 1-8701A, RHRP1 HL RECIRC ISOL VLV, AND 1-8702A, RHRP1 HL RECIRC ISOL VLV.

D. 1-8804A, RHRP 1 TO CCP SUCT VLV, and EITHER 1-8701A, RHRP1 HL RECIRC ISOL VLV, OR 1-8702A, RHRP1 HL RECIRC ISOL VLV.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because closing all these valves will allow 1-8811A to be closed manually, but both 1-8702A and 1-8701A need not be closed to allow this.

B. Correct. This is the proper interlock logic for opening 1-8811A.

C. Incorrect. Plausible because 1-8701A/1-8702A are part of the interlock function, however, 1-8804A is not interlocked to 1-8811A and only one of the RHR Recirc Isolation Valves need be open.

D. Incorrect. Plausible because the second half of answer will allow 1-8811A to be closed, however, 1-8804A is not interlocked to 1-8811A.

Technical Reference(s) RHR Study Guide, Page 16 Attached w/ Revision # See EOS-1.3A, Step 3.a RNO Comments / Reference Proposed references to be provided during examination: None Learning Objective: DEMONSTRATE an understanding of the components of the Emergency Core Cooling System including interrelations with other systems to include interlocks and control loops.

Question Source: Bank # SYS.SI1.OB03.010 Modified Bank # (Note changes or attach parent)

New Page 25 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /

Reference:

From RHR Study Guide, Page 16 Revision # 10/20/11 The Containment Sump to RHR Pump Suction Isolation Valves are motor-operated valves which are operated from CB-04. Valve u-8811A receives power from uEB3-2 and valve u-8811B receives power from uEB4-2.

Opening the Train A valve using the Main Control Board switch requires the following interlocks be met:

RWST to RHR Pump Suction Valve (u-8812A) must be CLOSED, and One of the RHR Pump Hot Leg Recirculation Isolation Valve (u-8701A or u-8702A) must be CLOSED, and The Main Control Board switch in the OPEN position Page 26 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.3A, Step 3a RNO Revision # 8 Page 27 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.3A, Step 3a RNO Revision # 8 Page 28 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007 K1.01 Importance Rating 2.9 Pressurizer Relief/Quench Tank System: Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems: Containment system Proposed Question: Common 7 Given the following conditions:

A Unit 1 Reactor Trip has occurred.

EOP-0.0A, Reactor Trip or Safety Injection, is in progress.

One Pressurizer Safety Valve has stuck partially open.

Pressurizer Relief Tank (PRT) pressure is 32 psig and rising rapidly.

Containment pressure is 0.3 psig and stable Which of the following describes the highest PRT pressure that will exist just prior to Containment pressure rising due to this event?

A. 76.4 psig.

B. 85.4 psig.

C. 91.1 psig.

D. 114.8 psig.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because it is 91 psig minus 14.7 psi and taking into account 0.3 psig inside Containment, yields 76.6 psig. 76.4 psig is just prior to the rupture disc rupturing.

B. Incorrect. Plausible because 100 psig is the design pressure of the PRT minus 14.7 psi and taking into account 0.3 psi inside Containment, yields a value of 85.6 psig. 85.4 psig is just prior to the rupture disc rupturing.

C. Correct. This is the pressure just prior to the rupture disc on the PRT rupturing taking into account 0.3 psig inside Containment as the rupture disc ruptures at 91 psid.

D. Incorrect. Plausible because 100 psig is the design pressure of the PRT plus 14.7 psi and taking into account 0.3 psig inside Containment, yields a value of 115.0 psig. 114.8 psig is just prior to the rupture disc rupturing.

Technical Reference(s) SOP-109A, Section 4.2 Attached w/ Revision # See Comments / Reference Page 29 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: Steam Tables Learning Objective: DEMONSTRATE an understanding of the components of the Reactor Coolant System including interrelations with other systems to include interlocks and control loops.

Question Source: Bank # SYS.RC1.OB03.006 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments /

Reference:

From SOP-109A, Section 4.2 Revision # 12 Page 30 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 008 A2.03 Importance Rating 3.0 Component Cooling Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low CCW temperature Proposed Question: Common 8 Given the following conditions:

Unit 1 is in MODE 1.

Station Service Water (SSW) Pump 1-01 has tripped.

Component Cooling Water (CCW) Pump 1-02 automatically started.

CCW Heat Exchanger 1-01 outlet temperature is 123°F and rising.

Which of the following actions is required per ABN-501, Station Service Water System Malfunction?

A. Isolate the Train A CCW Safeguards Loop.

B. Secure Component Cooling Water Pump 1-01.

C. Cross-tie Unit 1 SSW Trains to supply cooling to CCW Train A.

D. Cross Tie Unit 1 and Unit 2 Train A SSW.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because this would remove any Non-Safeguards heat loads being carried by the CCW Pump, however, ABN-501 requires that the CCW Pump be secured.

B. Correct. ABN-501 requires that the affected train CCW Pump be secured if the CCW Heat Exchanger outlet temperature exceeds 122°F.

C. Incorrect. Plausible because the CCW Trains are normally cross-tied via the Non-Safeguards Loop, however, SSW Trains are not cross-tied.

D. Incorrect. Plausible because this is a possible action to be taken in the event of a complete loss of SSW on a Unit, however, with one train of SSW available this action would not be taken.

Technical Reference(s) ABN-501, Step 2.3.6.b RNO Attached w/ Revision # See ABN-501, Step 5.3.7.a RNO Comments / Reference Proposed references to be provided during examination: None Page 31 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE the response to Station Service Water Pump Trip in accordance with ABN-501, Station Service Water System Malfunction.

Question Source: Bank # ABN.501.OB01.002 Modified Bank # (Note changes or attach parent)

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

Reference:

From ABN-501, Step 2.3.6.b RNO Revision # 9 Page 32 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Step 5.3.7.a RNO Revision # 9 Page 33 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010 A1.05 Importance Rating 2.8 Pressurizer Pressure Control System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: Pressure effect on level Proposed Question: Common 9 Given the following conditions:

Unit 2 has been tripped due to a Steam Generator Tube Rupture (SGTR) on Steam Generator 2-02.

All Reactor Coolant Pumps are running.

Steam Generator 2-02 has been isolated.

EOP-3.0B, Steam Generator Tube Rupture, is in progress.

Steps to verify normal Pressurizer Spray available, deenergize all Pressurizer Heaters and initiate maximum Pressurizer Spray are being performed.

Which of the following identifies why these actions are performed per EOP-3.0B, Steam Generator Tube Rupture?

The Reactor Coolant System is depressurized to A. minimize break flow and refill the Pressurizer.

B. minimize break flow and improve RCS subcooling.

C. prevent voiding the upper head region and improve RCS subcooling.

D. prevent voiding the upper head region and refill the Pressurizer.

Proposed Answer: A Explanation:

A. Correct. Lowering RCS pressure reduces or stops break flow to the Steam Generator and refills the Pressurizer via spray flow and possible back-flow from the ruptured Steam Generator.

B. Incorrect. Plausible because minimizing break flow is correct but the Steam Generator will not be cooled by lowering Pressurizer pressure. The Steam Generator is cooled with the RCS.

C. Incorrect. Plausible because voiding of the upper head region is discussed in the bases of EOP-3.0B, depressurizing the RCS is likely to cause little if any voiding and will not prevent voiding.

D. Incorrect. Plausible because refilling the Pressurizer is correct but depressurizing the RCS is likely to cause little if any voiding and will not prevent voiding.

Page 34 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) EOP-3.0B, Step 19 Attached w/ Revision # See EOP-3.0B, Attachment 6 Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a procedural step, or sequence of steps from EOP-3.0, Steam Generator Tube Rupture, STATE the purpose/basis for the step(s).

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 10 55.43 Page 35 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-3.0B, Step 19 Revision # 8 Page 36 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-3.0B, Attachment 6 Revision # 8 Page 37 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-3.0B, Attachment 6 Revision # 8 Page 38 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012 K4.09 Importance Rating 2.8 Reactor Protection System: Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following:

Separation of control and protection circuits Proposed Question: Common 10 Given the following conditions:

Unit 1 is in MODE 1.

Pressurizer Pressure Channel 1-PI-455A has failed LOW.

1/1-PS-455F, PRZR PRESS CTRL CHAN SELECT switch is in the 455/456 position.

Which of the following channel output signals passed through an isolation amplifier in the 7300 Process Racks?

Input to

1. Pressurizer Pressure Low Backup Heaters On Annunciator Signal.

2. 1-PT-455A, Pressurizer Master Pressure Control Signal.

3. Pressurizer Pressure Low Reactor Trip Bistable Input.

4. Pressurizer Pressure Low Safety Injection Bistable Input.

A. 1 and 2.

B. 1 and 4.

C. 2 and 3.

D. 3 and 4.

Proposed Answer: A Explanation:

A. Correct. Both signals are outputs of Pressurizer Pressure Channel 1-PI-455A, and both are control signals which are separated from protection circuitry via an isolation circuit.

B. Incorrect. Plausible because both signals are outputs of Pressurizer Pressure Channel 1-PI-455A, but the Safety Injection Bistable input is a protection circuit which is NOT isolated.

C. Incorrect. Plausible because both signals are outputs of Pressurizer Pressure Channel 1-PI-455A, but Pressurizer Pressure Low Reactor Trip Bistable Input is a protection circuit output which is NOT isolated.

D. Incorrect. Plausible because both signals are outputs of Pressurizer Pressure Channel 1-PI-455A, but both signals are protection circuit outputs which are NOT isolated.

Page 39 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) DBD-EE-021, Paragraph 6.2.5.7 Attached w/ Revision # See 7300 PCS Study Guide, Page 32 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DEMONSTRATE an understanding of the components of the Reactor Protection and Engineered Safeguard Actuation Systems 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 40 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From DBD-EE-021, Paragraph 6.2.5.7 Revision # 31 6.2.5.7 Control and Protection System Interaction Control and protection system interaction addresses any mechanism whereby the ability of the protection system to accomplish its safety-related function is adversely affected by nonprotective functions. Nonprotective functions include those signals used to control, remote processing indication and computer monitoring. Interactions between the protection system and nonprotective functions may be physical or functional. An example of a physical interaction is when electrical faults originate in the control system and propagate to the protection system thereby bringing about an attendant failure within the protection system. An example of a functional interaction is when the action of a control system is coupled to the ability of the protection system to provide adequate core protection consistent with the requirements of IEEE 279-1971. To prevent control and protection system interaction, the protection system was designed with due regard for the requirements of physical, electrical, and functional independence relative to non-protection (control) systems to ensure that protective actions will not be degraded by the control system.

In the Comanche Peak RPS design, the NSSS Related Control Systems derive many of their input signals not from dedicated control system instrument channels, but directly from protection system instruments. The requirements for process parameter measurements for control and protection function so nearly overlap that the optimum for one purpose is also the optimum for the other.

Therefore, common sensors are used both for the RPS and the NSSS Related Control Systems for those parameters used in both the protection and control systems. This practice ensures that the NSSS will be controlled from the same measurements with which it is protected. This precludes any sensor drift between control and protection functions which serves to maintain margins between operating conditions and safety limits thereby reducing the likelihood of spurious reactor trips, and considerably reduces the task of channel calibration and maintenance.

Redundant sensor channels required for protection purposes are first routed to the protection system.

If necessary, their output is transmitted to the control system through isolation devices that prevent any credible control system malfunction from being fed back to the protection system, thereby causing consequential protection system failure. The isolation devices are classified as part of the protection system and are located in the analog protection racks. For each variable monitored, the best type of equipment available is selected for the measurement.

Because of the use of isolation devices to feed signals to the control system, the RPS and the NSSS Related Control Systems are separate and distinct. (The control systems are, however, dependent on signals derived from the protection system through the isolation devices.) The equipment design intent is that the control system "sensor" is the output of the isolation device. By this principle, no components are shared between control and protection systems - they are either part of the protection system and are located and designed as such, or they are part of the control system. This is a very important feature of the design, and permits a "dividing line," both functionally and physically, to be drawn between control and protection systems. It also ensures that inadvertent or deliberate changes to the control system have no more effect on the RPS than if the control system contained completely independent sensors. The isolation amplifiers are designed such that a short circuit, open circuit, or the application of credible ac or dc voltage on the isolated output portion of the circuit (i.e., the non-protective side of the circuit) will not affect the input (protective) side of the circuit. The signals obtained through the isolation amplifiers are never returned to the protective racks.

Comments /

Reference:

From 7300 PCS Study Guide, Page 32 Revision # 05/02/11 Isolation networks provide for electrical separation between process protection and control. In Figure 21 the loop power supply performs this function; however, other isolation devices are also used.

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ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 K5.01 Importance Rating 2.8 Engineered Safety Features Actuation System: Knowledge of the operational implications of the following concepts as they apply to the ESFAS: Definitions of safety train and ESF channel Proposed Question: Common 11 Given the following conditions:

All Unit 1 systems are in a normal MODE 1 alignment.

A steam leak occurs on Steam Generator 1-02 outside Containment.

Annunciator 1-ALB-6C, Window 3.7 - MSL PRESS LO SI ACT, is FLASHING red.

Annunciator PCIP Window 1.8 - SI ACT, is ON and FLASHING.

Which of the following describes the status of the Engineered Safety Feature Actuation System?

At least _____ Main Steam Line Pressure Low Channel(s) has(have) actuated and _____

train(s) of Emergency Core Cooling System equipment is(are) operating.

A. one one B. one two C. two one D. two two Proposed Answer: C Page 42 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible if thought that to actuate a Low Main Steam Line Pressure SI requires only 1 of 3 pressure channels on 1 of 4 Main Steam Lines to be less than the setpoint. Alarm PCIP Window 1.8 - SI ACT ON, but NOT SOLID correctly indicates that only 1 of 2 ECCS equipment trains is operating.

B. Incorrect. Plausible if thought that to actuate a Low Main Steam Line Pressure SI requires only 1 of 3 pressure channels on 1 of 4 Main Steam Lines to be less than the setpoint and if PCIP Window 1.8 is NOT SOLID was the condition if both Trains of SI had actuated until the alarm was acknowledged.

C. Correct. Actuation channels for Low Main Steam Line Pressure SI are 2 of 3 channels on any 1 of 4 Main Steam Lines. A single Train actuation of SI will place PCIP Window 1.8 in the ON but NOT SOLID state.

D. Incorrect. Plausible if thought that to actuate a Low Main Steam Line Pressure SI requires only 1 of 3 pressure channels on 1 of 4 Main Steam Lines to be less than the setpoint and if PCIP Window 1.8 is NOT SOLID was the condition if both Trains of SI had actuated until the alarm was acknowledged.

Technical Reference(s) ALM-0063A, 1-ALB-6C, Window 3.7 Attached w/ Revision # See EOP-0.0A, Step 4 Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Solid State Protection System.

COMPREHEND the normal, abnormal and emergency operation of the Safety Injection and Blackout Sequencers.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7, 8 55.43 Page 43 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0063A, 1-ALB-6C, Window 3.7 Revision # 5 Page 44 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Step 4 Revision # 8 Page 45 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.06 Importance Rating 3.7 Engineered Safety Features Actuation System: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS actuation Proposed Question: Common 12 Given the following conditions:

A Main Steam Line Break outside Containment occurs.

The Reactor was tripped and Safety Injection was actuated.

Subsequently, a single Containment Spray Actuation switch was placed in ACTUATE.

Which of the following describes the effect on continued Reactor Coolant Pump (RCP) operation?

A. There is NO Containment Spray flow and Component Cooling Water isolation has occurred; the RCPs should immediately be tripped.

B. Two Containment Spray Pumps are providing Containment Spray flow and Component Cooling Water isolation has NOT occurred; the RCPs may continue to run.

C. Four Containment Spray Pumps are providing Containment Spray flow and Component Cooling Water isolation has occurred; the RCPs should immediately be tripped.

D. There is NO Containment Spray flow and Component Cooling Water isolation has NOT occurred; the RCPs may continue to run.

Proposed Answer: D Page 46 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because most actuations require only 1 of 2 handswitches to be properly manipulated, however, Containment Spray and Phase B require 2 of 2 handswitches. The misconception that the Phase B only requires 1 handswitch would yield this plant condition.

B. Incorrect. Plausible because most actuations require only 1 of 2 handswitches to be properly manipulated, however, Containment Spray and Phase B require 2 of 2 handswitches. The misconception that the Containment Spray requires 1 handswitch per train would yield this plant condition.

C. Incorrect. Plausible because most actuations require only 1 of 2 handswitches to be properly manipulated, however, Containment Spray and Phase B require 2 of 2 handswitches. The misconception that the Containment Spray and Phase B only requires 1 handswitch would yield this plant condition.

D. Correct. Containment Spray and Phase B requires 2 of 2 switches at 1 of 2 locations.

Technical Reference(s) LO21.SYS.CT1.LP, Page 10 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Containment Spray System.

DEMONSTRATE an understanding of the components of the Containment Spray System including interrelations with other systems to include interlocks and control loops.

Question Source: Bank # SYS.CT1.OB04.002 Modified Bank # (Note changes or attach parent)

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

Reference:

From LO21.SYS.CT1.LP, Page 10 Revision # 05/02/11 Page 47 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 022 A3.01 Importance Rating 4.1 Containment Cooling System: Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation Proposed Question: Common 13 Given the following conditions:

Both Units are at 100% power.

All systems are normally aligned when a Loss of Offsite Power occurs.

Which of the following describes the response of the Containment Air Cooling and Recirculation System Cooling Units and Fans?

A. Cooling Units and Fans are load shed and must be manually reset.

B. Cooling Units and Fans are load shed and CANNOT be restarted.

C. Cooling Units and Fans are tripped and then sequenced onto the safety-related electrical buses.

D. Two of the four Cooling Units and Fans are sequenced onto the safety-related electrical buses after all four have been tripped.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because CPNPP has ventilation systems which respond to a Loss of Offsite Power as stated.

B. Incorrect. Plausible because CPNPP has ventilation systems which cannot be manually restarted until electrical realignments are performed in the field.

C. Correct. The Containment Air Cooling and Recirculation System responds to a Loss of Offsite Power in this manner.

D. Incorrect. Plausible because this would be representative of restoring adequate Containment Cooling but not all cooling is restored in order to prevent overload of the Emergency Diesel Generators.

Technical Reference(s) ABN-601, Attachment 2 Attached w/ Revision # See SOP-801A, Step 5.1.1 NOTE Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Containment Ventilation System.

Page 48 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # SYS.CL1.OB03.005 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 9 55.43 Comments /

Reference:

From ABN-601, Attachment 2 Revision # 7 Page 49 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-601, Attachment 2 Revision # 7 Comments /

Reference:

From SOP-801A, Step 5.1.1 NOTE Revision # 13 Page 50 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026 A3.01 Importance Rating 4.3 Containment Spray System: Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning Proposed Question: Common 14 Given the following conditions:

Unit 2 was at 100% power with the Train A Safety Injection Sequencer deenergized for I&C troubleshooting.

A Reactor Trip and Safety Injection occurred due to low Pressurizer pressure.

Containment pressure is 20 psig and rising.

All systems functioned as expected for the given plant conditions.

Which of the following describes the response of Train A Containment Spray System?

Train A Containment Spray Pumps will A. start and the Heat Exchanger Outlet Valve will open.

B. NOT start and the Heat Exchanger Outlet Valve will open.

C. start and the Heat Exchanger Outlet Valve will NOT open.

D. NOT start and the Heat Exchanger Outlet Valve will NOT open.

Proposed Answer: A Explanation:

A. Correct. The slave relays in the Solid State Protection System will start the Containment Spray Pumps and cause the Heat Exchanger Outlet Valve to open.

B. Incorrect. Plausible because the Heat Exchanger Outlet Valve will open, however, the Containment Spray Pumps will also start because they are operated by a slave relay that is independent of the Train A Safety Injection Sequencer.

C. Incorrect. Plausible because the Containment Spray Pumps will start, however, the Heat Exchanger Outlet Valve will also open.

D. Incorrect. Plausible if it is thought that the Containment Spray Pumps and Heat Exchanger Outlet Valve are driven by the Sequencer. They are operated by a slave relay that is independent of the Train A Safety Injection Sequencer.

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ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) RPS & ESFAS Study Guide, Page 84 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the purpose of the Reactor Protection and Engineered Safeguard Actuation Systems and EXPLAIN the systems interrelationship with other plant systems based on approved station documents, including but not limited to, Design Basis Documents, appropriate system drawings, Final Safety Analysis Report, vendor manuals, procedures or other appropriate documents.

Question Source: Bank # SYS.ES1.OB10 01 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 9 55.43 Page 52 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From RPS & ESFAS Study Guide, Page 84 Revision # 05/04/11 Figure 31 - P-Signal/Cntmt Spray/Cntmt Phase B Isolation Logic Even though containment spray and containment isolation Phase B are both initiated by the same P signal they are differentiated not only by their functions but by how they are actuated. If 2 of 4 containment pressures exceed 18.2 psig, the SSPS logic card will produce a P signal. This P signal goes to three different safeguards driver circuits on the safeguards driver card A516. Each safeguards driver card has eight independent driver circuits. Only one safeguards driver card output (O2 of A516),

energizing one master relay (K506), is needed to energize the slave relays which cause a Phase B actuation (K625, K626, K632 and K633). However, two different safeguards driver card outputs (O1 and O4 of A516), energizing two different master relays (K505 and K519), are needed to energize the slave relays which cause a containment spray actuation (K643, K644 and K645). When either pair of CS/Phase B actuation switches are turned to actuate, they directly energize the three master relays mentioned above.

Page 53 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 039 K3.06 Importance Rating 2.8 Main and Reheat Steam System: Knowledge of the effect that a loss or malfunction of the MRSS will have on the following:

SDS Proposed Question: Common 15 Given the following conditions:

Unit 2 is in MODE 3 after performing a normal shutdown.

43/1-SD, STM DMP MODE SELECT is in STM PRESS.

2-PK-507, STM DMP PRESS CTRL is in AUTO.

2-PK-507 POT is set to control Reactor Coolant System temperature at 500°F.

Circulating Water Pumps 2-01 and 2-03 are in service.

Condenser vacuum is 27 Hg.

What would be the Steam Dump System response to 2-PT-0507, Main Steam Header Pressure Transmitter, failing high?

A. Bank 1 would open in response to the difference between the setpoint and measured pressure.

B. Banks 1 and 2 would open in response to the difference between the setpoint and measured pressure.

C. Bank 1 would open in response to the Hi-1 Bistable actuation.

D. Banks 1 and 2 would open in response to the Hi-1 Bistable actuation.

Proposed Answer: A Explanation:

A. Correct. In the Steam Pressure Mode of control the Bank 1 valves will open in an attempt to control Main Steam header pressure at the desired setpoint.

B. Incorrect. Plausible because the demand would be high enough to open both the Bank 1 and 2 valves, however, the Bank 2 valves will not open below the P-12 interlock.

C. Incorrect. Plausible because in the TAVE Mode of control the bistable 1 actuation opens both Banks 1 and 2, however, the controller is in the Steam Pressure Mode and the bistable is not in the circuit. Additionally, if believed that the Hi-1 bistable would open both Bank 1 and 2, should realize that the Bank 2 valves will not open below the P-12 interlock.

D. Incorrect. Plausible because in the TAVE Mode of control the Hi-1 bistable actuation opens both Banks 1 and 2, however, the controller is in the Steam Pressure Mode and the bistable is not in the circuit.

Page 54 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) Steam Dump Study Guide, Pages 13 & 15 Attached w/ Revision # See ABN-709, Section 3.2 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Steam Dump System and PREDICT the system response.

Question Source: Bank #

Modified Bank # SYS.SD1.OB15.007 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /

Reference:

From Steam Dump Study Guide, Page 13 Revision # 05/04/11 STEAM DUMP MODE SELECTOR SWITCH The Steam Dump Mode Selector Switch is located on CB-08. The switch has three positions. The Tave and Steam Pressure positions are maintained positions. The Reset position will spring return to the center position (Tave) when released by the operator. The Reset position has only one function and that is to reset the C-7 signal. The Tave position removes the Steam Pressure controller from the control circuit and places either the Load Rejection controller or the Plant Trip controller into service. This enables the steam dumps to operate on either a load rejection or plant trip. The Steam Pressure position removes the Load Rejection and Plant Trip controllers from the control circuit and places the Steam Pressure controller into the control circuit.

Comments /

Reference:

From Steam Dump Study Guide, Page 15 Revision # 05/04/11 Page 55 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 STEAM DUMP MODE SELECTOR SWITCH The Steam Dump Mode Selector Switch is located on CB-08. The switch has three positions. The Tave and Steam Pressure positions are maintained positions. The Reset position will spring return to the center position (Tave) when released by the operator. The Reset position has only one function and that is to reset the C-7 signal. The Tave position removes the Steam Pressure controller from the control circuit and places either the Load Rejection controller or the Plant Trip controller into service. This enables the steam dumps to operate on either a load rejection or plant trip. The Steam Pressure position removes the Load Rejection and Plant Trip controllers from the control circuit and places the Steam Pressure controller into the control circuit.

Each of the four bistables has different temperature deviations which energize the bistables. They are:

Load Rejection Controller - Hi-1 = 10.6°F and Hi-2 = 16.2°F Plant Trip Controller - Hi-1 = 20.0°F and Hi-2 = 40.0°F The Hi-1 bistables port Instrument Air to six of the twelve Steam Dump Valves causing them to open (Banks 1 & 2). The Hi-2 bistables port Instrument Air to the remaining six Steam Dump Valves causing them to open (Banks 3 & 4). Once the Steam Dump Valves have reduced the temperature deviation below the temperature which causes energization of the bistables, the bistables de-energize and allow the normal controls of the Steam Dump System to respond to the temperature deviation.

Page 56 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-709, Section 3.2 Revision # 8 Page 57 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SYS.SD1.OB15.007 Revision # N/A Given the following conditions:

Unit 2 is in MODE 3 after performing a normal shutdown.

Steam Dump Selector Switch is in STEAM PRESSURE MODE.

Both Steam Dump Interlock Select Switches are in the BYPASS INTERLOCK position.

2-PK-507, Steam Dump Pressure Controller, is in AUTO.

2-PK-507 POT is set to control Reactor Coolant System temperature at 500°F.

Circulating Water Pumps 1-01 and 1-03 are in service.

Condenser pressure is 27 Hg.

Assuming NO operator action, what would be the Steam Dump System response to 2-PT-0507, Main Steam Header pressure transmitter failing high?

A. Group 1 would fully open.

B. Groups 1 and 2 would fully open.

C. Groups 1 and 2 would not respond due to the P-12 interlock.

D. Group 1 would modulate open to maintain RCS temperature at 500°F.

Page 58 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 039 A3.02 Importance Rating 3.1 Main and Reheat Steam System: Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS Proposed Question: Common 16 Given the following conditions following a Steam Line Break outside Containment:

EOP-2.0A, Faulted Steam Generator Isolation, is in progress.

125 VDC Battery BT1D2 is verified aligned from either 125 VDC Battery Chargers BC1D2 or BC1D24.

Which of the following identifies the reason for ensuring an OPERABLE Battery Charger is aligned to Distribution Panel 1D2 per EOP-2.0A, Faulted Steam Generator Isolation?

A. Loss of Unit Auxiliary Transformer 1UT.

B. Loss of Main Turbine Emergency DC Oil Pump.

C. The Main Steam Isolation Valves may inadvertently open.

D. Two (2) Steam Generator Atmospheric Release Valves may inadvertently open.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because power for Unit Auxiliary Transformer 1UT comes from Bus 1D2-2.

B. Incorrect. Plausible because the Main Turbine Emergency DC Oil Pump is powered from Bus 1D2, however, not Distribution Panel 1D2.

C. Correct. Because the power supply to Battery Charger BC1D2 is load shed on a Safety Injection Signal (SIS), EOP-2.0A requires an alignment to Battery Charger BC1D24. If Battery Charger BC1D24 is not available, the SIS is reset, and Battery Charger BC1D2 is placed in service. Either of these actions is performed to ensure that the Main Steam Isolation Valves remain closed.

D. Incorrect. Plausible because the emergency overrides for Atmospheric Release Valves #2 and #4 are powered from Bus 1ED2.

Technical Reference(s) EOP-2.0A, Attachment 2 Attached w/ Revision # See DC Electrical Study Guide, Pages 35 & 36 Comments / Reference Electrical Print E1-0019, Sheet C Proposed references to be provided during examination: None Learning Objective: Given a procedural step, or sequence of steps from EOP-2.0, Faulted Steam Generator Isolation, STATE the purpose/basis for the step(s).

Page 59 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # ERG.E2A.OB04.002 Modified Bank # (Note changes or attach parent)

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

Reference:

From EOP-2.0A, Attachment 2 Revision # 8 Comments /

Reference:

From DC Electrical Study Guide, Pages 35 & 36 Revision # 05/05/11 EOP-2.0, FAULTED STEAM GENERATOR ISOLATION If a large steam leak has occurred and the operators have entered the Emergency Operating Procedures, the steam generator(s) will be isolated by EOP-2.0. Special steps may be required to ensure that the Main Steam Isolation Valves which are closed by the procedure remain closed.

The MSIV hydraulic dump solenoid valves are not environmentally qualified. A steam leak in the MSIV room(s) can result in the hydraulic dump solenoid valves failing closed. If the oil pump were to now supply oil to the MSIV (without the dump path) the MSIV would open. It is very important to ensure that the DC supply to the air operated oil pump solenoid valve be maintained because if the air supply solenoid were to deenergize, the air supply valve would open and operate the oil pump.

The Class 1E AC supply breakers for the battery chargers normally supplying 125 VDC bus uD2 are load shed by a Safety Injection Signal. With the battery chargers deenergized, the batteries will start to discharge. The non-class 1E bus uB1-1 (which supplies BCuD24) is not shed on an SI signal. If the steam leak is in the MSIV room(s) an operator is dispatched to align BCuD24 to the bus. This alignment will allow BCuD24 to supply the MSIV air supply solenoid valve to maintain it closed. If BCuD24 is not available, (due to loss of non 1E power, for example) then the SI signal is reset and the bus is powered from a Class 1E bus via BCuD2.

Page 60 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Electrical Print E1-0019, Sheet C Revision # CP-27 Page 61 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059 A4.01 Importance Rating 3.1 Main Feedwater System: Ability to manually operate and monitor in the control room: MFW turbine trip indication Proposed Question: Common 17 Given the following condition:

Unit 1 is operating at 100% power when Main Feedwater Pump A trips.

Which of the following describes the automatic action that occurs due to the Main Feedwater Pump trip?

The Main Turbine will run back to A. 700 MWe and Main Feedwater Pump A Recirculation Valve opens.

B. 700 MWe and Main Feedwater Pump A Recirculation Valve closes.

C. 800 MWe and Main Feedwater Pump A Recirculation Valve opens.

D. 800 MWe and Main Feedwater Pump A Recirculation Valve closes.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because the runback is to 700 MWe, however, the recirculation valve closes. A misconception that the pump still needs flow to cool the pump would require the valve to open on a pump trip.

B. Correct. The runback is to 700 MWe and the recirculation valve closes to ensure adequate forward flow to the SGs and adequate NPSH for the running pump.

C. Incorrect. Plausible because 800 MWe is the automatic runback target for a Heater Drain Pump trip and a misconception that the pump still needs flow to cool the pump would require the valve to open on a pump trip.

D. Incorrect. Plausible because 800 MWe is the automatic runback target for a Heater Drain Pump trip and the recirculation valve closes to ensure adequate forward flow to the SGs and adequate NPSH for the running pump.

Technical Reference(s) ABN-302, Steps 2.3.1 & 2.3.3 Attached w/ Revision # See Main Feedwater Study Guide, Page 36 Comments / Reference Proposed references to be provided during examination: None Page 62 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Main Feedwater System.

Question Source: Bank # SYS.MF1.OB05.001 Modified Bank # (Note changes or attach parent)

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

Reference:

From ABN-302, Step 2.3.1 Revision # 14 Page 63 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-302, Step 2.3.3 RNO Revision # 14 Comments /

Reference:

From Main Feedwater Study Guide, Page 36 Revision # 05/07/11 FEED PUMP RECIRCULATION VALVE CONTROL Low feedwater flow protection for the FWPs is provided by individual minimum flow recirculation valves. These valves, u-FV-2289 and u-FV-2290, have manual/auto stations on the main control board that monitor suction flow to protect the FWPs.

If a FWP trips the recirc valves will close provided the HP and LP steam supply valves are shut and the recirc valve controllers are in auto. On a loss of air, the recirculation valves fail open. If an electrical failure occurs on the recirc valves associated driver card, the loss of the 4 ma output enables a flow switch and a normally deenergized solenoid valve on the recirc valve actuator. Under this condition, if a low flow condition occurs, the solenoid energizes at 4275 GPM, venting air from the actuator and opening the recirc valve. When flow increases above 6625 GPM, the recirc valve closes. A common alarm for FWP A/B RECIRC VLV NOT CLOSED provides immediate feedback when the recirc valve is not closed (i.e. closed limit switch not made up) on any FWP.

Page 64 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061 K1.05 Importance Rating 2.6 Auxiliary/Emergency Feedwater System: Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: Condensate system Proposed Question: Common 18 Given the following conditions:

Unit 1 is in MODE 3 following a Reactor Trip.

Steam Generator (SG) narrow range levels are as follows:

SG 1-01 is 36%.

SG 1-02 is 45%.

SG 1-03 is 32%.

SG 1-04 is 43%.

1-LI-2217, CNDSR HOT WELL LVL, is 5.8 feet.

Which of the following is the alignment of the Condensate System?

A. 1-HS-2211/12, CNDS REJECT VLV, is open to lower Condenser Hot Well level.

B. 1-HS-2211/12, CNDS REJECT VLV, is closed to preserve Condenser Hot Well level C. 1-HS-2484, CST DISCH VLV and 1-HS-2485, CST DISCH VLV, are open to allow water in the Condenser Hot Well to be transferred to the Condensate Storage Tank.

D. 1-HS-2484, CST DISCH VLV and 1-HS-2485, CST DISCH VLV, are closed to preserve level in the Condensate Storage Tank.

Proposed Answer: D Page 65 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because at a Hot Well level of 5.8 feet the valve would normally be open to reduce Hot Well level, however, with an Auxiliary Feedwater signal present the valve should be closed from the closed limit switch of either HS-2484 or HS-2485.

B. Incorrect. Plausible because the valve is closed and Hot Well level is required to ensure the condensate pumps do not automatically trip, however, this level is more than sufficient for adequate suction head and the valve is closed to preserve condensate storage tank level.

C. Incorrect. Plausible because this would be the normal alignment for a high level in the Condenser Hot Well, however, with an Auxiliary Feedwater signal present the valves would be closed.

D. Correct. With two out of four Steam Generator levels less than 38% on any Steam Generator, an automatic Auxiliary Feedwater System actuation signal is generated. HS-2484 and HS-2485 close on an Auxiliary Feedwater signal to preserve level in the CST.

Technical Reference(s) Auxiliary Feedwater Study Guide, Page 9 Attached w/ Revision # See Auxiliary Feedwater Study Guide, Page 11 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the basic design and flow path of the Auxiliary Feedwater System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

Reference:

From Auxiliary Feedwater Study Guide, Page 9 Revision # 05/11/11 AFW automatic starts will isolate other tank users automatically by closing the CST discharge valves, HV-2484 and HV-2485, to isolate the Condensate System makeup and reject lines. The CST discharge valves also close automatically on HI-HI level in the CST to prevent overfilling the CST from Main Condenser reject. The CST discharge valves can be operated manually from the control room using handswitches HS-2484 and HS-2485 located on CB-09. The handswitch positions are CLOSE-AUTO-OPEN with spring return to AUTO.

Page 66 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Auxiliary Feedwater Study Guide, Page 11 Revision # 05/11/11 The MDAFWPs will automatically start due to (Figure 2):

Low-low Steam Generator narrow range level at 38% ( 35.4% for Unit 2) in two out of four detectors on any one Steam Generator, Trip of both main feed pumps, Safety injection sequence signal (SI),

Blackout (BO) sequence signal, or AMSAC signal Page 67 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 K4.10 Importance Rating 3.1 AC Electrical Distribution System: Knowledge of AC distribution system design feature(s) and/or interlock(s) which provide for the following: Uninterruptable AC power sources Proposed Question: Common 19 Given the following condition:

Inverter 1PC4 has been declared inoperable due to an internal failure.

Which of the following alignments would be acceptable to allow Unit 1 to continue to operate for the next several weeks while parts are procured for repairs to Inverter 1PC4?

Align 118 VAC A. Distribution Panel 1EC6 to 118 VAC Vital Distribution Panel 1PC4.

B. Distribution Panel 1EC5 to 118 VAC Vital Distribution Panel 1PC4.

C. Inverter IV1EC2/4 to 118 VAC Vital Distribution Panel 1PC4.

D. Inverter IV1EC1/3 to 118 VAC Vital Distribution Panel 1PC4.

Proposed Answer: C Page 68 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because 1EC6 is a Vital Train B Bus, however, 1EC6 cannot be aligned to supply 1PC4.

B. Incorrect. Plausible because 1EC5 is a Vital Train A Bus, however, 1EC5 cannot be aligned to supply 1PC4.

C. Correct. In accordance with Technical Specifications and System Operating Procedures, the installed spare Inverter IV1EC2/4 can be aligned to provide inverted power to 1PC4.

D. Incorrect. Plausible because this is the Train A installed spare inverter which can be aligned to provide power to Train A Vital Buses.

Technical Reference(s) SOP-607A, Attachment 1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DEMONSTRATE an understanding of the components of the 118 VAC Instrument Power System including interrelations with other systems to include interlocks and control loops.

Question Source: Bank # SYS.AC3.OB04.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 69 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-607A, Attachment 1 Revision # 23 Page 70 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-607A, Attachment 1 Revision # 23 Comments /

Reference:

From SOP-607A, Attachment 1 Revision # 23 Page 71 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 72 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-607A, Attachment 1 Revision # 23 Page 73 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063 A1.01 Importance Rating 2.5 DC Electrical Distribution System: Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate Proposed Question: Common 20 Given the following condition:

Unit 1 was in MODE 1 with all systems in their NORMAL lineup.

A Loss of Offsite and Onsite AC Power occurred 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

ECA-0.0A, Loss of All AC Power, is in progress.

INITIAL DC load shedding was performed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago per ECA-0.0A, Loss of All AC Power, Attachment 2 (DC Load Shedding), Step 1.

It will take approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore Offsite Power.

Emergency Diesel Generator 1-02 will be available to energize Bus 1EA2 in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

A fault occurred on Emergency Diesel Generator 1-01 and it will not be available for at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Battery parameters are as follows:

Battery BT1ED1 Voltage: 109 VDC Battery BT1ED1 Current: 75 amps discharging Battery BT1ED2 Voltage: 108 VDC Battery BT1ED2 Current: 80 amps discharging Due to plant conditions, ADDITIONAL DC load shedding is required on Bus 1ED2 ONLY per ECA-0.0A, Loss of All AC Power, Attachment 2 (DC Load Shedding), Step 2.

Which of the following necessitates that additional load shedding be performed?

Additional load shedding is performed on Bus 1ED2 to A. maintain Battery BT1ED2 voltage greater than 105 VDC to allow accurate monitoring of vital plant parameters from the Control Room.

B. restore Battery BT1ED2 voltage to greater than 110 VDC to ensure minimum system voltage for subsequent power restoration activities.

C. restore Battery BT1ED2 voltage to greater than 110 VDC to allow accurate monitoring of vital plant parameters from the Control Room.

D. maintain Battery BT1ED2 voltage greater than 105 VDC to ensure minimum system voltage for subsequent power restoration activities.

Page 74 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed Answer: D Explanation:

A. Incorrect. Plausible since 105 VDC is the minimum voltage required for equipment operation, however, additional load shedding is performed to ensure DC power is available for subsequent power restoration activities.

B. Incorrect. Plausible since additional load shedding is required to conserve energy for subsequent restoration activities, however, battery voltage need only be greater than approximately 105 VDC to allow equipment operation. Below 110 VDC, additional actions are necessary to conserve battery power. Additionally, reducing battery discharge rate by shedding additional load will not raise battery voltage.

C. Incorrect. Plausible since below 110 VDC, additional actions are necessary to conserve battery power, however, battery voltage need only be greater than approximately 105 VDC to allow equipment operation. Additionally, load shedding is performed to ensure DC power is available for subsequent power restoration activities.

D. Correct. Battery voltage need only be greater than approximately 105 VDC to allow equipment operation. Additional load shedding is performed on the DC Bus in the Train that will be restored first. This will conserve DC energy to assist in recovery actions, such as starting the Emergency Diesel Generator.

Technical Reference(s) ECA-0.0A, Attachment 2, Step 2 Attached w/ Revision # See ECA-0.0A, Attachment 7, Step 16 Bases Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the DC Electrical Distribution System.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 7 55.43 Page 75 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-0.0A, Attachment 2, Step 2 Revision # 8 Page 76 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-0.0A, Attachment 2, Step 2 Revision # 8 Page 77 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-0.0A, Attachment 7, Step 16 Bases Revision # 8 Page 78 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064 K6.07 Importance Rating 2.7 Emergency Diesel Generator System: Knowledge of the effect of a loss or malfunction of the following will have on the EDG system: Air receivers Proposed Question: Common 21 Which of the following describes the effect of allowing BOTH the Diesel Starting Air Receivers to drop to 145 psig?

The Emergency Diesel Generator Engine Start Circuit will accept a A. Local Emergency Start signal.

B. Safety Injection Start signal.

C. Bus Undervoltage Start signal.

D. Manual Normal Start signal.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because it would seem that a Local Emergency Start Signal should attempt to start the EDG without regard to starting air receiver pressure as the concern for multiple automatic start attempts is eliminated. When receiver pressure is below 150 psig, only a Manual Normal Start signal will be accepted.

B. Incorrect. Plausible because it would seem that an Emergency Start Signal should attempt to start the EDG without regard to starting air receiver pressure, however, automatic emergency starts would continue to lower the starting air receiver pressure so this is not the case. When receiver pressure is below 150 psig, only a Manual Normal Start signal will be accepted.

C. Incorrect. Plausible because it would seem that a Bus Undervoltage Start Signal would be the highest priority start of the EDG and should occur without regard to starting air receiver pressure, however, automatic emergency starts would continue to lower the starting air receiver pressure so this is not the case. When receiver pressure is below 150 psig, only a Manual Normal Start signal will be accepted D. Correct. When receiver pressure is below 150 psig, only a Manual Normal Start signal will be accepted.

Technical Reference(s) SOP-609A, Section 4.2 Attached w/ Revision # See SOP-609A, Step 5.2.F CAUTION Comments / Reference Proposed references to be provided during examination: None Page 79 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Starting Air System.

Question Source: Bank # SYS.ED1.OB11.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments /

Reference:

From SOP-609A, Section 4.2 Revision # 20 Comments /

Reference:

From SOP-609A, Section 4.2 Revision # 20 Page 80 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-609A, Step 5.2.F CAUTION Revision # 20 Page 81 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 073 G 2.4.45 Importance Rating 4.1 Process Radiation Monitoring System: Emergency Procedures/Plan: Ability to prioritize and interpret the significance of each annunciator or alarm Proposed Question: Common 22 Given the following conditions on Unit 1:

EOP-0.0A, Reactor Trip or Safety Injection, is in progress following a manual Reactor Trip and Safety Injection due to a 25 GPM leak.

A Main Steam Line N-16 Radiation Monitor had been in alarm with a reading of greater than 150 GPD.

Ten minutes have passed since the Reactor was tripped and the Main Steam Line N-16 Radiation Monitor is now reading one GPD.

Which of the following explains this trend?

The trend is...

A. unexpected because when the Reactor and Turbine were tripped, the steam flow past the detector decreased resulting in the lower reading.

B. expected because while the Reactor was critical, high energy gamma radiation was being produced and entering the Steam Generator through a tube leak. The high energy gamma production has reduced resulting in a lower reading.

C. expected because the Main Steam Line N-16 Radiation Monitors are isolated on the Safety Injection signal resulting in the decreased reading.

D. unexpected because the radiation monitor was in alarm, the trend should continue to rise as high energy gamma production will increase as the secondary isotopic concentration rises toward equilibrium until the leak is stopped.

Proposed Answer: B Page 82 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the steam flow past the Radiation Monitor will reduce by approximately two orders of magnitude, however, the trend is unexpected.

B. Correct. The N-16 production will significantly decrease once the Reactor is tripped.

C. Incorrect. Plausible because flow past the monitors is stopped when a Main Steam Line Isolation occurs, however, a Safety Injection signal does not create a Main Steam Line Isolation.

D. Incorrect. Plausible because primary to secondary leakage will continue to increase the activity of the Steam Generator, however, high energy gamma production will significantly decrease and the trend is unexpected.

Technical Reference(s) EOP-0.0A, Step 13 Bases Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Digital Radiation Monitoring System.

Question Source: Bank # ERG.E12.OB06.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 11 55.43 Page 83 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Step 13 Bases Revision # 8 Page 84 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 K2.01 Importance Rating 2.7 Service Water System: Knowledge of bus power supplies to the following: Service water Proposed Question: Common 23 Given the following conditions:

Unit 2 is in MODE 1 when a Loss of Offsite Power occurs.

Both Station Service Water (SSW) Pumps were in operation prior to the trip.

Safeguards Bus 2EA2 has an 86-2 Lockout Relay actuated.

Both Emergency Diesel Generators have responded per design.

Which of the following is the status of the SSW Pumps forty-five seconds 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.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because misconceptions on when the SSW Pumps are started could exist.

B. Correct. With an 86-2 the bus should be powered from the EDG, the other bus should also be powered from the EDG and the SSW Pumps should have started on the Blackout Sequencer at 25 seconds.

C. Incorrect. Plausible because SSW Pump 1-02 would not be running if the lockout was an 86-1.

D. Incorrect. Plausible because misconceptions on when the SSW Pumps are started could exist.

Technical Reference(s) ABN-602, Step 2.3.3 NOTE Attached w/ Revision # See ABN-602, Step 8.3.2 NOTE Comments / Reference Proposed references to be provided during examination: None Learning Objective: DEMONSTRATE an understanding of the components of the Station Service Water System including interrelations with other systems to include interlocks and control loops.

Page 85 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 8, 10 55.43 Comments /

Reference:

From ABN-602, Step 2.3.3 NOTE Revision # 7 Page 86 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Step 8.3.2 NOTE Revision # 7 Page 87 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 A2.02 Importance Rating 2.7 Service Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Proposed Question: Common 24 Given the following conditions:

Unit 1 Station Service Water (SSW) was in an abnormal lineup with Station Service Water Pump (SSWP) 1-01 running and SSWP 1-02 in STANDBY.

Component Cooling Water Pump (CCWP) 1-02 is out of service for preventative maintenance.

Subsequently SSWP 1-01 trips and SSWP 1-02 automatically starts.

Which of the following describes the SSWP AUTO start feature and how cooling to Component Cooling Water (CCW) System heat loads is initially accomplished per ABN-501, Station Service Water System Malfunction?

SSWP 1-02 AUTO started when A. the header pressure in Train A SSW dropped to 10 psig.

Cross connect Train A SSW Unit 1 with Train A SSW Unit 2.

B. the return header flow in Train A SSW dropped to 14,000 GPM.

Cross connect Train A SSW Unit 1 with Train A SSW Unit 2.

C. the return header flow in Train A SSW dropped to 14,000 GPM.

Ensure CCWP 1-01 running with both Train Safeguards Loop Isolation Valves open.

D. the header pressure in Train A SSW dropped to 10 psig.

Ensure CCWP 1-01 running with both Train Safeguards Loop Isolation Valves open.

Proposed Answer: D Page 88 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the standby Service Water Pump starts on low header pressure of 10 psig, however, cross-connecting SSW between Units is not required or desired.

B. Incorrect. Plausible because it could be thought that the AUTO start feature was on low flow and that the cooling option would be to cross-tie Unit SSW Trains.

C. Incorrect. Plausible because it could be thought that the AUTO start feature was on low flow and the CCW System cooling is accomplished via flow though both Safeguards Loop Isolation Valves to the header being cooled by the running SSW Pump.

D. Correct. The standby Service Water Pump starts on low header pressure of 10 psig and the CCW System cooling is accomplished via flow though both Safeguards Loop Isolation Valves to the header being cooled by the running SSW Pump.

Technical Reference(s) ABN-501, Step 2.2 Attached w/ Revision # See ABN-501, Step 2.3.3 & 2.3.4 Note Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to Station Service Water Pump Trip in accordance with ABN-501, Station Service Water System Malfunction.

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

Question Source: Bank # ABN.501.OB01.005 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam CPNPP 2010 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7, 10 55.43 Page 89 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Step 2.2 Revision # 9 Page 90 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Step 2.3.3 Revision # 9 Page 91 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Step 2.3.4 Note Revision # 9 Page 92 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 K1.01 Importance Rating 2.8 Instrument Air System: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Sensor air Proposed Question: Common 25 Given the following conditions:

Unit 1 is in MODE 1.

Instrument Air (IA) Compressor 1-01 is operating as the LEAD Compressor.

IA Compressor 1-02 is in an AUTO-START condition as the BACKUP Compressor.

IA Compressor X-01 is in STANDBY and aligned to Unit 1 through Air Dryer X-01.

The following sequence of events occur:

At 1415, 1-ALB-01, Window 2.4 - CNTMT INSTR AIR HDR PRESS LO, alarms as pressure drops to 84 psig.

At 1416, 1-ALB-01, Window 3.3 - INSTR AIR HDR PRESS LO, alarms as pressure drops to 85 psig.

All other Unit 1 Control Room alarms related to the IA System remain clear.

At 1420, a stuck-open relief valve on Air Dryer 1-01 reseats.

At 1422, both Instrument Air alarms (1-ALB-01-2.4 and 3.3) clear.

At 1423, Instrument Air header pressure is 93 psig and slowly rising.

At 1424, assuming NO additional operator actions and with IA Compressor 1-01 running and loaded, which of the following is the status of IA Compressors 1-02 and X-01?

IA Compressor 1-02 is __________ and IA Compressor X-01 is __________.

A. running and loaded; running and loaded B. running and loaded; shutdown C. running and unloaded; running and unloaded D. running and unloaded; shutdown Proposed Answer: A Page 93 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Given the conditions listed, the BACKUP and STANDBY IA Compressors will both be running and loaded.

B. Incorrect. Plausible because the BACKUP compressor is running and loaded (See NOTE for Step 5.2.1.J) given that a low pressure alarms are cleared but header pressure is unknown. The STANDBY compressor would have to see Instrument Air header pressure greater than 115 psig to be shut down. (See NOTE for Step 5.4.1.H).

C. Incorrect. Plausible because the BACKUP and STANDBY IA Compressors will be running, however, they will also be loaded.

D. Incorrect. Plausible because the BACKUP IA Compressor will be running, however, it will also be loaded. The STANDBY compressor would have to see Instrument Air header pressure greater than 115 psig to be shut down.

Technical Reference(s) SOP-509A, Step 5.2.1.J NOTE Attached w/ Revision # See SOP-509A, Step 5.4.1.H NOTE Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Instrument Air System and PREDICT the system response.

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

Question Source: Bank # SYS.IA1.OB05.006 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Page 94 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-509A, Step 5.2.1.J Note Revision # 21 Comments /

Reference:

From SOP-509A, Step 5.4.1.H Note Revision # 21 Page 95 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 96 of 96 CPNPP NRC 2012 RO Written Exam Worksheet 1 to 25 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078 A4.01 Importance Rating 3.1 Instrument Air System: Ability to manually operate and/or monitor in the control room: Pressure gauges Proposed Question: Common 26 Given the following conditions:

Unit 1 is in MODE 1.

1/1-8149A, LTDN ORIFICE ISOL VLV (45 GPM) is CLOSED.

1/1-8149B, LTDN ORIFICE ISOL VLV (75 GPM) is CLOSED.

1/1-8149C, LTDN ORIFICE ISOL VLV (75 GPM) is CLOSED.

1/1-LCV-459, LTDN ISOL VLV indicates mid position.

1/1-LCV-460, LTDN ISOL VLV indicates mid position.

1-PI-3488, INSTR AIR AFTFILT OUT PRESS indicates 112 psig and stable.

1-PI-3490, CNTMT INSTR AIR HDR PRESS indicates 75 psig and lowering slowly.

Instrument Air Compressor 1-01 is running.

Which of the following actions are required?

A. Cross-Tie Unit 1 and Unit 2 instrument air headers.

B. Start and align temporary air compressor.

C. Start and align common instrument air compressor X-01.

D. Open 1-HS-3487, CNTMT INSTR AIR ISOL VLV.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because cross-tying the Unit 1 and Unit 2 Instrument Air headers is an acceptable action per ABN-301 for lowering Instrument Air header pressure, however, Instrument Air header pressure is not lowering but the Containment Instrument Air header is isolated.

B. Incorrect. Plausible because starting and aligning a Temporary Air Compressor is an acceptable action per ABN-301 for lowering Instrument Air header pressure, however, Instrument Air header pressure is not lowering but the Containment Instrument Air header is isolated.

C. Incorrect. Plausible because starting and aligning a Common Instrument Air Compressor is an acceptable action per ABN-301 for lowering Instrument Air header pressure, however, Instrument Air header pressure is not lowering but the Containment Instrument Air header is isolated.

D. Correct. In accordance with ALM-0011A, the plant indications require opening the Containment Instrument Air Isolation Valve.

Page 1 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) ALM-0011A, 1-ALB-1, Window 2.4 Attached w/ Revision # See ABN-301, Step 2.1.b Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to Instrument Air Compressor Trip or Header Pressure Low in accordance with ABN-301, Instrument Air System Malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 2 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0011A, 1-ALB-1, Window 2.4 Revision # 9 Page 3 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-301, Step 2.1.b Revision # 11 Page 4 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103 K3.01 Importance Rating 3.3 Containment System: Knowledge of the effect that a loss or malfunction of the containment system will have on the following:

Loss of containment integrity under shutdown conditions Proposed Question: Common 27 Given the following condition:

Unit 2 is operating at reduced inventory in accordance with IPO-010B, Reactor Coolant System Reduced Inventory Operations.

Under this condition Containment hatches must be closed prior to A. core boiling following a loss of Residual Heat Removal.

B. commencing vacuum fill of the Reactor Coolant System.

C. throttling the Residual Heat Removal Cold Leg Injection Valve.

D. reducing inventory to less than or equal to 80 inches above Core Plate.

Proposed Answer: A Explanation:

A. Correct. In accordance with IPO-010B, Attachment 1.

B. Incorrect. Plausible because placing the RCS under vacuum has an increased potential to introduce level instrument errors and possibly lead to RHR pump cavitation.

C. Incorrect. Plausible because RHR Cold Leg Injection Valve throttling only occurs when RCS level is lowered below 56 above core plate. The throttling is performed in response to CPNPP flow data which indicates an increased probability of air introduction via vortexing into the RHR pump suctions.

D. Incorrect. Plausible because this defines the transition to reduced inventory operation at CPNPP.

Technical Reference(s) IPO-010B, Step 3.2.12 Attached w/ Revision # See IPO-010B, Attachment 1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DISCUSS the Precautions, Limitations and key Attachments of IPO-010, RCS Reduced Inventory Operations.

DISCUSS specific outage items related to Reduced Inventory.

Page 5 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments /

Reference:

From IPO-010B, Step 3.2.12 Revision # 13 Comments /

Reference:

From IPO-010B, Attachment 1 Revision # 13 Page 6 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103 A1.01 Importance Rating 3.7 Containment System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity Proposed Question: Common 28 Given the following conditions:

Reactor Coolant System temperature is 540°F during a Unit 1 heatup.

Three Containment Air Recirculation Fan Coolers are in service.

Four Ventilation Chillers are in service.

Containment air temperature is 122°F.

Containment pressure is 0.9 psig.

Which of the following actions are taken to ensure Containment does not exceed design limits upon the occurrence of a Loss of Coolant Accident or a Steam Line Break inside Containment?

Reduce Containment...

A. pressure by placing the Containment Pressure Relief System in service.

B. pressure by placing the Containment Purge Supply and Exhaust System in service.

C. temperature by placing an additional Ventilation Chiller in service.

D. temperature by placing an additional Containment Air Recirculation Fan Cooler in service.

Proposed Answer: D Explanation:

A. Incorrect. Plausible since Containment pressure higher than normal (~0.1 to 0.3 psig), however, Containment temperature is about to exceed the upper limit of 120°F.

B. Incorrect. Plausible since Containment pressure higher than normal (~0.1 to 0.3 psig), however, the Containment Purge Supply and Exhaust System is only permitted to be used in MODES 5 and 6.

C. Incorrect. Plausible because Containment temperature exceeds the upper limit of 120°F, however, there are already four (4) Ventilation Chillers in service.

D. Correct. Containment temperature exceeds the upper limit of 120°F. Per the guidance in the Alarm Procedure, verify adequate Ventilation Chillers in service (Step 7) then start an additional Containment Air Recirculation Fan Cooler (Step 11). Additionally, operation of 4 fans is allowed per SOP-801A during conditions of high Containment temperature.

Page 7 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SOP-801A, Steps 4.1 & 5.1.1 NOTE Attached w/ Revision # See ALM-0031A, ALB-3A, Window 1.1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Containment Ventilation System.

Question Source: Bank #

Modified Bank # SYS.CL1.OB03.007 (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 9, 10 55.43 Comments /

Reference:

From SOP-801A, Step 5.1.1 Revision # 13 Page 8 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-801A, Step 4.1 Revision # 13 Comments /

Reference:

From ALM-0031A, ALB-3A, Window 1.1 Revision # 7 Page 9 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0031A, ALB-3A, Window 1.1 Revision # 7 Page 10 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0031A, ALB-3A, Window 1.1 Revision # 7 Page 11 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SYS.CL1.OB03.007 Revision # N/A Given the following conditions:

Reactor Coolant System temperature is 540°F during a Unit 1 heatup.

Three (3) Containment Air Recirculation Fan Coolers are in service.

Four (4) Ventilation Chillers are in service.

Containment air temperature is 108°F.

Containment pressure is 1.4 psig.

Which of the following actions are taken to ensure Containment does not exceed design limits upon the occurrence of a Loss of Coolant Accident or a Steam Line Break inside Containment?

Reduce Containment...

A. pressure by placing the Containment Pressure Relief System in service.

B. pressure by placing the Containment Purge Supply and Exhaust System in service.

C. temperature by placing an additional Ventilation Chiller in service.

D. temperature by placing an additional Containment Air Recirculation Fan Cooler in service.

Page 12 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 001 A4.05 Importance Rating 3.7 Control Rod Drive System: Ability to manually operate and/or monitor in the control room: Determination of the amount of boron needed to back the rods out of the core, including xenon effects if equilibrium is not yet achieved Proposed Question: Common 29 Given the following conditions:

Unit 2 has been at 100% power for three months.

Unit 2 has been at 96% power for the past 5 days due to a secondary inefficiency.

Control Bank D is at 190 steps.

Considering Power Defect, Rod Worth, and Boron Worth, which of the following is the amount of boron necessary to restore Unit 2 to 100% with Control Bank D at 215 steps?

A. ~12 gallons.

B. ~19 gallons.

C. ~94 gallons.

D. ~169 gallons.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because 12 gallons would be the answer derived if mistakenly reverse the use of the boration and boron worth thumb rules: [(-60 + 75)/10] x 9 = 12 B. Correct. Using IPO-003B, Power Change Thumb Rules: (4% power x 15 pcm/% = -60 pcm) + (215 steps - 190 steps = 25 steps x 3 pcm/step = +75 pcm) ÷ 8 pcm/ppm = 1.875 ppm x 10 gallons/ppm

= ~19 gallons of boron. [(-60 + 75)/8] x 10 = ~19 C. Incorrect. Plausible because 94 gallons would be the answer derived if mistakenly ignored the Power Defect: [75/8] x 10 = ~ 94.

D. Incorrect. Plausible because 169 gallons would be the answer if mistakenly reversed the direction of the Power Defect: [(+60+75)/8] x 10 = ~ 169 Technical Reference(s) IPO-003B, Step 4.2.10 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: IPO-003B, Power Change Thumb Rules Page 13 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: DESCRIBE the monitoring and control of Tave, Tref, and power during power operation.

DESCRIBE the means by which reactor power will be increased to rated power.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1 55.43 Comments /

Reference:

From IPO-003B, Step 4.2.10 Revision # 18 Page 14 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 015 K2.01 Importance Rating 3.3 Nuclear Instrumentation System: Knowledge of bus power supplies to the following: NIS channels, components, and interconnections Proposed Question: Common 30 Given the following condition:

While recording Unit 2 Critical Data at 10-8 amps, a fault causes a loss of 118 VAC Protection Bus 2PC3.

Which of the following is the expected Nuclear Instrument (NI) plant response?

A. Reactor will trip due to Intermediate Range NI High Flux trip.

B. Bistables for Power Range NI N-43 will trip, Reactor will NOT trip.

C. Bistables for Power Range NI N-42 will trip, Reactor will NOT trip.

D. Reactor will trip due to removal of P-6 block reenergizing the Source Range NIs.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because Critical Data is taken at 1X10-8 amps where the IR High Flux Trip is still active and a loss of power to an IR Channel would cause a trip, however, IR channels N-35 and N-36 are powered from 2PC1 and 2PC2 respectively and no IR channels will be lost.

B. Correct. Power Range N-43 is powered from 2PC3 and bistables will trip on loss of power. Since the coincidence for a Reactor Trip is 2 of 4 channels, the Reactor will NOT trip.

C. Incorrect. Plausible because bistables for Power Range N-42 will trip upon a loss of power, however, N-42 is powered from 2PC2 and will not lose power.

D. Incorrect. Plausible because removal of P-6 will reenergize Source Ranges and since Critical Data is taken at a power above the Source Range High Flux setpoint, a Reactor Trip would occur, however, the P-6 permissive signal is generated from the IR channels (1 of 2 >10-10 amps). It is automatically removed when 2 of 2 IR channels are < 10-10 amps. Since both IR channels remain powered, P-6 remains active.

Technical Reference(s) ABN-603, Attachment 1 Attached w/ Revision # See ABN-701, Step 2.2.a Comments / Reference Proposed references to be provided during examination: None Page 15 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: EXPLAIN the instrumentation and controls of the Excore Instrumentation System and PREDICT the system response.

Question Source: Bank # SYS.EC1.OB03.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 6, 7 55.43 Comments /

Reference:

From ABN-603, Attachment 1 Revision # 7 Page 16 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-701, Step 2.2.a Revision # 11 Page 17 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 016 A3.02 Importance Rating 2.9 Non-Nuclear Instrumentation System: Ability to monitor automatic operation of the NNIS, including: Relationship between meter readings and actual parameter value Proposed Question: Common 31 Given the following conditions:

Unit 1 is at 55% power with a power ascension evolution in progress.

Rod Control is in MANUAL.

An instrument failure causes the following changes to plant parameters:

BEFORE FAILURE AFTER FAILURE Loop 1 TAVE (1-TI-412): 571F 571F Loop 2 TAVE (1-TI-422): 570F 569F Loop 3 TAVE (1-TI-432): 570F 607F Loop 4 TAVE (1-TI-442): 569F 570F Which of the following describes the response of the plant?

Charging flow will initially A. increase and actual Pressurizer level will stabilize at a higher level.

B. increase and actual Pressurizer level will rise causing a Reactor Trip.

C. decrease and actual Pressurizer level will stabilize at a lower level.

D. decrease and actual Pressurizer level will lower until Letdown isolates.

Proposed Answer: A Page 18 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. The increase in average TAVE will raise the Pressurizer Level Control Setpoint, thus Charging flow will increase and Pressurizer level will stabilize at the new setpoint.

B. Incorrect. Plausible because the increase in average TAVE will raise the Pressurizer Level Control Setpoint, thus Charging flow will increase, however, the new level setpoint will not be greater than 60% thus a Reactor Trip will not occur.

C. Incorrect. Plausible because the increase in average TAVE will raise the Pressurizer Level Control Setpoint, an operator misconception could lead to a belief that the setpoint will lower and Charging flow will decrease until Pressurizer level stabilizes at the new setpoint.

D. Incorrect. Plausible because the increase in average TAVE will raise the Pressurizer Level Control Setpoint, an operator misconception could lead to a belief that the setpoint will lower and Charging flow will decrease until Pressurizer level lowers to 17% and Letdown isolates.

Technical Reference(s) ABN-704, Steps 2.1 & 2.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to a Pressurizer Level Instrument Malfunction in accordance with ABN-706, Pressurizer Level Instrument Malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Page 19 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-704, Step 2.1 Revision # 10 Page 20 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-704, Step 2.1 Revision # 10 Page 21 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 028 K3.01 Importance Rating 3.3 Hydrogen Purge Control System: Knowledge of the effect that a loss or malfunction of the HPS will have on the following:

Hydrogen concentration in containment Proposed Question: Common 32 Given the following conditions:

Unit 2 has experienced a Small Break Loss of Coolant Accident.

Through various failures core cooling was lost for several minutes and transition to FRC-0.2B, Degraded Core Cooling, was required.

Core cooling has now been restored and operation is continuing in EOS-1.2B, Post LOCA Cooldown and Depressurization.

Containment Hydrogen concentration has just been determined as 2% in dry air.

Containment pressure is currently 8 psig and stable which precludes use of the Hydrogen Purge System.

If Containment pressure cannot be lowered sufficiently to establish Hydrogen Purge, what are the potential effects on the Containment atmosphere?

During the coming months Hydrogen concentration will A. continue to increase as a result of the zirconium/water reaction.

B. continue to increase as a result of corrosion off gassing.

C. slowly decrease from recombination of hydrogen and oxygen.

D. slowly decrease as a result of Reactor Coolant System degassing.

Proposed Answer: B Page 22 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it is implied that core temperature has exceeded 750°F but has remained less than 1200°F otherwise FRC-0.1B, Response to Inadequate Core Cooling, would have had to be entered. The zirc/water reaction does not start until approximately 2300°F.

B. Correct. In accordance with EOS-1.2B, Step 34 Bases, hydrogen production results from the corrosion of construction materials. This hydrogen production will continue for a significant duration.

C. Incorrect. Plausible because some natural recombination between free hydrogen and oxygen may occur but without a hydrogen recombination system this amount will be negligible, however, hydrogen production will continue to increase the hydrogen concentration.

D. Incorrect. Plausible because RCS degassing is a normal plant evolution for entering outages, however, the Unit is not in an alignment or configuration to accomplish RCS degassing.

Additionally, RCS degassing would not lower the Containment hydrogen concentration, only potentially prevent it from rising as much from hydrogen produced in the core.

Technical Reference(s) EOS-1.2B, Attachment 5, Step 34 Bases Attached w/ Revision # See FRC-0.2B, Core Cooling CSFST Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a Step, NOTE or CAUTION from EOS-1.2, Post LOCA Cooldown and Depressurization, STATE the reason or actions to be taken for the Step, NOTE or CAUTION.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 10 55.43 Page 23 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.2B, Attachment 5, Step 34 Bases Revision # 8 Page 24 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRC-0.2B, Core Cooling CSFST Revision # 8 Page 25 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 034 A1.02 Importance Rating 2.9 Fuel Handling Equipment System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including: Water level in the refueling canal Proposed Question: Common 33 Given the following conditions:

Unit 1 is in a Refueling outage, and fuel transfer activities are in progress.

Refueling Cavity level begins lowering.

Annunciator 1-ALB-2A, Window 2.7 - RX CAV SMP LVL HI-HI, is in alarm.

All radiation levels are normal and there are NO Radiation Monitors in alarm.

Which of the following should be performed?

A. Ensure the Fuel Transfer Cart is in the Containment Building.

Close the Transfer Tube Gate Valve.

Commence filling the Refueling Cavity.

B. Ensure the Fuel Transfer Cart is in the Fuel Building.

Close the Transfer Tube Gate Valve.

Place all Fuel Assemblies in a safe location.

C. Ensure the Fuel Transfer Cart is in the Containment Building.

Open the Transfer Tube Gate Valve.

Place all Fuel Assemblies in a safe location.

D. Ensure the Fuel Transfer Cart is in the Fuel Building.

Open the Transfer Tube Gate Valve.

Commence filling the Refueling Cavity.

Proposed Answer: B Page 26 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the actions include filling the Refueling Cavity and closing the Transfer Tube Gate Valve, however, the Fuel Transfer Cart must be in the Fuel Building to close the gate valve.

B. Correct. These are all required actions from ABN-909.

C. Incorrect. Plausible because all Fuel Assemblies are to be placed in a safe location and if believed that the Transfer Tube Gate Valve was closed, opening the valve would refill the Refueling Cavity adding significant time to allow for recovery.

D. Incorrect. Plausible because ensuring the Fuel Transfer Cart is in the Fuel Building is correct and the need to fill the Refueling Cavity is evident. Opening of the gate valve would fill the Refueling Cavity if the gate valve were not already open.

Technical Reference(s) ABN-909, Section 2.0 Attached w/ Revision # See ABN-909, Step 2.3.2 & 2.3.3 RNO Comments / Reference ALM-0021A, 1-ALB-2A, Window 2.7 Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of conducting fuel handling.

Question Source: Bank #

Modified Bank # RFO.FH5.OB11.01 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10, 13 55.43 Page 27 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-909, Section 2.0 Revision # 8 Page 28 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-909, Step 2.3.2 & 2.3.3 RNO Revision # 8 Page 29 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0021A, 1-ALB-2A, Window 2.7 Revision # 9 Comments /

Reference:

From RFO.FH5.OB117.01 Revision # N/A Given the following conditions:

Unit 1 is in a Refueling outage, the Fuel Transfer Tube Gate Valve is open and fuel transfer activities are in progress.

Spent Fuel Pool #1 level begins lowering.

Annunciator 1-ALB-2A, Window 3.8 - FB PIT EL-800 SMP LVL HI-HI, is in alarm.

All radiation levels are normal and there are NO Radiation Monitors in alarm.

Which of the following should be performed?

A. Ensure the Fuel Transfer Cart is in the Containment Building, close the Transfer Tube Gate Valve, and commence filling Spent Fuel Pool #1.

B. Ensure the Fuel Transfer Cart is in the Fuel Building, close the Transfer Tube Gate Valve, and place all Fuel Assemblies in a safe location.

C. Ensure the Fuel Transfer Cart is in the Containment Building, open the Transfer Tube Gate Valve, and place all Fuel Assemblies in a safe location.

D. Ensure the Fuel Transfer Cart is in the Fuel Building, open the Transfer Tube Gate Valve, and commence filling Spent Fuel Pool #1.

Page 30 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 035 K6.03 Importance Rating 2.6 Steam Generator System: Knowledge of the effect of a loss or malfunction on the following will have on the SGS: SG level detector Proposed Question: Common 34 Given the following conditions:

Unit 2 is operating at 50% power.

2-FS-510C, SG 1 FW FLO CHAN SELECT, is in the 2-FY-510C position.

2-FS-512C, SG 1 STM FLO CHAN SELECT, is in the 2-FY-512B position.

2-LS-519C, SG 1 LVL CHAN SELECT, is in the 2-LQY-551 position.

Steam Generator (SG) 2-01 level begins to lower.

All other SG levels are stable at approximately 64%.

Which of the following is the cause of the lowering level in Steam Generator 2-01?

A. 2-LT-551, SG 1 LVL (NR) CHAN I, has failed high.

B. 2-PT-514A, MSL 1 PRESS CHAN I, has failed high.

C. 2-FT-512A, SG 1 STM FLO CHAN I, has failed high.

D. 2-FT-510A, SG 1 FW FLO CHAN I, has failed low.

Proposed Answer: A Explanation:

A. Correct. The controlling level channel failing high results in a decrease in feed flow to restore level to program. The decrease in feed flow causes actual level in the SG to decrease.

B. Incorrect. Plausible because this is an input to level control, but a failed high steam pressure channel causes a corresponding increase in steam flow and an increase in feed flow, accompanied by an increasing actual level.

C. Incorrect. Plausible because this is an input to level control, but a failed high steam flow channel causes an increase in feed flow, accompanied by an increasing actual level.

D. Incorrect. Plausible because this is an input to level control, but a failed low feed flow channel causes an increase in feed flow, accompanied by an increasing actual level.

Page 31 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) ABN-710, Section 2.2 Attached w/ Revision # See ABN-709, Section 2.2 Comments / Reference ABN-707, Section 2.2 ABN-708, Section 2.2 Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Steam Generator Water Level Control System and PREDICT the system response.

Question Source: Bank # SYS.SN1.OB04.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments /

Reference:

From ABN-710, Section 2.2 Revision # 10 Page 32 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-709, Section 2.2 Revision # 8 Page 33 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-707, Section 2.2 Revision # 6 Page 34 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-708, Section 2.2 Revision # 6 Page 35 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 041 G 2.1.25 Importance Rating 3.9 Steam Dump/Turbine Bypass Control System: Conduct of Operations: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Proposed Question: Common 35 Given the following condition on Unit 1:

During a plant cooldown and depressurization, Reactor Coolant System (RCS) temperature is being stabilized at 508°F.

Assuming minimal T between the Reactor Coolant System and Steam Generator, which of the following identifies the proper pot setting for PK-507, STM DUMP PRESS CTRL, to maintain RCS temperature with the Steam Dump System in AUTO?

A. 2.37 B. 3.97 C. 4.09 D. 4.20 Proposed Answer: B Explanation:

A. Incorrect. Plausible if pressure of 508 psig is read directly off the graph prior to converting to saturation pressure for 508°F. Setting for 508 psig is 2.37.

B. Correct. A temperature of 508°F corresponds to a saturation pressure of 731.4 psia.

731.4 psia is 716.7 psig which equals a potentiometer setting of 3.97.

C. Incorrect. Plausible if pressure is not converted from psia to psig prior to calculating setpoint.

Setting for 731.4 psig is 4.09.

D. Incorrect. Plausible if pressure is converted to psig in wrong direction. 731.4 psia wrongly converted would yield 746.1 psig. Setting for 746.1 is 4.20.

Technical Reference(s) TDM-501A, 1-PK-507 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables & TDM-501A Learning Objective: EXPLAIN the instrumentation and controls of the Steam Dump System and PREDICT the system response.

Page 36 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # SYS.SD1.OB04.008 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 7, 10, 14 55.43 Page 37 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From TDM-501A, 1-PK-507 Revision # 5 Page 38 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SYS.SD1.OB04.008 Revision # N/A During a plant cooldown and depressurization, Reactor Coolant System (RCS) temperature is being stabilized at 500°F.

Assuming minimal T between the Reactor Coolant System and Steam Generator, which of the following identifies the proper pot setting for PK-507, STM DUMP PRESS CTRL, to maintain RCS temperature with the Steam Dump System in AUTO?

A. 3.58 B. 3.82 C. 4.43 D. 4.63 Page 39 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 045 K5.17 Importance Rating 2.5 Main Turbine Generator System: Knowledge of the operational implications of the following concepts as the apply to the MTG System: Relationship between moderator temperature coefficient and boron concentration in RCS as TG load increases Proposed Question: Common 36 Which of the following is the reason TAVE lowers less at end-of-life (EOL) conditions than at beginning-of-life (BOL) conditions when a 10% Main Turbine step increase in load occurs?

During EOL conditions, Moderator Temperature Coefficient is A. less negative with a higher boron concentration.

B. less negative with a lower boron concentration.

C. more negative with a lower boron concentration.

D. more negative with a higher boron concentration.

Proposed Answer: C Explanation:

A. Incorrect. Plausible if thought that a less negative MTC would result in a smaller temperature change and believed that boron concentration increased. CPNPP does increase boron concentration for the first 1/4 of the cycle and then exhibits a steady decrease to EOL.

B. Incorrect. Plausible because the boron concentration does lower, however, this results in a more negative MTC.

C. Correct. The MTC becomes more negative at EOL with a lower boron concentration, this results in a much smaller temperature change in order to compensate for the same amount of reactivity.

D. Incorrect. Plausible because MTC becomes more negative at EOL and believed that boron concentration increased. CPNPP does increase boron concentration for the first 1/4 of the cycle and then exhibits a steady decrease to EOL.

Technical Reference(s) NDR Figures 4.1 & 5.25 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the effect on the magnitude of the moderator temperature coefficient of reactivity from changes in moderator temperature, boron concentration, and core age.

Page 40 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From MCO.TA8.OB101.006 Revision # N/A Which of the following is the reason TAVE lowers less at end-of-life (EOL) conditions than at beginning-of-life (BOL) conditions when a 10% Main Turbine step rise in load is implemented?

During EOL conditions, A. Moderator Temperature Coefficient is less (less negative).

B. pressure decrease due to the Pressure Coefficient is less.

C. Moderator Temperature Coefficient is more (more negative).

D. Doppler Coefficient is less (less negative).

Page 43 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 071 K4.05 Importance Rating 2.7 Waste Gas Disposal System: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Point of release Proposed Question: Common 37 Which of the following Radiation Monitors will cause HCV-014, Waste Gas Discharge Control Valve to automatically close?

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.

Proposed Answer: A 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 Waste Gas Radiation Monitor (WGS083) monitors downstream of HCV-0014, but neither of these monitors will 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 Waste Gas Radiation Monitor (WGS083) 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) ALM-3200, Attachment 3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operations of the Gaseous Waste System.

Page 44 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # SYS.RWS.OB04.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11, 13 55.43 Comments /

Reference:

From ALM-3200, Attachment 3 Revision # 4 Page 45 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 086 K1.03 Importance Rating 3.4 Fire Protection System: Knowledge of the physical connections and/or cause-effect relationships between the Fire Protection System and the following systems: AFW system Proposed Question: Common 38 Given the following conditions:

Unit 1 has tripped.

All Auxiliary Feedwater (AFW) flow has been lost due to low Condensate Storage Tank (CST) level.

Which of the following lists the priority for restoration of AFW per ABN-305, Auxiliary Feedwater System Malfunction?

1. Fill the CST from Main Condenser Hotwell.

2. Fill the CST from Fire Protection Water.

3. Align Station Service Water to AFW Pump suctions.

A. 1, 2, 3.

B. 2, 1, 3.

C. 3, 2, 1.

D. 1, 3, 2.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because the 1st alignment is correct, however, SSW takes priority over Fire Protection Water.

B. Incorrect. Plausible because the Main Condenser Hotwell has priority over SSW, however, the Fire Protection Water is the last source used.

C. Incorrect. Plausible because SSW has priority over Fire Protection Water, however, the Main Condenser Hotwell is the 1st source used.

D. Correct. This is the correct order as listed in ABN-305.

Technical Reference(s) ABN-305, Steps 5.3.5 to 5.3.11 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 46 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE the response to Inadequate Condensate Storage Tank Level in accordance with ABN-305, Auxiliary Feedwater System Malfunction.

Question Source: Bank # ABN.305.OB05.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments /

Reference:

From ABN-305, Steps 5.3.5 to 5.3.8 Revision # 7 Page 47 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-305, Steps 5.3.9 Revision # 7 Page 48 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-305, Steps 5.3.10 Revision # 7 Page 49 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-305, Steps 5.3.11 Revision # 7 Page 50 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 007 EK3.01 Importance Rating 4.0 Reactor Trip - Stabilization - Recovery: Knowledge of the reasons for the following as the apply to a reactor trip: Actions contained in EOP for reactor trip Proposed Question: Common 39 Given the following conditions:

A Main Steam Line Break outside Containment has occurred on Unit 2.

The Reactor was tripped and Safety Injection actuated.

Containment Spray was inadvertently actuated.

Which of the following describes the required actions and why?

A. Trip all RCPs per EOP-0.0B, Reactor Trip or Safety Injection, due to water spray causing damage to RCPs.

B. Trip all RCPs per EOP-0.0B, Reactor Trip or Safety Injection, due to a loss of CCW cooling to the RCPs.

C. Reset the Containment Spray and Phase B signals and realign CCW to RCPs per Attachment 9 of EOP-0.0B, Reactor Trip or Safety Injection, due to a loss of CCW cooling to the RCPs.

D. Reset the Containment Spray and Phase B signals and stop Containment Spray Pumps per Attachment 9 of EOP-0.0B, Reactor Trip or Safety Injection, due to water spray causing damage to RCPs.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because the RCPs must be tripped, however, the reason is due to loss of Component Cooling Water.

B. Correct. Phase B isolates Component Cooling Water to the RCPs.

C. Incorrect. Plausible because these actions may be performed later in the procedure but Containment Spray was inadvertently actuated and RCPs must be tripped.

D. Incorrect. Plausible because CCW cooling is lost to the RCPs, however, Containment Spray would not be reset per Attachment 9 if RCP's are running without cooling water.

Technical Reference(s) EOP-0.0B, Step 7 RNO Attached w/ Revision # See EOP-0.0B, Attachment 10, Step 7 Bases Comments / Reference Page 51 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: DISCUSS EOP-0.0, Reactor Trip or Safety Injection including the Purpose, Applicability, Symptoms/Entry Conditions, Operator Actions, Bases, Foldout Pages and Attachments.

Question Source: Bank # ERG.E0A.OB07.003 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 52 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0B, Step 7 RNO Revision # 8 Page 53 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0B, Attachment 10, Step 7 Bases Revision # 8 Page 54 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 008 AK1.02 Importance Rating 3.1 Pressurizer Vapor Space Accident: Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure Proposed Question: Common 40 Given the following conditions:

A Pressurizer Power Operated Relief Valve (PORV) has stuck open.

Reactor Coolant System (RCS) pressure is 1500 psig.

Containment pressure is 2 psig and rising.

RCS break flow is approximately 140 GPM.

Subsequently, the PORV cannot be isolated.

RCS pressure continues to lower and is currently 750 psig.

Containment pressure is 4 psig and rising.

Which of the following is the approximate value for RCS break flow at this time?

Approximately A. 35 GPM.

B. 70 GPM.

C. 100 GPM.

D. 140 GPM.

Proposed Answer: C Explanation:

A. Incorrect. Plausible if thought that the differential pressure is proportional to the square root of flow.

B. Incorrect. Plausible if thought that flow is directly proportional to differential pressure.

C. Correct. Flow is proportional to the square root of the differential pressure, therefore, 140 GPM times the square root of 0.5 equals 0.707. 140 x 0.707 equals approximately 100 GPM.

D. Incorrect. Plausible if thought that flow was constant through a stuck open valve.

Technical Reference(s) NRC Generic Fundamentals Equation Sheet Attached w/ Revision # See Comments / Reference Page 55 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: NRC Generic Fundamentals Equation Sheet Learning Objective: ANALYZE the Thermal-Hydraulic theory of the LOCA.

Question Source: Bank #

Modified Bank # MCO.TAA.OB02.001 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 14 55.43 Page 56 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From NRC Generic Fundamentals Equation Sheet Revision # N/A Page 57 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From MCO.TAA.OB02.001 Revision # N/A Given the following conditions:

A Pressurizer Power Operated Relief Valve (PORV) has stuck open.

Reactor Coolant System (RCS) pressure is 1400 PSIG.

Containment pressure is 2 PSIG and rising.

RCS break flow is approximately 100 GPM.

Subsequently, the PORV cannot be isolated.

RCS pressure continues to lower and is currently 700 PSIG.

Containment pressure is 4 PSIG and rising.

Which of the following is the approximate value for RCS break flow at this time?

A. 30 GPM.

B. 50 GPM.

C. 70 GPM D. 90 GPM Page 58 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 009 EK2.03 Importance Rating 3.0 Small Break LOCA: Knowledge of the interrelations between the small break LOCA and the following: Steam Generators Proposed Question: Common 41 Given the following conditions:

A Small Break Loss of Coolant Accident has occurred on Unit 1.

EOP-1.0A, Loss of Reactor or Secondary Coolant, is in progress.

Containment pressure is 3 psig and slowly rising.

Which of the following is the purpose for checking intact Steam Generator (SG) narrow range water levels greater than or equal to 43%?

A. SG water levels are sufficient to cover a ruptured SG tube.

B. An excessive SG cooldown does not complicate the recovery procedure.

C. Sufficient SG water inventory is available to provide an adequate heat sink.

D. SG water level instrumentation is functioning properly and the AFW Throttle Valves are adjusted correctly.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because 43% is required for this reason when a SGTR is in progress.

B. Incorrect. Plausible because an excessive cooldown could complicate the recovery and having SG tubes in direct contact with the steam space in the SG can lead to rapid SG pressure fluctuations and corresponding RCS temperature changes.

C. Correct. This level is required without adverse containment parameters to ensure an adequate secondary heat sink which is necessary in most SBLOCA recoveries.

D. Incorrect. Plausible because ensuring proper instrumentation and AFW control for further recovery actions could be necessary, however, other EOP actions verify proper operation of these components.

Technical Reference(s) EOP-1.0A, Attachment 4, Step 3 Bases Attached w/ Revision # See EOP-3.0A, Attachment 6, Step 4 Bases Comments / Reference Proposed references to be provided during examination: None Learning Objective: DISCUSS the operator actions, including all cautions, notes, RNOs and bases associated with EOP-1.0, Loss of Reactor or Secondary Coolant.

Page 59 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # EO1.XG3.OB406.001 Modified Bank # (Note changes or attach parent)

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

Reference:

From EOP-1.0A, Attachment 4, Step 3 Bases Revision # 8 Page 60 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-3.0A, Attachment 6, Step 4 Bases Revision # 8 Page 61 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 011 EA1.04 Importance Rating 4.4 Large Break LOCA: Ability to operate and monitor the following as they apply to a Large Break LOCA: ESF actuation system in manual Proposed Question: Common 42 Given the following conditions on Unit 2:

A Safety Injection and Containment Spray Actuation occurred as a result of a Large Break Loss of Coolant Accident.

Safety Injection has been RESET.

EOS-1.3B, Transfer to Cold Leg Recirculation, was completed with Containment pressure still at 20 psig.

A loss of power to both 1E Safeguards Buses occurs and the Emergency Diesels start and load.

Which of the following choices below indicates pumps that must be manually started?

1. Centrifugal Charging Pump

2. Safety Injection Pump

3. Residual Heat Removal Pump

4. Containment Spray Pump

5. Station Service Water Pump

6. Component Cooling Water Pump A. 1, 2, 3 B. 2, 3, 4 C. 3, 4, 5 D. 4, 5, 6 Proposed Answer: B Page 62 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the Centrifugal Charging Pump will start, however, Safety Injection and Residual Heat Removal Pumps must be manually started.

B. Correct. Given the conditions listed, these are the pumps that must be manually started.

C. Incorrect. Plausible because the Station Service Water Pump will start, however, Residual Heat Removal and Containment Spray Pumps must be manually started.

D. Incorrect. Plausible because the Station Service Water and Component Cooling Water Pumps will start, however, Containment Spray Pumps must be manually started.

Technical Reference(s) ABN-602, Attachment 2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal, and emergency operation of the Safety Injection and Blackout Sequencers.

Question Source: Bank #

Modified Bank # SYS.ES3.OB06.001 (Note changes or attach parent)

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

Reference:

From ABN-602, Attachment 2 Revision # 7 Page 63 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Attachment 2 Revision # 7 Comments /

Reference:

From ABN-602, Attachment 2 Revision # 7 Page 64 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Attachment 2 Revision # 7 Comments /

Reference:

From SYS.ES3.OB06.001 Revision # N/A Given the following conditions on Unit 2:

A Safety Injection and Containment Spray Actuation occurred as a result of a Large Break LOCA.

EOS-1.3B, Transfer to Cold Leg Recirculation was completed with Containment pressure still at 20 psig.

A loss of power to both 1E Safeguards Buses occurs and the Emergency Diesels start and load.

Which of the following choices below indicates pumps that will automatically start?

1. Centrifugal Charging Pump

2. Safety Injection Pump

3. Residual Heat Removal Pump

4. Containment Spray Pump

5. Station Service Water Pump

6. Component Cooling Water Pump

7. Motor Driven Auxiliary Feedwater Pump

8. Turbine Driven Auxiliary Feedwater Pump A. 1, 2, 3, 4 B. 2, 3, 4, 5 C. 4, 5, 6, 7 D. 1, 5, 6, 7, 8 Page 65 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 015/17 G 2.4.20 Importance Rating 3.8 RCP Malfunctions: Emergency Procedures/Plan: Knowledge of the operational implications of EOP warnings, cautions, and notes Proposed Question: Common 43 Given the following conditions:

A Small Break Loss of Coolant Accident has occurred on Unit 1.

Both Centrifugal Charging Pumps and both Safety Injection Pumps failed to start automatically or manually.

FRC-0.2A, Response to Degraded Core Cooling, is in progress due to a Critical Safety Function Status Tree ORANGE path.

Attempts to start the Positive Displacement Pump and restore Charging flow have been unsuccessful.

Current plant parameters are as follows:

Reactor Coolant System pressure is 1300 psig and slowly lowering.

Core Exit Thermocouples are 765F and slowly rising.

All Reactor Coolant Pumps (RCP) are running.

Seal Injection flow to all RCPs is 0 gpm.

Containment pressure is 6 psig and slowly rising.

Annunciator 1-ALB-5B, Window 3.5 - RCP 3 VIBR HI, is in ALARM.

RCP 1-03 shaft vibration is 17 mils and increasing at a rate of 3 mils/hr.

For the current plant conditions, which of the following is proper RCP operation?

Stop A. RCP 1-03 due to high shaft vibration.

B. all RCPs due to a loss of RCS subcooling.

C. all RCPs to minimize heat addition to the RCS.

D. RCP 1-04 to minimize likelihood of pump damage.

Proposed Answer: D Page 66 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because ABN-101 requires the RCP with shaft vibration > 15 mils and vibration increasing at a rate > 1mil/hr.to be secured, however, the NOTE prior to Step 1 of FRC-0.2A requires that RCPs should be maintained running until FRC-0.2A directs stopping the RCPs. Additionally, the amplitude trip rate of 1 mil per hour is based on operation at 100% power.

When not in MODE 1, the amplitude rate of change may be ignored.

B. Incorrect. Plausible because with RCS temperature greater than 750F, two-phase flow will exist and subcooling will be lost regardless of RCS pressure (temperature is greater than the critical temperature of 705.47F). The Foldout Page of EOP-0.0A directs securing RCPs when RCS subcooling is < 25F AND at least one CCP or SI pump is running, which is not the case.

Additionally, the NOTE prior to Step 1 of FRC-0.2A requires that RCPs should be maintained running until FRC-0.2A directs stopping the RCPs.

C. Incorrect. Plausible because this is the bases for securing RCPs in FRH-0.1A, however, FRC-0.2A requires RCPs to continue to operate to lower the likelihood of causing inadequate core cooling.

D. Correct. A RCP is stopped to reserve it for future use. RCP 1-04 is chosen since it provides the most effective Pressurizer Spray flow.

Technical Reference(s) FRC-0.2A, Steps 1 NOTE & 7 Attached w/ Revision # See FRH-0.1A, Step 6 Comments / Reference EOP-0.0A, Attachment 1.A ABN-101, Step 6.3.1 & NOTE Proposed references to be provided during examination: None Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in EOS-1.2A, Post LOCA Cooldown and Depressurization.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 67 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRC-0.2A, Step 1 Revision # 8 Page 68 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRC-0.2A, Step 7 Revision # 8 Page 69 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1A, Step 6 Revision # 8 Page 70 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Attachment 1.A Revision # 8 Comments /

Reference:

From ABN-101, Step 6.3.1 & NOTE Revision # 10 Page 71 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 022 AA2.03 Importance Rating 3.1 Loss of Reactor Coolant Makeup: Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Failures of flow control valve or controller Proposed Question: Common 44 Given the following conditions:

Unit 1 is operating at 95% power during a power ramp.

1-TI-412A, AVE TAVE TREF DEV indicates minus (-) 2.0°F and lowering.

SOP-104A, Reactor Make-up and Chemical Control System, is in progress to perform a 200 gallon dilution for temperature control.

43/1-MU, RCS MU MODE SELECT, was placed in DILUTE.

When 1/1-MU, RCS MU MAN ACT, was placed in START, makeup flow did NOT commence.

PROMPT Team reports that it will take approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair the 43/1-MU, RCS MU MODE SELECT, switch.

Control Rods are in MANUAL with Control Bank D @ 220 steps.

Which of the following actions should be taken per ABN-105, Chemical and Volume Control System Malfunction?

A. Manually align for Dilution.

B. Raise Main Turbine Load to adjust Reactor Coolant System temperature.

C. Manually align for Alternate Dilution.

D. Withdraw Control Rods to adjust Reactor Coolant System temperature.

Proposed Answer: A Page 72 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. With the RMU Mode Select Switch not functioning, the only option available to dilute is to perform a Manual Dilution.

B. Incorrect. Plausible because adjusting Turbine Load will result in a change in RCS temperature, but temperature is low requiring dilution, and raising Turbine Load will lower it even further.

C. Incorrect. Plausible because Alternate Dilution is a viable method of diluting the RCS, but Alternate Dilution is not performed per ABN-105.

D. Incorrect. Plausible because withdrawing Control Rods would raise temperature, but Control Bank D is already above the normal 100% position and little if any temperature increase would be expected if Control Rods were withdrawn further.

Technical Reference(s) ABN-105, Step 6.3.1 RNO Attached w/ Revision # See ABN-105, Steps 6.3.2, 6.3.3, 6.3.4 & 6.3.6 Comments / Reference SOP-104A, Section 5.2.2 Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Reactor Makeup System.

Question Source: Bank #

Modified Bank # SYS.CS2.OB05.002 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 73 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Step 6.3.1 RNO Revision # 7 Page 74 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Steps 6.3.2 & 6.3.3 Revision # 7 Page 75 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Step 6.3.4 Revision # 7 Page 76 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Step 6.3.6 Revision # 7 Page 77 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-104A, Section 5.2.2 Revision # 14 Page 78 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SYS.CS2.OB05.002 Revision # N/A Given the following conditions:

Unit 1 is operating at 95% power during a power ramp.

SOP-104A, Reactor Make-up and Chemical Control System, is in progress for a group for temperature control.

43/1-MU, RCS MU MODE SELECT, was placed in DILUTE.

When 1/1-MU, RCS MU MAN ACT, was placed in START, makeup flow did NOT commence.

PROMPT Team reports that it will take approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to troubleshoot and repair the problem Which of the following actions should be taken?

A. Refer to ABN-105, Chemical and Volume Control System Malfunction, and perform a Manual Dilution.

B. Raised Main Turbine Load per IPO-003A, Power Operation, to adjust Reactor Coolant System temperature.

C. Refer to ABN-105, Chemical and Volume Control System Malfunction, and perform an Alternate Dilution.

D. Continue in SOP-104A, Reactor Makeup and Chemical Control System, and perform an Alternate Dilution.

Page 79 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 025 AK2.02 Importance Rating 3.2 Loss of RHR System: Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:

LPI or Decay Heat Removal/RHR pumps Proposed Question: Common 45 Given the following conditions:

A Large Break Loss of Coolant Accident is in progress on Unit 1.

A transition to EOS-1.3A, Transfer to Cold Leg Recirculation, is being initiated.

Residual Heat Removal Pump 1-01 tripped just before the transition was made to EOS-1.3A, Transfer to Cold Leg Recirculation.

Which of the following actions should be taken?

A. Transition to ECA-1.1A, Loss of Emergency Coolant Recirculation, and secure the running Residual Heat Removal Pump while maintaining both Centrifugal Charging Pumps and both Safety Injection Pumps running.

B. Continue with the transfer to Cold Leg Recirculation and remain in EOS-1.3A, Transfer to Cold Leg Recirculation, but only align one Centrifugal Charging Pump and one Safety Injection Pump for recirculation.

C. Transition to ECA-1.1A, Loss of Emergency Coolant Recirculation, and reduce injection flow to one Residual Heat Removal Pump, one Centrifugal Charging Pump, and one Safety Injection Pump running.

D. Continue with the transfer to Cold Leg Recirculation and remain in EOS-1.3A, Transfer to Cold Leg Recirculation, aligning both Centrifugal Charging Pumps and both Safety Injection Pumps for recirculation.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because entry into ECA-1.1A is based on the inability to establish a flowpath from the Containment Sump. With one RHR Pump running, transfer to EOS-1.3A will be successful.

B. Incorrect. Plausible if thought that one RHR Pump would not be able to supply both Trains, however, procedurally this action is allowed.

C. Incorrect. Plausible because entry into ECA-1.1A is based on the inability to establish at least one flowpath from the Containment Sump, however, this option is available.

D. Correct. EOS-1.3A assumes that RHR Pumps are not operating upon procedure entry; therefore, loss of an RHR Pump would not prevent the transition as stated.

Page 80 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) EOS-1.3A, Step 3 RNO Attached w/ Revision # See EOS-1.3A, Applicability Comments / Reference ECA-1.1A, Entry Conditions Proposed references to be provided during examination: None Learning Objective: Given a set of plant conditions, IDENTIFY the proper transitions through/out of EOS-1.3, Transfer to Cold Leg Recirculation.

Question Source: Bank # ERG.E13.OB06.003 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 81 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.3A, Step 3 RNO Revision # 8 Page 82 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.3A, Applicability Revision # 8 Comments /

Reference:

From ECA-1.1A, Entry Conditions Revision # 8 Page 83 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Page 84 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 026 AK3.02 Importance Rating 3.6 Loss of Component Cooling Water: Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS Proposed Question: Common 46 Which of the following describes the basis for the Component Cooling Water (CCW) System valve realignment upon receipt of a Containment Isolation Phase B actuation?

A. Reduces Diesel Generator loading requirements with Containment Spray in operation.

B. Reduces heat load on CCW System by eliminating unnecessary cooling requirements.

C. Ensures CCW System is not an additional potential radioactive release path from Containment.

D. Ensures that CCW System meets design cooling function for loads within Containment during Design Basis Loss of Coolant Accident.

Proposed Answer: C Explanation:

A. Incorrect. Plausible if thought that Emergency Diesel Generator load changes due to a Phase B Isolation.

B. Incorrect. Plausible because there would be a reduction in heat load on the CCW System, however, a heat load reduction is not required to meet design load limits.

C. Correct. Isolation of Component Cooling Water is required for Containment Integrity.

D. Incorrect. Plausible because the CCW System has a heat removal function during a DBA LOCA, however, there are no loads associated with CCW operating in Containment.

Technical Reference(s) EOP-0.0A, Attachment 10, Step 7 Bases Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Component Cooling Water System.

Question Source: Bank # SYS.CC1.OB04.010 Modified Bank # (Note changes or attach parent)

New Page 85 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments /

Reference:

From EOP-0.0A, Attachment 10, Step 7 Bases Revision # 8 Page 86 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 027 AA1.03 Importance Rating 3.6 Pressurizer Pressure Control System Malfunction: Ability to operate and / or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Pressure control when on a steam bubble Proposed Question: Common 47 Given the following conditions:

Unit 1 is at 100% power.

The controlling Pressurizer Pressure Channel has failed high.

Initial Operator Actions have been performed per ABN-705, Pressurizer Pressure Control Malfunction.

Which of the following is the next appropriate action to take based on this failure?

A. Declare the associated PORV INOPERABLE.

B. Transfer control to an alternate controlling channel.

C. Remove power to the associated PORV Block Valve.

D. Verify PCIP 2.6, PRZR PRESS SI BLK PERM P-11 is LIT.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because the controlling channel has failed high, however, this does not render the PORV INOPERABLE.

B. Correct. Once the failed channel is removed from control an alternate channel is selected to restore automatic pressure control.

C. Incorrect. Plausible because it may be desirable to remove power to the PORV Block Valve, however, the NOTE in Section 2.3 states that this should not be performed per this procedure section.

D. Incorrect. Plausible because P-11 status is verified in ABN-705, however, the light should be DARK.

Technical Reference(s) ABN-705, Sections 2.1 & 2.3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 87 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE the response to a Pressurizer Pressure Instrument Malfunction in accordance with ABN-705, Pressurizer Pressure Malfunction.

Question Source: Bank # ABN.705.OB01.013 Modified Bank # (Note changes or attach parent)

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

Reference:

From ABN-705, Section 2.2 Revision # 12 Page 88 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-705, Section 2.3 Revision # 12 Page 89 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 029 EK1.02 Importance Rating 2.6 ATWS: Knowledge of the operational implications of the following concepts as they apply to the ATWS: Definition of reactivity Proposed Question: Common 48 Given the following conditions:

An Anticipated Transient Without Trip (ATWT) event is in progress on Unit 1.

FRS-0.1A, Response to Nuclear Power Generation/ATWT is in progress and the Reactor is still NOT tripped.

Boration CANNOT be initiated because of blockage in the Boration flowpaths.

All Power Range Channels indicate 6%.

Startup rate is zero on both Intermediate Range Channels.

Average Core Exit Thermocouple temperature is 580°F and slowly lowering.

Which of the following describes the operator actions under these conditions and the primary reason for taking these actions?

A. Transition to FRS-0.2A, Response to Loss of Core Shutdown, Step 1, Verify Containment Pressure Less Than 5 PSIG, as it is now the procedure and step in effect.

B. Remain in FRS-0.1A, Response to Nuclear Power Generation / ATWT, and allow RCS temperature to lower while continuing efforts to establish Emergency Boration.

A lower temperature will maintain an appropriate DNBR margin.

C. Transition to FRS-0.2A, Response to Loss of Core Shutdown. This is required by the Critical Safety Function SUBCRITICALITY Status Tree based on the current YELLOW path condition.

D. Remain in FRS-0.1A, Response to Nuclear Power Generation / ATWT, and allow the RCS to heat up while continuing efforts to establish Emergency Boration. The heatup will insert negative reactivity.

Proposed Answer: D Page 90 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because review of the SUBCRITICALITY Status Tree would indicate that this is a possible transition, however, exit conditions for FRS-0.1 have not been met.

B. Incorrect. Plausible because procedure entry is correct, however, actions include allowing the RCS to heat up and add negative reactivity.

C. Incorrect. Plausible because review of the SUBCRITICALITY Status Tree would indicate that this is the current CSFST condition, however, exit conditions for FRS-0.1 have not been met.

D. Correct. Remaining in FRS-0.1 and allowing the plant to heat up will insert negative reactivity.

Technical Reference(s) FRS-0.1A, CSFST Attached w/ Revision # See FRS-0.1A, Step 17 RNO Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the applicability of FRS-0.1, Response To Nuclear Generation /

ATWT regarding modes and the actions taken if the procedure is otherwise used.

Question Source: Bank # ERG.FS1.OB02.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam CPNPP 2010 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1, 5, 10 55.43 Page 91 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRS-0.1A, CSFST Revision # 8 Page 92 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRS-0.1A, Step 17 RNO Revision # 8 Page 93 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055 G 2.4.49 Importance Rating 4.6 Station Blackout: Emergency Procedures/Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls Proposed Question: Common 49 Given the following conditions:

ECA-0.0A, Loss of All AC Power, has been directly entered on Unit 1.

1/1-RTBAL, RX TRIP BKR, red light is LIT and green light is DARK.

1/1-RTBBL, RX TRIP BKR, red light is DARK and green light is LIT.

1-NI-35B, IR CURRENT CHAN 1, indicates 2 x 10-6 amps and lowering.

1-NI-36B, IR CURRENT CHAN 2, indicates 2 x 10-6 amps and lowering.

Which of the following actions should be performed next per ECA-0.0A, Loss of All AC Power?

A. Verify all Control Rod Position Bottom Lights - ON.

B. Place 1/1-RTC, RX TRIP BKR, in TRIP.

C. Verify all High Pressure Turbine Stop Valves - CLOSED.

D. Dispatch an NEO to locally trip Reactor Trip Breaker A.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because verifying all Rod Position Bottom Lights are on would be the next step in EOP-0.0A, however, all DRPI indication is lost on a Loss of All AC Power and that action is not contained in ECA-0.0A.

B. Incorrect. Plausible because if at least one of the Reactor Trip Breakers (RTBs) was not open this would be the next required action per ECA-0.0A, Step 1 RNO.

C. Correct. In accordance with ECA-0.0A, the Reactor has been verified tripped and the next action is to verify the Turbine is tripped per Step 2.

D. Incorrect. Plausible as this action is performed in FRS-0.1A when the Reactor has failed to trip from the Control Room and is also performed for a single RTB being closed in ECA-0.0A, Step 7 if the RTB fails to open from manual actuation.

Technical Reference(s) ECA-0.0A, Steps 1, 2, & 7 RNO Attached w/ Revision # See EOP-0.0A, Step 1 Comments / Reference Page 94 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: LIST the two IMMEDIATE ACTION steps of ECA-0.0, Loss of All AC Power.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

Reference:

From ECA-0.0A, Steps 1 & 2 Revision # 8 Page 95 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-0.0A, Step 7 RNO Revision # 8 Page 96 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Step 1 Revision # 8 Page 97 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056 AA1.32 Importance Rating 3.4 Loss of Offsite Power: Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power: PZR PORV hand switch Proposed Question: Common 50 Given the following conditions:

Unit 2 has experienced a Loss of Offsite Power.

EOS-0.2B, Natural Circulation Cooldown, is in progress.

Normal Letdown cannot be established since 1/2-LCV-459, LTDN ISOL VLV, has failed closed.

All other systems and components operated as required.

Which of the following actions must be performed to commence Reactor Coolant System depressurization following a Loss of Offsite Power per EOS-0.2B, Natural Circulation Cooldown?

Commence depressurization A. by opening 1/2-PCV-455A, PRZR PORV or 1/2-PCV-456, PRZR PORV.

B. by raising demand on 2-PK-455C, RC LOOP 4 PRZR SPRY VLV CTRL, to establish Normal Spray flow.

C. by opening 1/2-8145, PRZ AUX SPR VLV, to establish Auxiliary Spray flow.

D. by raising demand on 2-PK-455B, RC LOOP 1 PRZR SPRY VLV CTRL, to establish Normal Spray flow.

Proposed Answer: A Explanation:

A. Correct. In accordance with EOS-0.2B, Step 9.a RNO, one PORV should be opened to depressurize when Letdown cannot be established.

B. Incorrect. Plausible because this would be normal for pressure control with RCP 2-04 running, which is the preferred RCP to run first, however, with no RCPs running the driving head for spray flow does not exist.

C. Incorrect. Plausible because Auxiliary Spray is available, however, in EOS-0.2B Auxiliary Spray is not utilized if Letdown is not available.

D. Incorrect. Plausible because this would be normal for pressure control with RCP 2-01 running, however, with no RCPs running the driving head for spray flow does not exist.

Page 98 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) EOS-0.2B, Step 9.a RNO Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.2, Natural Circulation Cooldown.

ANALYZE the plant response and operator actions necessary to accurately complete Natural Circulation Cooldown.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

Reference:

From EOS-0.2B, Step 9.a RNO Revision # 8 Page 99 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.2B, Step 9.a RNO Revision # 8 Page 100 of 100 CPNPP NRC 2012 RO Written Exam Worksheet 26 to 50 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 058 AA2.02 Importance Rating 3.3 Loss of DC Power: Ability to determine and interpret the following as they apply to the Loss of DC Power: 125V DC bus voltage, low/critical low, alarm Proposed Question: Common 51 Given the following conditions:

Unit 1 is operating at 100% power with all systems in normal alignment.

1ED1/1-1/DSW, 125 VDC STATION BATTERY BT1ED1 DISCONNECT SWITCH, was placed in OFF.

Which of the following would provide the Control Room with indication of this condition?

A. Low Bus Voltage indicated on DC Bus 1ED1 voltmeter on CB-11.

B. SSII Train A alarms for SSW, ECCS, CS, MDAFW, DG PWR, SFTY CH WTR, CR HVAC, CCW and RHR.

C. High amperage on Battery BT1ED1 ammeter on CB-11.

D. SSII Train B alarms for SSW, ECCS, CS, MDAFW, DG PWR, SFTY CH WTR, CR HVAC, CCW and RHR.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because the location of the voltmeter with respect to the DC Bus and the Battery. One must determine that voltage will be maintained by the Battery Charger.

B. Correct. These are the correct alarm indications for the conditions listed.

C. Incorrect. Plausible because of the location of the ammeter with respect to the DC Bus and the Battery. One must determine that the ammeter will be indicating outflow from the Battery and not the Battery Charger amperage.

D. Incorrect. Plausible because one must determine the proper Train for the Battery versus the alarm indications given.

Technical Reference(s) ALM-1901A, SSII Train AA Attached w/ Revision # See OP51.SYS.DC1, Figure 8 Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the DC Electrical Distribution System.

Page 1 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # SYS.DC1.OB04.008 Modified Bank # (Note changes or attach parent)

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

Reference:

From ALM-1901A, SSII Train AA Revision # 5 Page 2 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-1901A, SSII Train AA Revision # 5 Page 3 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From OP51.SYS.DC1, Figure 8 Revision # 05/04/11 Page 4 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 065 G 2.4.35 Importance Rating 3.8 Loss of Instrument Air: Emergency Procedures/Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Proposed Question: Common 52 Given the following conditions:

Unit 2 has experienced a Station Blackout.

The Unit Supervisor directs that Steam Generator levels be maintained between 40%

and 50% per ECA-0.0B, Loss of All AC Power.

Which of the following describes the status of the Auxiliary Feedwater System per ECA-0.0B, Loss of All AC Power?

The Turbine Driven Auxiliary Feedwater Pump will be running at __________ speed, and the Auxiliary Feedwater Flow Control Valves will require local control in __________.

A. minimum; 30 minutes B. minimum; 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. maximum; 30 minutes D. maximum; 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Proposed Answer: C Explanation:

A. Incorrect. Plausible because the time rating of the AFW Flow Control Valve Accumulators is correct, however, the TDAFW Pump fails to maximum speed.

B. Incorrect. Plausible if thought the TDAFW Pump failed to minimum speed and that the rating of the AFW Flow Control Valves Accumulators was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, however, this is the rating of the Atmospheric Relief Valve Accumulators.

C. Correct. This is the correct failure speed of the TDAFW Pump and time rating of the AFW Flow Control Valve Accumulators.

D. Incorrect. Plausible because the TD AFW pump fails to maximum speed, however, the AFW Flow Control Valve Accumulators will only maintain position for 30 minutes.

Technical Reference(s) ECA-0.0B, Step 15 and NOTE Attached w/ Revision # See Comments / Reference Page 5 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: Given a procedural step, or sequence of steps from ECA-0.0 Loss of All AC Power, STATE the purpose/basis for the step(s).

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

Reference:

From ECA-0.0B, Step 15 and NOTE Revision # 8 Page 6 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # W/E12 EK2.1 Importance Rating 3.5 Uncontrolled Depressurization of All Steam Generators: Knowledge of the interrelations between the Uncontrolled Depressurization of All Steam Generators and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Proposed Question: Common 53 Given the following conditions:

A Steam Line Break inside Containment occurred on Unit 1.

ECA-2.1A, Uncontrolled Depressurization of All Steam Generators, is in progress.

Current plant conditions are as follows:

Reactor Coolant System (RCS) pressure is 1200 psig and slowly lowering.

Steam Generators 1-01, 1-03, and 1-04 narrow range levels are 3% and stable.

Steam Generator 1-02 narrow range level is 25% and slowly lowering.

All Steam Generator pressures are 175 psig and lowering.

RCS cooldown rate is 127F/hr.

Containment pressure is 12 psig and slowly rising.

Which of the following is required and the reason for that action?

A. REDUCE Auxiliary Feedwater flow to Steam Generators 1-01, 1-03, and 1-04 to NOT LESS THAN 100 GPM. STOP feeding Steam Generator 1-02 to minimize RCS cooldown.

B. STOP feeding Steam Generator 1-02 until Narrow Range Level is less than 10%.

ESTABLISH Auxiliary Feedwater Flow to all Steam Generators at 100 GPM to minimize steam line break flow.

C. MAINTAIN total Auxiliary Feedwater flow greater than 460 GPM until all Steam Generator narrow range levels are greater than 50% to ensure a proper heat sink.

D. REDUCE Auxiliary Feedwater flow to all Steam Generators to 100 GPM to prevent Steam Generator tube dry out.

Proposed Answer: D Page 7 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because Auxiliary Feedwater flow is reduced to 100 GPM, in part, minimizing RCS cooldown. However, flow is not stopped to any Steam Generator when cooldown rate is >

100F/hr regardless of Steam Generator water level.

B. Incorrect. Plausible because auxiliary Feedwater Flow is reduced to 100 GPM, in part, minimizing steam line break flow. However, flow is not stopped to any Steam Generator when cooldown rate is > 100F/hr regardless of Steam Generator water level.

C. Incorrect. Plausible because this is the method (and bases) for Auxiliary Feedwater flow control prior to entering ECA-2.1A. However, once ECA-2.1A is in effect, Auxiliary Feedwater flow to all Steam Generators is reduced to 100 GPM while cooldown rate is > 100F/hr without regard to Steam Generator level.

D. Correct. Per Step 2 of ECA-2.1A (continuous action step), Auxiliary Feedwater flow is reduced to 100 GPM per Steam Generator while RCS cooldown rate is > 100F/hr. This is done to minimize RCS cooldown, prevent Steam Generator tube dry out, and minimize steam line break flow.

Technical Reference(s) ECA-2.1A, Attachment 4, Step 2 Bases Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a procedural step, or sequence of steps from ECA-2.1, Uncontrolled Depressurization of All Steam Generators, STATE the purpose/basis for the step(s).

Question Source: Bank #

Modified Bank # ERG.C21.OB04.004 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 8 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-2.1A, Attachment 4, Step 2 Bases Revision # 8 Page 9 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ERG.C21.OB04.004 Revision # N/A ECA-2.1, Uncontrolled Depressurization of All Steam Generators has been entered and the following conditions are noted:

SGs 1, 3, and 4 narrow range levels are 3%.

SG 2 narrow range level is 23%.

RCS pressure is 1200 psig and decreasing.

RCS subcooling is 92ºF.

Containment pressure is 14 psig.

RCS cooldown rate is greater than 100ºF/HR.

All S/G pressures are decreasing.

Which one of the following best describes the actions that should be taken for the given conditions?

A. Reduce AFW flow to SG's 1, 3, and 4 to NOT less than 100 GPM. Stop feeding S/G 2. This is done to minimize the RCS cooldown rate.

B. Reduce AFW flow to all SG's to 100 GPM until cooldown is <100ºF/HR. This will prevent dry out.

C. Stop AFW flow to all SGs, reestablish at least 100 GPM as SG levels approach 10%. This will prevent dry out.

D. Stop AFW flow to all but one SG. Maintain at least 100 GPM flow to one SG for minimum required for heat sink.

Page 10 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # W/E11 EA2.2 Importance Rating 3.4 Loss of Emergency Coolant Recirculation: Ability to determine and interpret the following as they apply to the Loss of Emergency Coolant Recirculation: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments Proposed Question: Common 54 Given the following conditions:

Unit 2 experienced a Loss of Coolant Accident 30 minutes ago.

Neither 2-8811A, CNTMT SMP TO RHRP 1 SUCT ISOL VLV, nor 2-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV, can be opened.

As a result of these valve failures, ECA-1.1B, Loss of Emergency Coolant Recirculation, is in progress.

Only the Train A Centrifugal Charging Pump (CCP), Safety Injection Pump (SIP), and Residual Heat Removal Pump (RHRP) are running.

Reactor Coolant System (RCS) pressure is 340 psig and stable.

2-FI-917, CCP SI FLO, is indicating 250 GPM.

2-FI-918, SIP 1 DISCH FLO, is indicating 400 GPM.

Emergency Core Cooling System (ECCS) CANNOT be terminated due to inadequate subcooling.

Actions to establish minimum ECCS flow are in progress.

Per ECA-1.1B, Loss of Emergency Coolant Recirculation, Attachment 5, Minimum Required ECCS Flow, which of the following describes the method for establishing the required flow?

Secure A. CCP 2-01 and RHRP 2-01, allowing only SIP 2-01 to inject into the RCS.

B. CCP 2-01 and SIP 2-01, allowing only RHRP 2-01 to inject into the RCS.

C. RHRP 2-01, allowing both CCP 2-01 and SIP 2-01 to inject into the RCS.

D. SIP 2-01, allowing both CCP 2-01 and RHRP 2-01 to inject into the RCS.

Proposed Answer: C Page 11 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because RCS pressure might lower to allow increased SIP injection flow, or if Attachment 5 were read incorrectly, but this would only provide 400 GPM of the required 470 GPM.

B. Incorrect. Plausible because this condition would leave only a single pump running, but the RHR Pump is not capable of injecting into the RCS at this pressure so the minimum flow requirement would NOT be met.

C. Correct. Per Attachment 5, the minimum required flow is 470 GPM. Between the CCP and SIP the total injected flow is 650 GPM which is the lowest possible value while still meeting the minimum required flow.

D. Incorrect. Plausible because RCS pressure might lower to allow increased CCP and RHR Pump injection flow, or if Attachment 5 were read incorrectly, but this would only provide 250 GPM of the required 470 GPM since the RHR Pump is not capable of injecting into the RCS at this pressure.

Technical Reference(s) ECA-1.1B, Attachment 5 Attached w/ Revision # See ECCS Study Guide, Pages 16, 19, & 24 Comments / Reference Proposed references to be provided during examination: ECA-1.1B, Attachment 5 Learning Objective: Given a procedural step, or sequence of steps from ECA-1.1, Loss of Emergency Coolant Recirculation, STATE the purpose / basis for the step(s).

Question Source: Bank # ERG.C11.OB04.009 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 12 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-1.1B, Attachment 5 Revision # 8 Comments /

Reference:

From ECCS Study Guide, Page 16 Revision # 05/02/11 Centrifugal Charging Pumps The Centrifugal Charging Pumps are eleven stage centrifugal pumps manufactured by Pacific Pumps Company (section of the Dresser Corporation). These pumps provide flow to the Reactor Coolant System at any design pressure (RCS design pressure is 2485 psig). Shutoff head for each pump is ~

2590 psid. Each pump is rated for 150 GPM at a differential pressure of 2510 psid, with flow increasing to 550 GPM as system backpressure decreases to approximately 625 psid. 600 hp motors, supplied by the safeguards 6.9 kV busses, uEA1 & uEA2 power the pumps. The Centrifugal Charging Pumps are located in individual rooms on the 810' level of the Auxiliary Bldg.

Page 13 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECCS Study Guide, Page 19 Revision # 05/02/11 Safety Injection Pumps The Safety Injection Pumps are eleven stage centrifugal pumps manufactured by the Pacific Pumps Company (section of the Dresser Corporation). The main function of these pumps is to develop the necessary head to cause discharge into the Reactor Coolant System at intermediate system pressure

(~1520 psig). When RCS pressure is greater than Safety Injection Pump shutoff head, minimum flow through the pump is assured by the mini-flow recirculation lines, which direct flow back to the Refueling Water Storage Tank. An orifice in each pump s miniflow line allows 45 GPM of flow. The Safety Injection Pumps begin to inject at approximately 1520 psig RCS pressure. Shutoff head is ~ 1558 psid. Pump discharge flow increases as discharge pressure (RCS pressure) decreases. At approximately 700 psid, the pumps are rated for ~ 650 GPM flow. Each pump s 450 HP motor is powered from a safeguards 6.9 KV bus. Train A is powered from uEA1 and Train B is powered from uEA2. The pumps are located in individual rooms on the 773' level of the Safeguards Bldg. Water tight doors are provided to isolate the room in the event of flooding since these rooms are below lake level.

Comments /

Reference:

From ECCS Study Guide, Page 24 Revision # 05/02/11 Residual Heat Removal Pumps Each train of the RHR System contains a single pump. The Residual Heat Removal Pumps are manufactured by the Dresser Rand Company and are single stage centrifugal pumps. The RHR Pumps were selected as low head, high flow pumps to serve their normal function to remove core residual heat during a normal plant cooldown. However, in the event of a very large loss of coolant accident, the RHR Pumps will begin to deliver water from the RWST to the RCS when pressure drops to approximately 200 psig. As RCS pressure continues to decrease each RHR Pump will deliver up to ~ 4900 GPM of injection flow (the pumps are rated for 5500 GPM flow, but system head losses will limit injection flow to ~ 4900 GPM). The pumps and associated piping are rated for 600 psi and 400 °F. Minimum flow through the pump should never fall below 500 GPM to ensure the mechanical seals do not overheat.

Minimum flow is controlled by motor operated valves in a recirculation line, provided to direct water from downstream of the RHR heat exchanger back the pump suction. Their 450 HP motors are powered from the safeguards 6.9 KV buses uEA1 and uEA2. These pumps are located in their own individual rooms on the 773' level of the Safeguards Bldg. Water tight doors are provided to isolate the room in the event of flooding since these rooms are below lake level.

Page 14 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 057 AK3.01 Importance Rating 4.1 Loss of Vital AC Instrument Bus: Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus Proposed Question: Common 55 Given the following:

Unit 1 is at 100% power.

All systems are in their normal alignments.

Annunciator 1-ALB-10B, Window 1.16 - 118V CHAN 1 INV TRBL, is in alarm.

It has been determined that the associated Protection Bus is deenergized.

Which of the following describes the effect on the Chemical and Volume Control Makeup System?

A. AUTO Reactor Coolant Makeup Control to the Volume Control Tank is disabled ONLY.

B. AUTO and MANUAL Reactor Coolant Makeup Control to the Volume Control Tank is disabled.

C. 1-LCV-112D and 112E, RWST TO CHRG PMP SUCT VLVs open.

1-LCV-112B and 112C, VCT TO CHRG PMP SUCT VLVs close.

D. 1-LCV-112D and 112E, RWST TO CHRG PMP SUCT VLVs open.

1-LCV-112B and 112C, VCT TO CHRG PMP SUCT VLVs open.

Proposed Answer: A Explanation:

A. Correct. A loss of Protection Bus 1PC1 disables automatic Reactor Coolant Makeup Control to the VCT.

B. Incorrect. Plausible because automatic makeup control is disabled, however, manual Reactor Coolant Makeup Valve Control is not lost.

C. Incorrect. Plausible if thought that a loss of automatic Reactor Coolant Makeup Control caused VCT suction to shift, however, this occurs with a VCT LO-LO level alarm.

D. Incorrect. Plausible if thought that a loss of automatic Reactor Coolant Makeup Control caused the RWST Suction Valves to open, however, this occurs on a VCT LO-LO level alarm.

Page 15 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) ABN-603, Step 2.2.b Attached w/ Revision # See ALM-0102A, 1-ALB-10B, Window 1.16 Comments / Reference ALM-0061A, 1-ALB-6A, Window 4.5 Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to Loss of a Protection Bus in accordance with ABN-603, Loss of Protection or Instrument Bus.

Question Source: Bank # ABN.603.OB01.010 Modified Bank # (Note changes or attach parent)

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

Reference:

From ABN-603, Step 2.2.b Revision # 7 Page 16 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0102A, 1-ALB-10B, Window 1.16 Revision # 11 Page 17 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0061A, 1-ALB-6A, Window 4.5 Revision # 7 Page 18 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 077 AK3.01 Importance Rating 3.9 Generator Voltage and Electric Grid Disturbances: Knowledge of the reasons for the following responses as they apply to Generator Voltage and Electric Grid Disturbances: Reactor and turbine trip criteria Proposed Question: Common 56 Given the following conditions:

Unit 2 is in MODE 1, Reactor power is 60%.

ABN-601, Response to a 138/345 KV System Malfunction, Section 9.0, Grid Frequency Fluctuations/Loss of QSE Generation Controller Communications, is in progress.

Main Turbine speed has lowered to 1770 rpm.

Grid frequency is 59 Hz and lowering.

Which of the following identifies the ERCOT Nodal Operating Guidance when operating below normal Grid Frequency?

ABN-601, Response to a 138/345 KV System Malfunction, requires the operator to TRIP the A. Reactor if Grid Frequency is less than 58.4 Hz for greater than 30 seconds.

B. Turbine if Grid Frequency is less than 58.4 Hz for greater than 30 seconds.

C. Reactor if Grid Frequency is less than 59.4 Hz for greater than 30 seconds.

D. Turbine if Grid Frequency is less than 59.4 Hz for greater than 30 seconds.

Proposed Answer: A Page 19 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. If Grid Frequency cannot be restored to greater than 58.4 Hz in 30 seconds, an immediate Reactor Trip is required. This action minimizes turbine blade fatigue when operating below 60 Hz (closer to resonance).

B. Incorrect. Plausible because the frequency and time are correct. Since Reactor power is greater than 50%, the Reactor is required to be tripped prior to tripping the Turbine.

C. Incorrect. Plausible because a Reactor trip is required if Grid Frequency cannot be restored, but the Reactor is tripped when Grid Frequency is < 58.4 Hz for more than 30 seconds. 59.4 Hz is a plausible number since ABN-601 requires a Reactor Trip if Grid Frequency cannot be raised >

59.4 Hz in 9 minutes.

D. Incorrect. Plausible a Reactor Trip is required if Grid Frequency cannot be restored, but the Reactor is tripped when Grid Frequency is < 58.4 Hz for more than 30 seconds. 59.4 Hz is a plausible number since ABN-601 requires a Reactor Trip if Grid Frequency cannot be raised >

59.4 Hz in 9 minutes. Since Reactor power is greater than 50%, the Reactor is required to be tripped prior to tripping the Turbine.

Technical Reference(s) ABN-601, Step 9.3.6 RNO & 9.3.7 Attached w/ Revision # See ERCOT Nodal Operating Guides 2.6.2 Comments / Reference Luminant Corporate Procedure G-3010 Proposed references to be provided during examination: None Learning Objective: EVALUATE the following as they apply to a Station Electrical malfunction:

When to trip the unit.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Page 20 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-601, Step 9.3.6 RNO Revision # 11 Page 21 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-601, Step 9.3.7 RNO Revision # 11 Page 22 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ERCOT Nodal Operating Guides 2.6.2 Revision # 03/01/11 Page 23 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Luminant Corporate Procedure G-3010 Revision # 04/03/07 Page 24 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 003 AA1.07 Importance Rating 3.8 Dropped Control Rod: Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: Incore and excore instrumentation Proposed Question: Common 57 Given the following conditions:

A Reactor Startup is in progress on Unit 1.

Reactor Power has been leveled at 1 x 10-8 amps in the Intermediate Range per Step 5.2.23 of IPO-002A, Plant Startup from Hot Standby.

1-PI-507, MS HDR PRESS, is being maintained at approximately 1092 psig using Steam Dumps in AUTO.

The following indications are observed:

Control Rod CBD M-12 Rod Bottom Light is LIT.

1-ALB-06D, Window 3.5 - DRPI ROD DEV, is in alarm.

1-ALB-06D, Window 3.7 - ANY ROD AT BOTTOM, is in alarm.

For the given conditions, how will Reactor Power respond and what actions are required by ABN-712, Rod Control System Malfunction?

Reactor Power will make a step change lower, then A. slowly lower into the Source Range while TAVE remains constant.

Immediately TRIP the Reactor and go to EOP-0.0A, Reactor Trip or Safety Injection.

B. slowly lower into the Source Range while TAVE remains constant.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, INSERT all Control Banks to the Control Bank Offset Position.

C. return to 1 x 10-8 amps while TAVE decreases.

Immediately TRIP the Reactor and go to EOP-0.0A, Reactor Trip or Safety Injection.

D. return to 1 x 10-8 amps while TAVE decreases.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, INSERT all Control Banks to the Control Bank Offset Position.

Proposed Answer: B Page 25 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because Reactor Power will continue to lower into the Source Range since power is below the Point of Adding Heat (POAH). Steam Dumps in AUTO will maintain TAVE constant, however, ABN-712 requires all Control Bank Rods to be inserted to the Control Bank Offset Position. The Reactor is required to be tripped only when > 1 rod is > 12 steps misaligned.

B. Correct. Reactor Power will continue to lower into the Source Range since power is below the POAH. Steam Dumps in AUTO will maintain TAVE constant. Actions are per ABN-712, Step 3.3.2 RNO.

C. Incorrect. Plausible because Reactor Power would return to 1 x 10-8 amps if greater than the POAH, however, Reactor Power is below the POAH and power will continue to lower into the Source Range. Steam Dumps in AUTO will maintain TAVE constant. Additionally, ABN-712 requires all Control Bank Rods to be inserted to the Control Bank Offset Position. The Reactor is required to be tripped only when > 1 rod is > 12 steps misaligned.

D. Incorrect. Plausible because actions are per ABN-712, Step 3.3.2 RNO, however, Reactor Power will continue to lower into the source range since power is below the POAH and Steam Dumps in AUTO will maintain TAVE constant.

Technical Reference(s) ABN-712, Steps 3.3.1 & 3.3.2 RNO Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to a Dropped or Misaligned Rod in MODE 1 or 2 in accordance with ABN-712, Rod Control System Malfunction.

EVALUATE systems and component status using the plant computer while responding to a Rod Control malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1, 5, 10 55.43 Page 26 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-712, Steps 3.3.1 & 3.3.2 RNO Revision # 10 Page 27 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 032 AK2.01 Importance Rating 2.7 Loss of Source Range Nuclear Instrument: Knowledge of the interrelations between the Loss of Source Range Nuclear Instrumentation and the following: Power supplies, including proper switch positions Proposed Question: Common 58 Given the following conditions:

A Reactor Startup is in progress.

Intermediate Range power indicates 5 x 10-11 amps on both Channels.

Source Range High Flux trip has NOT been blocked.

For the two switch positions shown below, which of the following describes the Reactor Protection System response to a blown INSTRUMENT POWER fuse on Source Range Channel N-31 per ABN-701, Source Range Instrument Malfunction?

SR Level Trip Switch: NORMAL SR Level Trip Switch: BYPASS A. NO Reactor Trip NO Reactor Trip B. Reactor Trip NO Reactor Trip C. NO Reactor Trip Reactor Trip D. Reactor Trip Reactor Trip Proposed Answer: B Explanation:

A. Incorrect. Plausible because the BYPASS position is correct, however, a Reactor Trip occurs with the switch in NORMAL.

B. Correct. Removing the Source Range Instrument power fuses will result in a Reactor Trip with the switch in NORMAL. It does not occur if the switch is in BYPASS.

C. Incorrect. Plausible because the conditions are reversed, however, a Reactor Trip occurs with the switch in NORMAL and does NOT occur with the switch in BYPASS.

D. Incorrect. Plausible because the NORMAL position is correct, however, a Reactor Trip does NOT occur with the switch in BYPASS.

Technical Reference(s) ABN-701, Section 2.2 Attached w/ Revision # See ABN-701, Step 2.3.1 CAUTION Comments / Reference LO21.SYS.EC1, Slide #16 Page 28 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Excore Instrumentation System.

EXPLAIN the instrumentation and controls of the Excore Instrumentation System and PREDICT the system response.

Question Source: Bank # ABN.SELF.701.006 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 29 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-701, Section 2.2 Revision # 11 Page 30 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-701, Step 2.3.1 CAUTION Revision # 11 Comments /

Reference:

From LO21.SYS.EC1, Slide #16 Revision # 05/30/11 120V AC CONT Power Contact(s)

High Flux Trip CLSD to Trip Level Trip Bypass 2/2 Open in Normal Logic 25V DC Trip Low Voltage PS (120V AC INST Power)

Input Error Inhibit switch Reactor Above P6 Above P6 Above P10 Below P6 Power Not Blocked Blocked Blocked/Not Blocked Level Normal Bypass Normal Bypass Normal Bypass Normal Bypass Trip Sw Loss of No No No No No No Reactor Reactor INST Reactor Reactor Reactor Reactor Reactor Reactor Trip Trip PWR Trip Trip Trip Trip Trip Trip Loss of No No No No Reactor Reactor Reactor Reactor CONT Reactor Reactor Reactor Reactor Trip Trip Trip Trip PWR Trip Trip Trip Trip Page 31 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 036 AK3.01 Importance Rating 3.1 Fuel Handling Accident: Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents:

Different inputs that will cause a reactor building evacuation Proposed Question: Common 59 Which of the following describes the input that automatically causes a Containment Evacuation alarm?

A. Source Range High Flux at Shutdown.

B. Source Range High Flux Level Trip.

C. Containment Area Radiation Monitor High.

D. Containment Ventilation Isolation Signal.

Proposed Answer: A Explanation:

A. Correct. This is the source of the Containment Evacuation alarm.

B. Incorrect. Plausible because this is driven by the same Source Range Nuclear Instrument level amplifier, however, it is a separate bistable.

C. Incorrect. Plausible because Containment would be evacuated, however, this is not the source of the Containment Evacuation Alarm.

D. Incorrect. Plausible because a Containment Ventilation Isolation Signal could be the result of high radiation, however, this is not the source of the Containment Evacuation alarm.

Technical Reference(s) ALM-0064A, 1-ALB-6D, Window 2.1 Attached w/ Revision # See LO21.SYS.EC1, Slide 15 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Excore Instrumentation System and PREDICT the system response.

Question Source: Bank # SYS.EC1.OB04.007 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis Page 32 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 10 CFR Part 55 Content: 55.41 7, 9 55.43 Comments /

Reference:

From ALM-0064A, 1-ALB-6D, Window 2.1 Revision # 6 Page 33 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From LO21.SYS.EC1, Slide 15 Revision # 05/01/11 N32 Source Range Proportional BF3 +2000V dc Counter Detector Open > P6 & manually blocked by 1/1-N33A & 1/1-N33B in Block Open > P10 Also Open when Input Error Inhibit SR High switch is in inhibit.

Voltage A Failure Increases Signal to Noise Preamp Ratio Detector Voltage Amplification Pulse Amp &

Eliminates Gamma Pulses & Noise Discriminator SR Audio Count Rate FLUX Isol Amp Circuit DBLG 1PC1 Demultiplexer Power A 6D-2.12 Log Pulse P6 1/1-N32A (BLK)

Pulse Shaper Pulse Driver Integrator Square Wave Impedance matches DC output current N35D (>10-10 Amps)

N36D (>10-10 Amps)

R Amplification Pulse Shaper output to proportional to the L 2 pulses / 1 square the Log Pulse Integrator log of input pulses 1/1-N32A (RES)

Bypass Amplifies Level Amp DC output current N31 SR Flux (x2)

< 9 Min Flux Doubling Bypass Calculates 1 min average CR and compares to 9 previous 1 min averages. N32 SR Flux (x2)

Isol Amp < 9 Min If last average CR is (2x) any previous, then alarm occurs.

1/1-N31A (BLK) 1/1-N31A (RES)

R L

P6 NR-45 Recorder Isol Amp SUR Circuit CB-07 MCB 120V AC CONT Power Indication Contact(s)

High Flux Trip CLSD to Trip SR SHTDN FLUX ALM BLK Level Trip Bypass Open in Normal 2/2 5x 6D-3.1 Logic A SR SHTDN FLUX HI Bkgrd 25V DC Trip Low Voltage PS A 6D-2.1 (120V AC INST Power)

Block Switch (SR Drawer) Input Error Inhibit switch SR/IR TRIP BYP SR FLUX HI 1/2 A 6D-4.1 A 6C-1.5 5

> 10 CPS Level Trip Bypass (SR Drawer)

Detector CPS Page 34 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 051 G 2.1.7 Importance Rating 4.4 Loss of Condenser Vacuum: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Proposed Question: Common 60 Given the following conditions:

During a plant startup, Unit 1 is operating at 23% power following synchronization of the Main Generator to the grid.

Three Circulating Water Pumps are in service.

All three Condenser Vacuum Pumps are in operation.

Main Condenser vacuum is 20.5 Hg in both Condensers and slowly degrading.

Which of the following actions should be taken in accordance with ABN-304, Main Condenser and Circulating Water System Malfunction?

A. Start an additional Circulating Water Pump.

B. Reduce Turbine Load to restore Main Condenser vacuum.

C. Trip the Main Turbine and enter ABN-403, Turbine Trip Response.

D. Trip the Reactor and enter EOP-0.0A, Reactor Trip or Safety Injection.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because operating additional Circ Water Pumps may improve Condenser vacuum, but vacuum is below the automatic trip setpoint and the Reactor is to be tripped since the unit is above P-7 (10%).

B. Incorrect. Plausible because this action is taken if Main Condenser vacuum is degrading, but vacuum is below the automatic trip setpoint and the Reactor must be tripped since the Unit is above P-7 (10%).

C. Incorrect. Plausible because this action is taken if the Unit is below the P-7 setpoint (10%), but above P-7 a Turbine Trip signal generates a Reactor Trip signal so the Reactor should be tripped.

D. Correct. Given the conditions listed, vacuum is below the automatic trip setpoint and with the Unit above the P-7 setpoint (10%) an automatic Reactor Trip will occur on the Turbine Trip. The Unit must be tripped.

Technical Reference(s) ABN-304, Steps 2.3.3 & 2.3.4 Attached w/ Revision # See Comments / Reference Page 35 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Condenser Vacuum System.

ANALYZE the response to a decreasing Main or Auxiliary Condenser Vacuum per ABN-304, Main Condenser and Circulating Water System Malfunction.

Question Source: Bank # SYS.CV1.OB03.003 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 7 55.43 Page 36 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-304, Steps 2.3.3 & 2.3.4 Revision # 8 Page 37 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 067 AA2.16 Importance Rating 2.9 Plant Fire On Site: Ability to determine and interpret the following as they apply to the Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire Proposed Question: Common 61 Given the following conditions:

Both Units are operating at power.

Train A Control Room Ventilation is in service.

Following a report of a fire outside of the Control Building, smoke enters the Train A Intake, actuating the Air Intake Smoke Alarm.

Which of the following is the appropriate action to be taken per SOP-802, Control Room Ventilation System?

A. Manually initiate Emergency Recirculation; manually shift to single train operation and shift the operating train to Isolation Mode.

B. Manually initiate Emergency Ventilation; manually shift both trains to Isolation Mode.

C. Verify automatic actuation of Emergency Recirculation; manually shift both trains to Isolation Mode.

D. Verify automatic actuation of Emergency Ventilation; manually shift to single train operation and shift the operating train to Isolation Mode.

Proposed Answer: A Explanation:

A. Correct. Emergency Recirculation is not automatically initiated by smoke alarms. Isolation Mode alignment is manually performed from Emergency Recirculation for a single train in accordance with SOP-802.

B. Incorrect. Plausible if believed that Control Room Ventilation Emergency Ventilation is initiated, however, Emergency Recirculation is required.

C. Incorrect. Plausible if believed that Emergency Recirculation is generated automatically from a smoke alarm, however, this is a manual initiation.

D. Incorrect. Plausible if believed that Emergency Ventilation is generated automatically from a smoke alarm, however, it is required to manually shift to Emergency Recirculation.

Page 38 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) SOP-802, Section 3.0 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Control Room Ventilation System.

Question Source: Bank #

Modified Bank # SYS.HV1.OB05.001 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8, 10 55.43 Comments /

Reference:

From SOP-802, Section 3.0 Revision # 12 Page 39 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 076 AA2.01 Importance Rating 2.7 High Reactor Coolant Activity: Ability to determine and interpret the following as they applied to the High Reactor Coolant Activity: Location or process point that is causing alarm Proposed Question: Common 62 Which of the following identifies the process point that causes FFL-160, Gross Failed Fuel Monitor, to alarm?

High activity in the A. Steam Generator Blowdown flow.

B. Main Steam Line Steam flow.

C. Reactor Coolant System Letdown flow.

D. Containment Purge (or Ventilation) System flow.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because the Steam Generator Blowdown flow monitor is used in diagnosing a Steam Generator Tube Rupture and could be thought to also be used in diagnosing failed fuel.

B. Incorrect. Plausible because the Main Steam Line Steam flow monitor is used in diagnosing a Steam Generator Tube Rupture and could be thought to also be used in diagnosing failed fuel.

C. Correct. The Gross Failed Fuel Monitor is in the Letdown flow.

D. Incorrect. Plausible because the Containment Purge System flow would be indicative of RCS leakage with failed fuel.

Technical Reference(s) ALM-3200, Page 44 Attached w/ Revision # See ALM-3200, Attachments 3 & 10 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Digital Radiation Monitoring System and PREDICT the system response.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Page 40 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11, 13 55.43 Comments /

Reference:

From ALM-3200, Page 44 Revision # 4 Page 41 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-3200, Attachment 10 Revision # 4 Page 42 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-3200, Attachment 3 Revision # 4 Page 43 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # W/E03 G 2.4.1 Importance Rating 4.6 LOCA Cooldown - Depressurization: Emergency Procedures/Plan: Knowledge of EOP entry conditions and immediate action steps Proposed Question: Common 63 Given the following conditions:

EOS-1.1A, Safety Injection Termination, is in progress on Unit 1.

Centrifugal Charging Pump (CCP) 1-01 is operating with injection aligned through the Normal Charging line.

CCP 1-02 is in Standby.

Containment pressure is 3 psig and stable.

The step to determine if Safety Injection Pumps can be stopped is being performed.

Which of the following conditions would indicate that Safety Injection CANNOT be terminated and that a transition to EOS-1.2A, Post LOCA Cooldown and Depressurization, is required?

NO Steam Generator is faulted or still depressurizing and A. Reactor Coolant System pressure is 1900 psig and slowly rising.

B. Pressurizer level is 15% and slowly rising.

C. Reactor Coolant System pressure is 1400 psig and slowly lowering.

D. 1-FI-121A, CHRG FLO, indicates 32 GPM and stable.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because Pressurizer pressure is still well below normal MODE 3 pressure.

B. Incorrect. Plausible because Pressurizer level is still well below normal MODE 3 level but is above the 13% level for SI reinitiation and below the 34% level which would require reinitiation if Adverse Containment parameters existed.

C. Correct. With pressure lowering and below the Safety Injection (SI) Pump shutoff head, the SI Pumps cannot be stopped per EOS-1.1A, Step 12 and a transition to EOS-1.2A is required.

D. Incorrect. Plausible because 32 GPM appears to be insufficient makeup but without Letdown in service, Charging flow is only directed to the RCP seals.

Technical Reference(s) EOS-1.2A, Entry Conditions Attached w/ Revision # See EOS-1.1A, Step 12 & Attachment 1.A Comments / Reference Page 44 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: Given a set of plant conditions, IDENTIFY the proper transitions through/out of EOS-1.2, Safety Injection Termination.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments /

Reference:

From EOS-1.2A, Entry Conditions Revision # 8 Page 45 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.1A, Step 12 RNO Revision # 8 Page 46 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-1.1A, Attachment 1.A Revision # 8 Page 47 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # W/E09 & E10 EA1.2 Importance Rating 3.6 Natural Circulation: Ability to operate and/or monitor the following as they apply to the Natural Circulation with Steam Void in Vessel with/without RVLIS: Operating behavior characteristics of the facility Proposed Question: Common 64 Given the following conditions:

A Unit 1 Reactor Trip and Loss of Offsite Power have occurred.

EOS-0.3A, Natural Circulation Cooldown with Steam Void in Vessel (With RVLIS), is in progress.

Reactor Coolant System (RCS) cooldown is in progress.

1/1-8145, PRZR AUX SPR VLV, was opened to depressurize the RCS.

Charging and Letdown are in service.

During the cooldown and depressurization, the following indications are observed:

RVLIS 61 IN ABOVE CORE PLATE light is DARK.

Pressurizer level is 75% and rising.

RCS pressure is 925 psig and slowly lowering.

RCS cooldown rate is 60F/hr.

RCS subcooling is 50F.

Due to current plant conditions, 1/1-8147, RCS LOOP 1 CHRG VLV, was OPENED to raise RCS pressure.

What condition will allow 1/1-8147, RCS LOOP 1 CHRG VLV, to be closed to continue RCS depressurization per EOS-0.3A, Natural Circulation Cooldown with Steam Void in Vessel (with RVLIS)?

CLOSE 1/1-8147, RCS LOOP 1 CHRG VLV, when A. the RVLIS 61 IN ABOVE CORE PLATE light is LIT.

B. Pressurizer level is less than 40%.

C. RCS pressure is greater than 1075 psig.

D. RCS subcooling is greater than 75F.

Proposed Answer: A Page 48 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Per EOS-0.3A, Step 5 RNO. If necessary, Vessel Head void growth is limited by raising RCS pressure to prevent interference with Hot Leg Natural Circulation flow.

B. Incorrect. Plausible because Pressurizer level is initially established at 30-40% prior to depressurization, however, once cooldown is started Pressurizer level need only be reduced when it exceeds 90%.

C. Incorrect. Plausible if in EOS-0.4A, Natural Circulation Cooldown With Steam Void in Vessel (WITHOUT RVLIS), however, when RVLIS is available, Vessel Head void size is monitored with RVLIS and RCS pressure is controlled accordingly.

D. Incorrect. Plausible if in EOS-0.2A, Natural Circulation Cooldown, however, since a steam void is in the vessel, EOS-0.3A allows for a faster cooldown rate than EOS-0.2A, along with minimal subcooling requirements (45F).

Technical Reference(s) EOS-0.3A, Steps 3, 4, & 5 Attached w/ Revision # See EOS-0.3A, Attachment 4, Step 5 Bases Comments / Reference Proposed references to be provided during examination: None Page 49 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.3, Natural Circulation Cooldown with Steam Void in Vessel (with RVLIS) and EOS-0.4, Natural Circulation Cooldown with Steam Void in Vessel (without RVLIS).

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3, 5, 14 55.43 Page 50 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.3A, Step 3 Revision # 8 Page 51 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.3A, Steps 4 & 5 Revision # 8 Page 52 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.3A, Attachment 4, Step 5 Bases Revision # 8 Page 53 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 024 AK1.02 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 Proposed Question: Common 65 Given the following conditions:

Unit 1 is in MODE 1 at 7% power and stable.

Rod Control is in MANUAL.

1/1-FLRM, CONTROL ROD MOTION CTRL, is DANGER tagged for repairs.

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.

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 DANGER 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.

Proposed Answer: A Page 54 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 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 DANGER tag in place the control will not be operated.

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, Section 8.1 Attached w/ Revision # See ABN-105, Steps 1, 3, & 4 Comments / Reference Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to a Dilution Anomaly in accordance with ABN-105, Chemical and Volume Control System Malfunctions.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1, 5, 10 55.43 Page 55 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Section 8.1 Revision # 7 Comments /

Reference:

From ABN-105, Step 3 & 4 Revision # 7 Page 56 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Step 1 Revision # 7 Page 57 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.5 Importance Rating 2.9 Conduct of Operations: Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Proposed Question: Common 66 Given the following conditions:

You are on watch in the Control Room as the BOP with both Units at 100% power.

Shifts are 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> long and all shifts are manned to the minimum composition of ODA-102, Conduct of Operations.

Your relief is NOT on site for Shift Turnover.

Which of the following describes the procedural guidance in this situation?

Shift composition may A. NOT drop below the minimum unless an operator exceeds 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on watch.

Turnover your watch station to the on-coming RO and depart.

B. be one less than the minimum for two hours while attempting to find a replacement.

Turnover your watch station to the on-coming RO and attempt to contact a replacement.

C. NOT drop below the minimum as a result of an on-coming watchstander being absent. Remain on watch.

D. be one less than the minimum for two hours. Turnover your watchstation to the on-coming RO but remain on site in standby until a replacement is found.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is the maximum shift time excluding turnover, however, because the oncoming shift member is late or absent the position should not be unmanned.

B. Incorrect. Plausible because Shift Composition can be one less than minimum for two hours, however, this does not apply when an oncoming shift member is late or absent.

C. Correct. Per the guidance in ODA-102, Attachment 8.A, Item #13.

D. Incorrect. Plausible because shift composition can be one less than minimum for two hours, however, this does not apply when an oncoming shift member is not yet present.

Page 58 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Technical Reference(s) ODA-102, Attachment 8.A, Item #13 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: STATE requirements for Conduct of Operations in accordance with ODA-102, ODA-407 and Operations Guideline 3.

Question Source: Bank # ADM.XA1.OB01.013 Modified Bank # (Note changes or attach parent)

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

Reference:

From ODA-102, Attachment 8.A, Item #13 Revision # 26 Page 59 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.15 Importance Rating 2.7 Conduct of Operations: Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.

Proposed Question: Common 67 In accordance with ODA-106, Review of Documents and Operational Experience Feedback, the approval authority for a Lessons Learned is the __________, unless the information is of immediate "need to know" importance in which case the approval authority should be the A. Plant Manager; Director Operations B. Director Operations; Shift Operations Manager C. Shift Operations Manager; Shift Manager D. Shift Manager; Field Support Supervisor Proposed Answer: C Explanation:

A. Incorrect. Plausible because the Plant Manager and Director Operations would represent the top level of Operations management and would ensure that Operating Experience carries upper management support to the line organization.

B. Incorrect. Plausible as the Director Operations could be seen as the individual who ensures that guidance is always consistent to the operators, however, this falls to the Shift Operations Manager except when information needs immediate dissemination at which time the task falls to the Shift Manager.

C. Correct. Per the guidance outlined in ODA-106.

D. Incorrect. Plausible because as the Shift Manager could be seen as the individual with the most direct involvement with the Operating Experience and the FSS could be seen as the individual who directs the NEOs which are often involved with the Lessons Learned.

Technical Reference(s) ODA-106, Section 4.0 Attached w/ Revision # See ODA-106, Step 6.5 Comments / Reference ODA-106, Section 5.0 Proposed references to be provided during examination: None Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Page 60 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

Reference:

From ODA-106, Section 4.0 Revision # 14 Page 61 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ODA-106, Step 6.5 Revision # 14 Comments /

Reference:

From ODA-106, Section 5.0 Revision # 14 Page 62 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.6 Importance Rating 3.0 Equipment Control: Knowledge of the process for making changes to procedures.

Proposed Question: Common 68 Given the following:

A Reactor Operator is performing a procedure.

Only ONE Senior Reactor Operator is available.

Which of the following is a condition that will allow a step in the procedure to be marked "N/A" by the Reactor Operator?

A. A clearance is installed on the component to be operated.

B. The step does not apply to the conditions under which the activity is being performed.

C. Performance of the step will prevent proper performance or result in a personnel hazard.

D. Performance of the step will cause a violation of administrative controls or other plant commitments.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because if a clearance is in place on a component, two SROs can concur that the procedure step can be marked N/A.

B. Correct. If the condition does not apply the RO may mark the step N/A.

C. Incorrect. Plausible because if a personnel hazard is created the step may not be N/A, performance of the procedure should be stopped at this point.

D. Incorrect. Plausible because a conflict between guidance may require a change in performance but performance must be stopped and a procedure change performed.

Technical Reference(s) STA-201, Section 6.5 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Page 63 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # ADM.XA1.OB01.007 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 64 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-201, Section 6.5 Revision # 16 Page 65 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-201, Section 6.5 Revision # 16 Page 66 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.14 Importance Rating 3.9 Equipment Control: Knowledge of the process for controlling equipment configuration or status.

Proposed Question: Common 69 Given the following conditions:

Unit 2 is in MODE 3.

A LOCKED OPEN valve is requested by Engineering to be UNLOCKED and CLOSED, WITHOUT an approved procedure, to gather information for a proposed design modification.

A status review has concluded that the system impact is acceptable at this time.

This valve will be repositioned to OPEN and verified LOCKED OPEN per IPO-002B, Plant Startup from Hot Standby.

Is procedure OWI-103-3, Locked Component Deviation Log, required to be completed?

A. No, as long as the valve will be closed by a Shift Manager's clearance.

B. Yes, unless the Shift Manager suspends the Locked Component Deviation Log.

C. No, as long as the valve is opened and verified locked open per an approved procedure.

D. Yes, even though the valve is opened and verified locked open per an approved procedure, completion of the Locked Component Deviation Log is still required.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because a Shift Managers clearance could appear as stronger administrative guidance for the configuration control of the valve, however, the Locked Component Deviation Log is still required.

B. Incorrect. Plausible because the Shift Manager can suspend the Locked Component Deviation Log in MODES 5, 6 and defueled, however, the Log cannot be suspended in MODE 3.

C. Incorrect. Plausible because the valve is being restored per an approved procedure, however, the valve is not being closed per an approved procedure thus requiring a Log entry.

D. Correct. In accordance with ODA-403.

Technical Reference(s) ODA-403, Step 6.5 Attached w/ Revision # See Comments / Reference Page 67 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Question Source: Bank #

Modified Bank # ADM.XA1.OB02.009 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 68 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ODA-403, Step 6.5 Revision # 7 Page 69 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ADM.XA1.OB02.009 Revision # N/A Given the following conditions:

A locked open valve is requested to be unlocked and closed.

This valve will be repositioned to open and verified locked open per an approved Operations Department procedure during the upcoming return to power.

Is OWI-103-3, Locked Component Deviation Log, required to be completed?

A. No, as long as the valve will be closed by a Shift Manager's clearance.

B. Yes, unless the Shift Manager directs the restoration prior to entering MODE 5.

C. No, as long as the valve is opened and verified locked open per an approved procedure.

D. Yes, even though the valve is opened and verified locked open per an approved procedure, completion of the Locked Component Deviation Log is still required.

Page 70 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.23 Importance Rating 3.1 Equipment Control: Ability to track Technical Specification limiting conditions for operations.

Proposed Question: Common 70 Which of the following is an example or definition of Limiting Condition for Operation (LCO)

Initiation Time?

A. Time the LCO was discovered NOT satisfied.

B. Time that the NOT satisfied LCO was entered in the Unit Log.

C. Amount of time necessary to complete the LCO REQUIRED ACTION.

D. Time that the Shift Manager was notified that a Quick Turnaround Technical Evaluation had been initiated.

Proposed Answer: A Explanation:

A. Correct. As defined per ODA-308, LCO Tracking Program.

B. Incorrect. Plausible because Unit Log entries are made per ODA-308, however, the time of the Log entry is not the Initiation Time.

C. Incorrect. Plausible because this condition is defined per ODA-308, LCO Tracking Program, however, this is referred to as Completion Time.

D. Incorrect. Plausible because the time that the Shift Manager is notified that a Quick Turnaround Technical Evaluation has been evaluated as rendering equipment inoperable is the Initiation Time, however, this is the time that the QTE is initiated not evaluated.

Technical Reference(s) ODA-308, Steps 4.5 & 4.13 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DISCUSS the requirements of ODA-308, LCO Tracking Program.

Question Source: Bank # ADM.XA5.OB12 07 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Page 71 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments /

Reference:

From ODA-308, Step 4.5 Revision # 15 Page 72 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ODA-308, Step 4.13 Revision # 15 Page 73 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.11 Importance Rating 3.8 Radiation Control: Ability to control radiation releases.

Proposed Question: Common 71 Which of the following is required if a liquid radioactive release is terminated due to a high radiation alarm on the associated release monitor?

A. Verify the high radiation alarm was valid, and if not, recommence the release with current permit.

B. When the cause of the high radiation alarm is determined, the release may be recommenced once a new permit is issued.

C. Initiate a Condition Report to determine the cause of the high radiation alarm, obtain Shift Manager approval to recommence the release with a new permit.

D. Raise the high radiation alarm setpoint with Radiation Protection Managers approval and obtain Shift Managers concurrence to recommence release with current permit.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because the high radiation alarm must be validated, however, a new permit must be issued to continue the release.

B. Correct. Per the guidance in STA-603, the cause of the high radiation must be determined and new permit issued before the release can be performed.

C. Incorrect. Plausible because a new permit must be issued, however, the cause of the high radiation must be determined prior to Shift Manager approval.

D. Incorrect. Plausible if thought that the Radiation Protection Manager's approval is necessary, however, a new release permit must be issued.

Technical Reference(s) STA-603, Step 6.3.11 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 74 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: Given conditions that warrant a radioactive effluent release, EVALUATE and DETERMINE the proper methodology for review and authorization of the release permit.

Given a valid automatic termination of a planned radioactive effluent release, EVALUATE and DETERMINE the proper recovery from automatic termination of a planned radioactive effluent release in accordance with the applicable portion of STA-603, Control of Station Radioactive Effluents.

Question Source: Bank # ADM.XA1.OB03.003 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 13 55.43 Page 75 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-603, Step 6.3.11 Revision # 20 Page 76 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.15 Importance Rating 2.9 Radiation Control: Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: Common 72 An individual is attempting to exit the Radiologically Controlled Area (RCA) following work involving grinding in the vicinity of the Refueling Cavity and enters the Personnel Contamination Monitor (PCM), when the following occurs:

The PCM alarms indicating contamination of the lower left leg.

The count is repeated with the same alarm.

Three other Radiological Workers pass through the same PCM successfully.

Two more attempts by the individual at passing through the PCM are unsuccessful.

Which of the following should be performed per STA-653, Contamination Control Program?

Perform a A. whole body count to check for internal contamination.

B. whole body frisk to check for a discrete radioactive particle.

C. bio-assay examination to check for medical radioisotope usage.

D. calibration check of the PCM to check for setpoint drift.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because as internal contamination could cause the PCM to alarm, however, this would most likely not be in the lower leg area.

B. Correct. In accordance with STA-653, Attachment 3.

C. Incorrect. Plausible because medical radioisotopic use could cause the PCM to alarm, however, this usage is required to be reported to Radiation Protection prior to being granted access to the RCA.

D. Incorrect. Plausible if thought that this was required, however, other individuals are successfully clearing the monitor and the indications are repeatable which does not indicate a calibration issue.

Technical Reference(s) STA-653, Attachment 3 Attached w/ Revision # See STA-653, Step 4.7 Comments / Reference Proposed references to be provided during examination: None Page 77 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11, 12 55.43 Comments /

Reference:

From STA-653, Attachment 3 Revision # 14 Page 78 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-653, Step 4.7 Revision # 14 Page 79 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.12 Importance Rating 4.0 Emergency Procedures / Plan: Knowledge of general operating crew responsibilities during emergency operations.

Proposed Question: Common 73 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.

Proposed Answer: C 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, Attachment 8.A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: DESCRIBE the requirements associated with deviating from an ERG.

Question Source: Bank # ERG.XD2.OB28 01 Modified Bank # (Note changes or attach parent)

New Page 80 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO 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 10 55.43 Comments /

Reference:

From ODA-407, Attachment 8.A Revision # 14 Page 81 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ODA-407, Attachment 8.A Revision # 14 Page 82 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.31 Importance Rating 4.1 Emergency Procedures / Plan: Knowledge of annunciator alarms, indications, or response procedures.

Proposed Question: Common 74 Which of the following must occur in order for annunciator 1-ALB-6B, Window 4.5 - LPMS TRBL, to go into alarm per ABN-910, Loose Part Monitoring Alarms?

A. At least two events exceeding the alarm threshold by 50% must occur greater than one minute apart.

B. At least two events exceeding the alarm threshold must occur greater than one minute apart.

C. At least two events exceeding the alarm threshold by 50% must occur within one minute.

D. At least two events exceeding the alarm threshold must occur within one minute.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because a misconception may exist that a valid loose part alarm would occur over duration instead of during a short time. Additionally, it may be thought that in order to discriminate valid from non-valid alarms the event must exceed the threshold value by a substantial amount.

B. Incorrect. Plausible because a misconception may exist that a valid loose part alarm would occur over duration instead of during a short time.

C. Incorrect. Plausible because the timing of the events is correct and it may be thought that in order to discriminate valid from non-valid alarms the event must exceed the threshold value by a substantial amount.

D. Correct. In accordance with ABN-910, this is the required coincidence to cause ALB-6B Window 4.5 to alarm.

Technical Reference(s) ABN-910, Step 2.3.1 NOTE Attached w/ Revision # See ALM-0062A, 1-ALB-6B, Window 4.5 Comments / Reference Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Loose Parts Monitor system.

DEMONSTRATE an understanding of the components of the Loose Parts Monitor system including interrelations with other systems to include interlocks and control loops.

Page 83 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Question Source: Bank # ABN.SELF.910.001 Modified Bank # (Note changes or attach parent)

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

Reference:

From ABN-910, Step 2.3.1 NOTE Revision # 5 Page 84 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0062A, 1-ALB-6B, Window 4.5 Revision # 6 Page 85 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.34 Importance Rating 4.2 Emergency Procedures / Plan: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

Proposed Question: Common 75 Given the following conditions:

ABN-905, Loss of Control Room Habitability, actions are in progress.

Pressurizer Heater control has been transferred from the Control Room to the Remote Shutdown Panel.

Which of the following identifies the response of the Pressurizer Heaters as Pressurizer level lowers to 10%?

Pressurizer Heaters...

A. will NOT automatically deenergize.

B. will automatically deenergize.

C. Control Group C will NOT automatically deenergize; Backup Groups A, B, and D will deenergize.

D. Backup Groups A, B, and D will NOT automatically deenergize; Control Group C will deenergize.

Proposed Answer: A Explanation:

A. Correct. With the Pressurizer Heaters transferred from the CR to the HSP the low-level heater cut out at 17% Pressurizer level is overridden. This switch selects control from either the Control Room or Hot Shutdown Panel.

B. Incorrect. Plausible if CR were substituted with HSP. When HSP is selected the interlock is overridden.

C. Incorrect. Plausible because all Pressurizer Heaters can be turned OFF at this location, however, they will NOT automatically deenergize.

D. Incorrect. Plausible because all Pressurizer Heaters can be turned OFF at this location, however, they will NOT automatically deenergize.

Technical Reference(s) ABN-905, Step 2.3.26 CAUTION Attached w/ Revision # See Comments / Reference Page 86 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: ANALYZE the response to a Loss of Control Room Habitability in accordance with ABN-905, Loss of Control Room Habitability.

Question Source: Bank # ABN.803.OB02.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Page 87 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 RO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-905, Step 2.3.26 CAUTION Revision # 9 Page 88 of 88 CPNPP NRC 2012 RO Written Exam Worksheet 51 to 75 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 054 G 2.2.4 Importance Rating 3.6 Loss of Main Feedwater: Equipment Control: (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Proposed Question: SRO 76 Given the following conditions:

• Unit 1 was at 100% power when a Reactor Trip occurred due to a Loss of Main Feedwater.

• EOP-0.0A, Reactor Trip or Safety Injection, was exited at Step 4 and the crew transitioned to EOS-0.1A, Reactor Trip Response.

• While in EOS-0.1A, a RED path developed on the Heat Sink Critical Safety Function Status Tree due to a loss of all Auxiliary Feedwater flow.

• The crew transitioned to FRH-0.1A, Response to Loss of Secondary Heat Sink.

• Both Centrifugal Charging Pumps and Condensate Pumps are available.

• Pressurizer pressure is 2000 psig and slowly rising.

• The Reactor Coolant Pumps have been stopped.

• Main Feedwater Pump A was restarted and Feedwater flow has been established to all Steam Generators through the Feedwater Bypass Control Valves.

• Steam Generator (SG) narrow range levels are as follows:

• SG 1-01 is 5%.

• SG 1-02 is 7%.

• SG 1-03 is 6%.

• SG 1-04 is 8%.

Which of the following actions must be performed per FRH-0.1A, Response to Loss of Secondary Heat Sink?

FRH-0.1A, Response to Loss of Secondary Heat Sink, can be exited as soon as narrow range level in any Steam Generator exceeds A. 10%. A transition back to EOS-0.1A, Reactor Trip Response, is performed and continues at the step in effect.

B. 43%. A transition back to EOS-0.1A, Reactor Trip Response, is performed and continues at the step in effect.

C. 10%. A transition to EOP-0.0A, Reactor Trip or Safety Injection, is performed and proper Safety Injection actuation and alignment is verified.

D. 43%. A transition to EOP-0.0A, Reactor Trip or Safety Injection, is performed and proper Safety Injection actuation and alignment is verified.

Page 1 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: B Explanation:

A. Incorrect. Plausible as the procedure entry is correct, however, this is the proper level setpoint to have an adequate heat sink on Unit 2 with no Adverse Containment condition.

B. Correct. The proper level setpoint to have an adequate heat sink on Unit 1 is 43% with no Adverse Containment condition. EOS-0.1A, Step 8, instructs a return to procedure and step in effect.

C. Incorrect. Plausible as this is the proper level setpoint for Unit 2, however, the procedure transition is not correct. This procedure transition would be correct had bleed and feed previously been established in FRH-0.1A.

D. Incorrect. Plausible as this is the proper level setpoint for Unit 1. This procedure transition would be correct had bleed and feed previously been established in FRH-0.1A.

Technical Reference(s) FRH-0.1A, Steps 7 & 8 Attached w/ Revision # See FRH-0.1B, Steps 7 & 8 Comments / Reference Proposed references to be provided during examination: None Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1, Response to Loss of Secondary Heat Sink.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 2 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1A, Step 8 Revision # 8 Page 3 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1A, Step 7 Revision # 8 Page 4 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1B, Step 8 Revision # 8 Page 5 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1B, Step 7 Revision # 8 Page 6 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038 EA2.08 Importance Rating 4.4 Steam Generator Tube Rupture: Ability to determine and interpret the following as they apply to the Steam Generator Tube Rupture: Viable alternatives for placing plant in safe condition when condenser is not available Proposed Question: SRO 77 Given the following conditions:

• Unit 1 is responding to a Steam Generator Tube Rupture (SGTR).

• EOP-3.0A, Steam Generator Tube Rupture, has been completed and a transition to EOS-3.1A, Post-SGTR Cooldown Using Backfill, was made.

• Prior to commencing a Reactor Coolant System (RCS) cooldown, it was determined that 1-PCIP, Window 1.4 - CNDSR AVAIL STM DMP ARMED C-9, was DARK.

Which of the following actions should be taken to cooldown the RCS?

A. Transition to EOS-3.2A, Post-SGTR Cooldown Using Blowdown, and dump steam using the intact Steam Generator Atmospheric Relief Valves.

B. Remain in EOS-3.1A, Post-SGTR Cooldown Using Backfill, and dump steam using the intact Steam Generator Atmospheric Relief Valves.

C. Remain in EOS-3.1A, Post-SGTR Cooldown Using Backfill, and cooldown using the Turbine Driven Auxiliary Feedwater Pump.

D. Transition to EOS-3.3A, Post-SGTR Cooldown Using Steam Dumps, and dump steam using the Steam Dump Valves.

Proposed Answer: B Explanation:

A. Incorrect. Plausible because using the intact Steam Generator Atmospheric Relief Valves if the Steam Dump System is not available is correct if EOS-3.2A is the procedure in use, however, there is no transition point from EOS-3.1A to EOS-3.2A. Entry into EOS-3.3A is from EOP-3.0A when the blowdown method is selected by Plant Staff.

B. Correct. As outlined in EOS-3.1A, Step 6 RNO, use the intact Steam Generator Atmospheric Relief Valves if the Steam Dump System is not available.

C. Incorrect. Plausible because use of the Turbine Driven Auxiliary Feedwater Pump would remove steam and cool the RCS, however, this condition is undesirable due to the potential for a release.

D. Incorrect. Plausible because using the intact Steam Generator Atmospheric Relief Valves if the Steam Dump System is not available is correct if EOS-3.3A is the procedure in use, however, there is no transition point from EOS-3.1A to EOS-3.3A. Entry into EOS-3.3A is either from EOP-3.0A or EOS-3.2A.

Page 7 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) EOS-3.1A, Step 6 Attached w/ Revision # See ALM-0065A, 1-PCIP, Window 1.4 Comments / Reference EOS-3.2A, Step 6 EOS-3.3A, Step 7 Proposed references to be provided during examination: None Learning Objective: Given a procedural step, or sequence of steps from EOS-3.1, Post-SGTR Cooldown Using Backfill, STATE the purpose/basis for the step(s).

Question Source: Bank # ERG.E31.OB04.008 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 8 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-3.1A, Step 6 Revision # 8 Page 9 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0065A, 1-PCIP, Window 1.4 Revision # 4 Page 10 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-3.2A, Step 6 Revision # 8 Page 11 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-3.3A, Step 7 Revision # 8 Page 12 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 040 G 2.2.38 Importance Rating 4.5 Steam Line Rupture - Excessive Heat Transfer: Equipment Control: Knowledge of conditions and limitations in the facility license.

Proposed Question: SRO 78 Given the following condition:

• Unit 1 has experienced a Main Steam Line Break inside Containment.

Which of the following actions is required and the reason for the action in accordance with OWI-214, Control of Time Critical Actions?

Isolate Auxiliary Feedwater to the faulted Steam Generator within A. 10 minutes to preclude exceeding 10CFR100 dose limits.

B. 30 minutes to preclude exceeding 10CFR100 dose limits.

C. 10 minutes to preclude exceeding Containment design pressure and temperature.

D. 30 minutes to preclude exceeding Containment design pressure and temperature.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because this is the proper analysis time for AFW isolation, however, the reason stated is correct for a Main Feedwater Line rupture.

B. Incorrect. Plausible because this is the proper analysis time and reason for a Main Feedwater Line rupture.

C. Correct. This is the proper time and reason as stated in OWI-214 for AFW isolation following a Main Steam Line rupture.

D. Incorrect. Plausible because this is the proper time for a Main Feedwater Line rupture and the proper reason for the Main Steam Line rupture.

Technical Reference(s) OWI-214, Attachment 8.A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Page 13 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Learning Objective: STATE the bases for operator actions, notes and cautions from EOP-2.0, Faulted Steam Generator Isolation.

DISCUSS EOP-0.0, Reactor Trip or Safety Injection, including the Purpose, Applicability, Symptoms/Entry Conditions, Operator Actions, Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1 Comments /

Reference:

From OWI-214, Attachment 8.A Revision # 0 Page 14 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 062 AA2.06 Importance Rating 3.1 Loss of Nuclear Service Water: Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of SWS flow to component before that component may be damaged Proposed Question: SRO 79 Given the following conditions:

• Unit 1 is performing OPT-214A, Diesel Generator Operability Test.

• Diesel Generator (DG) 1-01 is currently running in parallel on Bus 1EA1 and loaded to 6 MWe.

• Annunciator 1-ALB-1, Window 3.11 - DG 1/2 SSW RET FLO LO, alarms during testing.

• 1-FI-4391, DG1 CLR SSW RET FLO, indicates 0 GPM.

• 1-FI-4258A, SSWP 1 DISCH FLO indicates 17,000 GPM.

How long can DG 1-01 continue to operate without affecting diesel performance and what procedure should be used to address the issue?

A. 1 minute; ALM-0011A, 1-ALB-1, Window 3.11 - DG 1/2 SSW RET FLO LO.

B. 15 minutes; ALM-0011A, 1-ALB-1, Window 3.11 - DG 1/2 SSW RET FLO LO.

C. 1 minute; ABN-501, Station Service Water System Malfunction.

D. 15 minutes; ABN-501, Station Service Water System Malfunction.

Proposed Answer: A Explanation:

A. Correct. Per the NOTE in ALM-0011A, the DG can run only 1 minute without affecting DG performance and the response should continue with ALM-0011A.

B. Incorrect. Plausible because the 15 minute time is correct guidance if the DG was not loaded and the response should continue with ALM-0011A.

C. Incorrect. Plausible because the 1 minute time is correct per ALM-0011A, however, the response should continue in accordance with the ALM.

D. Incorrect. Plausible because the 15 minute time is correct guidance if the DG was not loaded and the response should continue in accordance with the ALM.

Technical Reference(s) ALM-0011A, 1-ALB-1, Window 3.11 Attached w/ Revision # See Comments / Reference ABN-501, Step 3.3.5 Page 15 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 ABN-602, Step 2.3.1 CAUTION Proposed references to be provided during examination: None Learning Objective: LOCATE and OPERATE components, including local controls, and VERIFY proper alignment of equipment associated with responding to a SSW / CCW malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2 Page 16 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0011A, 1-ALB-1, Window 3.11 Revision # 9 Page 17 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Step 3.3.5 Revision # 9 Page 18 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Step 2.3.1 CAUTION Revision # 7 Page 19 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # W/E04 G 2.2.22 Importance Rating 4.7 LOCA Outside Containment: Equipment Control: Knowledge of limiting conditions for operations and safety limits.

Proposed Question: SRO 80 Given the following conditions:

• Unit 1 was in MODE 5 with preparations to defuel the Reactor in progress.

• 1-LI-462, PRZR LVL COLD CAL, was being maintained at 20% to 25%.

• 1-PI-403, HL 4 PRESS (WR), indicated 20 psig and stable.

• 1-PI-405, HL 1 PRESS (WR), indicated 19 psig and stable.

• 1-TI-413A, HL 1 TEMP (WR), indicated 110°F and sta ble.

• 1-TI-423A, HL 2 TEMP (WR), indicated 110°F and sta ble.

• Both Residual Heat Removal (RHR) Trains were OPERABLE with Train B in operation.

• All four Steam Generator narrow range water levels were approximately 10%.

• 1/1-PCV-455A PRZR PORV and 1/1-PCV-456 PRZR PORV were both inoperable.

• A Hot Leg vent path had NOT been established.

• A significant Reactor Coolant System (RCS) leak was identified at the suction of the Train A RHR Pump.

• Per ABN-104, Residual Heat Removal System Malfunction, Attachment 20, RHR Train Leak Isolation the 1/1-8701A, RHRP 1 HOT LEG RECIRC ISOL VLV, was CLOSED stopping the RCS leak.

• 1-LI-462, PRZR LVL COLD CAL, lowered to 12% and is being restored to between 20% and 25%.

Which of the following are the REQUIRED ACTIONS in accordance with Technical Specifications?

Immediately restore BOTH Trains of RHR to OPERABLE status per Limiting Condition for Operation (LCO)

A. 3.4.7, RCS Loops - MODE 5, Loops Filled, and restore one required RCS Relief to OPERABLE status per LCO 3.4.12, LTOP System, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. 3.4.8, RCS Loops - MODE 5, Loops Not Filled, and restore one required RCS Relief to OPERABLE status per LCO 3.4.12, LTOP System, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. 3.4.7, RCS Loops - MODE 5, Loops Filled, and restore one required RCS Relief to OPERABLE status per LCO 3.4.12, LTOP System, within 7 days.

D. 3.4.8, RCS Loops - MODE 5, Loops Not Filled, and restore one required RCS Relief to OPERABLE status per LCO 3.4.12, LTOP System, within 7 days.

Page 20 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed Answer: B Explanation:

A. Incorrect. Plausible because if the Loops were considered filled { 35% Cold Cal PRZR level (previously established at 17% level per old revision)} LCO 3.4.7 would be correct, however, the Loops are NOT filled. Twenty-four hours is the correct COMPLETION TIME for one RCS Relief Valves inoperable.

B. Correct. LCO 3.4.8 immediate restoration is correct and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is the correct COMPLETION TIME for one RCS Relief Valve inoperable.

C. Incorrect. Plausible because if the Loops were considered filled { 35% Cold Cal PRZR level (previously established at 17% level per old revision)} LCO 3.4.7 would be correct, however, the Loops are NOT filled. Additionally, 7 days is the COMPLETION TIME with one RCS Relief Valve inoperable in MODE 4.

D. Incorrect. Plausible because LCO 3.4.8 immediate restoration is correct, however, 7 days is the COMPLETION TIME with one RCS Relief Valve inoperable in MODE 4.

Technical Reference(s) ABN-104, Section 1.0 Attached w/ Revision # See ABN-104, Section 5.0 Comments / Reference ABN-104, Attachment 20 Technical Specification LCO 3.4.7 Technical Specification LCO 3.4.8 Technical Specification LCO 3.4.12 Technical Specification LCO 3.9.6 Proposed references to be provided during examination: None Learning Objective: LIST and DESCRIBE the Technical Specifications (i.e. LCOs, Action Statements and conditional surveillance requirements of one hour or less, if applicable) for the RCS 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 55.43 2 Page 21 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-104, Section 1.0 Revision # 8 Page 22 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-104, Section 5.0 Revision # 8 Page 23 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-104, Attachment 20 Revision # 8 Comments /

Reference:

From Technical Specification LCO 3.4.7 Amendment # 150 Page 24 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.7 Amendment # 150 Page 25 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.8 Amendment # 150 Page 26 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.8 Amendment # 150 Comments /

Reference:

From Technical Specification LCO 3.4.12 Amendment # 150 Page 27 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.12 Amendment # 150 Page 28 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.12 Amendment # 150 Comments /

Reference:

From Technical Specification LCO 3.9.6 Amendment # 150 Page 29 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # W/E05 EA2.2 Importance Rating 4.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink: Ability to determine and interpret the following as they apply to the Loss of Secondary Heat Sink: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Proposed Question: SRO 81 Given the following conditions:

• Adverse Containment conditions exist on Unit 1 and all Steam Generator narrow range levels are less than 50%.

• Total Auxiliary Feedwater flow to the Steam Generators is being throttled to less than 460 GPM.

• FRH-0.1A, Response to Loss of Secondary Heat Sink, is about to be entered.

Which of the following sets of procedures would NOT require entry into FRH-0.1A, Response to Loss of Secondary Heat Sink, if Auxiliary Feedwater flow was previously throttled and what is the reasoning behind each?

A. FRS-0.1A, Response to Nuclear Power Generation / ATWT, in order to insert negative reactivity into the Reactor core.

ECA-2.1A, Uncontrolled Depressurization of All Steam Generators, in order to minimize thermal stresses on Steam Generator components.

B. FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition, in order to minimize effects of Reactor Coolant System cooldown.

FRZ-0.2A, Response to Containment Flooding, in order to minimize water input to the Containment Building Sumps.

C. FRZ-0.1A, Response to High Containment Pressure, in order to minimize thermal stresses on Steam Generator components.

ECA-0.1A, Loss of All AC Power Recovery Without SI Required, in order to avoid initiation of Safety Injection while cooling down.

D. ECA-2.1A, Uncontrolled Depressurization of All Steam Generators, in order to minimize thermal stresses on Steam Generator components.

FRH-0.3A, Response to Steam Generator High Level, in order to restore the Steam Generator levels to the normal control band.

Proposed Answer: A Page 30 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. NOTE in FRH-0.1A Critical Safety Function Status Tree identifies ECA-2.1A, FRP-0.1A, FRS-0.1A, and FRZ-0.1A as procedures that have operator actions to throttle AFW flow that may cause a RED path condition. The bases for each procedure listed states the reason for throttling AFW flow.

B. Incorrect. Plausible because FRP-0.1A and reason given are correct, however, FRZ-0.2A does not direct throttling AFW flow to minimize water input to the Containment Sump.

C. Incorrect. Plausible because FRZ-0.1A and reason given are correct, however, ECA-0.1A does not direct throttling AFW flow to avoid Safety Injection.

D. Incorrect. Plausible because ECA-2.1A and reason given are correct, however, FRH-0.3A does not direct throttling AFW flow to lower SG level without level satisfying heat sink requirements.

Technical Reference(s) FRH-0.1A, CSF Status Tree Attached w/ Revision # See FRS-0.1A, Attachment 3, Step 17 Bases Comments / Reference FRP-0.1A, Attachment 4, Step 2 Bases FRZ-0.1A, Attachment 6, Step 6 Bases ECA-2.1A, Attachment 4, Step 2 Bases Proposed references to be provided during examination: None Learning Objective: DISCUSS the symptoms or Entry Conditions for FRH-0.1, Response to Loss of Secondary Heat Sink.

Question Source: Bank #

Modified Bank # ERG.FH1.OB03.004 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 31 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRH-0.1A, CSF Status Tree Revision # 8 Page 32 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRS-0.1A, Attachment 3 Step 17 Bases Revision # 8 Page 33 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Attachment 4, Step 2 Bases Revision # 8 Page 34 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRZ-0.1A, Attachment 6, Step 6 Bases Revision # 8 Page 35 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-2.1A, Attachment 4, Step 2 Bases Revision # 8 Page 36 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ERG.FH1.OB03.004 Revision # N/A Given the following conditions:

• Adverse Containment conditions exist and all Steam Generator narrow range levels are less than 50% on Unit 1.

• Total Auxiliary Feedwater flow to the Steam Generators is being throttled to less than 460 GPM.

• FRH-0.1A, Response to Loss of Secondary Heat Sink, is about to be entered.

FRH-0.1A, Response to Loss of Secondary Heat Sink, entry would NOT be required if feedwater flow was throttled as instructed by which of the following group of procedures?

A. FRS-0.1A, Response to Nuclear Power Generation / ATWT.

FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

FRZ-0.1A, Response to High Containment Pressure.

ECA-2.1A, Uncontrolled Depressurization of All Steam Generators.

B. FRS-0.1A, Response to Nuclear Power Generation / ATWT.

FRC-0.1A, Response to Inadequate Core Cooling.

ECA-2.1A, Uncontrolled Depressurization of All Steam Generators.

ECA-0.1A, Loss of All AC Power Recovery Without SI Required.

C. FRC-0.1A, Response to Inadequate Core Cooling.

FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

ECA-0.1A, Loss of All AC Power Recovery Without SI Required.

ECA-2.1A, Uncontrolled Depressurization of All Steam Generators.

D. FRS-0.1A, Response to Nuclear Power Generation / ATWT.

FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

FRZ-0.1A, Response to High Containment Pressure.

ECA-0.1A, Loss of All AC Power Recovery Without SI Required.

Page 37 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 028 AA2.07 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 Proposed Question: SRO 82 Given the following conditions:

• Unit 2 is in MODE 1.

• ABN-706, Pressurizer Level Instrumentation Malfunction, was entered due to controlling level channel, 2-LT-0459, PRESSURIZER 2-01 LEVEL PROT CHANNEL I failing low.

• While performing Attachment 6, Reestablishing Normal Letdown Following Letdown Isolation, the following annunciator alarmed:

• 2-ALB-5A, Window 1.6 - ANY RCP SEAL INJ FLO LO.

• Centrifugal Charging Pump 2-01 is in service.

• All Reactor Coolant Pumps (RCP) seal injection flows indicate approximately 5.5 GPM.

Which of the following actions are required?

A. Enter ABN-105, Chemical and Volume Control System Malfunction, and manually control 2-FK-121, CCP CHRG FLO CTRL and 2-HC-182 RCP SEAL WTR PRESS CTRL.

B. Trip the Reactor, enter EOP-0.0B, Reactor Trip or Safety Injection, then stop all Reactor Coolant Pumps.

C. Enter ABN-101, Reactor Coolant Pump Malfunction, and verify Component Cooling Water flow to the RCP Thermal Barrier Coolers greater than or equal to 35 GPM.

D. Remain in ABN-706, Pressurizer Level Instrumentation Malfunction, and adjust Charging flow while maintaining seal injection flows between 6 and 13 GPM.

Proposed Answer: D Page 38 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because ABN-105 contains a procedure section for Pressurizer Level Increasing Above Program which it would be with a Pressurizer level instrument failure, however, ABN-105 instructs recovery actions to be performed per ABN-706.

B. Incorrect. Plausible because a loss of seal injection and CCW Thermal Barrier cooling would require this response, however, adjusting 2-HC-182 is the proper course of action.

C. Incorrect. Plausible because these actions would be correct for a loss of seal injection flow, however, seal injection flow has not been lost but adjustment to 2-HC-182 is required per ABN-706.

D. Correct. ABN-706, Attachment 6, has instructions to maintain seal injection flow between 6 and 13 GPM. Maintain seal injection carries a continual action performance and the operator should continue to adjust 2-HC-182 per ABN-706.

Technical Reference(s) ABN-706, Attachment 6 Attached w/ Revision # See ABN-101, Steps 7.3.1 & 9.3.1 Comments / Reference ABN-105, Section 4.0 & Step 4.3.2 Proposed references to be provided during examination: None 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 Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 39 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-706, Attachment 6 Revision # 7 Page 40 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-101, Step 7.3.1 Revision # 10 Page 41 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-101, Step 9.3.1 Revision # 10 Page 42 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-105, Section 4.0 Revision # 7 Comments /

Reference:

From ABN-105, Step 4.3.2 Revision # 7 Page 43 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 037 G 2.4.6 Importance Rating 4.7 Steam Generator Tube Leak: Emergency Procedures/Plan: Knowledge of EOP mitigation strategies.

Proposed Question: SRO 83 Given the following conditions:

• Unit 1 is at full power.

• A Steam Generator (SG) sample taken at 1130 indicated total SG tube leakage at 25 GPD.

• A subsequent Steam Generator sample taken at 1200 indicated 130 GPD tube leakage in SG 1-01.

• 1-RE-2325A, (N16-174) MAIN STEAM LINE 1-01 LEAK RATE, is in RED alarm and has shown a steady increase.

• 1-RE-2959, (COG-182) CONDENSER OFF GAS, is trending up.

Which of the following action(s) are required per ABN-106, High Secondary Activity?

A. Place the Unit in MODE 3 by 1600 today per Technical Specification LCO 3.4.13, RCS Operational LEAKAGE.

B. Place the Unit in MODE 3 by 1200 tomorrow per IPO-003A, Power Operation.

C. Trip the Reactor and respond per EOP-0.0A, Reactor Trip or Safety Injection and EOP-3.0A, Steam Generator Tube Rupture.

D. Reduce power to less than 50% by 1300 today and place the Unit in MODE 3 by 1500 per IPO-003A, Power Operation.

Proposed Answer: D Page 44 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because this would be the correct action based on the leak rate exceeding 150 GPD, however, the rate of the change of the leak requires a faster response to reduce power and take the Unit off-line.

B. Incorrect. Plausible because this is the correct action based on the leak rate being greater than 75 GPD and sustained, however, the rate of the change of the leak requires a faster response to reduce power and take the Unit off-line.

C. Incorrect. Plausible because under some conditions a Reactor Trip and Safety Injection would be appropriate, however, it is not required for this situation as the leak is well within the capacity of the Charging and Makeup Systems.

D. Correct. With leakage more than 75 GPD and increasing at greater than 30 GPD per hour, power must be reduced below 50% within one hour and MODE 3 achieved within the following two hours.

Technical Reference(s) ABN-106, Step 3 NOTE Attached w/ Revision # See ABN-106, Step 5.b RNO Comments / Reference STA-732, Attachment 8.B Proposed references to be provided during examination: STA-732, Attachment 8.B Learning Objective: ANALYZE the response to a Steam Generator Tube Leakage less than 75 GPD in accordance with ABN-106, High Secondary Activity.

Question Source: Bank #

Modified Bank # ABN.106.OB01.001 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2, 5 Page 45 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-106, Step 3 NOTE Revision # 9 Page 46 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-106, Step 5.b RNO Revision # 9 Page 47 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-732, Attachment 8.B Revision # 3 Page 48 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # W/E15 EA2.1 Importance Rating 3.2 Containment Flooding: Ability to determine and interpret the following as they apply to the (Containment Flooding): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Proposed Question: SRO 84 Given the following conditions:

• A Large Break Loss of Coolant Accident has occurred on Unit 2.

• EOP-1.0B, Loss of Reactor or Secondary Coolant, is in progress.

• The initial scan of Critical Safety Function Status Tree parameters indicate the following:

• Pressurizer level is 0%.

• Containment water level indicates 817 feet and slowly rising.

• Containment Spray has automatically actuated and was verified in EOP-0.0B, Reactor Trip or Safety Injection.

• Containment pressure is 14 psig and slowly lowering.

• Containment Radiation Monitors are in ALARM at 25 REM/hr.

• Reactor Vessel Level Indication System has NO lights LIT.

• Core Exit Thermocouples are 292°F.

Which procedure has entry priority to address the above conditions?

A. FRZ-0.2B, Response to Containment Flooding.

B. FRZ-0.1B, Response to High Containment Pressure.

C. FRI-0.2B, Response to Low Pressurizer Level.

D. FRZ-0.3B, Response to High Containment Radiation Level.

Proposed Answer: A Page 49 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Given the conditions listed, entry into FRZ-0.2B is correct due to a Containment Flooding condition existing.

B. Incorrect. Plausible because Containment pressure is 16 psig and slowly rising, however, it does not meet the Critical Safety Function Status Tree (CSFST) requirement for entry into FRZ-0.1B.

C. Incorrect. Plausible because Pressurizer level is low and the requirements to enter FRI-0.2B are met, however, it is a Yellow Path condition in the CSFST hierarchy.

D. Incorrect. Plausible because Containment radiation level is high and entry conditions for FRZ-0.3B are met, however, it is a Yellow Path condition in the CSFST hierarchy.

Technical Reference(s) FRZ-0.2B, Containment CSFST Attached w/ Revision # See FRI-0.2B, Inventory CSFST Comments / Reference Proposed references to be provided during examination: None Learning Objective: DISCUSS the symptoms, or Entry Conditions for FRZ-0.2, Response to Containment Flooding.

Question Source: Bank # ERG.FZ2.OB03.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam CPNPP 2010 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 50 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRZ-0.2B, Containment CSFST Revision # 8 Page 51 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRI-0.2B, Inventory CSFST Revision # 8 Page 52 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # W/E08 G 2.1.23 Importance Rating 4.4 RCS Overcooling - PTS: Conduct of Operations: Ability to perform specific and integrated plant procedures during all modes of plant operation.

Proposed Question: SRO 85 Given the following conditions:

• A Reactor Trip from 100% power occurred 35 minutes ago on Unit 1.

• Reactor Coolant System TCOLD is 240°F and slowly lowering slowly.

• Reactor Coolant System pressure is 30 psig and slowly lowering.

• Containment pressure is 30 psig and slowly lowering.

• Pressurizer level indicates 0%.

• Reactor Vessel Level Indication System - 11 inches above the Core Plate is LIT.

• Reactor Coolant System (RCS) subcooling is 0°F.

• Emergency Core Cooling System (ECCS) flow is occurring.

• All Engineered Safety Feature Actuations were as expected.

Which of the following addresses Pressurized Thermal Shock and the required actions?

A. ECCS flow has caused RCS cooldown to exceed the entry criteria for FRP-0.2A, Response to Anticipated Pressurized Thermal Shock Condition.

Enter FRP-0.2A and reduce Reactor Coolant System cooldown by throttling ECCS flow.

B. RCS cooldown has exceeded the entry criteria for FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

Enter FRP-0.1A and verify RCS pressure is less than Residual Heat Removal Pump shutoff head.

C. RCS cooldown has exceeded the entry criteria for FRP-0.2A, Response to Anticipated Pressurized Thermal Shock Condition.

Enter FRP-0.2A and the place Low Temperature Overpressure Protection System in service.

D. RCS pressure and temperature are to the right of the Limit A curve so no challenge exists to Pressurized Thermal Shock.

Enter FRI-0.3A, Response to Voids in the Reactor Vessel, to perform Reactor Head venting.

Proposed Answer: B Page 53 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because Emergency Core Cooling System (ECCS) flow has caused the cooldown, however, a criterion to reduce ECCS flow does not exist.

B. Correct. An ORANGE Path Pressurized Thermal Shock challenge exists but ECCS flow due to a Large Break Loss of Coolant Accident is the cause and repressurizing is unlikely. The actions are to ensure the Residual Heat Removal Pumps are preserved.

C. Incorrect. Plausible because placing Low Temperature Overpressure Protection in service would be performed if ECCS was not required, however, criteria for entry into FRP-0.1A has been met.

D. Incorrect. Plausible because RCS pressure and temperature are to the right of the curve but that doesnt mean a PTS challenge does not exist. FRI-0.3A does not take actions if ECCS is in service.

Technical Reference(s) FRP-0.1A, Integrity CSFST Attached w/ Revision # See FRP-0.1A, Step 1 Comments / Reference Proposed references to be provided during examination: None Learning Objective: DISCUSS the symptoms or Entry Conditions for FRP-0.1, Response to Imminent Pressurized Thermal Shock Condition.

Question Source: Bank # ERG.FP1.OB03.002 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 54 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Integrity CSFST Revision # 8 Page 55 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From FRP-0.1A, Step 1 Revision # 8 Page 56 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 G 2.4.35 Importance Rating 4.0 Reactor Coolant Pump System: Emergency Procedures/Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Proposed Question: SRO 86 Given the following conditions:

• Unit 1 is in MODE 3 following a Reactor Trip.

• EOS-0.2A, Natural Circulation Cooldown, has been entered.

• Starting a Reactor Coolant Pump (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. HOT LOOP position in accordance with SOP-108A, Reactor Coolant Pump, to ensure locked rotor protection is properly defeated.

B. COLD LOOP position in accordance with SOP-108A, Reactor Coolant Pump, to restore the locked rotor and failure to accelerate automatic trips.

C. HOT LOOP position in accordance with EOS-0.2A, Natural Circulation Cooldown, Attachment 3, Starting an RCP, to ensure locked rotor protection is properly defeated.

D. COLD LOOP position in accordance with EOS-0.2A, Natural Circulation Cooldown, Attachment 3, Starting an RCP, to restore the locked rotor and failure to accelerate automatic trips.

Proposed Answer: D Page 57 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. 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. Further, the procedure referenced is not appropriate for the current procedure usage hierarchy.

B. Incorrect. Plausible because the Cold Loop position is correct for the appropriate reason, however, as the ERG is the higher tier procedure using the guidance of SOP-108A would be inappropriate when guidance is provided in the ERG.

C. Incorrect. 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. The procedure referenced is correct.

D. Correct. When performing the ERGs, the guidance of the Attachment should be used for an evolution when direction is given. The Cold Loop position restores the locked rotor and failure to accelerate automatic RCP trips.

Technical Reference(s) EOS-0.2 A, Attachment 3, Step 2.g Attached w/ Revision # See SOP-108A, Section 4.2 Comments / Reference SOP-108A, Steps 5.1.L & 5.1.AC Proposed references to be provided during examination: None Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.2, Natural Circulation Cooldown.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 58 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.2 A, Attachment 3, Step 2.g Revision # 8 Page 59 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-108A, Section 4.2 Revision # 12 Comments /

Reference:

From SOP-108A, Step 5.1.L Revision # 12 Page 60 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-108A, Step 5.1.AC Revision # 12 Page 61 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005 A2.02 Importance Rating 3.7 Residual Heat Removal System: Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown Proposed Question: SRO 87 Given the following conditions:

• Unit 2 is in MODE 4.

• Train A Residual Heat Removal (RHR) System is in standby readiness alignment.

• Train B RHR System is operating in the Shutdown Cooling Mode.

• 1/2-PCV-455A, PRZR PORV and 1/2-PCV-456, PRZR PORV are both operable.

• All four Reactor Coolant System (RCS) Cold Leg temperatures are 330°F and stable.

• Pressurizer level is 50% and stable.

• IPO-001B, Plant Heatup from Cold Shutdown to Hot Standby, is in progress.

• IPO-001B, Plant Heatup from Cold Shutdown to Hot Standby, Attachment 6, Elevated Pressure for ECCS Check Valve Testing, is being implemented.

Which of the following configurations, identified in IPO-001B, Plant Heatup from Cold Shutdown to Hot Standby, Attachment 6, Elevated Pressure for ECCS Check Valve Testing, would allow exiting the Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System LCO and allow raising Reactor Coolant System pressure to 1800 psig?

Train B RHR in A. standby readiness, two Reactor Coolant Pumps running, and RCS heatup rate at 50°F per hour.

B. Shutdown Cooling Mode, one Reactor Coolant Pump running, and RCS heatup rate at 50°F per hour.

C. standby readiness, one Reactor Coolant Pump running, and RCS heatup rate at 70°F per hour.

D. Shutdown Cooling Mode, two Reactor Coolant Pumps running, and RCS heatup rate at 70°F per hour.

Proposed Answer: A Page 62 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Technical Specification LCO 3.4.12 NOTE and IPO-001B, Attachment 6 direction.

B. Incorrect. Plausible because RCP and heatup rate status are correct, however, RHR status is not correct. IPO-001B requires all Hot Leg Suction Valves CLOSED which renders RHR inoperable.

C. Incorrect. Plausible because RCP and RHR status are correct, however, heatup rate has to be less than or equal to 60°F.

D. Incorrect. Plausible because RCP status is correct, however, heatup rate and RHR status are not correct.

Technical Reference(s) Technical Specification LCO 3.4.12, LTOP Attached w/ Revision # See IPO-001B, Attachment 6 Comments / Reference Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Low Temperature Overpressure Protection System and PREDICT the system response.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 63 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.12, LTOP Amendment # 150 Page 64 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From IPO-001B, Attachment 6 Revision # 10 Page 65 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010 A2.03 Importance Rating 4.2 Pressurizer Pressure Control System: Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures Proposed Question: SRO 88 Given the following conditions:

• A Unit 1 Reactor Trip has occurred on Low Pressurizer Pressure.

• EOP-0.0A, Reactor Trip or Safety Injection, is in progress.

• All Emergency Core Cooling System (ECCS) equipment is operating as required.

• While performing EOP-0.0A, Reactor Trip or Safety Injection, Step 10, Check PRZR Valve Status, the following conditions exist:

• Reactor Coolant System (RCS) subcooling is 17°F.

• Pressurizer level is 100%.

• 1-PCV-456, PRZR PORV, red position indicator is LIT.

• Steam Generator 1-02 is depressurizing uncontrollably.

Which of the following lists ALL actions required per EOP-0.0A, Reactor Trip or Safety Injection?

A. Trip Reactor Coolant Pumps.

If the PORV CANNOT be isolated then transition directly to EOP-2.0A, Faulted Steam Generator Isolation, Step 1.

B. Trip Reactor Coolant Pumps.

If the PORV CANNOT be isolated then transition directly to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

C. Maintain Reactor Coolant Pumps in operation.

If the PORV CANNOT be isolated then transition directly to EOP-2.0A, Faulted Steam Generator Isolation, Step 1.

D. Maintain Reactor Coolant Pumps in operation.

If the PORV CANNOT be isolated then transition directly to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

Proposed Answer: B Page 66 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the Reactor Coolant Pumps must be tripped due to a loss of subcooling, however, a transition to EOP-2.0A does not occur until SG pressures are checked later in the procedure.

B. Correct. Given the conditions listed, the Reactor Coolant Pumps are tripped per the EOP-0.0A Foldout Page upon loss of Reactor Coolant System subcooling. At Step 10, if the PORV and/or Block Valve cannot be closed, a transition is made to EOP-1.0A, Loss of Reactor or Secondary Coolant.

C. Incorrect. Plausible if thought that a direct transition to EOP-2.0A was correct and that the RCPs could continue to be operated.

D. Incorrect. Plausible because EOP-0.0A actions are correct, however, the RCPs must be stopped.

Technical Reference(s) EOP-0.0A, Attachment 1.0A, Foldout Page Attached w/ Revision # See EOP-0.0A, Step 10 RNO Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: DISCUSS EOP-0.0, Reactor Trip or Safety Injection including the Purpose, Applicability, Symptoms/Entry Conditions, Operator Actions, Bases, Foldout Pages and Attachments.

ANALYZE the diagnostic steps of EOP-0.0, Reactor Trip or Safety Injection.

Question Source: Bank #

Modified Bank # ERG.E0A.OB07.002 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 67 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Attachment 1.0A, Foldout Page Revision # 8 Page 68 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Step 10 RNO Revision # 8 Page 69 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ERG.E0A.OB07.002 Revision # N/A Given the following conditions:

• A Reactor Trip has occurred on Low Pressurizer Pressure.

• EOP-0.0A, Reactor Trip or Safety Injection, is in progress.

• All Train A Emergency Core Cooling System (ECCS) equipment is operating as required.

• Train B ECCS equipment has failed to start.

• While performing Step 10, Check PRZR Valve Status, the following conditions exist:

• Reactor Coolant System (RCS) pressure is 1000 PSIG.

• RCS temperature is 550°F.

• Pressurizer level is 100%.

• 1-PCV-456, PRZR PORV, red position indicator is LIT.

Which of the following lists all the actions that are required per EOP-0.0A, Reactor Trip or Safety Injection?

A. Attempt to close the PORV and/or Block Valve; if the PORV CANNOT be isolated, continue in EOP-0.0A, Reactor Trip or Safety Injection to determine appropriate transition.

B. Attempt to close the PORV and/or Block Valve; if the PORV CANNOT be isolated, transition directly to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

C. Trip Reactor Coolant Pumps; attempt to close the PORV and/or Block Valve; if the PORV CANNOT be isolated, and continue in EOP-0.0A, Reactor Trip or Safety Injection to determine appropriate transition.

D. Trip Reactor Coolant Pumps; attempt to close the PORV and/or Block Valve; if the PORV CANNOT be isolated, transition directly to EOP-1.0A, Loss of Reactor or Secondary Coolant Step 1.

Page 70 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064 A2.04 Importance Rating 3.0 Emergency Diesel Generator System: Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unloading prior to securing an EDG Proposed Question: SRO 89 Given the following conditions:

• Unit 1 is in MODE 1.

• A fault occurred on XST2.

• XST1 was available and a Slow Transfer was completed.

• During the transient, Emergency Diesel Generator (EDG) 1-01 inadvertently started.

CS-1EG1, DG1 BKR 1EG1, remained open.

• Reactor power has been reduced to 95%.

• All Auxiliary Feedwater Pumps have been secured and placed in Standby.

• As a result of higher priority issues in the Control Room, 40 minutes have elapsed since the fault on XST2.

• ABN-602, Response to a 6900/480V System Malfunction, Section 8.0, Plant Recovery from a Blackout Sequencer Signal, Step 8.3.8, Check Either DG Supply Breaker -

CLOSED, is in progress.

Which of the following actions is required for the present plant conditions and what procedure should be used to perform this action?

EDG 1-01 should be A. loaded to 3.5 MW for at least 60 minutes per ABN-602, Response to a 6900/480V System Malfunction.

B. loaded to 3.5 MW for at least 60 minutes per SOP-609A, Diesel Generator System.

C. stopped per ABN-602, Response to a 6900/480V System Malfunction.

D. stopped per SOP-609A, Diesel Generator System.

Proposed Answer: B Page 71 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because the proper action is to run EDG 1-01 for at least 60 minutes at 3.5 MW, however, the proper procedure is SOP-609A per ABN-602, Step 8.3.8 RNO.

B. Correct. This is the proper action per ABN-602 and SOP-609A.

C. Incorrect. Plausible because if EDG 1-01 were not loaded for greater than 30 minutes, ABN-602 Step 8.3.8 RNO would have the DGs stopped by taking the DG EMER STOP/START handswitch to STOP, however, EDG 1-01 has been loaded for greater than 30 minutes and therefore must be loaded to 3.5 MW for at least 60 minutes per SOP-609A.

D. Incorrect. Plausible because if EDG 1-01 were not loaded for greater than 30 minutes, ABN-602 Step 8.3.8 RNO would have the DGs stopped by taking the DG EMER STOP/START handswitch to STOP, however, EDG 1-01 has been loaded for greater than 30 minutes and therefore must be loaded to 3.5 MW for at least 60 minutes per SOP-609A.

Technical Reference(s) SOP-609A, Section 3.2 Attached w/ Revision # See ABN-602, Steps 8.3.8 & 8.3.11 Comments / Reference ABN-602, Section 8.0 Proposed references to be provided during examination: None Learning Objective: PERFORM required plant procedures as required in response to a Station Electrical malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 72 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-609A, Section 3.2 Revision # 20 Page 73 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Steps 8.3.8 & 8.3.11 Revision # 7 Page 74 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-602, Section 8.0 Revision # 7 Page 75 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076 G 2.4.46 Importance Rating 4.2 Service Water System: Emergency Procedures/Plan: Ability to verify that the alarms are consistent with the plant conditions.

Proposed Question: SRO 90 Given the following conditions:

• Unit 1 is in MODE 1.

• Both Trains of Station Service Water (SSW) are in service.

• Component Cooling Water (CCW) Train A is in service.

• Annunciator 1-ALB-1, Window 1.10 - SSW TO CCW TRN A P LO, has alarmed.

Which of the following actions is required in accordance with ALM-0011A, 1-ALB-1, Window 1.10 - SSW TO CCW TRN A P LO?

Ensure CCW Pump 1-01 is in service; monitor CCW Surge Tank level and if CCW Surge Tank level is A. rising, enter ABN-502, Component Cooling Water System Malfunctions, for leakage into the CCW system.

B. stable, remain in ALM-0011A, Alarm Procedures Manual to isolate Train A CCW Heat Exchanger.

C. lowering and can NOT be maintained greater than 65%, enter ABN-502, Component Cooling Water System Malfunctions, for leakage out of CCW.

D. lowering but can be maintained greater than 65%, enter ABN-501, Station Service Water System Malfunctions, to ensure SSW Pump 1-01 is shutdown.

Proposed Answer: C Page 76 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because leakage into the CCW System would result in an entry into ABN-502, however, based on differential pressures of the SSW and CCW Systems leakage would always be from CCW to SSW.

B. Incorrect. Plausible because the ALM does address the potential for level to be stable, however, the proper actions would be to have maintenance address an instrument malfunction. Isolation of the Heat Exchanger (HX) would only occur for an actual leak.

C. Correct. In accordance with the ALM, if CCW Surge Tank level cannot be maintained above 65%,

entry into ABN-502 is required.

D. Incorrect. Plausible because if level can be maintained in the CCW Surge Tank, further actions to shutdown CCWP 1-01 are required but not SSWP 1-01. These actions are in ALM-0011A and not in ABN-501.

Technical Reference(s) ALM-0011A, 1-ALB-1, Window 1.10 Attached w/ Revision # See ABN-502, Sections 3.1, 3.2, & 3.3 Comments / Reference ABN-501, Section 1.0 Proposed references to be provided during examination: None Learning Objective: OPERATE and / or MONITOR the following in response to a SSW / CCW malfunction: Alarm indicators & Control board indicators.

EVALUATE plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation while responding to a SSW / CCW malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 77 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ALM-0011A, 1-ALB-1, Window 1.10 Revision # 9 Page 78 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-502, Sections 3.1 & 3.2 Revision # 6 Page 79 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Section 3.3 Revision # 6 Page 80 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-501, Section 1.0 Revision # 9 Page 81 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 029 A2.03 Importance Rating 3.1 Containment Purge System: Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Startup operations and the associated required lineups Proposed Question: SRO 91 Given the following conditions:

• Unit 1 is in MODE 5.

• A Containment Purge is planned.

• Containment pressure is 1.1 psig.

Which of the following identifies the impact on the Containment and what actions should be taken?

A. Containment Ventilation Isolation signal must be bypassed until the purge is initiated.

Refer to SOP-706, Digital Radiation Monitoring System, for Bypassing Containment Ventilation Isolation.

B. Outage Auxiliary Containment Cooling Unit Fan should be redirected towards any highly contaminated areas to maximize purge impact.

Contact Health Physics personnel for guidance on redirecting discharge flow per SOP-801A, Containment Ventilation System.

C. Containment pressure must be reduced using the Containment Pressure Relief System.

Refer to SOP-801A, Containment Ventilation System, and lower Containment pressure to atmospheric.

D. Fuel Transfer Tube gate valve must be closed to ensure Spent Fuel Pool level is unaffected by the purge.

Refer to RF0-404, Refueling Gate Operation for guidance regarding positioning of the Fuel Transfer Tube gate valve.

Proposed Answer: C Page 82 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because starting a Containment Purge can generate spurious Containment Ventilation Isolation signals, however, CVI must remain operational during core alterations or movement of irradiated fuel per Technical Specification LCO 3.9.4.

B. Incorrect. Plausible because Health Physics personnel should be contacted if this fan is to be used, however, Precautions of SOP-801A do not allow this action.

C. Correct. With Containment pressure greater than atmospheric, pressure must be reduced per SOP-801A.

D. Incorrect. Plausible because a Precaution does exist regarding the differential pressure created and resultant change in Spent Fuel Pool and Refueling Pool levels, however, this valve need not be closed. The Fuel Transfer Tube Gate Valves are closed for Transfer Canal and Refueling Cavity Lift Gate operations.

Technical Reference(s) SOP-801A, Step 5.6.5 Attached w/ Revision # See SOP-801A, Precautions & Step 4.1.A Comments / Reference SOP-801A, Step 5.1.1.C Proposed references to be provided during examination: None Learning Objective: COMPREHEND the normal, abnormal and emergency operation of the Containment System.

APPLY the administrative requirements of the Containment Ventilation System including Technical Specifications, TRM and ODCM.

Question Source: Bank # CPNPP 2011 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam CPNPP 2011 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 83 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-801A, Step 5.6.5 Revision # 13 Page 84 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-801A, Precautions Revision # 13 Comments /

Reference:

From SOP-801A, Step 4.1 Revision # 13 Page 85 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From SOP-801A, Step 5.1.1.C Revision # 13 Page 86 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 056 A2.05 Importance Rating 2.5 Condensate System: Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Condenser tube leakage Proposed Question: SRO 92 Given the following conditions:

• Unit 1 is at 100% power.

• Annunciator 1-ALB-7B, Window 3.5 - SEC SMPL PNL TRBL, is in alarm.

• ABN-304, Main Condenser and Circulating Water System Malfunction, Section 4.0, Main or Auxiliary Condenser Tube Leak, is in progress.

• Chemistry has verified Steam Generator Blowdown Sodium concentration at 1500 ppb.

Which of the following is performed to mitigate the situation?

A. Trip the Reactor and enter EOP-0.0A, Reactor Trip or Safety Injection.

Remove all Condensate Polishers from service.

B. Trip the Reactor and enter EOP-0.0A, Reactor Trip or Safety Injection.

Maximize Steam Generator Blowdown flow.

C. Initiate a power reduction per IPO-003A, Power Operation to be less than or equal to 50% power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Maximize Steam Generator Blowdown flow.

D. Initiate a power reduction per IPO-003A, Power Operation to be less than or equal to 50% power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Remove all Condensate Polishers from service.

Proposed Answer: B Page 87 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect Plausible because the correct action per ABN-304 is to trip the Reactor, however, all Condensate Polishers are to be placed in service. As the polishers will exhaust quickly with high sodium levels it is reasonable to assume removing them from service would protect the polishers for later secondary cleanup efforts.

B. Correct. These are the proper actions in accordance with ABN-304 to trip the Reactor and maximize blowdown flow.

C. Incorrect. Plausible because maximizing Steam Generator blowdown flow is required, however, a Reactor Trip is required with this sodium concentration.

D. Incorrect. Plausible because the polishers will exhaust quickly with high sodium levels it is reasonable to assume removing them from service would protect the polishers for later secondary cleanup efforts. Additionally, a Reactor Trip is required with this sodium concentration.

Technical Reference(s) ABN-304, Steps 4.1.a, 4.3.3, & 4.3.7.b Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: EVALUATE plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation while responding to a Main Condenser, Circulating Water, and TPCW malfunction.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1, 5 Page 88 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-304, Step 4.3.3 Revision # 8 Page 89 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-304, Step 4.3.7 Revision # 8 Page 90 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-304, Step 4.1.a Revision # 8 Page 91 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 072 G 2.4.3 Importance Rating 3.9 Area Radiation Monitoring System: Emergency Procedures/Plan: Ability to identify post-accident instrumentation Proposed Question: SRO 93 Given the following conditions:

• Unit 1 is performing a heatup per IPO-001A, Plant Heatup from Cold Shutdown to Hot Standby.

• Reactor Coolant System temperature is 340°F.

• 1-RE-6290A, Containment High Range Radiation Monitor, has failed.

Which of the following describes the Technical Specification impact as a result of this failure?

A. Upon entering MODE 3, initiate the REQUIRED ACTION to restore the monitor to OPERABLE status within 7 days.

B. Initiate the REQUIRED ACTION to restore the monitor to OPERABLE status within 7 days.

C. Upon entering MODE 3, initiate the REQUIRED ACTION to restore the monitor to OPERABLE status within 30 days.

D. Initiate the REQUIRED ACTION to restore the monitor to OPERABLE status within 30 days.

Proposed Answer: C Explanation:

A. Incorrect. Plausible because this is action required by CONDITION C, however; only one required channel is inoperable.

B. Incorrect. Plausible because this is the required COMPLETION TIME for CONDITION B, however; the REQUIRED ACTION and associated COMPLETION TIME of CONDITION A are still in effect.

C. Correct. The Technical Specification applies in MODES 1, 2 & 3, so upon entry into MODE 3 CONDITION A applies and the COMPLETION TIME to restore the monitor to OPERABLE status is 30 days.

D. Incorrect. Plausible because this is the required COMPLETION TIME for CONDITION C, however; the REQUIRED ACTION and associated COMPLETION TIME of CONDITION A are still in effect.

Technical Reference(s) Technical Specification LCO 3.3.3 Attached w/ Revision # See Technical Specification Table 3.3.3-1 Comments / Reference Page 92 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Proposed references to be provided during examination: None Learning Objective: APPLY the administrative requirements of the Post Accident Instrumentation including Technical Specifications, TRM and ODCM.

Question Source: Bank # SYS.PA1.OB04.005 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2, 4 Page 93 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Technical Specification LCO 3.3.3 Amendment # 150 Page 94 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Technical Specification LCO 3.3.3 Amendment # 150 Page 95 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Technical Specification Table 3.3.3-1 Amendment # 150 Page 96 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.34 Importance Rating 3.5 Conduct of Operations: Knowledge of primary and secondary plant chemistry limits.

Proposed Question: SRO 94 Given the following conditions:

• Unit 2 has been at 100% power for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Chemistry has just reported the following Reactor Coolant System samples:

• Chloride concentration is 2000 ppb.

• Fluoride concentration is 1900 ppb.

Which of the following actions should be performed per the Technical Requirements Manual and why?

Within six hours, place the Unit in...

A. MODE 2 because only the chloride concentration has exceeded the transient limit.

B. MODE 2 because the chloride and fluoride concentrations have exceeded the steady-state limit.

C. MODE 3 because only the fluoride concentration has exceeded the steady-state limit.

D. MODE 3 because the chloride and fluoride concentrations have exceeded the transient limit.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because the chloride concentration has exceeded the transient limits, however, the Unit must be placed in MODE 3 within six (6) hours.

B. Incorrect. Plausible because the steady-state chloride and fluoride limits have been exceeded, however, the TRM allows up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the parameters to within specification.

C. Incorrect. Plausible because the steady-state fluoride limit has been exceeded, however, the TRM allows up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the parameter to within specification.

D. Correct. Unit must be placed in MODE 3 within six (6) hours and be in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> because the chloride and fluoride concentrations have exceeded the transient limit.

Page 97 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) Technical Requirement Table 13.4.33-1 Attached w/ Revision # See Technical Requirement TR LCO 13.4.33 Comments / Reference STA-609, Attachment 8.A Proposed references to be provided during examination: None Learning Objective: APPLY the administrative requirements of Primary Chemistry Control including Technical Specifications, TRM and ODCM.

Question Source: Bank # GFE.PC1.OB04.007 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1, 2 Comments /

Reference:

From Technical Requirement Table 13.4.33-1 Revision # 56 Page 98 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Requirement TR LCO 13.4.33 Revision # 56 Page 99 of 129 CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From STA-609, Attachment 8.A Revision # 11 Page 100 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 1 K/A # G 2.1.45 Importance Rating 4.3 Conduct of Operations: Ability to identify and interpret diverse indications to validate the response of another indication.

Proposed Question: SRO 95 Given the following conditions:

• Unit 1 is at 100% power

• The following annunciators are in alarm:

• 1-ALB-8A, Window 2.7 - MSL 2 1 OF 3 PRESS LO.

• 1-ALB-8A, Window 2.8 - SG 2 STM & FW FLO MISMATCH.

• 1-ALB-8A, Window 2.12 - SG 2 LVL DEV.

• Plant indications are as follows:

• 1-FI-522A, SG 2 STM FLO, is 3.8x106 lbm/hr and steady.

• 1-FI-523A, SG 2 STM FLO, is 0 lbm/hr and stable.

• 1-PI-524A, MSL 2 PRESS CHAN I, is 1000 psig and stable.

• 1-PI-525A, MSL 2 PRESS CHAN II, is 0 psig and stable.

• 1-LT-529A, SG 2 LVL (NR) CHAN I, is 64% and lowering.

• 1-FI-520A, SG 2 FW FLO, is 1.5x106 lbm/hr and stable.

Which of the following identifies the failure and what procedure entry should be taken to mitigate the situation?

A. A Steam Flow instrument has failed.

Enter ABN-707, Steam Flow Instrument Malfunction.

B. A Steam Line Pressure instrument has failed.

Enter ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st Stage Pressure, And Feed Header Pressure Instrument Malfunction.

C. A Feedwater Flow instrument has failed.

Enter ABN-708, Feedwater Flow Instrument Malfunction.

D. A Steam Generator Level instrument has failed.

Enter ABN-710, Steam Generator Level Instrument Malfunction.

Proposed Answer: B Page 101 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because listed indications would seem to verify that a Steam Flow Instrument has failed, however, the failure of a Steam Line Pressure Instrument will affect the associated Steam Flow Pressure Compensation and provide the indications listed.

B. Correct. Given the indications listed this is the correct instrument failure and required procedure entry.

C. Incorrect. Plausible because there is a Steam Flow/Feed Flow mismatch, however, it is the Steam Pressure Instrument that has failed.

D. Incorrect. Plausible because Steam Generator level is lowering, however, it is due to the system response of a failed Steam Line Pressure Instrument.

Technical Reference(s) ABN-709, Steps 2.1 & 2.2 Attached w/ Revision # See ABN-708, Steps 2.1 & 2.2 Comments / Reference ABN-707, Steps 2.1 & 2.2 ABN-710, Steps 2.1 & 2.2 IPO-001A, Attachment 4 Proposed references to be provided during examination: None Learning Objective: EXPLAIN the instrumentation and controls of the Main Steam System and PREDICT the system response.

Question Source: Bank # SYS.MR1.OB04.001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 102 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-709, Step 2.1 Revision # 8 Page 103 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-709, Step 2.2 Revision # 8 Page 104 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-708, Steps 2.1 & 2.2 Revision # 6 Page 105 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-707, Step 2.1 Revision # 6 Page 106 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-707, Step 2.2 Revision # 6 Page 107 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-710, Step 2.1 Revision # 10 Comments /

Reference:

From ABN-710, Step 2.2 Revision # 10 Page 108 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From IPO-001A, Attachment 4 Revision # 21 Page 109 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.40 Importance Rating 4.7 Equipment Control: Ability to apply Technical Specifications for a system.

Proposed Question: SRO 96 Given the following conditions:

• The only OPERABLE Hydrogen Recombiner X-01 is in service for Unit 1 Reactor Coolant System degasification.

• Hydrogen feed concentration is 5% and the Oxygen feed is 2%.

• The Outlet (Product) Oxygen Analyzer has failed.

What are the required actions for this failure?

A. Immediately suspend Waste Gas Holdup System operations or analyze grab samples every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and maintain Oxygen less than 1%.

Restore the channel to OPERABLE status within 30 days.

B. Immediately suspend Oxygen Supply and Waste Gas addition to the Recombiner.

Restore the Channel to OPERABLE status within 60 days.

C. No impact on Recombiner operations.

Restore the Channel to OPERABLE status within 30 days.

D. Immediately reduce Hydrogen Feed Concentration to less than 4%.

Restore the Channel to OPERABLE status within 60 days.

Proposed Answer: A Explanation:

A. Correct. These are the actions per Technical Requirements TR LCO 13.10.31 Action D.1 and D.2.

B. Incorrect. Plausible because it could be thought that without indication of Oxygen on the outlet that all Recombiner gas additions should stop, however, TR LCO 13.10.31 Action D.1 and D.2 require either securing Waste Gas Holdup System Operations or performance of grab samples with tight Oxygen controls and the channel must be restored within 30 days.

C. Incorrect. Plausible because it could be thought that loss of a single channel would not require an action, however, TR LCO 13.10.31 Action D.1 and D.2 require either securing Waste Gas Holdup System Operations or performance of grab samples with tight Oxygen controls.

D. Incorrect. Plausible because it could be thought that reducing hydrogen below the 4% threshold would eliminate the concern for lack of Oxygen indication on the outlet, however, TR LCO 13.10.31 Action D.1 and D.2 require either securing Waste Gas Holdup System Operations or performance of grab samples with tight Oxygen controls.

Page 110 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Technical Reference(s) Technical Requirement TR LCO 13.10.31.B Attached w/ Revision # See Technical Requirement TR LCO 13.10.31.D Comments / Reference Proposed references to be provided during examination: TRM 13.10.31 Learning Objective: APPLY the administrative requirements of the Gaseous Waste system including Technical Specifications, TRM and ODCM.

Question Source: Bank # SYS.RWS.OB05.005 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 1 Page 111 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Requirements TR LCO 13.10.31.B Revision # 65 Page 112 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Requirements TR LCO 13.10.31.D Revision # 65 Page 113 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 2 K/A # G 2.2.18 Importance Rating 3.9 Equipment Control: Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

Proposed Question: SRO 97 Given the following conditions:

• Unit 1 is in Mid-Loop Operation with vessel level at 48" above core plate.

• Reactor Coolant System temperature is 106°F.

Which of the following describes how these plant conditions impact the ability to perform work on Containment penetrations?

A. NO work may be performed which impairs any penetrations.

B. There are NO limitations or restrictions placed on the number of impaired penetrations.

C. Work may impair up to 10 penetrations only if pre-approved temporary seals available at the work site.

D. Work may impair an unlimited number of penetrations with pre-approved temporary seals available at the work site.

Proposed Answer: C Explanation:

A. Incorrect. Plausible as this would be the most conservative approach for outage risk management, however, the administrative guidance allows up to 10 penetrations to be impaired with pre-approved temporary seals.

B. Incorrect. Plausible because as long as Containment Closure can be obtained, no limit should be required, however, adequate administrative control for Containment Closure is not provided.

C. Correct. In accordance with IPO-010A.

D. Incorrect. Plausible because as long as Containment Closure can be obtained, no limit should be required, however, administrative controls have determined that a maximum of 10 impaired penetrations is allowed.

Technical Reference(s) IPO-010A, Step 3.2.12 Attached w/ Revision # See IPO-101A, Attachment 1 Comments / Reference Proposed references to be provided during examination: None Page 114 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Learning Objective: DISCUSS the Precautions, Limitations and key Attachments of IPO-010, RCS Reduced Inventory Operations.

Question Source: Bank # IPO.010.OB04.004 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments /

Reference:

From IPO-101A, Step 3.2.12 Revision # 18 Page 115 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From IPO-101A, Attachment 1 Revision # 18 Page 116 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.5 Importance Rating 2.9 Radiation Control: Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: SRO 98 Page 117 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Given the following conditions:

• Unit 1 has experienced a manual Reactor Trip and Safety Injection initiation based on lowering Reactor Coolant System (RCS) pressure and lowering Pressurizer level.

• EOP-0.0A, Reactor Trip and Safety Injection is in progress.

• The following parameters are noted during diagnostics:

• All three Pressurizer Safety Valves are CLOSED.

• Both Pressurizer Spray Valves are CLOSED.

• Both Pressurizer PORVs are CLOSED.

• RCS subcooling is 15°F and stable.

• RCS pressure is 1530 psig and stable.

• All Reactor Coolant Pumps have been STOPPED.

• All Steam Generator Pressures are 1080 psig and slowly rising.

• COG-182, Condenser Off-Gas Radiation Monitor, is Normal.

• MSL-178 through MSL-181, Main Steam Line Radiation Monitors, are GREEN and stable.

• SGS-164, SG Blowdown Sample Radiation Monitor, is GREEN and stable.

• All Steam Generator levels are 52% and slowly rising under operator control.

• Containment Pressure is 0.2 psig and stable.

• Containment Recirc Sump level is 808 and stable.

• Containment Radiation on Grid 4 is Normal.

• The following Area Radiation Monitors on Grid 4 indicate RED and rising.

• 1-RE-6259A, PENET AREA RM 77S.

• 1-RE-6259B, PENET AREA RM 77N.

• X-RE-5570A, S WRGM EFFLUENT.

Which of the following indicates the proper action for optimal recovery?

A. Continue with EOP-0.0A, Reactor Trip or Safety Injection, as no procedure transitions have been identified.

B. Transition to EOS-1.1A, Safety Injection Termination, as ECCS flow is NOT required.

C. Transition to ECA-1.2A, LOCA Outside Containment, based on probable leakage into the Safeguards Building.

D. Transition to EOS-0.0, Rediagnosis, to identify what indication was misinterpreted.

Proposed Answer: C Page 118 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Incorrect. Plausible because it could be evaluated that no procedural transitions have yet been identified, however, indications are correct for a transition to ECA-1.2A.

B. Incorrect. Plausible because with none of the major accident (SGTR, Faulted SG or LOCA) transitions identified, it could be interpreted that SI Termination should take place, however, subcooling would not allow SI Termination and a transition to ECA-1.2A is correct.

C. Correct. Interpretation of the readings on Grid 4 Radiation Monitors indicates that a transition to ECA-1.2A is required.

D. Incorrect. Plausible because the major diagnostic steps of EOP-0.0A have been completed, however, transition from EOP-0.0A to EOS-0.0A is not proper when a transition has not been identified.

Technical Reference(s) EOP-0.0A, Step 19 Attached w/ Revision # See ECA-1.2A, Entry Conditions Comments / Reference EOS-0.0A, Entry Conditions EOS-1.1A, Attachment 1.A Proposed references to be provided during examination: None Learning Objective: ANALYZE the diagnostic steps of EOP-0.0, Reactor Trip or Safety Injection.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 119 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOP-0.0A, Step 19 Revision # 8 Page 120 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ECA-1.2A, Entry Conditions Revision # 8 Page 121 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From EOS-0.0A, Entry Conditions Revision # 8 Comments /

Reference:

From EOS-1.1A, Attachment 1.A Revision # 8 Page 122 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 3 K/A # G 2.3.14 Importance Rating 3.8 Radiation Control: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Proposed Question: SRO 99 Which of the following conditions may the Shift Manager waive the requirement for an Independent Verification or Concurrent Verification?

A. Radiation exposure greater than 5 mrem is likely.

B. Areas of radiation dose rates in excess of 10 mrem/hr.

C. While performing an alignment required by a System Operating Procedure.

D. On component located inside Unit 1 or Unit 2 Containment during MODE 2.

Proposed Answer: D Explanation:

A. Incorrect. Plausible because limitations exist for radiation exposure, however, the limit outlined in STA-694 is greater than 10 mrem.

B. Incorrect. Plausible because limitations exist for radiation dose rates, however, the limit outlined in STA-694 is greater than 100 mrem/hr.

C. Incorrect. Plausible because Independent Verification and Concurrent Verification activities are not required during performance of or in response to abnormal operating conditions, however, this waiver is restricted to Emergency Operating Procedures ERGs), Abnormal Condition Procedures (ABNs), Or Alarm Response Procedures (ALMs).

D. Correct. Independent Verification and Concurrent Verification are not required inside Containment during MODES 1, 2, 3, or 4.

Technical Reference(s) STA-694, Steps 6.5.1 & 6.5.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: None Learning Objective: INTERPRET and ENSURE compliance with plant administrative and operational procedures, guidelines, and policies.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Page 123 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 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 1, 4 Comments /

Reference:

From STA-694, Steps 6.5.1 & 6.5.2 Revision # 5 Page 124 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Category # 4 K/A # G 2.4.32 Importance Rating 4.6 Emergency Procedures / Plan: Knowledge of operator response to loss of all annunciators.

Proposed Question: SRO 100 Given the following conditions:

• Unit 2 is in a steady-state full power condition.

• ABN-740B, Control Room Annunciators System and Status Light Malfunction, Section 2.0, Loss of All Control Room Annunciators, was just entered.

Which of the following Technical Specifications / Technical Requirements and associated frequency must be addressed during this event?

Technical Specifications / Technical Requirements Limiting Condition for Operation A. Technical Requirement LCO 13.2.32, Axial Flux Difference (AFD), monitor and log AFD within 30 minutes and hourly thereafter.

B. Technical Requirement LCO 13.2.32, Axial Flux Difference (AFD), reduce Reactor power to less than 50% within 30 minutes.

C. Technical Specification LCO 3.4.15, RCS Leakage Detection Instrumentation, perform OPT-303, Reactor Coolant System Water Inventory, every shift.

D. Technical Specification LCO 3.4.15, RCS Leakage Detection Instrumentation, perform OPT-303, Reactor Coolant System Water Inventory every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Proposed Answer: A Page 125 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Explanation:

A. Correct. Technical Requirement LCO 13.2.32, Axial Flux Difference requires monitoring and logging AFD within 30 minutes and hourly thereafter when the AFD alarm is out of service.

B. Incorrect. Plausible because Technical Specification LCO 3.2.3 Axial Flux Difference (AFD)

Relaxed Axial Offset Control (RAOC) Methodology not being met requires lowering Reactor power to less than 50% within 30 minutes, however, the AFD alarm is what is affected in this condition which requires monitoring and logging AFD within 30 minutes and hourly thereafter.

C. Incorrect. Plausible because surveillance for Technical Specification LCO 3.4.15, RCS Leakage Detection Instrumentation, must be performed, however, it must be completed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in this condition. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> frequency is the normal surveillance frequency for Technical Specification LCO 3.4.15.

D. Incorrect. Plausible because surveillance for Technical Specification LCO 3.4.15, RCS Leakage Detection Instrumentation, must be performed, however, it must be completed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in this condition. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> frequency is the normal surveillance frequency for Technical Specification LCO 3.4.15.

Technical Reference(s) ABN-740B, Attachment 1 Attached w/ Revision # See Technical Specification LCO 3.2.3 Comments / Reference Technical Specification LCO 3.4.15 Proposed references to be provided during examination: None Learning Objective: LIST and DESCRIBE the Technical Specifications (i.e. LCOs, action statements and conditional surveillance requirements of one hour and less, if applicable) for the Axial Flux Difference.

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1, 2 Page 126 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From ABN-740B, Attachment 1 Revision # 1 Page 127 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.2.3 Amendment # 150 Page 128 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx

ES-401 CPNPP NRC 2012 SRO Written Exam Worksheet Form ES-401-5 Comments /

Reference:

From Technical Specification LCO 3.4.15 Amendment # 150 Page 129 of 129CPNPP NRC 2012 SRO Written Exam Worksheet 76 to 100 Rev f.docx