ML12205A412

CP-2012-06 Final Operating Test

ML12205A412
Person / Time
Site:	Comanche Peak
Issue date:	06/11/2012
From:	NRC Region 4
To:	Luminant Generation Co
References
Download: ML12205A412 (339)

Text

Administrative Topics Outline Facility: CPNPP Units 1 and 2 Date of Examination: 06/11/12 Examination Level RO Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9).

Conduct of Operations M, R (RA1)

JPM: Determine Loss of Residual Heat Removal Time Limitations (RO1413).

2.1.23 Ability to perform specific system and integrated plant procedures during all modes Conduct of Operations of plant operation (4.3).

M, R (RA2)

JPM: Perform a Calorimetric Heat Balance (RO1804).

2.2.12 Knowledge of surveillance procedures (3.7).

Equipment Control M, R (RA3) JPM: Perform Control Room Air Conditioning System Surveillance Data (RO4108).

2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling Radiation Control responsibilities, access to locked high M, R (RA4) radiation areas, aligning filters, etc. (3.4).

JPM: Determine Containment Stay Time Requirements (RWT029).

Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected) 05r.CPNPP NRC 2012 ES-301-1 RO Admin JPM Outline Rev g.doc

Administrative Topics Outline Task Summary RA1 The applicant will determine the Time to Boil and Time to Achieve Containment Closure during a Loss of Residual Heat Removal System per ABN-104, RHR System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure. Critical steps include determining the time for each evolution. This is a modified bank JPM.

RA2 The applicant will perform a calorimetric heat balance per OPT-309, Unit Calorimetric. Critical steps include completing OPT-309-2, Calorimetric Data Reduction Worksheet, and determining the thermal output of the Reactor. This is a modified bank JPM.

RA3 The applicant will record and evaluate the data obtained in a surveillance of the Control Room Air Conditioning System per OPT-116, Control Room Air Conditioning System, and determine whether Acceptance Criteria are met. Critical steps include recording data, performing calculations, and applying Acceptance Criteria. This is a modified bank JPM.

RA4 The applicant will calculate maximum allowable stay time within Containment per STA-620, Containment Entry, STA-655, Exposure Monitoring Program, STA-657, ALARA Job Planning/Debriefing, STA-660, Control of High Radiation Areas, and STA-674, Heat Stress Management. Critical steps include calculating allowable gamma dose, neutron dose, and Heat Stress Stay Time. This is a modified bank JPM.

05r.CPNPP NRC 2012 ES-301-1 RO Admin JPM Outline Rev g.doc

Administrative Topics Outline Facility: CPNPP Units 1 and 2 Date of Examination: 06/11/12 Examination Level SRO Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.2 Knowledge of operator responsibilities during all modes of plant operation (4.4).

Conduct of Operations N, R (SA1)

JPM: Identify Reduced Inventory Contingencies (SO1002).

2.1.23 Ability to perform specific system and integrated plant procedures during all modes Conduct of Operations of plant operation (4.4).

M, R (SA2)

JPM: Perform a Calorimetric Heat Balance and Evaluate Technical Specifications (SO1058).

2.2.12 Knowledge of surveillance procedures (4.1).

Equipment Control M, R JPM: Perform Control Room Air Conditioning (SA3)

System Surveillance Data and Evaluate Technical Specifications (SO1202).

2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling Radiation Control responsibilities, access to locked high M, R radiation areas, aligning filters, etc. (3.8).

(SA4)

JPM: Determine Containment Stay Time Requirements and Event Reportability (SO1005).

2.4.41 Knowledge of the emergency action level Emergency Plan thresholds and classifications. (4.6)

N, R (SA5)

JPM: Classify an Emergency Plan Event (SO1136).

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected) 05s.CPNPP NRC 2012 ES-301-1 SRO Admin JPM Outline Rev g.doc

Administrative Topics Outline Task Summary SA1 The applicant will identify the Reactor Coolant System Reduced Inventory contingencies regarding the Containment Equipment Hatch being removed per IPO-010A, Reactor Coolant System Reduced Inventory Operations, Attachment 1, Shiftly Checklist. Critical steps include identifing Reduced Inventory contingencies when it is determined that the standby RHR Pump is not available.

This is a new JPM.

SA2 The applicant will perform a Calorimetric Heat Balance per OPT-309, Unit Calorimetric. Critical steps include completing OPT-309-2, Calorimetric Data Reduction Worksheet, determining the thermal output of the Reactor and evaluating Technical Specification Surveillance Requirements. This is a modified bank JPM.

SA3 The applicant will record and evaluate the data obtained in a surveillance of the Control Room Air Conditioning System per OPT-116, Control Room Air Conditioning System, and determine whether Acceptance Criteria are met. Critical steps include recording the data, performing calculations, applying Acceptance Criteria, then identifying any impacted Technical Specification Limiting Condition for Operation, Required Action, and Completion Time. This is a modified bank JPM.

SA4 The applicant will calculate maximum allowable stay time within Containment per STA-501, Nonroutine Reporting, STA-620, Containment Entry, STA-655, Exposure Monitoring Program, STA-657, ALARA Job Planning/Debriefing, STA-660, Control of High Radiation Areas, and STA-674, Heat Stress Management. Critical steps include calculating allowable gamma dose, neutron dose, Heat Stress Stay Time, and the oral and written Reporting Requirements for a contaminated injured person. This is a modified bank JPM.

SA5 The applicant will classify an Emergency Plan event per EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

Critical steps include determining the Event Category and Event Classification using the Hot and Cold Emergency Action Level Classification Charts. This is a new JPM.

05s.CPNPP NRC 2012 ES-301-1 SRO Admin JPM Outline Rev g.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA1 Task # RO1413 K/A # 2.1.25 3.9 / 4.2

Title:

Determine Loss of RHR Time Limitations Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 2 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 100°F.

The Reactor was shut down 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> ago.

A Loss of Residual Heat Removal cooling has just occurred.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

CALCULATE per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation. ________

DETERMINE most limiting Containment Closure Time. ________

Task Standard: Utilizing ABN-104, determined Time to Saturation and most limiting Containment Closure Time following a Loss of the Residual Heat Removal System.

Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 8-10.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 4 CPNPP NRC 2012 JPM RA1 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ABN-104, Residual Heat Removal Malfunction.

Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory.

Attachment 19, Available Time for Containment Closure.

PROVIDE the examinee a Straightedge or ruler.

Page 2 of 4 CPNPP NRC 2012 JPM RA1 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-104, Attachment 5.

Perform Step: 1 Determine Time to Saturation:

Find Time to Saturation from Attachment 5, Page 1.

Standard: REFERRED to Page 1 of Attachment 5 and PLOTTED the intersection of Time After Shutdown (520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />) and Initial Temp (100ºF) and DETERMINED: TIME TO SATURATION = 27 +/- 1 minutes.

Comment: SAT UNSAT Examiner Note: The following step is from ABN-104, Attachment 19.

Perform Step: 2 Determine most limiting Containment Closure time:

Find Containment Closure Time from Attachment 19:

Radiological Environment Limiting Curve.

Thermal Environment Limiting Curve.

Standard: REFERRED to Attachment 19 and PLOTTED the intersection of Time After Shutdown (520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />) and DETERMINED: Radiological Environment Limiting Containment Closure Time is most limiting =

100 +/- 3 minutes.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 3 of 4 CPNPP NRC 2012 JPM RA1 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 2 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 100°F.

The Reactor was shut down 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> ago.

A Loss of Residual Heat Removal cooling has just occurred.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

CALCULATE per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation. ________

DETERMINE most limiting Containment Closure Time. ________

Page 4 of 4 CPNPP NRC 2012 JPM RA1 Rev h

CPNPP NRC 2012 JPM RA1 Answer Key Rev h CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 58 OF 102 ATTACHMENT 5 PAGE 1 OF 2

[C] TIME TO SATURATION FOR LOSS OF ALL RHR WITH THE RCS AT REDUCED INVENTORY (assuming no makeup)

Attachment 5 CPNPP NRC 2012 JPM RA1 Answer Key Rev h Page 1 of 2

CPNPP NRC 2012 JPM RA1 Answer Key Rev h CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 99 OF 102 ATTACHMENT 19 PAGE 1 OF 1

[C] AVAILABLE TIME FOR CONTAINMENT CLOSURE Attachment 19 CPNPP NRC 2012 JPM RA1 Answer Key Rev h Page 2 of 2

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA2 Task # RO1804 K/A # 2.1.23 4.3 / 4.4

Title:

Perform a Calorimetric Heat Balance Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

COMPLETE through Step 8.2.2.11.

Task Standard: Utilizing OPT-309, OPT-309-2, and OPT-309-11 calculated a Unit 1 calorimetric.

Required Materials: OPT-309, Unit Calorimetric, Rev 14.

OPT-309-2, Calorimetric Data Reduction Worksheet, Rev 8.

OPT-309-11, Unit 1 Calorimetric Data Sheet, Rev 6.

Validation Time: 20 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 CPNPP NRC 2012 JPM RA2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-309, Unit Calorimetric, completed through Step 8.2.2.8.

OPT-309-2, Calorimetric Data Reduction Worksheet, completed through Step 8.2.2.8.

OPT-309-11, Unit 1 Calorimetric Data Sheet with data entered.

Steam Tables.

Calculator.

Page 2 of 5 CPNPP NRC 2012 JPM RA2 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-309, Section 8.2.

Perform Step: 1 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.A, & Enter corrected steam pressures given in column 5 of Step 8.2.2.9.B 8.2.2.5, in column 2.

Using Steam Tables obtain the steam enthalpies AND enter results in column 3.

Standard: CALCULATED Steam Generator Enthalpy Rise using corrected steam pressures (PSIA) then CALCULATED associated steam enthalpy values using Steam Tables and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 2 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.C, Enter feedwater enthalpy from one of the following sources:

8.2.2.9.C 2nd bullet, &

8.2.2.9.D IF Steam Generator Blowdown NOT isolated, THEN enter value given in column 2 of Step 8.2.2.8 into column 3, or Using Steam Tables obtain the enthalpy of the feedwater liquid AND enter result in column 4.

Subtract the value in column 4 from values in column 3 AND enter the results in column 5.

Standard: CALCULATED Feedwater Enthalpy using Steam Tables then SUBTRACTED value in column 4 from values in column 3 and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2012 JPM RA2 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Perform Steam Generator Heat Gain Calculation as follows:

8.2.2.10, 8.2.2.10.A, Enter the enthalpy rise for each Steam Generator given in column 8.2.2.10.B, 8.2.2.10.C, 5 of Step 8.2.2.9, into column 2.

& 8.2.2.10.D Calculate steam flow for each Steam Generator by using the formula given in the heading of column 3. Use data for Feedwater flow given in column 4 of Step 8.2.2.4 AND blowdown flow given in column 3 of Step 8.2.2.7. Enter results in column 3.

Multiply the entries in column 2 by entries in column 3, AND enter results in column 4.

Total the entries of column 4 and enter result at the base of this column.

Standard: CALCULATED Steam Generator Heat Gain; RECORDED enthalpy rise for each Steam Generator then RECORDED steam flow for each Steam Generator then MULTIPLIED the entries in column 2 by entries in column 3, and ENTERED results in column 4 then TOTALED the entries and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 4 Perform Percent Rated Thermal Power Calculation as follows:

8.2.2.11, 8.2.2.11.A, Enter the Steam Generator Heat Gain given in space at the base 8.2.2.11.B, 8.2.2.11.C, of column 4 from Step 8.2.2.10, in column 1.

& 8.2.2.11.D IF Steam Generator Blowdown NOT isolated, THEN enter the Blowdown Heat Loss given in column 3 of Step 8.2.2.8, in column 2.

Calculate Net Reactor Power by using the formula given in the heading of column 4 AND the data given in columns 1, 2 and 3.

Enter results in column 4.

Substitute values from column 4 and column 5 into the formula in the heading of column 6 AND calculate Percent Rated Thermal Power. Enter the result in column 6.

Standard: CALCULATED Percent Rated Thermal Power using Steam Generator Heat Gain then CALCULATED Net Reactor Power value then SUBSTITUTED values and CALCULATED Percent Rated Thermal Power and ENTERED data on OPT-309-2.

CALCULATED a Percent Rated Thermal Power of 94 +/- 1.0%.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP NRC 2012 JPM RA2 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

COMPLETE through Step 8.2.2.11.

Page 5 of 5 CPNPP NRC 2012 JPM RA2 Rev h

CPNPP NRC 2012 JPM RA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET Unit 1 Date Today 8.2.2.2 - Feedwater Average Temperature Parameter Average Value of Overall Data Sets Average

(°F) (°F)

S/G 1 Feedwater Temperature 440 S/G 2 Feedwater Temperature 440 440 S/G 3 Feedwater Temperature 440 S/G 4 Feedwater Temperature 440 8.2.2.3 Feedwater Average Pressure Parameter Average of Data Sets Corrected Pressure Overall Average (PSIG) (PSIG + 14.7 = PSIA) (PSIA)

S/G 1 Feedwater Pressure 1160 1175 S/G 2 Feedwater Pressure 1160 1175 1175 S/G 3 Feedwater Pressure 1160 1175 S/G 4 Feedwater Pressure 1160 1175 8.2.2.4 - Feedwater Flow Averages Parameter Average Value of Correction Factor Corrected Value (WF) Data Sets (CF) LB/HR x CF (LB/HR) (NOTE 1) (LB/HR)

S/G 1 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 2 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 3 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 4 Feedwater Flow 3.8xE6 1.0 3.8xE6 8.2.2.5 - Corrected Steam Generator Steam Pressure Averages Parameter Average of Corrected Pressure Pressure Drop Due to Corrected Overall Data Sets Line Loss (PSIA) Pressure Average (PSIG) (PSIG+14.7 = PSIA) (NOTE 2) (PSIA) (PSIA)

S/G 1 Steam Pressure 979.7 994.4 5.55 999.95 979.4 994.1 999.98 1000 S/G 2 Steam Pressure 5.88 S/G 3 Steam Pressure 978.4 993.1 7.04 1000.14 S/G 4 Steam Pressure 979.1 993.8 6.13 999.93 NOTE 1: Correction Factor is 1 when LEFM data is used. When other Feedwater Flow data is used, Correction Factor is from Attachment 10.1 using Feedwater Temperature for the associated SG calculated in Step 8.2.2.2 (Column 2).

NOTE 2: The steam line pressure drops are the same for both Units.

OPT-309-2 REV. 8 PAGE 1 OF 3 CPNPP NRC 2012 JPM RA2 Answer Key Rev h Page 1 of 3

CPNPP NRC 2012 JPM RA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.6 - Steam Generator Blowdown Average Values Parameter Average Value of Data Sets SG Blowdown Flow (GPM) 335 SG Blowdown Hx Out Temp (°F) 250 8.2.2.7 - Blowdown Flow Conversion Average Specific Blowdown Flow, Fbd Blowdown Volume, V Flow, F (GPM) FT3/lbm (LBM/HR) 335 0.0170 161967 8.2.2.8 - Blowdown Heat Loss Calculation Blowdown Enthalpy, Feedwater Enthalpy, Blowdown Heat Loss, Qbd (BTU/LBM) (BTU/LBM) (BTU/HR) 542.6 419.9 19873351 8.2.2.9 - S/G Enthalpy Rise Calculation SG No. Corrected Steam Feedwater Enthalpy Steam Enthalpy, Enthalpy, Rise Pressure (PSIA)

(BTU/LBM) (BTU/LBM) (BTU/LBM) 1 1000 1192.9 773 2 1000 1192.9 773 419.9 3 1000 1192.9 773 4 1000 1192.9 773 OPT-309-2 REV. 8 PAGE 2 OF 3 CPNPP NRC 2012 JPM RA2 Answer Key Rev h Page 2 of 3

CPNPP NRC 2012 JPM RA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.10 - SG Heat Gain Calculation SG No. Enthalpy Rise, Steam Flow S/G Heat Gain, (BTU/LBM) (LBM/HR) (BTU/HR) 1 773 3,759,508 2,906,099,877 2 773 3,759,508 2,906,099,877 3 773 3,759,508 2,906,099,877 4 773 3,759,508 2,906,099,877 1.1624xE10 8.2.2.11 - Percent Rated Thermal Power Calculation SG Blowdown Non-Reactor Net Reactor Rated Percent Rated Heat Heat Loss, Heat Gains, Power, Thermal Thermal Power Gain Power, (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (%)

1.1624xE10 19873351 5.4 X 107 1.1590xE10 1.2328 x10 10 94.02 Comments:

Performed By: Date:

Reviewed By: Date:

OPT-309-2 REV. 8 PAGE 3 OF 3 CPNPP NRC 2012 JPM RA2 Answer Key Rev h Page 3 of 3

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA3 Task # RO4108 K/A # 2.2.12 3.7 / 4.1

Title:

Perform Control Room Air Conditioning System Surveillance Data Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 33%

unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 140 psig and is operating 50%

unloaded.

X-TR-4123 reads 105°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

Task Standard: Utilizing OPT-116, recorded data on OPT-116-1, plotted air conditioning unit cooling capacity, and determined Acceptance Criteria met.

Required Materials: OPT-116, CR AC System, Rev. 4.

OPT-116-1, CR AC System Data Sheet, Rev. 4.

Validation Time: 25 minutes Completion Time: ________ minutes Page 1 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-116, CR AC System.

INITIAL and N/A as appropriate up to Step 8.3.

OPT-116-1, CR AC System Data Sheet.

INITIAL and N/A as appropriate up to Step 8.3 Page 3 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-116, Section 8.0.

Perform Step: 1 RECORD the following:

st 8.3 & 1 bullet X-TR-4123, outside temperature (10M PRI) (X-CV-05)

Standard: RECORDED X-TR-4123, outside temperature of 105°F on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 2 RECORD the following:

nd 8.3 & 2 bullet X-TI-5933 ECB EXH TEMP (X-CV-01)

Standard: RECORDED X-TI-5933, ECB EXH TEMP of 72°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 3 RECORD the following:

8.3 & 3rd bullet X-TI-5734, AB EXH TEMP EL-852' 6" (X-CV-03)

Standard: RECORDED X-TI-5734, AB EXH TEMP of 73°F on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 4 RECORD the following:

8.3 & 4th bullet X-TI-5735, AB EXH TEMP EL-831' 6" (X-CV-03)

Standard: RECORDED X-TI-5735, AB EXH TEMP of 73°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units.

CR A/C Unit 03 (X-PI-3585A)

Standard: RECORDED CR A/C Unit 03 (X-PI-3585A) pressure of 150 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Perform Step: 6 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units CR A/C Unit 04 (X-PI-3586A)

Standard: RECORDED CR A/C Unit 04 (X-PI-3586A) pressure of 140 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Examiner Cue: If asked about Independent Verification (IV), REPORT to proceed as if the IV has been performed.

Perform Step: 7 VERIFY the above readings are within the specified limits. If any of the 8.4 above readings are NOT within the specified limits, this test should be terminated and restarted when the above conditions can be met.

Standard: VERIFIED that all readings are within limits and INITIALED.

Comment: SAT UNSAT Perform Step: 8 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 03 Standard: RECORDED A/C UNIT 03 % unloaded of 33% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 04 Standard: RECORDED A/C UNIT 04 % unloaded of 50% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 10 CALCULATE the average % unloaded by adding the % unloaded from 8.6 the operating compressors and dividing by 2.

Standard: ADDED 33% and 50% and DIVIDED by 2 to yield an average of 41.5%;

RECORDED on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 11 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: PLOTTED the intersection point for 105 degrees and 41.5% on Figure 1 and COMPARED to the acceptability curve.

Comment: SAT UNSAT Perform Step: 12 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: VERIFIED plotted point is ABOVE the curve on Figure 1 and CIRCLED ABOVE then SAT on OPT-116-1 and INITIALED.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2012 JPM RA3 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 33% unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 140 psig and is operating 50% unloaded.

X-TR-4123 reads 105°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

Page 7 of 7 CPNPP NRC 2012 JPM RA3 Rev h

CPNPP NRC 2012 JPM RA3 Answer Key Rev h CR A/C SYSTEM DATA SHEET REQUIRED TEST STEP OBSERVED CONDITIONS INITIALS 6.0 PREREQUISITES MET N/A N/A RB AND TIME/DATE Today @ 0800 N/A RB 8.1 CR A/C UNITS BEING TESTED Units 03 & 04 N/A RB Today @ 0900 $30 MIN RB 8.2 TIME AND DATE PAST STEP 6.0 8.3 RECORD THE FOLLOWING:

! X-TR-4123 OUTSIDE TEMPERATURE 105 F N/A RB

! X-TI-5933 72 F $60°F RB

! 73 F RB X-TI-5734 $60°F

! 73 F RB X-TI-5735 $60°F

! COMPRESSOR DISCHARGE PRESSURES (N/A for shutdown units)

CR A/C UNIT 01 (X-PI-3583A) N/A <170 PSIG N/A CR A/C UNIT 02 (X-PI-3584A)

N/A <170 PSIG N/A CR A/C UNIT 03 150 psig (X-PI-3585A) <170 PSIG RB CR A/C UNIT 04 (X-PI-3586A) 140 psig <170 PSIG RB 8.4 ALL ABOVE REQUIRED TEST CONDITIONS MET N/A NOTE 1 RB NOTE 1: If test conditions are not met, terminate test at this point. Test shall be restarted when conditions can be met.

CONTINUOUS USE OPT-116-1 PAGE 1 OF 4 R-4 CPNPP NRC 2012 JPM RA3 Answer Key Rev h Page 1 of 4

CPNPP NRC 2012 JPM RA3 Answer Key Rev h CR A/C SYSTEM DATA SHEET STEP OBSERVED INITIALS 8.5 A/C UNIT % UNLOADED (N/A for shutdown units)

A/C UNIT 01 N/A N/A A/C UNIT 02 N/A N/A A/C UNIT 03 33 RB A/C UNIT 04 50 RB 8.6 CALCULATE AVERAGE A/C UNIT NO. 03 A/C UNIT NO. 04 RB

% UNLOADED 33 + % UNLOADED 50 = 41.5 2 TRAIN AVERAGE N/A COMPRESSOR COOLING VERIFIED CAPACITY AVAILABILITY 8.7 COMPARE OUTSIDE TEMP (STEP 8.3) AND AVERAGE OPERATION COMPRESSOR COOLING CAPACITY AVAILABILITY ABOVE/BELOW (STEP 8.6) TO CURVE (FIGURE 1) CURVE RB ACCEPTANCE CRITERIA SAT IF OPERATION IS ABOVE CURVE SAT/UNSAT RB CONTINUOUS USE OPT-116-1 PAGE 2 OF 4 R-4 CPNPP NRC 2012 JPM RA3 Answer Key Rev h Page 2 of 4

CPNPP NRC 2012 JPM RA3 Answer Key Rev h CR A/C SYSTEM DATA SHEET FIGURE 1 OUTSIDE PERCENT UNLOADED TEMPERATURE 16.7 110 24.3 100 32.0 90 39.6 80 47.2 70 51.7 60 54.1 50 56.5 40 58.9 30 61.3 20 CONTROL ROOM HVAC MINIMUM REQUIRED AVAILABILITY THE UNLOADED COMBINED AVERAGE OF THE TWO 50% CONTROL ROOM HVAC UNITS MUST BE ABOVE THE CURVE REPRESENTED BELOW:

COOLING CAPACITY AVAILABLE (%)

70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 OUTSIDE TEMPERATURE (F)

CONTINUOUS USE OPT-116-1 PAGE 3 OF 4 R-4 CPNPP NRC 2012 JPM RA3 Answer Key Rev h Page 3 of 4

CPNPP NRC 2012 JPM RA3 Answer Key Rev h CR A/C SYSTEM DATA SHEET COMMENTS/DISCREPANCIES:

CORRECTIVE ACTIONS:

PERFORMED BY: DATE:

SIGNATURE REVIEWED BY: DATE:

OPERATIONS MANAGEMENT CONTINUOUS USE OPT-116-1 PAGE 4 OF 4 R-4 CPNPP NRC 2012 JPM RA3 Answer Key Rev h Page 4 of 4

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA4 Task # RWT029 K/A # 2.3.13 3.4 / 3.8

Title:

Determine Containment Stay Time Requirements Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Containment entry is about to be performed by a 4 member team.

The estimated gamma dose rate is 75 mrem/hr.

The estimated neutron dose rate is 10 mrem/hr.

Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

The Heat Stress Action Time has been determined to be 40 minutes.

Initiating Cue: The Work Control Supervisor directs you to PERFORM the following:

CALCULATE the following:

Gamma dose stay time per team. _____ minutes.

Neutron dose stay time per team. _____ minutes.

Heat Stress Stay Time _____ minutes.

DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

Limiting Containment entry time: _____ minutes.

Task Standard: Utilizing STA-620/655/657/660/674, calculated gamma and neutron dose stay times for the team, Heat Stress Stay Time, and determined limiting Containment entry time.

Required Materials: STA-620, Containment Entry, Rev. 13.

STA-655, Exposure Monitoring Program, Rev. 20.

STA-657, ALARA Job Planning/Debriefing, Rev. 14.

STA-660, Control of High Radiation Areas, Rev. 15.

STA-674, Heat Stress Management, Rev. 8.

Page 1 of 5 CPNPP NRC 2012 JPM RA4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 5 CPNPP NRC 2012 JPM RA4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

MAKE the following available in the classroom:

STA-620, Containment Entry.

STA-655, Exposure Monitoring Program.

STA-657, ALARA Job Planning/Debriefing.

STA-660, Control of High Radiation Areas.

STA-674, Heat Stress Management ENSURE examinee has a calculator.

Page 3 of 5 CPNPP NRC 2012 JPM RA4 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Provide the examinee with copy of JPM Cue Sheet #1.

Perform Step: 1 Calculate gamma dose stay time per team.

Standard: CALCULATED the following:

75 mrem/hr gamma x 4 persons = 300 mrem/hr from gamma.

500 person-REM allowed 100 minute gamma Stay Time Comment: SAT UNSAT Perform Step: 2 Calculate neutron dose stay time per team.

Standard: CALCULATED the following:

10 mrem/hr neutron x 4 persons = 40 mrem/hr from neutron.

50 person-REM allowed 75 minute neutron Stay Time Comment: SAT UNSAT Examiner Note: The following step is from STA-674, Section 4.0, Definitions.

Perform Step: 3 Calculate Heat Stress Stay Time.

Standard: CALCULATED the following:

Heat Stress Action Time is 40 minutes per the Initial Conditions.

Heat Stress Stay Time is 2 x 40 minutes = 80 minutes Comment: SAT UNSAT Perform Step: 4 Determine limiting Containment entry time.

Standard: DETERMINED the limiting Containment entry time is 75 minutes based on Neutron Dose Stay Time.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP NRC 2012 JPM RA4 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Containment entry is about to be performed by a 4 member team.

The estimated gamma dose rate is 75 mrem/hr.

The estimated neutron dose rate is 10 mrem/hr.

Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

The Heat Stress Action Time has been determined to be 40 minutes.

INITIATING CUE: The Work Control Supervisor directs you to PERFORM the following:

CALCULATE the following:

Gamma dose stay time per team. _____ minutes.

Neutron dose stay time per team. _____ minutes.

Heat Stress Stay Time _____ minutes.

DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

Limiting Containment entry time: _____ minutes.

Page 5 of 5 CPNPP NRC 2012 JPM RA4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task # SO1002 K/A # 2.1.2 4.1 / 4.4

Title:

Identify Reduced Inventory Contingencies Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

Reactor Coolant System Loops are NOT filled.

The Containment Equipment Hatch is removed.

IPO-010A, Reactor Coolant System Reduced Inventory Operations, Attachment 1, Shiftly Checklist is complete.

Safeguards Bus 1EA1 was lost on an 86-1 Lockout Relay actuation.

Train B Residual Heat Removal Pump will NOT start.

Containment Equipment Hatch closure has been initiated.

Initiating Cue: Based on the Initial Conditions, contingencies were verified in place due to the Containment Equipment Hatch being removed prior to the loss of Safeguards Bus 1EA1 and the failure of RHR Pump 1-02 to start.

IDENTIFY the Reactor Coolant System Reduced Inventory contingencies regarding the Containment Equipment Hatch being removed.

Task Standard: Utilizing IPO-010A, Attachment 1, identified contingencies required with Containment Equipment Hatch removed while the Reactor Coolant System is at Reduced Inventory.

Required Materials: IPO-010A, Reactor Coolant System Reduced Inventory Operations, Rev 18-2.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM SA1 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

IPO-010A, Reactor Coolant System Reduced Inventory Operations.

PROVIDE the examinee a Straightedge or ruler.

Page 2 of 6 CPNPP NRC 2012 JPM SA1 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from IPO-010A, Attachment 1.

Perform Step: 1 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.1) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY the four swing bolts are in place with nuts and washers installed.

Comment: SAT UNSAT Perform Step: 2 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.2) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY the gasket is in place or is available.

Comment: SAT UNSAT Perform Step: 3 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.3) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY that the equipment door handling device or hoists are available for re-positioning the door.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM SA1 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.4) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY that all lines penetrating Containment through the open equipment hatch have isolation and disconnect capability.

Comment: SAT UNSAT Perform Step: 5 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.5) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

RECORD the name and telephone extension of the Maintenance Supervisor/ Containment Coordinator responsible for emergency equipment hatch installation.

Comment: SAT UNSAT Perform Step: 6 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.6) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

ENSURE a phone check has been conducted within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM SA1 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.7) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY scaffolding is in place, as necessary, for hatch installation.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM SA1 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

Reactor Coolant System Loops are NOT filled.

The Containment Equipment Hatch is removed.

IPO-010A, Reactor Coolant System Reduced Inventory Operations, Attachment 1, Shiftly Checklist is complete.

Safeguards Bus 1EA1 was lost on an 86-1 Lockout Relay actuation.

Train B Residual Heat Removal Pump will NOT start.

Containment Equipment Hatch closure has been initiated.

INITIATING CUE: Based on the Initial Conditions, contingencies were verified in place due to the Containment Equipment Hatch being removed prior to the loss of Safeguards Bus 1EA1 and the failure of RHR Pump 1-02 to start.

IDENTIFY the Reactor Coolant System Reduced Inventory contingencies regarding the Containment Equipment Hatch being removed.

Page 6 of 6 CPNPP NRC 2012 JPM SA1 Rev h

CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev h

&3133 352&('85(12

,17(*5$7('3/$1723(5$7,1*352&('85(60$18$/ 81,7 ,32$

5($&725&22/$176<67(0 5(9,6,2112

5('8&(',19(1725<23(5$7,216 3$*(2)

&217,1828686(

$77$&+0(17

3$*(2)

>&@ 6+,)7/<&+(&./,67

&$87,21 $OODSSOLFDEOHUHVWULFWLRQVFRQGLWLRQVDQGWLPHDIWHUVKXWGRZQFULWHULDVSHFLILHGLQ

$WWDFKPHQWPXVWEHPHWWRVDWLVI\WKHIROORZLQJUHTXLUHPHQW

 & ,)DQ2SHQ5&6&ROG/HJ3HQHWUDWLRQH[LVWV25D7HPSRUDU\6HDOLVLQVWDOOHGRQDQ\5&6 FRPSRQHQW7+(1(1685(DQDGHTXDWHKRWOHJYHQWSDWKH[LVWVSHU$WWDFKPHQW

! 5HDFWRU9HVVHO+HDGGHWHQVLRQHGRU5HPRYHG IRU7HPSRUDU\6HDOV21/< 

,QLWLDOV'DWH

! 3UHVVXUL]HUPDQZD\UHPRYHG 

,QLWLDOV'DWH

! $OOWKH3UHVVXUL]HUVDIHWLHVUHPRYHG 

,QLWLDOV'DWH

! 2QH6WHDP*HQHUDWRUKRWOHJPDQZD\DQGPDQZD\GLDSKUDJPUHPRYHGZLWK LWVDVVRFLDWHGQR))OHGDP127LQVWDOOHG 

,QLWLDOV'DWH

 &RQWDLQPHQW&ORVXUH 127( ! &RQWDLQPHQWKDWFKHVVKRXOGHLWKHUEHFORVHGRUFDSDEOHRIEHLQJFORVHGSULRUWR FRUHERLOLQJIROORZLQJDORVVRI5+5

! ,QIRUPDWLRQRQWLPHWRERLODQGWLPHUHTXLUHGWRFORVHWKH(TXLSPHQW+DWFKFDQ EHREWDLQHGIURPWKH2XWDJH&RQWURO&HQWHU

>&@ $ ,)WKHHTXLSPHQWKDWFKLVUHPRYHG7+(13(5)250WKHIROORZLQJVWHSV

  9(5,)<WKHIRXUVZLQJEROWVDUHLQSODFHZLWKQXWVDQGZDVKHUVLQVWDOOHG 

,QLWLDOV'DWH

  9(5,)<WKHJDVNHWLVLQSODFHRULVDYDLODEOH 

,QLWLDOV'DWH

  9(5,)<WKDWWKHHTXLSPHQWGRRUKDQGOLQJGHYLFHRUKRLVWVDUHDYDLODEOHIRU UHSRVLWLRQLQJWKHGRRULIUHTXLUHG 

,QLWLDOV'DWH CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev h Page 1 of 2

CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev h

&3133 352&('85(12

,17(*5$7('3/$1723(5$7,1*352&('85(60$18$/ 81,7 ,32$

5($&725&22/$176<67(0 5(9,6,2112

5('8&(',19(1725<23(5$7,216 3$*(2)

&217,1828686(

$77$&+0(17

3$*(2)

>&@ 6+,)7/<&+(&./,67

 $

>&@   9(5,)<WKDWDOOOLQHVSHQHWUDWLQJ&RQWDLQPHQWWKURXJKWKHRSHQHTXLSPHQW KDWFKKDYHLVRODWLRQDQGGLVFRQQHFWFDSDELOLW\ 

,QLWLDOV'DWH

 5(&25'WKHQDPHDQGWHOHSKRQHH[WHQVLRQRIWKH0DLQWHQDQFH6XSHUYLVRU&RQWDLQPHQW

&RRUGLQDWRUUHVSRQVLEOHIRUHPHUJHQF\HTXLSPHQWKDWFKLQVWDOODWLRQ





0DLQWHQDQFH6XSHUYLVRU&RQWDLQPHQW&RRUGLQDWRU1DPH ([W ,QLWLDOV'DWH

 (1685(DSKRQHFKHFNKDVEHHQFRQGXFWHGZLWKLQWKHSUHYLRXVKRXUV 

,QLWLDOV'DWH

 9(5,)<VFDIIROGLQJLVLQSODFHDVQHFHVVDU\IRUKDWFKLQVWDOODWLRQ 

,QLWLDOV'DWH 127( ! $&RQWDLQPHQWSHQHWUDWLRQVKRXOGEHFRQVLGHUHGLPSDLUHGLIDEUHDFKH[LVWV EHWZHHQ&RQWDLQPHQWDWPRVSKHUHDQGRXWVLGHDWPRVSKHUH([DPSOHVRILPSDLUHG

&RQWDLQPHQWSHQHWUDWLRQVPD\LQFOXGH

&RQWDLQPHQWLVRODWLRQYDOYHVGLVDVVHPEOHGRUUHPRYHG 2SHQWHVWFRQQHFWLRQVRUYHQWVEHWZHHQ&RQWDLQPHQWLVRODWLRQYDOYHVDQG

&RQWDLQPHQW (OHFWULFDOSHQHWUDWLRQVGLVDVVHPEOHGRUUHPRYHG

%ODQNIODQJHVUHPRYHGIURPVSDUHSHQHWUDWLRQV

RUNLQSURJUHVVZKLFKGLVDEOHVWKHDFWXDWRUIRUDQ\RSHQ&RQWDLQPHQW9HQWLODWLRQ

,VRODWLRQ9DOYH

! 7KHLQWHQWRIWKLVVHFWLRQRI$WWDFKPHQWLVWRHQVXUHWKDW&RQWDLQPHQWFORVXUH FDQEHDFKLHYHGZLWKLQDSSOLFDEOHWLPHOLPLWVIROORZLQJDORVVRI5+5FRROLQJ,WLV 127LQWHQGHGWKDW&RQWDLQPHQWRSHUDELOLW\EHHVWDEOLVKHGEXWVWDWXVRIWKH SHQHWUDWLRQVVKRXOGEHGRFXPHQWHGWRHQVXUH&RQWDLQPHQWRSHUDELOLW\FDQEH HVWDEOLVKHGLQWKHHYHQWRID/RVVRI5+5FRROLQJ

! 237$FRQWDLQVGLDJUDPVRIDOO&RQWDLQPHQWSHQHWUDWLRQV7KH237PD\EH XVHGDVDUHIHUHQFHZKHQGHWHUPLQLQJSHQHWUDWLRQVWDWXV

 % &RQWDLQPHQWSHQHWUDWLRQVDUHVHDOHGRUFORVHG 

,QLWLDOV'DWH CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev h Page 2 of 2

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA2 Task # SO1058 K/A # 2.1.23 4.3 / 4.4

Title:

Perform a Calorimetric Heat Balance and Evaluate Technical Specifications Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

COMPLETE through Step 8.2.2.11 When completed, IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Task Standard: Utilizing OPT-309, OPT-309-2, and OPT-309-11 calculated a Unit 1 calorimetric.

Utilizing Technical Specifications, identified and recorded LCO 3.3.1 Surveillance Requirement 3.3.1.2.

Required Materials: OPT-309, Unit Calorimetric, Rev 14.

OPT-309-2, Calorimetric Data Reduction Worksheet, Rev 8.

OPT-309-11, Unit 1 Calorimetric Data Sheet, Rev 6.

Unit 1 Technical Specifications, Amendment 154.

Validation Time: 25 minutes Completion Time: ________ minutes Page 1 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-309, Unit Calorimetric, completed through Step 8.2.2.8.

OPT-309-2, Calorimetric Data Reduction Worksheet, completed through Step 8.2.2.8.

OPT-309-11, Unit 1 Calorimetric Data Sheet with data entered.

Unit 1 Technical Specifications.

Steam Tables.

Calculator.

Page 3 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-309, Section 8.2.

Perform Step: 1 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.A, & Enter corrected steam pressures given in column 5 of Step 8.2.2.9.B 8.2.2.5, in column 2.

Using Steam Tables obtain the steam enthalpies AND enter results in column 3.

Standard: CALCULATED Steam Generator Enthalpy Rise using corrected steam pressures (PSIA) then CALCULATED associated steam enthalpy values using Steam Tables and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 2 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.C, 8.2.2.9.C 2nd bullet, &

• Enter feedwater enthalpy from one of the following sources:

8.2.2.9.D

• IF Steam Generator Blowdown NOT isolated, THEN enter value given in column 2 of Step 8.2.2.8 into column 3, or

• Using Steam Tables obtain the enthalpy of the feedwater liquid AND enter result in column 4.

• Subtract the value in column 4 from values in column 3 AND enter the results in column 5.

Standard: CALCULATED Feedwater Enthalpy using Steam Tables then SUBTRACTED value in column 4 from values in column 3 and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Perform Steam Generator Heat Gain Calculation as follows:

8.2.2.10, 8.2.2.10.A, Enter the enthalpy rise for each Steam Generator given in column 8.2.2.10.B, 8.2.2.10.C, 5 of Step 8.2.2.9, into column 2.

& 8.2.2.10.D Calculate steam flow for each Steam Generator by using the formula given in the heading of column 3. Use data for Feedwater flow given in column 4 of Step 8.2.2.4 AND blowdown flow given in column 3 of Step 8.2.2.7. Enter results in column 3.

Multiply the entries in column 2 by entries in column 3, AND enter results in column 4.

Total the entries of column 4 and enter result at the base of this column.

Standard: CALCULATED Steam Generator Heat Gain; RECORDED enthalpy rise for each Steam Generator then RECORDED steam flow for each Steam Generator then MULTIPLIED the entries in column 2 by entries in column 3, and ENTERED results in column 4 then TOTALED the entries and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 4 Perform Percent Rated Thermal Power Calculation as follows:

8.2.2.11, 8.2.2.11.A, Enter the Steam Generator Heat Gain given in space at the base 8.2.2.11.B, 8.2.2.11.C, of column 4 from Step 8.2.2.10, in column 1.

& 8.2.2.11.D IF Steam Generator Blowdown NOT isolated, THEN enter the Blowdown Heat Loss given in column 3 of Step 8.2.2.8, in column 2.

Calculate Net Reactor Power by using the formula given in the heading of column 4 AND the data given in columns 1, 2 and 3.

Enter results in column 4.

Substitute values from column 4 and column 5 into the formula in the heading of column 6 AND calculate Percent Rated Thermal Power. Enter the result in column 6.

Standard: CALCULATED Percent Rated Thermal Power using Steam Generator Heat Gain then CALCULATED Net Reactor Power value then SUBSTITUTED values and CALCULATED Percent Rated Thermal Power and ENTERED data on OPT-309-2.

CALCULATED a Percent Rated Thermal Power of 94 +/- 1.0%.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following step is from Technical Specification LCO 3.3.1.

Perform Step: 5 IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Standard: REVIEWED OPT-309-11, Unit 1 Calorimetric Data Sheet and IDENTIFIED Technical Specification LCO 3.3.1 Surveillance Requirement 3.3.1.2 and RECORDED the following in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet:

Adjust NIS Power Range channel outputs if calorimetric heat balance calculation exceeds NIS Power Range channel outputs by more than +2% RTP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Adjust N-16 Power Monitor channel outputs if calorimetric heat balance calculation exceeds N-16 Power Monitor channel outputs by more than +2% RTP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2012 JPM SA2 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

COMPLETE through Step 8.2.2.11.

When completed, IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Page 7 of 7 CPNPP NRC 2012 JPM SA2 Rev h

CPNPP NRC 2012 JPM SA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET Unit 1 Date Today 8.2.2.2 - Feedwater Average Temperature Parameter Average Value of Overall Data Sets Average

(°F) (°F)

S/G 1 Feedwater Temperature 440 S/G 2 Feedwater Temperature 440 440 S/G 3 Feedwater Temperature 440 S/G 4 Feedwater Temperature 440 8.2.2.3 Feedwater Average Pressure Parameter Average of Data Sets Corrected Pressure Overall Average (PSIG) (PSIG + 14.7 = PSIA) (PSIA)

S/G 1 Feedwater Pressure 1160 1175 S/G 2 Feedwater Pressure 1160 1175 1175 S/G 3 Feedwater Pressure 1160 1175 S/G 4 Feedwater Pressure 1160 1175 8.2.2.4 - Feedwater Flow Averages Parameter Average Value of Correction Factor Corrected Value (WF) Data Sets (CF) LB/HR x CF (LB/HR) (NOTE 1) (LB/HR)

S/G 1 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 2 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 3 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 4 Feedwater Flow 3.8xE6 1.0 3.8xE6 8.2.2.5 - Corrected Steam Generator Steam Pressure Averages Parameter Average of Corrected Pressure Pressure Drop Due to Corrected Overall Data Sets Line Loss (PSIA) Pressure Average (PSIG) (PSIG+14.7 = PSIA) (NOTE 2) (PSIA) (PSIA)

S/G 1 Steam Pressure 979.7 994.4 5.55 999.95 979.4 994.1 999.98 1000 S/G 2 Steam Pressure 5.88 S/G 3 Steam Pressure 978.4 993.1 7.04 1000.14 S/G 4 Steam Pressure 979.1 993.8 6.13 999.93 NOTE 1: Correction Factor is 1 when LEFM data is used. When other Feedwater Flow data is used, Correction Factor is from Attachment 10.1 using Feedwater Temperature for the associated SG calculated in Step 8.2.2.2 (Column 2).

NOTE 2: The steam line pressure drops are the same for both Units.

OPT-309-2 REV. 8 PAGE 1 OF 3 CPNPP NRC 2012 JPM SA2 Answer Key Rev h Page 1 of 3

CPNPP NRC 2012 JPM SA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.6 - Steam Generator Blowdown Average Values Parameter Average Value of Data Sets SG Blowdown Flow (GPM) 335 SG Blowdown Hx Out Temp (°F) 250 8.2.2.7 - Blowdown Flow Conversion Average Specific Blowdown Flow, Fbd Blowdown Volume, V Flow, F (GPM) FT3/lbm (LBM/HR) 335 0.0170 161967 8.2.2.8 - Blowdown Heat Loss Calculation Blowdown Enthalpy, Feedwater Enthalpy, Blowdown Heat Loss, Qbd (BTU/LBM) (BTU/LBM) (BTU/HR) 542.6 419.9 19873351 8.2.2.9 - S/G Enthalpy Rise Calculation SG No. Corrected Steam Feedwater Enthalpy Steam Enthalpy, Enthalpy, Rise Pressure (PSIA)

(BTU/LBM) (BTU/LBM) (BTU/LBM) 1 1000 1192.9 773 2 1000 1192.9 773 419.9 3 1000 1192.9 773 4 1000 1192.9 773 OPT-309-2 REV. 8 PAGE 2 OF 3 CPNPP NRC 2012 JPM SA2 Answer Key Rev h Page 2 of 3

CPNPP NRC 2012 JPM SA2 Answer Key Rev h CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.10 - SG Heat Gain Calculation SG No. Enthalpy Rise, Steam Flow S/G Heat Gain, (BTU/LBM) (LBM/HR) (BTU/HR) 1 773 3,759,508 2,906,099,877 2 773 3,759,508 2,906,099,877 3 773 3,759,508 2,906,099,877 4 773 3,759,508 2,906,099,877 1.1624xE10 8.2.2.11 - Percent Rated Thermal Power Calculation SG Blowdown Non-Reactor Net Reactor Rated Percent Rated Heat Heat Loss, Heat Gains, Power, Thermal Thermal Power Gain Power, (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (%)

1.1624xE10 19873351 5.4 X 107 1.1590xE10 1.2328 x10 10 94.02 Comments: Adjust NIS Power Range channel outputs if calorimetric heat balance calculation exceeds NIS Power Range channel outputs by more

+2% RTP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Performed By: Date:

Reviewed By: Date:

OPT-309-2 REV. 8 PAGE 3 OF 3 CPNPP NRC 2012 JPM SA2 Answer Key Rev h Page 3 of 3

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA3 Task # SO1202 K/A # 2.2.12 3.7 / 4.1

Title:

Perform Control Room Air Conditioning System Surveillance Data and Evaluate Technical Specifications Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 50%

unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 160 psig and is operating 0%

unloaded.

X-TR-4123 reads 80°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME and record in Comments Section of surveillance.

Task Standard: Utilizing OPT-116, recorded collected data on OPT-116-1, plotted air conditioning unit cooling capacity, and determined Acceptance Criteria NOT met. Identified Technical Specification LCO 3.7.11 CONDITION, REQUIRED ACTION, and COMPLETION TIME and recorded in Comments Section of surveillance.

Page 1 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: OPT-116, CR AC System, Rev. 4.

OPT-116-1, CR AC System Data Sheet, Rev. 4.

Unit 1 Technical Specifications, Amendment 154.

Validation Time: 30 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-116, CR AC System.

INITIAL and N/A as appropriate up to Step 8.3.

OPT-116-1, CR AC System Data Sheet.

INITIAL and N/A as appropriate up to Step 8.3.

Page 3 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-116, Section 8.0.

Perform Step: 1 RECORD the following:

st 8.3 & 1 bullet X-TR-4123, outside temperature (10M PRI) (X-CV-05)

Standard: RECORDED X-TR-4123, outside temperature of 80°F on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 2 RECORD the following:

nd 8.3 & 2 bullet X-TI-5933 ECB EXH TEMP (X-CV-01)

Standard: RECORDED X-TI-5933, ECB EXH TEMP of 72°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 3 RECORD the following:

8.3 & 3rd bullet X-TI-5734, AB EXH TEMP EL-852' 6" (X-CV-03)

Standard: RECORDED X-TI-5734, AB EXH TEMP of 73°F on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 4 RECORD the following:

8.3 & 4th bullet X-TI-5735, AB EXH TEMP EL-831' 6" (X-CV-03)

Standard: RECORDED X-TI-5735, AB EXH TEMP of 73°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Page 4 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units.

CR A/C Unit 03 (X-PI-3585A)

Standard: RECORDED CR A/C Unit 03 (X-PI-3585A) pressure of 150 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Perform Step: 6 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units CR A/C Unit 04 (X-PI-3586A)

Standard: RECORDED CR A/C Unit 04 (X-PI-3586A) pressure of 160 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Examiner Cue: If asked about Independent Verification (IV), REPORT to proceed as if the IV has been performed.

Perform Step: 7 VERIFY the above readings are within the specified limits. If any of the 8.4 above readings are NOT within the specified limits, this test should be terminated and restarted when the above conditions can be met.

Standard: VERIFIED that all readings are within limits and INITIALED.

Comment: SAT UNSAT Perform Step: 8 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 03 Standard: RECORDED A/C UNIT 03 % unloaded of 50% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 04 Standard: RECORDED A/C UNIT 04 % unloaded of 0% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 10 CALCULATE the average % unloaded by adding the % unloaded from 8.6 the operating compressors and dividing by 2.

Standard: ADDED 50% and 0% and DIVIDED by 2 to yield an average of 25%;

RECORDED on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 11 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: PLOTTED the intersection point for 80°F and 25% on Figure 1 and COMPARED to the acceptability curve.

Comment: SAT UNSAT Perform Step: 12 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: VERIFIED plotted point is BELOW the curve on Figure 1 and CIRCLED BELOW then UNSAT on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Page 6 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following is from Technical Specification LCO 3.7.11.

Perform Step: 13 RECORD any required Technical Specification CONDITION, REQUIRED ACTION, and COMPLETION TIME in the Comments Section of the Surveillance.

Standard: DETERMINED entry into Technical Specification LCO 3.7.11, Control Room Air Conditioning System (CRACS):

CONDITION A - One CRACS train inoperable; REQUIRED ACTION A.1 - Restore CRACS train to OPERABLE status.

COMPLETION TIME - Within 30 days.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP NRC 2012 JPM SA3 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 50% unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 160 psig and is operating 0% unloaded.

X-TR-4123 reads 80°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME and record in Comments Section of surveillance.

Page 8 of 8 CPNPP NRC 2012 JPM SA3 Rev h

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h CR A/C SYSTEM DATA SHEET REQUIRED TEST STEP OBSERVED CONDITIONS INITIALS 6.0 PREREQUISITES MET N/A N/A RB AND TIME/DATE Today @ 0800 N/A RB 8.1 CR A/C UNITS BEING TESTED Units 03 & 04 N/A RB Today @ 0900 $30 MIN RB 8.2 TIME AND DATE PAST STEP 6.0 8.3 RECORD THE FOLLOWING:

! X-TR-4123 OUTSIDE TEMPERATURE 80 F N/A RB

! X-TI-5933 72 F $60°F RB

! 73 F RB X-TI-5734 $60°F

! 73 F RB X-TI-5735 $60°F

! COMPRESSOR DISCHARGE PRESSURES (N/A for shutdown units)

CR A/C UNIT 01 (X-PI-3583A) N/A <170 PSIG N/A CR A/C UNIT 02 (X-PI-3584A)

N/A <170 PSIG N/A CR A/C UNIT 03 150 psig (X-PI-3585A) <170 PSIG RB CR A/C UNIT 04 (X-PI-3586A) 160 psig <170 PSIG RB 8.4 ALL ABOVE REQUIRED TEST CONDITIONS MET N/A NOTE 1 RB NOTE 1: If test conditions are not met, terminate test at this point. Test shall be restarted when conditions can be met.

CONTINUOUS USE OPT-116-1 PAGE 1 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h Page 1 of 4

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h CR A/C SYSTEM DATA SHEET STEP OBSERVED INITIALS 8.5 A/C UNIT % UNLOADED (N/A for shutdown units)

A/C UNIT 01 N/A N/A A/C UNIT 02 N/A N/A A/C UNIT 03 50 RB A/C UNIT 04 0 RB 8.6 CALCULATE AVERAGE A/C UNIT NO. 03 A/C UNIT NO. 04 RB

% UNLOADED 50 + % UNLOADED 0 = 25 2 TRAIN AVERAGE N/A COMPRESSOR COOLING VERIFIED CAPACITY AVAILABILITY 8.7 COMPARE OUTSIDE TEMP (STEP 8.3) AND AVERAGE OPERATION COMPRESSOR COOLING CAPACITY AVAILABILITY ABOVE/BELOW (STEP 8.6) TO CURVE (FIGURE 1) CURVE RB ACCEPTANCE CRITERIA SAT IF OPERATION IS ABOVE CURVE SAT/UNSAT RB CONTINUOUS USE OPT-116-1 PAGE 2 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h Page 2 of 4

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h CR A/C SYSTEM DATA SHEET FIGURE 1 OUTSIDE PERCENT UNLOADED TEMPERATURE 16.7 110 24.3 100 32.0 90 39.6 80 47.2 70 51.7 60 54.1 50 56.5 40 58.9 30 61.3 20 CONTROL ROOM HVAC MINIMUM REQUIRED AVAILABILITY THE UNLOADED COMBINED AVERAGE OF THE TWO 50% CONTROL ROOM HVAC UNITS MUST BE ABOVE THE CURVE REPRESENTED BELOW:

COOLING CAPACITY AVAILABLE (%)

70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 OUTSIDE TEMPERATURE (F)

CONTINUOUS USE OPT-116-1 PAGE 3 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h Page 3 of 4

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h CR A/C SYSTEM DATA SHEET COMMENTS/DISCREPANCIES:

Technical Specification LCO 3.7.11, Control Room Air Conditioning System (CRACS)

• CONDITION A - One CRACS train inoperable

• REQUIRED ACTION A.1 - Restore CRACS train to OPERABLE status.

• COMPLETION TIME - Within 30 days.

CORRECTIVE ACTIONS:

PERFORMED BY: DATE:

SIGNATURE REVIEWED BY: DATE:

OPERATIONS MANAGEMENT CONTINUOUS USE OPT-116-1 PAGE 4 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev h Page 4 of 4

CPNPP NRC 2012 JPM SA3 Answer Key 2 Rev h CRACS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRACS)

LCO 3.7.11 Two CRACS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRACS train A.1 Restore CRACS train to OPERABLE 30 days inoperable. status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not met AND in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Required Action and C.1 Place OPERABLE CRACS train in Immediately associated Completion operation.

Time of Condition A not met in MODE 5, or 6, or during OR movement of irradiated fuel assemblies. C.2.1 Suspend CORE ALTERATIONS. Immediately AND C.2.2 Suspend movement of irradiated Immediately fuel assemblies.

COMANCHE PEAK - UNITS 1 AND 2 3.7-26 Amendment No. 150 CPNPP NRC 2012 JPM SA3 Answer Key 2 Rev h Page 1 of 1

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA4 Task # SO1005 K/A # 2.3.13 3.4 / 3.8

Title:

Determine Containment Stay Time Requirements and Event Reportability Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #1

• A Containment entry is about to be performed by a 4 member team.

• The estimated gamma dose rate is 75 mrem/hr.

• The estimated neutron dose rate is 10 mrem/hr.

• Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

• Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

• The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

• The Heat Stress Action Time has been determined to be 40 minutes.

Initiating Cue: The Work Control Supervisor directs you to PERFORM the following:

JPM Cue Sheet #1

• CALCULATE the following:

• Gamma dose stay time per team. _____ minutes.

• Neutron dose stay time per team. _____ minutes.

• Heat Stress Stay Time _____ minutes.

• DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

• Limiting Containment entry time: _____ minutes.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #2

• The Shift Manager was notified by Radiation Protection that a member of the Containment entry team was injured and contaminated.

• The individual is in route to the hospital.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet #2

• DETERMINE Oral Reportability Requirements, if any.

• Oral Reporting Requirement _______________

Page 1 of 7 CPNPP NRC 2012 JPM SA4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing STA-620/655/657/660/674, calculated gamma and neutron dose stay times for the team, Heat Stress Stay Time, and determined limiting Containment entry time.

Utilizing STA-501, determined oral Reporting Requirements for a contaminated injured person.

Required Materials: STA-501, Nonroutine Reporting, Rev. 15-3.

STA-620, Containment Entry, Rev. 13.

STA-655, Exposure Monitoring Program, Rev. 20.

STA-657, ALARA Job Planning/Debriefing, Rev. 14.

STA-660, Control of High Radiation Areas, Rev. 15.

STA-674, Heat Stress Management, Rev. 8.

Validation Time: 25 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2012 JPM SA4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee JPM Cue Sheet #1 and MAKE the following available in the classroom:

• STA-501, Nonroutine Reporting.

• STA-620, Containment Entry.

• STA-655, Exposure Monitoring Program.

• STA-657, ALARA Job Planning/Debriefing.

• STA-660, Control of High Radiation Areas.

• STA-674, Heat Stress Management.

ENSURE examinee has a calculator.

When JPM Cue Sheet #1 is completed, PROVIDE JPM Cue Sheet #2.

Page 3 of 7 CPNPP NRC 2012 JPM SA4 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Provide the examinee with copy of JPM Cue Sheet #1.

Perform Step: 1 Calculate gamma dose stay time per team.

Standard: CALCULATED the following:

• 75 mrem/hr gamma x 4 persons = 300 mrem/hr from gamma.

• 500 person-REM allowed 100 minute gamma Stay Time Comment: SAT UNSAT Perform Step: 2 Calculate neutron dose stay time per team.

Standard: CALCULATED the following:

• 10 mrem/hr neutron x 4 persons = 40 mrem/hr from neutron.

• 50 person-REM allowed 75 minute neutron Stay Time Comment: SAT UNSAT Examiner Note: The following step is from STA-674, Section 4.0, Definitions.

Perform Step: 3 Calculate Heat Stress Stay Time.

Standard: CALCULATED the following:

• Heat Stress Action Time is 40 minutes per the Initial Conditions.

• Heat Stress Stay Time is 2 x 40 minutes = 80 minutes Comment: SAT UNSAT Perform Step: 4 Determine limiting Containment entry time.

Standard: DETERMINED the limiting Containment entry time is 75 minutes based on Neutron Dose Stay Time.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM SA4 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Provide the examinee with copy of JPM Cue Sheet #2.

Examiner Note: The following steps are from STA-501, Attachment 8.D/13.

Perform Step: 5 Determine oral Reporting Requirements per STA-501. .D/13 Page 9 of 17 Standard: DETERMINED oral Reporting Requirements per STA-501:

Any event requiring the transport of a radioactively contaminated person to an off-site medical facility for treatment.

• Oral Report within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Examiner Note: Answer in bold print.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 7 CPNPP NRC 2012 JPM SA4 Rev h

Appendix C JPM CUE SHEET #1 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• A Containment entry is about to be performed by a 4 member team.

• The estimated gamma dose rate is 75 mrem/hr.

• The estimated neutron dose rate is 10 mrem/hr.

• Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

• Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

• The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

• The Heat Stress Action Time has been determined to be 40 minutes.

INITIATING CUE: The Work Control Supervisor directs you to PERFORM the following:

• CALCULATE the following:

• Gamma dose stay time per team. _____ minutes.

• Neutron dose stay time per team. _____ minutes.

• Heat Stress Stay Time _____ minutes.

• DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

• Limiting Containment entry time: _____ minutes.

Page 6 of 7 CPNPP NRC 2012 JPM SA4 Rev g

Appendix C JPM CUE SHEET #2 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• The Shift Manager was notified by Radiation Protection that a member of the Containment entry team was injured and contaminated.

• The individual is in route to the hospital.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

• DETERMINE Oral Reportability Requirements, if any.

• Oral Reporting Requirement _______________

Page 7 of 7 CPNPP NRC 2012 JPM SA4 Rev h

CPNPP NRC 2012 JPM SA4 Answer Key Rev h CPNPP PROCEDURE NO.

STATION ADMINISTRATION MANUAL STA-501 REVISION NO. 15 NONROUTINE REPORTING PAGE 106 0F 189 INFORMATION USE ATTACHMENT 8.D/13 PAGE 9 OF 17 10CFR50.72 and 10CFR50.73 MATRIX 10CFR50.72 hrs 10CFR50.73 LER Refer to the plant's Emergency Plan regarding (a)(2)(viii) 60 declaration of an Emergency Class. (A) Any airborne radioactive release that, when day Refer to 10CFR50.72(b)(2)(xi) below regarding a news averaged over a time period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, resulted in LER release or notification of another agency. airborne radionuclide concentrations in an unrestricted Refer to 10CFR20.2202 regarding events reportable area that exceeded 20 times the applicable under that section. concentration limits specified in appendix B to part 20, table 2, column 1.

(a)(2)(viii)

(B)Any liquid effluent release that, when averaged over a time period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, exceeds 20 times the applicable concentrations specified in appendix B to part 20, table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases.

(a)(2)(ix)(A) 60 Any event or condition that as day a result of a single cause could have prevented the LER fulfillment of a safety function for two or more trains or channels in different systems that are needed to:

(1) Shut down the reactor and maintain it in a safe shutdown condition; (2) Remove residual heat; (3) Control the release of radioactive material; or (4) Mitigate the consequences of an accident.

(a)(2)(ix)(B) 60 Events covered in paragraph day (ix)(A) of this section may include cases of procedural LER error, equipment failure, and/or discovery of a design, analysis, fabrication, construction, and/or procedural inadequacy. However, licensees are not required to report an event pursuant to paragraph (ix)(A) of this section if the event results from:

(1) A shared dependency among trains or channels that is a natural or expected consequence of the approved plant design; or (2) Normal and expected wear or degradation.

Refer to the plant's Emergency Plan regarding (a)(2)(x) 60 declaration of an Emergency Class. Any event that posed an actual threat to the safety of day the nuclear power plant or significantly hampered site LER personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.

(b)(3)(xii) There is no corresponding requirement in Any event requiring the transport of a radioactively 10CFR50.73.

contaminated person to an offsite medical facility for 8 treatment.

NR-13 CPNPP NRC 2012 JPM SA4 Answer Key Rev h Page 1 of 1

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA5 Task # SO1136 K/A # 2.4.41 2.9 / 4.6

Title:

Classify an Emergency Plan Event Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 5.

Unit 2 is in MODE 1.

A sodium hypochlorite hose has ruptured while transferring chemicals at the Service Water Intake Structure.

Personnel performing the evolution were wearing respirators and have evacuated the area; however, nearby maintenance workers are requesting medical attention related to breathing difficulties.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE the Emergency Action Level Group / Category, Subcategory, and Event Classification per EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

Task Standard: Utilizing EPP-201, determined the Event Category and Event Classification using the Emergency Action Level All Modes/Hot Conditions & All Modes/Cold Conditions Classification Charts.

Required Materials: EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation, Rev. 12.

CPNPP Emergency Action Level All Modes/Hot Conditions & All Modes/Cold Conditions Classification Charts, Rev. 12.

Sodium Hypochlorite Material Safety Data Sheet, Rev. 1.0 Time Critical: 15 minutes Completion Time: ________ minutes Validation Time: 10 minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 4 CPNPP NRC 2012 JPM SA5 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

MAKE the following available in the classroom:

EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

CPNPP Emergency Action Level All Modes/Hot Conditions & All Modes/Cold Conditions Classification Charts.

Sodium Hypochlorite Material Safety Data Sheet.

Page 2 of 4 CPNPP NRC 2012 JPM SA5 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step CRITICAL START TIME:

Examiner Note: Start time should coincide with applicant understanding cue and being ready to begin.

Examiner Note: The following steps are from CPNPP Emergency Action Levels All Modes.

Perform Step: 1 DETERMINE the Event Category.

Standard: REFERRED to CPNPP Emergency Action Level Charts and DETERMINED the following chart is applicable:

CPNPP EAL All Modes Chart Comment: SAT UNSAT Perform Step: 2 MATCH plant conditions in the EAL Group / Category.

Standard: IDENTIFIED EAL Group / Category as HAZARDS (H).

Comment: SAT UNSAT Perform Step: 3 MATCH plant conditions in the selected EAL Subcategory.

Standard: IDENTIFIED EAL Subcategory as Hazardous Gas (3).

Comment: SAT UNSAT Examiner Note: Stop time should coincide with applicant indicating that an ALERT must be declared based on Hazardous Gas (HA3.1).

Perform Step: 4 Classify the event.

Standard: CLASSIFIED the event as an ALERT (HA3.1).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT CRITICAL STOP TIME:

Page 3 of 4 CPNPP NRC 2012 JPM SA5 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5.

Unit 2 is in MODE 1.

A sodium hypochlorite hose has ruptured while transferring chemicals at the Service Water Intake Structure.

Personnel performing the evolution were wearing respirators and have evacuated the area; however, nearby maintenance workers are requesting medical attention related to breathing difficulties.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

DETERMINE the Emergency Action Level Group /

Category, Subcategory, and Event Classification per EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

TIME CRITICAL JPM Page 4 of 4 CPNPP NRC 2012 JPM SA5 Rev h

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: CPNPP Units 1 and 2 Date of Examination: 06/11/12 Exam Level: RO SRO(I) SRO (U) Operating Test No.: NRC Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1 001 - Control Rod Drive System (RO1014A) (RO ONLY) A, M, S 1 Perform a Dropped Control Rod Recovery S-2 004 - Chemical and Volume Control System (RO1305A) N, S 2 Remove Excess Letdown from Service S-3 002 - Reactor Coolant System (RO1412B) A, L, N, S 4P Respond to Shutdown Loss of Coolant S-4 059 - Main Feedwater System (RO3301C) D, S 4S Place 2nd Main Feedwater Pump in Service S-5 026 - Containment Spray (CS) System (RO2002) D, EN, S 5 Transfer CS From Injection to Recirculation S-6 062 - AC Electrical Distribution System (RO4201) A, D, P, S 6 Shift Normal Bus 1A4 Between UAT and SUT S-7 073 - Process Radiation Monitoring System (RO4103A) A, D, S 7 Respond to Control Room Ventilation Radiation Alarms S-8 086 - Component Cooling Water System (RO3603A) A, D, S 8 Rotate Component Cooling Water Pumps S- 086 - Component Cooling Water System (RO3603A) D, S 8 8.a Rotate Component Cooling Water Pumps In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 061 - Auxiliary Feedwater System (AFW) (AO6415A) D, E, R 4S Align Alternate AFW Supply From SSW P-2 068 - Liquid Radwaste System (RO4005C) N, R 9 Terminate Release of Radioactive Liquid P-3 006 - Emergency Core Cooling System (RO7017) E, M, R 2 Align Emergency Makeup to the RWST Page 1 of 3 06.CPNPP NRC 2012 ES-301-2 RO & SRO JPM Outline Rev h.doc

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator NRC JPM Examination Summary Description S-1 The applicant will perform a dropped Control Rod recovery per ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or Misaligned Control Rod in MODE 1 or 2.

The alternate path requires a Reactor Trip when a second Control Rod drops into the core during recovery actions. This is a modified bank JPM under the Control Rod Drive System - Reactivity Control Safety Function. (K/A 003.AA1.02 - IR 3.6 / 3.4)

S-2 The applicant will remove Excess Letdown from service per SOP-103A, Chemical and Volume Control System, Section 5.5.4, Removing Excess Letdown from Service. This is a new JPM under the Chemical and Volume Control System - Reactor Coolant System Inventory Control Safety Function. (K/A 004.A2.02 - IR 3.2 / 3.2)

S-3 The applicant will respond to a lowering Pressurizer level with the Residual Heat Removal System in service per ABN-108, Shutdown Loss of Coolant, Section 2.0, Shutdown Loss of Coolant. The alternate path occurs when it is determined that Pressurizer level continues to lower until Letdown is isolated. This is a new JPM under the Residual Heat Removal System - Primary System Heat Removal from Reactor Core Safety Function. This is a PRA significant action. (K/A 025.AA1.02- IR 3.8 / 3.9)

S-4 The applicant will place the second Main Feedwater Pump in service per IPO-003A, Power Operations, Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

This is a bank JPM under the Main Feedwater System - Secondary System Heat Removal from Reactor Core Safety Function. (K/A 059.A4.10 - IR 3.9 / 3.8)

S-5 The applicant will transfer Containment Spray suction to the Containment Sumps per EOS-1.3A, Transfer to Cold Leg Recirculation, Attachment 1.H, Containment Spray Switchover Criterion. This is a time critical, bank JPM under the Containment Spray System - Containment Integrity Safety Function. This is a PRA significant action.

(K/A 026.A4.01 - IR 4.5 / 4.3)

Page 2 of 3 06.CPNPP NRC 2012 ES-301-2 RO & SRO JPM Outline Rev h.doc

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-6 The applicant will shift Normal Bus 1A4 between the Unit Auxiliary Transformer and the Startup Transformer per SOP-603A, 6900 V Switchgear, Step 5.3.2, Transferring a 6.9 KV Normal Bus from Unit 1 Auxiliary Transformer 1UT to Station Service Transformer 1ST. The alternate path occurs when Incoming Breaker 1A4-1 fails to trip during Bus transfer. This is a bank JPM under the AC Electrical Distribution System - Electrical Safety Function. (K/A 062.A4.07 - IR 3.1 / 3.1)

S-7 The applicant will respond to PC-11, Digital Radiation Monitoring System alarms per ABN-902 Release of Radioactive/Toxic Gas. The alternate path occurs when the Control Room Ventilation System fails to shift to the Emergency Recirculation Mode and the alignment must be manually performed per SOP-802, Control Room Ventilation System.

This is a bank JPM under the Process Radiation Monitoring System - Instrumentation Safety Function. (K/A 073.A4.02 - IR 3.7 / 3.7)

S-8 The applicant will shift from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System, Step 5.2.2.1, Starting a Standby CCW Pump During Normal Operation, then Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation. The alternate path occurs when the Train B CCW Pump trips shortly after it is started. This is a bank JPM under the Component Cooling Water System

- Plant Service Systems Safety Function. (K/A 008.A2.01 - IR 3.3 / 3.6)

S-8.a The applicant will shift from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System, Step 5.2.2.1, Starting a Standby CCW Pump During Normal Operation, then Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation. For one RO applicant, an error by simulator operators resulted in the alternate path denoted in JPM S-8 not being inserted.

P-1 The applicant will align an alternate source of Auxiliary Feedwater from the Station Service Water System per ABN-803A(B), Response to a Fire in the Control Room or Cable Spreading Room, Attachment 9, Alternate AFW Supply. This is a bank JPM under the Auxiliary Feedwater System - Secondary System Heat Removal from the Reactor Core Safety Function. This is a PRA significant action. (K/A 054.AA1.01 - IR 4.5 / 4.4)

P-2 The applicant will perform actions to terminate a radioactive discharge per RWS-103, Drain Channel B, Section 5.2.3, Discharging PET X-01 with Pump X-01 with Radiation Monitor Operable, Step 5.2.3 N. This is a new JPM under the Liquid Radwaste System -

Radioactivity Release Safety Function. (K/A 059.AA2.04 - IR 3.2 / 3.5)

P-3 The applicant will align makeup to the Refueling Water Storage Tank during a Loss of Emergency Coolant Recirculation per ECA-1.1A(B), Loss of Emergency Coolant Recirculation, Attachment 3, RWST Makeup Methods. This is a modified bank JPM under the Emergency Core Cooling System - Reactor Coolant System Inventory Control Safety Function. This is a PRA significant action. (K/A E11.EA1.1 - IR 3.9 / 4.0)

Page 3 of 3 06.CPNPP NRC 2012 ES-301-2 RO & SRO JPM Outline Rev h.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-1 Task # RO1014 K/A # 003.AA1.02 3.6 / 3.4 SF-1

Title:

Perform a Dropped Control Rod Recovery Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2, actions are complete through Step 3.3.15.e.

Control Bank D was last moved in the OUTWARD direction.

Control Rod H8 is ready to be withdrawn.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

RECOVER the dropped Control Rod per ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2.

START at Step 3.3.15.f.

Task Standard: Utilizing ABN-712, withdrew dropped Control Rod H8, and following a second dropped Control Rod tripped the Reactor from the Reactor Trip Switch on CB-10 and performed EOP-0.0A, Step 1 from memory.

Required Materials: ABN-712, Rod Control System Malfunction, Rev. 10-13.

EOP-0.0A, Reactor Trip or Safety Injection, Rev. 8-7.

Validation Time: 5 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-38 or any at 100% power Initial Condition and load Scenario File LC20 NRC JPM 1. PERFORM the following:

EXECUTE the following malfunctions:

RD03H8, Dropped Control Rod.

RP01, Automatic Reactor Trip Failure.

RP13A, Manual Reactor Trip Switch at CB-07 DISABLED.

LOWER Turbine Load to1160 MWe and STABILIZE temperature.

REMOVE Malfunction RD03H8, for Control Rod H8.

EXECUTE remote function RDR03, PLACE and HOLD P/A Converter in MANUAL position.

ENSURE Control Bank D is at 215 steps.

PERFORM any additional actions required per ABN-712, Steps 3.3.1 through 3.3.15.e.

PLACE Control Rods D4, M12, D12, and M4 in DISCONNECT at the Rod Disconnect Panel.

EXECUTE the following during recovery actions:

During the rod recovery, EXECUTE malfunction RD03G13, Control Rod G13 Drop and RDO3H8, control Rod H8 Drop 10 seconds after Control Rod H8 Rod Bottom Light clears.

BOOTH OPERATOR NOTE:

After each JPM, RESET Rod Bank Update when Simulator is INITIALIZED.

EXAMINER:

PROVIDE the examinee with a copy of Procedure 1:

ABN-712, Rod Control System Malfunction.

Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2.

INITIAL through Step 3.3.15.e.

Page 2 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-712, Section 3.0.

Perform Step: 1 WHEN moving affected rod for realignment, THEN perform the 3.3.15.f & 3.3.15.f.1) following:

Maintain TAVE within 2°F of TREF by controlling the following as necessary:

Turbine Power Steam Dumps Boration Dilution Standard: REVIEWED NOTE box in order to maintain TAVE within 2°F of TREF during Control Rod recovery.

Comment: SAT UNSAT Perform Step: 2 WHEN moving affected rod for realignment, THEN perform the 3.3.15.f & 3.3.15.f.2) following:

Verify that only affected rod is moving.

Standard: VERIFIED that only Control Rod H8 moves during Control Rod recovery.

Comment: SAT UNSAT Perform Step: 3 WHEN moving affected rod for realignment, THEN perform the 3.3.15.f & 3.3.15.f.3) following:

Ensure last movement of affected rod is in same direction as last movement of affected group.

Standard: VERIFIED per Initial Conditions that Control Bank D was last moved in the OUTWARD direction.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Slowly move affected rod until aligned with its group by DRPI indication.

3.3.15.g Standard: WITHDREW Control Rod H8 to 215 steps as indicated on Control Bank D Demand Step Counter and PLACED 1/1-FLRM, CONTROL ROD MOTION CTRL to OUT position.

Comment: SAT UNSAT Examiner Note: When the Rod Bottom Light for Control Rod H8 clears, two Control Rods (G13 and H8) will drop.

Perform Step: 5 RESPOND to Multiple Rod Control System Alarms.

Standard: DETERMINED Control Rods G13 and H8 have dropped and REFERRED to Step 3.3.1 RNO.

Comment: SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 6 IF two or more rods dropped, THEN trip Reactor AND GO TO 3.3.1.a) RNO E0P-0.0A/B.

Standard: At CB-07, PLACED 1/1-RTC, RX TRIP Switch in TRIP and DETERMINED Reactor is NOT tripped.

Comment: SAT UNSAT Perform Step: 7 IF two or more rods dropped, THEN trip Reactor AND GO TO 3.3.1.a) RNO E0P-0.0A/B.

Standard: At CB-10, PLACED 1/1-RT, RX TRIP Switch in TRIP and DETERMINED Reactor is tripped.

Comment: SAT UNSAT Examiner Note: The following steps are from EOP-0.0A.

Perform Step: 8 Verify Reactor Trip:

1, 1.a, & 1st bullet Verify the following: Reactor trip breakers - AT LEAST ONE OPEN Standard: OBSERVED 1/1-RTBAL & 1/1-RTBBL, RX TRIP BKR green OPEN lights LIT.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Verify Reactor Trip:

1, 1.a, & 2nd bullet Verify the following: Neutron flux - DECREASING Standard: OBSERVED 1-NI-35B, IR CURRENT CHAN I and 1-NI-36B, IR CURRENT CHAN II are lowering.

Comment: SAT UNSAT Perform Step: 10 Verify Reactor Trip:

1 & 1.b All control rod position rod bottom lights - ON Standard: OBSERVED all Control Rods INSERTED on CTRL ROD POSN bezel.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2, actions are complete through Step 3.3.15.e.

Control Bank D was last moved in the OUTWARD direction.

Control Rod H8 is ready to be withdrawn.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

RECOVER the dropped Control Rod per ABN-712, Rod Control System Malfunction.

START at Step 3.3.15.f Page 6 of 6 CPNPP NRC 2012 JPM S-1 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-2 Task # RO1305A K/A # 004.A2.02 3.2 / 3.2 SF-2

Title:

Remove Excess Letdown from Service Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Excess Letdown was placed in service following closure of a Normal Letdown Containment Isolation Valve.

• Excess Letdown flow was NOT aligned to the top of the Volume Control Tank.

• A LCOAR was NOT initiated to track Excess Letdown flow.

• Seal Water Heat Exchanger flow does not require any adjustments.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• REMOVE Excess Letdown from Service per SOP-103A, Chemical and Volume Control System, Section 5.5.4, Removing Excess Letdown from Service.

Task Standard: Utilizing SOP-103A, removed Excess Letdown from service and adjusted Reactor Coolant Pump Seal Injection flow.

Required Materials: SOP-103A, Chemical and Volume Control System, Rev. 17-26.

Validation Time: 8 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-37 or any at power Initial Condition and PERFORM the following:

• PLACE Excess Letdown in service.

• ENSURE Excess Letdown NOT ALIGNED to the top of the VCT.

• Adjust VCT Level to 48%.

• ADJUST Seal Water flow to ~ 11.5 GPM to all RCPs.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-103A, Chemical and Volume Control System.

• Section 5.5.4, Removing Excess Letdown from Service.

Page 2 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-103A, Section 5.5.4.

Perform Step: 1 Place handswitch 1/1-8143, XS LTDN DIVERT VLV, in RCDT.

5.5.4.A Standard: PERFORMED the following:

• PLACED 1/1-8143, XS LTDN DIVERT VLV to RCDT (critical).

• OBSERVED red RCDT light LIT (NOT critical).

Examiner Cue:

Comment: SAT UNSAT Perform Step: 2 IF excess letdown/seal water return flow was established to the top of 5.5.4.B the VCT (through the VCT Auxiliary spray nozzle), THEN realign flow to the charging pump suction header:

Standard: DETERMINED from Initial Conditions that Excess Letdown was NOT ALIGNED to the VCT.

Comment: SAT UNSAT Perform Step: 3 CLOSE 1-HC-0123, XS LTDN HX FLO CTRL 5.5.4.C Standard: ROTATED 1-HC-123, XS LTDN HX FLO CTRL potentiometer COUNTERCLOCKWISE to 0% position.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Closing either Excess Letdown Loop Isolation Valve meets the Critical Step requirements. Steps 4 and 5 may be performed in any order.

Perform Step: 4 CLOSE the loop isolation valves to the excess letdown heat exchanger.

ST 5.5.4.D & 1 bullet

• 1/1-8153, XS LTDN ISOL VLV Standard: PERFORMED the following:

• PLACED 1/1-8153, XS LTDN ISOL VLV in CLOSE (critical).

• OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 5 CLOSE the loop isolation valves to the excess letdown heat exchanger.

5.5.4.D & 2nd bullet

• 1/1-8154, XS LTDN ISOL VLV Standard: PERFORMED the following:

• PLACED 1/1-8154, XS LTDN ISOL VLV in CLOSE (critical).

• OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Examiner Note: Perform Steps 6 and 7 may be completed in any order.

Perform Step: 6 Ensure the following charging pump suction high point vent valves are 5.5.4.E & 1st bullet OPEN.

• 1-HV-8220, U1 CHRG PMP SUCT HI PNT VNT VLV 8220 Standard: OBSERVED 1-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV red light LIT.

Comment: SAT UNSAT Perform Step: 7 Ensure the following charging pump suction high point vent valves are 5.5.4.E & 2nd bullet OPEN.

• 1-HV-8221, U1 CHRG PMP SUCT HI PNT VNT VLV 8221 Standard: OBSERVED 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV red light LIT.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 IF LCOAR ODA-308-13.1.31-2 was initiated to track Excess Letdown in 5.5.4.F service to the top of the VCT, THEN exit the LCOAR.

Standard: DETERMINED from Initial Conditions that a LCOAR was NOT INITIATED to track Excess Letdown.

Comment: SAT UNSAT Perform Step: 9 Ensure handswitch 1/1-8143, XS LTDN DIVERT VLV, is in VCT.

5.5.4.G Standard: PERFORMED the following:

• PLACED 1/1-8143, XS LTDN DIVERT VLV to VCT.

• OBSERVED red VCT light LIT.

Comment: SAT UNSAT Perform Step: 10 Adjust CCW to the Seal Water Heat Exchanger by throttling 1CC-0341, 5.5.4.H SL WTR 1-01 CCW RET ISOL VLV per TDM-901A. (Letdown heat exchanger valve room).

Standard: DETERMINED step is N/A from Initial Conditions.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 Ensure No. 1 seal injection flow is between 6 and 10 gpm for each RCP.

5.5.4.I

• 1-FI-145, RCP 1 SEAL WTR INJ FLO

• 1-FI-144, RCP 2 SEAL WTR INJ FLO

• 1-FI-143, RCP 3 SEAL WTR INJ FLO

• 1-FI-142, RCP 4 SEAL WTR INJ FLO Standard: ADJUSTED 1-HC-182, RCP SEAL WTR PRESS CTRL and RESTORED No. 1 seal injection flow between 6 and 10 GPM per Reactor Coolant Pump:

• 1-FI-145, RCP 1 SEAL WTR INJ FLO

• 1-FI-144, RCP 2 SEAL WTR INJ FLO

• 1-FI-143, RCP 3 SEAL WTR INJ FLO

• 1-FI-142, RCP 4 SEAL WTR INJ FLO Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Excess Letdown was placed in service following closure of a Normal Letdown Containment Isolation Valve.

• Excess Letdown flow was NOT aligned to the top of the Volume Control Tank.

• A LCOAR was NOT initiated to track Excess Letdown flow.

• Seal Water Heat Exchanger flow does not require any adjustments.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• REMOVE Excess Letdown from Service per SOP-103A, Chemical and Volume Control System, Section 5.5.4, Removing Excess Letdown from Service.

Page 7 of 7 CPNPP NRC 2012 JPM S-2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-3 Task # RO1412 K/A # 025.AA1.02 3.8 / 3.9 SF-4P

Title:

Respond to Shutdown Loss of Coolant Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is in MODE 3 with a boron concentration of 2500 ppm.

• Reactor Coolant System temperature is approximately 358°F.

• Reactor Coolant System pressure is approximately 280 psig.

• Entry into MODE 4 is about to be performed.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• RESPOND to a lowering Pressurizer level per ABN-108, Shutdown Loss of Coolant.

Task Standard: Utilizing ABN-108, responded to a Shutdown Loss of Coolant, isolated Letdown, and secured Pressurizer Heaters.

Required Materials: ABN-108, Shutdown Loss of Coolant, Rev. 4-5.

Validation Time: 12 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-39 and load scenario file LC20 NRC JPM 3, or any at MODE 3 Initial Condition (with plant conditions prior to MODE 4 entry) and PERFORM the following:

• VERIFY Unit is in MODE 3.

• EXECUTE malfunction RC17A, Hot Leg #1 leak at 2000 gpm and LOWER Pressurizer Cold Calibrated Level to less than 30% but greater than 17%.

• DELETE malfunction RC17A.

• LOWER Charging flow to less than Letdown flow.

• RE-EXECUTE malfunction RC17A, Hot Leg #1 leak at 500 gpm.

• ENSURE all Pressurizer Heaters are ON.

• FREEZE Simulator and MAINTAIN until examinee is ready.

• When either Letdown Isolation Valve is closed, DELETE malfunction RC17A.

• ENSURE ALL Pressurizer level indications (HOT & COLD calibrated) are < 30%.

EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-108, Shutdown Loss of Coolant.

Page 2 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-108, Section 2.0.

Perform Step: 1 Verify Reactor Tripped:

2.3.1.a

• Reactor Trip and Bypass breakers - OPEN Standard:

• VERIFIED Reactor Trip and Bypass breakers - OPEN.

Comment: SAT UNSAT Perform Step: 2 Verify Reactor Tripped:

2.3.1.b

• All DRPI Rod Bottom lights - ON Standard: VERIFIED All DRPI Rod Bottom lights - ON.

Comment: SAT UNSAT Perform Step: 3 Verify Charging flow and Letdown Flow Status:

2.3.2.a

• Verify Charging flow - AT DESIRED FLOW RATE AND GREATER THAN LETDOWN FLOW.

Standard: PERFORMED the following:

• OBSERVED 1-FI-132, LTDN FLO at 73 GPM (NOT critical).

• OBSERVED 1-FI-121A, CHRG FLO at 60 GPM (NOT critical).

• DEPRESSED 1-FK-121, CCP FLO CTRL, red OUTPUT ()

pushbutton until Charging flow is greater than Letdown flow (critical).

Comment: SAT UNSAT Perform Step: 4 Verify Charging flow and Letdown Flow Status:

2.3.2.b

• Verify Pressurizer level - GREATER THAN OR EQUAL TO 30%

Standard: OBSERVED Pressurizer level hot calibrated and cold calibrated instruments and DETERMINED Pressurizer level less than 30%.

Comment: SAT UNSAT Page 3 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 5 IF Pressurizer level is decreasing, THEN perform the following:

2.3.2.b RNO Standard: DETERMINED Pressurizer level is lowering and REFERRED to RNO actions.

Comment: SAT UNSAT Examiner Note: Steps 6 through 10 may be performed in any order.

Perform Step: 6 Ensure Letdown isolated:

ST 2.3.2.b.1) RNO 1

• 1/u-8149A, LTDN ORIFICE ISOL VLV (45 GPM) - CLOSED bullet Standard: PLACED 1/1-8149A, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Perform Step: 7 Ensure Letdown isolated:

nd 2.3.2.b.1) RNO 2

• 1/u-8149B, LTDN ORIFICE ISOL VLV (75 GPM) - CLOSED bullet Standard: PLACED 1/1-8149B, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Perform Step: 8 Ensure Letdown isolated:

rd 2.3.2.b.1) RNO 3

• 1/u-8149C, LTDN ORIFICE ISOL VLV (75 GPM) - CLOSED bullet Standard: PLACED 1/1-8149C, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Page 4 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: When either Letdown Isolation Valve is closed, the leak is isolated.

Examiner Note: Closing either Letdown Isolation Valve meets Critical Task requirements.

Perform Step: 9 Ensure Letdown isolated:

2.3.2.b.1) RNO 4th

• 1/u-LCV-459, LTDN ISOL VLV - CLOSED bullet Standard: PLACED 1/1-LCV-459, LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Perform Step: 10 Ensure Letdown isolated:

2.3.2.b.1) RNO 5th

• 1/u-LCV-460, LTDN ISOL VLV - CLOSED bullet Standard: PLACED 1/1-LCV-460, LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Perform Step: 11 Ensure Letdown isolated:

2.3.2.b RNO

• IF LTDN is being supplied by the RHR SYSTEM, THEN CLOSE u-PK-131, LTDN HX OUT PRESS CTRL AND u-HC-128 RHR LTDN FLO CTRL.

Standard: DETERMINED Residual Heat Removal System is NOT in operation.

Comment: SAT UNSAT Examiner Note: Steps 12 and 13 may be performed in any order.

Perform Step: 12 Ensure Excess Letdown isolated:

2.3.2.b.2) RNO 1st

• 1/u-8153, XS LTDN ISOL VLV - CLOSED bullet Standard: VERFIED 1/1-8153, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 13 Ensure Excess Letdown isolated:

2.3.2.b.2) RNO 2nd

• 1/u-8154, XS LTDN ISOL VLV - CLOSED bullet Standard: VERIFIED 1/1-8154, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT Examiner Note: Steps 14 through 17 may be performed in any order.

Perform Step: 14 Ensure PRZR HTRs - OFF st 2.3.2.b.3) RNO 1

• 1/u-PCPR, PRZR HTR GROUP C bullet Standard: PLACED 1/1-PCPR, PRZR HTR GROUP C in OFF.

Comment: SAT UNSAT Perform Step: 15 Ensure PRZR HTRs - OFF 2.3.2.b.3) RNO 2nd

• 1/u-PCPR1, PRZR HTR GROUP A bullet Standard: PLACED 1/1-PCPR1, PRZR HTR GROUP A in OFF.

Comment: SAT UNSAT Perform Step: 16 Ensure PRZR HTRs - OFF rd 2.3.2.b.3) RNO 3

• 1/u-PCPR2, PRZR HTR GROUP B bullet Standard: PLACED 1/1-PCPR2, PRZR HTR GROUP B in OFF.

Comment: SAT UNSAT Perform Step: 17 Ensure PRZR HTRs - OFF 2.3.2.b.3) RNO 4th

• 1/u-PCPR3, PRZR HTR GROUP D bullet Standard: PLACED 1/1-PCPR3, PRZR HTR GROUP D in OFF.

Comment: SAT UNSAT Page 6 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 18 Verify Pressurizer level - STABLE OR INCREASING.

2.3.2.c Standard: DETERMINED Pressurizer level stable or rising.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is in MODE 3 with a boron concentration of 2500 ppm.

• Reactor Coolant System temperature is approximately 358°F.

• Reactor Coolant System pressure is approximately 280 psig.

• Entry into MODE 4 is about to be performed.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• RESPOND to a lowering Pressurizer level per ABN-108, Shutdown Loss of Coolant.

Page 8 of 8 CPNPP NRC 2012 JPM S-3 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-4 Task # RO3301C K/A # 059.A4.10 3.9 / 3.8 SF-4 nd

Title:

Place 2 Main Feedwater Pump in Service Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Main Feedwater Pump A is in service.

Main Feedwater Pump B is running at 2000 rpm.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

PLACE Main Feedwater Pump B in service per IPO-003A, Power Operations, Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

START at Step 5.4.18.

Task Standard: Utilizing IPO-003A, aligned Main Feedwater Pump B and placed in parallel operation with Main Feedwater Pump A.

Required Materials: IPO-003A, Power Operations, Rev. 28-9.

Validation Time: 20 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-40 or any 45% power Initial Condition with the 2nd Feedwater Pump ready to be placed in service and PERFORM the following:

PLACE the Digital Feedwater System (DFS) Summary Screen in service.

ENSURE B MFW Pump is at ~2000 rpm.

ENSURE MFWP Drain Valves 1-HS-2173 and 1-HS-2176 are CLOSED.

EXAMINER:

PROVIDE examinee with a copy of:

IPO-003A, Power Operations.

Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

INITIAL Step 5.4.17.

Page 2 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from IPO-003A, Section 5.4.

Perform Step: 1 Review NOTE prior to Step 5.4.18.

5.4.18 Note Standard: REVIEWED Note at Step 5.4.18.

Comment: SAT UNSAT Perform Step: 2 Verify the following controllers are in AUTO:

st 5.4.18.A & 1 bullet 1-SK-509A, FWP MASTER SPEED CTRL.

Standard: VERIFIED 1-SK-509A, FWPT MASTER SPEED CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT Examiner Note: Steps 3 through 5 may be performed in any order.

Perform Step: 3 Verify the following controllers are in AUTO:

nd 5.4.18.A & 2 bullet 1-SK-509B, FWPT A AUTO SPD CTRL.

Standard: VERIFIED 1-SK-509B, FWPT A AUTO SPD CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT Perform Step: 4 Verify the following controllers are in AUTO:

rd 5.4.18.A & 3 bullet 1-SK-509C, FWPT B AUTO SPD CTRL.

Standard: VERIFIED 1-SK-509C, FWPT B AUTO SPD CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Place the oncoming FWP recirculation valve in MANUAL and open it as 5.4.18.B & 2nd bullet required to obtain 5000 gpm suction flow, or fully open the valve (100%

demand) if 5000 gpm cannot be achieved.

1-FK-2290, SG FW PMP B RECIRC CTRL Standard: PERFORMED the following:

DEPRESSED 1-FK-2290, FWP B RECIRC FLO CTRL amber MAN pushbutton (critical).

OBSERVED amber MAN light LIT and white AUTO light OFF (NOT critical).

DEPRESSED 1-FK-2290, FWP B RECIRC FLO CTRL red OUTPUT pushbutton until 1-FI-2290, FWP B SUCT FLO reads

~5000 GPM or full open (critical).

Comment: SAT UNSAT Examiner Note: Annunciator 1-ALB-6D, Window 1.10 - AVE TAVE - TREF DEV, will alarm because of the increased efficiencies with the B MFWP Recirculation Valve close.

Perform Step: 6 Perform the following steps alternately in controlled, incremental steps 5.4.18.C until the recirc valve for the oncoming FWP is closed.

Adjust speed on the oncoming FWP to approach that of the running FWP while maintaining its speed at or below that of the running FWP.

1-SC-2112B FWPT B MAN SPD CTRL Close down on the oncoming FWP recirc valve as much as possible without decreasing flow for the oncoming FWP below 5000 gpm.

Standard: PERFORMED the following:

PLACED 1-SC-2112B, FWPT B MAN SPD CTRL in SLOW RAISE or FAST RAISE position and OBSERVED 1-SI-2112F, FWPT B SPD rising.

DEPRESSED 1-FK-2290, SG FW PMP B RECIRC FLO CTRL green LOWER pushbutton as necessary to maintain 1-FI-2290, FWP B SUCT FLO at 5000 GPM.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 When the oncoming FWP Recirc Valve indicates closed, place the 5.4.18.D & 2nd bullet controller in AUTO:

1-FK-2290, SG FW PMP B RECIRC CTRL Standard: PERFORMED the following:

DEPRESSED 1-FK-2290, SG FW PMP B RECIRC CTRL white AUTO pushbutton (critical).

OBSERVED white AUTO light LIT and amber MAN light OFF (NOT critical).

Comment: SAT UNSAT Perform Step: 8 When the oncoming FWP FW REF and SPD CMD are approximately 5.4.18.E & 2nd bullet the same on the DFS screen, depress the FWPT SPD CTRL MODE SELECT AUTO pushbutton.

1-HS-2112B, FWPT B SPD CTRL MODE SELECT - AUTO Standard: PERFORMED the following:

DEPRESSED 1-HS-2112B, FWPT B SPD CTRL MODE SELECT black AUTO pushbutton (critical).

OBSERVED white AUTO light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 9 Adjust the FWPT AUTO SPD CTRL Pots as required to balance load 5.4.18.F & 2nd bullet and flow.

1-SK-509C, FWPT B AUTO SPD CTRL Standard: As required, ADJUSTED POT Setpoint on 1-SK-509C, FWPT B AUTO SPD CTRL to balance both Main Feedwater Pump flows.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Main Feedwater Pump A is in service.

Main Feedwater Pump B is running at 2000 rpm.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

PLACE Main Feedwater Pump B in service per IPO-003A, Power Operations, Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

START at Step 5.4.18.

Page 6 of 6 CPNPP NRC 2012 JPM S-4 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-5 Task # RO2002B K/A # 026.A4.01 4.5 / 4.3 SF-5

Title:

Transfer Containment Spray From Injection to Recirculation Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical: X READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Large Break LOCA has occurred.

EOS-1.3A, Transfer to Cold Leg Recirculation, is in progress.

Refueling Water Storage Tank level is LESS THAN 6%.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

TRANSFER Containment Spray to the Containment Sumps per EOS-1.3A, Transfer to Cold Leg Recirculation.

PERFORM Attachment 1.H, Containment Spray Switchover Criterion.

Task Standard: Utilizing EOS-1.3A, transferred Containment Spray from the Injection Mode to the Recirculation Mode from the Containment Sumps within 70 seconds.

Required Materials: EOS-1.3A, Transfer to Cold Leg Recirculation, Rev. 8-3.

Time Critical: 70 seconds Completion Time: ________ seconds Validation Time: 2 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC #36 and or any Post LOCA with RHR Swapover completed IC.

If IC #36 is not available, RESET to any at power IC and PERFORM the following:

INSERT malfunction RC08A2 (or equivalent LB LOCA).

PLACE Simulator in RUN.

REDUCE AFW Flow to all SGs.

RESET SI, SIS, Containment and Isolation Phases A & B and Containment Spray.

STOP both Emergency Diesel Generators.

STOP all Reactor Coolant Pumps.

When RWST level reaches LO-LO level, TRANSFER ECCS to Cold Leg Recirculation by performing Steps 1-3 of EOS-1.3A.

FREEZE simulator when RWST level is LESS THAN 6%.

EXAMINER:

PROVIDE the examinee with a copy of:

EOS-1.3A, Transfer to Cold Leg Recirculation.

Attachment 1.H, Containment Spray Switchover Criterion.

Page 2 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step CRITICAL START TIME:

Examiner Note: The following steps are from EOS-1.3, Attachment 1.H.

Examiner Cue: INFORM examinee to review the procedure prior to starting. When preparations are completed the JPM will begin.

Examiner Note: After the examinee signals they are ready to begin, CUE the Booth Operator to PLACE the Simulator in RUN.

Perform Step: 1 Check RWST level - LESS THAN 6%.

4.a.

Standard: OBSERVED 1-LI-930, RWST LVL CHAN 1 or 1-LI-931, RWST LVL CHAN 2 and VERIFY level is less than 6%.

Standard:

Comment: SAT UNSAT Examiner Note: Steps 2 and 3 may be performed in any order or simultaneously.

Perform Step: 2 Realign Containment Spray System as follows:

4.b.1) & 1st bullet Open CNTMT SMP TO CSP 1 & 3 AND 2 & 4 SUCT ISOL VLVs:

1-HS-4782 Standard: PERFORMED the following:

PLACED 1-HS-4782, CNTMT SMP TO CSP 1 & 3 to OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 3 Realign Containment Spray System as follows:

nd 4.b.1) & 2 bullet Open CNTMT SMP TO CSP 1 & 3 AND 2 & 4 SUCT ISOL VLVs:

1-HS-4783 Standard: PERFORMED the following:

PLACED 1-HS-4783, CNTMT SMP TO CSP 2 & 4 to OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Steps 4 and 5 may be performed in any order or simultaneously.

Perform Step: 4 Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs:

4.b.2) & 1st bullet 1-HS-4758 Standard: PERFORMED the following:

PLACED 1-HS-4758, RWST TO CSP 1 & 3 to CLOSE (critical).

OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 5 Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs:

nd 4.b.2) & 2 bullet 1-HS-4759 Standard: PERFORMED the following:

PLACED 1-HS-4759, RWST TO CSP 2 & 4 to CLOSE (critical).

OBSERVED green CLOSE light LIT (NOT critical).

Examiner Note: Steps 1 through 6 must be performed within 70 seconds.

Comment: SAT UNSAT CRITICAL STOP TIME:

Perform Step: 6 IF containment spray pumps have been stopped due to RWST level, 4.b.3) THEN perform the following:

Standard: DETERMINED Containment Spray Pumps were NOT stopped due to low RWST Level.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Verify containment spray flows.

4.b.4)

Standard: OBSERVED Containment Spray flows on:

1-FI-4772-1, CSP 1 DISCH FLO at ~3700 GPM.

1-FI-4773-1, CSP 2 DISCH FLO at ~3700 GPM.

1-FI-4772-2, CSP 3 DISCH FLO at ~3700 GPM.

1-FI-4773-2, CSP 4 DISCH FLO at ~3700 GPM.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Large Break LOCA has occurred.

EOS-1.3A, Transfer to Cold Leg Recirculation, is in progress.

Refueling Water Storage Tank level is LESS THAN 6%.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

TRANSFER Containment Spray to the Containment Sumps per EOS-1.3A, Transfer to Cold Leg Recirculation.

PERFORM Attachment 1.H, Containment Spray Switchover Criterion.

TIME CRITICAL JPM Page 6 of 6 CPNPP NRC 2012 JPM S-5 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-6 Task # RO4201 K/A # 062.A4.07 3.1 / 3.1 SF-6

Title:

Shift Normal Bus 1A4 Between Unit Auxiliary Transformer and Startup Transformer Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is at 100% power.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• SHIFT Normal Bus 1A4 between the Unit Auxiliary Transformer and the Startup Transformer per SOP-603A, 6900 V Switchgear, Step 5.3.2, Transferring a 6.9 KV Normal Bus from Unit 1 Auxiliary Transformer 1UT to Station Service Transformer 1ST.

Task Standard: Utilizing SOP-603A, shifted Normal Bus 1A4 between the Unit Auxiliary Transformer and the Station Service Transformer and manually opened Incoming Breaker 1A4-1.

Required Materials: SOP-603A, 6900 V Switchgear, Rev. 14-9.

ALM-0102A, 1-ALB-10B, Window 3.4 - 6.9 KV ANY NON-1E BUS PARALLELED, Rev. 11-4.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-18 or any at power Initial Condition and PERFORM the following:

• When directed, EXECUTE malfunction ED20L, Breaker 1A4-2 interlock failure.

BOOTH OPERATOR NOTE:

• After each JPM, PERFORM the following:

• MOVE the Synchroscope Switch to an alternate 6900 V Bus position.

• PLACE VS-1A, 6.9 KV BUS VOLT / FREQ SELECT switch in the 1A1 position.

EXAMINER:

PROVIDE the examinee with a copy of Procedure 1:

• SOP-603A, 6900 V Switchgear.

• Step 5.3.2, Transferring a 6.9 KV Normal Bus from Unit 1 Auxiliary Transformer 1UT to Station Service Transformer 1ST.

Page 2 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-603A, Step 5.3.2.

Perform Step: 1 Ensure the prerequisites in Section 2.3 are met for the selected bus.

th 5.3.2.A & 4 bullet

• 6.9 KV SWITCHGEAR 1A4 Standard: DETERMINED Station Service Transformer 1ST is at ~350 KV by OBSERVING V/ST2/1ST, INCOMING 345 KV XFMR FDR VOLT.

Comment: SAT UNSAT Perform Step: 2 Turn synchroscope ON for the selected Bus Feeder Breaker AND 5.3.2.B & 4th bullet ensure proper phasing and frequency.

• SS-1A4-2, BKR 1A4-2 SYNCHROSCOPE Standard: PLACED synchroscope switch into SS-1A4-2, BKR 1A4-2 SYNCHROSCOPE position and TURNED to ON and OBSERVED proper phasing and frequency.

Examiner Note: Synchroscope is at 12 oclock without movement.

Comment: SAT UNSAT Perform Step: 3 Close the incoming breaker from Station Service Transformer 1ST to the th 5.3.2.C & 4 bullet desired bus.

• CS-1A4-2, INCOMING BKR 1A4-2 Standard: PLACED CS-1A4-2, INCOMING BKR 1A4-2 in CLOSE and OBSERVED red CLOSE light lit.

Comment: SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 4 Ensure the feeder breaker from Unit Auxiliary Transformer 1UT to the 5.3.2.D & 4th bullet bus being transferred trips open.

• CS-1A4-1, INCOMING BKR 1A4-1 Standard: OBSERVED CS-1A4-1, INCOMING BKR 1A4-1 red CLOSE light lit and DETERMINED breaker did NOT OPEN.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following NOTE is from 1-ALB-10B, Window 3.4.

Perform Step: 5 Acknowledge annunciator alarm.

Standard: ACKNOWLEDGED annunciator alarm 1-ALB-10B, Window 3.4 - 6.9 KV ANY NON-1E BUS PARALLELED.

Comment: SAT UNSAT Perform Step: 6 Ensure the feeder breaker from Unit Auxiliary Transformer 1UT to the 5.3.2.D & 4th bullet bus being transferred trips open.

• CS-1A4-1, INCOMING BKR 1A4-1 Standard: PLACED CS-1A4-1, INCOMING BKR 1A4-1 in TRIP and OBSERVED green TRIP light lit.

Comment: SAT UNSAT Perform Step: 7 Check transferred bus voltage normal by performing the following:

5.3.2.E & 5.3.2.E.1)

• Position VS-1A, 6.9 KV BUS VOLT/FREQ SELECT to the desired bus.

Standard: PLACED VS-1A, 6.9 KV BUS VOLT/FREQ SELECT to BUS 1A4 position.

Comment: SAT UNSAT Perform Step: 8 Check transferred bus voltage normal by performing the following:

5.3.2.E & 5.3.2.E.2)

• Verify V-1A, 6.9 KV NON-SFGD BUS VOLT approximately 6900 VOLTS, for the selected bus (6450-7150 volts required).

Standard: OBSERVED V-1A, 6.9 KV NON-SFGD BUS VOLT approximately 6900 volts for BUS 1A4.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Match handswitch target by placing the selected breaker, for the bus 5.3.2.F & 4th bullet transferred, in NEUTRAL-AFTER-TRIP.

• CS-1A4-1, INCOMING BKR 1A4-1 Standard: DETERMINED CS-1A4-1, INCOMING BKR 1A4-1 is in NEUTRAL-AFTER-TRIP position with green FLAG indicating.

Comment: SAT UNSAT Perform Step: 10 Turn synchroscope OFF for the selected breaker.

5.3.2.G & 4th bullet

• SS-1A4-2, BKR 1A4-2 SYNCHROSCOPE Standard: TURNED SS-1A4-2, BKR 1A4-2 SYNCHROSCOPE to OFF.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is at 100% power.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• SHIFT Normal Bus 1A4 between the Unit Auxiliary Transformer and the Startup Transformer per SOP-603A, 6900 V Switchgear, Step 5.3.2, Transferring a 6.9 KV Normal Bus from Unit 1 Auxiliary Transformer 1UT to Station Service Transformer 1ST.

Page 6 of 6 CPNPP NRC 2012 JPM S-6 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-7 Task # RO4103A K/A # 073.A4.02 3.7 / 3.7 SF-7

Title:

Respond to Control Room Ventilation Radiation Alarms Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• The Unit is at 100% power with no evolutions in progress.

• CRV053 and CRV054 are in alarm on the PC-11, Digital Radiation Monitoring System.

• Unit 2 has been notified of ABN-902, Release of Radioactive/Toxic Gas, Section 2.0 entry.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• RESPOND to PC-11, Digital Radiation Monitoring System alarms per ABN-902, Release of Radioactive/Toxic Gas.

Task Standard: Utilizing ABN-902, identified failure of the Control Room Ventilation System alignment. Utilizing SOP-802, manually aligned the Control Room Ventilation System for Emergency Recirculation operation.

Required Materials: ABN-902, Release of Radioactive/Toxic Gas, Rev. 7.

SOP-802, Control Room Ventilation System, Rev. 13.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-35 and load scenario file LC20 NRC JPM 6, 7, or any 100% power IC and PERFORM the following:

• INSERT malfunction RM03C1, Process Radiation Monitor X-RE-5895A/CVR04 @ 1.5 x 10-4.

• INSERT malfunction RM03C2, Process Radiation Monitor X-RE-5895B/CVR05 @ 1.5 x 10-4.

• INSERT remote function RMR02, RM-80 Actuations to OFF.

EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-902, Release of Radioactive/Toxic Gas, Section 2.0, Release of Radioactive Gas.

When required, PROVIDE the examinee with a copy of:

• SOP-802, Control Room Ventilation System, Section 5.3.2, Emergency Recirculation Manual Initiation.

Page 2 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-902, Section 2.0.

Perform Step: 1 Verify Containment air radiation alarms - CLEAR:

2.3.1.a

• CAPu98 (u-RE-5502), CNTMT AIR PIG PART

• CAGu97 (u-RE-5503), CNTMT AIR PIG GAS Standard: OBSERVED PC-11 and DETERMINED the following:

• CAP198 (1-RE-5502), CNTMT AIR PIG PART is NOT in alarm.

• CAP197 (1-RE-5503), CNTMT AIR PIG GAS is NOT in alarm.

Comment: SAT UNSAT Perform Step: 2 Verify the following radiation alarms - CLEAR:

2.3.1.b

• PVF684 (X-RE-5570A), S. WRGM EFFLUENT

• PVF685 (X-RE-5570B), N. WRGM EFFLUENT

• ABV089 (X-RE-5701), AUX BLDG VENT DUCT Standard: OBSERVED PC-11 and DETERMINED the following:

• PVF684 (X-RE-5570A), S. WRGM EFFLUENT is NOT in alarm.

• PVF685 (X-RE-5570B), N. WRGM EFFLUENT is NOT in alarm.

• ABV089 (X-RE-5701), AUX BLDG VENT DUCT is NOT in alarm.

Comment: SAT UNSAT Perform Step: 3 Verify the following radiation alarms - CLEAR:

2.3.1.c

• CRV053 (X-RE-5895A), CR HVAC, N VENT

• CRV054 (X-RE-5895B), CR HVAC, N VENT

• CRV091 (X-RE-5896A), CR HVAC, S VENT INTK

• CRV092 (X-RE-5896B), CR HVAC, S VENT Standard: OBSERVED PC-11 and DETERMINED the following:

• CRV053 (X-RE-5895A), CR HVAC, N VENT is in HIGH alarm.

• CRV054 (X-RE-5895B), CR HVAC, N VENT is in HIGH alarm.

Comment: SAT UNSAT Page 3 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Perform the following:

2.3.1.c RNO c.1)

• Ensure Emergency Recirculation Automatic Initiation has occurred (X-ZL-5877A/B, CR EMER RECIRC).

Standard: DETERMINED Control Room Ventilation did NOT shift to the Emergency Recirculation Mode and OBSERVED the following on Panel CV-03:

• X-ZL-5877A & X-ZL-5877B, CR EMER RECIRC, red lights DARK.

• X-ZL-5878A & X-ZL-5878B, CR NORM VENT, white lights LIT.

Comment: SAT UNSAT Perform Step: 5 Perform the following:

2.3.1.c RNO c.2)

• Manually initiate Emergency Recirculation per SOP-802.

Standard: REFERRED to SOP-802, Control Room Ventilation System, Section 5.3.2, Emergency Recirculation Manual Initiation.

Comment: SAT UNSAT Examiner Note: The following steps are from SOP-802, Section 5.3.2.

Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 6 VERIFY outside ambient air temperature is between 20°F to 110°F.

5.3.2.A Standard: DETERMINED outside ambient air temperature is approximately 83°F as read on X-UR-4115 Meteorological Tower indication.

Examiner Cue: Another operator is tracking runtimes per OPT-115, Charcoal Adsorber Runtime Monitoring.

Comment: SAT UNSAT Page 4 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 PLACE handswitch X-HS-5877, EMER RECIRC MAN ACT in ACTUATE 5.3.2.B & 5.3.2.B.1) AND VERIFY the following occur.

• The Pressurization and Filtration Unit fans have started AND the associated inlet dampers have opened.

Standard: PERFORMED the following:

• PLACED X-HS-5877, EMER RECIRC MAN ACT handswitch in ACT position (critical).

• OBSERVED Train A X-HS-5831A, CR EMER PRZN FN 5 (X-HV-5831 on X-HS-5831D) red light LIT (NOT critical).

• OBSERVED Train A X-HS-5845, CR EMER FILT FN 23 & FILT IN DMPR 41 (X-HV-5839) red FAN and DAMPER lights LIT (NOT critical).

• OBSERVED Train B X-HS-5834A, CR EMER PRZN FN 6 (X-HV-5834 on X-HS-5834D) red light LIT (NOT critical).

• OBSERVED Train B X-HS-5846, CR EMER FILT FN 24 & FILT IN DMPR 42 (X-HV-5840) red FAN and DAMPER lights LIT (NOT critical).

Comment: SAT UNSAT Page 5 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 PLACE handswitch X-HS-5877, EMER RECIRC MAN ACT in ACTUATE 5.3.2.B & 5.3.2.B.2) AND VERIFY the following occur.

• The operating supply and exhaust fans have stopped.

Standard: VERIFIED Supply and Exhaust Fans have STOPPED:

• OBSERVED X-HS-5825A, CR MU AIR SPLY FN 37 & SUCT DMPR 16 (X-HV-5825A) green DAMPER and FAN lights LIT.

• OBSERVED X-HS-5828A, CR MU AIR SPLY FN 38 & SUCT DMPR 19 (X-HV-5828A) green DAMPER and FAN lights LIT.

• OBSERVED X-HS-5855, CR EXH FN 1 (X-PV-5855 on X-HS-5855A) green light LIT.

• OBSERVED X-HS-5856, CR EXH FN 2 (X-PV-5856 on X-HS-5856A) green light LIT.

• OBSERVED X-HS-5857, CR KTCHN & TOIL EXH FN 3 & SUCT DMPR 27 (X-HV-5857) green DAMPER and FAN lights LIT.

• OBSERVED X-HS-5858, CR KTCHN & TOIL EXH FN 4 & SUCT DMPR 28 (X-HV-5858) green DAMPER and FAN lights LIT.

Comment: SAT UNSAT Perform Step: 9 PERFORM the following steps to shift to single train operation.

5.3.2.C Standard: DETERMINED single train operation is required.

Examiner Cue: The Unit Supervisor directs you to shift to single Train A operation.

Comment: SAT UNSAT Perform Step: 10 Momentarily PLACE the reset switch in RESET for the train to be 5.3.2.D shutdown.

Standard: PERFORMED the following:

• PLACED Train B X-HS-5877B, EMER RECIRC RESET switch to RESET position (critical).

• OBSERVED Train B red X-ZL-5877B light DARK and white X-ZL-5878B CR NORM VENT light LIT (NOT critical).

Comment: SAT UNSAT Page 6 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Cue: Two minutes have passed.

Perform Step: 11 After approximately 1 to 3 minutes, STOP the selected operating 5.3.2.E for Train B 1st Emergency Filtration and Pressurization Unit fans AND ENSURE the bullet handswitches are in AUTO with the associated inlet damper closed.

• X-HS-5834A, CR EMER PRZN FN 6 Standard: PERFORMED the following after 1 to 3 minutes:

• TURNED Train B X-HS-5834A, CR EMER PRZN FN 6 (X-HV-5834 on X-HS-5834D) switch to STOP (critical).

• OBSERVED green STOP light LIT (NOT critical).

• RELEASED switch to AUTO (critical).

Comment: SAT UNSAT Perform Step: 12 After approximately 1 to 3 minutes, STOP the selected operating 5.3.2.E for Train B 2nd Emergency Filtration and Pressurization Unit fans AND ENSURE the bullet handswitches are in AUTO with the associated inlet damper closed.

• X-HS-5846, CR EMER FILT FN 24 & FILT IN DMPR 42 Standard: PERFORMED the following after 1 to 3 minutes:

• TURNED Train B X-HS-5846, CR EMER FILT FN 24 & FILT IN DMPR 42 (X-HV-5840) switch to STOP (critical).

• OBSERVED green DAMPER and FAN lights LIT (NOT critical).

• RELEASED switch to AUTO (critical).

Comment: SAT UNSAT Page 7 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Train B Air Conditioning Fans #2 & #4 are verified shutdown.

Perform Step: 13 ENSURE air conditioning units NOT required are shutdown AND nd th 5.3.2.F, 2 & 4 VERIFY the associated suction damper is closed.

bullets

• X-HS-5851A, CR A/C FN 2 & SUCT DMPR 10 (X-HV-5851)

• X-HS-5853A, CR A/C FN 4 & SUCT DMPR 12 (X-HV-5853)

Standard: PERFORMED the following:

• OBSERVED X-HS-5851A, CR A/C FN 2 & SUCT DMPR 10 (X-HV-5851) green DAMPER and FAN STOP lights LIT.

• OBSERVED X-HS-5853A, CR A/C FN 4 & SUCT DMPR 12 (X-HV-5853) green DAMPER and FAN STOP lights LIT.

Comment: SAT UNSAT Perform Step: 14 ENSURE power supply breakers for the following fans are ON (manually 5.3.2.G reset breakers, as required):

• 480V MCC XEB1-1 (AB 852')

• 480V MCC XEB2-1 (ECB 854')

Standard: CONTACTED a Nuclear Equipment Operator to ENSURE breakers are ON.

Examiner Cue: Another operator will perform Step 5.3.2.G.

Comment: SAT UNSAT Perform Step: 15 VERIFY X-ALB-13A, 4.3, CR EMER PRZN ANY SPLY FN/HTR TRIP is 5.3.2.H dark.

Standard: DETERMINED Annunciator X-ALB-13A, Window 4.3 - CR EMER PRZN ANY SPLY FN/HTR TRIP, is DARK.

Comment: SAT UNSAT Page 8 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 16 CLOSE the intake damper for the shutdown train:

5.3.2.I

• X-HS-5838A, CR S INTK DMPR 15 (TRN B)

Standard: PERFORMED the following:

• PLACED Train B X-HS-5838A, CR S. INTK DMPR 15 switch to CLOSE (critical).

• OBSERVED green CLOSE light LIT (NOT critical).

Terminating Cue: Another operator will verify proper train operation by observing light indication of Attachment 4. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 9 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• The Unit is at 100% power with no evolutions in progress.

• CRV053 and CRV054 are in alarm on the PC-11, Digital Radiation Monitoring System.

• Unit 2 has been notified of ABN-902, Release of Radioactive/Toxic Gas, Section 2.0 entry.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• RESPOND to the PC-11 alarms per ABN-902, Release of Radioactive/Toxic Gas.

Page 10 of 10 CPNPP NRC 2012 JPM S-7 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-8 Task # RO3603A K/A # 008.A2.01 3.3 / 3.6 SF-8

Title:

Rotate Component Cooling Water Pumps Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is in MODE 1.

• Biweekly rotation of the Component Cooling Water Pumps is required per OWI-409, Equipment Rotation Program.

• A Nuclear Equipment Operator (NEO) is standing by for pump start.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• SHIFT from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System.

• START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

• CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Task Standard: Utilizing SOP-502A, transferred from Train A to Train B Component Cooling Water System. Utilizing ABN-502, restored Component Cooling Water System flow using the Train A Component Cooling Water System.

Required Materials: SOP-502A, Component Cooling Water System, Rev. 18-12.

ABN-502, Component Cooling Water System Malfunctions, Rev. 6-11.

Validation Time: 16 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

EXECUTE IC-40 or any at power Initial Condition and load scenario file LC20 NRC JPM 4, 8 and PERFORM the following:

• EXECUTE malfunction CC03B, CCW Train B Loop pressure switch failure.

• INSERT malfunction CC02B on a conditional so that 10 seconds after CCW Pump 1-01 is stopped, malfunction is executed to trip CCW Pump 1-02.

• SET UP Plant Computer screen to monitor CCW Pump temperatures.

• INSERT malfunction RP13C, Manual Reactor Trip Failure at CB-07 and CB-10 to prevent examinee from tripping Reactor.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-502A, Component Cooling Water System.

• Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation.

• Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation.

When located or requested, PROVIDE the examinee with a copy of:

• ABN-502, Component Cooling Water System Malfunctions.

Page 2 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-502A, Step 5.2.1.1.

Perform Step: 1 Ensure the Station Service Water Pump, associated with the CCW 5.2.1.1.A Pump to be started is operating.

• SSWP 2 Standard: DETERMINED SSWP 2, Station Service Water Pump is running and OBSERVED red PUMP light LIT.

Comment: SAT UNSAT Perform Step: 2 Ensure the oil level in the bearing housings are normal.

5.2.1.1.B

• CCWP 2 Standard: DISPATCHED NEO to verify oil levels for CCWP 2.

Examiner Cue: The NEO reports that bearing housing oil levels are normal.

Comment: SAT UNSAT Page 3 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Critical action is to establish sufficient flow to lower CCW Pump discharge pressure during two pump operation.

Perform Step: 3 IF CCW heat load is low, THEN additional CCW flow should be 5.2.1.1.C established through the CS HX or RHR HX prior to starting the second pump.

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• PLACED 1-HS-4574, CS HX 1 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4572, RHR HX 1 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4575, CS HX 2 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4573, RHR HX 2 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 4 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step:4 Start the idle CCW Pump.

5.2.1.1.D

• 1-HS-4519A, CCWP 2 Standard: PERFORMED the following:

• PLACED 1-HS-4519A, CCWP 2 to START (critical).

• OBSERVED red FAN and PUMP lights LIT (NOT critical).

• OBSERVED 1-PI-4521, CCWP2 DISCH PRESS rising (NOT critical).

• OBSERVE 1-FI-4537A, CCW HX 2 OUT FLO rising (NOT critical).

Comment: SAT UNSAT Page 5 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Expected action is to momentarily establish flow through all four heat exchangers during the transfer.

Flow may have previously been established through any/all of these heat exchangers.

Perform Step: 5 IF the CCW PUMPS are being alternated for their bi-weekly rotation per 5.2.1.1.E OWI-409 EQUIPMENT ROTATION PROGRAM, THEN momentarily initiate flow through each RHR and CS heat exchanger while BOTH pumps are in service.

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• Momentarily OPENED then CLOSED 1-HS-4574, CS HX 1 CCW RET VLV and OBSERVED 1-FI-4560, CS HX 1 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4572, RHR HX 1 CCW RET VLV and OBSERVED 1-FI-4556, RHR HX 1 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4575, CS HX 2 CCW RET VLV and OBSERVED 1-FI-4562, CS HX 2 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4573, RHR HX 2 CCW RET VLV and OBSERVED 1-FI-4558, RHR HX 2 CCW RET FLO rising.

Comment: SAT UNSAT Page 6 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from SOP-502A, Step 5.2.1.2.

Perform Step: 6 IF the safeguards loops are not cross-connected, THEN ensure the 5.2.1.2.A & B following equipment for the pump to be stopped has been removed from service:

Standard: DETERMINED the Safeguards Loops ARE cross-connected and N/A.

Comment: SAT UNSAT Perform Step: 7 IF additional flow was established for two pump operation AND is not 5.2.1.2.C.1) required, THEN throttle the following valve(s) as necessary such that CCWP DISCHARGE PRESSURE is approximately 140 to 150 psig as indicated on 1-PI-4520 and 1-PI-4521. (MCB)

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• OBSERVED 1-PI-4520, CCWP1 DISCH PRESS approximately 140 to 150 PSIG.

• OBSERVED 1-PI-4521, CCWP2 DISCH PRESS approximately 140 to 150 PSIG.

Comment: SAT UNSAT Page 7 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Stop the desired CCW Pump AND hold the handswitch in STOP.

5.2.1.2.C.2)

• 1-HS-4518A, CCWP 1 Standard: PERFORMED the following:

• PLACED and HELD 1-HS-4518A, CCWP 1 in STOP (critical).

• OBSERVED green PUMP and red FAN lights LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 9 WHEN CCW flow and pressure stabilize, THEN release the CCW Pump 5.2.1.2.C.3) handswitch.

Standard: RELEASED 1-HS-4518A, CCWP 1 handswitch when CCW flow and pressure stabilized.

Comment: SAT UNSAT Perform Step: 10 Ensure BOTH CCW Pump handswitches are in AUTO:

5.2.1.2.D

• 1-HS-4518A, CCWP 1

• 1-HS-4519A, CCWP 2 Standard: VERIFIED 1-HS-4518A, CCWP 1 and 1-HS-4519A, CCWP 2 handswitches are in AUTO.

Comment: SAT UNSAT Examiner Note: ABN-502, CCW System Malfunctions, may be referred to for guidance upon CCW Pump trip. ODA-102, Conduct of Operations, allows for immediate pump start.

Examiner Note: Examinee may attempt to trip Reactor per ABN-502, Section 6.0, Loss of all CCW Flow, however, they should refer to ABN-502, Section 2.0, CCW Pump Trip, and attempt to start CCWP 1-01.

Examiner Note: The following steps are from ABN-502, Section 2.0.

Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 11 Verify unaffected train CCW pump - RUNNING

2.3.1 Standard

DETERMINED Train A CCW Pump NOT Running.

Comment: SAT UNSAT Page 8 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 Manually start the CCW Pump in the unaffected train. IF the pump fails 2.3.1 RNO to start, THEN GO TO Section 6.0 of this procedure.

Standard: PERFORMED the following:

• PLACED 1-HS-4518A, CCWP 1 to START (critical).

• OBSERVED red FAN and PUMP lights LIT (NOT critical).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 9 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is in MODE 1.

• Biweekly rotation of the Component Cooling Water Pumps is required per OWI-409, Equipment Rotation Program.

• A Nuclear Equipment Operator (NEO) is standing by for pump start.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• SHIFT from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System.

• START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

• CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Page 10 of 10 CPNPP NRC 2012 JPM S-8 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-8.a Task # RO3603A K/A # 008.A2.01 3.3 / 3.6 SF-8

Title:

Rotate Component Cooling Water Pumps Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is in MODE 1.

• Biweekly rotation of the Component Cooling Water Pumps is required per OWI-409, Equipment Rotation Program.

• A Nuclear Equipment Operator (NEO) is standing by for pump start.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• SHIFT from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System.

• START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

• CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Task Standard: Utilizing SOP-502A, transferred from Train A to Train B Component Cooling Water System. Utilizing ABN-502, restored Component Cooling Water System flow using the Train A Component Cooling Water System.

Required Materials: SOP-502A, Component Cooling Water System, Rev. 18-12.

ABN-502, Component Cooling Water System Malfunctions, Rev. 6-11.

Validation Time: 16 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

EXECUTE IC-18 or any at power Initial Condition and load scenario file LC20 NRC JPM 4, 8 and PERFORM the following:

• EXECUTE malfunction CC03B, CCW Train B Loop pressure switch failure.

• INSERT malfunction CC02B to trip CCW Pump 1-02 after CCW Pump 1-02 is running.

• SET UP Plant Computer screen to monitor CCW Pump temperatures.

• INSERT malfunction RP13C, Manual Reactor Trip Failure at CB-07 and CB-10 to prevent examinee from tripping Reactor.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-502A, Component Cooling Water System.

• Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation.

• Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation.

When located or requested, PROVIDE the examinee with a copy of:

• ABN-502, Component Cooling Water System Malfunctions.

Page 2 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-502A, Step 5.2.1.1.

Perform Step: 1 Ensure the Station Service Water Pump, associated with the CCW 5.2.1.1.A Pump to be started is operating.

• SSWP 2 Standard: DETERMINED SSWP 2, Station Service Water Pump is running and OBSERVED red PUMP light LIT.

Comment: SAT UNSAT Perform Step: 2 Ensure the oil level in the bearing housings are normal.

5.2.1.1.B

• CCWP 2 Standard: DISPATCHED NEO to verify oil levels for CCWP 2.

Examiner Cue: The NEO reports that bearing housing oil levels are normal.

Comment: SAT UNSAT Page 3 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Critical action is to establish sufficient flow to lower CCW Pump discharge pressure during two pump operation.

Perform Step: 3 IF CCW heat load is low, THEN additional CCW flow should be 5.2.1.1.C established through the CS HX or RHR HX prior to starting the second pump.

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• PLACED 1-HS-4574, CS HX 1 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4572, RHR HX 1 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4575, CS HX 2 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

and/or

• PLACED 1-HS-4573, RHR HX 2 CCW RET VLV in OPEN (critical).

• OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 4 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step:4 Start the idle CCW Pump.

5.2.1.1.D

• 1-HS-4519A, CCWP 2 Standard: PERFORMED the following:

• PLACED 1-HS-4519A, CCWP 2 to START (critical).

• OBSERVED red FAN and PUMP lights LIT (NOT critical).

• OBSERVED 1-PI-4521, CCWP2 DISCH PRESS rising (NOT critical).

• OBSERVE 1-FI-4537A, CCW HX 2 OUT FLO rising (NOT critical).

Comment: SAT UNSAT Page 5 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Expected action is to momentarily establish flow through all four heat exchangers during the transfer.

Flow may have previously been established through any/all of these heat exchangers.

Perform Step: 5 IF the CCW PUMPS are being alternated for their bi-weekly rotation per 5.2.1.1.E OWI-409 EQUIPMENT ROTATION PROGRAM, THEN momentarily initiate flow through each RHR and CS heat exchanger while BOTH pumps are in service.

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• Momentarily OPENED then CLOSED 1-HS-4574, CS HX 1 CCW RET VLV and OBSERVED 1-FI-4560, CS HX 1 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4572, RHR HX 1 CCW RET VLV and OBSERVED 1-FI-4556, RHR HX 1 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4575, CS HX 2 CCW RET VLV and OBSERVED 1-FI-4562, CS HX 2 CCW RET FLO rising.

• Momentarily OPENED then CLOSED 1-HS-4573, RHR HX 2 CCW RET VLV and OBSERVED 1-FI-4558, RHR HX 2 CCW RET FLO rising.

Comment: SAT UNSAT Page 6 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from SOP-502A, Step 5.2.1.2.

Perform Step: 6 IF the safeguards loops are not cross-connected, THEN ensure the 5.2.1.2.A & B following equipment for the pump to be stopped has been removed from service:

Standard: DETERMINED the Safeguards Loops ARE cross-connected and N/A.

Comment: SAT UNSAT Perform Step: 7 IF additional flow was established for two pump operation AND is not 5.2.1.2.C.1) required, THEN throttle the following valve(s) as necessary such that CCWP DISCHARGE PRESSURE is approximately 140 to 150 psig as indicated on 1-PI-4520 and 1-PI-4521. (MCB)

TRAIN A

• 1-HS-4574, CS HX 1 CCW RET VLV

• 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B

• 1-HS-4575, CS HX 2 CCW RET VLV

• 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

• OBSERVED 1-PI-4520, CCWP1 DISCH PRESS approximately 140 to 150 PSIG.

• OBSERVED 1-PI-4521, CCWP2 DISCH PRESS approximately 140 to 150 PSIG.

Comment: SAT UNSAT Page 7 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: ABN-502, CCW System Malfunctions, may be referred to for guidance upon CCW Pump trip. ODA-102, Conduct of Operations, allows for immediate pump start.

Examiner Note: Examinee may attempt to trip Reactor per ABN-502, Section 6.0, Loss of all CCW Flow, however, they should refer to ABN-502, Section 2.0, CCW Pump Trip.

Examiner Note: The following steps are from ABN-502, Section 2.0.

Perform Step: 8 Verify unaffected train CCW pump - RUNNING

2.3.1 Standard

DETERMINED Train A CCW Pump Running.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 8 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is in MODE 1.

• Biweekly rotation of the Component Cooling Water Pumps is required per OWI-409, Equipment Rotation Program.

• A Nuclear Equipment Operator (NEO) is standing by for pump start.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• SHIFT from Train A to Train B Component Cooling Water Pumps per SOP-502A, Component Cooling Water System.

• START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

• CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Page 9 of 9 CPNPP NRC 2012 JPM S-8.a Rev h.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-1 Unit 1 Task # AO6415 K/A # 054.AA1.01 4.5 / 4.4 SF-4S

Title:

Align Alternate Auxiliary Feedwater Supply From Station Service Water Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A fire has occurred in the Unit 1 Cable Spreading Room and the crew is performing ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room.

Motor Driven Auxiliary Feedwater Pump 1-01 has been stopped from the Remote Shutdown Panel due to a loss of suction pressure.

An operator is standing by at the Remote Shutdown Panel.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

ALIGN the Unit 1 alternate suction source to Motor Driven Auxiliary Feedwater Pump 1-01 per ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Attachment 9, Alternate AFW Supply.

Task Standard: Utilizing ABN-803A, Attachment 9, aligned the alternate source of Auxiliary Feedwater supply using the Unit 1 Station Service Water System.

Required Materials: ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Rev. 9-5.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Attachment 9, Alternate AFW Supply.

Page 2 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-803A, Attachment 9.

Perform Step: 1 Place the following breakers - OFF

a. & 1st bullet 1EB1-1/10E/BKR, MD AFW PUMP 1-01 SSW SUCTION ISOLATION VALVE 1-HV-2480 MOTOR BREAKER (Trn A Switchgear Room, SFGD 810 Rm 1-083)

Standard: ROTATED 1EB1-1/10E/BKR, MD AFW PUMP 1-01 SSW SUCTION ISOLATION VALVE 2480 MOTOR BREAKER in OFF position.

Examiner Cue: Breaker handle is in OFF position.

Comment: SAT UNSAT Perform Step: 2 Place the following breakers - OFF

a. & 2nd bullet 1EB3-1/3M/DSW, SSW TRAIN A TO UNIT 1 AFW PUMP SUCTION VALVE 4395 MOTOR FUSED SWITCH (North/South Corridor, SFGD 790 Rm 1-070)

Standard: ROTATED 1EB3-1/3M/DSW, SSW TRAIN A TO UNIT 1 AFW PUMP SUCTION VALVE 4395 FUSED SWITCH handle to OFF position.

Examiner Cue: Disconnect switch is in OFF position.

Comment: SAT UNSAT Examiner Note: May not perform this step based on the Initial Conditions.

Perform Step: 3 STOP 1-HS-2450C, MD AFWP 1.

b.

Standard: DETERMINED Auxiliary Feedwater Pump 1-01 is STOPPED per the Initial Conditions.

Examiner Cue: If asked, REPORT that the operator at the Remote Shutdown Panel confirms Auxiliary Feedwater Pump 1-01 is stopped.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 CLOSE 1AF-0020, SSW TO U1 AFW PMP SUCT HDR DRN VLV

c. (North/South Corridor, SFGD 790 Rm 1-070).

Standard: CLOSED 1AF-0020, SSW TO U1 AFW PMP DRN VLV by ROTATING handwheel in CLOCKWISE direction.

Examiner Cue: Handwheel has rotated fully clockwise and stopped.

Comment: SAT UNSAT Examiner Note: Tools are available locally to operate the valve.

Perform Step: 5 Unlock AND CLOSE 1AF-0013, CST TO MD AFW PMP 1-01 SUCT

d. VLV (AFW Corridor, SFGD 790 Rm 1-071).

Standard: PERFORMED the following:

UNLOCKED 1AF-0013, CST TO MD AFW PMP 1-01 SUCT VLV.

ROTATED handwheel in CLOCKWISE direction until CLOSED.

Examiner Cue: Handwheel has rotated fully clockwise and stopped.

Comment: SAT UNSAT Examiner Note: OWI-206, Guidelines for Operation of Manual and Power Operated Valves, Section 6.2, Motor Operated Valves, provides guidance for MOV operation.

Perform Step: 6 Locally OPEN 1-HV-4395, SSW TRN A TO U1 AFW PMP SUCT VLV

e. (North/South Corridor, SFGD 790 Rm 1-070).

Standard: ENGAGED the de-clutch lever and ROTATED 1-HV-4395, SSW TRN A TO U1 AFW PMP SUCT VLV handwheel in COUNTERCLOCKWISE direction until OPENED.

Examiner Cue: Handwheel has rotated fully counterclockwise and stopped.

Comment: SAT UNSAT Perform Step: 7 Locally OPEN 1-HV-2480, MD AFW PMP 1-01 SSW SUCT ISOL VLV

f. (Trn A MDAFWP Room, SFGD 790 Rm 1-072).

Standard: ENGAGED the de-clutch lever and ROTATED 1-HV-2480, MD AFW PMP 1-01 SSW SUCT ISOL VLV handwheel in COUNTERCLOCKWISE direction until OPENED.

Examiner Cue: Handwheel has rotated fully counterclockwise and stopped.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 WHEN system is vented and PRIOR to starting pump, CLOSE

g. 1AF-0120, SSW TO U1 AFW PMP HI PNT VNT VLV (TDAFWP Room, SFGD 790 Rm 1-074).

Standard: OBSERVED solid stream of water issuing from 1AF-0120, SSW TO U1 AFW PMP HI PNT VNT VLV.

Examiner Cue: A solid stream of water is issuing from the vent.

Comment: SAT UNSAT Perform Step: 9 WHEN system is vented and PRIOR to starting pump, CLOSE

g. 1AF-0120, SSW TO U1 AFW PMP HI PNT VNT VLV (TDAFWP Room, SFGD 790 Rm 1-074).

Standard: ROTATED 1AF-0120, SSW TO U1 AFW PMP HI PNT VNT VLV handwheel in CLOCKWISE direction until CLOSED.

Examiner Cue: Handwheel has rotated fully clockwise and stopped.

Comment: SAT UNSAT Examiner Note: Under normal conditions, AFW suction pressure reads ~ 22 PSIG.

Perform Step: 10 Verify 1-PI-2486, MOTOR DRIVEN AUXILIARY FEEDWATER PUMP

h. 1-01 SUCTION PRESSURE INDICATOR greater than or equal to 10 psig (Trn A MDAFWP Room, SFGD 790 Rm 1-072).

Standard: OBSERVED 1-PI-2486, MOTOR DRIVEN AUXILIARY FEEDWATER PUMP 1-01 SUCTION PRESSURE INDICATOR and VERIFIED gauge greater than or equal to 10 PSIG.

Examiner Cue: The gauge reads 35 PSIG.

Comment: SAT UNSAT Perform Step: 11 START 1-HS-2450C, MD AFWP 1.

i.

Standard: NOTIFIED the Remote Shutdown Panel Operator that Motor Driven Auxiliary Feedwater Pump 1-01 is ready to be started.

Terminating Cue: The operator at the Remote Shutdown Panel has been notified.

This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A fire has occurred in the Unit 1 Cable Spreading Room and the crew is performing ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room.

Motor Driven Auxiliary Feedwater Pump 1-01 has been stopped from the Remote Shutdown Panel due to a loss of suction pressure.

An operator is standing by at the Remote Shutdown Panel.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

ALIGN the Unit 1 alternate suction source to Motor Driven Auxiliary Feedwater Pump 1-01 per ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Attachment 9, Alternate AFW Supply.

Page 6 of 6 CPNPP NRC 2012 JPM P-1 Unit 1 Rev h.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-2 Task # RO4005C K/A # 059.AA2.04 3.2 / 3.5 SF-9

Title:

Terminate Release of Radioactive Liquid Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A radioactive discharge is in progress per RWS-103, Drain Channel B, Section 5.2.3, Discharging PET X-01 with Pump X-01 with Radiation Monitor Operable.

X-RE-5253, Liquid Radwaste Effluent Line Radiation Monitor (LWE076) is in HIGH alarm in the Control Room.

The Shift Manager has provided the key to operate X-HS-5253, Laundry Holdup & Monitor Tank Discharge Valve.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

TERMINATE the discharge per RWS-103, Drain Channel B, Section 5.2.3, Discharging PET X-01 with Pump X-01 with Radiation Monitor Operable.

START at Step 5.2.3 N.

Task Standard: Utilizing RWS-103, terminated the discharge of radioactive liquid, stopped the PET Monitor Tank Pump, and closed all discharge path valves.

Required Materials: RWS-103, Drain Channel B, Rev. 17-1.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 CPNPP NRC 2012 JPM P-2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

RWS-103, Drain Channel B, Step 5.2.3 N.

Attachment 7, PET Discharge Data Sheet.

Page 2 of 5 CPNPP NRC 2012 JPM P-2 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from RWS-103, Step 5.2.3.

Examiner Note: The pump is located in the Fuel Building, Elev. 810', Room 252.

Perform Step: 1 In the FB 810' Rm 252, PERFORM the following:

5.2.3.N.1) & STOP PET Pump X-01, by pressing push button X-PB02, PET 5.2.3.N.1).a MONITOR TANK PUMP 01 STOP.

Standard: PERFORM the following:

DEPRESSED X-PB02, PET MONITOR TANK PUMP 01 STOP pushbutton (critical).

OBSERVED green STOP light LIT (NOT critical).

Examiner Cue: The green light is LIT.

Comment: SAT UNSAT Examiner Note: The valves are located in the Fuel Building, Elev. 810', Room 252.

Examiner Note: A green CLOSE tab would be used to lock the valve in position.

Perform Step: 2 PERFORM the following:

5.2.3.N.1).b & CLOSE AND LOCK XWP-0435, LWPS PLT EFL HOLDUP/MON 1st bullet TK X-01/X-02 DISCH ISOL VLV.

(INITIAL on Attachment 7, PET Discharge Data Sheet.)

Standard: PERFORMED the following:

CLOSED XWP-0435, LWPS PLT EFL HOLDUP/MON TK X-01/X-02 DISCH ISOL VLV (critical).

LOCKED XWP-0435, LWPS PLT EFL HOLDUP/MON TK X-01/X-02 DISCH ISOL VLV (NOT critical)

INITIALED on Attachment 7, PET Discharge Data Sheet (NOT critical).

Examiner Cue: The stem is inserted to the nut and handwheel will not turn in the clockwise direction. Locking device is installed.

Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2012 JPM P-2 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 PERFORM the following:

5.2.3.N.1).b & CLOSE XWP-0406, LWPS PLT EFL HOLDUP/MON TK PMP 2nd bullet X-01 DISCH HDR ISOL VLV.

Standard: PERFORMED the following:

CLOSED XWP-0406, LWPS PLT EFL HOLDUP/MON TK PMP X-01 DISCH HDR ISOL VLV.

Examiner Cue: The stem is fully inserted and handwheel will not turn in the clockwise direction.

Comment: SAT UNSAT Examiner Cue: XWP-0407 stem is extended 1/2 inch.

Perform Step: 4 PERFORM the following:

5.2.3.N.1).b & IF CLOSED THEN THROTTLE XWP-0407, LWPS PLT EFL 3rd bullet HOLDUP/MON TK PMP X-01 RECIRC VLV, ~ 1/2 turn OPEN.

Standard: DETERMINED XWP-0407, LWPS PLT EFL HOLDUP/MON TK PMP X-01 RECIRC VLV is OPEN and N/A step.

Examiner Note: If operator chooses to throttle valve, PROVIDE the following cue.

Examiner Cue: The stem is fully inserted and handwheel will not turn in the clockwise direction then opened 1/2 turn counterclockwise.

Comment: SAT UNSAT Examiner Note: Liquid Waste Process Panel (LPP) is located in the Auxiliary Building, Elev. 790'.

Examiner Note: The key operated valve has CLOSE/AUTO/OPEN positions.

Perform Step: 5 At the AB 790' LPP CLOSE X-HS-5253, LAUNDRY HOLDUP 5.2.3.N.2) MONITOR TANK.

Standard: PERFORMED the following:

INSERTED PB key and TURNED XHS-5253 handswitch to CLOSE position (critical).

OBSERVED X-RV-5253, LWPS LHMT X-01/X-02 DISCH HDR RAD ISOL VLV, green CLOSE light LIT (NOT critical).

Terminating Cue: The red light is DARK and the green light is LIT.

This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP NRC 2012 JPM P-2 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A radioactive discharge is in progress per RWS-103, Drain Channel B, Section 5.2.3, Discharging PET X-01 with Pump X-01 with Radiation Monitor Operable.

X-RE-5253, Liquid Radwaste Effluent Line Radiation Monitor (LWE076) is in HIGH alarm in the Control Room.

The Shift Manager has provided the key to operate X-HS-5253, Laundry Holdup & Monitor Tank Discharge Valve.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

TERMINATE the discharge per RWS-103, Drain Channel B, Section 5.2.3, Discharging PET X-01 with Pump X-01 with Radiation Monitor Operable.

START at Step 5.2.3 N.

Page 5 of 5 CPNPP NRC 2012 JPM P-2 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-3 Unit 1 Task # RO7017 K/A # E11.EA1.1 3.9 / 4.0 SF-2

Title:

Align Emergency Makeup to the RWST Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 has a Large Break a Loss of Coolant Accident in progress.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

ALIGN emergency makeup to the Unit 1 Refueling Water Storage Tank (RWST) per ECA-1.1A, Loss of Emergency Coolant Recirculation, Attachment 3, RWST Makeup Methods.

START at Step 2, Makeup to Unit 1 RWST from Unit 2 RWST.

Task Standard: Utilizing ECA-1.1A, Attachment 3, completed alignment of makeup to Unit 1 RWST from Unit 2 RWST through Step 2.c.2)D) Open XSF-0044, REFUEL WTR PURIF PMP X-02 TO SFP PURIF FILT X-02 ISOL VLV.

Required Materials: ECA-1.1A, Loss of Emergency Coolant Recirculation, Rev. 8-6.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ECA-1.1A, Loss of Emergency Coolant Recirculation for Unit 1.

Attachment 3, RWST Makeup Methods, Step 2.

EXAMINER NOTE:

This JPM MUST be performed on Unit 1.

ENSURE examinee has a flashlight.

Page 2 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ECA-1.1A, Attachment 3.

Examiner Note: Valve is located in Unit 1 RWST Tank Room 810'. PB key may be required.

Perform Step: 1 Makeup to Unit 1 RWST from Unit 2 RWST.

2, 2.a, & 1st bullet Ensure the following valves open:

2SI-0047, RWST 2-01 TO SI ISOL VLV (Unit 2 RWST Tank room).

Standard: ROTATED 2SI-0047, RWST 2-01 TO SI ISOL VLV handwheel COUNTERCLOCKWISE to OPEN position.

Examiner Cue: If Control Room is called, REPORT Unit 2 Control Room has remote indication that 2SI-0047, RWST 2-01 to SI isolation valve is OPEN. If Control Room is not contacted then the handwheel rotated COUNTERCLOCKWISE then stopped.

Comment: SAT UNSAT Examiner Note: Valve is located in Auxiliary Building 790' overhead in front of Boron Recycle Panel. In order to verify valve position, a ladder and Radiation Protection personnel are required.

Perform Step: 2 Makeup to Unit 1 RWST from Unit 2 RWST.

2, 2.a, & 2nd bullet Ensure the following valves open:

2SI-8977, RWST 2-01 TO SFPCS WTR PURIF PMP X-01/

X-02 ISOL VLV (AB 790 in overhead)

Standard: ROTATED 2SI-8977, RWST 2-01 TO SFPCS WTR PURIF PMP X-01/X-02 ISOL VLV handwheel COUNTERCLOCKWISE to OPEN position.

Examiner Cue: Handwheel rotated COUNTERCLOCKWISE then stopped.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Makeup to Unit 1 RWST from Unit 2 RWST.

2, 2.b, both bullets Ensure the following valves open:

1/2-8800A, RWST TO SFCS DRN VLV 1/2-8800B, RWST TO SFCS DRN VLV Standard: Contacted Unit 2 Control Room to have valves 1/2-8800A and 1/2-8800B opened.

Examiner Cue: REPORT Unit 2 Control Room has completed ECA-1.1A, Attachment 3, Step 2.b and valves 1/2-8800A and 1/2-8800B, RWST to Spent Fuel Pool Cooling System drain valves are open.

Comment: SAT UNSAT Examiner Note: Spent Fuel Pool Control Panel is located in the Fuel Building 810'.

Examiner Cue: The red light is LIT and green light is DARK.

Perform Step: 4 Align SFP Purification loop 02 to transfer water to Unit 1 RWST.

2.c & 2.c.1) Ensure RFL WTR PURIF pump 02, X-HS-4827 stopped (SFPC control panel).

Standard: PERFORMED the following:

Handswitch X-HS-4827, RFL WTR PURIF PUMP 02 is rotated to the STOP position and released (critical).

OBSERVED green STOP light LIT (NOT critical).

Examiner Cue: The green light is LIT.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Valve is located in the Auxiliary Building 790' near the Refueling Water Purification Pumps.

Examiner Note: Refueling Water Purification Pump valves have rising stems.

Perform Step: 5 Perform the following to align a flowpath from Unit 2 RWST To Unit 1 2.c.2) & 2.c.2).A) RWST:

Ensure XSF-0075, REFUEL WTR PURIF PMP X-02 U2 REFUEL CAV ISOL VLV closed (AB 790 by Refueling Water Purif pumps).

Standard: ROTATED XSF-0075, REFUEL WTR PURIF PMP X-02 U2 REFUEL CAV ISOL VLV handwheel CLOCKWISE to CLOSE position.

Examiner Cue: Handwheel rotated CLOCKWISE then stopped.

Comment: SAT UNSAT Examiner Note: Valve is located in the Auxiliary Building 790' near the Refueling Water Purification Pumps.

Perform Step: 6 Perform the following to align a flowpath from Unit 2 RWST To Unit 1 2.c.2) & 2.c.2).B) RWST:

Open XSF-0200, U2 RWST TO REFUEL WTR PURIF PMP X-02 ISOL VLV (AB 790 by Refueling Water Purif pumps).

Standard: ROTATED XSF-0200, U2 RWST TO REFUEL WTR PURIF PMP X-02 ISOL VLV handwheel COUNTERCLOCKWISE to OPEN position.

Examiner Cue: Handwheel rotated COUNTERCLOCKWISE then stopped.

Comment: SAT UNSAT Examiner Note: Valve is located in the Auxiliary Building 790' near the Refueling Water Purification Pumps.

Perform Step: 7 Perform the following to align a flowpath from Unit 2 RWST To Unit 1 2.c.2) & 2.c.2).C) RWST:

Ensure XSF-0047, U2 RCDT TO SFPCS ISOL VLV closed (AB 790 by Refueling Water Purif pumps).

Standard: ROTATED XSF-0047, U2 RCDT TO SFPCS ISOL VLV handwheel CLOCKWISE to CLOSE position.

Examiner Cue: Handwheel rotated CLOCKWISE then stopped.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Valve is located in the Auxiliary Building 790' near the Refueling Water Purification Pumps.

Perform Step: 8 Perform the following to align a flowpath from Unit 2 RWST To Unit 1 2.c.2) & 2.c.2).D) RWST:

Open XSF-0044, REFUEL WTR PURIF PMP X-02 TO SFP PURIF FILT X-02 ISOL VLV (AB 790 by Refueling Water Purif pumps).

Standard: ROTATED XSF-0044, REFUEL WTR PURIF PMP X-02 TO SFP PURIF FILT X-02 ISOL VLV handwheel COUNTERCLOCKWISE to OPEN position.

Terminating Cue: Handwheel rotated COUNTERCLOCKWISE then stopped.

This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 has a Large Break a Loss of Coolant Accident in progress.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

ALIGN emergency makeup to the Unit 1 Refueling Water Storage Tank (RWST) per ECA-1.1A, Loss of Emergency Coolant Recirculation, Attachment 3, RWST Makeup Methods.

START at Step 2, Makeup to Unit 1 RWST from Unit 2 RWST.

Page 7 of 7 CPNPP NRC 2012 JPM P-3 Unit 1 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: June 2012 NRC Examiners: Operators:

Initial Conditions: 100% power MOL - RCS Boron is 908 ppm (by sample).

Turnover: Maintain steady-state power conditions. Boric Acid Transfer Pump 1-01 is OOS.

Critical Tasks:

• Close PORV Block Valve to Maintain RCS Pressure Greater Than Low Pressure Reactor Trip Setpoint Following Entry Into ABN-705, Pressurizer Pressure Malfunction.

• Control Steam Generator Level to Avoid RPS or ESFAS Actuation per ABN-710, Steam Generator Level Instrumentation Malfunction.

• Initiate Emergency Boration due to Two (2) Stuck Control Rods Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

• Trip Reactor Coolant Pumps Prior to Establishing Bleed and Feed per FRH-0.1A, Response to Loss of Secondary Heat Sink.

• Establish Core Cooling via Reactor Coolant System Bleed and Feed per FRH-0.1A, Response to Loss of Secondary Heat Sink.

Event No. Malf. No. Event Type* Event Description 1 RX08B I (RO, SRO) Pressurizer Pressure Channel (PT-456) Fails High.

+10 min RX16B TS (SRO) Stuck Power Operated Relief Valve (PCV-456) at 25% Open.

2 RX04B I (BOP, SRO) Steam Generator (1-02) Level Transmitter (LT-552) Fails High.

+20 min TS (SRO) 3 RP06B I (RO, SRO) Loop 2 N-16 Channel (JI-421A/B) Fails Low.

+30 min TS (SRO) 4 FW03A R (RO) Main Feedwater Pump A Trip.

+40 min TC09C N (BOP, SRO) Automatic Turbine Runback Failure.

5 FW06A M (RO, BOP, SRO) Main Feedwater Pumps A & B Recirculation Valves

+45 min FW06B (FV-2289/FV-2290) Fail Open. Loss of Main Feedwater Pumps.

6 RD04K2 C (RO) Two Control Rods Fail to Insert Upon Reactor Trip.

+45 min RD04K8 Emergency Boration Required.

7 FW08B C (BOP) Motor Driven Auxiliary Feedwater Pump (1-02) Start Failure.

+47 min 8 OVRDE C (BOP) Turbine Driven Auxiliary Feedwater Pump (TDAFW) Steam Valves

+47 min FW09B Fail to Auto Open Followed by TDAFW Trip (60 second time delay).

9 ED05H C (BOP) 6900 Volt Train A Safeguards Bus 1EA1 86-1 Trip and Lockout

+50 min M (RO, BOP, SRO) Five minutes Post Trip. Loss of Feedwater Flow.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 4 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 5 Critical tasks (2-3)

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h SCENARIO

SUMMARY

NRC #2 The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations. Boric Acid Transfer Pump 1-01 is out-of-service.

The first event it is a high failure of a Pressurizer Pressure Channel. Operator actions are per ABN-705, Pressurizer Pressure Malfunction, Section 2.0, and require closing the Block Valve on a partially open Power Operated Relief Valve (PORV), placing the Pressurizer Master Pressure Controller in MANUAL, selecting an alternate controlling Channel, and restoring Pressurizer pressure to normal. The SRO will refer to Technical Specifications.

The next event is a high failure of a Steam Generator (1-02) Level Transmitter. Crew actions are per ABN-710, Steam Generator Level Instrumentation Malfunction, Section 2.0, and include placing Steam Generator (SG) Level Control in MANUAL, stabilizing the plant, aligning an Alternate Channel, and transferring SG Level Control back to AUTO. The SRO will refer to Technical Specifications.

When Technical Specifications are referenced, a low failure of Loop 2 N-16 Instrument (JI-421A/B) will occur. Operator actions are per ABN-704, TC/N-16 Instrumentation Malfunction, Section 2.0, and require stopping Control Rod motion and stabilizing Reactor Coolant System (RCS) temperature and Pressurizer level. The SRO will refer to Technical Specifications.

When RCS temperature is restored to normal, a Main Feedwater Pump (MFW) will trip and an AUTO Turbine Runback will fail to initiate. Rod Control will be placed in AUTO and a Manual Turbine Runback to 700 MWe is commenced per ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 2.0. Both MFW Pump Recirculation Valves will fail open and result in lowering Steam Generator level and a Reactor Trip. The automatic Reactor Trip on low Steam Generator level will require entry into EOP-0.0A, Reactor Trip or Safety Injection.

Two Control Rods failed to insert on the Reactor Trip and an Emergency Boration is required. While performing the actions of EOP-0.0A, a Motor Driven Auxiliary Feedwater (AFW) Pump will fail to start and require placing the Turbine Driven AFW (TDAFW) Pump in service. Shortly after the TDAFW Pump is started, the pump will trip. The crew will transition from EOP-0.0A to EOS-0.1A, Reactor Trip Response. Five minutes after the Reactor trips, Train A Safeguards Bus 1EA1 will trip and lockout resulting in a Loss of Feedwater Flow. Entry into FRH-0.1A, Response to Loss of Secondary Heat Sink, will be performed with an immediate transition to Step 12 for RCS Bleed and Feed.

The scenario success path includes tripping the Reactor Coolant Pumps and opening the Pressurizer and Reactor Head Vents.

Risk Significance:

• Failure of risk important system prior to trip: Automatic Turbine Runback Failure

• Risk significant core damage sequence: Loss of Feedwater Flow

• Risk significant operator actions: Close PORV Block Valve Restore Steam Generator 1-02 Level Control Start TDAFW Pump Trip Reactor Coolant Pumps Initiate RCS Bleed and Feed CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h BOOTH OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC #18 and NRC #2 Scenario File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP Boric Acid Transfer Pump 1-01 PULLOUT -

Boric Acid Transfer Pump 1-02 AUTO -

RD04K2 Stuck Control Bank B Control Rod K2 STUCK K0 RD04K8 Stuck Control Bank A Control Rod K8 STUCK K0 FW08B Motor Driven AFW Pump (1-02) Start Failure OFF K0 OVRDE TDAFW Pump Steam Valves Failure - K0 FW09B TDAFW Pump Trip TRIP 60 second TD Post Start ED05H Train A Safeguards Bus 1EA1 Trip and Lockout TRIP 300 second TD Post Trip NOTE: ENSURE keys for Pressurizer & Reactor Head Vent Valves are moved to top of Key Locker.

1 RX08B Pressurizer Pressure Channel (PT-456) Failure 2500 psig K1 1 RX16B Stuck PORV (PCV-456) at 25% Open 25% K1 1 RCR24 PORV Block Valve 1/1-8000B Breaker OPEN K6 2 RX04B SG (1-02) Level Transmitter (LT-552) 100% K2 3 RP06B Loop 2 N-16 Channel (JI-421A/B) Failure 0% K3 4 FW03A Main Feedwater Pump (1-01) Trip TRIP K4 4 TC09C Automatic Turbine Runback Failure FAIL K4 5 FW06A MFW Pump (1-01) Recirculation Valve Failure OPEN K4 5 FW06B MFW Pump (1-02) Recirculation Valve Failure OPEN K4 6 RD04K2 Stuck Control Bank B Control Rod K2 228 K0 6 RD04K8 Stuck Control Bank A Control Rod K8 228 K0 7 FW08B Motor Driven AFW Pump (1-02) Start Failure OFF K0 CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h 8 OVRDE TDAFW Pump Steam Supply Valve 1-HS-2451-1 CLOSED K0 DIFWHS24521 from SG 1-04 (NOTE 1) 8 OVRDE TDAFW Pump Steam Supply Valve 1-HS-2451-2 CLOSED K0 DIFWHS24522 from SG 1-01 (NOTE 1)

NOTE 1: 1-HS-2452-1/2, TDAFW Pump Valves will NOT AUTO open but will open when taken to START.

This will prevent an AUTO start on 86-1 Trip and Lockout if TDAFW Pump was not previously started.

8 FW09B TDAFW Pump Trip TRIP 60 second TD Post Start 8 TDAFW Pump Trip {AOFW SI 2452A. Value > 1600} IMF FW09B f:1 d:60 9 ED05H Train A Safeguards Bus 1EA1 Trip and Lockout 86-1 300 second TD Post Trip 9 EDR74 IA Compressor 1-02 1EB4/11D FDR BKR CLOSED When directed RCR24 PORV Block Valve 1/1-8000B Breaker (NOTE 2) CLOSE K7 NOTE 2: Power is restored to PORV Block Valve 1/1-8000B when FRH-0.1A is entered.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: INITIALIZE to IC #18 and NRC #2 Scenario File.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE Boric Acid Transfer Pump 1-01 in PULLOUT and TAGGED.

ENSURE Boric Acid Transfer Pump 1-02 in AUTO.

ENSURE keys for PRZR & RX Head Vent Valves moved to top of Key Locker.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON at half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.5, Operating at Constant Turbine Load.

ENSURE Control Rods are in AUTO with Bank D at 215 steps.

Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: When directed, EXECUTE Event 1 (Key 1).

- RX08B, Pressurizer Pressure Channel (PT-456) fails high.

- RX16B, PORV (PCV-456) fails 25% open.

Indications Available:

5B-3.1 - PRZR PORV OUT TEMP HI 5B-4.1 - PRZR ANY SFTY RLF VLV OUT TEMP HI 5C-1.4 - PORV 455A / 456 NOT CLOSE 5C-2.1 - PRZR PRESS HI 5C-3.1 - PRZR 1 OF 4 PRESS HI 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON 6A-3.4 - CHRG FLO HI / LO (~10 seconds later) 1-TI-463, PRZR PORV OUT TEMP indication rising 1-PI-456, PRZR PRESS CHAN II indication failed high 1/1-PCV-456, PRZR PORV indicates mid position

+1 min RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE PRZR pressure lowering.

DIRECT performance of ABN-705, Pressurizer Pressure Malfunction, US Section 2.0.

Examiner Note: Diamond steps () are Initial Operator Actions.

RO VERIFY PORV - CLOSED. [Step 2.3.1 - NO]

• PLACE 1/1-PCV-456, PRZR PORV in CLOSE. [Step 2.3.1 RNO - YES]

Close PORV Block Valve to Maintain Reactor Coolant System Pressure Greater CRITICAL TASK Than Low Pressure Reactor Trip Setpoint Following Entry into ABN-705, STATEMENT Pressurizer Pressure Malfunction.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h CRITICAL RO CLOSE PORV Block Valve. [Step 2.3.1 RNO - YES]

TASK

• PLACE 1/1-8000B, PRZR PORV BLK VLV in CLOSE.

RO

[Step 2.3.1 RNO - YES]

PLACE 1-PK-455A, PRZR MASTER PRESS CTRL in MANUAL.

RO

[Step 2.3.2 - YES]

RO ADJUST 1-PK-455A for current RCS pressure. [Step 2.3.3 - YES]

TRANSFER 1/1-PS-455F, PRZR PRESS CTRL CHAN SELECT to an RO Alternate Controlling Channel. [Step 2.3.4 - YES]

PLACE 1-PK-455A, PRZR MASTER PRESS CTRL in AUTO.

RO

[Step 2.3.5 - YES]

VERIFY automatic control restoring Pressurizer pressure to 2235 PSIG.

RO

[Step 2.3.6 - YES]

ENSURE valid channel to recorder 1/1-PS-455G, 1-PR-455 PRZR PRESS RO SELECT. [Step 2.3.7 - YES]

IF necessary, RETURN PORV closed in Step 1 RNO to AUTO and ENSURE RO it remains CLOSED. [Step 2.3.8 - NO]

• VERIFY 1/1-PCV-456, PRZR PORV failed in mid position.

MAINTAIN 1/1-8000B, PRZR PORV BLK VLV in CLOSE due to PORV in RO mid position. [Step 2.3.9 - YES]

Within one hour, VERIFY PCIP Window 2.6 - PRZR PRESS SI BLK PERM US/RO P DARK. [Step 2.3.10 - YES]

VERIFY other instruments on common instrument line - NORMAL.

US/RO

[Step 2.3.11 - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

• VERIFY Loop 2 Instruments LT-460 and PT-458 responding normally per Attachment 1.

Examiner Note: The next two (2) steps are only performed following I&C maintenance.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, PERFORM the following: [Step 2.3.12 - YES]

• PLACE 1/1-RBSS, CONTROL ROD BANK SELECT in MANUAL.

[Step 2.3.12.a - YES]

• SELECT the failed channel on following switches: [Step 2.3.12.b - YES]

• 1-TS-412T, TAVE CHAN DEFEAT

• 1/1-JS-411E, N16 PWR CHAN DEFEAT

• ENSURE valid N16 channel is supplying recorder: [Step 2.3.12.c - YES]

• 1/1-TS-411E, 1-TR-411 CHAN SELECT

• CONTACT I&C to place bistable test switches for PT-456 in CLOSE.

[Step 2.3.12.d - YES]

VERIFY appropriate alarms and trip status lights ON per Attachment 4.

[Step 2.3.13 - YES]

• OBSERVE TSLB-1, Window 2.7 - PRZR PRESS LO PB-456D is LIT.

• OBSERVE TSLB-5, Window 2.2 - PRZR PRESS LO PB-456C is LIT.

• OBSERVE TSLB-5, Window 2.3 - PRZR PRESS HI PB-456A is LIT.

• OBSERVE TSLB-9, Window 2.3 - PRZR PRESS SI PERM PB-456B is LIT.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

+10 min US EVALUATE Technical Specifications. [Step 2.3.14 - YES]

• LCO 3.3.1.E, Reactor Trip System Instrumentation.

(Function 8.b, Pressurizer Pressure High)

• CONDITION E - One channel inoperable.

• ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.

• LCO 3.3.1.M, Reactor Trip System Instrumentation.

(Function 8.a, Pressurizer Pressure Low)

• CONDITION M - One channel inoperable.

• ACTION M.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION M.2 - Reduce THERMAL POWER to < P-7 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.

• LCO 3.3.2.D, ESFAS Instrumentation.

(Function 1.d, Pressurizer Pressure Low)

• CONDITION D - One channel inoperable.

• ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION D.2.1 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, AND

• ACTION D.2.2 - Be in MODE 4 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.

• LCO 3.3.2.L, ESFAS Instrumentation.

(Function 8.b, Pressurizer Pressure P-11)

• CONDITION L - One or more required channel(s) inoperable.

• ACTION L.1 - Verify interlock is in required state for existing unit condition within one hour, OR

• ACTION L.2.1 - Be in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, AND

• ACTION L.2.2 - Be in MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Booth Operator: When contacted to remove power to 1/1-8000B, PRZR PORV BLK VLV, EXECUTE remote function RCR24 (Key 6), 1/1-8000B to OFF.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

• LCO 3.4.11.B, Pressurizer Power Operated Relief Valve.

• CONDITION B - One PORV inoperable and not capable of being manually cycled.

• ACTION B.1 - Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, AND

• ACTION B.2 - Remove power from associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, AND

• ACTION B.3 - Restore PORV to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

US INITIATE a work request per STA-606. [Step 2.3.15 - YES]

+10 min US INITIATE a Condition Report per STA-421. [Step 2.3.16 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: When directed, EXECUTE Event 2 (Key 2).

- RX04B, Steam Generator 1-02 Level Channel (LT-552) fails high.

Indications Available:

8A-2.8 - SG 2 STM & FW FLO MISMATCH 8A-2.12 - SG 2 LVL DEV 1-LI-552, SG 2 LVL (NR) CHAN II indication failed high

+30 sec BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Steam Generator 1-02 level lowering.

Examiner Note: Steam Generator (SG) Level Channel II failing HIGH will cause the Feedwater Control Valve to CLOSE, thereby lowering SG level. Unit 1 LOW LEVEL REACTOR TRIP is at 38%.

DIRECT performance of ABN-710, Steam Generator Level Instrumentation US Malfunction, Section 2.0.

RECOGNIZE Steam Generator 1-02 Level Channel (LT-552) failed high.

BOP

[Step 2.3.1 - YES]

BOP VERIFY controlling level channel - FAILED. [Step 2.3.1 - YES]

CRITICAL TASK Control Steam Generator Level to Avoid RPS or ESFAS Actuation per STATEMENT ABN-710, Steam Generator Level Instrumentation Malfunction.

CRITICAL PLACE 1-FK-520, SG 2 FW FLO CTRL in MANUAL and CONTROL level.

TASK BOP

[Step 2.3.2 - YES]

VERIFY instruments on common instrument line - NORMAL.

BOP

[Step 2.3.3 - YES]

• VERIFY Loop 2 Instrument LT-502 responding normally per Attachment 1.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h VERIFY all HI-HI level bistable windows on TSLB-3 for SG 1 DARK.

BOP

[Step 2.3.4 - YES]

• OBSERVE TSLB-3, Window 1.3 - SG 2 LVL HI-HI LB-529A is DARK.

• OBSERVE TSLB-3, Window 3.3 - SG 2 LVL HI-HI LB-528A is DARK.

• OBSERVE TSLB-3, Window 4.3 - SG 2 LVL HI-HI LB-527A is DARK.

BOP VERIFY automatic SG level control available: [Step 2.3.5 - YES]

• OBSERVE alternate level control channel 1-LI-529A indication NORMAL.

[Step 2.3.5.a - YES]

• DETERMINE automatic level control desired by Unit Supervisor.

[Step 2.3.5.b - YES]

BOP SELECT Alternate Channel: [Step 2.3.6 - YES]

• PLACE 1-LS-529C, SG 2 LVL CHAN SELECT to the LY-529 position.

BOP VERIFY affected SG conditions for auto level control: [Step 2.3.7 - YES]

• OBSERVE Feedwater and Steam Flows - MATCHED.

• OBSERVE Steam Generator Level - STABLE AT PROGRAM.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h PLACE 1-FK-520, SG 2 FW FLO CTRL in AUTO and MONITOR operation.

BOP

[Step 2.3.8 - YES]

Examiner Note: The next two (2) steps are performed after I&C troubleshooting is completed.

WITHIN 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, CONTACT I&C to PLACE bistable test switches for Level Channel II in CLOSE per Attachments 2 and 3. [Step 2.3.9 - YES]

VERIFY appropriate alarms and Trip Status Lights LIT per Attachment 3 and NOTE in the Unit Log. [Step 2.3.10 - YES]

• OBSERVE TSLB-3, Window 1.3 - SG 2 LVL HI-HI LB-529A is LIT.

• OBSERVE TSLB-5, Window 2.5 - SG 2 LVL LO-LO LB-552B is LIT.

US EVALUATE Technical Specifications. [Step 2.3.11 - YES]

• LCO 3.3.1.E, Reactor Trip System Instrumentation.

(Function 14, Steam Generator Water Level Low-Low)

• CONDITION E - One channel inoperable (Channel 2 LO-LO).

• ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.

• LCO 3.3.2.D, ESFAS Instrumentation.

(Function 6.c, Steam Generator Water Level Low-Low)

• CONDITION D - One channel inoperable.

• ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION D.2.1 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, AND

• ACTION D.2.2 - Be in MODE 4 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.

• LCO 3.3.2.I, ESFAS Instrumentation.

(Function 5.b, SG Water Level High-High P-14)

• CONDITION I - One channel inoperable (Channel 2 HI-HI).

• ACTION I.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION I.2 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h US INITIATE a work request per STA-606. [Step 2.3.12 - YES]

+10 min US INITIATE a Condition Report per STA-421. [Step 2.3.13 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: When directed, EXECUTE Event 3 (Key 3).

- RP06B, Loop 2 N-16 Channel (1-JI-421A/B) fails low.

Indications Available:

5C-1.3 - PRZR LVL DEV HI 5C-1.5 - ANY N16 DEV HI/LO 5C-3.5 - ANY TAVE DEV HI/LO 6D-1.10 - ANY TAVE TREF DEV 6D-3.13 - TREF-AUCT LO TAVE MISMATCH 6D-4.13 - AUCT TAVE LO 1-JI-421A/B, RC LOOP 2 N16 PWR CHAN II indication failed low 1-TI-421B, RC LOOP 2 OT N16 SETPOINT CHAN II indication reads higher than the others

+30 sec RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Loop 2 N-16 Channel failure at 1-JI-421A/B on CB-05 and/or RO CB-07.

DIRECT performance of ABN-704, Tc / N16 Instrumentation Malfunction, US Section 2.0.

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT in MANUAL.

RO

[Step 2.3.1 - YES]

PLACE 1-TS-412T, TAVE CHAN DEFEAT in LOOP 2 position.

RO

[Step 2.3.2 - YES]

VERIFY Steam Dump System - NOT ACTUATED AND NOT ARMED.

BOP

[Step 2.3.3 - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Using Control Rods, RESTORE TAVE to within 1ºF of TREF.

RO

[Step 2.3.4 - YES]

PLACE 1/1-JS-411E, N16 PWR CHAN DEFEAT in LOOP 2 position.

RO

[Step 2.3.5 - YES]

ENSURE valid N16 Channel supplying recorder on 1/1-TS-411E, 1-TR-411 RO CHAN SELECT. [Step 2.3.6 - YES]

BOP VERIFY Steam Dump System - NOT ARMED. [Step 2.3.7 - YES]

• PCIP Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7 is DARK.

BOP VERIFY Steam Dump System - NOT BLOCKED. [Step 2.3.8 - YES]

Examiner Note: The next two (2) steps are performed after I&C troubleshooting is completed.

WITHIN 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, CONTACT I&C to PLACE bistable test switches for LOOP 2 in CLOSE per Attachments 1 and 2. [Step 2.3.9 - YES]

VERIFY appropriate alarms and Trip Status Lights LIT per Attachment 3 and NOTE in the Unit Log. [Step 2.3.10 - YES]

• VERIFY TSLB-5, Window 2.8 - RC LOOP 2 OT N16 is LIT.

• VERIFY TSLB-9, Window 2.4 - OT N16 ROD STOP & TURB RUNBACK is LIT.

US EVALUATE Technical Specifications. [Step 2.3.11 - YES]

• LCO 3.3.1.E, Reactor Trip System Instrumentation.

(Functions 6 & 7, Overtemperature N-16 and Overpower N-16)

• CONDITION E - One channel inoperable (Channel 2 LO-LO).

• ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.

US INITIATE a work request per STA-606. [Step 2.3.12 - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

+10 min US INITIATE a Condition Report per STA-421. [Step 2.3.13 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: When directed, EXECUTE Event 4 (Key 4).

- FW03A, Main Feedwater Pump A trip.

- TC09C, Auto Turbine Runback failure.

- FW06A, Main Feedwater Pump A Recirculation Valve fails open.

- FW06B, Main Feedwater Pump B Recirculation Valve fails open.

Indications Available:

7B-1.12 - FWPT A TRIP 8A-1.8 / 2.8 / 3.8 / 4.8 - SG 1 / 2 / 3 / 4 STM & FW FLO MISMATCH 8A-1.12 / 2.12 / 3.12 / 4.12 - SG 1 / 2 / 3 / 4 LVL DEV (~10 seconds later) 6D-1.9 - ANY TURB RUNBACK EFFECTIVE (when Manual Runback initiated) 6D-1.10 - AVE TAVE-TREF DEV (when Manual Runback initiated) 1-HS-2111, FWPT A TRIP light LIT Steam Dump System Group 1 Valves OPEN Control Rods stepping IN

+30 sec RO/BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE trip of Main Feedwater Pump A with no Automatic Turbine BOP Runback.

DIRECT performance of ABN-302, Feedwater, Condensate, Heater Drain US System Malfunction, Section 2.0.

Examiner Note: Diamond steps () are Initial Operator Actions.

RO/BOP VERIFY automatic plant response. [Step 2.3.1 - NO]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h RO

• VERIFY Control Rods in - AUTO.

BOP

• VERIFY Turbine Runback - IN PROGRESS.

If Turbine Power is > ~700 MWe, PERFORM the following:

RO/BOP

[Step 2.3.1 RNO - YES].

• PLACE 1/1-RBSS, CONTROL ROD BANK SELECT in AUTO.

RO

[Step 2.3.1.a RNO - YES].

• ENSURE Turbine Runback to 700 MWE initiated.

BOP

[Step 2.3.1.b RNO - YES].

• DEPRESS 700 MWe MANUAL RUNBACK button.

• CLICK on 0/1 button.

• CLICK on Execute then VERIFY Manual Runback in progress.

Examiner Note: When Main Feedwater Pump (MFWP) A & B Recirculation Valves fail open, MFWP B suction pressure will lower and trip MFWP B.

STABILIZE Reactor power using one or more of the following:

RO/BOP

[Step 2.3.2 - YES]

• Control Rods / Steam Dumps / Boration / Turbine Load.

BOP VERIFY Main Feedwater flow to Steam Generators. [Step 2.3.3 - YES]

• VERIFY one Main Feedwater Pump - RUNNING. [Step 2.3.3.a - NO]

• VERIFY Main Feedwater - ALIGNED. [Step 2.3.3.a - NO]

• PERFORM the following: [Step 2.3.3.a RNO - YES]

• If SG level is lowering in an uncontrolled manner, TRIP the Reactor and GO to EOP-0.0A. [Step 2.3.3.a.1) RNO - YES]

• THROTTLE AFW Control Valves to 25%.

[Step 2.3.3.a.2) RNO - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

• START both Motor Driven AFW Pumps.

[Step 2.3.3.a.3) RNO - YES]

• ENSURE Feedwater System Bypass Valves - CLOSED.

[Step 2.3.3.a.4) RNO - YES]

• ENSURE Main Feedwater ALIGNED. [Step 2.3.3.a.5) RNO - NO]

• ADJUST AFW Flow Control Valves to maintain SG narrow range

+10 min level between 60% and 75%. [Step 2.3.3.a.6) RNO - YES]

When the Reactor is tripped, PROCEED to Events 6, 7, 8, and 9.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h Booth Operator: When Reactor Trip occurs, EXECUTE Events 6, 7, 8, and 9.

- RD04K2 / RD04K8, Two (2) Stuck Control Rods.

- FW08B, Motor Driven Auxiliary Feedwater Pump 1-02 start failure.

- OVRDE, Turbine Driven Auxiliary Feedwater Pump Steam Supply Valves fail to AUTO open.

- FW09B, Turbine Driven Auxiliary Feedwater Pump trip.

- ED05H, Train A Bus 1EA1 86-1 trip and lockout (5 minutes post trip).

Indications Available:

Numerous Reactor Trip alarms US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1 - YES]

• VERIFY Reactor Trip Breakers - OPEN. [Step 1.a - YES]

• VERIFY Neutron flux - DECREASING. [Step 1.a - YES]

• VERIFY all Control Rod Position Rod Bottom Lights - ON.

[Step 1.b - NO]

BOP VERIFY Turbine Trip: [Step 2 - YES]

• VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2 - YES]

BOP VERIFY Power to AC Safeguards Buses: [Step 3 - YES]

• VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a - YES]

• VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b - YES]

RO CHECK SI status: [Step 4 - YES]

• CHECK if SI is actuated. [Step 4.a - NO]

• CHECK if SI is required. [Step 4.a RNO - YES]

• VERIFY Steam Line Pressure < 610 PSIG. [Step 4.a RNO - NO]

• VERIFY Pressurizer Pressure < 1820 PSIG. [Step 4.a RNO - NO]

• VERIFY Containment Pressure > 3.0 PSIG. [Step 4.a RNO - NO]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h

• IF SI is NOT required, GO to EOS-0.1A, Reactor Trip Response, Step 1.

US

[Step 4.a RNO - YES]

Examiner Note: Emergency boration is performed per the Foldout Page of EOP-0.0A using steps outlined in ABN-107, Emergency Boration, Attachment 1.

CRITICAL TASK Initiate Emergency Boration Due to Two (2) Stuck Control Rods Prior to Exiting STATEMENT EOP-0.0, Reactor Trip or Safety Injection.

CRITICAL TASK RO INITIATE Emergency Boration of 3600 gallons of Boric Acid.

• ENSURE a Charging Pump is RUNNING. [Step 1 - YES]

• START a Boric Acid Transfer Pump: [Step 2 - YES]

• PLACE 1/1-APBA1, BA XFER PMP 2 in START.

• PLACE 1/1-8104, EMER BORATE VLV in OPEN. [Step 3 - YES]

• VERIFY flow on 1-FI-183A, EMER BORATE FLO. [Step 4 - YES]

• VERIFY flow on 1-FI-121A, CHRG FLO. [Step 5 - YES]

Examiner Note: The following steps are from EOS-0.1A, Reactor Trip Response.

Examiner Note: Depending on crew response, the RED PATH for Heat Sink will occur at some point early in EOS-0.1A. This condition occurred at Step 3 during validation.

RO CHECK RCS Temperature: [Step 1 - YES]

• VERIFY RCS average temperature stable at or trending to 557ºF.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h RO/BOP CHECK FW Status: [Step 2 - YES]

• VERIFY Reactor Trip Breakers - OPEN. [Step 2.a - YES]

• CHECK RCS average temperatures < 564ºF. [Step 2.b - NO]

• CONTINUE with Step 3. When temperature is less than 564°F PERFORM Steps 2.c & 2.d. [Step 2.b RNO - YES]

VERIFY total AFW flow to SGs - GREATER THAN 460 GPM.

BOP

[Step 2.d - YES]

RO CHECK PRZR Level Control: [Step 3 - YES]

• VERIFY PRZR Level - GREATER THAN 17%. [Step 3.a - YES]

• VERIFY Charging - IN SERVICE. [Step 3.b - YES]

• VERIFY Letdown - IN SERVICE. [Step 3.c - YES]

• VERIFY PRZR Level - TRENDING TO 25%. [Step 3.d - YES]

RO CHECK PRZR Pressure Control: [Step 4 - YES]

• VERIFY Pressurizer Pressure - GREATER THAN 1820 PSIG.

[Step 4.a - YES]

• VERIFY Pressurizer Pressure - STABLE AT OR TRENDING TO 2235 PSIG. [Step 4.b - YES]

RO CHECK Steam Generator Levels: [Step 5 - YES]

• VERIFY Steam Generator Level - GREATER THAN 43%.

[Step 5.a - NO]

• MAINTAIN total feed flow greater than 460 GPM until narrow range level greater than 43% in at least one SG. [Step 5.a RNO - YES]

• VERIFY Pressurizer Pressure - STABLE AT OR TRENDING TO 2235 PSIG. [Step 4.b - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h RO VERIFY All AC Buses - ENERGIZED BY OFFSITE POWER: [Step 6 - YES]

Examiner Note: FRH-0.1A, Response to Loss of Secondary Heat Sink, steps begin here.

US/BOP CHECK If Secondary Heat Sink Is Required: [Step 1 - YES]

• VERIFY RCS pressure -GREATER THAN ANY NON-FAULTED SG PRESSURE. [Step 1.a - YES]

• VERIFY RCS temperature > 350ºF. [Step 1.b - YES]

US/RO CHECK CCP Status - BOTH AVAILABLE. [Step 2 - NO]

• IMMEDIATELY PERFORM the following: [Step 2 RNO - YES]

CRITICAL TASK Trip Reactor Coolant Pumps Prior to Establishing Bleed and Feed per STATEMENT FRH-0.1A, Response to Loss of Secondary Heat Sink.

CRITICAL TASK RO

• STOP all RCPs. [Step 2.a RNO - YES]

• VERIFY power to PRZR PORV Block Valves - AVAILABLE.

[Step 2.b RNO - NO]

• Locally RESTORE power to PRZR PORV Block Valves.

[Step 2.b RNO - YES]

• GO to Step 12. Observe CAUTION prior to Step 12.

[Step 2.c RNO - YES]

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h RO/BOP Manually ACTUATE Safety Injection. [Step 12 - YES]

RO/BOP VERIFY RCS Feed Path: [Step 13 - YES]

• VERIFY at least one (1) CCP and one (1) SI PUMP - RUNNING.

[Step 13.a - YES]

Examiner Note: Attachment 3, ECCS Valve Alignment, valves are in their proper position.

• CHECK valve alignment for operating pumps - PROPER EMERGENCY ALIGNMENT PER ATTACHMENT 3. [Step 13.b - YES]

Examiner Note: The following six (6) steps are performed per FRH-0.1A, Attachment 1.D.

RO/BOP [1.D] PLACE Train B DG EMER STOP/START handswitch in START.

[Step 14 - YES]

RO/BOP [1.D] VERIFY SI - RESET. [Step 15 - YES]

• DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton.

• DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton.

RO/BOP [1.D] VERIFY SI Sequencers - RESET. [Step 16 - YES]

• At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

• After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

• At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

• After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h RO/BOP [1.D] VERIFY Containment Isolation Phase A and Phase B - RESET.

[Step 17 - YES]

• DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton.

• DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton.

• DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton.

• DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton.

RO/BOP [1.D] VERIFY Containment Spray Signal - RESET. [Step 18 - YES]

• DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton.

• DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton.

Booth Operator: If requested, EXECUTE remote function EDR74, 1EB4/11D BKR to CLOSE to RESET Instrument Air Compressors 1-02.

RO/BOP [1.D] ESTABLISH Instrument Air and Nitrogen to Containment.

[Step 19 - YES]

• ESTABLISH Instrument Air: [Step 19.a - YES]

• VERIFY Air Compressor - RUNNING. [Step 19.a.1) - NO]

• Manually START Air Compressor and align valves.

[Step 19.a.1) RNO - YES]

• ESTABLISH Instrument Air to Containment: [Step 19.a.2) - YES]

• ESTABLISH Nitrogen: [Step 19.b - YES]

• VERIFY ACCUM 14 VENT CTRL, 1-HC-943 - CLOSED.

[Step 19.b.1) - YES]

• OPEN SI/PORV ACCCUM N2 ISOL VLV 1/1-8880.

[Step 19.b.2) - YES]

RO/BOP NOTIFY Unit Supervisor Attachment 1.D steps - COMPLETE.

[Step 20 - YES]

Examiner Note: FRH-0.1A, Response to Loss of Secondary Heat Sink, Steps 20 and 21 must both be completed to meet the Critical Task requirements.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #2 Rev h CRITICAL TASK Establish Core Cooling via Reactor Coolant System Bleed and Feed per STATEMENT FRH-0.1A, Response to Loss of Secondary Heat Sink.

CRITICAL TASK RO ESTABLISH RCS Bleed Path: [Step 20 - YES]

• VERIFY power to PRZR PORV Block Valves - AVAILABLE.

[Step 20.a - YES]

• VERIFY OPEN 1/1-8000A, PRZR PORV Block Valve. [Step 20.b - YES]

• OPEN 1/1-8000B, PRZR PORV Block Valve. [Step 20.b - NO]

• OPEN 1-PCV-455A, PRZR PORV. [Step 20.c - YES]

+20 min RO VERIFY Adequate RCS Bleed Path: [Step 21 - YES]

• VERIFY both PRZR PORVs - OPEN. [Step 21.a - NO]

• OPEN Reactor Vessel Head and Pressurizer Vents.

[Step 21.a RNO - YES]

• INSERT key and OPEN 1-HV-3607, RV HEAD VENT VLV.

[Step 21.a RNO - YES]

• INSERT key and OPEN 1-HV-3608, RV HEAD VENT VLV.

[Step 21.a RNO - YES]

• INSERT key and OPEN 1-HV-3609, PRZR VENT VLV.

[Step 21.a RNO - YES]

• INSERT key and OPEN 1-HV-3610, PRZR VENT VLV.

[Step 21.a RNO - YES]

When an adequate Reactor Coolant System bleed and feed path is aligned, TERMINATE the scenario.

CPNPP NRC 2012 Sim Scenario #2 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Facility: CPNPP 1 & 2 Scenario No.: 3 Op Test No.: June 2012 NRC Examiners: Operators:

Initial Conditions: 100% power MOL - RCS Boron is 908 ppm (by sample).

Turnover: Maintain steady-state power conditions.

Critical Tasks:

• Identify and Isolate Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture.

• Initiate Cooldown of Reactor Coolant System Prior to Exiting EOP-3.0A, Steam Generator Tube Rupture.

Event No. Malf. No. Event Type* Event Description 1 CV31A C (RO, SRO) Centrifugal Charging Pump (1-01) Sheared Shaft.

+5 min TS (SRO) 2 CH10 C (BOP, SRO) Control Rod Drive Mechanism Ventilation Fan (1-01) Overcurrent

+10 min Trip.

3 RX15A C (RO, SRO) Pressurizer Spray Valve (PCV-455B) Fails 35% Open.

+20 min OVRDE TS (SRO) Pressurizer Heater AUTO ON Relay Failure.

4 RX18 I (BOP, SRO) Main Feedwater Header Pressure Transmitter (PT-508) Fails Low.

+25 min 5 SG01A R (RO) Steam Generator (1-01) Tube Leak at 10 GPM.

+45 min N (BOP, SRO) Rapid Down Power Required.

TS (SRO) 6 SG01A M (RO, BOP, SRO) Steam Generator (1-01) Tube Rupture at 300 GPM (300 second

+50 min ramp).

7 SS02A1 I (BOP) Main Turbine Trip Block Failure.

+50 min SS02A2 TC07C 8 CS02E C (RO) Train A Containment Spray Pumps (1-01 & 1-03) Safety Injection

+55 min CS02G Sequencer Start Failure.

9 OVRDE Main Steam Isolation Valve (HV-2333A) Fails to Auto Close.

+55 min

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h SCENARIO

SUMMARY

NRC #3 The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations. The first event is a sheared shaft of the running Centrifugal Charging Pump (CCP). When low flow alarms are received, the initial operator actions of ABN-105, Chemical and Volume Control System Malfunction, Section 3.0, will be performed (start the standby CCP). Any delay in determining the cause of the low Charging flow will result in the isolation of Letdown which will be restored prior to proceeding. The SRO will refer to Technical Specifications.

The next event is an overcurrent trip of the running Control Rod Drive Mechanism (CRDM) Ventilation Fan. Crew actions are per 1-ALB-3A, Window 2-1, CONTAINMENT FAN MASTER TRIP. The Alarm Light Box (ALB) will direct starting of the standby CRDM Vent Fan.

This event is followed by a Pressurizer Spray Valve that is failed 35% open and a Pressurizer Heater Backup Heater Group D fails to automatically energize. Group D heaters will be manually energized.

The crew enters ABN-705, Pressurizer Pressure Malfunction, Section 3.0, and attempts to close the valve. When this action fails, Pressurizer Heaters are energized and the Driver Card for the failed Spray Valve is pulled to close the valve. The SRO will refer to Technical Specifications.

When Pressurizer pressure is restored, a Main Feedwater (MFW) Header Pressure Transmitter will fail low. Entry into ABN-709, Feedwater Header Pressure Instrument Malfunction, Section 5.0, is required and the MFW Pump Turbine Master Speed Controller is placed in MANUAL. This controller will remain in MANUAL for the duration of the scenario and require monitoring during the subsequent down power.

When Feedwater Pressure Control is restored, a 10 GPM Steam Generator (SG) Tube Leak will ensue.

The crew will enter ABN-106, High Secondary Activity, Section 3.0, and determine that a Rapid Downpower is required. The SRO will refer to Technical Specifications. When power has been reduced 3% to 5%, a 300 GPM Steam Generator Tube Rupture will commence on a 300 second ramp.

When control of the power reduction is no longer feasible, the crew will trip the Reactor, initiate a Safety Injection, and enter EOP-0.0A, Reactor Trip or Safety Injection. While performing the actions of EOP-0.0A, the Main Turbine will fail to trip until the Electro Hydraulic Control Pumps are secured. The crew will transition from EOP-0.0A to EOP-3.0A, Steam Generator Tube Rupture.

The scenario includes Train A Containment Spray Pumps that fail to start upon initiation of the Safety Injection Sequencer and a Main Steam Isolation Valve (HV-2333A) that fails to AUTO Close. This scenario is terminated when the Ruptured Steam Generator is isolated, Reactor Coolant System (RCS) temperature is lowered, and a depressurization of the RCS to the Ruptured Steam Generator pressure is commenced as outlined in EOP-3.0A.

Risk Significance:

• Failure of risk important system prior to trip: Loss of Centrifugal Charging Pump

• Risk significant core damage sequence: Steam Generator Tube Rupture Main Turbine Trip Failure

• Risk significant operator actions: Close Pressurizer Spray Valve Restore Steam Generator Level Control Identify & Isolate Ruptured SG Cooldown/Depressurize RCS CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h BOOTH OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC #18 and NRC #3 Scenario File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP SS02A1 Main Turbine Trip Block Failure ON K0 SS02A2 TC07C CS02E CS Pump (1-01) Auto Start Failure on SI Signal - K0 CS02G CS Pump (1-03) Auto Start Failure on SI Signal - K0 OVRDE MSIV (HV-2333A) Fails to Auto Close - K0 1 CV31A Centrifugal Charging Pump (1-01) Sheared Shaft SHEARED K1 1 CVR05 CCP (1-01) Auxiliary Lube Oil Pump OFF K10 1 CVR06 CCP (1-02) Auxiliary Lube Oil Pump AUTO K10 2 CH10 CRDM Ventilation Fan (1-01) Overcurrent Trip TRIP K2 3 RX15A Pressurizer Spray Valve (PCV-455B) Fails Open 35% K3 3 OVRDE Pressurizer Heater AUTO ON Relay Failure OFF K3 IOR-DIRXPCPR3 {f:1}

3 RXR096 PRZR Spray Valve (PCV-455B) Driver Card OUT K6 3 RX15A Pressurizer Spray Valve (PCV-455B) Fails Open DELETE K6 4 RX18 MFW Header Pressure (PT-508) Failure 200 PSIG K4 5 SG01A Steam Generator (1-01) Tube Leak 10 GPM K5 6 SG01A Steam Generator (1-01) Tube Rupture 300 GPM K7 (300 sec. ramp) 7 SS02A1 Main Turbine Trip Block Failure ON K0 SS02A2 TC07C 8 CS02E CS Pump (1-01) Auto Start Failure on SI Signal - K0 CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h 8 CS02G CS Pump (1-03) Auto Start Failure on SI Signal - K0 9 OVRDE MSIV (HV-2333A) Fails to AUTO Close - K0 9 DIMSHS2333A MSIV (HS-2333A) Manually Closes - K0 CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: INITIALIZE to IC #18 and NRC #3 Scenario File.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON at half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.5, Operating at Constant Turbine Load.

ENSURE Control Rods are in AUTO with Bank D at 215 steps.

Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 1 (Key 1).

- CV31A, Centrifugal Charging Pump 1-01 sheared shaft.

Indications Available:

5A-1.6 - ANY RCP SEAL WTR INJ FLO LO 6A-1.4 - REGEN HX LTDN OUT TEMP HI 6A-3.4 - CHG FLO HI / LO 1-FI-121A, CHRG FLO lowers to zero (0) GPM

+1 min RO RESPOND to Annunciator Procedure Alarms.

RECOGNIZE Charging Pump 1-01 sheared shaft due to loss of Charging RO flow.

DIRECT performance of ABN-105, Chemical and Volume Control System US Malfunction, Section 3.0.

Examiner Note: Diamond steps () are Initial Operator Actions.

RO START Centrifugal Charging Pump 1-02. [Step 3.3.1 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h RO VERIFY one Centrifugal Charging Pump - RUNNING. [Step 3.3.2 - YES]

VERIFY Seal Injection Flow to each RCP - BETWEEN 6 GPM AND 13 RO GPM. [Step 3.3.3 - YES]

Booth Operator: When contacted, REPORT shaft of CCP 1-01 is sheared between the motor and speed increaser.

Booth Operator: When contacted, EXECUTE remote functions CVR05 and CVR06 for the Centrifugal Charging Pump (1-01 & 1-02) Auxiliary Lube Oil Pumps.

VERIFY RCP parameters in - NORMAL OPERATING RANGE.

RO

[Step 3.3.4 - YES]

VERIFY PRZR level - GREATER THAN 17% AND RISING.

RO

[Step 3.3.5 - YES]

Examiner Note: ABN-706, Attachment 6 is used in the event Letdown is isolated in Step 1.

Letdown flow is re-established using the Letdown Restoration Job Aid.

When Pressurizer level is greater than 17%, RESTORE Letdown per RO Attachment 6. [Step 3.3.6 RNO - YES/NO]

• OPEN or VERIFY OPEN Letdown Isolation Valves 1/1-LCV-460 &

1/1-LCV 459. [Step 1 - YES]

• Manually OPEN 1-PK-131, LTDN HX OUT PRESS CTRL to 30% (75 GPM) or 50% (120 GPM) DEMAND. [Step 2 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• Manually OPEN 1-TK-130, LTDN HX OUT TEMP CTRL to 50%

DEMAND. [Step 3 - YES]

• ADJUST Charging to desired flow and MAINTAIN Seal Injection flow between 6 and 13 GPM. [Step 4 - YES]

• OPEN selected Orifice Isolation Valves. [Step 5 - YES]

• 1/1-8149A, LTDWN ORIFICE ISOL VLV (45 GPM)

• 1/1-8149B, LTDWN ORIFICE ISOL VLV (75 GPM)

• 1/1-8149C, LTDWN ORIFICE ISOL VLV (75 GPM)

• ADJUST 1-PK-131, LTDN HX OUT PRESS CTRL to ~310 psig on 1-PI-131, LTDN HX OUT PRESS then PLACE in AUTO. [Step 6 - YES]

• ADJUST 1-TK-130, LTDN HX OUT TEMP CTRL to obtain ~95ºF on 1-TI-130, LTDN HX OUT TEMP, then PLACE in AUTO. [Step 7 - YES]

RO VERIFY RCS leakage - NORMAL: [Step 3.3.7 - YES]

• VERIFY PRZR level stable at or trending to program. [Step 3.3.7.a - YES]

• VERIFY Charging flow less than 15 GPM above Letdown flow.

[Step 3.3.7.b - YES]

Examiner Note: Technical Requirements Manual (TRM) TR LCO 13.1.31, Borating Injection System - Operating, may also be referenced.

US EVALUATE Technical Specifications. [Step 3.3.8 - YES]

• LCO 3.5.2.A, ECCS - Operating.

• CONDITION A - One train inoperable because of the inoperability of a centrifugal charging pump.

• ACTION A.1 - Restore pump to OPERABLE status within 7 days.

US INITIATE a work request per STA-606. [Step 3.3.9 - YES]

+10 min US INITIATE a Condition Report per STA-421. [Step 3.3.10 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 2 (Key 2).

- CH10, Control Rod Drive Mechanism Fan (1-01) trips.

Indications Available:

3A-2.1 - CNTMT FN MASTER TRIP 3A-1.3 - CRDM VENT FN 1 P LO 3A-1.6 - CRDM SHROUD EXH TEMP HI 3B-4.2 - CRDM ANY VENT FAN DISCH TEMP HI (30 seconds later) 1-HS-5421, CRDM VENT FN amber MISMATCH, white TRIP, and green STOP lights LIT

+1 min BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE CRDM Vent Fan 1-01 tripped.

DIRECT performance of ALM-0031A, 1-ALB-3A, Window 1.6 - CRDM US SHROUD EXH TEMP HI.

BOP VERIFY at least one CRDM Vent Fan in service. [Step 1 - NO]

• If NO fans are in service, START one CRDM Vent Fan per SOP-801A, BOP Containment Ventilation System. [Step 1.a - YES]

Examiner Note: The following two steps are from SOP-801A, Containment Ventilation System.

PLACE 1-HS-5423, CRDM VENT FN 2 handswitch in START.

BOP

[Step G - YES]

BOP MONITOR Containment Radiation levels until they stabilize. [Step I - YES]

Examiner Note: The next steps continue with ALM-0031A, 1-ALB-3A, Window 1.6 - CRDM SHROUD EXH TEMP HI.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h BOP MONITOR 1-TI-5400A, CNTMT AVE TEMP. [Step 2 - YES]

VERIFY X-TI-6071, CH WTR SPLY HDR TEMP is 45ºF to 55ºF at X-CV-01.

BOP

[Step 3 - YES]

Examiner Note: A Procedure Enhancement will be submitted to verify Simulator conditions for Chill Water flow.

ENSURE 1-FI-6081, CNTMT FN CLR CH WTR RET FLO is between 912 BOP and 1008 GPM with any combination of 3 of 4 units in service. [Step 4 - YES]

BOP MONITOR CRDM Shroud exhaust temperature. [Step 5 - YES]

• 1-TI-5455, CRDM VENT FN 2 DISCH TEMP.

REFER to Technical Specifications LCO 3.6.5, Containment Air US Temperature. [Step 6 - YES]

CORRECT the condition or INITIATE a work request per STA-606.

+5 min US

[Step 7 - YES]

When CRDM cooling is restored, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 3 (Key 3).

- RX15A, Pressurizer Spray Valve (PCV-455B) fails 35% open.

- OVRDE, Pressurizer Heater AUTO ON relay failure.

Indications Available:

6C-3.3 - PRZR PRESS LO BACKUP HTRS ON (~2 minutes later) 5B-1.6 - PRZR LO PRESS PORV 456 BLK (~3 minutes later) 5B-2.6 - PRZR LO PRESS PORV 455A BLK (~3 minutes later)

Plant Computer System low Pressurizer Pressure alarms Pressurizer pressure lowering

+2 min RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE PZR pressure lowering and DETERMINE PCV-455B, RO Pressurizer Spray Valve malfunction.

DIRECT implementation of ABN-705, Pressurizer Pressure Malfunction, US Section 3.0.

RO CLOSE Pressurizer Spray Valve(s): [Step 3.3.1 - YES]

• PLACE PK-455B, RC LOOP 1 PRZR SPR VLV CTRL in MANUAL and CLOSE Spray Valve. [Step 3.3.1 - NO]

• DETERMINE Pressurizer Pressure NOT lowering in an uncontrolled manner. [Step 3.3.1.a RNO - YES]

• INITIATE load reduction per IPO-003A as directed by Shift Manager.

[Step 3.3.1.b RNO - NO]

• ENSURE All Pressurizer Heaters - ON. [Step 3.3.1.c RNO - NO]

• PLACE Pressurizer Heater Group D handswitch to ON.

Booth Operator: When contacted as I&C, WAIT 1 minute then EXECUTE remote function RXR096 (Key 6), to remove 1-PCY-0455B, Pressurizer Pressure Control Driver Card AND REMOVE malfunction RX15A (Key 6).

• CONTACT I&C to deenergize and fail CLOSED Loop 1 Spray Valve RO by removing Controller Driver Card. [Step 3.3.1.d RNO - YES]

• ACKNOWLEDGE annunciator 1-ALB-4B, Window 2.6 - CTRL GRP PROC CTRL CAB PWR SPLY FAIL.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: The crew may execute a 50 MWe power reduction (Runback) to restore pressure.

BOP PERFORM the following to INITIATE 50 MWe Turbine Runback:

• DEPRESS 50 MWe Manual Runback button.

• CLICK on 0/1 button.

• CLICK on EXECUTE then VERIFY Runback in progress.

RO CHECK PRZR Pressure - STABLE OR RISING. [Step 3.3.2 - YES]

RO VERIFY PRZR Pressure - TRENDING TO 2235 PSIG. [Step 3.3.3 - YES]

Examiner Note: When RCS pressure drops below 2220 PSIG during steady-state conditions, Pressurizer Pressure is less than the limit specified in the COLR.

US EVALUATE Technical Specifications. [Step 3.3.4 - YES]

• LCO 3.4.1.A, RCS Pressure, Temperature, and Flow Departure from Nuclear Boiling (DNB) Limits.

• CONDITION A - One or more RCS DNB parameters not within limits.

• ACTION A.1 - Restore RCS DNB parameter(s) to within limit in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

US INITIATE a work request per STA-606. [Step 3.3.5 - YES]

+10 min US INITIATE a Condition Report per STA-421. [Step 3.3.6 - YES]

When Technical Specifications are referenced, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 4 (Key 4).

- RX18, Feed Header Pressure Transmitter (PT-508) fails low.

Indications Available:

Plant Computer Alarm for low Feed Header pressure 1-PI-508, FWP DISCH HDR PRESS indication fails low

+1 min BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Feed Header Pressure 1-PT-508 transmitter failure.

Examiner Note: Feed header pressure failing low will cause Feedwater Pump speed to rise.

The Main Feedwater Pump Master Speed Controller will remain in MANUAL for the subsequent down power during Event 5.

DIRECT performance of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 5.0.

PLACE 1-SK-509A, FWPT Master Speed Controller in MANUAL.

BOP

[Step 5.3.1 - YES]

ADJUST 1-SK-509A, FWPT Master Speed Controller to MAINTAIN P BOP between FWP Discharge Pressure and Steam Line Pressure.

[Step 5.3.2 - YES]

• From 20% to 100% power, RAMP P from 80 PSIG to 170 PSIG.

[Step 5.3.2 - YES]

US INITIATE a Condition Report per STA-421. [Step 5.3.3 - YES]

+5 min US INITIATE a work request per STA-606. [Step 5.3.4. - YES]

When control of Feedwater is restored, or at Lead Examiner discretion, PROCEED to Event 5.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 5 (Key 5).

- SG01A, Steam Generator 1-01 Tube Leak at 10 GPM.

Indications Available:

PC MSL-178 (1-RE-2325) is RED PC N16-174 MSL #1 (1-RE-2325A) is RED PC COG-182 (1-RE-2959) is RED (Condenser Off Gas is delayed)

+1 min RO/BOP RESPOND to PC-11, Digital Radiation Monitoring System alarms.

RO/BOP RECOGNIZE radiation monitor alarms associated with Steam Generator 1-01.

US DIRECT performance of ABN-106, High Secondary Activity, Section 3.0.

DETERMINE Main Steam Line 1-01 radiation alarm 1-RE-2325 is RED on RO/BOP PC-11. [Step 3.3.1 - YES]

• REDUCE power to 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND be in MODE 3 in the next 2 US hours. [Step 3.3.1.a RNO - YES]

US

• GO to Step 5.b. [Step 3.3.1.b RNO - YES]

Examiner Note: Crew may implement Reactivity Briefing Sheet for a Rapid Plant Shutdown within one (1) hour. This guidance includes a boration of ~ 650 gallons at ~20 GPM and a Main Turbine load reduction to 200 MWe at ~20 MWe/min.

VERIFY PRZR level - STABLE OR TRENDING TO NORMAL LEVEL.

RO

[Step 3.3.5.b - YES]

VERIFY Condenser off Gas Radiation Monitor OR Main Steam Line Leak US Rate Radiation Monitor on Affected Steam Generator - OPERABLE.

[Step 3.3.6 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h US DIRECT Chemistry to implement CHM-113. [Step 3.3.7 - YES]

ADJUST Steam Generator 1-01 Atmospheric Relief Controller setpoint to BOP 1160 PSIG per TDM-501A. [Step 3.3.8 - YES]

BOP VERIFY Affected Steam Generator - SG 1-01. [Step 3.3.9 - YES]

• PLACE 1-HV-2452-2, TDAFW Pump Steam Supply Valve from SG 1-01 in PULLOUT. [Step 3.3.9.a - YES]

+10 min US EVALUATE Technical Specifications. [Step 3.3.9.b - YES]

• LCO 3.7.5.A, Auxiliary Feedwater System

• CONDITION A - One steam supply to turbine driven AFW pump inoperable.

• ACTION A.1 - Restore steam supply to OPERABLE status within 7 days.

• LCO 3.4.13, RCS Operational Leakage

• CONDITION B - Primary to secondary LEAKAGE not within limits.

• ACTION B.1 - Be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• ACTION B.2 - 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 />.

Examiner Note: The following steps are from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to MODE 3.

DIRECT load reduction to 200 MWe per IPO-003A, Power Operations, US Section 5.6, Reducing Turbine Power from 100% to MODE 3.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CONTACT Chemistry and place specified demineralizers in-service.

RO

[Step 5.6.1 - YES]

RO NOTIFY QSC Generation Controller prior to reducing load. [Step 5.6.2 - YES]

NOTIFY Chemistry and Radiation Protection that power will be lowered RO 15% within a one hour period. [Step 5.6.3 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h PERFORM the following to reduce Turbine Load to ~200MWe:

RO

[Step 5.6.4 - YES]

• DETERMINE the amount of Boration required to reduce Reactor Power to 200 MWe (~15% power). [Step 5.6.4.A - YES]

If desired, DETERMINE the rate of Boration required to allow slow Control RO Rod inward motion as Turbine load lowers. [Step 5.6.4.B - NO]

REFER to Attachment 2 for guidance in controlling AFD during power ramp.

RO

[Step 5.6.4.C - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h INITIATE RCS boration per SOP-104A, Reactor Make-up and Chemical RO Control System. [Step 5.6.4.D - YES]

Examiner Note: The following steps are from SOP-104A, Reactor Make-up and Chemical Control System, Section 5.1.2, Borate Mode.

RO PERFORM the following to COMMENCE RCS boration:

• ENSURE Prerequisites of Section 2.1 and 2.2 or met.

[Step 5.1.2.A - YES]

• ENSURE 1/1-MU, RCS MU MAN ACT is in STOP.

[Step 5.1.2.B - YES]

• PLACE 43/1-MU, RCS MU MODE SELECT in BORATE.

[Step 5.1.2.C - YES]

• SET 1-FK-110, BA BLNDR FLO CTRL to 5.3 pot setting for ~20 GPM.

[Step 5.1.2.D - YES]

• SET 1-FY-110B, BA BATCH FLO counter for ~650 gallons.

[Step 5.1.2.E - YES]

• ENSURE 1/1-FCV-110A, BA BLNDR FLO CTRL VLV in AUTO.

[Step 5.1.2.F - AS IS]

• PLACE 1/1-MU, RCS MU MAN ACT in START. [Step 5.1.2.G - YES]

• VERIFY 1/1-APBA1, BA XFR PMP 1 STARTS.

[Step 5.1.2.H - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• VERIFY 1/1-FCV-110A, BA BLNDR FLO CTRL VLV throttles to 20 GPM.

[Step 5.1.2.I - YES]

• VERIFY 1/1-FCV-110B, RCS MU TO CHG PMP SUCT ISOL VLV OPEN. [Step 5.1.2.I - YES]

• VERIFY 1-FY-110B, BA BATCH FLO counter operating properly.

[Step 5.1.2.J - YES]

• VERIFY 1-FR-110, BA BATCH FLO TO BLNDR red pen operating properly. [Step 5.1.2.J - YES]

• OPERATE 1/1-LCV-112A, VCT LVL CTRL VLV as necessary to maintain proper VCT level. [Step 5.1.2.K - YES]

• When desired amount of boric acid is added, PLACE 1/1-MU, RCS MU MAN ACT in STOP. [Step 5.1.2.L - N/A]

Examiner Note: The following steps continue from IPO-003A, Power Operations, Section 5.6.

SET Turbine Load Rate Setpoint Controller to ~20 MWe/min.

BOP

[Step 5.6.4.E - YES]

• OPEN Load Rate Setpoint OSD.

• SELECT blue bar and ENTER 20 MWe/min.

• CLOSE Load Rate Setpoint OSD.

BOP SET Turbine Load Target to 200 MWe. [Step 5.6.4.F - YES]

• OPEN Load Target OSD.

• SELECT blue bar and ENTER 200 MWe.

• DEPRESS Accept then VERIFY value in blue bar is desired Load Target (magnitude and direction).

• DEPRESS Execute then VERIFY Load Target changes to desired load.

• CLOSE Load Target OSD.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

+20 min CREW MONITOR load change.

When power has been reduced 3% to 5%, or at Lead Examiner discretion, PROCEED to Events 6, 7, 8, and 9.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Events 6, 7, 8, and 9.

- SG01A, SG 1-01 Tube Rupture at 300 GPM on 300 second ramp (Key 7).

- SS02A1 / SS02A2, Main Turbine Trip Block failure.

- CS02E, Containment Spray Pump 1-01 SI Sequencer start failure.

- CS02G, Containment Spray Pump 1-03 SI Sequencer start failure.

- TC07 Turbine Fails to Trip (Auto and Pushbutton)

- OVRDE, Main Steam Isolation Valve (HV-2333A) fails to AUTO close.

Indications Available:

6A-3.4 - CHRG FLO HI / LO 5C-1.2 - PRZR LVL DEV LO 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON PC MSL-178 (1-RE-2325) is RED Main Steam Line Radiation level rising Pressurizer pressure lowering Examiner Note: The Main Steam Isolation Valve (HV-2333A) failure is required in the event the Main Turbine is not tripped in a timely manner. This prevents an AUTO closure on a Main Steam Isolation Signal.

+2 min RO/BOP RECOGNIZE Pressurizer level and pressure LOWERING at a rising rate.

RECOGNIZE PRZR pressure decreasing with Steam Line Radiation RO/BOP Monitors in alarm and steam / feed mismatch.

RO Manually INITIATE a Reactor Trip.

• PLACE 1/1-RTC, RX TRIP Switch in TRIP.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1 - YES]

• VERIFY Reactor Trip Breakers - OPEN. [Step 1.a - YES]

• VERIFY Neutron flux - DECREASING. [Step 1.a - YES]

• VERIFY all Control Rod Position Rod Bottom Lights - ON.

[Step 1.b - YES]

BOP VERIFY Turbine Trip: [Step 2 - YES]

• VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2 - NO]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• Manually TRIP Turbine. [Step 2 RNO - YES]

• If Turbine will NOT trip, PULLOUT all EHC Fluid Pumps.

[Step 2 RNO - YES]

BOP VERIFY Power to AC Safeguards Buses: [Step 3 - YES]

• VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a - YES]

• VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b - YES]

RO CHECK SI status: [Step 4 - YES]

RO

• CHECK if SI is actuated. [Step 4.a - NO]

RO

• CHECK if SI is required. [Step 4.a RNO - YES]

• VERIFY Steam Line Pressure < 610 PSIG. [Step 4.a RNO - NO]

• VERIFY Pressurizer Pressure < 1820 PSIG. [Step 4.a RNO - YES]

• VERIFY Containment Pressure > 3.0 PSIG. [Step 4.a RNO - NO]

• PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and RO DETERMINE SI has actuated. [Step 4.a RNO - YES]

RO

• VERIFY Both Trains SI Actuated: [Step 4.b - YES]

RO

• SI Actuated blue status light - ON NOT FLASHING.

Examiner Note: EOP-0.0A, Attachment 2 steps performed by the BOP are identified later in the scenario.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5 - YES]

RO VERIFY AFW Alignment: [Step 6 - YES]

• VERIFY both MDAFW Pumps - RUNNING. [Step 6.a - YES]

• PLACE TDAFW Pump in PULLOUT per Foldout Page. [Step 6.b - YES]

• VERIFY AFW total flow - GREATER THAN 460 GPM. [Step 6.c - YES]

• VERIFY AFW valve alignment - PROPER ALIGNMENT. [Step 6.d - YES]

RO DETERMINE Containment Spray NOT Required: [Step 7 - YES]

• VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED.

[Step 7.a - YES]

• VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 7.a - YES]

• VERIFY Containment pressure - LESS THAN 18.0 PSIG.

[Step 7.a - YES]

• VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.

[Step 7.b - YES]

• VERIFY Containment Spray Pumps - RUNNING. [Step 7.c - NO]

RO

• START Containment Spray Pumps 1-01 and 1-03.

[Step 7.c RNO - YES]

RO CHECK if Main Steam lines should be ISOLATED: [Step 8 - YES]

• VERIFY Containment pressure - GREATER THAN 6.0 PSIG.

[Step 8.a - NO]

• VERIFY Steam Line pressure - LESS THAN 610 PSIG. [Step 8.a - NO]

• GO to Step 9. [Step 8.a RNO - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h RO CHECK RCS Temperature:

• VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9 - YES]

RO CHECK PRZR Valve Status: [Step 10 - YES]

• VERIFY PRZR Safeties - CLOSED. [Step 10.a - YES]

• VERIFY Normal PRZR Spray Valves - CLOSED. [Step 10.b - YES]

• VERIFY PORVs - CLOSED. [Step 10.c - YES]

• VERIFY Power to at least 1 Block Valve - AVAILABLE. [Step 10.d - YES]

• VERIFY Block Valves - AT LEAST ONE OPEN. [Step 10.e - YES]

RO CHECK If RCPs Should Be Stopped: [Step 11 - YES]

• VERIFY RCS subcooling - LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 11.a - NO]

• GO to Step 12. [Step 11.a RNO - YES]

US/RO CHECK if any SG is Faulted: [Step 12 - YES]

• VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a - NO]

• VERIFY any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 12.a - NO]

• GO to Step 13. [Step 12.a RNO - YES]

+15 min US/RO CHECK if SG Tubes are Not Ruptured: [Step 13 - YES]

• DETERMINE SG 1-01 is ruptured and TRANSITION to EOP-3.0A, Steam Generator Tube Rupture, Step 1. [Step 13 RNO - YES]

Examiner Note: EOP-3.0A, Steam Generator Tube Rupture, steps begin here.

US/RO CHECK If RCPs Should Be Stopped: [Step 1 - YES]

• VERIFY RCS subcooling - LESS THAN 25°F. [Step 1.a - NO]

• GO to Step 12. [Step 1.a RNO - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h US/BOP IDENTIFY Steam Generator 1-01 as ruptured. [Step 2 - YES]

• OBSERVE rise in Steam Generator 1-01 narrow range level.

• OBSERVE high radiation from Steam Generator 1-01 Main Steam Line.

CRITICAL TASK Identify and Isolate the Ruptured Steam Generator Prior to Commencing an STATEMENT Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture.

CRITICAL TASK RO/BOP ISOLATE flow from Ruptured Steam Generator 1-01: [Step 3 - YES]

• ADJUST SG 1-01 Atmospheric Controller Setpoint to 1160 PSIG.

[Step 3.a - DONE]

• CHECK SG 1-01 Atmospheric Relief Valve - CLOSED.

[Step 3.b - YES]

• CLOSE SG 1-01 Main Steam Line Isolation Valve. [Step 3.c - YES]

• CLOSE SG 1-01 Drip Pot Isolation Valves. [Step 3.c - YES]

• PLACE 1-HS-2452-2, SG 1-01 TDAFW Pump Steam Supply Valve in PULLOUT. [Step 3.d - YES]

• VERIFY SG 1-01 Blowdown Valves - CLOSED. [Step 3.e - DONE]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h RO/BOP CHECK Ruptured SG 1-01 Level: [Step 4 - YES]

• VERIFY narrow range level - GREATER THAN 43%. [Step 4.a -

YES]

• STOP AFW flow to SG 1-01. [Step 4.b - YES]

• CLOSE 1-FK-2453A, MD AFW 1 SG 1 FLO CTRL. [Step 4.b - YES]

RO/BOP CHECK SG 1-01 Pressure - GREATER THAN 420 PSIG. [Step 5 - YES]

CRITICAL TASK Initiate Cooldown of the Reactor Coolant System Prior to Exiting EOP-3.0A, STATEMENT Steam Generator Tube Rupture.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CRITICAL TASK RO/BOP INITIATE RCS Cooldown using Steam Dump Valves. [Step 6 - YES]

When PRZR pressure decreases to less than 1960 psig, BLOCK the Low RO/BOP Steam Line Pressure SI Signal. [Step 6.a - YES]

• PLACE 1/1-SLS-1RBA and 1/1-SLS-1RBB, Main Steam Line Isolation Safety Injection Reset / Block in BLOCK position.

Examiner Note: When ruptured Steam Generator pressure is between two values provided on the Table at Step 6.b, the correlating Core Exit Temperature for the lower pressure value is used.

DETERMINE required Core Exit Thermocouple (CET) temperature from US Table 1. [Step 6.b - YES]

• OBSERVED Steam Generator pressure = _____ PSIG

• TARGET Core Exit Thermocouple (CET) temperature = _____ ºF CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h DUMP steam to Condenser from intact SG(s) at maximum rate and avoid BOP Main Steam Isolation. [Step 6.c. - YES]

• TRANSFER Steam Dump to Steam Pressure Mode. [Step 6.c.1) - YES]

• PLACE Steam Pressure Controller in MANUAL and RAISE demand.

[Step 6.c.2) - YES]

• When P-12 (553°F TAVE) is reached, SELECT Bypass Interlock on Steam Dumps and continue cooldown. [Step 6.c.3) - YES]

US/RO VERIFY Core Exit Thermocouples - LESS THAN REQUIRED TEMPERATURE. [Step 6.d - YES]

BOP STOP RCS cooldown. [Step 6.e - YES]

RO/BOP MAINTAIN Core Exit Thermocouples - LESS THAN REQUIRED TEMPERATURE. [Step 6.f - YES]

Examiner Note: Steam Generator levels may be controlled between 50% and 60% per EOP operating practices (should ADVERSE Containment conditions occur).

+30 min RO/BOP CHECK Intact SG Levels: [Step 7 - YES]

• VERIFY Narrow Range Level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [Step 7.a - YES]

• CONTROL AFW flow to maintain level between 43% and 60%.

[Step 7.b - YES]

When the Steam Generator is isolated and required CET temperature is approached, TERMINATE the scenario.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [Step 1 - YES]

• VERIFY SSW Pumps - RUNNING. [Step 1.a - YES]

• VERIFY EDG Cooler SSW return flow. [Step 1.b - YES]

BOP VERIFY Safety Injection Pumps - RUNNING. [Step 2 - YES]

BOP VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS). [Step 3 - YES]

BOP VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT INDICATION (GREEN WINDOWS). [Step 4 - YES]

BOP VERIFY CCW Pumps - RUNNING. [Step 5 - YES]

BOP VERIFY RHR Pumps - RUNNING. [Step 6 - YES]

BOP VERIFY Proper CVCS Alignment: [Step 7 - YES]

• VERIFY Train B CCP - RUNNING. [Step 7.a - YES]

• VERIFY Letdown Relief Valve Isolation: [Step 7.b - YES]

• Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1) - YES]

• Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2) - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h BOP VERIFY ECCS flow: [Step 8 - YES]

• CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a - YES]

• RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b - YES]

• SIP discharge flow indicator - CHECK FOR FLOW. [Step 8.c - YES]

• RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 8.d - NO]

• GO to Step 9. [Step 8.d RNO - YES]

BOP VERIFY Feedwater Isolation Complete: [Step 9 - YES]

• Feedwater Isolation Valves - CLOSED.

• Feedwater Isolation Bypass Valves - CLOSED.

• Feedwater Bypass Control Valves - CLOSED.

• Feedwater Control Valves - CLOSED.

BOP VERIFY Diesel Generators - RUNNING. [Step 10 - YES]

BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB10 -

LIT. [Step 11 - YES]

BOP VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

[Step 12 - YES]

BOP INITIATE periodic monitoring of Spent Fuel Cooling. [Step 13 - YES]

• Spent Fuel Pool temperature (T2900A, T2901A).

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• Spent Fuel Pool level (L4800A, L4801A, L4802A, L4803A).

BOP VERIFY Components on Table 1 are Properly Aligned. [Step 14 - YES]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED BOP NOTIFY Unit Supervisor attachment instructions complete AND to IMPLEMENT FRGs as required. [Step 14 - YES]

EOP-0.0A, Attachment 2 steps are now complete.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Actual Target Quantitative Attributes 8 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 4 Critical tasks (2-3)

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h SCENARIO

SUMMARY

NRC #4 The crew will assume the watch with power at approximately 3% per IPO-003A, Power Operations.

With Safety Injection Pump 1-01 running in the recirculation mode per SOP-201A, Safety Injection System, raise Safety Injection Accumulator (1-01) level prior to MODE 1 entry per SOP-202A, Safety Injection Accumulators. When Accumulator level is within specification, the crew will continue with IPO-003A, Section 5.1, Warmup and Synchronization of the Turbine Generator, Step 5.1.16, and perform a power ascension using the Rod Control and Steam Dump Systems.

When power has been raised 3% to 5%, a Pressurizer Level Channel will fail high. Response is per ABN-706, Pressurizer Level Instrumentation Malfunction, Section 2.0, and requires MANUAL control of either the Pressurizer Level Controller or the Charging Flow Controller. If response to this channel failure is not timely, Letdown will isolate. Once an Alternate Channel is selected, Pressurizer Level is restored to AUTO operation.

The next event is caused by a Main Steam Line Pressure Instrument that fails high and opens its associated Steam Generator Atmospheric Relief Valve. Actions are per ABN-709, Steam Line Pressure Instrument Malfunction, Section 2.0, and requires taking MANUAL control of the Atmospheric Relief Valve and closing the valve.

When conditions are stable, Station Service Water Pump 1-02 will trip. The crew will enter ABN-501, Station Service Water System Malfunction, Section 2.0. Initial operator actions include placing the Train A Emergency Diesel Generator in PULLOUT. The SRO will refer to Technical Specifications.

The next event is a Containment Pressure Transmitter failure. Actions are per ALM-0022A, 1-ALB-2B, Window 3.10 - CNTMT 1 OF 4 PRESS HI-3. The SRO will refer to Technical Specifications.

A Faulted Steam Generator is the major event, and a manual Reactor Trip and Safety Injection should be performed per EOP-0.0A, Reactor Trip or Safety Injection, with a transition to EOP-2.0, Faulted Steam Generator Isolation. When EOP-0.0A, Attachment 2, Safety Injection Actuation Alignment, actions are complete, the SRO may transition to FRZ-0.1A, Response to High Containment Pressure, if an Orange Path exists at that time. With Containment pressure remaining less than 50 PSIG, the Response Not Obtained actions of FRZ-0.1A, Step 1, will return the crew to the Procedure and Step in effect.

This event is complicated by a trip and lockout of the Train B 6900 Volt Safeguards Bus, Train A Safety Injection Actuation failure, and a Train A Containment Spray System (CSS) Isolation Valve that does not open. These conditions reduce the event success path to single Train A operation.

When the Faulted Steam Generator is isolated, the crew will transition from EOP-2.0A to EOS-1.1A, Safety Injection Termination.

Risk Significance:

• Failure of risk important system prior to trip: Station Service Water Pump Trip

• Risk significant core damage sequence: Faulted Steam Generator Containment Spray Flow Failure

• Risk significant operator actions: Manually Initiate Train A Safety Injection Manually Open CSS Isolation Valve Identify and Isolate Faulted SG BOOTH OPERATOR INSTRUCTIONS for SIMULATOR SETUP CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Initialize to IC #34 and NRC #4 Scenario File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP ED05F Safeguards Bus 1EA2 86-2 Trip and Lockout TRIP Reactor Trip RP07A Train A Safety Injection Actuation Failure FAIL Reactor Trip CS07A Train A CSS Isolation Valve (HS-4776) Failure AS IS Reactor Trip NOTE: ENSURE SIP 1 is running and aligned per SOP-201A.

1 - Raise Safety Injection Accumulator (1-01) Level - N/A 2 - Raise power to 6% to 8% - N/A 3 RX05A Pressurizer Level Channel (LT-459) Failure 100% K3 4 MS13B SG Pressure Failure (PT-2326) 1300 PSIG K4 5 SW01B Station Service Water Pump (1-02) Trip TRIP K5 6 RP17D Containment Pressure Failure (PT-937) 60 PSIG K6 7 MS01C Faulted SG 1-03 Inside Containment 2.0 ft2 K7 (180 sec. ramp) 8 ED05F Safeguards Bus 1EA2 86-2 Trip and Lockout TRIP Reactor Trip 9 RP07A Train A Safety Injection Actuation Failure FAIL Reactor Trip 10 CS07A Train A CSS Isolation Valve (HS-4776) Failure AS IS Reactor Trip CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: INITIALIZE to IC #34 and NRC #4 Scenario File.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Control Rods are in MANUAL with Control Rod Bank C @ 225 steps and Bank D @ 110 steps.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE SIP 1-01 is running and aligned per SOP-201A.

REMOVE N-16 detectors from POLL on PC-11.

ENSURE 1-HS-2484 & 1-HS-2485, Condensate Storage Tank Isolation Valves are OPEN.

SET Plant Computer screen for MODE 2.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

PLACE Plant Computer, right hand RO and US Computer screens for MODE 2.

PLACE Plant Computer, left hand RO with SIP 1-01 information (GD-SIP12).

PLACE Group Display LPTDIFF on the BOP Desktop Computer.

ENSURE all PRZR Heaters energized.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, INITIALED to Step 5.1.15.

- COPY of IPO-003A, Power Operations, Attachment 17, MODE 1 Bubble Chart.

- COPY of SOP-201A, Safety Injection System, Section 5.4.1, Starting an SIP in Recirculation (RCS Temperature > 350°F OR TS 3.4.12 Not Applicable),

INITIALED to Step 5.4.1.H.

- COPY of SOP-202A, Safety Injection Accumulators, Section 5.4.1, Raising Accumulator Level, INITIALED to Step 5.4.1.A.

Significant Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.3 - AMSAC BLK TURB < 40% PWR C-20 PCIP-1.4 - CNDNSR AVAIL STM DUMP ARMED C-9 PCIP-1.7 - RX 50% PWR TURB TRIP PERM P-9 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.4 - LO TURB PWR ROD WTHDRWL BLK C-5 PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.4 - TURB LOAD REJ STM DMP ARMED C-7 PCIP-3.5 - RX & TURB 10% PWR P-7 PCIP-4.5 - RX 48% PWR 3-LOOP FLO PERM P-8 PCIP-4.6 - TURB 10% PWR P-13 6D-1.1 - SR HI VOLT FAIL 7B-4.8 - FWP A/B RECIRC VLV NOT CLOSED 8A-1.3 - FWPT B TRIP 8A-1.10 - 1 OF 4 TURB STOP VLV CLOSE Numerous 9A Feedwater alarms CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: ENSURE Simulator in RUN when crew is ready to assume the watch.

Examiner Note: Safety Injection Accumulator level is raised using procedures SOP-202A, Safety Injection Accumulators, and SOP-201A, Safety Injection System.

DIRECT performance of SOP-202A, Safety Injection Accumulators, Section

+1 min US 5.4.1, Raising Accumulator Level.

START a Safety Injection Pump in recirculation per SOP-201A.

BOP

[Step 5.4.1.A - DONE]

BOP OPEN 1/1-8888, ACCUM FILL ISOL VLV. [Step 5.4.1.B - YES]

BOP OPEN 1/1-8871, SI TEST HDR RET ISOL VLV. [Step 5.4.1.C - YES]

BOP OPEN 1/1-8878A, ACCUM 1 FILL VLV. [Step 5.4.1.D - YES]

When level is restored to between 39% and 61%, then CLOSE 1/1-8878A, BOP ACCUM 1 FILL VLV. [Step 5.4.1.E - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h ENSURE ACCUMULATOR 1 level is between 39% AND 61%.

BOP

[Step 5.4.1.F - YES]

• ACCUM 1; 1-LI-950 _____%, 1-LI-951 _____%.

BOP CLOSE 1/1-8871, SI TEST HDR RET ISOL VLV. [Step 5.4.1.G - YES]

BOP CLOSE 1/1-8888, ACCUM FILL ISOL VLV. [Step 5.4.1.H - YES]

BOP STOP the SI Pump per SOP-201A. [Step 5.4.1.I - YES]

Examiner Note: The following steps are from SOP-201A, Safety Injection System, Section 5.4.1.

When the recirculation is completed, STOP 1/1-APSI1 SIP 1 and PLACE BOP handswitch in AUTO. [Step 5.4.1.I - YES]

ENSURE OPEN 1/1-8821A SIP 1 XTIE VLV, associated train cross tie valve.

+10 min BOP

[Step 5.4.1.J - YES]

Examiner Note: The following steps are from SOP-202A, Safety Injection Accumulators, Section 5.4.1.

ENSURE the Accumulator 1 pressure is between 623 PSIG and 644 PSIG.

BOP

[Step 5.4.1.J - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CONTACT Chemistry to sample of Accumulator 1 to ENSURE Boron BOP concentration is between 2300 and 2600 PPM. [Step 5.4.1.K - YES]

When Accumulator pressure is verified, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: MONITOR Simulator parameters while the crew transitions to IPO-003A.

Examiner Note: The following steps are from IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, Step 5.1.16.

If desired, ENSURE Feedwater Bypass Control Valve Controllers in AUTO.

BOP

[Step 5.1.16.A - YES]

VERIFY Attachment 1 was COMPLETED & REVIEWED by the Shift Manager US per the Turnover Sheet prior to exceeding 5% power.

[Step 5.1.16.B - DONE]

As Reactor power rises, VERIFY Steam Dump System continues to maintain BOP Main Steam pressure at approximately 1092 psig. [Step 5.1.16.C - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: The next three (3) steps are guidance from the Unit Supervisor per OPGD-3, Operations Standards and Expectations, Section 5.0, Operating Tactics.

Direct WITHDRAWAL of Control Rods in no more than five (5) step US increments to raise power.

WITHDRAW Control Rods in no more than five (5) step increments while RO monitoring Reactor power level.

RO VERIFY Power Range Channels respond appropriately as power level rises.

Examiner Note: Crew will likely use N-16 power indication from Plant Computer.

When reactor power is greater than 5%, LOG entry into MODE 1.

US

[Step 5.1.16.D - YES]

US PERFORM OPT-102A for MODE 1 Surveillances. [Step 5.1.16.E - YES]

Floor Cue: If requested, REPORT OPT-102A, Operations Shiftly Routine Tests was completed last shift.

+15 min RO Slowly RAISE Reactor power to between 6% and 8%. [Step 5.1.16.F - YES]

When power level is stabilized at 6% to 8%, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 3 (Key 3).

- RX05A, Pressurizer Level Transmitter (LT-459A) fails high.

Indications Available:

5A-1.6 - ANY RCP SEAL WTR INJ FLO LO 5C-4.2 - PRZR 1 OF 3 LVL HI 5C-1.3 - PRZR LVL DEV HI 1-LI-459A, PRZR LVL CHAN I indication failed high

+30 sec RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE PZR level lowering and REPORT Pressurizer Level Channel I RO (LT-459A) failed high.

DIRECT performance of ABN-706, Pressurizer Level Instrumentation US Malfunction, Section 2.0.

PLACE PZR Level Control or Charging Flow in MANUAL to maintain level on RO program using one of the following controllers: [Step 2.3.1 - YES]

• 1-LK-459, PRZR LVL CTRL

• 1-FK-121, CCP CHRG FLO CTRL TRANSFER 1/1-LS-459D, PZR Level Control Channel Select to an RO/BOP OPERABLE channel. [Step 2.3.2 - YES]

TRANSFER 1/1-LS-459E, 1/1-LR-459 PZR Level Select to an OPERABLE RO/BOP channel. [Step 2.3.3 - YES]

RO DETERMINE Normal Letdown aligned. [Step 2.3.4 - YES]

RO VERIFY PZR Control Heater Group C operating normally. [Step 2.3.5 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h RESTORE PZR Level Control or Charging Flow Control to AUTO as desired.

RO

[Step 2.3.6 - YES]

VERIFY other instruments on common instrument line - NORMAL.

US/RO

[Step 2.3.7 - YES]

• VERIFY Loop 1 Instruments LT-459A and PT-455 responding normally per Attachment 1.

Examiner Note: The next two (2) steps are only performed following I&C maintenance.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, CONTACT I&C to place Bistable Test Switches for LT-459 in CLOSE. [Step 2.3.8 - YES]

VERIFY appropriate alarms and trip status lights ON per Attachment 4 and NOTE verification in Unit Log. [Step 2.3.9 - YES]

• OBSERVE TSLB-5, Window 1.1 - PRZR LVL HI LB-459A is LIT.

US EVALUATE Technical Specifications. [Step 2.3.10 - Tracking LCOAR only]

US INITIATE repairs per STA-606. [Step 2.3.11 - YES]

+10 min US INITIATE a Condition Report per STA-421. [Step 2.3.12 - YES]

When Pressurizer Level is restored, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 4 (Key 4).

-MS13B, SG 1-02 Steam Pressure Channel (PT-2326) fails high.

Indications Available:

1-PI-2326, MSL 2 PRESS failed high 1-ZL-2326, SG 2 ATMOS RLF VLV red OPEN light LIT Y6704B Plant Computer alarm

+1 min BOP RESPOND to Dynamic Alarm Display (DAD) Alarm.

DIRECT performance of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st-Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 2.0.

IDENTIFY Steam Generator 1-02 Steam Pressure Transmitter (PT-2326) -

BOP GREATER THAN 60 PSIG difference between remaining channels.

[Step 2.3.1 - YES]

VERIFY Steam Generator Atmospheric Relief Valve - CLOSED.

BOP

[Step 2.3.2 - NO]

• If pressure is less than 1125 PSIG, PLACE 1-PK-2326, SG 2 ATMOS RLF VLV CTRL in MANUAL and 0% DEMAND to CLOSE Valve.

[Step 2.3.2.a RNO - YES]

• NOTIFY Chemistry that a release has occurred and DETERMINE if a release permit is required per STA-603. [Step 2.3.2.b RNO - YES]

• GO to Step 11. [Step 2.3.2.c RNO - YES]

REFER to Attachment 6 and DETERMINE that no Technical Specifications US are applicable to PT-2326 failure. [Step 2.3.11 - YES]

US INITIATE a Condition Report per STA-421. [Step 2.3.12 - YES]

+5 min US INITIATE repairs per STA-606. [Step 2.3.13 - YES]

When the Atmospheric Relief Valve is closed, or at Lead Examiner discretion, PROCEED to Event 5.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 5 (Key 5).

- SW01B, Station Service Water Pump 1-02 trip.

Indications Available:

01-1.8 - SSWP 1 / 2 OVRLOAD / TRIP 01-2.11 - CCP 2 L/O CLR SSW RET FLO LO 01-2.12 - SIP 2 L/O CLR SSW RET FLO LO 01-4.8 - CSP 2 & 4 BRG CLR SSW RET FLO LO Station Service Water Pump 1-02 amber MISMATCH and white TRIP lights lit

+30 sec BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE 1-HS-4251A, Service Water Pump 1-02 amber MISMATCH BOP and white TRIP lights LIT.

DIRECT performance of ABN-501, Station Service Water System US Malfunction, Section 2.0.

Examiner Note: Diamond steps () are Initial Operator Actions.

CRITICAL TASK Emergency Stop Train B Diesel Generator within 15 minutes upon Loss of STATEMENT Train B Station Service Water Pump.

CRITICAL PLACE CS-1DG2E, Train B Diesel Generator Emergency Start/Stop TASK BOP handswitch in PULLOUT. [Step 2.3.1 - YES]

BOP VERIFY Train A SSW Pump - RUNNING. [Step 2.3.2 - YES]

BOP VERIFY Train A CCW Pump - RUNNING. [Step 2.3.3 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When asked about status of SSW Pump, REPORT that the SSW Pump 1-02 50/51 overcurrent relays on Phases B & C are tripped.

VERIFY equipment on Train B - NOT REQUIRED FOR OPERATION:

RO/BOP

[Step 2.3.4 - YES]

• Centrifugal Charging Pump 1-02

• Diesel Generator 1-02

• Component Cooling Water Pump 1-02

• Safety Injection Pump 1-02

• Containment Spray Pumps 1-02 & 1-04 RO/BOP PLACE equipment on Train B in PULLOUT. [Step 2.3.5 - YES]

• Centrifugal Charging Pump 1-02

• Station Service Water Pump 1-02 (may leave as is due to CAUTION)

• Safety Injection Pump 1-02

• Containment Spray Pumps 1-02 & 1-04 BOP CHECK status of Train B CCW Pump. [Step 2.3.6 - YES]

• VERIFY CCW Pump - NOT RUNNING. [Step 2.3.6.a - YES]

• VERIFY CCW Heat Exchanger outlet temperature on Train B < 122ºF.

[Step 2.3.6.b - YES]

US INITIATE a work request per STA-606. [Step 2.3.6 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h US REFER to EPP-201. [Step 2.3.7 - YES]

US EVALUATE Technical Specifications. [Step 2.3.8 - YES]

• LCO 3.7.8.B, Station Service Water System.

• CONDITION B - One SSWS Train inoperable.

• ACTION B.1 - Restore SSWS Train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• LCO 3.8.1.B, AC Sources - Operating.

• CONDITION B - One DG inoperable.

• ACTION B.1 - Perform SR 3.8.1.1 for the required offsite circuit(s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, AND

• ACTION B.2 - Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent within inoperability of redundant required feature(s), AND

• ACTION B.3.1 - Determine OPERABLE DG(s) is not inoperable due to common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, OR

• ACTION B.3.2 - Perform SR 3.8.1.1 for OPERABLE DG(s) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Booth Operator: If contacted, INFORM the Unit Supervisor that another operator will perform required Technical Specification Surveillance.

US COMPLETE OPT-215 verification within one hour. [Step 2.3.9 - YES]

+10 min US SUBMIT a Condition Report per STA-421. [Step 2.3.10 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 6.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Event 6 (Key 6).

- RP17D, Containment Pressure Transmitter (PT-937) fails high.

Indications Available:

2B-3.10 - CNTMT 1 OF 4 PRESS HI-3 1-PT-937, CNTMT PRESS (IR) CHAN I Containment pressure transmitter indication failed high

+30 secs RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Containment pressure transmitter 1-PT-937, CNTMT PRESS RO (IR) CHAN I failed high.

DIRECT performance of ALM-0022A, 1-ALB-2B, Window 3.10 - CNTMT 1 US OF 4 PRESS HI-3.

RO MONITOR Containment pressure. [Step 1 - YES]

• 1-PI-934, CNTMT PRESS (IR) CHAN IV

• 1-PI-935, CNTMT PRESS (IR) CHAN III

• 1-PI-936, CNTMT PRESS (IR) CHAN II

• 1-PI-937, CNTMT PRESS (IR) CHAN I RO VERIFY all channels - GREATER THAN 18 PSIG. [Step 2 - NO]

DETERMINE 1-PI-937, CNTMT PRESS (IR) CHAN I reading 2.5 PSIG RO from other channels. [Step 3 - YES]

If a single instrument is affected, REFER to Technical Specifications.

RO

[Step 3.A - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h US EVALUATE Technical Specifications. [Step 3.A - YES]

• LCO 3.3.2.E, ESFAS Instrumentation [Function 2.c, 3.b.(3)].

• CONDITION E - One Containment Pressure channel inoperable.

• ACTION E.1 - Place channel in bypass within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• ACTION E.2.1 - Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, AND

• ACTION E.2.2 - Be in MODE 4 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.

RO/BOP MONITOR 1-MR-5460, DEW PT TEMP °F. [Step 4 - YES]

• If Containment dewpoint temperatures indicate an increasing trend, PERFORM OPT-303 to determine source of leakage. [Step 4.A - YES]

+5 min CORRECT the condition or INITIATE a Work Request per STA-606.

US

[Step 5 - YES]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Events 7, 8, 9, and 10.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Booth Operator: When directed, EXECUTE Events 7, 8, 9, and 10 (Key 7).

- MS01C, SG 1-03 2 ft2 Steam Line Break inside Containment on 180 second ramp.

- ED05F, Train B Safeguards Bus 86-2 trip and lockout on Reactor Trip.

- RP07A, Train A Safety Injection fails to AUTO actuate.

- CS07A, Train A Containment Spray Isolation Valve (HV-4776) fails to open.

Indications Available:

6D-1.10 - AVE TAVE -TREF DEV 2B-3.12 - CNTMT FN CLR 3 & 4 CND FILL RATE HI 2B-4.12 - CNTMT FN CLR 1 & 2 CND FILL RATE HI 3A-1.1 - CNTMT TEMP HI

+30 sec RO/BOP RECOGNIZE lowering RCS temperature and pressure.

RO/BOP DETERMINE Reactor Trip required and manually TRIP Reactor.

Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1 - YES]

• VERIFY Reactor Trip Breakers - OPEN. [Step 1.a - YES]

• VERIFY Neutron flux - DECREASING. [Step 1.a - YES]

• VERIFY all Control Rod Position Rod Bottom Lights - ON.

[Step 1.b - YES]

BOP VERIFY Turbine Trip: [Step 2 - YES]

• VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2 - YES]

BOP VERIFY Power to AC Safeguards Buses: [Step 3 - YES]

• VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a - YES]

• VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b - NO]

• RESTORE power to deenergized AC Safeguards Bus per ABN-601, Response to a 138/345 KV System Malfunction OR ABN-602, RO Response to a 6900/480 Volt System Malfunction.

[Step 3.b RNO - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h RO CHECK SI status: [Step 4 - YES]

RO

• CHECK if SI is actuated. [Step 4.a - NO]

CRITICAL TASK Manually Initiate Train A Safety Injection Signal prior to Exiting EOP-0.0A, STATEMENT Reactor Trip or Safe Injection.

CRITICAL TASK RO Manually INITIATE Train A Safety Injection Signal.

RO

• VERIFY Both Trains SI Actuated: [Step 4.b - NO]

• SI Actuated blue status light - ON NOT FLASHING. [Step 4.b -

RO NO]

• PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and RO DETERMINE SI has actuated on both Trains. [Step 4.b RNO - YES]

Examiner Note: EOP-0.0A, Attachment 2 steps performed by the BOP are at the end of the scenario.

INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5 - YES]

Examiner Note: The RCPs may be tripped if subcooling is observed to be < 55ºF for Adverse Containment conditions per EOP-0.0A, Reactor Trip or Safety Injection, Foldout Page criteria.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: The Turbine Driven Auxiliary Feedwater Pump (TDAFW) Pump must be started per EOP-0.0A Foldout Page due to loss of Train B Motor Driven AFW Pump 1-02. AFW flow is then aligned as required.

RO VERIFY AFW Alignment: [Step 6 - YES]

• VERIFY Train A MDAFW Pump - RUNNING. [Step 6.a - YES]

• START TDAFW Pump per Foldout Page. [Step 6.b - YES]

• VERIFY AFW total flow - GREATER THAN 460 GPM. [Step 6.c - YES]

• VERIFY AFW valve alignment - PROPER ALIGNMENT. [Step 6.d - NO]

• STOP AFW flow to SG 1-03 per Foldout Page. [Step 6.d RNO - YES]

RO VERIFY Containment Spray NOT Required: [Step 7 - YES]

• VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED.

[Step 7.a - NO]

• VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 7.a - NO]

• VERIFY Containment pressure - LESS THAN 18.0 PSIG.

[Step 7.a - NO]

• VERIFY Containment Spray AND Phase B Actuation - INITIATED.

[Step 7.a.1) RNO - NO]

• Manually ACTUATE Containment Spray AND Phase B Actuation.

[Step 7.a.1) RNO - YES]

• VERIFY appropriate MLB indication for CNTMT SPRAY (blue windows) AND PHASE B (orange windows). [Step 7.a.2) RNO - NO]

• Manually ALIGN Containment Spray Valves.

[Step 7.a.1) RNO - YES]

CRITICAL TASK Manually Initiate Train A Containment Spray Flow prior to Exiting EOP-0.0A, STATEMENT Reactor Trip or Safe Injection.

CRITICAL

• OPEN HV-4776, Train A CSS Isolation Valve to INITIATE Train A TASK RO Containment Spray flow. [Step 7.a.3) RNO - YES]

• ENSURE 1-HS-4752, Train A Chemical Addition Tank Discharge Valve - OPEN. [Step 7.a.4) RNO - YES]

• STOP all RCPs. [Step 7.a.5) RNO - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h US

• GO to Step 8. [Step 7.a.6) RNO - YES]

RO CHECK if Main Steam lines should be ISOLATED: [Step 8 - YES]

• VERIFY Containment pressure - GREATER THAN 6.0 PSIG AND Main Steam Line pressure less than 610 PSIG. [Step 8.a - YES]

• VERIFY Main Steam Line Isolation - COMPLETE. [Step 8.a - YES]

RO CHECK RCS Temperature: [Step 9 - YES]

• VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9 - NO]

• STOP dumping steam. [Step 9.a RNO - YES]

• REDUCE AFW flow as necessary to minimize cooldown.

[Step 9.b RNO - YES]

• CLOSE Main Steam Isolation Valves. [Step 9.c RNO - DONE]

RO CHECK PRZR Valve Status: [Step 10 - YES]

• VERIFY PRZR Safeties - CLOSED. [Step 10.a - YES]

• VERIFY Normal PRZR Spray Valves - CLOSED. [Step 10.b - YES]

• VERIFY PORVs - CLOSED. [Step 10.c - YES]

• VERIFY Power to at least 1 Block Valve - AVAILABLE. [Step 10.d - YES]

• VERIFY Block Valves - AT LEAST ONE OPEN. [Step 10.e - YES]

RO CHECK If RCPs Should Be Stopped: [Step 11 - DONE]

• VERIFY RCS subcooling - LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 11.a - NO]

• GO to Step 12. [Step 11.a RNO - YES]

US/RO CHECK if any SG is Faulted: [Step 12 - YES]

• VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a - YES]

• VERIFY any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 12.a - YES]

• GO to EOP-2.0A, Faulted Steam Generator Isolation, Step 1.

[Step 12.b - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: EOP-2.0A, Faulted Steam Generator Isolation, steps begin here.

+15 min US/RO CHECK Main Steam Line Isolation Valves - CLOSED. [Step 1 - YES]

CHECK at Least One Steam Generator Pressure - STABLE OR US/RO INCREASING. [Step 2 - YES]

US/RO IDENTIFY Faulted Steam Generator 1 COMPLETELY DEPRESSURIZED. [Step 3 - YES]

CRITICAL TASK Identify and Isolate Faulted Steam Generator Prior to Exiting EOP-2.0A, Faulted STATEMENT Steam Generator Isolation.

CRITICAL TASK RO/BOP ISOLATE Faulted Steam Generator 1-03. [Step 4 - YES]

• ISOLATE Main Feed Line to Steam Generator 1-03. [Step 4 - DONE]

• ISOLATE AFW flow to Steam Generator 1-03. [Step 4 - YES]

• CLOSE 1-HS-2493, AFWIV 3.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• ISOLATE Blowdown and Sample Lines to Steam Generator 1-03.

[Step 4 - DONE]

• ENSURE Steam Generator 1-03 Atmospheric Relief Valve - CLOSED.

[Step 4 - DONE]

• ENSURE Main Steam Line Drip Pot Isolation Valve - CLOSED.

[Step 4 - DONE]

RO CHECK CST Level - GREATER THAN 10%. [Step 5 - YES]

US/BOP VERIFY Faulted Steam Generator 1-03 Break Inside Containment.

[Step 6 - YES]

US/RO CHECK Secondary Radiation: [Step 7 - YES]

• REQUEST periodic activity samples of all Steam Generators.

[Step 7.a - YES]

• CHECK available secondary radiation monitors - NORMAL.

[Step 7.b - YES]

US/RO CHECK if ECCS Flow to Should Be Reduced: [Step 8 - YES]

• VERIFY Secondary heat sink: [Step 8.a - YES]

• DETERMINE Total AFW Flow to intact SGs > 460 GPM.

• DETERMINE Narrow Range Level in SGs 1-01, 1-02, & 1-04 > 50%.

• DETERMINE RCS subcooling - GREATER THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 8.b - YES]

• VERIFY RCS pressure - STABLE OR INCREASING. [Step 8.c - YES]

• VERIFY PRZR level - GREATER THAN 13% (34% FOR ADVERSE CONTAINMENT). [Step 8.d - YES]

• GO to EOS-1.1A, Safety Injection Termination, Step 1. [Step 8.e - YES]

Examiner Note: EOS-1.1A, Safety Injection Termination steps begin here.

Examiner Note: The following six (6) steps are performed per EOS-1.1A, Attachment 1.D.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h BOP [1.D] PLACE Train A Diesel EMER START/STOP handswitch in START.

[Step 1 - YES]

BOP [1.D] RESET SI. [Step 2 - YES]

• DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton.

• DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton.

BOP [1.D] RESET SI Sequencers. [Step 3 - YES]

• At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

• After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

• At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

• After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

BOP [1.D] RESET Containment Isolation Phase A and B. [Step 4 - YES]

• DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton.

• DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton.

• DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton.

• DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton.

BOP [1.D] RESET Containment Spray Signal. [Step 5 - YES]

• DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton.

• DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton.

[1.D] ESTABLISH Instrument Air and Nitrogen to Containment.

RO/BOP

[Step 6 - YES]

• ESTABLISH instrument air. [Step 6.a - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• VERIFY air compressor running. [Step 6.a.1) - YES]

• OPEN 1-HS-3487, Containment Instrument Air Isolation Valve.

[Step 6.a.2) - YES]

• ESTABLISH Nitrogen: [Step 6.b - YES]

• VERIFY 1-HC-3943, ACCUM 14 VENT CTRL Valve - CLOSED.

[Step 6.b.1) - YES]

• OPEN 1/1-8880, SI/PORV ACCUM N2 ISOL VLV. [Step 6.b.2) - YES]

RO STOP all but one CCP and PLACE in Standby. [Step 7 - DONE]

US/RO CHECK RCS Pressure - STABLE OR INCREASING. [Step 8 - YES]

Examiner Note: The following two (2) steps are performed per EOS-1.1A, Attachment 1.J.

Examiner Note: None of the Train B Valves repositioned due to a loss of power, therefore, they are in the correct position for performance of EOS-1.1A, Attachment 1.J actions. Valve position is verified via the Monitor Light Boxes (MLB).

RO [1.J] ISOLATE CCP Injection Line Flow Path: [Step 9 - YES]

• VERIFY CCP - SUCTION ALIGNED TO RWST. [Step 9.a - YES]

• ALIGN CCP Miniflow Valves: [Step 9.b - YES]

• OPEN 1/1-8110 and 1/1-8111, CCP Miniflow Valves.

[Step 9.b.1) - YES]

• CLOSE 1/1-8511A and 1/1-8511B, CCP Alternate Miniflow Isolation Valves. [Step 9.b.2) - YES]

• PLACE Charging Flow Control Valve in MANUAL and 35% demand.

[Step 9.c - YES]

• CLOSE 1/1-8801A and 1/1-8801B, CCP Injection Line Isolation Valves.

[Step 9.d - YES]

+30 min RO [1.J] ESTABLISH Charging Flow Path: [Step 10 - YES]

• OPEN 1/1-8105 and 1/1-8106, Charging Line Isolation Valves.

[Step 10.a - YES]

• ADJUST Charging Flow Control Valve to establish Charging flow.

[Step 10.b - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• ADJUST RCP seal flow to maintain between 6 GPM and 13 GPM.

[Step 10.c - YES]

When EOS-1.1A, Safety Injection Termination, Attachment 1.J is complete, TERMINATE the scenario.

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [Step 1 - YES]

• VERIFY Train A SSW Pump - RUNNING. [Step 1.a - YES]

• VERIFY EDG Cooler SSW return flow. [Step 1.b - YES]

BOP VERIFY Train A Safety Injection Pump - RUNNING. [Step 2 - YES]

BOP VERIFY Containment Isolation Phase A (Train A) - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS). [Step 3 - YES]

BOP VERIFY Containment Ventilation Isolation (Train A) - APPROPRIATE MLB LIGHT INDICATION (GREEN WINDOWS). [Step 4 - YES]

BOP VERIFY Train A CCW Pump - RUNNING. [Step 5 - YES]

BOP VERIFY Train A RHR Pump - RUNNING. [Step 6 - YES]

BOP VERIFY Proper CVCS Alignment: [Step 7 - YES]

• VERIFY Train A CCP - RUNNING. [Step 7.a - YES]

• VERIFY Letdown Relief Valve Isolation: [Step 7.b - YES]

• Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1) - YES]

• Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2) - YES]

BOP VERIFY ECCS flow: [Step 8 - YES]

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h

• CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a - YES]

• RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b - YES]

• SIP discharge flow indicator - CHECK FOR FLOW. [Step 8.c - YES]

• RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 8.d - NO]

• GO to Step 9. [Step 8.d RNO - YES]

BOP VERIFY Feedwater Isolation Complete: [Step 9 - YES]

• Feedwater Isolation Valves - CLOSED.

• Feedwater Isolation Bypass Valves - CLOSED.

• Feedwater Bypass Control Valves - CLOSED.

• Feedwater Control Valves - CLOSED.

BOP VERIFY Train A Diesel Generator - RUNNING. [Step 10 - YES]

BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB10 -

LIT. [Step 11 - YES]

• Window 1.4, 1EB2-1EB4 Not Load Shed (DARK).

BOP VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

[Step 12 - YES]

BOP INITIATE periodic monitoring of Spent Fuel Cooling. [Step 13 - YES]

• Spent Fuel Pool temperature (T2900A, T2901A).

• Spent Fuel Pool level (L4800A, L4801A, L4802A, L4803A).

CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h BOP VERIFY Components on Table 1 are Properly Aligned. [Step 14 - YES]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR CPNPP NRC 2012 Sim Scenario #3 Rev h

CPNPP NRC 2012 Sim Scenario #3 Rev h CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 Examiner Note: X-HS-3632 on CV-01 will NOT start due to loss of power.

CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CPNPP NRC 2012 Sim Scenario #3 Rev h

ES-301 Transient and Event Checklist Form ES-301-5 Facility: CPNPP 1 and 2 Date of Exam: 06/11/12 Operating Test No.: NRC A E SCENARIOS P V P E CPNPP #1 CPNPP #2 CPNPP #3 CPNPP #4 L N T MINIMUM(*)

I T CREW CREW CREW CREW O C

POSITION POSITION POSITION POSITION T A T A

N Y S A B S A B S A B S A B R T O R T O R T O R T O L T P R I U O C P O C P O C P O C P E

RX - 5 - 1 1 1 0 NOR 4 - 1,2 3 1 1 1 SROI-1 I/C 2,7,8,9 1,3,8 3,4,5,6 11 4 4 2 MAJ 5,9 6 7 4 2 2 1 TS - - 5,6 2 0 2 2 RX - - 2 1 1 1 0 NOR 4 5 - 2 1 1 1 SROI-2 I/C 1,2,3 2,4,7 3,9,10 9 4 4 2 MAJ 5,9 6 7 4 2 2 1 TS 1,2,3 - - 3 0 2 2 RX 4 - - 1 1 1 0 NOR - 5 1 2 1 1 1 SROI-3 I/C 1,3,6 1,2,3,4 4,5,8 10 4 4 2 MAJ 5,9 6 7 4 2 2 1 TS - 1,3,5 - 3 0 2 2 RX - - - 1 1 0 NOR 4 1,2 3 1 1 1 SROU-1 I/C 1,2,3 3,4,5,6 7 4 4 2 MAJ 5,9 7 3 2 2 1 TS 1,2,3 5,6 5 0 2 2 RX - - - 1 1 0 NOR - 1,2 2 1 1 1 SROU-2 I/C 1,2,3 3,4,5,6 7 4 4 2 MAJ 6 7 2 2 2 1 TS 1,3 5,6 4 0 2 2 RX - - - 1 1 0 NOR 5 1,2 3 1 1 1 SROU-3 I/C 1,2,3,4 3,4,5,6 8 4 4 2 MAJ 6 7 2 2 2 1 TS 1,3,5 5,6 5 0 2 2 RX - - - 1 1 0 NOR 4 1,2 3 1 1 1 SROU-4 I/C 1,2,3 3,4,5,6 7 4 4 2 MAJ 5,9 7 3 2 2 1 TS 1,2,3 5,6 5 0 2 2 RX - - - 1 1 0 NOR 4 5 2 1 1 1 SROU-5 I/C 1,2,3 1,2,3,4 7 4 4 2 MAJ 5,9 6 3 2 2 1 TS 1,2,3 1,3,5 6 0 2 2 CPNPP NRC 2012 As Given ES-301-5 Transient and Event Checklist Rev h.doc

ES-301 Transient and Event Checklist Form ES-301-5 Facility: CPNPP 1 and 2 Date of Exam: 06/11/12 Operating Test No.: NRC A E SCENARIOS P V P E CPNPP #1 CPNPP #2 CPNPP #3 CPNPP #4 L N T MINIMUM(*)

I T CREW CREW CREW CREW O C

POSITION POSITION POSITION POSITION T A T A

N Y S A B S A B S A B S A B R T O R T O R T O R T O L T P R I U E O C P O C P O C P O C P RX - 2 1 1 1 0 NOR 4 - 1 1 1 1 RO-1 I/C 2,7,8,9 3,9,10 7 4 4 2 MAJ 5,9 7 3 2 2 1 TS - - - 0 2 2 RX 4 - 1 1 1 0 NOR - 1 1 1 1 1 RO-2 I/C 1,3,6 4,5,8 6 4 4 2 MAJ 5,9 7 3 2 2 1 TS - - - 0 2 2 RX - - 2 1 1 1 0 NOR 3 - - 1 1 1 1 RO-3 I/C 1,4 2, 7 3,9,10 7 4 4 2 MAJ 5 6 7 3 2 2 1 TS - - - - 0 2 2 RX 3 - - 1 1 1 0 NOR - - 1 1 1 1 1 RO-4 I/C 2,4,6 1,3,8 4,5,8 9 4 4 2 MAJ 5 6 7 3 2 2 1 TS - - - - 0 2 2 RX - 2 1 1 1 0 NOR 5 - 1 1 1 1 RO-5 I/C 2,4,7 3,9,10 6 4 4 2 MAJ 6 7 2 2 2 1 TS - - - 0 2 2 RX 5 - 1 1 1 0 NOR - 1 1 1 1 1 RO-6 I/C 1,3,8 4,5,8 6 4 4 2 MAJ 6 7 2 2 2 1 TS - - - 0 2 2 RX - 2 1 1 1 0 NOR 4 - 1 1 1 1 RO-7 I/C 2,7,8,9 3,9,10 7 4 4 2 MAJ 5,9 7 3 2 2 1 TS - - - 0 2 2 CPNPP NRC 2012 As Given ES-301-5 Transient and Event Checklist Rev h.doc

ES-301 Transient and Event Checklist Form ES-301-5 Facility: CPNPP 1 and 2 Date of Exam: 06/11/12 Operating Test No.: NRC A E SCENARIOS P V P E CPNPP #1 CPNPP #2 CPNPP #3 CPNPP #4 L N T MINIMUM(*)

I T CREW CREW CREW CREW O C

POSITION POSITION POSITION POSITION T A T A

N Y S A B S A B S A B S A B R T O R T O R T O R T O L T P R I U E O C P O C P O C P O C P RX 4 - 1 1 1 0 NOR - 1 1 1 1 1 RO-8 I/C 1,3,6 4,5,8 6 4 4 2 MAJ 5,9 7 3 2 2 1 TS - - - 0 2 2 RX 4 - 1 1 1 0 NOR - 5 1 1 1 1 RO-9 I/C 1,3,6 2,4,7 6 4 4 2 MAJ 5,9 6 3 2 2 1 TS - - - 0 2 2 RX - 5 1 1 1 0 NOR 4 - 1 1 1 1 RO-10 I/C 2,7,8,9 1,3,8 7 4 4 2 MAJ 5,9 6 3 2 2 1 TS - - - 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

CPNPP NRC 2012 As Given ES-301-5 Transient and Event Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants SROU-1 SROU-2 SROU-3 Competencies SCENARIO SCENARIO SCENARIO 2 4 3 4 3 4 Interpret/Diag-1,2,3,4, 3,4,5 3,4,5, 1,2,3,4, 3,4,5, nose Events 5 ,6,7 1,2,3,6 6,7 5,6 6,7 and Conditions Comply With and Use ALL ALL ALL ALL ALL ALL Procedures (1)

Operate Control Boards N/A N/A N/A N/A N/A N/A (2)

Communicate and ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL ALL ALL ALL ALL ALL Ability (3)

Comply With and Use Tech. 1,2,3 5,6 1,3 5,6 1,3,5 5,6 Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants SROU-4 SROU-5 Competencies SCENARIO SCENARIO 2 4 2 3 Interpret/Diag-1,2,3,4, 3,4,5 1,2,3,4, 1,2,3,4, nose Events 5 ,6,7 5 5,6 and Conditions Comply With and Use ALL ALL ALL ALL Procedures (1)

Operate Control Boards N/A N/A N/A N/A (2)

Communicate and ALL ALL ALL ALL Interact Demonstrate Supervisory ALL ALL ALL ALL Ability (3)

Comply With and Use Tech. 1,2,3 5,6 1,2,3 1,3,5 Specs. (3)

Notes:

(4) Includes Technical Specification compliance for an RO.

(5) Optional for an SRO-U.

(6) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants SROI-1 SROI-2 SROI-3 Competencies SCENARIO SCENARIO SCENARIO 2 3 4 2 3 4 2 3 4 Interpret/Diag- 2,3,6, 2,4,5,7, 1,3,5, 3,4,5 1,2,3,4, 2,4,5, 1,3,4,5, 1,2,3,4, 1,2,4, nose Events 8,9 6,8 ,6,7 5 6,7 7,8,9, 6,9 5,6 5,7,8 10 and Conditions Comply With 2,4,5,7, 1,3,5, 2,4,5, 2,3,6, 1,3,4,5, 1,2,4, and Use 8,9 6,8 ALL ALL 6,7 7,9,10 6,9 ALL 5,7,8, Procedures (1)

Operate 2,3,6, 2,4,5,7, 1,3,5, 2,4,5, 1,3,4,5, 1,2,4, Control Boards 8,9 6,8 N/A N/A 6,7 7,8,9, 6,9 N/A 5,7,8, 10 (2)

Communicate 2,3,5, 2,3,4,5, 1,3,5, 2,3,4, 1,2,3,4, 1,2,4, and 7,8,9 6,7,8 ALL ALL 5,6,7 6,7,8, 5,6,9 ALL 5,7,8, 9,10 Interact Demonstrate Supervisory N/A N/A ALL ALL N/A N/A N/A ALL N/A Ability (3)

Comply With and Use Tech. N/A N/A 5,6 1,2,3 N/A N/A N/A 1,3,5 N/A Specs. (3)

Notes:

(7) Includes Technical Specification compliance for an RO.

(8) Optional for an SRO-U.

(9) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants RO-1 RO-2 RO-3 Competencies SCENARIO SCENARIO SCENARIO 2 4 2 4 1 3 4 Interpret/Diag- 2,3,6 2,3,6, 2,4,5,7, 1,3,4,5, 1,2,4, nose Events 8,9

,7,8, 6,9 5,7,8 1,3,5 2,6,7 7,8,9, 9,10 10 and Conditions Comply With 1,2,3, 2,4,5,7, 2,3,6, 1,3,4,5, 1,2,4, 2,3,6, and Use 8,9 7,9,10 6,9 5,7,8, 2,6,7 7,9,10 4,5 Procedures (1)

Operate 2,3,6 1,2,3, 2,3,6, 2,4,5,7, 1,3,4,5, 1,2,4, Control Boards 8,9

,7,8, 6,9 5,7,8, 2,6,7 7,8,9, 9,10 4,5 10 (2)

Communicate 2,3,5, 1,2,3, 2,3,5, 2,3,4,5, 1,2,3,4, 1,2,4, 2,3,6, and 7,8,9 6,7,8, 5,6,9 5,7,8, 4,5 7 6,7,8, 9,10 9,10 Interact Demonstrate Supervisory N/A N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants RO-4 RO-5 RO-6 Competencies SCENARIO SCENARIO SCENARIO 1 3 4 3 4 3 4 Interpret/Diag- 2,4 1,2,4 2,3,6, 1,3,6, 2,4,5, 1,3,5, 1,2,4, nose Events 5,6 8

,5,7, 6,7 7,8,9, 6,8 5,7,8 8 10 and Conditions Comply With 2,3,4 1,2,4 1,3,6, 2,4,5, 2,3,6, 1,3,5, 1,2,4, and Use 8

,5,7, 6,7 7,9,10 6,8 5,7,8, 5,6 8, Procedures (1)

Operate 2,3,4 2,3,6, 1,3,6, 1,2,4, 2,4,5, 1,3,5, 1,2,4, Control Boards 8 5,7,8, 6,7 7,8,9, 6,8 5,7,8, 5,6 10 (2)

Communicate 2,3,4 2,3,5, 1,3, 1,2,4, 2,3,4, 1,3,5, 1,2,4, and 5,6 6,7,8 5,7,8, 5,6,7 6,7,8, 6,7,8 5,7,8, 9,10 Interact Demonstrate Supervisory N/A N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants RO-7 RO-8 RO-9 Competencies SCENARIO SCENARIO SCENARIO 2 4 2 4 2 3 Interpret/Diag- 2,3,6 2,4,5,7, 1,3,4,5, 1,2,4, 1,3,4,5, 2,4,5, nose Events 8,9

,7,8, 6,9 5,7,8 6,9 6,7 9,10 and Conditions Comply With 2,4,5,7, 2,3,6, 1,3,4,5, 1,2,4, 1,3,4,5, 2,4,5, and Use 8,9 7,9,10 6,9 5,7,8, 6,9 6,7 Procedures (1)

Operate 2,3,6 2,4,5,7, 1,3,4,5, 1,2,4, 1,3,4,5, 2,4,5, Control Boards 8,9

,7,8, 6,9 5,7,8, 6,9 6,7 9,10 (2)

Communicate 2,3,5 2,3,4,5, , 1,2,3,4, 1,2,4, 1,2,3,4, 2,3,4, and 7,8,9 6,7,8 5,6,9 5,7,8, 5,6,9 5,6,7 Interact ,9,10 Demonstrate Supervisory N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination: 06/11/12 Operating Test No. NRC 2, 3, 4 Applicants RO-10 Competencies SCENARIO 2 3 Interpret/Diag-2,4,5,7, 1,3,5, nose Events 8,9 6,8 and Conditions Comply With 2,4,5,7, 1,3,5, and Use 8,9 6,8 Procedures (1)

Operate 2,4,5,7, 1,3,5, Control Boards 8,9 6,8 (2)

Communicate 2,3,4,5, 1,3,5, and 7,8,9 6,7,8 Interact Demonstrate Supervisory N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CPNPP NRC 2012 ES-301-6 Competencies Checklist Rev h.doc